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Sample records for rcra inspection manual

  1. Resource Conservation and Recovery Act (RCRA) new-employee training manual for the Operations Division RCRA personnel

    Energy Technology Data Exchange (ETDEWEB)

    Barkenbus, B.D.

    1987-03-01

    This manual has been prepared for the training of new employees who will work with RCRA hazardous waste management in the Operations Division. It will be taught by a person who is trained in hazardous waste regulations/procedures. It consists of nine modules. The topics of these modules are: RCRA Training, Hazardous Waste Regulations, Transportation Regulations, Hazardous Waste Management at ORNL, Chemical Hazards and Safety, Hazardous Waste Operations Training, Sampling of Hazardous Waste, Hazardous Waste Identification/Classification, and RCRA Contingency Plans and Emergency Procedures. The on-the-job training areas are identified in the modules. They are an integral part of training.

  2. Construction inspection manual of procedures

    Science.gov (United States)

    2009-01-01

    This manual provides highway construction personnel with relevant, practical information in order to perform accurate inspections and provide relevant construction procedural information for the various roadway and structures items of work. It is the...

  3. 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

  4. Detecting accuracy of flaws by manual and automatic ultrasonic inspections

    International Nuclear Information System (INIS)

    Iida, K.

    1988-01-01

    As the final stage work in the nine year project on proving tests of the ultrasonic inspection technique applied to the ISI of LWR plants, automatic ultrasonic inspection tests were carried out on EDM notches, surface fatigue cracks, weld defects and stress corrosion cracks, which were deliberately introduced in full size structural components simulating a 1,100 MWe BWR. Investigated items are the performance of a newly assembled automatic inspection apparatus, detection limit of flaws, detection resolution of adjacent collinear or parallel EDM notches, detection reproducibility and detection accuracy. The manual ultrasonic inspection of the same flaws as inspected by the automatic ultrasonic inspection was also carried out in order to have comparative data. This paper reports how it was confirmed that the automatic ultrasonic inspection is much superior to the manual inspection in the flaw detection rate and in the detection reproducibility

  5. First annual report RCRA post-closure monitoring and inspections for the U-3fi waste unit. Final report, July 1995--October 1996

    International Nuclear Information System (INIS)

    Emer, D.F.

    1997-01-01

    This annual Neutron Soil Moisture Monitoring report provides an analysis and summary for site inspections, meteorological information, and neutron soil moisture monitoring data obtained at the U-3fi RCRA Unit, located in Area 3 of the Nevada Site (NTS), Nye County, Nevada during the July 1995 to October 1996 period. Inspections of the U-3fi RCRA Unit are conducted to determine and document the physical condition of the covers, facilities, and any unusual conditions that could impact the proper operation of the waste unit closure. The objective of the neutron logging is to monitor the soil moisture conditions along the 420 ft ER3-3 borehole and detect changes that may be indicative of moisture movement in the regulated interval. This is the first annual report on the U-3fi closure and includes the first year baseline monitoring data as well as one quarter of compliance monitoring data

  6. 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

  7. Annual Report RCRA Post-Closure Monitoring and Inspections for CAU 112: Area 23 Hazardous Waste Trenches, Nevada Test Site, Nevada, for the period October 2000-July 2001

    International Nuclear Information System (INIS)

    Tobiason, D. S.

    2002-01-01

    This annual Neutron Soil Moisture Monitoring report provides an analysis and summary for site inspections, meteorological information, and neutron soil moisture monitoring data obtained at the Area 23 Hazardous Waste Trenches Resource Conservation and Recovery Act (RCRA) unit, located in Area 23 of the Nevada Test Site, Nye County, Nevada, during the October 2000--July 2001 monitoring period. Inspections of the Area 23 Hazardous Waste Trenches RCRA unit are conducted to determine and document the physical condition of the covers, facilities, and any unusual conditions that could impact the proper operation of the waste unit closure. Physical inspections of the closure were completed quarterly and indicated that the site is in good condition with no significant findings noted. An annual subsidence survey of the elevation markers was conducted in July 2001. There has been no subsidence at any of the markers since monitoring began eight years ago. Precipitation for the period October 2000 through July 2001 was 9.42 centimeters (cm) (3.71 inches [in]) (U.S. National Weather Service, 2001). The prior year annual rainfall (January 2000 through December 2000) was 10.44 cm (4.1 1 in.). The recorded average annual rainfall for this site from 1972 to January 2000 is 14.91 cm (5.87 in.). The objective of the neutron logging program is to monitor the soil moisture conditions along 30 neutron access tubes and detect changes that may be indicative of moisture movement at a point located directly beneath each trench. All monitored access tubes are within the compliance criteria of less than 5 percent residual volumetric moisture content at the compliance point directly beneath each respective trench. Soil conditions remain dry and stable underneath the trenches

  8. Annual Report RCRA Post-Closure Monitoring and Inspections for CAU 112: Area 23 Hazardous Waste Trenches, Nevada Test Site, Nevada, for the Period October 1999-October 2000

    Energy Technology Data Exchange (ETDEWEB)

    D. F. Emer

    2001-03-01

    This annual Neutron Soil Moisture Monitoring report provides an analysis and summary for site inspections, meteorological information, and neutron soil moisture monitoring data obtained at the Area 23 Hazardous Waste Trenches Resource Conservation and Recovery Act (RCRA) unit, located in Area 23 of the Nevada Test Site, Nye County, Nevada, during the October 1999-October 2000 period. Inspections of the Area 23 Hazardous Waste Trenches RCRA unit are conducted to determine and document the physical condition of the covers, facilities, and any unusual conditions that could impact the proper operation of the waste unit closure. Physical inspections of the closure were completed quarterly and indicated that the site is in good condition with no significant findings noted. An annual subsidence survey of the elevation markers was conducted in August 2000. There has been no subsidence at any of the markers since monitoring began seven years ago. The objective of the neutron logging program is to monitor the soil moisture conditions along 30 neutron access tubes and detect changes that maybe indicative of moisture movement at a point located directly beneath each trench. Precipitation for the period October 1999 through October 2000 was 10.44 centimeters (cm) (4.11 inches [in.]) (U.S. National Weather Service, 2000). The prior year annual rainfall (January 1999 through December 1999) was 10.13cm (3.99 in.). The highest 30-day cumulative rainfall occurred on March 8, 2000, with a total of 6.63 cm (2.61 in.). The heaviest daily precipitation occurred on February 23,2000, with a total of 1.70 cm (0.67 in.) falling in that 24-hour period. The recorded average annual rainfall for this site, from 1972 to January 1999, is 15.06 cm (5.93 in.). All monitored access tubes are within the compliance criteria of less than 5 percent residual volumetric moisture content at the compliance point directly beneath each respective trench. Soil conditions remain dry and stable underneath the

  9. 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...

  10. Exercise manual for the Augmented Computer Exercise for Inspection Training (ACE-IT) software

    Energy Technology Data Exchange (ETDEWEB)

    Dobranich, P.R.; Widney, T.W.; Goolsby, P.T. [Sandia National Labs., Albuquerque, NM (United States). Cooperative Monitoring Center and Regional Security; Nelson, J.D.; Evanko, D.A. [Ogden Environmental and Energy Services, Inc., Albuquerque, NM (United States)

    1997-09-01

    The on-site inspection provisions in many current and proposed arms control agreements require extensive preparation and training on the part of both the Inspected Party and the Inspection Team. Current training techniques include table-top inspections and practice inspections. The Augmented Computer Exercise for Inspection Training (ACE-IT), an interactive computer training tool, increases the utility of table-top inspections. ACE-IT has been designed to provide training for a hypothetical challenge inspection under the Chemical Weapons Convention (CWC); however, this training tool can be modified for other inspection regimes. Although ACE-IT provides training from notification of an inspection through post-inspection activities, the primary emphasis of ACE-IT is in the inspection itself--particularly with the concept of managed access. ACE-IT also demonstrates how inspection provisions impact compliance determination and the protection of sensitive information. The Exercise Manual supplements the ACE-IT software by providing general information on on-site inspections and detailed information for the CWC challenge inspection exercise. The detailed information includes the pre-inspection briefing, maps, list of sensitive items, medical records, and shipping records.

  11. Transferring manual ultrasonic inspection procedures - results of a pilot study

    International Nuclear Information System (INIS)

    Anderson, M.; Taylor, T.; Kadenko, I.

    2002-01-01

    Results of a manual ultrasonic pilot study for NDE specialists at RBMK nuclear reactor sites are presented. Probabilities of detection and false calls, using two different grading criteria, are estimated. Analyses of performance parameters lead to conclusions regarding attributes for improved test discrimination capabilities. (orig.)

  12. Manual phased arrays for weld inspections using North American codes

    International Nuclear Information System (INIS)

    Moles, Michael

    2008-01-01

    Phased arrays are primarily a method of generating and receiving ultrasound, not a new technology. In addition, the physics of ultrasound generated by phased arrays is identical to that from conventional monocrystals. Not surprisingly, all the major North American (and some European) codes accept phased arrays, either explicitly or implicitly. However, the technique and procedures needs to be proven, typically by a Performance Demonstration. The ASME (AmeicanSociety for Mechanical Engineers) Section V and API RP2X explicitly accept phased arrays. Three ASME code cases have been written specifically fo manual phased array: Code Cases 2541. 2557 and 2558. Over and above the general requirements of Article 4, these Code Cases require full waveform calibration. This is echoed in ASTM E-2491, a Standard Guide for setting up phased arrays. In addition. details such as focusing and reporting are addressed. The American Petroleum Institute QUTE procedure did not need any modifications to be compatible with manual phased arrays. The American Welding Society (AWS) Structural Welding Code D1.1 implicitly accepts phased arrays. New technologies such as phased arrays can be proven using Annex K. Nonetheless, a manual phased array unit using the standard AWS probe and displaying 45, 60 and 70degrees waveforms would be acceptable for D1.1 a s is . Overall, most major North American codes accept phased arrays, however, the technique and procedures must be proven, often using a Performance Demonstration. (author)

  13. Field Operations and Enforcement Manual for Air Pollution Control. Volume III: Inspection Procedures for Specific Industries.

    Science.gov (United States)

    Weisburd, Melvin I.

    The Field Operations and Enforcement Manual for Air Pollution Control, Volume III, explains in detail the following: inspection procedures for specific sources, kraft pulp mills, animal rendering, steel mill furnaces, coking operations, petroleum refineries, chemical plants, non-ferrous smelting and refining, foundries, cement plants, aluminum…

  14. Hanford Facility RCRA permit handbook

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-03-01

    Purpose of this Hanford Facility (HF) RCRA Permit Handbook is to provide, in one document, information to be used for clarification of permit conditions and guidance for implementing the HF RCRA Permit.

  15. User's manual for remote-handled transuranic waste container welding and inspection fixture

    International Nuclear Information System (INIS)

    Hauptmann, J.P.

    1985-09-01

    Rockwell Hanford Operations (Rockwell) has designed built, and tested a prototype remotely operated welding and inspection fixture to be used in making the closure weld on the remote-handled transuranic (RH-TRU) waste container. The RH-TRU waste container has an average TRU concentration in excess of 100 nCi/gm, and a surface radiation dose rate in excess of 200 mrem/h, but not exceeding 100 rem/h. The RH-TRU waste container is to be used by defense waste generator sites in the United States for final packaging of RH-TRU wastes and is compatible with the requirements of the Waste Isolation Pilot Plant (WIPP) and the WIPP handling system. Standard and stacked RH-TRU container designs are available. The standard container is 26 in. in dia. by 121 in. high; the stacked containers are 26 in. in dia. by 61.25 in. high. After loading, two stacked containers are fitted and welded together to form the identical measurements of the standard 121-in. container. The prototype RH-TRU waste container welding and inspection fixture was intended for test and evaluation only, and not for installation in an operating facility. The final RH-TRU waste container welding and inspection fixture drawings (see appendix) incorporate several changes made following operational testing of the original fixture. These modifications are identified in this manual. However, not all modifications have been functionally tested. The purpose of this manual is to aid waste generator sites in designing a remotely operated welding and inspection fixture that will conform to their own requirements. Modifications to the Rockwell design must be evaluated for structural and WIPP handling requirements. This manual also provides design philosophy, component vendor information, and cost estimates

  16. When RCRA meets ALARA

    International Nuclear Information System (INIS)

    Kirner, N.P.

    1990-01-01

    This paper proposes a method to identify an inconsistency between RCRA and AEA and for distinguishing a true inconsistency from a compliance difficulty. The paper also provides examples of each situation, accommodating specific RCRA requirements to maintain adherence to radiation protection requirements. The proposed method is derived from radiation protection guidance to Federal agencies for occupational exposure that was issued by EPA, under authority derived from Executive Order 10831, the AEA, and Reorganization Plan No. 3 of 1970. This EPA guidance was approved by President Reagan on January 20, 1987 and closely reflects the guidance of national and international radiation standard-setting groups

  17. RCRA facility stabilization initiative

    International Nuclear Information System (INIS)

    1995-02-01

    The RCRA Facility Stabilization Initiative was developed as a means of implementing the Corrective Action Program's management goals recommended by the RIS for stabilizing actual or imminent releases from solid waste management units that threaten human health and the environment. The overall goal of stabilization is to, as situations warrant, control or abate threats to human health and/or the environment from releases at RCRA facilities, and/or to prevent or minimize the further spread of contamination while long-term remedies are pursued. The Stabilization initiative is a management philosophy and should not be confused with stabilization technologies

  18. NGLW RCRA Storage Study

    International Nuclear Information System (INIS)

    Waters, R.J.; Ochoa, R.; Fritz, K.D.; Craig, D.W.

    2000-01-01

    The Idaho Nuclear Technology and Engineering Center (INTEC) at the Idaho National Engineering and Environmental Laboratory contains radioactive liquid waste in underground storage tanks at the INTEC Tank Farm Facility (TFF). INTEC is currently treating the waste by evaporation to reduce the liquid volume for continued storage, and by calcination to reduce and convert the liquid to a dry waste form for long-term storage in calcine bins. Both treatment methods and activities in support of those treatment operations result in Newly Generated Liquid Waste (NGLW) being sent to TFF. The storage tanks in the TFF are underground, contained in concrete vaults with instrumentation, piping, transfer jets, and managed sumps in case of any liquid accumulation in the vault. The configuration of these tanks is such that Resource Conservation and Recovery Act (RCRA) regulations apply. The TFF tanks were assessed several years ago with respect to the RCRA regulations and they were found to be deficient. This study considers the configuration of the current tanks and the RCRA deficiencies identified for each. The study identifies four potential methods and proposes a means of correcting the deficiencies. The cost estimates included in the study account for construction cost; construction methods to minimize work exposure to chemical hazards, radioactive contamination, and ionizing radiation hazards; project logistics; and project schedule. The study also estimates the tank volumes benefit associated with each corrective action to support TFF liquid waste management planning

  19. NGLW RCRA Storage Study

    Energy Technology Data Exchange (ETDEWEB)

    R. J. Waters; R. Ochoa; K. D. Fritz; D. W. Craig

    2000-06-01

    The Idaho Nuclear Technology and Engineering Center (INTEC) at the Idaho National Engineering and Environmental Laboratory contains radioactive liquid waste in underground storage tanks at the INTEC Tank Farm Facility (TFF). INTEC is currently treating the waste by evaporation to reduce the liquid volume for continued storage, and by calcination to reduce and convert the liquid to a dry waste form for long-term storage in calcine bins. Both treatment methods and activities in support of those treatment operations result in Newly Generated Liquid Waste (NGLW) being sent to TFF. The storage tanks in the TFF are underground, contained in concrete vaults with instrumentation, piping, transfer jets, and managed sumps in case of any liquid accumulation in the vault. The configuration of these tanks is such that Resource Conservation and Recovery Act (RCRA) regulations apply. The TFF tanks were assessed several years ago with respect to the RCRA regulations and they were found to be deficient. This study considers the configuration of the current tanks and the RCRA deficiencies identified for each. The study identifies four potential methods and proposes a means of correcting the deficiencies. The cost estimates included in the study account for construction cost; construction methods to minimize work exposure to chemical hazards, radioactive contamination, and ionizing radiation hazards; project logistics; and project schedule. The study also estimates the tank volumes benefit associated with each corrective action to support TFF liquid waste management planning.

  20. INSPTRAX - The Inspection Targeting, Planning and Tracking Database

    Data.gov (United States)

    U.S. Environmental Protection Agency — The INSPTRAX System tracks Air, RCRA, and Water inspection targeting, planning and tracking information. It is used by the the Air, RCRA, and Water programs to input...

  1. RCRA corrective action and closure

    International Nuclear Information System (INIS)

    1995-02-01

    This information brief explains how RCRA corrective action and closure processes affect one another. It examines the similarities and differences between corrective action and closure, regulators' interests in RCRA facilities undergoing closure, and how the need to perform corrective action affects the closure of DOE's permitted facilities and interim status facilities

  2. 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…

  3. ORGDP RCRA/PCB

    International Nuclear Information System (INIS)

    Rodgers, T.

    1986-01-01

    A dual purpose solid/liquid incinerator is currently being constructed at the Oak Ridge Gaseous Diffusion Plant [ORGDP (K-25)] to destroy uranium contaminated, hazardous organic wastes in compliance with the Toxic Substances Control Act (TSCA) and the Resource Conservation and Recovery Act (RCRA). These wastes are generated by the gaseous diffusion plants in Oak Ridge, TN; Paducah, KY; and Portsmouth, OH. In addition, waste will also be received from the Y-12 Plant, Oak Ridge National Laboratory (ORNL), and the Feed Materials Production Center (FMPC). Destruction of PCBs and hazardous liquid organic wastes will be accomplished in a rotary kiln incinerator with an afterburner. This system was selected after a study of various alternatives which are covered in Report No. X-OE-141. Incineration was chosen because it is dependable, permanent, detoxifies organics, and reduces volume. The rotary kiln incinerator was selected because it can thermally destroy organic constituents of liquids, solids, and sludges to produce an organically inert ash. The incineration system, off-gas treatment system, and related instrumentation and controls are being provided by International Waste Energy Systems (IWES) which is responsible for design, construction, startup, and performance testing

  4. Information to licensees regarding two NRC Inspection Manual sections on resolution of degraded and nonconforming conditions and on operability (Generic Letter 91-18)

    International Nuclear Information System (INIS)

    Partlow, J.G.

    1992-01-01

    The NRC staff has issued two sections to be included in Part 9900, Technical Guidance, of the NRC Inspection Manual. The first is, ''Resolution of Degraded and Nonconforming Conditions.'' The second is, ''Operable/Operability: Ensuring the Functional Capability of a System or Component.'' Copies of the additions to the NRC Inspection Manual are provided for information only. No specific licensee actions are required. The additions to the NRC Inspection Manual are based upon previously issued guidance. However, because of the complexity involved in operability determinations and the resolution of degraded and nonconforming conditions, there have been differences in application by NRC staff during past inspection activities. Thus, the purpose of publishing this guidance is to ensure consistency in application of this guidance by the NRC. Regional inspection personnel have been briefed on this guidance. The NRC will conduct further training on these topics to ensure uniform staff understanding

  5. Probabilistic methodology for assessing steam generator tube inspection - Phase II: User's manual for CANTIA Version 1.1

    International Nuclear Information System (INIS)

    Harris, J.E.; Gorman, J.A.; Turner, A.P.L.

    1997-03-01

    The objectives of this project were to develop a computer-based method for probabilistic assessment of inspection strategies for steam generator tubes, and to document the source code and to provide a user's manual for it. The program CANTIA was created to fulfill this objective, and the user's manual is provided in this volume. The documentation and verification of the CANTIA code is provided as a separate report. CANTIA uses Monte Carlo techniques to determine approximate probabilities of steam generator tube failures under accident conditions and primary-to-secondary leak rates under normal and accident conditions at future points in time. The program also determines approximate future flaw distributions and non-destructive examination results from the input data. The probabilities of failure and leak rates and the future flaw distributions can be influenced by performing inspections of the steam generator tubes at some future points in time, and removing defective tubes from the population. The effect of different inspection and maintenance strategies can therefore be determined as a direct effect on the probability of tube failure and primary-to-secondary leak rate

  6. Slaughterhouse Inspection (Egypt). Training Manual : Guidelines for the Planning and Organisation of Training Activities

    NARCIS (Netherlands)

    Blomne Sopov, M.; Ghouti, C.A.; Benlafquih, R.; Vugt, van F.; Latief, A.M.A.

    2014-01-01

    The training manual was prepared for the inspectors of slaughterhouses in Egypt to support the training activities of the General Organization for Veterinary Services (GOVS). The manual has two main parts: 1. Overview on how to design, organize, implement and evaluate training programs in general 2.

  7. Qualification of Manual Phased Array Ultrasonic Techniques for Pipe Weld Inspection in Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Poirier, J.; Hayes, P.; Vicat, F. [GE Inspection Technologies (United States)

    2011-07-01

    Phasor XS can be used for piping weld inspection in any facilities that use EPRI procedures (example: nuclear power plant in Usa, Japan, ...). Whole pipe range is inspected with 5 probes and 6 wedges: 4 1-dimensional probe for sound wave scanning (different frequency, different apertures); 1 dual matrix probe for LW scanning; there are 3 types of wedges optimized for weld inspection. Weld is scanned in 'Raster Scan', maximum range from 35 up to 80 degrees. Probe selection is defined in the procedure according to pipe diameter, pipe thickness and type of access (single or dual side). We have to note that datasets for dual matrix probe are provided with the procedure because this kind of probe cannot be programmed inside Phasor XS

  8. Annual Report RCRA Post-Closure Monitoring and Inspections for Corrective Action Unit 91: Area 3 U-3fi Injection Well, Nevada Test Site, Nevada, for the Period October 2001 - October 2002

    International Nuclear Information System (INIS)

    Richardson, G.

    2003-01-01

    This annual monitoring and inspection report provides an analysis and summary for site inspections, meteorological information, and neutron soil moisture monitoring data obtained at the U-3fi Injection Well during the October 2001 to October 2002 period. The U-3fi Injection Well is located in Area 3 of the Nevada Test Site (NTS), Nye County, Nevada. Inspections of the Area 3 U-3fi Injection Well are conducted to determine and document the physical condition of the concrete pad, facilities, and any unusual conditions that could impact the proper operation of the waste disposal unit closure. The objective of the neutron logging is to monitor the soil moisture conditions along the 128-meter (m) (420-feet [ft]) ER3-3 monitoring well and detect changes that may be indicative of moisture movement in the regulated interval extending between 73 to 82 m (240 to 270 ft)

  9. Implementing RCRA during facility deactivation

    International Nuclear Information System (INIS)

    Lebaron, G.J.

    1997-01-01

    RCRA regulations require closure of permitted treatment, storage and disposal (TSD) facilities within 180 days after cessation of operations, and this may essentially necessitate decommissioning to complete closure. A more cost effective way to handle the facility would be to significantly reduce the risk to human health and the environment by taking it from its operational status to a passive, safe, inexpensive-to-maintain surveillance and maintenance condition (deactivation) prior to decommissioning. This paper presents an innovative approach to the cost effective deactivation of a large, complex chemical processing facility permitted under RCRA. The approach takes into account risks to the environment posed by this facility in comparison to risks posed by neighboring facilities at the site. The paper addresses the manner in which: 1) stakeholders and regulators were involved; 2) identifies a process by which the project proceeds and regulators and stakeholders were involved; 3) end points were developed so completion of deactivation was clearly identified at the beginning of the project, and 4) innovative practices were used to deactivate more quickly and cost effectively

  10. Hanford Facility Resource Conservation and Recovery Act Permit General Inspection Plan

    International Nuclear Information System (INIS)

    Beagles, D.S.

    1995-02-01

    This inspection plan describes the activities that shall be conducted for a general inspection of the Hanford Facility. RCRA includes a requirement that general facility inspections be conducted of the 100, 200 East, 200 West, 300, 400, and 1100 areas and the banks of the Columbia River. This plan meets the RCRA requirements and also provides for scheduling of inspections and defines general and specific items to be noted during the inspections

  11. Annual Report RCRA Post-Closure Monitoring and Inspections for CAU 91: Area 3 U-3fi Injection Well, Nevada Test Site, Nevada, for the period October 2000-October 2001

    International Nuclear Information System (INIS)

    Tobiason, D. S.

    2002-01-01

    This annual Neutron Soil Moisture Monitoring report provides an analysis and summary for site inspections, meteorological information, and neutron soil moisture monitoring data obtained at the U-3fi Injection Well during the October 2000 to October 2001 period. The U-3fi Injection Well is located in Area 3 of the Nevada Test Site (NTS), Nye County, Nevada. Inspections of the Area 3 U-3fi Injection Well are conducted to determine and document the physical condition of the concrete pad, facilities, and any unusual conditions that could impact the proper operation of the waste disposal unit closure. The objective of the neutron-logging program is to monitor the soil moisture conditions along the 128-meter (m) (420-ft) ER3-3 monitoring well and detect changes that may be indicative of moisture movement in the regulated interval extending between 73 to 82 m (240 to 270 ft) or to detect changes that may be indicative of subsidence within the disposal unit itself

  12. Hazardous Waste/IGD: EF_RCRA

    Data.gov (United States)

    U.S. Environmental Protection Agency — EF_RCRA is a subset of facilities from FRS_INTEREST and FRS_FACILITY_SITE which are updated on a monthly basis as part of the Locational Reference Tables (LRT)...

  13. Clues to interpretation of RCRA regulations

    International Nuclear Information System (INIS)

    Siebach, P.R.; Brown, P.H.

    1992-01-01

    Waste waters from industrial facilities are often treated at waste water treatment plants and then discharged to streams or rivers, or may be reused. Discharges of pollutants to waterways are regulated under the Clean Water Act, and require a permit. The Resource Conservation and Recovery Act (RCRA) regulates the management of solid wastes. This paper discusses the status of waste water treatment plant discharges and sludges pursuant to RCRA. It concludes that some exceptions to RCRA allow waste water treatment plants to accept dilute solvent mixtures, treat them, and discharge effluent without needing a RCRA permit. If residual sludges do not exhibit a hazardous characteristic, then they may be managed as nonhazardous solid waste. For DOE and other generators of mixed waste (both radioactive and hazardous), this may allow sludges to be managed as low level radioactive waste. (author)

  14. Interpreting the SARA and RCRA training requirements

    International Nuclear Information System (INIS)

    Moreland, W.M.; Wells, S.M.

    1987-01-01

    The Resource Conservation and Recovery Act (RCRA) and the Superfund Amendments and Reauthorization Act (SARA) promulgated by the EPA (RCRA) and the OSHA (SARA) require hazardous materials training for all individuals working with hazardous materials. Facilities that are involved in the generation, storage, treatment, transportation, or disposal/removal of hazardous materials/waste must comply with all relevant training regulations. Using the guidelines contained in the RCRA and SARA regulations, decisions must be made to determine: the type of regulatory requirement based on facility function (i.e., whether the facility is a RCRA or CERCLA facility). The type of training required for specific categories of workers (e.g. managers, supervisors, or general site workers). The level of training needed for each category of worker. This presentation outlines how the Environmental Compliance and Health Protection Technical Resources and Training Group, working with waste operations personnel, establishes specific training requirements

  15. RCRA corrective action program guide (Interim)

    Energy Technology Data Exchange (ETDEWEB)

    1993-05-01

    The US Department of Energy (DOE) is responsible for compliance with an increasingly complex spectrum of environmental regulations. One of the most complex programs is the corrective action program proposed by the US Environmental Protection Agency (EPA) under the authority of the Resource Conservation and Recovery Act (RCRA) as amended by the Hazardous and Solid Waste Amendments (HSWA). The proposed regulations were published on July 27, 1990. The proposed Subpart S rule creates a comprehensive program for investigating and remediating releases of hazardous wastes and hazardous waste constituents from solid waste management units (SWMUs) at facilities permitted to treat, store, or dispose of hazardous wastes. This proposed rule directly impacts many DOE facilities which conduct such activities. This guidance document explains the entire RCRA Corrective Action process as outlined by the proposed Subpart S rule, and provides guidance intended to assist those persons responsible for implementing RCRA Corrective Action at DOE facilities.

  16. Condition Assessment Survey (CAS) Program. Deficiency standards and inspections methods manual: Volume 7, 0.07 Conveying

    Energy Technology Data Exchange (ETDEWEB)

    1993-05-01

    System information is given for asset determinant factor/CAS repair codes/CAS cost factors; guide sheet tool & material listing; testing methods; inspection frequency; standard system design life tables; and system work breakdown structure. Deficiency standards and inspection methods are presented for elevators and special conveyors.

  17. Condition Assessment Survey (CAS) Program. Deficiency standards and inspections methods manual: Volume 2, 0.02 Substructure

    Energy Technology Data Exchange (ETDEWEB)

    1993-05-01

    System information is given for asset determinant factor/CAS repair codes/CAS cost factors; guide sheet tool & material listing; testing methods; inspection frequency; standard system design life tables; system work breakdown structure; and general system/material data. System assembly/component deficiencies and inspection methods are given for slabs-on-grade, columns, and column fireproofing.

  18. Condition Assessment Survey (CAS) Program. Deficiency standards and inspections methods manual: Volume 3, 0.03 Superstructure

    Energy Technology Data Exchange (ETDEWEB)

    1993-05-01

    General information is presented on asset determinant factor/CAS profile codes/CAS cost process; guide sheet tool & material listing; testing methods; inspection frequency; standard system design life tables; system work breakdown structure; and general system/material data. Deficiency standards and inspection methods are presented for beams; pre-engineered building systems; floors; roof structure; stairs; and fireproofing.

  19. Condition Assessment Survey (CAS) Program. Deficiency standards and inspections methods manual: Volume 1, 0.01 Foundations and footings

    Energy Technology Data Exchange (ETDEWEB)

    1993-05-01

    General information is presented for asset determinant factor/CAS repair codes/CAS cost factors; guide sheet tool & material listing; testing methods; inspection frequency; standard system design life tables; system work breakdown structure; and general system/material data. Deficiency standards and inspection methods are given for footings - spread/strip/grade beams; foundation walls; foundation dampproofing/waterproofing; excavation/backfill/ and piles & caissons.

  20. Condition Assessment Survey (CAS) Program. Deficiency standards and inspections methods manual: Volume 12, 0.12 Sitework

    Energy Technology Data Exchange (ETDEWEB)

    1993-05-01

    General information is presented for asset determinant factor/CAS repair codes/CAS cost factors; guide sheet tool & material listing; testing methods; inspection frequency; standard system design life tables; system work breakdown structure; and general system/material data. Deficiency standards and inspection methods are given for utility distribution systems, central heating, central cooling, electrical, utility support structures, paving roadways/walkways, and tunnels.

  1. Condition Assessment Survey (CAS) Program. Deficiency standards and inspections methods manual: Volume 11, 0.11 Specialty systems

    Energy Technology Data Exchange (ETDEWEB)

    1993-05-01

    General information is presented for asset determinant factor/CAS repair codes/CAS cost factors; guide sheet tool & material listing; testing methods; inspection frequency; standard system design life tables; system work breakdown structure; and general system/material data. Deficiency standards and inspection methods are presented for canopies; loading dock systems; tanks; domes (bulk storage, metal framing); louvers & vents; access floors; integrated ceilings; and mezzanine structures.

  2. Condition Assessment Survey (CAS) Program. Deficiency standards and inspections methods manual: Volume 6, 0.06 Interior construction

    Energy Technology Data Exchange (ETDEWEB)

    1993-05-01

    General information is presented for asset determinant factor/CAS repair codes/CAS cost factors; guide sheet tool & material listing; testing methods; inspection frequency; standard system design life tables; system work breakdown structure; and general system/material data. Deficiency standards and inspection methods are presented for conventional and specialty partitions, toilet partitions & accessories, interior doors, paint finishes/coatings/ wall covering systems; floor finishing systems; and ceiling systems.

  3. Condition Assessment Survey (CAS) Program. Deficiency standards and inspections methods manual: Volume 5, 0.05 Roofing

    Energy Technology Data Exchange (ETDEWEB)

    1993-05-01

    General information is presented for asset determinant factor/CAS repair codes/CAS cost factors; guide sheet tool & material listing; testing methods; inspection frequency; standard system design life tables; and system work breakdown structure. Deficiency standards and inspection methods are presented for built-up membrane; single- ply membrane; metal roofing systems; coated foam membrane; shingles; tiles; parapets; roof drainage system; roof specialties; and skylights.

  4. Federal environmental inspections handbook

    International Nuclear Information System (INIS)

    1991-10-01

    This Federal Environmental Inspection Handbook has been prepared by the Department of Energy (DOE), Office of Environmental Guidance, RCRA/CERCLA Division (EH-231). It is designed to provide DOE personnel with an easily accessible compilation of the environmental inspection requirements under Federal environmental statutes which may impact DOE operations and activities. DOE personnel are reminded that this Handbook is intended to be used in concert with, and not as a substitute for, the Code of Federal Regulations (CFR). Federal Register (FR), and other applicable regulatory documents

  5. Guidance Manual On The RCRA Regulation Of Recycled ...

    Science.gov (United States)

    ... 5 •. K JT •«: *: i a " 1" ' — a « • ba C •- • > a — u — i • • a tt tt e 9 a > i j ... be o »• — eax a > ea — aa §— a — a — B a >. a - i — • e *• «• *rt taM •« »!• 2-20 ...

  6. Condition Assessment Survey (CAS) Program. Deficiency standards and inspections methods manual: Volume 8, 0.08 Mechanical, Book 1

    Energy Technology Data Exchange (ETDEWEB)

    1993-05-01

    System information is presented for asset determinant factor/CAS repair codes/CAS cost factors; guide sheet too & material listing; testing methods; inspection frequency; standard system design life tables; and system work breakdown structure. Deficiency standards are given for plumbing, fire protection, heating, cooling, and special (drinking water cooling systems).

  7. Resource Conservation and Recovery Act (RCRA)

    International Nuclear Information System (INIS)

    1989-01-01

    This Resource Conservation and Recovery Act (RCRA) Facility Investigation Program Plan has been developed to provide a framework for the completion of RCRA Facility Investigations (RFI) at identified units on the Savannah Rive Site (SRS) facility. As such, the RFI Program Plan provides: technical guidance for all work to be performed, managerial control, a practical, scientific approach. The purpose of this Overview is to demonstrate how the basic RFI Program Plan elements (technical, management, and approach) are interwoven to provide a practical and workable plan. The goal of the RFI Program Plan is to provide a systematic, uniform approach for performance and reporting. In addition, the RFI Program Plan has been developed to be specific to the SRS facility and to adhere to the Environmental Protection Agency (EPA) RFI guidance received as part of the SRS. The US EPA publication ''Characterization of Hazardous Waste Sites'' has been liberally adapted for use in this RFI Program Plan

  8. Costs of RCRA corrective action: Interim report

    International Nuclear Information System (INIS)

    Tonn, B.; Russell, M.; Hwang Ho-Ling; Goeltz, R.; Warren, J.

    1991-09-01

    This report estimates the cost of the corrective action provisions of the Resource Conservation and Recovery Act (RCRA) for all non-federal facilities in the United States. RCRA is the federal law which regulates the treatment, storage, disposal, and recovery of hazardous waste. The 1984 amendment to RCRA, known as the Hazardous and Solid Waste Amendments, stipulates that facilities that treat, store or dispose of hazardous wastes (TSDs) must remediate situations where hazardous wastes have escaped into the environment from their solid waste management units (SWMUs). The US Environmental Protection Agency (USEPA 1990a), among others, believes that the costs of RCRA corrective action could rival the costs of SUPERFUND. Evaluated herein are costs associated with actual remedial actions. The remedial action cost estimating program developed by CH2M Hill is known as the Cost of Remedial Action Model (CORA). It provides cost estimates, in 1987 dollars, by technology used to remediate hazardous waste sites. Rules were developed to categorize each SWMU in the RTI databases by the kinds of technologies that would be used to remediate them. Results were then run through CORA using various assumptions for variable values that could not be drawn from the RTI databases and that did not have CORA supplied default values. Cost estimates were developed under several scenarios. The base case assumes a TSD and SWMU universe equal to that captured in the RTI databases, a point of compliance at the SWMU boundary with no ability to shift wastes from SWMU to SWMU, and a best-as-practical clean-up to health-based standards. 11 refs., 12 figs., 12 tabs

  9. Establishing a regulatory framework for a RCRA corrective action program

    International Nuclear Information System (INIS)

    Krueger, J.W.

    1989-01-01

    Recently, the environmental community has become keenly aware of problems associated with integration of the demanding regulations that apply to environmental restoration activities. Once can not attend an EPA-sponsored conference on Superfund without hearing questions concerning the Resource, Conservation, and Recovery Act (RCRA) and the applicability of the National Contingency Plan (NCP) to sites that do not qualify for the National Priorities List (NPL). In particular, the U.S. Department of Energy (DOE) has been greatly criticized for its inability to define a comprehensive approach for cleaning up its hazardous waste sites. This article presents two decision flowcharts designed to resolve some of this confusion for DOE. The RCRA/CERCLA integration diagram can help the environmental manager determine which law applies and under what conditions, and the RCRA corrective action decision flowchart can guide the manager in determining which specific sections of RCRA apply to a RCRA-lead environmental restoration program

  10. Autonomy and manual operation in a small robotic system for under-vehicle inspections at security checkpoints

    Science.gov (United States)

    Smuda, William; Muench, Paul L.; Gerhart, Grant R.; Moore, Kevin L.

    2002-07-01

    Unmanned ground vehicle (UGV) technology can be used in a number of ways to assist in counter-terrorism activities. In addition to the conventional uses of tele-operated robots for unexploded ordinance handling and disposal, water cannons and other crowd control devices, robots can also be employed for a host of terrorism deterrence and detection applications. In previous research USU developed a completely autonomous prototype robot for performing under- vehicle inspections in parking areas (ODIS). Testing of this prototype and discussions with the user community indicated that neither the technology nor the users are ready for complete autonomy. In this paper we present a robotic system based on ODIS that balances the users' desire/need for tele- operation with a limited level of autonomy that enhances the performance of the robot. The system can be used by both civilian law enforcement and military police to replace the traditional mirror on a stick system of looking under cars for bombs and contraband.

  11. Ground-water monitoring under RCRA

    International Nuclear Information System (INIS)

    Coalgate, J.

    1993-11-01

    In developing a regulatory strategy for the disposal of hazardous waste under the Resource Conservation and Recovery Act (RCRA), protection of ground-water resources was the primary goal of the Environmental Protection Agency (EPA). EPA's ground-water protection strategy seeks to minimize the potential for hazardous wastes and hazardous constituents in waste placed in land disposel units to migrate into the environment. This is achieved through liquids management (limiting the placement of liquid wastes in or on the land, requiring the use of liners beneath waste, installing leachate collection systems and run-on and run-off controls, and covering wastes at closure). Ground-water monitoring serves to detect any failure in EPA's liquids management strategy so that ground-water contamination can be detected and addressed as soon as possible

  12. NPL deletion policy for RCRA-regulated TSD facilities finalized

    International Nuclear Information System (INIS)

    Anon.

    1995-01-01

    Under a new policy published by EPA on March 20, 1995, certain sites may be deleted from the National Priorities List (NPL) and deferred to RCRA corrective action. To be deleted from the NPL, a site must (1) be regulated under RCRA as a treatment, storage, or disposal (TSD) facility and (2) meet the four criteria specified by EPA. The new NPL deletion policy, which does not pertain to federal TSD facilities, became effective on April 19, 1995. 1 tab

  13. Accelerating RCRA corrective action: The principles of the DOE approach

    International Nuclear Information System (INIS)

    Kimmell, T.A.; Green, D.R.; Ranek, N.L.; Coalgate, J.L.

    1995-01-01

    The US Department of Energy (DOE) is involved in the remediation of environmental contamination at many of its facilities under the Resource Conservation and Recovery Act (RCRA). RCRA's corrective action provisions were established by the Hazardous and Solid Waste Amendments of 1984 (HSWA). In response to the HSWA mandate, EPA established a program for the conduct of RCRA corrective action that was similar to that established under the Comprehensive Environmental Response Compensation and Liability Act (CERCLA). In addition, EPA developed and implemented its ''stabilization'' initiative as a means of quickly addressing immediate risks posed by releases until long term solutions can be applied. To improve the efficiency of environmental restoration at its facilities, DOE is developing guidance and training programs on accelerated environmental restoration under RCRA. A RCRA guidance document, entitled ''Accelerating RCRA Corrective Action at DOE Facilities,'' is currently being developed by DOE's Office of Environmental Policy and Assistance. The new guidance document will outline a decision-making process for determining if acceleration is appropriate for individual facilities, for identifying, evaluating, and selecting options for program acceleration, and for implementing selected acceleration options. The document will also discuss management and planning strategies that provide a firm foundation for accelerating RCRA corrective action. These strategies include a number of very basic principles that have proven effective at DOE and other federal facilities, as well as some new approaches. The purpose of this paper is to introduce DOE's new guidance document, discuss the general approach presented in the guidance for accelerating RCRA corrective action, and to emphasize some of the more important principles of effective management and planning

  14. EPA seeks to make RCRA more effective through legislative changes

    International Nuclear Information System (INIS)

    Anon.

    1995-01-01

    Since RCRA was enacted in 1976 and amended in 1984, hazardous waste management has been transformed. To protect human health and the environment as mandated by the act, EPA has developed a complex cradle-to-grave system for managing hazardous waste. The agency recognizes that some targeted legislative changes could make RCRA even more useful, particularly by (1) establishing some open-quotes middle groundclose quotes for waste posing low risks, and (2) emphasizing sensible and enforceable hazardous waste management practices

  15. RCRA corrective action determination of no further action

    International Nuclear Information System (INIS)

    1996-06-01

    On July 27, 1990, the U.S. Environmental Protection Agency (EPA) proposed a regulatory framework (55 FR 30798) for responding to releases of hazardous waste and hazardous constituents from solid waste management units (SWMUs) at facilities seeking permits or permitted under the Resource Conservation and Recovery Act (RCRA). The proposed rule, 'Corrective Action for Solid Waste Management Units at Hazardous Waste Facilities', would create a new Subpart S under the 40 CFR 264 regulations, and outlines requirements for conducting RCRA Facility Investigations, evaluating potential remedies, and selecting and implementing remedies (i.e., corrective measures) at RCRA facilities. EPA anticipates instances where releases or suspected releases of hazardous wastes or constituents from SWMUs identified in a RCRA Facility Assessment, and subsequently addressed as part of required RCRA Facility Investigations, will be found to be non-existent or non-threatening to human health or the environment. Such releases may require no further action. For such situations, EPA proposed a mechanism for making a determination that no further corrective action is needed. This mechanism is known as a Determination of No Further Action (DNFA) (55 FR 30875). This information Brief describes what a DNFA is and discusses the mechanism for making a DNFA. This is one of a series of Information Briefs on RCRA corrective action

  16. ORGDP RCRA/PCB incinerator facility

    International Nuclear Information System (INIS)

    Rogers, T.

    1987-01-01

    A dual purpose solid/liquid incinerator is currently being constructed at the Oak Ridge Gaseous Diffusion Plant [ORGDP (K-25)] to destroy uranium contaminated, hazardous organic wastes in compliance with the Toxic Substances Control Act (TSCA) and the Resource Conservation and Recovery Act (RCRA). These wastes are generated by the gaseous diffusion plants in Oak Ridge, TN; Paducah, KY; and Portsmouth, OH. In addition, waste will also be received from the Y-12 Plant, Oak Ridge National Laboratory (ORNL), and the Feed Materials Production Center (FMPC). Destruction of PCBs and hazardous liquid organic wastes will be accomplished in a rotary kiln incinerator with an afterburner. This system was selected faster a study of various alternatives. Incineration was chosen because it is dependable, permanent, detoxifies organics, and reduces volume. The rotary kiln incinerator was selected because it can thermally destroy organic constituents of liquids, solids, and sludges to produce an organically inert ash. In addition to the incineration off-gas treatment system, the facility includes a tank farm, drum storage buildings, a solids preparation area, a control room, and a data management system. The incineration system, off-gas treatment system, and related instrumentation and controls are being provided by International Waste Energy Systems (IWES) which is responsible for design, construction, startup, and performances testing

  17. Notification: EPA Progress on Meeting Resource Conservation and Recovery Act Statutory Mandate for Minimum Frequency of Inspections at Hazardous Waste Disposal Facilities

    Science.gov (United States)

    Project #OPE-FY15-0018, January 20, 2015. The EPA OIG plans to begin preliminary research on EPA’s progress in meeting minimum inspection requirements under the RCRA at treatment, storage and disposal facilities (TSDFs).

  18. IAEA safeguards technical manual

    International Nuclear Information System (INIS)

    1980-02-01

    The necessity for statistical inference procedures arises because of time and cost limitations imposed on inspection activities, and also because of inherent limitations of inspection measurement instruments and techniques. This manual produces statistical concepts and techniques in the field of nuclear material control

  19. Quarterly RCRA Groundwater Monitoring Data for the Period July through September 2006

    Energy Technology Data Exchange (ETDEWEB)

    Hartman, Mary J.

    2007-02-01

    This report provides information about RCRA groundwater monitoring for the period July through September 2006. Eighteen Resource Conservation and Recovery Act (RCRA) sites were sampled during the reporting quarter.

  20. EPA R1 RCRA Corrective Action 2020 Baseline Site Property Boundaries

    Data.gov (United States)

    U.S. Environmental Protection Agency — Property boundaries as indicated in figures of all facilities subject to RCRA Corrective Action on the 2020 baseline in Region 1. For more information on the RCRA...

  1. Achieving RCRA compliance in DOE defense waste management operations

    International Nuclear Information System (INIS)

    Frankhauser, W.A.; Shepard, M.D.

    1989-01-01

    The U.S. Department of Energy (DOE) generates significant volumes of radioactive mixed waste (RMW) through its defense-related activities. Defense RMW is co-regulated by DOE and the U.S. Environmental Protection Agency/State agencies in accordance with requirements of the Resource Conservation and Recovery Act (RCRA) and the Atomic Energy Act (AEA). This paper highlights some of the problems encountered in co-regulation and discusses achievements of the defense waste management program in integrating RCRA requirements into RMW operations. Defense waste sites are planning facility modifications and major new construction projects to develop treatment, storage and disposal capacity for existing RMW inventories and projected needs

  2. Application of non-destructive testing and in-service inspections to research reactors and preparation of ISI programme and manual for WWR-C research reactors

    International Nuclear Information System (INIS)

    Khattab, M.

    1996-01-01

    The present report gives a review on the results of application of non-destructive testing and in-service inspections to WWR-C reactors in different countries. The major problems related to reactor safety and the procedure of inspection techniques are investigated to collect the experience gained from this type of reactors. Exchangeable experience in solving common problems in similar reactors play an important role in the effectiveness of their rehabilitation programmes. 9 figs., 4 tabs

  3. Automated ultrasonic inspection of nuclear plant components

    International Nuclear Information System (INIS)

    Baron, J.A.; Dolbey, M.P.

    1982-01-01

    For reasons of safety and efficiency, automated systems are used in performing ultrasonic inspection of nuclear components. An automated system designed specifically for the inspection of headers in a nuclear plant is described. In-service inspection results obtained with this system are shown to correlate with pre-service inspection results obtained by manual methods

  4. RCRA groundwater data analysis protocol for the Hanford Site, Washington

    International Nuclear Information System (INIS)

    Chou, C.J.; Jackson, R.L.

    1992-04-01

    The Resource Conservation and Recovery Act of 1976 (RCRA) groundwater monitoring program currently involves site-specific monitoring of 20 facilities on the Hanford Site in southeastern Washington. The RCRA groundwater monitoring program has collected abundant data on groundwater quality. These data are used to assess the impact of a facility on groundwater quality or whether remediation efforts under RCRA corrective action programs are effective. Both evaluations rely on statistical analysis of groundwater monitoring data. The need for information on groundwater quality by regulators and environmental managers makes statistical analysis of monitoring data an important part of RCRA groundwater monitoring programs. The complexity of groundwater monitoring programs and variabilities (spatial, temporal, and analytical) exhibited in groundwater quality variables indicate the need for a data analysis protocol to guide statistical analysis. A data analysis protocol was developed from the perspective of addressing regulatory requirements, data quality, and management information needs. This data analysis protocol contains four elements: data handling methods; graphical evaluation techniques; statistical tests for trend, central tendency, and excursion analysis; and reporting procedures for presenting results to users

  5. Decontamination Study for Mixed Waste Storage Tanks RCRA Closure

    International Nuclear Information System (INIS)

    Leaphart, D.M.; Reed, S.R.; Rankin, W.N.

    1995-01-01

    The Savannah River Site (SRS) plans to close six underground tanks storing mixed waste under RCRA regulations. In support of this closure effort, a study was performed to determine the optimal method of decontaminating these tanks to meet the closure requirements. Items consaidered in the evaluation of the decontamination methods included effectiveness, compatibility with existing waste residues, possible cleaning solution disposal methods, and cost

  6. Resource Conservation and Recovery Act (RCRA) Part B permit application for tank storage units at the Oak Ridge Y-12 Plant

    International Nuclear Information System (INIS)

    1994-05-01

    In compliance with the Resource Conservation and Recovery Act (RCRA), this report discusses information relating to permit applications for three tank storage units at Y-12. The storage units are: Building 9811-1 RCRA Tank Storage Unit (OD-7); Waste Oil/Solvent Storage Unit (OD-9); and Liquid Organic Solvent Storage Unit (OD-10). Numerous sections discuss the following: Facility description; waste characteristics; process information; groundwater monitoring; procedures to prevent hazards; contingency plan; personnel training; closure plan, post closure plan, and financial requirements; record keeping; other federal laws; organic air emissions; solid waste management units; and certification. Sixteen appendices contain such items as maps, waste analyses and forms, inspection logs, equipment identification, etc

  7. A RCRA clean closure of a unique site - Kerr Hollow quarry at the Y-12 Plant

    International Nuclear Information System (INIS)

    Stone, J.E.; Yemington, C.

    1991-01-01

    An abandoned rock quarry, Kerr Hollow Quarry (KHQ), near the DOE Oak Ridge Y-12 Plant, Oak Ridge, Tennessee, was used from 1951-1988 as a site to treat RCRA wastes which were reactive, corrosive, or ignitable and which posed major concerns for personnel safety. The wastes were generated from operations at the Y-12 Plant and Oak Ridge National Laboratory and were previously treated by allowing the wastes to react with the water in KHQ. When closure of the site was required by the RCRA regulations, a closure method was selected to allow for clean closure of the quarry without treatment or removal of the water in KHQ. The method proposed to and approved by the Tennessee Department of Health and Environment (TDHE) was one of surveying the containers in the quarry by a submersible Remotely Operated Vehicle (ROV) using sonar and visually inspecting the containers by camera to confirm that all containers are breached and empty. Any container found intact would be breached to allow the contents to react with water and form non-hazardous residue. The progress of this unique type of closure is presented along with a summary of the problems encountered, planning activities, equipment utilized and other information about the closure. All work was done with remotely operated equipment. This work is being performed by Sonsub, Inc. This closure project showed the practicality and cost benefits of telerobotic systems for work on hazardous waste sites. In addition to the intangible benefit of reduced exposure of workers, insurance costs are much lower and efficiency is higher. Daily start-up time is reduced since there is no need to don protective suits or other gear. Productivity is higher since personnel work only in clean areas where they are not hampered by protective gear. Cleanup time at shift end is minimized since the remote equipment does not leave the hazardous area and personnel need not go through decontamination

  8. Automated PCB Inspection System

    Directory of Open Access Journals (Sweden)

    Syed Usama BUKHARI

    2017-05-01

    Full Text Available Development of an automated PCB inspection system as per the need of industry is a challenging task. In this paper a case study is presented, to exhibit, a proposed system for an immigration process of a manual PCB inspection system to an automated PCB inspection system, with a minimal intervention on the existing production flow, for a leading automotive manufacturing company. A detailed design of the system, based on computer vision followed by testing and analysis was proposed, in order to aid the manufacturer in the process of automation.

  9. Drum inspection robots: Application development

    International Nuclear Information System (INIS)

    Hazen, F.B.; Warner, R.D.

    1996-01-01

    Throughout the Department of Energy (DOE), drums containing mixed and low level stored waste are inspected, as mandated by the Resource Conservation and Recovery Act (RCRA) and other regulations. The inspections are intended to prevent leaks by finding corrosion long before the drums are breached. The DOE Office of Science and Technology (OST) has sponsored efforts towards the development of robotic drum inspectors. This emerging application for mobile and remote sensing has broad applicability for DOE and commercial waste storage areas. Three full scale robot prototypes have been under development, and another project has prototyped a novel technique to analyze robotically collected drum images. In general, the robots consist of a mobile, self-navigating base vehicle, outfitted with sensor packages so that rust and other corrosion cues can be automatically identified. They promise the potential to lower radiation dose and operator effort required, while improving diligence, consistency, and documentation

  10. Characterizing cemented TRU waste for RCRA hazardous constituents

    International Nuclear Information System (INIS)

    Yeamans, D.R.; Betts, S.E.; Bodenstein, S.A.

    1996-01-01

    Los Alamos National Laboratory (LANL) has characterized drums of solidified transuranic (TRU) waste from four major waste streams. The data will help the State of New Mexico determine whether or not to issue a no-migration variance of the Waste Isolation Pilot Plant (WIPP) so that WIPP can receive and dispose of waste. The need to characterize TRU waste stored at LANL is driven by two additional factors: (1) the LANL RCRA Waste Analysis Plan for EPA compliant safe storage of hazardous waste; (2) the WIPP Waste Acceptance Criteria (WAC) The LANL characterization program includes headspace gas analysis, radioassay and radiography for all drums and solids sampling on a random selection of drums from each waste stream. Data are presented showing that the only identified non-metal RCRA hazardous component of the waste is methanol

  11. Analysis of TRU waste for RCRA-listed elements

    International Nuclear Information System (INIS)

    Mahan, C.; Gerth, D.; Yoshida, T.

    1996-01-01

    Analytical methods for RCRA listed elements on Portland cement type waste have been employed using both microwave and open hot plate digestions with subsequent analysis by inductively coupled plasma atomic emission spectroscopy (ICP-AES), inductively coupled plasma mass spectrometry (ICP-AES), inductively coupled plasma mass spectrometry (ICP-MS), graphite furnace atomic absorption (GFAA) and cold vapor atomic absorption and fluorescence (CVAA/CVAFS). Four different digestion procedures were evaluated including an open hot plate nitric acid digestion, EPA SW-846 Method 3051, and 2 methods using modifications to Method 3051. The open hot plate and the modified Method 3051, which used aqua regia for dissolution, were the only methods which resulted in acceptable data quality for all 14 RCRA-listed elements. Results for the nitric acid open hot plate digestion were used to qualify the analytical methods for TRU waste characterization, and resulted in a 99% passing score. Direct chemical analysis of TRU waste is being developed at Los Alamos National Laboratory in an attempt to circumvent the problems associated with strong acid digestion methods. Technology development includes laser induced breakdown spectroscopy (LIBS), laser ablation inductively coupled plasma mass spectrometry (LA-ICPMS), dc arc CID atomic emission spectroscopy (DC-AES), and glow discharge mass spectrometry (GDMS). Analytical methods using the Portland cement matrix are currently being developed for each of the listed techniques. Upon completion of the development stage, blind samples will be distributed to each of the technology developers for RCRA metals characterization

  12. Glossary of CERCLA, RCRA and TSCA related terms and acronyms

    International Nuclear Information System (INIS)

    1993-10-01

    This glossary contains CERCLA, RCRA and TSCA related terms that are most often encountered in the US Department of Energy (DOE) Environmental Restoration and Emergency Preparedness activities. Detailed definitions are included for key terms. The CERCLA definitions included in this glossary are taken from the Comprehensive Environmental Response, Compensation and Liability Act (CERCLA), as amended and related federal rulemakings. The RCRA definitions included in this glossary are taken from the Resource Conservation and Recovery Act (RCRA) and related federal rulemakings. The TSCA definitions included in this glossary are taken from the Toxic Substances and Control Act (TSCA) and related federal rulemakings. Definitions related to TSCA are limited to those sections in the statute and regulations concerning PCBs and asbestos.Other sources for definitions include additional federal rulemakings, assorted guidance documents prepared by the US Environmental Protection Agency (EPA), guidance and informational documents prepared by the US Department of Energy (DOE), and DOE Orders. The source of each term is noted beside the term. Terms presented in this document reflect revised and new definitions published before July 1, 1993

  13. RCRA Facilities Assessment (RFA)---Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    1987-03-01

    US Department of Energy (DOE) facilities are required to be in full compliance with all federal and state regulations. In response to this requirement, the Oak Ridge National Laboratory (ORNL) has established a Remedial Action Program (RAP) to provide comprehensive management of areas where past and current research, development, and waste management activities have resulted in residual contamination of facilities or the environment. This report presents the RCRA Facility Assessment (RFA) required to meet the requirements of RCRA Section 3004(u). Included in the RFA are (1) a listing of all sites identified at ORNL that could be considered sources of releases or potential releases; (2) background information on each of these sites, including location, type, size, period of operation, current operational status, and information on observed or potential releases (as required in Section II.A.1 of the RCRA permit); (3) analytical results obtained from preliminary surveys conducted to verify the presence or absence of releases from some of the sites; and (4) ORNL's assessment of the need for further remedial attention

  14. National RCRA Hazardous Waste Biennial Report Data Files

    Science.gov (United States)

    The United States Environmental Protection Agency (EPA), in cooperation with the States, biennially collects information regarding the generation, management, and final disposition of hazardous wastes regulated under the Resource Conservation and Recovery Act of 1976 (RCRA), as amended. Collection, validation and verification of the Biennial Report (BR) data is the responsibility of RCRA authorized states and EPA regions. EPA does not modify the data reported by the states or regions. Any questions regarding the information reported for a RCRA handler should be directed to the state agency or region responsible for the BR data collection. BR data are collected every other year (odd-numbered years) and submitted in the following year. The BR data are used to support regulatory activities and provide basic statistics and trend of hazardous waste generation and management. BR data is available to the public through 3 mechanisms. 1. The RCRAInfo website includes data collected from 2001 to present-day (https://rcrainfo.epa.gov/rcrainfoweb/action/main-menu/view). Users of the RCRAInfo website can run queries and output reports for different data collection years at this site. All BR data collected from 2001 to present-day is stored in RCRAInfo, and is accessible through this website. 2. An FTP site allows users to access BR data files collected from 1999 - present day (ftp://ftp.epa.gov/rcrainfodata/). Zip files are available for download directly from this

  15. RCRA Facilities Assessment (RFA)---Oak Ridge National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    1987-03-01

    US Department of Energy (DOE) facilities are required to be in full compliance with all federal and state regulations. In response to this requirement, the Oak Ridge National Laboratory (ORNL) has established a Remedial Action Program (RAP) to provide comprehensive management of areas where past and current research, development, and waste management activities have resulted in residual contamination of facilities or the environment. This report presents the RCRA Facility Assessment (RFA) required to meet the requirements of RCRA Section 3004(u). Included in the RFA are (1) a listing of all sites identified at ORNL that could be considered sources of releases or potential releases; (2) background information on each of these sites, including location, type, size, period of operation, current operational status, and information on observed or potential releases (as required in Section II.A.1 of the RCRA permit); (3) analytical results obtained from preliminary surveys conducted to verify the presence or absence of releases from some of the sites; and (4) ORNL`s assessment of the need for further remedial attention.

  16. RCRA Facilities Assessment (RFA)---Oak Ridge National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    1987-03-01

    US Department of Energy (DOE) facilities are required to be in full compliance with all federal and state regulations. In response to this requirement, the Oak Ridge National Laboratory (ORNL) has established a Remedial Action Program (RAP) to provide comprehensive management of areas where past and current research, development, and waste management activities have resulted in residual contamination of facilities or the environment. This report presents the RCRA Facility Assessment (RFA) required to meet the requirements of RCRA Section 3004(u). Included in the RFA are (1) a listing of all sites identified at ORNL that could be considered sources of releases or potential releases; (2) background information on each of these sites, including location, type, size, period of operation, current operational status, and information on observed or potential releases (as required in Section II.A.1 of the RCRA permit); (3) analytical results obtained from preliminary surveys conducted to verify the presence or absence of releases from some of the sites; and (4) ORNL's assessment of the need for further remedial attention.

  17. RCRA closure plan for the Bear Creek Burial Grounds B Area and Walk- In Pits at the Oak Ridge Y-12 Plant, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1993-01-01

    In June 1987, the RCRA Closure/Postclosure Plan for the Bear Creek Burial Grounds (BCBG) was submitted to the Tennessee Department of Environment and Conservation (TDEC) for review and approval. TDEC modified and issued the plan approved on September 30, 1987. Subsequently, this plan was modified again and approved as Y/TS-395, Revised RCRA Closure Plan for the Bear Creek Burial Grounds (February 29, 1988). Y/TS-395 was initially intended to apply to A Area, C-West, B Area, and the Walk-In Pits of BCBG. However, a concept was developed to include the B Area (non-RCRA regulated) in the Walk-In Pits so that both areas would be closed under one cap. This approach included a tremendous amount of site preparation with an underlying stabilization base of 16 ft of sand for blast protection. The plan was presented to the state of Tennessee on March 8, 1990, and the Department of Energy was requested to review other unique alternatives to close the site. This amended closure plan goes further to include inspection and maintenance criteria along with other details

  18. CY2003 RCRA GROUNDWATER MONITORING WELL SUMMARY REPORT

    International Nuclear Information System (INIS)

    MARTINEZ, C.R.

    2003-01-01

    This report describes the calendar year (CY) 2003 field activities associated with the installation of two new groundwater monitoring wells in the A-AX Waste Management Area (WMA) and four groundwater monitoring wells in WMA C in the 200 East Area of the Hanford Nuclear Reservation. All six wells were installed by Fluor Hanford Inc. (FH) for CH2M Hill Hanford Group, Inc. (CHG) in support of Draft Hanford Facility Agreement and Consent Order (Tri-Party Agreement) M-24-00 milestones and ''Resource Conservation and Recovery Act of 1976'' (RCRA) groundwater monitoring requirements. Drilling data for the six wells are summarized in Table 1

  19. RCRA Treatment, Disposal, and Storage Site Boundaries in Louisiana, Geographic NAD83, EPA (2002) [RCRA_TSD_LA_poly_EPA_2002)

    Data.gov (United States)

    Louisiana Geographic Information Center — This is a shapefile of RCRA Treatment, Storage, and Disposal facility boundaries developed by PRC Environmental Management, Inc (PRC) per a Work Assignment from the...

  20. Quarterly RCRA Groundwater Monitoring Data for the Period April Through June 2006

    Energy Technology Data Exchange (ETDEWEB)

    Hartman, Mary J.

    2006-11-01

    This report provides information about RCRA groundwater monitoring for the period April through June 2006. Seventeen RCRA sites were sampled during the reporting quarter. Sampled sites include seven monitored under groundwater indicator evaluation (''detection'') programs, eight monitored under groundwater quality assessment programs, and two monitored under final-status programs.

  1. Calendar Year 2007 Resource Conservation and Recovery Act Annual Monitoring Report for the U.S. Department of Energy Y-12 National Security Complex, Oak Ridge, Tennessee - RCRA Post-Closure Permit Nos. TNHW-113, TNHW-116, and TNHW-128

    Energy Technology Data Exchange (ETDEWEB)

    Elvado Environmental

    2008-02-01

    This report contains groundwater quality monitoring data obtained during calendar year (CY) 2007 at the following hazardous waste treatment, storage, and disposal (TSD) units located at the US Department of Energy (DOE) Y-12 National Security Complex (hereafter referenced as Y-12) in Oak Ridge, Tennessee; this S-3 Site, Oil Landfarm, Bear Creek Burial Grounds/Walk-In Pits (BCBG/WIP), Eastern S-3 Site Plume, Chestnut Ridge Security Pits (CRSP), Chestnut Ridge Sediment Disposal Baste (CRSDB), few Hollow Quarry (KHQ), and East Chestnut Ridge Waste Pile (ECRWP). Hit monitoring data were obtained in accordance with the applicable Resource Conservation and Recovery Act of 1976 (RCRA) hazardous waste post-closure permit (PCP). The Tennessee Department of Environment and Conservation (TDEC) - Division of Solid Waste Management issued the PCPs to define the requirements for RCRA post-closure inspection, maintenance, and groundwater monitoring at the specified TSD units located within the Bear Creek Hydrogeologic Regime (PCP no. TNHW-116), Upper East Fork Poplar Creek Hydrogeologic Regime (PCP no. TNHW-113), and Chestnut Ridge Hydrogeologic Regime (PCP no. TNHW-128). Each PCP requires the Submittal of an annual RCRA groundwater monitoring report containing the groundwater sampling information and analytical results obtained at each applicable TSD unit during the preceding CY, along with an evaluation of groundwater low rates and directions and the analytical results for specified RCRA groundwater target compounds; this report is the RCRA annual groundwater monitoring report for CY 2007. The RCRA post-closure groundwater monitoring requirements specified in the above-referenced PCP for the Chestnut Ridge Regime replace those defined in the previous PCP (permit no. TNHW-088), which expired on September 18, 2005, but remained effective until the TDEC issued the new PCP in September 2006. The new PCP defines site-specific groundwater sampling and analysis requirements for the

  2. RCRA, a state perspective: the buck should stop with us

    Energy Technology Data Exchange (ETDEWEB)

    McCall, III, M N

    1977-11-01

    The states must carry the ball of realizing the Resource Conservation and Recovery Act (RCRA); state agencies and the EPA can work together, though they don't always agree; adequate funding is absolutely necessary. The states' perspective of their role is threefold-regulation, assistance, and leadership, with maximum input into implementation. A National Governors' Association committee on waste management was established. Neither RCRA itself nor supporting committee reports allow definition of open dumps and sanitary landfills with other than traditional meaning. Conducting the open dump inventory should be the responsibility of the states, with financial support from EPA. The existence of state nonimportation laws should not preclude that state from receiving money for a hazardous waste program. The criteria for defining hazardous wastes must be realistic if an unmanageable list is to be avoided. State solid waste management agencies must provide aid to local government and private industry. The state-not EPA- is the best level of government to carry out an effective solid waste program. The Federal program should concentrate on resource and energy conservation, research and development, demonstration projects, establishing markets for recycled materials, and education and training programs. Planning should be coordinated through state agencies.

  3. 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

  4. Endoscopic inspection of steam turbines

    International Nuclear Information System (INIS)

    Maliniemi, H.; Muukka, E.

    1990-01-01

    For over ten years, Imatran Voima Oy (IVO) has developed, complementary inspection methods for steam turbine condition monitoring, which can be applied both during operation and shutdown. One important method used periodically during outages is endoscopic inspection. The inspection is based on the method where the internal parts of the turbine is inspected through access borings with endoscope and where the magnified figures of the internal parts is seen on video screen. To improve inspection assurance, an image-processing based pattern recognition method for cracks has been developed for the endoscopic inspection of turbine blades. It is based on the deduction conditions derived from the crack shape. The computer gives an alarm of a crack detection and prints a simulated image of the crack, which is then checked manually

  5. Packaging supplier inspection guide

    International Nuclear Information System (INIS)

    Stromberg, H.M.; Gregg, R.E.; Kido, C.; Boyle, C.D.

    1991-05-01

    This is document is a guide for conducting quality assurance inspections of transportations packaging suppliers, where suppliers are defined as designers, fabricators, distributors, users, or owners of transportation packaging. This document can be used during an inspection to determine regulatory compliance within the requirements of 10 Code of Federal Regulations, Part 71, Subpart H (10 CFR 71.101--71.135). The guidance described in this document provides a framework for an inspection. It provides the inspector with the flexibility to adapt the methods and concepts presented here to meet the needs of the particular facility being inspected. The guide was developed to ensure a structured and consistent approach for inspections. The method treats each activity at a supplier facility as a separate entity (or functional element), and combines the activities within the framework of an ''inspection tree.'' The method separates each functional element into several areas of performance and then identifies guidelines, based on regulatory requirements, to be used to qualitatively rate each area. This document was developed to serve as a field manual to facilitate the work of inspectors. 1 ref., 1 fig., 5 tabs

  6. POST-CLOSURE INSPECTION REPORT FOR CORRECTIVE ACTION UNIT 92: AREA 6 DECON PAD FACILITY, NEVADA. TEST SITE NEVADA, FOR THE PERIOD JANUARY 2004 - DECEMBER 2004

    International Nuclear Information System (INIS)

    BECHTEL NEVADA

    2005-01-01

    This Post-Closure Inspection Report provides an analysis and summary of inspections for Corrective Action Unit (CAU) 92, Area 6 Decon Pond Facility, Nevada Test Site, Nevada. CAU 92 was closed in accordance with the Resource Conservation and Recovery Act (RCRA) Part B Operational Permit (Nevada Division of Environmental Protection, 1995) and the Federal Facility Agreement and Consent Order of 1996 on May 11, 1999. CAU 92 consists of two Corrective Action Sites (CASs): CAS 06-04-01, Decon Pad oil/Water Separator; and CAS 06-05-02, Decontamination Pond (RCRA). Both CASs have use restrictions; however, only CAS 06-05-02, Decontamination Pond (RCRA), requires post-closure inspections. CAS 06-04-01, Decon Pad Oil/Water Separator, is located inside the fence at the Building 6-605 compound. This report covers the annual period January 2004 through December 2004

  7. 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...

  8. Intelligent Automated Nuclear Fuel Pellet Inspection System

    International Nuclear Information System (INIS)

    Keyvan, S.

    1999-01-01

    At the present time, nuclear pellet inspection is performed manually using naked eyes for judgment and decisionmaking on accepting or rejecting pellets. This current practice of pellet inspection is tedious and subject to inconsistencies and error. Furthermore, unnecessary re-fabrication of pellets is costly and the presence of low quality pellets in a fuel assembly is unacceptable. To improve the quality control in nuclear fuel fabrication plants, an automated pellet inspection system based on advanced techniques is needed. Such a system addresses the following concerns of the current manual inspection method: (1) the reliability of inspection due to typical human errors, (2) radiation exposure to the workers, and (3) speed of inspection and its economical impact. The goal of this research is to develop an automated nuclear fuel pellet inspection system which is based on pellet video (photographic) images and uses artificial intelligence techniques

  9. Petitions to delist hazardous wastes: A guidance manual. Second edition

    International Nuclear Information System (INIS)

    1993-03-01

    EPA developed the guidance document to assist facilities in preparing delisting petitions for the exclusion of listed hazardous wastes. The manual provides general information on hazardous waste delisting, discusses sampling strategies and testing protocols in detail, and presents a step-by-step approach to compiling a complete delisting petition. This updated edition incorporates recent changes in RCRA regulations, agency policies, and delisting criteria. It also reflects the current emphasis on ground-water monitoring data and new concepts such as upfront delistings

  10. The Pinellas Plant RCRA facility investigation - A case study

    International Nuclear Information System (INIS)

    Kilbury, Richard; Keshian, Berg; Farley, Dwain; Meyer, David; Ingle, David; Biedermann, Charles

    1992-01-01

    Under the direction of the U.S. Department of Energy Albuquerque Field Office Environmental Restoration Program, a Resource Conservation and Recovery Act (RCRA) Facility Investigation (RFI) was completed at the Pinellas Plant to fulfill requirements of the Hazardous and Solid Waste Amendments of 1984 (HSWA) permit issued on February 9, 1990 by the U.S. Environmental Protection Agency (EPA). This RFI addressed potential contaminant releases and environmental conditions at 15 solid waste management units (SWMUs). The RFI characterization program began in April 1990 and was completed in May 1991. The scope of RFI data collection activities is presented in the Pinellas Plant RFI Workplan issued in May 1990 and approved by EPA on April 16, 1991. An RFI Report was submitted to EPA on September 1, 1991. This paper presents a summary of RFI results and conclusions. Primary environmental concerns at the Pinellas Plant are emphasized. (author)

  11. RCRA corrective action ampersand CERCLA remedial action reference guide

    International Nuclear Information System (INIS)

    1994-07-01

    This reference guide provides a side-by-side comparison of RCRA corrective action and CERCLA Remedial Action, focusing on the statutory and regulatory requirements under each program, criterial and other factors that govern a site's progress, and the ways in which authorities or requirements under each program overlap and/or differ. Topics include the following: Intent of regulation; administration; types of sites and/or facilities; definition of site and/or facility; constituents of concern; exclusions; provisions for short-term remedies; triggers for initial site investigation; short term response actions; site investigations; remedial investigations; remedial alternatives; clean up criterial; final remedy; implementing remedy; on-site waste management; completion of remedial process

  12. 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)

  13. Development of guidance for preparing treatability variance petitions from the RCRA Land Disposal Restrictions for DOE [Department of Energy] mixed-waste streams

    International Nuclear Information System (INIS)

    Harms, T.; Scheuer, N.; Martin, R.; Van Epp, T.; Triplett, M.

    1990-01-01

    In response to the Department of Energy's (DOE) anticipated need for variances from the Resource Conservation and Recovery Act (RCRA) Land Disposal Restriction (LDR) treatment requirements, a treatability variance guidance document is being prepared for use by DOE facilities and operations offices. The guidance document, although applicable to non-mixed hazardous waste streams, provides specific guidance regarding radioactive mixed-waste streams. Preparation of the guidance manual has involved developing an overview of the Land Disposal Restrictions, as well as an overview of the petition preparation process. The DOE internal review requirements are specifically addressed in the manual. Specific data requirements and engineering analyses are also described. A discussion of EPA's criteria for granting a treatability variance is also provided. A checklist for completeness of the petition is provided. Model language for use in DOE treatability variance petitions will be provided in a petition for a DOE waste stream as an appendix to the document

  14. Special Focus Areas for Hazardous Waste Cleanups under the Resource Conservation and Recovery Act (RCRA)

    Science.gov (United States)

    In order to manage the new and changing needs of the RCRA Corrective Action Program, EPA is constantly exploring program enhancements, alternate exposure pathways, and new technologies available to protect human health and environment.

  15. Low-level mixed waste: An RCRA perspective for NRC licensees

    International Nuclear Information System (INIS)

    1990-08-01

    The publication presents an overview of RCRA requirements for commercially-generated low-level mixed waste. It is designed for Nuclear Regulatory Commission (NRC) licensees who may not be familiar with EPA regulations that apply to their waste products

  16. Cleanups In My Community (CIMC) - RCRA and Base Realignment and Closure (BRAC) Federal Facilities, National Layer

    Data.gov (United States)

    U.S. Environmental Protection Agency — This data layer provides access to Resource Conservation and Recovery Act (RCRA) Base Realignment and Closure (BRAC) sites as part of the CIMC web service. The...

  17. RCRA closures at Rocky Flats Plant: A programmatic perspective and case study

    International Nuclear Information System (INIS)

    Ogg, Randy T.; Peterman, Bruce D.

    1992-01-01

    The Interagency Agreement (IAG) integrates a unique mechanism for remediating hazardous waste sites at the Rocky Flats Plant (RFP), which include utilizing RCRA and CERCLA technical/regulatory processes. Pursuant to the IAG signed by the Department of Energy (DOE), Environmental Protection Agency (EPA), and the Colorado Department of Health (CDH) on January 22, 1991, sixteen operable units (OUs) were defined for characterization and remediation at RFP. Of the sixteen OUs, six are classified as Resource Conservation and Recovery Act (RCRA) closure units. The six RCRA interim status closure units are: Solar Evaporation Ponds-OU 4, Present LandfUl-OU 7, Original Process Waste Lines-OU 9, Other Outside Closures-OU 10, West Spray Field-OU II, and Inside Building Closures-OU 15. The IAG will function as a technical/regulatory mechanism for managing/complying with all aspects of the RCRA interim status closure units at RFP. (author)

  18. EPA Linked Open Data: Resource Conservation and Recovery Act Handlers (RCRA)

    Data.gov (United States)

    U.S. Environmental Protection Agency — RCRAInfo is EPA’s comprehensive information system that supports the Resource Conservation and Recovery Act (RCRA) of 1976 and the Hazardous and Solid Waste...

  19. IAEA safeguards technical manual

    International Nuclear Information System (INIS)

    1982-03-01

    Part F of the Safeguards Technical Manual is being issued in three volumes. Volume 1 was published in 1977 and revised slightly in 1979. Volume 1 discusses basic probability concepts, statistical inference, models and measurement errors, estimation of measurement variances, and calibration. These topics of general interest in a number of application areas, are presented with examples drawn from nuclear materials safeguards. The final two chapters in Volume 1 deal with problem areas unique to safeguards: calculating the variance of MUF and of D respectively. Volume 2 continues where Volume 1 left off with a presentation of topics of specific interest to Agency safeguards. These topics include inspection planning from a design and effectiveness evaluation viewpoint, on-facility site inspection activities, variables data analysis as applied to inspection data, preparation of inspection reports with respect to statistical aspects of the inspection, and the distribution of inspection samples to more than one analytical laboratory. Volume 3 covers generally the same material as Volumes 1 and 2 but with much greater unity and cohesiveness. Further, the cook-book style of the previous two volumes has been replaced by one that makes use of equations and formulas as opposed to computational steps, and that also provides the bases for the statistical procedures discussed. Hopefully, this will help minimize the frequency of misapplications of the techniques

  20. 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

  1. 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.)

  2. T-3 cask users' manual. Revision 1

    International Nuclear Information System (INIS)

    1986-06-01

    This user's manual for the T-C spent fuel cask provides information on: operating procedures; inspection and maintenance procedures; criticality evaluation; shielding evaluation; thermal evaluation; structural evaluation; and limitations

  3. Inspector's manual for mechanically stabilized earth walls.

    Science.gov (United States)

    2010-06-01

    The scope of the project is to develop a condition rating system, creation of an inspector's manual to reference during : inspection or address any training for inspectors at the district level. The research project will develop a MSE wall : conditio...

  4. RIMACS, Reactor Inspection Main Control System

    International Nuclear Information System (INIS)

    2008-01-01

    1 - Description of program or function: RIMACS prepares for automatic inspection files on each inspection item for the reactor. These automatic inspection files provide the data to move RIROB (Reactor Inspection Robot) with laser by interpreting the coordinates of LASPO (Laser Positioner) and the laser detecting device of RIROB in three dimensional space. In addition, when RIROB arrives at the inspecting location, the files provide all values of the manipulator's motions to acquire the ultrasonic data. RIMACS provides various modules in order to perform these complex functions, and the functions are programmed on graphic user interface for the convenience of the user. RIMACS provides various functions, such as insertion of reactor production data, selection of the reactor for inspection, the creation of automatic inspection file, the selection of the inspection item, inspection simulation, and automatic inspection procedures. It also provides all other functions, which are necessary for the inspection, such as operating program download and manual control of LASPO and RIROB, the inspection simulation and the inspection status display by means of the graphic screen, and SODAS (ultra-Sonic Data Acquisition System) drive verification. 2 - Methods: Moving path and operation procedures for inspection robot are generated automatically with Kinematics algorithm. 3 - Restrictions on the complexity of the problem: A graphics display with MS-Window capability is required

  5. Temporal trend analysis of RCRA groundwater monitoring data

    International Nuclear Information System (INIS)

    Need, E.A.

    1994-01-01

    Statistical analysis of RCRA groundwater monitoring data at a uranium hexafluoride processing facility showed a statistically significant increase in the concentration of gross beta activity in monitor wells downgradient of surface impounds storing calcium fluoride sludge and high pH water. Because evidence of leakage had not been detected in lysimeters installed beneath the impounds, the operator sought an evaluation of other potential causes of the result, including natural variability. This study determined that all five data sets showed either long-term excursionary (spike-like), or seasonal forms of temporal variation. Gross beta had an upward long-term trend with multiple excursions that almost appeared to be seasonal. Gross alpha had an upward long-term trend with multiple excursions that were clearly not seasonal. Specific conductance had both upward and downward long-term trends but no other variations. pH had a downward long-term trend with multiple excursions that were clearly not seasonal. Fluoride had a downward long-term trend without excursions but with clear seasonal variations. The gross beta result that appeared to be a significant change was a spike event on the upward long-term trend

  6. 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

  7. RCRA Closure Plan for the Bear Creek Burial Grounds B Area and Walk-In Pits at the Oak Ridge Y-12 Plant, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1993-04-01

    In June 1987, the RCRA Closure/Postclosure Plan for the Bear Creek Burial Grounds (BCBG) was submitted to the Tennessee Department of Environment and Conservation (TDEC) for review and approval. TDEC modified and issued the plan approved on September 30, 1987. Y/TS-395 was initially intended to apply to A Area, C-West, B Area, and the Walk-In Pits of BCBG. However, a concept was developed to include the B Area (non-RCRA regulated) in the Walk-In Pits so that both areas would be closed under one cap. This approach included a tremendous amount of site preparation with an underlying stabilization base of 16 ft of sand for blast protection. In January 1993, the Closure Plan was revised to include inspection and maintenance criteria and to reflect that future monitoring and remediation would be conducted as part of the ongoing Comprehensive Environmental Response, Compensation, and Liability Act activities at the Oak Ridge Y-12 Plant. This Closure Plan revision is intended to reflect the placement of the Kerr Hollow Quarry debris at the Walk-In Pits, revise the closure dates, and acknowledge that the disposition of a monitoring well within the closure site cannot be verified

  8. Hanford Environmental Information System (HEIS) user's manual

    International Nuclear Information System (INIS)

    1991-10-01

    The Hanford Environmental Information System (HEIS) is a consolidated set of automated resources that effectively manage the data gathered during environmental monitoring and restoration of the Hanford Site. The HEIS includes an integrated database that provides consistent and current data to all users and promotes sharing of data by the entire user community. Data stored in the HEIS are collected under several regulatory programs. Currently these include the Comprehensive Environmental Response, Compensation and Liability Act of 1980 (CERCLA); the Resource Conservation and Recovery Act of 1976 (RCRA); and the Ground-Water Environmental Surveillance Project, managed by the Pacific Northwest Laboratory. The HEIS is an information system with an inclusive database. The manual, the HEIS User's Manual, describes the facilities available to the scientist, engineer, or manager who uses the system for environmental monitoring, assessment, and restoration planning; and to the regulator who is responsible for reviewing Hanford Site operations against regulatory requirements and guidelines

  9. An example of system integration for RCRA policy analysis

    International Nuclear Information System (INIS)

    Tonn, B.; Goeltz, R.; Schmidt, K.

    1991-01-01

    This paper describes the synthesis of various computer technologies and software systems used on a project to estimate the costs of remediating Solid Waste Management Units (SWMUs) that fall under the corrective action provisions of the Resource Conservation and Recovery Act (RCRA). The project used two databases collected by Research Triangle Institute (RTI) that contain information on SWMUs and a PC-based software system called CORA that develops cost estimates for remediating SWMUs. The project team developed rules to categorize every SWMU in the databases by the kinds of technologies required to clean them up. These results were input into CORA, which estimated costs associated with the technologies. Early on, several computing challenges presented themselves. First, the databases have several hundred thousand records each. Second, the categorization rules could not be written to cover all combinations of variables. Third, CORA is run interactively and the analysis plan called for running CORA tens of thousands of times. Fourth, large data transfers needed to take place between RTI and Oak Ridge National Laboratory. Solutions to these problems required systems integration. SWMU categorization was streamlined by using INTERNET as was the data transfer. SAS was used to create files used by a program called SuperKey that was used to run CORA. Because the analysis plan required the generation of hundreds of thousands of cost estimates, memory management software was needed to allow the portable IBM P70 to do the job. During the course of the project, several other software packages were used, including: SAS System for Personal Computers (SAS/PC), DBase III, LOTUS 1-2-3, PIZAZZ PLUS, LOTUS Freelance Plus, and Word Perfect. Only the comprehensive use of all available hardware and software resources allowed this project to be completed within the time and budget constraints. 5 refs., 3 figs., 3 tabs

  10. PNNL Hoisting and Rigging Manual

    Energy Technology Data Exchange (ETDEWEB)

    Haynie, Todd O.; Fullmer, Michael W.

    2008-12-29

    This manual describes the safe and cost effective operation, inspection, maintenance, and repair requirements for cranes, hoists, fork trucks, slings, rigging hardware, and hoisting equipment. It is intended to be a user's guide to requirements, codes, laws, regulations, standards, and practices that apply to Pacific Northwest National Laboratory (PNNL) and its subcontractors.

  11. Successful completion of a RCRA closure for the Fernald Environmental Management Project

    International Nuclear Information System (INIS)

    Lippitt, J.M.; Kolthoff, K.

    1995-01-01

    This paper discusses the successful completion of a RCRA (Resource Conservation and Recovery Act) closure of a HF (hydrofluoric acid) tank car at FEMP, which is on the national priorities list of hazardous waste sites and is undergoing CERCLA remediation. The HF tank car closure was conducted by FERMCO. Through a combination of sound planning and team work, the HF tank car was closed safely and ahead of schedule. During > 22,000 hr field work required for construction modifications and neutralization of 9,600 gallons of HF and decontamination rinseates, there were no OSHA recordable incidents. The system design avoided additional costs by maximizing use of existing equipment and facilities. This successful closure of the HF tank car demonstrates FEMP's commitment to reducing risks and cleaning up the facility in a manner consistent with objectives of RCRA regulations and the Ohio EPA hazardous waste rules. This in turn facilitated ongoing negotiations with Ohio EPA to integrate RCRA closure and the ongoing CERCLA remediation activities. This paper addresses why the unit was clean closed under an approved RCRA Closure Plan. Integration of EPA regulations for RCRA and CERCLA programs and the DOE-Orders impacting design, construction and operation of an acid neutralization system is also reviewed. The paper concludes with a discussion of lessons learned in the process in preparing the closure plant and through final project close out

  12. Hospital Inspections

    Data.gov (United States)

    U.S. Department of Health & Human Services — Welcome to hospitalinspections.org, a website run by the Association of Health Care Journalists (AHCJ) that aims to make federal hospital inspection reports easier...

  13. Hanford facility RCRA permit condition II.U.1 report: mapping of underground piping

    Energy Technology Data Exchange (ETDEWEB)

    Hays, C.B.

    1996-09-27

    The purpose of this report is to fulfill Condition Il.U.1. of the Hanford Facility (HF) Resource Conservation and Recovery Act (RCRA) Permit. The HF RCRA Permit, Number WA7890008967, became effective on September 28, 1994 (Ecology 1994). Permit Conditions Il.U. (mapping) and II.V. (marking) of the HF RCRA Permit, Dangerous Waste (OW) Portion, require the mapping and marking of dangerous waste underground pipelines subject to the provisions of the Washington Administrative Code (WAC) Chapter 173-303. Permit Condition Il.U.I. requires the submittal of a report describing the methodology used to generate pipeline maps and to assure their quality. Though not required by the Permit, this report also documents the approach used for the field marking of dangerous waste underground pipelines.

  14. Manual Therapy

    OpenAIRE

    Hakgüder, Aral; Kokino, Siranuş

    2002-01-01

    Manual therapy has been used in the treatment of pain and dysfunction of spinal and peripheral joints for more than a hundred years. Manual medicine includes manipulation, mobilization, and postisometric relaxation techniques. The aim of manual therapy is to enhance restricted movement caused by blockage of joints keeping postural balance, restore function and maintain optimal body mechanics. Anatomic, biomechanical, and neurophysiological evaluations of the leucomotor system is essential for...

  15. Performance test results of noninvasive characterization of RCRA surrogate waste by prompt gamma neutron activation analysis

    International Nuclear Information System (INIS)

    Gehrke, R.J.; Propp, W.A.

    1997-11-01

    A performance evaluation to determine the feasibility of using prompt gamma neutron activation analysis (PGNAA) for noninvasive, quantitative assay of mixed waste containers was sponsored by DOE's Office of Technology Development (OTD), the Mixed Waste Focus Area (MWFA), and the Idaho National Engineering and Environmental Laboratory (INEEL). The evaluation was conducted using a surrogate waste, based on Portland cement, that was spiked with three RCRA metals, mercury, cadmium, and lead. The results indicate that PGNAA has potential as a process monitor. However, further development is required to improve its sensitivity to meet regulatory requirements for determination of these RCRA metals

  16. RCRA and operational monitoring 1994 fiscal year work plan, WBS 1.5.3

    Energy Technology Data Exchange (ETDEWEB)

    1993-12-01

    RCRA & Operational Monitoring (ROM) Program Office manages the direct funded Resource Conservation Recovery Act (RCRA) and Operational Monitoring under Work Breakdown Structure (WBS) 1.5.3. The ROM Program Office is a Branch of liquid Waste Disposal, a part of Restoration and Remediation of Westinghouse Hanford Company (WHC). The Fiscal Year Work Plan (FYWP) takes it direction from the Multi-Year Program Plan (MYPP). The FYWP provides the near term, enhanced details for the Program Office to use as baseline Cost, Scope and Schedule. Changs Control administered during the fiscal year is against the baseline provided by the FYWP.

  17. Exiting RCRA Subtitle C regulation data for supporting a new regulatory path for immobilized mixed debris

    Energy Technology Data Exchange (ETDEWEB)

    Porter, C.L. [Jetseal, Inc., Idaho Falls, ID (United States); Carson, S.D.; Cheng, Wu-Ching [Sandia National Labs., Albuquerque, NM (United States)

    1995-12-31

    This paper presents analytical and empirical data that provide technical support for the position that mixed debris (debris contaminated with both radioactive and hazardous constituents) treated by immobilization in accordance with 40 CFR 268.45 can exit RCRA Subtitle C requirements at the time the treatment is complete. Pathways analyses and risk assessments of low-level waste and RCRA mixed waste disposal facilities show that these two types of facilities provide equivalent long-term (> 100 years) performance and protection of human health and the environment. A proposed two-tier approach for waste form performance criteria is discussed.

  18. RCRA and operational monitoring 1994 fiscal year work plan, WBS 1.5.3

    International Nuclear Information System (INIS)

    1993-12-01

    RCRA ampersand Operational Monitoring (ROM) Program Office manages the direct funded Resource Conservation Recovery Act (RCRA) and Operational Monitoring under Work Breakdown Structure (WBS) 1.5.3. The ROM Program Office is a Branch of liquid Waste Disposal, a part of Restoration and Remediation of Westinghouse Hanford Company (WHC). The Fiscal Year Work Plan (FYWP) takes it direction from the Multi-Year Program Plan (MYPP). The FYWP provides the near term, enhanced details for the Program Office to use as baseline Cost, Scope and Schedule. Changs Control administered during the fiscal year is against the baseline provided by the FYWP

  19. Structures manual

    Science.gov (United States)

    2001-01-01

    This manual was written as a guide for use by design personnel in the Vermont Agency of Transportation Structures Section. This manual covers the design responsibilities of the Section. It does not cover other functions that are a part of the Structu...

  20. Quality Manual

    Science.gov (United States)

    Koch, Michael

    The quality manual is the “heart” of every management system related to quality. Quality assurance in analytical laboratories is most frequently linked with ISO/IEC 17025, which lists the standard requirements for a quality manual. In this chapter examples are used to demonstrate, how these requirements can be met. But, certainly, there are many other ways to do this.

  1. 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.)

  2. Fall 2010 Semiannual (III.H. and I.U.) Report for the HWMA/RCRA Post Closure Permit for the INTEC Waste Calcining Facility and the CPP 601/627/640 Facility at the INL Site

    Energy Technology Data Exchange (ETDEWEB)

    Boehmer, Ann

    2010-11-01

    The Waste Calcining Facility is located at the Idaho Nuclear Technology and Engineering Center. In 1999, the Waste Calcining Facility was closed under an approved Hazardous Waste Management Act/Resource Conservation and Recovery Act (HWMA/RCRA) Closure Plan. Vessels and spaces were grouted and then covered with a concrete cap. The Idaho Department of Environmental Quality issued a final HWMA/RCRA post-closure permit on September 15, 2003, with an effective date of October 16, 2003. This permit sets forth procedural requirements for groundwater characterization and monitoring, maintenance, and inspections of the Waste Calcining Facility to ensure continued protection of human health and the environment. The post closure permit also includes semiannual reporting requirements under Permit Conditions III.H. and I.U. These reporting requirements have been combined into this single semiannual report, as agreed between the Idaho Cleanup Project and Idaho Department of Environmental Quality. The Permit Condition III.H. portion of this report includes a description and the results of field methods associated with groundwater monitoring of the Waste Calcining Facility. Analytical results from groundwater sampling, results of inspections and maintenance of monitoring wells in the Waste Calcining Facility groundwater monitoring network, and results of inspections of the concrete cap are summarized. The Permit Condition I.U. portion of this report includes noncompliances not otherwise required to be reported under Permit Condition I.R. (advance notice of planned changes to facility activity which may result in a noncompliance) or Permit Condition I.T. (reporting of noncompliances which may endanger human health or the environment). This report also provides groundwater sampling results for wells that were installed and monitored as part of the Phase 1 post-closure period of the landfill closure components in accordance with HWMA/RCRA Landfill Closure Plan for the CPP-601 Deep

  3. RCRA corrective action for underground storage tanks -- Subtitle C for Subtitle I

    International Nuclear Information System (INIS)

    1995-08-01

    The purpose of this report is to provide guidance to DOE and DOE contractor personnel responsible for planning and implementation of corrective measures addressing cleanup of releases of hazardous materials or regulated substances from underground storage tanks regulated under RCRA Subtitle C or Subtitle I

  4. 76 FR 76158 - Agency Information Collection Activities; Proposed Collection; Comment Request; RCRA Expanded...

    Science.gov (United States)

    2011-12-06

    ... contents of the docket, and to access those documents in the public docket that are available..., including through the use of appropriate automated electronic, mechanical, or other technological collection... as State, local, or Tribal governments. Title: RCRA Expanded Public Participation. ICR numbers: EPA...

  5. RCRA Part A permit characterization plan for the U-2bu subsidence crater. Revision 1

    International Nuclear Information System (INIS)

    1998-04-01

    This plan presents the characterization strategy for Corrective Action Unit (CAU) 109, U-2bu Subsidence Crater (referred to as U-2bu) in Area 2 at the Nevada Test Site (NTS). The objective of the planned activities is to obtain sufficient characterization data for the crater soils and observed wastes under the conditions of the current Resource Conservation and Recovery Act (RCRA) Part A permit. The scope of the characterization plan includes collecting surface and subsurface soil samples with hand augers and for the purpose of site characterization. The sampling strategy is to characterize the study area soils and look for RCRA constituents. Observable waste soils and surrounding crater soils will be analyzed and evaluated according to RCRA closure criteria. Because of the status of the crater a RCRA Part A permit site, acquired radionuclide analyses will only be evaluated in regards to the health and safety of site workers and the disposition of wastes generated during site characterization. The U-2bu Subsidence Crater was created in 1971 by a Lawrence Livermore National Laboratory underground nuclear test, event name Miniata, and was used as a land-disposal unit for radioactive and hazardous waste from 1973 to 1988

  6. The implications of RCRA [Resource Conservation and Recovery Act] regulation for the disposal of transuranic and high-level waste

    International Nuclear Information System (INIS)

    Sigmon, C.F.; Sharples, F.E.; Smith, E.D.

    1988-01-01

    In May of 1987 the Department of Energy (DOE) published a rule interpreting the definition of ''byproduct'' under the Atomic Energy Act. This byproduct rule clarified the role of the Resource Conservation and Recovery Act (RCRA) in the regulation of DOE's radioactive waste management activities. According to the rule, only the radioactive portion of DOE's mixed radioactive and hazardous waste (mixed waste), including mixed transuranic (TRU) and high-level waste (HLW), is exempt from RCRA under the byproduct exemption. The portion of a waste that is hazardous as defined by RCRA is subject to full regulation under RCRA. Because the radioactive and hazardous portions of m any, if not most, DOE wastes are likely to be inseparable, the rule in effect makes most mixed wastes subject to dual regulation. The potential application of RCRA to facilities such as the Waste Isolation Pilot Plant (WIPP) and the HLW repository creates unique challenges for both the DOE and regulatory authorities. Strategies must be developed to assure compliance with RCRA without either causing excessive administrative burdens or abandoning the goal of minimizing radiation exposure. This paper will explore some of the potential regulatory options for and recent trends in the regulation of TRU and HLW under RCRA

  7. The SWAMI inspection robot: Fernald site requirements

    International Nuclear Information System (INIS)

    Hazen, F.B.

    1993-01-01

    The purpose of this document is to introduce and describe the Stored Waste Autonomous Mobile Inspector (SWAMI) robot project and to identify issues that will need to be addressed prior to its field demonstration at Fernald in mid-1995. SWAMI is a mobile robotic vehicle that will perform mandated weekly inspections of waste containers. Fernald has a large inventory of these containers and a need to protect workers from radiation hazards while enhancing the efficiency and effectiveness of the inspections. Fernald's role in this project is to supply the demonstration site and make all necessary preparations. This includes identification of the test areas and plans, and identification and compliance to Federal, State, DOE, and Site regulations on system safety and quality. In addition, Fernald will link SWAMI output images to off-line mass data storage, and also to an on-line ORACLE database. The authors shall initiate a dialog with State and Federal regulators towards the near term goal of acceptance of the SWAMI test plan and a longer term goal of acceptance of SWAMI as a supplement and improvement to present mandated RCRA inspections

  8. Biosafety Manual

    Energy Technology Data Exchange (ETDEWEB)

    King, Bruce W.

    2010-05-18

    Work with or potential exposure to biological materials in the course of performing research or other work activities at Lawrence Berkeley National Laboratory (LBNL) must be conducted in a safe, ethical, environmentally sound, and compliant manner. Work must be conducted in accordance with established biosafety standards, the principles and functions of Integrated Safety Management (ISM), this Biosafety Manual, Chapter 26 (Biosafety) of the Health and Safety Manual (PUB-3000), and applicable standards and LBNL policies. The purpose of the Biosafety Program is to protect workers, the public, agriculture, and the environment from exposure to biological agents or materials that may cause disease or other detrimental effects in humans, animals, or plants. This manual provides workers; line management; Environment, Health, and Safety (EH&S) Division staff; Institutional Biosafety Committee (IBC) members; and others with a comprehensive overview of biosafety principles, requirements from biosafety standards, and measures needed to control biological risks in work activities and facilities at LBNL.

  9. GRACE manual

    International Nuclear Information System (INIS)

    Ishikawa, T.; Kawabata, S.; Shimizu, Y.; Kaneko, T.; Kato, K.; Tanaka, H.

    1993-02-01

    This manual is composed of three kinds of objects, theoretical background for calculating the cross section of elementary process, usage and technical details of the GRACE system. Throughout this manual we take the tree level process e + e - → W + W - γ as an example, including the e ± -scalar boson interactions. The real FORTRAN source code for this process is attached in the relevant sections as well as the results of calculation, which might be a great help for understanding the practical use of the system. (J.P.N.)

  10. Implementation of the INSPECT software package for statistical calculation in nuclear material accountability

    International Nuclear Information System (INIS)

    Marzo, M.A.S.

    1986-01-01

    The INSPECT software package was developed in the Pacific Northwest Laboratory for statistical calculations in nuclear material accountability. The programs apply the inspection and evaluation methodology described in Part of the Safeguards Technical Manual. In this paper the implementation of INSPECT at the Safeguards Division of CNEN, and the main characteristics of INSPECT are described. The potential applications of INSPECT to the nuclear material accountability is presented. (Author) [pt

  11. Dewatering and RCRA partial closure action on solar evaporation ponds, Rocky Flats Plant, Golden, Colorado

    International Nuclear Information System (INIS)

    1991-06-01

    The Department of Energy (DOE) has prepared an Environmental Assessment (DOE/EA-0487) on its proposal to partially close five solar evaporation ponds at the Rocky Flats Plant (RFP) pursuant to the requirements of the Resource Conservation and Recovery Act (RCRA). This proposal would be known as a RCRA partial closure and would be accomplished by dewatering the ponds, where necessary, and converting any remaining sludge or evaporator concentrate to a solid wasteform (pondcrete and saltcrete). The pond sites would be stabilized to prevent erosion or other disturbance to the soil and to prevent infiltration of rain or snowmelt. The solid wasteform would be transported offsite for disposal. The five solar ponds (designated 207-A, 207-B (north, center, and south), and 207-C), are the only solar evaporation ponds that exist at the RFP. A finding of no significant impact is included

  12. Quarterly report of RCRA groundwater monitoring data for period January 1--March 31, 1995

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-07-01

    This quarterly report contains data received between January and March 1995, which are the cutoff dates for this reporting period. This report may contain not only data from the January through March quarter, but also data from earlier sampling events that were not previously reported. Nineteen Resource Conservation and Recovery Act of 1976 (RCRA) groundwater monitoring projects are conducted at the Hanford Site. These projects include treatment, storage, and disposal facilities for both solid and liquid waste. The groundwater monitoring programs described in this report comply with the interim-status federal (Title 40 Code of Federal Regulation [CFR] Part 265) and state (Washington Administrative Code [WAC] 173-303-400) regulations. The RCRA projects are monitored under one of three programs: background monitoring, indicator parameter evaluation, or groundwater quality assessment.

  13. Groundwater Monitoring Plan for the 1301-N, 1324-N/NA, and 1325-N RCRA Facilities

    International Nuclear Information System (INIS)

    Hartman, Mary J.

    2001-01-01

    The 1301-N and 1325-N Liquid Waste Disposal Facilities, the 1324-N Surface Impoundment, and the 1324-NA Percolation Pond, located in the 100 N Area of the Hanford Site, are regulated under the Resource Conservation and Recovery Act of 1976 (RCRA). The closure plans for these facilities stipulate that groundwater is monitored according to the 100-N Pilot Project: Proposed Consolidated Groundwater Monitoring Program (BHI-00725). This document supplements the consolidated plan by providing information on sampling and analysis protocols, quality assurance, data management, and a conceptual model for the RCRA sites. Monitoring well networks, constituents, and sampling frequency remain the same as in the consolidated plan or the previous groundwater monitoring plan (Hartman 1996)

  14. Groundwater monitoring plan for the Hanford Site 216-B-3 pond RCRA facility

    International Nuclear Information System (INIS)

    Barnett, D.B.; Chou, C.J.

    1998-06-01

    The 216-B-3 pond system was a series of ponds for disposal of liquid effluent from past Hanford production facilities. In operation since 1945, the B Pond system has been a RCRA facility since 1986, with Resource Conservation and Recovery Act (RCRA) interim-status groundwater monitoring in place since 1988. In 1994, discharges were diverted from the main pond, where the greatest potential for contamination was thought to reside, to the 3C expansion pond. In 1997, all discharges to the pond system were discontinued. In 1990, the B Pond system was elevated from detection groundwater monitoring to an assessment-level status because total organic halogens and total organic carbon were found to exceed critical means in two wells. Subsequent groundwater quality assessment failed to find any specific hazardous waste contaminant that could have accounted for the exceedances, which were largely isolated in occurrence. Thus, it was recommended that the facility be returned to detection-level monitoring

  15. Quarterly report of RCRA groundwater monitoring data for period April 1, 1993 through June 30, 1993

    Energy Technology Data Exchange (ETDEWEB)

    Jungers, D.K.

    1993-10-01

    Hanford Site interim-status groundwater monitoring projects are conducted as either background, indicator parameter evaluation, or groundwater quality assessment monitoring programs. This report contains data from Hanford Site groundwater monitoring projects. Westinghouse Hanford Company (WHC) manages the RCRA groundwater monitoring projects for federal facilities on the Hanford Site. Project management, specifying data needs, performing quality control (QC) oversight, managing data, and preparing project sampling schedules are all parts of this responsibility. Pacific Northwest Laboratory (PNL) administers the contract for analytical services and provides groundwater sampling services to WHC for the RCRA groundwater monitoring program. This quarterly report contains data received between May 24 and August 20, 1993, which are the cutoff dates for this reporting period. This report may contain not only data from samples collected during the April through June quarter but also data from earlier sampling events that were not previously reported.

  16. Quarterly report of RCRA groundwater monitoring data for period October 1 through December 31, 1994

    International Nuclear Information System (INIS)

    1995-04-01

    Hanford Site interim-status groundwater monitoring projects are conducted as either background, indicator parameter evaluation, or groundwater quality assessment monitoring programs as defined in the Resource Conservation and Recovery Act of 1976 (RCRA); and open-quotes Interim Status Standards for Owners and Operators of Hazardous Waste Treatment, Storage, and Disposal Facilitiesclose quotes (Title 40 Code of Federal Regulations [CFR] Part 265), as amended. Compliance with the 40 CFR 265 regulations is required by the Washington Administrative Code (WAC) 173-303. This report contains data from Hanford Site groundwater monitoring projects. The location of each facility is shown. Westinghouse Hanford Company (WHC) manages the RCRA groundwater monitoring projects for federal facilities on the Hanford Site. Performing project management, preparing groundwater monitoring plans, well network design and installation, specifying groundwater data needs, performing quality control (QC) oversight, data management, and preparing project sampling schedules are all parts of this responsibility. Pacific Northwest Laboratory (PNL) administers the contract for analytical services and provides groundwater sampling services to WHC for the RCRA groundwater monitoring program. This quarterly report contains data received between October and December 1994, which are the cutoff dates for this reporting period. This report may contain not only data from the October through December quarter, but also data from earlier sampling events that were not previously reported

  17. SACM and the RCRA stabilization initiative: Similarities of principles and applicability

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-01-01

    The Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) and the corrective action provisions of the Resource Conservation and Recovery Act (RCRA) provide standards for the remediation of environmental media contaminated with hazardous substances or hazardous waste, respectively. In both cases, prior to the US Environmental Protection Agency`s (EPA) development of the two subject reform initiatives, existing formal processes specified the level of site investigation required, the process for reaching a decision on the method of remediation, public participation in the decision process, and enforcement authorities that include orders and schedules of compliance. Traditionally, implementation of these processes has resulted in a great amount of time, effort, and money being expended before actual remediation began. Following criticism from the public and the regulated community, the EPA has proposed streamlining reforms for hazardous waste site cleanup under both CERCLA and RCRA that will begin remediation sooner with lower costs. The purpose of this Information Brief is to discuss the common goals, processes, and strategies of the Superfund Accelerated Cleanup Model (SACM) and the RCRA Stabilization Initiative.

  18. Guide to ground water remediation at CERCLA response action and RCRA corrective action sites

    International Nuclear Information System (INIS)

    1995-10-01

    This Guide contains the regulatory and policy requirements governing remediation of ground water contaminated with hazardous waste [including radioactive mixed waste (RMW)], hazardous substances, or pollutants/contaminants that present (or may present) an imminent and substantial danger. It was prepared by the Office of Environmental Policy and Assistance, RCRA/CERCLA Division (EH-413), to assist Environmental Program Managers (ERPMs) who often encounter contaminated ground water during the performance of either response actions under CERCLA or corrective actions under Subtitle C of RCRA. The Guide begins with coverage of the regulatory and technical issues that are encountered by ERPM's after a CERCLA Preliminary Assessment/Site Investigation (PA/SI) or the RCRA Facility Assessment (RFA) have been completed and releases into the environment have been confirmed. It is based on the assumption that ground water contamination is present at the site, operable unit, solid waste management unit, or facility. The Guide's scope concludes with completion of the final RAs/corrective measures and a determination by the appropriate regulatory agencies that no further response action is necessary

  19. Obtaining variances from the treatment standards of the RCRA Land Disposal Restrictions

    International Nuclear Information System (INIS)

    1990-05-01

    The Resource Conservation and Recovery Act (RCRA) Land Disposal Restrictions (LDRs) [40 CFR 268] impose specific requirements for treatment of RCRA hazardous wastes prior to disposal. Before the LDRs, many hazardous wastes could be land disposed at an appropriately designed and permitted facility without undergoing treatment. Thus, the LDRs constitute a major change in the regulations governing hazardous waste. EPA does not regulate the radioactive component of radioactive mixed waste (RMW). However, the hazardous waste component of an RMW is subject to RCRA LDR regulations. DOE facilities that manage hazardous wastes (including radioactive mixed wastes) may have to alter their waste-management practices to comply with the regulations. The purpose of this document is to aid DOE facilities and operations offices in determining (1) whether a variance from the treatment standard should be sought and (2) which type (treatability or equivalency) of petition is appropriate. The document also guides the user in preparing the petition. It shall be noted that the primary responsibility for the development of the treatability petition lies with the generator of the waste. 2 figs., 1 tab

  20. RCRA and CERCLA requirements affecting cleanup activities at a federal facility superfund site

    International Nuclear Information System (INIS)

    Walsh, T.J.

    1994-01-01

    The Fernald Environmental Management Project (FEMP) achieved success on an integrated groundwater monitoring program which addressed both RCRA and CERCLA requirements. The integrated plan resulted in a cost savings of approximately $2.6 million. At present, the FEMP is also working on an integrated closure process to address Hazardous Waste Management Units (HWMUs) at the site. To date, Ohio EPA seems willing to discuss an integrated program with some stipulations. If an integrated program is implemented, a cost savings of several million dollars will be realized since the CERCLA documents can be used in place of a RCRA closure plan. The success of an integrated program at the FEMP is impossible without the support of DOE and the regulators. Since DOE is an owner/operator of the facility and Ohio EPA regulates hazardous waste management activities at the FEMP, both parties must be satisfied with the proposed integration activities. Similarly, US EPA retains CERCLA authority over the site along with a signed consent agreement with DOE, which dictates the schedule of the CERCLA activities. Another federal facility used RCRA closure plans to satisfy CERCLA activities. This federal facility was in a different US EPA Region than the FEMP. While this approach was successful for this site, an integrated approach was required at the FEMP because of the signed Consent Agreement and Consent Decree. For federal facilities which have a large number of HWMUs along with OUs, an integrated approach may result in a timely and cost-effective cleanup

  1. Glossary of CERCLA, RCRA and TSCA related terms and acronyms. Environmental Guidance

    Energy Technology Data Exchange (ETDEWEB)

    1993-10-01

    This glossary contains CERCLA, RCRA and TSCA related terms that are most often encountered in the US Department of Energy (DOE) Environmental Restoration and Emergency Preparedness activities. Detailed definitions are included for key terms. The CERCLA definitions included in this glossary are taken from the Comprehensive Environmental Response, Compensation and Liability Act (CERCLA), as amended and related federal rulemakings. The RCRA definitions included in this glossary are taken from the Resource Conservation and Recovery Act (RCRA) and related federal rulemakings. The TSCA definitions included in this glossary are taken from the Toxic Substances and Control Act (TSCA) and related federal rulemakings. Definitions related to TSCA are limited to those sections in the statute and regulations concerning PCBs and asbestos.Other sources for definitions include additional federal rulemakings, assorted guidance documents prepared by the US Environmental Protection Agency (EPA), guidance and informational documents prepared by the US Department of Energy (DOE), and DOE Orders. The source of each term is noted beside the term. Terms presented in this document reflect revised and new definitions published before July 1, 1993.

  2. Results of RCRA groundwater quality assessment at the 216-B-3 Pond Facility

    International Nuclear Information System (INIS)

    Barnett, D.B.; Teel, S.S.

    1997-06-01

    This document describes a groundwater quality assessment of the 216-B-3 pond system, a Resources Conservation and Recovery act of 1976 (RCRA) waste facility. In 1990, sampling and chemical analysis of groundwater underlying the facility indicated that the contamination indicator parameters, total organic halogens (TOX), and total organic carbon (TOC) had exceeded established limits in two wells. This discovery placed the facility into RCRA groundwater assessment status and subsequently led to a more detailed hydrochemical analysis of groundwater underlying the facility. Comprehensive chemical analyses of groundwater samples from 1994 through 1996 revealed one compound, tris (2-chloroethyl) phosphate (TRIS2CH), that may have contributed to elevated TOX concentrations. No compound was identified as a contributor to TOC. Detailed evaluations of TOX, TOC, and TRIS2CH and comparison of occurrences of these parameters led to conclusions that (1) with few exceptions, these constituents occur at low concentrations below or near limits of quantitation; (2) it is problematic whether the low concentrations of TRIS2CH represent a contaminant originating from the facility or if it is a product of well construction; and (3) given the low and diminishing concentration of TOX, TOC, and TRIS2CH, no further investigation into the occurrent of these constituents is justified. Continued groundwater monitoring should include an immediate recalculation of background critical means of upgradient/downgradient comparisons and a return to seminannual groundwater monitoring under a RCRA indicator parameter evaluation program

  3. ROBOTIC TANK INSPECTION END EFFECTOR

    International Nuclear Information System (INIS)

    Rachel Landry

    1999-01-01

    The objective of this contract between Oceaneering Space Systems (OSS) and the Department of Energy (DOE) was to provide a tool for the DOE to inspect the inside tank walls of underground radioactive waste storage tanks in their tank farms. Some of these tanks are suspected to have leaks, but the harsh nature of the environment within the tanks precludes human inspection of tank walls. As a result of these conditions only a few inspection methods can fulfill this task. Of the methods available, OSS chose to pursue Alternating Current Field Measurement (ACFM), because it does not require clean surfaces for inspection, nor any contact with the Surface being inspected, and introduces no extra by-products in the inspection process (no coupling fluids or residues are left behind). The tool produced by OSS is the Robotic Tank Inspection End Effector (RTIEE), which is initially deployed on the tip of the Light Duty Utility Arm (LDUA). The RTEE combines ACFM with a color video camera for both electromagnetic and visual inspection The complete package consists of an end effector, its corresponding electronics and software, and a user's manual to guide the operator through an inspection. The system has both coarse and fine inspection modes and allows the user to catalog defects and suspected areas of leakage in a database for further examination, which may lead to emptying the tank for repair, decommissioning, etc.. The following is an updated report to OSS document OSS-21100-7002, which was submitted in 1995. During the course of the contract, two related sub-tasks arose, the Wall and Coating Thickness Sensor and the Vacuum Scarifying and Sampling Tool Assembly. The first of these sub-tasks was intended to evaluate the corrosion and wall thinning of 55-gallon steel drums. The second was retrieved and characterized the waste material trapped inside the annulus region of the underground tanks on the DOE's tank farms. While these sub-tasks were derived from the original intent

  4. Area 6 Decontamination Pond Corrective Action Unit 92 Post-Closure Inspection Annual Report for the Period January 2000-December 2000

    International Nuclear Information System (INIS)

    Traynor, J. L.

    2001-01-01

    The Area 6 Decontamination Pond, Corrective Action Unit 92, was closed in accordance with the Resource Conservation and Recovery Act (RCRA) Part B Operational Permit (Nevada Division of Environmental Protection [NDEP, 1995]) and the Federal Facility Agreement and Consent Order (NDEP, 1996) on May 11, 1999. Historically the Decontamination Pond was used for the disposal of partially treated liquid effluent discharged from the Decontamination Facility (Building 6-05) and the Industrial Laundry (Building 6-07) (U.S. Department of Energy, Nevada Operations Office [DOE/NV], 1996). The Decontamination Pond was constructed and became operational in 1979. Releases of RCRA-regulated hazardous waste or hazardous waste constituents have not been discharged to the Decontamination Pond since 1988 (DOE/NV, 1996). The pipe connecting the Decontamination Pond and Decontamination Facility and Industrial Laundry were cut and sealed at the Decontamination Pad Oil/Water Separator in 1992. The Decontamination Pond was closed in place by installing a RCRA cover. Fencing was installed around the periphery to prevent accidental damage to the cover. Post-closure monitoring at the site consists of quarterly inspections of the RCRA cover and fencing, and a subsidence survey. Additional inspections are conducted if: Precipitation occurs in excess of 1.28 centimeters (cm) (0.50 inches [in]) in a 24-hour period, or An earthquake occurs with a magnitude exceeding 4.5 on the Richter scale within 100 kilometers (km) (62 miles [mi]) of the closure

  5. Area 6 Decontamination Pond Corrective Action Unit 92 Post-Closure Inspection Annual Report for the Period January 2000-December 2000

    Energy Technology Data Exchange (ETDEWEB)

    J. L. Traynor

    2001-03-01

    The Area 6 Decontamination Pond, Corrective Action Unit 92, was closed in accordance with the Resource Conservation and Recovery Act (RCRA) Part B Operational Permit (Nevada Division of Environmental Protection [NDEP, 1995]) and the Federal Facility Agreement and Consent Order (NDEP, 1996) on May 11, 1999. Historically the Decontamination Pond was used for the disposal of partially treated liquid effluent discharged from the Decontamination Facility (Building 6-05) and the Industrial Laundry (Building 6-07) (U.S. Department of Energy, Nevada Operations Office [DOE/NV], 1996). The Decontamination Pond was constructed and became operational in 1979. Releases of RCRA-regulated hazardous waste or hazardous waste constituents have not been discharged to the Decontamination Pond since 1988 (DOE/NV, 1996). The pipe connecting the Decontamination Pond and Decontamination Facility and Industrial Laundry were cut and sealed at the Decontamination Pad Oil/Water Separator in 1992. The Decontamination Pond was closed in place by installing a RCRA cover. Fencing was installed around the periphery to prevent accidental damage to the cover. Post-closure monitoring at the site consists of quarterly inspections of the RCRA cover and fencing, and a subsidence survey. Additional inspections are conducted if: Precipitation occurs in excess of 1.28 centimeters (cm) (0.50 inches [in]) in a 24-hour period, or An earthquake occurs with a magnitude exceeding 4.5 on the Richter scale within 100 kilometers (km) (62 miles [mi]) of the closure.

  6. Pressure vessel design manual

    CERN Document Server

    Moss, Dennis R

    2013-01-01

    Pressure vessels are closed containers designed to hold gases or liquids at a pressure substantially different from the ambient pressure. They have a variety of applications in industry, including in oil refineries, nuclear reactors, vehicle airbrake reservoirs, and more. The pressure differential with such vessels is dangerous, and due to the risk of accident and fatality around their use, the design, manufacture, operation and inspection of pressure vessels is regulated by engineering authorities and guided by legal codes and standards. Pressure Vessel Design Manual is a solutions-focused guide to the many problems and technical challenges involved in the design of pressure vessels to match stringent standards and codes. It brings together otherwise scattered information and explanations into one easy-to-use resource to minimize research and take readers from problem to solution in the most direct manner possible. * Covers almost all problems that a working pressure vessel designer can expect to face, with ...

  7. Metrication manual

    International Nuclear Information System (INIS)

    Harper, A.F.A.; Digby, R.B.; Thong, S.P.; Lacey, F.

    1978-04-01

    In April 1978 a meeting of senior metrication officers convened by the Commonwealth Science Council of the Commonwealth Secretariat, was held in London. The participants were drawn from Australia, Bangladesh, Britain, Canada, Ghana, Guyana, India, Jamaica, Papua New Guinea, Solomon Islands and Trinidad and Tobago. Among other things, the meeting resolved to develop a set of guidelines to assist countries to change to SI and to compile such guidelines in the form of a working manual

  8. Selective removal/recovery of RCRA metals from waste and process solutions using polymer filtration{trademark} technology

    Energy Technology Data Exchange (ETDEWEB)

    Smith, B.F. [Los Alamos National Lab., NM (United States)

    1997-10-01

    Resource Conservation and Recovery Act (RCRA) metals are found in a number of process and waste streams at many DOE, U.S. Department of Defense, and industrial facilities. RCRA metals consist principally of chromium, mercury, cadmium, lead, and silver. Arsenic and selenium, which form oxyanions, are also considered RCRA elements. Discharge limits for each of these metals are based on toxicity and dictated by state and federal regulations (e.g., drinking water, RCRA, etc.). RCRA metals are used in many current operations, are generated in decontamination and decommissioning (D&D) operations, and are also present in old process wastes that require treatment and stabilization. These metals can exist in solutions, as part of sludges, or as contaminants on soils or solid surfaces, as individual metals or as mixtures with other metals, mixtures with radioactive metals such as actinides (defined as mixed waste), or as mixtures with a variety of inert metals such as calcium and sodium. The authors have successfully completed a preliminary proof-of-principle evaluation of Polymer Filtration{trademark} (PF) technology for the dissolution of metallic mercury and have also shown that they can remove and concentrate RCRA metals from dilute solutions for a variety of aqueous solution types using PF technology. Another application successfully demonstrated is the dilute metal removal of americium and plutonium from process streams. This application was used to remove the total alpha contamination to below 30 pCi/L for the wastewater treatment plant at TA-50 at Los Alamos National Laboratory (LANL) and from nitric acid distillate in the acid recovery process at TA-55, the Plutonium Facility at LANL (ESP-CP TTP AL16C322). This project will develop and optimize the PF technology for specific DOE process streams containing RCRA metals and coordinate it with the needs of the commercial sector to ensure that technology transfer occurs.

  9. Selective removal/recovery of RCRA metals from waste and process solutions using polymer filtration trademark technology

    International Nuclear Information System (INIS)

    Smith, B.F.

    1997-01-01

    Resource Conservation and Recovery Act (RCRA) metals are found in a number of process and waste streams at many DOE, U.S. Department of Defense, and industrial facilities. RCRA metals consist principally of chromium, mercury, cadmium, lead, and silver. Arsenic and selenium, which form oxyanions, are also considered RCRA elements. Discharge limits for each of these metals are based on toxicity and dictated by state and federal regulations (e.g., drinking water, RCRA, etc.). RCRA metals are used in many current operations, are generated in decontamination and decommissioning (D ampersand D) operations, and are also present in old process wastes that require treatment and stabilization. These metals can exist in solutions, as part of sludges, or as contaminants on soils or solid surfaces, as individual metals or as mixtures with other metals, mixtures with radioactive metals such as actinides (defined as mixed waste), or as mixtures with a variety of inert metals such as calcium and sodium. The authors have successfully completed a preliminary proof-of-principle evaluation of Polymer Filtration trademark (PF) technology for the dissolution of metallic mercury and have also shown that they can remove and concentrate RCRA metals from dilute solutions for a variety of aqueous solution types using PF technology. Another application successfully demonstrated is the dilute metal removal of americium and plutonium from process streams. This application was used to remove the total alpha contamination to below 30 pCi/L for the wastewater treatment plant at TA-50 at Los Alamos National Laboratory (LANL) and from nitric acid distillate in the acid recovery process at TA-55, the Plutonium Facility at LANL (ESP-CP TTP AL16C322). This project will develop and optimize the PF technology for specific DOE process streams containing RCRA metals and coordinate it with the needs of the commercial sector to ensure that technology transfer occurs

  10. INSPECT: a package of computer programs for planning and evaluating safeguards inspections

    International Nuclear Information System (INIS)

    Mullen, M.F.

    1980-01-01

    As part of the US Program of Technical Assistance to IAEA Safeguards, PNL has developed a package of computer programs, called INSPECT, that can be used in planning and evaluating safeguards inspections of various types of nuclear facilities. The programs are based on the statistical methods described in Part F of the IAEA Safeguards Technical Manual and can be used to calculate the variance components of the MUF (Material Unaccounted For) statistic, the variance components of the D (difference) statistic, attribute and variables sampling plans, and a measure of the effectiveness of the inspection plan. The paper describes the programs, reviews a number of applications, and indicates areas for future work

  11. Methane measurements manual; Handbok metanmaetningar

    Energy Technology Data Exchange (ETDEWEB)

    Holmgren, Magnus Andreas (SP Technical research institute of Sweden, Boraas (Sweden))

    2011-02-15

    Emissions to air in different parts of the system may arise in biogas plants, where there is biological treatment of organic matter by anaerobic degradation, and during upgrading of biogas to vehicle fuel. There are mainly four reasons why these emissions must be minimized. These are safety, greenhouse gas emissions, economy and smell. This manual gathers experience of several years of work with measurement of methane emissions from biogas and upgrading facilities. This work has been done mainly in the context of Swedish Waste Management's system of voluntary commitment. The purpose of this manual is to standardize methods and procedures when methane measurements are carried out so that the results are comparable between different providers. The main target group of the manual is measurement consultants performing such measurements. Calculation template in Excel is part of the manual, which further contributes to the measurements evaluated in a standardized way. The manual contains several examples which have been calculated in the accompanying Excel template. The handbook also contains a chapter mainly intended for facility staff, in which implementation of accurate leak detection is described, and where there are hints of a system of so-called intermediate inspections to detect leaks in time

  12. The WIPP RCRA Part B permit application for TRU mixed waste disposal

    International Nuclear Information System (INIS)

    Johnson, J.E.

    1995-01-01

    In August 1993, the New Mexico Environment Department (NMED) issued a draft permit for the Waste Isolation Pilot Plant (WIPP) to begin experiments with transuranic (TRU) mixed waste. Subsequently, the Department of Energy (DOE) decided to cancel the on-site test program, opting instead for laboratory testing. The Secretary of the NMED withdrew the draft permit in 1994, ordering the State's Hazardous and Radioactive Waste Bureau to work with the DOE on submittal of a revised permit application. Revision 5 of the WIPP's Resource Conservation and Recovery Act (RCRA) Part B Permit Application was submitted to the NMED in May 1995, focusing on disposal of 175,600 m 3 of TRU mixed waste over a 25 year span plus ten years for closure. A key portion of the application, the Waste Analysis Plan, shifted from requirements to characterize a relatively small volume of TRU mixed waste for on-site experiments, to describing a complete program that would apply to all DOE TRU waste generating facilities and meet the appropriate RCRA regulations. Waste characterization will be conducted on a waste stream basis, fitting into three broad categories: (1) homogeneous solids, (2) soil/gravel, and (3) debris wastes. Techniques used include radiography, visually examining waste from opened containers, radioassay, headspace gas sampling, physical sampling and analysis of homogeneous wastes, and review of documented acceptable knowledge. Acceptable knowledge of the original organics and metals used, and the operations that generated these waste streams is sufficient in most cases to determine if the waste has toxicity characteristics, hazardous constituents, polychlorinated biphenyls (PBCs), or RCRA regulated metals

  13. Rocky Flats Solar Evaporation Ponds RCRA hybrid-closure case study

    International Nuclear Information System (INIS)

    Ogg, R.T.; Everett, L.G.; Cullen, S.J.

    1994-01-01

    The Solar Evaporation Ponds (SEP)/Operable Unit 4 (OU 4), located at the Rocky Flats Plant (RFP) sixteen miles northwest of Denver, Colorado, is currently undergoing remediation/Resource Conservation and Recovery Act (RCRA) closure in accordance with the Rocky Flats Interagency Agreement (IAG) signed by the US Department of Energy (DOE), US Environmental Protection Agency (EPA) and Colorado Department of Health (CDH) on January 22, 1991. Based on the ''Phase 1'' (source and soils) RCRA Facility Investigation/Remedial Investigation (RFM data and interpretations), the DOE and EG and G Rocky Flats, Inc. (EG and G) have selected a permanent surface engineered/isolation barrier as the technological option for remediation of the SEP. The DOE and EG and G will utilize all natural materials to create an ''impermeable'' barrier/structure to isolate the waste being left in place from impacting human health and the environment for a minimum of 1,000 years. Their rationale for utilizing natural materials is two fold; (1) optimize long term performance of the barrier and; (2) design a structure which will be near maintenance free (passive remediation) for 1,000 years. The DOE and EG and G have taken a proactive approach in providing post closure performance assessment for this RCRA closure action. An integrated monitoring system has been designed which will include monitoring the engineered barrier, vadose zone and ground water systems. Rocky Flats will integrate instrumentation into the permanent engineered barrier which will provide early warning of potential liquid migration through the barrier and into the waste zone

  14. Self-assembled monolayers on mosoporous supports (SAMMS) for RCRA metal removal

    Energy Technology Data Exchange (ETDEWEB)

    Feng, Xiangdong; Liu, Jun; Fryxell, G. [Pacific Northwest National Lab., Richland, WA (United States)

    1997-10-01

    The Mixed Waste Focus Area has declared mercury removal and stabilization as the first and fourth priorities among 30 prioritized deficiencies. Resource Conservation and Recovery Act (RCRA) metal and mercury removal has also been identified as a high priority at DOE sites such as Albuquerque, Idaho Falls, Oak Ridge, Hanford, Rocky Flats, and Savannah River. Under this task, a proprietary new technology, Self-Assembled Monolayers on Mesoporous Supports (SAMMS), for RCRA metal ion removal from aqueous wastewater and mercury removal from organic wastes such as vacuum pump oils is being developed at Pacific Northwest National Laboratory (PNNL). The six key features of the SAMMS technology are (1) large surface area (>900 m{sup 2}/g) of the mesoporous oxides (SiO{sub 2}, ZrO{sub 2}, TiO{sub 2}) ensures high capacity for metal loading (more than 1 g Hg/g SAMMS); (2) molecular recognition of the interfacial functional groups ensures the high affinity and selectivity for heavy metals without interference from other abundant cations (such as calcium and iron) in wastewater; (3) suitability for removal of mercury from both aqueous wastes and organic wastes; (4) the Hg-laden SAMMS not only pass TCLP tests, but also have good long-term durability as a waste form because the covalent binding between mercury and SAMMS has good resistance to ion exchange, oxidation, and hydrolysis; (5) the uniform and small pore size (2 to 40 nm) of the mesoporous silica prevents bacteria (>2000 nm) from solubilizing the bound mercury; and (6) SAMMS can also be used for RCRA metal removal from gaseous mercury waste, sludge, sediment, and soil.

  15. Line-scan inspection of conifer seedlings

    Science.gov (United States)

    Rigney, Michael P.; Kranzler, Glenn A.

    1993-05-01

    Almost two billion conifer seedlings are produced in the U.S. each year to support reforestation efforts. Seedlings are graded manually to improve viability after transplanting. Manual grading is labor-intensive and subject to human variability. Our previous research demonstrated the feasibility of automated tree seedling inspection with machine vision. Here we describe a system based on line-scan imaging, providing a three-fold increase in resolution and inspection rate. A key aspect of the system is automatic recognition of the seedling root collar. Root collar diameter, shoot height, and projected shoot and root areas are measured. Sturdiness ratio and shoot/root ratio are computed. Grade is determined by comparing measured features with pre-defined set points. Seedlings are automatically sorted. The precision of machine vision and manual measurements was determined in tests at a commercial forest nursery. Manual measurements of stem diameter, shoot height, and sturdiness ratio had standard deviations three times those of machine vision measurements. Projected shoot area was highly correlated (r2 equals 0.90) with shoot volume. Projected root area had good correlation (r2 equals 0.80) with root volume. Seedlings were inspected at rates as high as ten per second.

  16. RCRA facility investigation report for the 200-PO-1 operable unit. Revision 1

    International Nuclear Information System (INIS)

    1997-05-01

    This Resource Conservation and Recovery Act (RCRA) Facility Investigation (RFI) report is prepared in support of the RFI/corrective measures study process for the 200-PO-1 Groundwater Operable Unit in the 200 East Area of the Hanford Site. This report summarizes existing information on this operable unit presented in the 200 East and PUREX Aggregate Area Management Study Reports, contaminant specific studies, available modeling data, and groundwater monitoring data summary reports. Existing contaminant data are screened against current regulatory limits to determine contaminants of potential concern (COPC). Each identified COPC is evaluated using well-specific and plume trend analyses

  17. POST-CLOSURE INSPECTION REPORT FOR CORRECTIVE ACTION UNIT 92: AREA 6 DECON POND FACILITY, NEVADA TEST SITE, NEVADA FOR CALENDAR YEAR 2005

    International Nuclear Information System (INIS)

    2006-01-01

    This Post-Closure Inspection Report provides an analysis and summary of inspections for Corrective Action Unit (CAU) 92, Area 6 Decon Pond Facility, Nevada Test Site, Nevada. CAU 92 was closed in accordance with the Resource Conservation and Recovery Act (RCRA) Part B Operational Permit (Nevada Division of Environmental Protection (NDEP), 1995) and the Federal Facility Agreement and Consent Order of 1996. Closure activities were completed on February 16, 1999, and the Closure Report (U.S. Department of Energy, Nevada Operations Office, 1999) was approved and a Notice of Completion issued by the NDEP on May 11, 1999. CAU 92 consists of two Corrective Action Sites (CASs): CAS 06-04-01, Decon Pad Oil/Water Separator; and CAS 06-05-02, Decontamination Pond (RCRA). Both CASs have use restrictions; however, only CAS 06-05-02 requires post-closure inspections. Visual inspections of the cover and fencing at CAS 06-05-02 are performed quarterly. Additional inspections are conducted if precipitation occurs in excess of 1.28 centimeters (cm) (0.50 inches [in]) in a 24-hour period. This report covers calendar year 2005. Quarterly site inspections were performed in March, June, September, and December of 2005. All observations indicated the continued integrity of the unit. No issues or concerns were noted, and no corrective actions were necessary. Copies of the inspection checklists and field notes completed during each inspection are included in Appendix A. Five additional inspections were performed after precipitation events that exceeded 1.28 cm (0.50 in) within a 24-hour period during 2005. No significant changes in site conditions were noted during these inspections, and no corrective actions were necessary. Copies of the inspection checklists and field notes completed during each inspection are included in Appendix A. Precipitation records for 2005 are included in Appendix C

  18. CERCLA and RCRA requirements affecting cleanup of a hazardous waste management unit at a Superfund site: A case study

    International Nuclear Information System (INIS)

    Walsh, T.J.

    1995-03-01

    The Fernald Environmental Management Project (FEMP) attempted to address both RCRA and CERCLA requirements at the fire training facility (FTF) by integrating a CERCLA removal action work plan with a RCRA closure plan. While the regulatory agencies involved with the FTF cleanup agreed the integrated document was a good idea, implementation proved complicated, owing to disposition of clean debris from a Superfund site, treatment of contaminated media, duration of cleanup activities, and cleanup certification. While all the complications have not been resolved, solutions to all have been proposed to Ohio EPA and U.S. EPA. Both agencies have worked closely with FEMP to find the most effective fulfillment of RCRA and CERCLA requirements

  19. A development of an automated ultrasonic TOFD inspection system using an welding line tracing robot

    International Nuclear Information System (INIS)

    Cho, Hyun; Song, Sung Jin; Lee, Kang Won; Kim, Young Jin; Woo, Jong Sik

    2006-01-01

    Large scaled ships, manufactured inside of the country, should be passed welding inspection and painting film inspection. Normally, these kind of inspections are conducted by human inspectors manually, although it cause industrial disasters such as falling accidents and diving accidents frequently. In addition, Ship makers are not to give a full trust to shipowners because manual inspections cannot be conducted all over the welding parts. So, in this study we developed an automated ultrasonic TOFD inspection system using an welding line tracing robot. This system, controlled by an inspector at a remote field, can inspect welding parts of ship outer panel both under water and in air. In this paper we present the developed robot and ultrasonic TOFD inspection system and the inspection result.

  20. A development of an automated ultrasonic TOFD inspection system using an welding line tracing robot

    International Nuclear Information System (INIS)

    Cho, Hyun; Song, Sung Jin; Lee, Kang Won; Kim, Young Jin; Woo, Jong Sik

    2006-01-01

    Large scaled ships, manufactured inside of the country, should be passed welding inspection and painting film inspection. Normally, these kind of inspections are conducted by human inspectors manually, although it cause industrial disasters such as falling accidents and diving accidents frequently. In addition, Ship makers are not to give a full trust to ship owners because manual inspections cannot be conducted all over the welding parts. So, in this study we developed an automated ultrasonic TOFD inspection system using an welding line tracing robot. This system, controlled by an inspector at a remote field, can inspect welding parts of ship outer panel both under water and in air. In this paper we present the developed robot and ultrasonic TOFD inspection system and the inspection result.

  1. Additive Manufacturing Infrared Inspection

    Science.gov (United States)

    Gaddy, Darrell; Nettles, Mindy

    2015-01-01

    The Additive Manufacturing Infrared Inspection Task started the development of a real-time dimensional inspection technique and digital quality record for the additive manufacturing process using infrared camera imaging and processing techniques. This project will benefit additive manufacturing by providing real-time inspection of internal geometry that is not currently possible and reduce the time and cost of additive manufactured parts with automated real-time dimensional inspections which deletes post-production inspections.

  2. Pdap Manual

    DEFF Research Database (Denmark)

    Pedersen, Mads Mølgaard; Larsen, Torben J.

    Pdap, Python Data Analysis Program, is a program for post processing, analysis, visualization and presentation of data e.g. simulation results and measurements. It is intended but not limited to the domain of wind turbines. It combines an intuitive graphical user interface with python scripting...... that allows automation and implementation of custom functions. This manual gives a short introduction to the graphical user interface, describes the mathematical background for some of the functions, describes the scripting API and finally a few examples on how automate analysis via scripting is presented....... The newest version, and more documentation and help on how to used, extend and automate Pdap can be found at the webpage www.hawc2.dk...

  3. Longitudinal wave ultrasonic inspection of austenitic weldments

    International Nuclear Information System (INIS)

    Gray, B.S.; Hudgell, R.J.; Seed, H.

    1980-01-01

    Successful volumetric inspection of LMFBR primary circuits, and also much of the secondary circuit, is dependent on the availability of satisfactory examination procedures for austenitic welds. Application of conventional ultrasonic techniques is hampered by the anisotropic, textured structure of the weld metal and this paper describes development work on the use of longitudinal wave techniques. In addition to confirming the dominant effects of the weld structure on ultrasound propagation some results are given of studies utilising deliberately induced defects in Manual Metal Arc Welds in 50 mm plate together with preliminary work on the inspection of narrow austenitic welds fabricated by automatic processes. (author)

  4. Transportable Vitrification System RCRA Closure Practical Waste Disposition Saves Time And Money

    International Nuclear Information System (INIS)

    Brill, Angie; Boles, Roger; Byars, Woody

    2003-01-01

    The Transportable Vitrification System (TVS) was a large-scale vitrification system for the treatment of mixed wastes. The wastes contained both hazardous and radioactive materials in the form of sludge, soil, and ash. The TVS was developed to be moved to various United States Department of Energy (DOE) facilities to vitrify mixed waste as needed. The TVS consists of four primary modules: (1) Waste and Additive Materials Processing Module; (2) Melter Module; (3) Emissions Control Module; and (4) Control and Services Module. The TVS was demonstrated at the East Tennessee Technology Park (ETTP) during September and October of 1997. During this period, approximately 16,000 pounds of actual mixed waste was processed, producing over 17,000 pounds of glass. After the demonstration was complete it was determined that it was more expensive to use the TVS unit to treat and dispose of mixed waste than to direct bury this waste in Utah permitted facility. Thus, DOE had to perform a Resource Conservation and Recovery Act (RCRA) closure of the facility and find a reuse for as much of the equipment as possible. This paper will focus on the following items associated with this successful RCRA closure project: TVS site closure design and implementation; characterization activities focused on waste disposition; pollution prevention through reuse; waste minimization efforts to reduce mixed waste to be disposed; and lessons learned that would be integrated in future projects of this magnitude

  5. RCRA Assessment Plan for Single-Shell Tank Waste Management Area TX-TY

    Energy Technology Data Exchange (ETDEWEB)

    Horton, Duane G.

    2007-03-26

    WMA TX-TY contains underground, single-shell tanks that were used to store liquid waste that contained chemicals and radionuclides. Most of the liquid has been removed, and the remaining waste is regulated under the RCRA as modi¬fied in 40 CFR Part 265, Subpart F and Washington State’s Hazardous Waste Management Act . WMA TX-TY was placed in assessment monitoring in 1993 because of elevated specific conductance. A groundwater quality assessment plan was written in 1993 describing the monitoring activities to be used in deciding whether WMA TX-TY had affected groundwater. That plan was updated in 2001 for continued RCRA groundwater quality assessment as required by 40 CFR 265.93 (d)(7). This document further updates the assessment plan for WMA TX-TY by including (1) information obtained from ten new wells installed at the WMA after 1999 and (2) information from routine quarterly groundwater monitoring during the last five years. Also, this plan describes activities for continuing the groundwater assessment at WMA TX TY.

  6. Quarterly report of RCRA groundwater monitoring data for period April 1 through June 30, 1994

    International Nuclear Information System (INIS)

    1994-10-01

    Hanford Site interim-status groundwater monitoring projects are conducted as either background, indicator parameter evaluation, or groundwater quality assessment monitoring programs as defined in the Resource Conservation and Recovery Act of 1976 (RCRA); and ''Interim Status Standards for Owners and Operators of Hazardous Waste Treatment, Storage, and Disposal Facilities,'' as amended (40 Code of Federal Regulations [CFR] 265). Compliance with the 40 CFR 265 regulations is required by the Washington Administrative Code (WAC) 173-303. This report contains data from Hanford Site groundwater monitoring projects. Westinghouse Hanford Company manages RCRA groundwater monitoring projects for federal facilities on the Hanford Site. Project management, specifying data needs, performing quality control oversight, managing data, and preparing project sampling schedules are all parts of this responsibility. This quarterly report contains data received between May 20 and August 19, 1994, which are the cutoff dates for this reporting period. This report may contain not only data from the April through June quarter but also data from earlier sampling events that were not previously reported

  7. RCRA permit modifications and the functional equivalency demonstration: A case study

    International Nuclear Information System (INIS)

    Kinker, J.; Lyon, W.; Carnes, R.; Loehr, C.; Elsberry, K.; Garcia, P.

    1996-01-01

    Hazardous waste operating permits issued under the Resource Conservation and Recovery Act (RCRA) often impose requirements, typically by reference to the original permit application, that specific components and equipment be used. Consequently, changing these items, even for the purpose of routine maintenance, may first require that the owner/operator request a potentially time-consuming and costly permit modification. However, the owner/operator may demonstrate that a modification is not required because the planned changes are functionally equivalent, as defined by RCRA, to the original specifications embodied by the permit. The Controlled-Air Incinerator at Los Alamos National Laboratory is scheduled for maintenance and improvements that involve replacement of components. The incinerator's carbon adsorption unit/high efficiency particulate air filtration system, in particular, was redesigned to improve reliability and minimize maintenance. A study was performed to determine whether the redesigned unit would qualify as functionally equivalent to the original component. in performing this study, the following steps were taken: (a) the key performance factors were identified; (b) performance data describing the existing unit were obtained; (c) performance of both the existing and redesigned units was simulated; and (d) the performance data were compared to ascertain whether the components could qualify as functionally equivalent

  8. HANFORD TANK FARM RESOURCE CONSERVATION and RECOVERY ACT (RCRA) CORRECTIVE ACTION PROGRAM

    International Nuclear Information System (INIS)

    KRISTOFZSKI, J.G.

    2007-01-01

    As a consequence of producing special nuclear material for the nation's defense, large amounts of extremely hazardous radioactive waste was created at the US Department of Energy's (DOE) Hanford Site in south central Washington State. A little over 50 million gallons of this waste is now stored in 177 large, underground tanks on Hanford's Central Plateau in tank farms regulated under the Atomic Energy Act and the Resource, Conservation, and Recovery Act (RCRA). Over 60 tanks and associated infrastructure have released or are presumed to have released waste in the vadose zone. In 1998, DOE's Office of River Protection established the Hanford Tank Farm RCRA Corrective Action Program (RCAP) to: (1) characterize the distribution and extent of the existing vadose zone contamination; (2) determine how the contamination will move in the future; (3) estimate the impacts of this contamination on groundwater and other media; (4) develop and implement mitigative measures; and (5) develop corrective measures to be implemented as part of the final closure of the tank farm facilities. Since its creation, RCAP has made major advances in each of these areas, which will be discussed in this paper

  9. Caltrans : construction manual

    Science.gov (United States)

    2009-08-01

    Caltrans intends this manual as a resource for all personnel engaged in contract administration. The manual establishes policies and procedures for the construction phase of Caltrans projects. However, this manual is not a contract document. It impos...

  10. Phase 1 RCRA Facility Investigation and Corrective Measures Study Work Plan for Single Shell Tank Waste Management Areas

    International Nuclear Information System (INIS)

    ROGERS, P.M.

    2000-01-01

    This document is the master work plan for the Resource Conservation and Recovery Act of 1976 (RCRA) for single-shell tank (SST) farms at the Hanford Site. Evidence indicates that releases at four of the seven SST waste management areas have impacted

  11. Phase 1 RCRA Facility Investigation and Corrective Measures Study Work Plan for Single Shell Tank Waste Management Areas

    Energy Technology Data Exchange (ETDEWEB)

    ROGERS, P.M.

    2000-06-01

    This document is the master work plan for the Resource Conservation and Recovery Act of 1976 (RCRA) for single-shell tank (SST) farms at the Hanford Site. Evidence indicates that releases at four of the seven SST waste management areas have impacted.

  12. Automated Inspection of Aircraft

    Science.gov (United States)

    1998-04-01

    This report summarizes the development of a robotic system designed to assist aircraft inspectors by remotely deploying non-destructive inspection (NDI) sensors and acquiring, processing, and storing inspection data. Carnegie Mellon University studie...

  13. Optimising import phytosanitary inspection

    NARCIS (Netherlands)

    Surkov, I.

    2007-01-01

    Keywords: quarantine pest, plant health policy, optimization, import phytosanitary inspection, ‘reduced checks’, optimal allocation of resources, multinomial logistic regression, the Netherlands World trade is a major vector of spread of quarantine plant pests. Border phytosanitary inspection

  14. 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)

  15. 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)

  16. Technical objectives of inspection

    International Nuclear Information System (INIS)

    Sorenson, R.J.; Stewart, K.B.; Schneider, R.A.

    1976-01-01

    The various technical objectives of inspection are discussed in a very general manner. The discussion includes how the inspection function is related to the assumed threat, the various degrees of assurance and reliance on criteria, and the hierarchy of assurance which is obtained from the various types or levels of inspection

  17. 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.

  18. In-service inspection of nuclear power plants

    International Nuclear Information System (INIS)

    1991-01-01

    This Manual is intended to provide more comprehensive considerations on the management, organization, preparation, improvement and implementation of in-service inspection activities and the related surveillance. It also gives illustrative examples of good practices and recommendations from operating and other organizations that are consistent with the requirements and recommendations of the Code and Safety Guides. The Manual is directed primarily towards plant management. This Manual should be used in conjunction with the Code and the Safety Guides, in particular with IAEA Safety Series Nos. 50-C-O, 50-SG-O2, 50-SG-05, 50-SG-07, 50-SG-08 and 50-SG-D1, which contain recommendations of a general character about maintenance activities and radiation protection in an operating power plant, and with the 'Manual on the Maintenance of Systems and Components Important to Safety'. This Manual is divided into four technical sections. The first introduces the purpose, structure and main requirements of the programme. The second section describes constituents of the programme, recommending its scope, scheduling, acceptance standards and documentation of results. The following section goes into details of the inspection programme's contents, such as the selection of components, inspection locations, defect types, applicable techniques and procedures, and the evaluation of results. The last section specifies recommended methods and techniques for inspection, such as visual, ultrasonic, eddy current, magnetic particle and others. This main part of the Manual is complemented by a number of annexes which reproduce actual national examples of established procedures, ISI programme parts, acceptance standards, personnel training programmes, testing techniques and other aspects of in-service inspection, illustrating practical implementation of the recommendations of the Manual

  19. Remotely deployable aerial inspection using tactile sensors

    Science.gov (United States)

    MacLeod, C. N.; Cao, J.; Pierce, S. G.; Sullivan, J. C.; Pipe, A. G.; Dobie, G.; Summan, R.

    2014-02-01

    For structural monitoring applications, the use of remotely deployable Non-Destructive Evaluation (NDE) inspection platforms offer many advantages, including improved accessibility, greater safety and reduced cost, when compared to traditional manual inspection techniques. The use of such platforms, previously reported by researchers at the University Strathclyde facilitates the potential for rapid scanning of large areas and volumes in hazardous locations. A common problem for both manual and remote deployment approaches lies in the intrinsic stand-off and surface coupling issues of typical NDE probes. The associated complications of these requirements are obviously significantly exacerbated when considering aerial based remote inspection and deployment, resulting in simple visual techniques being the preferred sensor payload. Researchers at Bristol Robotics Laboratory have developed biomimetic tactile sensors modelled on the facial whiskers (vibrissae) of animals such as rats and mice, with the latest sensors actively sweeping their tips across the surface in a back and forth motion. The current work reports on the design and performance of an aerial inspection platform and the suitability of tactile whisking sensors to aerial based surface monitoring applications.

  20. Computer automation of ultrasonic testing. [inspection of ultrasonic welding

    Science.gov (United States)

    Yee, B. G. W.; Kerlin, E. E.; Gardner, A. H.; Dunmyer, D.; Wells, T. G.; Robinson, A. R.; Kunselman, J. S.; Walker, T. C.

    1974-01-01

    Report describes a prototype computer-automated ultrasonic system developed for the inspection of weldments. This system can be operated in three modes: manual, automatic, and computer-controlled. In the computer-controlled mode, the system will automatically acquire, process, analyze, store, and display ultrasonic inspection data in real-time. Flaw size (in cross-section), location (depth), and type (porosity-like or crack-like) can be automatically discerned and displayed. The results and pertinent parameters are recorded.

  1. Validated automated ultrasonic inspections of the Sizewell 'B' reactor pressure vessel

    International Nuclear Information System (INIS)

    Dikstra, B.J.; Farley, J.M.

    1992-01-01

    Automated ultrasonic inspection was applied extensively during manufacture of the RPV for Sizewell 'B'. This was an important element of the safety case presented at the Sizewell 'B' public enquiry. This requirement reflected concern in the United Kingdom as to the effectiveness and reliability of ultrasonic inspections. By applying automated inspections in addition to the manual ultrasonic inspection carried out by the vessel manufacturer, the overall reliability of the inspection of the vessel would be considerably enhanced. The automated inspections carried out in the manufacturer's workshops were termed 'automated shop inspections' (ASIs). The ASIs were carried out in two contracts: the first to inspect the component forgings of the RPV, the second to inspect the pressure retaining welds. (author)

  2. RCRA closure of eight land-based units at the Y-12 plant

    International Nuclear Information System (INIS)

    Stone, J.E.; Welch, S.H.

    1988-01-01

    Eight land-based hazardous waste management units at the Oak Ridge Y-12 Plant are being closed under an integrated multi-year program. Closure plans for the units have been submitted and are in various stages of revision and regulatory review. These units will be closed by various combinations of methods, including liquid removal and treatment, sludge stabilization, contaminated sludge and/or soil removal, and capping. The closure of these sites will be funded by a new Department of Energy budget category, the Environmental Restoration Budget Category (ERBC), which is intended to provide greater flexibility in the response to closure and remedial activities. A major project, Closure and Post-Closure Activities (CAPCA), has been identified for ERBC funding to close and remediate the land units in accordance with RCRA requirements. Establishing the scope of this program has required the development of risk assessments and the preparation of an integrated schedule

  3. Construction of mixed waste storage RCRA facilities, Buildings 7668 and 7669: Environmental assessment

    International Nuclear Information System (INIS)

    1994-04-01

    The Department of Energy has prepared an environmental assessment, DOE/EA-0820, to assess the potential environmental impacts of constructing and operating two mixed waste Resource Conservation and Recovery Act (RCRA) storage facilities. The new facilities would be located inside and immediately west of the security-fenced area of the Oak Ridge National Laboratory Hazardous Waste Management Area in Melton Valley, Tennessee. Based on the analyses in the environmental assessment, the Department has determined that the proposed action does not constitute a major Federal action significantly affecting the quality of the human environment within the meaning of the National Environmental Policy Act of 1969. Therefore, the preparation of an environmental impact statement is not required, and the Department is issuing this finding of no significant impact

  4. Quarterly report of RCRA groundwater monitoring data for period January 1, 1993 through March 31, 1993

    Energy Technology Data Exchange (ETDEWEB)

    1993-07-01

    Hanford Site interim-status groundwater monitoring projects are conducted as either background, indicator parameter evaluation, or groundwater quality assessment monitoring programs as defined in the Resource Conservation and Recovery Act of 1976 (RCRA); and Interim Status Standards for Owners and Operators of Hazardous Waste Treatment, Storage, and Disposal Facilities, as amended (40 Code of Federal Regulations [CFR] 265). Compliance with the 40 CFR 265 regulations is required by the Washington Administrative Code (WAC) 173-303. This report contains data from Hanford Site groundwater monitoring projects. This quarterly report contains data received between March 8 and May 24, 1993, which are the cutoff dates for this reporting period. This report may contain not only data from the January through March quarter but also data from earlier sampling events that were not previously reported.

  5. Savannah River Site RCRA Facility Investigation plan: Road A Chemical Basin

    International Nuclear Information System (INIS)

    1989-06-01

    The nature of wastes disposed of at the Road A Chemical Basin (RACB) is such that some degree of soil contamination is probable. Lead has also been detected in site monitoring wells at concentrations above SRS background levels. A RCRA Facility Investigation (RFI) is proposed for the RACB and will include a ground penetrating radar (GPR) survey, collection and chemical and radiological analyses of soil cores, installation of groundwater monitoring wells, collection and chemical and radiological analyses of groundwater samples, and collection of chemical and radiological analyses of surface water and sediment samples. Upon completion of the proposed RFI field work and chemical and radiological analyses, and RFI report should be prepared to present conclusions on the nature and extent of contamination at the site, and to make recommendations for site remediation. If contamination is detected at concentrations above SRS background levels, a receptor analysis should be done to evaluate potential impacts of site contamination on nearby populations

  6. ENVIRONMENTALLY SOUND DISPOSAL OF RADIOACTIVE MATERIALS AT A RCRA HAZARDOUS WASTE DISPOSAL FACILITY

    International Nuclear Information System (INIS)

    Romano, Stephen; Welling, Steven; Bell, Simon

    2003-01-01

    The use of hazardous waste disposal facilities permitted under the Resource Conservation and Recovery Act (''RCRA'') to dispose of low concentration and exempt radioactive materials is a cost-effective option for government and industry waste generators. The hazardous and PCB waste disposal facility operated by US Ecology Idaho, Inc. near Grand View, Idaho provides environmentally sound disposal services to both government and private industry waste generators. The Idaho facility is a major recipient of U.S. Army Corps of Engineers FUSRAP program waste and received permit approval to receive an expanded range of radioactive materials in 2001. The site has disposed of more than 300,000 tons of radioactive materials from the federal government during the past five years. This paper presents the capabilities of the Grand View, Idaho hazardous waste facility to accept radioactive materials, site-specific acceptance criteria and performance assessment, radiological safety and environmental monitoring program information

  7. The marriage of RCRA and CERCLA at the Rocky Flats Environmental Technology Site

    International Nuclear Information System (INIS)

    Shelton, D.C.; Brooks, L.M.

    1998-01-01

    A key goal of the Rocky Flats Cleanup Agreement (RFCA) signed in July of 1996 was to provide a seamless marriage of the Resource Conservation and Recovery Act (RCRA) (and other media specific programs) and the Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) and the implementing agencies of each. This paper examines the two years since the signing of RFCA and identifies the successes, failures, and stresses of the marriage. RFCA has provided an excellent vehicle for regulatory and substantive progress at the Department of Energy's Rocky Flats facility. The key for a fully successful marriage is to build on the accomplishments to date and to continually improve the internal and external systems and relationships. To date, the parties can be proud of both the substantial accomplishment of substantive environmental work and the regulatory systems that have enabled the work

  8. RCRA Facilities Assessment (RFA), Oak Ridge National Laboratory, container storage accumulation areas

    International Nuclear Information System (INIS)

    1987-01-01

    The Oak Ridge National Laboratory (ORNL) remedial action strategy is based on a memorandum from the Environmental Protection Agency (EPA) to the Department of Energy (DOE) in which EPA elected to enforce regulatory requirements for ORNL through its amended Resource Conservation and Recovery Act (RCRA) authority. This report, which completes the requirements of II.A.1 of the Hazardous and Solid Waste Amendments (HSWA) permit, identifies areas near the point of waste generation in which wastes are accumulated before they are transferred into the permitted waste storage facilities. In includes background information on each area and an assessment of the need for further remedial attention. The waste accumulation areas described in this addendum bear identification numbers indicative of the WAGs of which they are a part. Waste accumulation areas that are located inside a building and in which there is no potential for releases to the environment are not included in this report

  9. Quality assurance inspections for shipping and storage containers

    Energy Technology Data Exchange (ETDEWEB)

    Stromberg, H.M.; Roberts, G.D.; Bryce, J.H. [Lockheed Idaho Technologies Co., Idaho Falls, ID (United States)

    1996-04-01

    This is a guide for conducting quality assurance inspections of transportation packaging and dry spent fuel storage system suppliers. (Suppliers are defined as designers, fabricators, distributors, users or owners of those packaging and storage systems.) This guide may be used during inspection to determine regulatory compliance with 10 CFR, Part 71, Subpart H; 10 CFR, Part 72, Subpart G; 10 CFR, Part 21; and supplier`s quality assurance program commitments. It was developed to provide a structured, consistent approach to inspections. The guidance therein provides a framework for evaluation of transportation packaging and dry spent fuel storage systems quality assurance programs. Inspectors are provided with the flexibility to adapt the methods and concepts to meet inspection requirements for the particular facility. The method used in the guide treats each activity at a facility as a separate performance element and combines the activities within the framework of an ``inspection tree.``The method separates each performance element into several areas for inspection and identifies guidelines, based on regulatory requirements, to qualitatively evaluate each area. This guide also serves as a field manual to facilitate quality assurance inspection activities. This guide replaces an earlier one, NUREG/CR-5717 (Packing Supplier Inspection Guide). This replacement guide enhances the inspection activities for transportation packagings and adds the dry spent fuel storage system quality assurance inspection activities.

  10. Quality assurance inspections for shipping and storage containers

    International Nuclear Information System (INIS)

    Stromberg, H.M.; Roberts, G.D.; Bryce, J.H.

    1996-04-01

    This is a guide for conducting quality assurance inspections of transportation packaging and dry spent fuel storage system suppliers. (Suppliers are defined as designers, fabricators, distributors, users or owners of those packaging and storage systems.) This guide may be used during inspection to determine regulatory compliance with 10 CFR, Part 71, Subpart H; 10 CFR, Part 72, Subpart G; 10 CFR, Part 21; and supplier's quality assurance program commitments. It was developed to provide a structured, consistent approach to inspections. The guidance therein provides a framework for evaluation of transportation packaging and dry spent fuel storage systems quality assurance programs. Inspectors are provided with the flexibility to adapt the methods and concepts to meet inspection requirements for the particular facility. The method used in the guide treats each activity at a facility as a separate performance element and combines the activities within the framework of an ''inspection tree.''The method separates each performance element into several areas for inspection and identifies guidelines, based on regulatory requirements, to qualitatively evaluate each area. This guide also serves as a field manual to facilitate quality assurance inspection activities. This guide replaces an earlier one, NUREG/CR-5717 (Packing Supplier Inspection Guide). This replacement guide enhances the inspection activities for transportation packagings and adds the dry spent fuel storage system quality assurance inspection activities

  11. 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

  12. Characterization of Vadose Zone Sediment: Uncontaminated RCRA Borehole Core Samples and Composite Samples

    International Nuclear Information System (INIS)

    Serne, R. Jeffrey; Bjornstad, Bruce N.; Schaef, Herbert T.; Williams, Bruce A.; Lanigan, David C.; Horton, Duane G.; Clayton, Ray E.; Mitroshkov, Alexandre V.; Legore, Virginia L.; O'Hara, Matthew J.; Brown, Christopher F.; Parker, Kent E.; Kutnyakov, Igor V.; Serne, Jennifer N.; Last, George V.; Smith, Steven C.; Lindenmeier, Clark W.; Zachara, John M.; Burke, Deborah Sd.

    2001-01-01

    The overall goal of the of the Tank Farm Vadose Zone Project, led by CH2M HILL Hanford Group, Inc., is to define risks from past and future single-shell tank farm activities. To meet this goal, CH2M HILL Hanford Group, Inc. asked scientists from Pacific Northwest National Laboratory to perform detailed analyses on vadose zone sediment from within the S-SX Waste Management Area. This report is the first in a series of four reports to present the results of these analyses. Specifically, this report contains all the geologic, geochemical, and selected physical characterization data collected on vadose zone sediment recovered from RCRA borehole bore samples and composite samples. Intact cores from two RCRA boreholes (299-W22-48 and 299-W22-50) near the SX Tank Farm and four, large-quantity grab samples from outcrop sediment on and off the Hanford Site were sampled to better understand the fate of contaminants in the vadose zone beneath underground storage tanks at the Hanford Site. Borehole and outcrop samples analyzed for this report are located outside the tank farms, and therefore may be considered standard or background samples from which to compare contaminated sediments within the tank farms themselves. This report presents our interpretation of the physical, chemical, and mineralogical properties of the uncontaminated vadose zone sediments, and variations in the vertical distribution of these properties. The information presented in this report is intended to support preparation of the S-SX Field Investigation Report to be prepared by CH2M Hill Hanford Group, Inc. as well as future remediation actions at the S-SX Tank Farm

  13. Performance Demonstration Program Plan for RCRA Constituent Analysis of Solidified Wastes

    International Nuclear Information System (INIS)

    2006-01-01

    The Performance Demonstration Program (PDP) for Resource Conservation and Recovery Act (RCRA) constituents distributes test samples for analysis of volatile organic compounds (VOCs), semivolatile organic compounds (SVOCs), and metals in solid matrices. Each distribution of test samples is termed a PDP cycle. These evaluation cycles provide an objective measure of the reliability of measurements performed for transuranic (TRU) waste characterization. The primary documents governing the conduct of the PDP are the Quality Assurance Program Document (QAPD; DOE/CBFO-94-1012) and the Waste Isolation Pilot Plant (WIPP) Waste Analysis Plan (WAP) contained in the Hazardous Waste Facility Permit (NM4890139088-TSDF) issued by the New Mexico Environment Department. The WAP requires participation in the PDP; the PDP must comply with the QAPD and the WAP. This plan implements the general requirements of the QAPD and the applicable requirements of the WAP for the RCRA PDP. Participating laboratories demonstrate acceptable performance by successfully analyzing single-blind performance evaluation samples (subsequently referred to as PDP samples) according to the criteria established in this plan. PDP samples are used as an independent means to assess laboratory performance regarding compliance with the WAP quality assurance objectives (QAOs). The concentrations of analytes in the PDP samples address levels of regulatory concern and encompass the range of concentrations anticipated in waste characterization samples. The WIPP requires analyses of homogeneous solid wastes to demonstrate compliance with regulatory requirements. These analyses must be performed by laboratories that demonstrate acceptable performance in this PDP. These analyses are referred to as WIPP analyses, and the samples on which they are performed are referred to as WIPP samples. Participating laboratories must analyze PDP samples using the same procedures used for WIPP samples.

  14. INEL RCRA [Resource Conservation and Recovery Act] permit for incineration of hazardous waste: Status report

    International Nuclear Information System (INIS)

    McFee, J.N.; Dalton, J.D.; Bohrer, H.A.

    1987-01-01

    The Waste Experimental Reduction Facility (WERF) was constructed to reduce the volume of low-level radioactive waste at the Idaho National Engineering Laboratory (INEL). To address the problem of radioactively contaminated ignitable hazardous waste resulting from INEL activities, a development program was carried out to evaluate WERF's ability to meet the regulated criteria for incinerating liquid and solid ignitable waste. Concurrently, INEL submitted its hazardous waste Part B application under the Resource Conservation and Recovery Act (RCRA). As required, and as a major step in the permitting process, the WERF incinerator portion of the permit application included a proposed trial burn, which is a demonstration test of the incinerator's ability to destroy hazardous materials. The trial burn plan was designed to demonstrate the system performance for liquid and solid ignitable wastes at three operating conditions, using a prepared mix of materials representative of waste to be processed. EPA Region X reviewed and commented on the plan prior to the trial burn. Results of the liquid feed trial burn showed a greater than 97% probability of meeting the RCRA-dictated DRE value for chlorinated solvents and a greater than 99% probability for nonchlorinated solvents. Nonchlorinated solid waste results were calculated at a 93% probability of meeting the required DRE, with a 75% probability for chlorinated solid wastes. In addition, the incinerator DRE continued to improve long after the assumed pre-test equilibrium period had ended. The trial burn demonstrates that the WERF incinerator can safely and adequately destroy ignitable hazardous and mixed waste and provides a significant enhancement of the INEL's waste management system

  15. Field Sampling Plan for the HWMA/RCRA Closure Certification of the TRA-731 Caustic and Acid Storage Tank System - 1997 Notice of Violation Consent Order

    International Nuclear Information System (INIS)

    Evans, S.K.

    2002-01-01

    This Field Sampling Plan for the HWMA/RCRA Closure Certification of the TRA-731 Caustic and Acid Storage Tank System is one of two documents that comprise the Sampling and Analysis Plan for the HWMA/RCRA closure certification of the TRA-731 caustic and acid storage tank system at the Idaho National Engineering and Environmental Laboratory. This plan, which provides information about sampling design, required analyses, and sample collection and handling procedures, is to be used in conjunction with the Quality Assurance Project Plan for the HWMA/RCRA Closure Certification of the TRA-731 Caustic and Acid Storage Tank System

  16. 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

  17. RCRA and Operational Monitoring (ROM). Multi-Year Program Plan and Fiscal Year 95 Work Plan WBS 1.5.3

    Energy Technology Data Exchange (ETDEWEB)

    1994-09-17

    This document contains information concerning the RCRA and Operational Monitoring Program at Hanford Reservation. Information presented includes: Schedules for ground water monitoring activities, program cost baseline, program technical baseline, and a program milestone list.

  18. RCRA Facility Investigation/Remedial Investigation Report with Baseline Risk Assessment for the Fire Department Hose Training Facility (904-113G)

    Energy Technology Data Exchange (ETDEWEB)

    Palmer, E. [Westinghouse Savannah River Company, AIKEN, SC (United States)

    1997-04-01

    This report documents the Resource Conservation and Recovery Act (RCRA) Facility Investigation/Remedial Investigation/Baseline Risk Assessment (RFI/RI/BRA) for the Fire Department Hose Training Facility (FDTF) (904-113G).

  19. 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.

  20. 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...

  1. ROOFER Inventory Procedures and Inspection Manual for Metal Panel Roofing

    Science.gov (United States)

    2012-12-01

    System. DISCLAIMER: The contents of this report are not to be used for advertising , publication, or promotional purposes. Citation of trade names does...and ollow<~g wacor to penwate CPM ~~~s~ dented. delormed or kinked. tlllow<~g pondong w’"er and/or Domogt<!Pen., C>-’H ~:,~.: ~~:r~~·~:,:;••system

  2. Comparison of Deep Packet Inspection (DPI) Tools for Traffic Classification

    DEFF Research Database (Denmark)

    Bujlow, Tomasz; Carela-Español, Valentín; Barlet-Ros, Pere

    the researchers do not only have the full payloads, but also they are provided the information which application created the flow. Therefore, the dataset is useful for testing Deep Packet Inspection (DPI) tools, as well as statistical, and port-based classifiers. The dataset was created in a fully manual way...

  3. Preparation of radioactive ''mixed'' waste samples for measurement of RCRA [Resource Conservation and Recovery Act] organic compounds

    International Nuclear Information System (INIS)

    Tomkins, B.A.; Caton, J.E.

    1987-01-01

    A radioactive ''mixed'' waste typically contains alpha-, beta-, or gamma-emitting radionuclides and varying quantities of semivolatile or volatile organic species, some or all of which may be named specifically by the Resource Conservation and Recovery Act (RCRA). Because there are no acceptable means available currently for disposing of these mixed wastes, they are presently stored above-ground in sealed drums. For this reason, analytical procedures which can determine RCRA organics in radioactive waste are necessary for deciding the proper approach for disposal. An important goal of this work is the development of methods for preparing mixed waste samples in a manner which allows the RCRA organics to be measured in conventional organic analysis laboratories without special precautions. Analytical procedures developed for handling mixed waste samples must satisfy not only the usual constraints present in any trace-level organic chemical determination, but also those needed to insure the protection of the operator from radioactive contamination. Consequently, procedures should be designed to use the least amount of radioactive sample commensurate with achieving acceptable sensitivity with the RCRA analytical methods. Furthermore, the unusual laboratory glassware which would normally be used should be replaced with disposable materials wherever possible, in order to reduce the ''clean-up'' time required, and thereby reduce the operator's exposure to radioactivity. Actual sample handling should be reduced to the absolute minimum. Finally, the final isolate must exhibit a sufficiently low level of alpha, beta, or gamma activity to permit detailed characterization in a conventional organic analysis laboratory. 4 refs., 5 tabs

  4. Feasibility study of X-ray K-edge analysis of RCRA heavy metal contamination of sludge packaged in drums

    International Nuclear Information System (INIS)

    Jensen, T.

    1999-01-01

    A study has been completed to assess the capabilities of X-ray K-edge analysis in the measurement of RCRA metal contamination of sludge packaged in drums. Results were obtained for mercury and lead contamination. It was not possible to measure cadmium contamination using this technique. No false positive signals were observed. In cases where uniformity of the sludge can be assumed, this analysis can provide a quick, accurate measurement of heavy-metal contamination

  5. Borehole Data Package for Calendar Year 2000-2001 RCRA Wells at Single-Shell Tank Waste Management Area T

    International Nuclear Information System (INIS)

    Horton, Duane G; Hodges, Floyd N

    2001-01-01

    This document compiles information of the drilling and construction, well development, pump installation, and sediment and groundwater sampling applicable to the installation of five new RCRA wells in calendar year 2000 - 2001. Appendix A contains the Well Summary Sheets (as-built diagrams); the Well Construction Summary Reports, and the geologist's logs; Appendix B contains physical properties data; and Appendix C contains the borehole geophysical logs

  6. RCRA [Resource Conservation and Recovery Act] ground-water monitoring projects for Hanford facilities: Annual progress report for 1988

    International Nuclear Information System (INIS)

    Fruland, R.M.; Lundgren, R.E.

    1989-04-01

    This report describes the progress during 1988 of 14 Hanford Site ground-water monitoring projects covering 16 hazardous waste facilities and 1 nonhazardous waste facility (the Solid Waste Landfill). Each of the projects is being conducted according to federal regulations based on the Resource Conservation and Recovery Act (RCRA) of 1976 and the State of Washington Administrative Code. 21 refs., 23 figs., 8 tabs

  7. The Management Advisory Committee of the Inspection Validation Centre. 2nd report

    International Nuclear Information System (INIS)

    1985-06-01

    The document is the second report of the Management Advisory Committee of the Inspection Validation Centre (I.V.C.). The IVC is concerned with the ultrasonic inspection of the CEGB's proposed PWR reactor pressure vessel, and other components. The report deals with the technical progress since May 1984, and includes: interim validation, retrospective validation, examination of procedures, test assembly manufacture, interim validation of manual forging inspections, and validation facilities. (U.K.)

  8. A review of state regulations that exceed those of the federal Resource Conservation and Recovery Act (RCRA)

    International Nuclear Information System (INIS)

    Coutant, C.C.; Heckman, C.L.

    1988-04-01

    This report identifies and provides information on state hazardous waste management programs and regulations in states where the US Department of Energy (DOE) has facilities. The objective is to describe for the DOE defense program and its contractors how state requirements are more stringent than the federal regulations under the Resource Conservation and Recovery Act (RCRA). DOE defense programs are located in 13 of the 50 states. Most of these states have regulations that are essentially equivalent to the federal RCRA requirements as they existed prior to the 1984 amendments, but their regulations are, in most instances, more stringment than the federal requirements. Differences are both substantive and procedural, and they are summarized and tabulated herein. All but three of these 13 states have been granted Final Authorization from the US Environmental Protection Agency (EPA) to operate their own hazardous waste management program in accord with the federal RCRA program prior to the 1984 amendments; two of the three others have some stage of Interim Authorization. EPA currently administers all of the provisions of the 1984 amendments, including requirements for corrective action under Sect. 3004(u). Two states, Colorado and Tennessee, have been granted revisions to their Final Authorizations delegating responsibility for the hazardous wastes. Responsible state agencies (with appropriate telephone numbers) are indicated, as are the relevant laws and current regulatory statutes

  9. RCRA facility investigation/corrective measures study work plan for the 100-DR-1 operable unit, Hanford Site, Richland, Washington

    International Nuclear Information System (INIS)

    1992-09-01

    Four areas of the Hanford Site (the 100, 200, 300, and 1100 Areas) have been included on the US Environmental Protection Agency's (EPA's) National Priorities List (NPL) under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). Under the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement, Ecology et. al. 1990a), signed by the Washington State Department of Ecology (Ecology), EPA, and the US Department of Energy (DOE), more than 1,000 inactive waste disposal and unplanned release sites on the Hanford Site have been grouped into a number of source and groundwater operable units. These operable units contain contamination in the form of hazardous waste, radioactive/hazardous mixed waste, and other CERCLA hazardous substances. Also included in the Tri-Party Agreement are 55 Resource Conservation and Recovery Act (RCRA) treatment, storage, or disposal (TSD) facilities that will be closed or permitted to operate in accordance with RCRA regulations. Some of the TSD facilities are included in the operable units. This work plan and the attached supporting project plans establish the operable unit setting and the objectives, procedures, tasks, and schedule for conducting the RCRA facility investigation/corrective measures study (RFI/CMS) for the 100-DR-1 source operable unit Source operable units include facilities and unplanned release sites that are potential sources of contamination

  10. Technical regulation of nondestructive inspection

    International Nuclear Information System (INIS)

    1995-01-01

    It starts with the explanation of definition of nondestructive inspection and qualifications for a inspection. It lists the technical regulations of nondestructive inspections which are radiographic testing, ultrasonic flaw detecting test, liquid penetrant test, magnetic particle inspection, eddy current test visual inspection and leakage test.

  11. A Manual of Style.

    Science.gov (United States)

    Nebraska State Dept. of Education, Lincoln.

    This "Manual of Style" is offered as a guide to assist Nebraska State employees in producing quality written communications and in presenting a consistently professional image of government documents. The manual is not designed to be all-inclusive. Sections of the manual discuss formatting documents, memorandums, letters, mailing…

  12. Health products inspection

    International Nuclear Information System (INIS)

    Stoltz, M.

    2009-01-01

    To protect public health, the Health Products Inspection is a public service mission where the application of regulations concerning activities on human health products and cosmetic products is verified. This mission permits a global approach to assess the health products risk-based benefit and, in monitoring by laboratory testing and by on site inspections, to verify their compliance with appropriate regulations. The seventy five inspectors perform about eight hundred inspections per year, in France and abroad. These inspections are related to data provided in the health products assessment and also to manufacturing and delivery practices. The French inspection body is also involved in the training of foreign inspectors and in the harmonization of national, European and international practices either for operators than for the competent authorities. (author)

  13. Characterization of sediment in a leaching trench RCRA (Resource Conservation and Recovery Act) site

    International Nuclear Information System (INIS)

    Zimmerman, M.G.; Kossik, C.D.

    1988-01-01

    Hazardous materials potentially were disposed of into a pair of leaching trenches from 1975 until Resource Conservation and Recovery Act (RCRA) regulations were imposed in 1985. These leaching trenches now are used for disposal of nonhazardous process water. The typical effluent (approximately 3 million gal/d) consisted of water with trace quantities of laboratory, maintenance, and fuel fabrication process chemicals. The largest constituent in the waste stream was uranium in low concentrations. This paper describes the project used to analyze and characterize the sediments in and below the leaching trenches. Two phases of sediment sampling were performed. The first phase consisted of taking samples between the bottom of the trenches and groundwater to locate contamination in the deep sediments under the trenches. To accomplish this sampling, a series of wells were drilled, and samples were obtained for every five feet in depth. The second phase consisted of samples taken at three depths in a series of positions along each trench. Sampling was completed to determine contamination levels in the shallow sediments and loose material washed into the trenches from the process sewer system. The project results were that no measurable contamination was found in the deep sediments. Measurable contamination from metals, such as chromium and nickel, was found in the shallow sediments. The primary contaminant in the shallow sediments was uranium. The concentration of contaminants decreased rapidly to near-background levels at shallow depths below the bottoms of the trenches

  14. RCRA materials analysis by laser-induced breakdown spectroscopy: Detection limits in soils

    International Nuclear Information System (INIS)

    Koskelo, A.; Cremers, D.A.

    1994-01-01

    The goal of the Technical Task Plan (TTP) that this report supports is research, development, testing and evaluation of a portable analyzer for RCRA and other metals. The instrumentation to be built will be used for field-screening of soils. Data quality is expected to be suitable for this purpose. The data presented in this report were acquired to demonstrate the detection limits for laser-induced breakdown spectroscopy (LIBS) of soils using instrument parameters suitable for fieldable instrumentation. The data are not expected to be the best achievable with the high pulse energies available in laboratory lasers. The report presents work to date on the detection limits for several elements in soils using LIBS. The elements targeted in the Technical Task Plan are antimony, arsenic, beryllium, cadmium, chromium, lead, selenium, and zirconium. Data for these elements are presented in this report. Also included are other data of interest to potential customers for the portable LIBS apparatus. These data are for barium, mercury, cesium and strontium. Data for uranium and thorium will be acquired during the tasks geared toward mixed waste characterization

  15. Sulfur polymer cement encapsulation of RCRA toxic metals and metal oxides

    International Nuclear Information System (INIS)

    Calhoun, C.L. Jr.; Nulf, L.E.; Gorin, A.H.

    1995-06-01

    A study was conducted to determine the suitability of Sulfur Polymer Cement (SPC) encapsulation technology for the stabilization of RCRA toxic metal and metal oxide wastes. In a series of bench-scale experiments, the effects of sodium sulfide additions to the waste mixture, residence time, and temperature profile were evaluated. In addition, an effort was made to ascertain the degree to which SPC affords chemical stabilization as opposed to physical encapsulation. Experimental results have demonstrated that at the 25 wt % loading level, SPC can effectively immobilize Cr, Cr 2 O 3 , Hg, Pb, and Se to levels below regulatory limits. SPC encapsulation also has been shown to significantly reduce the leachability of other toxic compounds including PbO, PbO 2 , As 2 O 3 , BaO, and CdO. In addition, data has confirmed sulfide conversion of Hg, Pb, PbO, PbO 2 , and BaO as the product of their reaction with SPC

  16. Quarterly report of RCRA groundwater monitoring data for period October 1, 1992--December 31, 1992

    International Nuclear Information System (INIS)

    1993-04-01

    Hanford Site interim-status groundwater monitoring projects are conducted as either background, indicator parameter evaluation, or groundwater quality assessment monitoring programs as defined in the Resource Conservation and Recovery Act of 1976 (RCRA); and Interim Status Standards for Owners and Operators of Hazardous Waste Treatment, Storage, and Disposal Facilities, as amended (40 CFR 265). Compliance with the 40 CFR 265 regulations is required by the Washington Administrative Code (WAC) 173-303. Long-term laboratory contracts were approved on October 22, 1991. DataChem Laboratories of Salt Lake City, Utah, performs the hazardous chemicals analyses for the Hanford Site. Analyses for coliform bacteria are performed by Columbia/Biomedical Laboratories and for dioxin by TMS Analytical Services, Inc. International Technology Analytical Services Richland, Washington performs the radiochemical analyses. This quarterly report contains data that were received prior to March 8, 1993. This report may contain not only data from the October through December quarter but also data from earlier sampling events that were not previously reported

  17. RCRA facility investigation for the townsite of Los Alamos, New Mexico

    International Nuclear Information System (INIS)

    Dorries, A.M.; Conrad, R.C.; Nonno, L.M.

    1992-01-01

    During World War II, Los Alamos, New Mexico was established as an ideal location for the secrecy and safety needed for the research and development required to design a nuclear fission bomb. Experiments carried out in the 1940s generated both radioactive and hazardous waste constituents on what is presently part of the Los Alamos townsite. Under the RCRA permit issued to Los alamos national Laboratory in 1990, the Laboratory is scheduled for investigation of its solid waste management units (SWMUs). The existing information on levels of radioactivity on the townsite is principally data from soil samples taken during the last site decontamination in 1976, little information on the presence of hazardous constituents exists today. This paper addresses pathway analysis and a preliminary risk assessment for current residents of the Los Alamos townsite. The estimated dose levels, in mrem per year, show that the previously decontaminated SWMU areas on the Los Alamos townsite will not contribute a radiation dose of any concern to the current residents

  18. RCRA land unit closures at the Y-12 Plant, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    Welch, S.H.; Kelly, B.A.; Delozier, M.F.P.; Manrod, W.E.

    1987-01-01

    Eight land-based hazardous waste management units at the Y-12 Plant are being closed under an integrated multi-year program. Closure plans for the units have been submitted and are in various stages of revision and regulatory review. These units will be closed by various combinations of methods, including liquid removal and treatment, sludge stabilization, contaminated sludge and/or soil removal, and capping. The closure of these sites will be funded by a new Department of Energy budget category, the Environmental Restoration Budget Category (ERBC), which is intended to provide greater flexibility in the response to closure and remedial activities. A major project, Closure and Post-Closure Activities (CAPCA), has been identified for ERBC funding to close and remediate the land units in accordance with RCRA requirements. Establishing the scope of this program has required the development of a detailed set of assumptions and a confirmation program for each assumption. Other significant activities in the CAPCA program include the development of risk assessments and the preparation of an integrated schedule

  19. Characterization of Vadose Zone Sediment: Uncontaminated RCRA Borehole Core Samples and Composite Samples

    International Nuclear Information System (INIS)

    Serne, R. Jeffrey; Bjornstad, Bruce N.; Schaef, Herbert T.; Williams, Bruce A.; Lanigan, David C.; Horton, Duane G.; Clayton, Ray E.; Mitroshkov, Alexandre V.; Legore, Virginia L.; O'Hara, Matthew J.; Brown, Christopher F.; Parker, Kent E.; Kutnyakov, Igor V.; Serne, Jennifer N.; Last, George V.; Smith, Steven C.; Lindenmeier, Clark W.; Zachara, John M.; Burke, Deborah S.

    2008-01-01

    This report was revised in September 2008 to remove acid-extractable sodium data from Tables 4.14, 4.16, 5.20, 5.22, 5.43, and 5.45. The sodium data was removed due to potential contamination introduced during the acid extraction process. The rest of the text remains unchanged from the original report issued in February 2002. The overall goal of the of the Tank Farm Vadose Zone Project, led by CH2M HILL Hanford Group, Inc., is to define risks from past and future single-shell tank farm activities. To meet this goal, CH2M HILL Hanford Group, Inc. asked scientists from Pacific Northwest National Laboratory to perform detailed analyses on vadose zone sediment from within the S-SX Waste Management Area. This report is one in a series of four reports to present the results of these analyses. Specifically, this report contains all the geologic, geochemical, and selected physical characterization data collected on vadose zone sediment recovered from Resource Conservation and Recovery Act (RCRA) borehole bore samples and composite samples

  20. Characterization of Vadose Zone Sediment: Uncontaminated RCRA Borehole Core Samples and Composite Samples

    Energy Technology Data Exchange (ETDEWEB)

    Serne, R. Jeffrey; Bjornstad, Bruce N.; Schaef, Herbert T.; Williams, Bruce A.; Lanigan, David C.; Horton, Duane G.; Clayton, Ray E.; Mitroshkov, Alexandre V.; Legore, Virginia L.; O' Hara, Matthew J.; Brown, Christopher F.; Parker, Kent E.; Kutnyakov, Igor V.; Serne, Jennifer N.; Last, George V.; Smith, Steven C.; Lindenmeier, Clark W.; Zachara, John M.; Burke, Deborah S.

    2008-09-11

    This report was revised in September 2008 to remove acid-extractable sodium data from Tables 4.14, 4.16, 5.20, 5.22, 5.43, and 5.45. The sodium data was removed due to potential contamination introduced during the acid extraction process. The rest of the text remains unchanged from the original report issued in February 2002. The overall goal of the of the Tank Farm Vadose Zone Project, led by CH2M HILL Hanford Group, Inc., is to define risks from past and future single-shell tank farm activities. To meet this goal, CH2M HILL Hanford Group, Inc. asked scientists from Pacific Northwest National Laboratory to perform detailed analyses on vadose zone sediment from within the S-SX Waste Management Area. This report is one in a series of four reports to present the results of these analyses. Specifically, this report contains all the geologic, geochemical, and selected physical characterization data collected on vadose zone sediment recovered from Resource Conservation and Recovery Act (RCRA) borehole bore samples and composite samples.

  1. RCRA permitting strategies for the development of innovative technologies: Lessons from Hanford

    International Nuclear Information System (INIS)

    Gajewski, S.W.; Donaghue, J.F.

    1994-01-01

    The Hanford Site restoration is the largest waste cleanup operation in history. The Hanford plutonium production mission generated two-thirds of all the nuclear waste, by volume, in the Department of Energy (DOE) Complex. Cleanup challenges include not only large stored volumes of radioactive, hazardous, and mixed waste, but contaminated soil and groundwater and scores of major structures slated for decontamination, decommissioning, and demolition. DOE and its contractors will need to invent the technology required to do the job on a timetable driven by negotiated milestones, public concerns, and budgetary constraints. This paper will discuss the effort at Hanford to develop an integrated, streamlined strategy for compliance with the Resource Conservation and Recovery Act (RCRA) and the Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) in the conduct of research, development, and demonstration (RD ampersand D) of innovative cleanup technologies. The aspects that will be discussed include the following: the genesis of the RD ampersand D permitting challenge at Hanford; permitting options in the existing regulatory framework; regulatory options that offered the best fit for Hanford RD ampersand D activities, and the problems associated with them; and conclusions and recommendations made to regulatory bodies

  2. Eddy current manual: v.1

    International Nuclear Information System (INIS)

    Cecco, V.S.; Van Drunen, G.; Sharp, F.L.

    1983-09-01

    This training and reference manual was assembled to provide those involved in eddy current testing with both the fundamental principles of the technique as well as the knowledge to deal with often complicated test results. A non-rigorous approach is used to simplify complex physical phenomena. Emphasis is placed on proper choice of test frequency and signal interpretation. Defect detection and diagnosis receive particular attention. Design and construction of probes are covered extensively since probes play a key role in eddy current testing. The advantages and limitations of various probe types are discussed. Electromagnetic theory, instrumentation, test methods and signal analysis are covered. Simplified derivations of probe response to test parameters are presented to develop a basic understanding of eddy current behaviour. Eddy current signals are presented on impedance plane diagrams throughout the manual since this is the most common display on modern, general purpose instruments. The use of Σphase lagΣ in signal analysis is covered in detail. To supplement theory, practical examples are presented to develop proficiency in performing inspections, and to illustrate how basic principles are applied to diagnose real signals

  3. 49 CFR 236.919 - Operations and Maintenance Manual.

    Science.gov (United States)

    2010-10-01

    ..., INSPECTION, MAINTENANCE, AND REPAIR OF SIGNAL AND TRAIN CONTROL SYSTEMS, DEVICES, AND APPLIANCES Standards for Processor-Based Signal and Train Control Systems § 236.919 Operations and Maintenance Manual. (a... identify all software versions, revisions, and revision dates. Plans must be legible and correct. (c...

  4. 49 CFR 236.1039 - Operations and Maintenance Manual.

    Science.gov (United States)

    2010-10-01

    ..., INSPECTION, MAINTENANCE, AND REPAIR OF SIGNAL AND TRAIN CONTROL SYSTEMS, DEVICES, AND APPLIANCES Positive Train Control Systems § 236.1039 Operations and Maintenance Manual. (a) The railroad shall catalog and... software versions, revisions, and revision dates. Plans must be legible and correct. (c) Hardware, software...

  5. 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

  6. Electronic Out-fall Inspection Application - 12007

    Energy Technology Data Exchange (ETDEWEB)

    Weymouth, A Kent III; Pham, Minh; Messick, Chuck [Savannah River Nuclear Solutions, Aiken, South Carolina 29808 (United States)

    2012-07-01

    In early 2009 an exciting opportunity was presented to the Geographic Information Systems (GIS) team at the Savannah River Site (SRS). The SRS maintenance group was directed to maintain all Out-falls on Site, increasing their workload from 75 to 183 out-falls with no additional resources. The existing out-fall inspection system consisted of inspections performed manually and documented via paper trail. The inspections were closed out upon completion of activities and placed in file cabinets with no central location for tracking/trending maintenance activities. A platform for meeting new improvements required for documentation by the Department of Health and Environmental Control (DHEC) out-fall permits was needed to replace this current system that had been in place since the 1980's. This was accomplished by building a geographically aware electronic application that improved reliability of site out-fall maintenance and ensured consistent standards were maintained for environmental excellence and worker efficiency. Inspections are now performed via tablet and uploaded to a central point. Work orders are completed and closed either in the field using tablets (mobile application) or in their offices (via web portal) using PCs. And finally completed work orders are now stored in a central database allowing trending of maintenance activities. (authors)

  7. 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.

  8. 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.

  9. Magnetic rubber inspection (MRI)

    International Nuclear Information System (INIS)

    Carro, L.

    1997-01-01

    Magnetic Rubber Inspection (MRI) was developed to inspect for small cracks and flaws encountered in high performance aircraft. A formula of very fine magnetic particles immersed in a room temperature curing rubber is catalysed and poured into dams (retainers) on the surface of the part to be inspected. Inducing a magnetic field then causes the particles to be drawn to discontinuities in the component under test. These indicating particles are held to the discontinuity by magnetic attraction, as the rubber cures. The solid rubber cast (Replica) is then removed and examined under a microscope for indicating lines of particle concentrations. 3 refs., 6 figs

  10. 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)

  11. Wheel inspection system environment.

    Science.gov (United States)

    2008-11-18

    International Electronic Machines Corporation (IEM) has developed and is now marketing a state-of-the-art Wheel Inspection System Environment (WISE). WISE provides wheel profile and dimensional measurements, i.e. rim thickness, flange height, flange ...

  12. Information-Driven Inspections

    International Nuclear Information System (INIS)

    Laughter, Mark D.; Whitaker, J. Michael; Lockwood, Dunbar

    2010-01-01

    New uranium enrichment capacity is being built worldwide in response to perceived shortfalls in future supply. To meet increasing safeguards responsibilities with limited resources, the nonproliferation community is exploring next-generation concepts to increase the effectiveness and efficiency of safeguards, such as advanced technologies to enable unattended monitoring of nuclear material. These include attribute measurement technologies, data authentication tools, and transmission and security methods. However, there are several conceptual issues with how such data would be used to improve the ability of a safeguards inspectorate such as the International Atomic Energy Agency (IAEA) to reach better safeguards conclusions regarding the activities of a State. The IAEA is pursuing the implementation of information-driven safeguards, whereby all available sources of information are used to make the application of safeguards more effective and efficient. Data from continuous, unattended monitoring systems can be used to optimize on-site inspection scheduling and activities at declared facilities, resulting in fewer, better inspections. Such information-driven inspections are the logical evolution of inspection planning - making use of all available information to enhance scheduled and randomized inspections. Data collection and analysis approaches for unattended monitoring systems can be designed to protect sensitive information while enabling information-driven inspections. A number of such inspections within a predetermined range could reduce inspection frequency while providing an equal or greater level of deterrence against illicit activity, all while meeting operator and technology holder requirements and reducing inspector and operator burden. Three options for using unattended monitoring data to determine an information-driven inspection schedule are to (1) send all unattended monitoring data off-site, which will require advances in data analysis techniques to

  13. Post-Closure Inspection Report for Corrective Action Unit 92: Area 6 Decon Pond Facility, Nevada Test Site, Nevada, for Calendar Year 2006

    International Nuclear Information System (INIS)

    NSTec Environmental Restoration

    2007-01-01

    This Post-Closure Inspection Report provides an analysis and summary of inspections for Corrective Action Unit (CAU) 92, Area 6 Decon Pond Facility. CAU 92 was closed according to the ''Resource Conservation and Recovery Act'' (RCRA) Part B Operational Permit (Nevada Division of Environmental Protection [NDEP], 1995) and the ''Federal Facility Agreement and Consent Order'' (FFACO) of 1996 (FFACO, 1996). Closure activities were completed on February 16, 1999, and the Closure Report (U.S. Department of Energy, Nevada Operations Office, 1999) was approved and a Notice of Completion issued by NDEP on May 11, 1999. CAU 92 consists of two Corrective Action Sites (CASs), CAS 06-04-01, Decon Pad Oil/Water Separator; and CAS 06-05-02, Decontamination Pond (RCRA). Both CASs have use restrictions; however, only CAS 06-05-02 requires post-closure inspections. Visual inspections of the cover and fencing at CAS 06-05-02 are performed quarterly. Additional inspections are conducted if precipitation occurs in excess of 1.28 centimeters (cm) (0.50 inches [in.]) in a 24-hour period. This report covers calendar year 2006. Quarterly site inspections were performed in March, June, September, and December of 2006. All observations indicated the continued integrity of the unit. No issues or concerns were noted, and no corrective actions were necessary. Copies of the inspection checklists and field notes completed during each inspection are included in Appendix A of this report, and photographs taken during the site inspections are included in Appendix B of this report. One additional inspection was performed after a precipitation event that exceeded 1.28 cm (0.50 in.) within a 24-hour period during 2006. No significant changes in site conditions were noted during this inspection, and no corrective actions were necessary. A copy of the inspection checklist and field notes completed during this additional inspection is included in Appendix A of this report. Precipitation records for 2006

  14. Effectiveness evaluation of three RCRA caps at the Y-12 Plant, Oak Ridge, Tennessee

    Energy Technology Data Exchange (ETDEWEB)

    Shevenell, L.A. [Nevada Bureau of Mines and Geology, Reno, NV (United States); Goldstrand, P.M. [Univ. of Tennessee, Knoxville, TN (United States). Dept. of Geological Sciences

    1994-01-01

    Because installation of Resource Conservation and Recovery Act (RCRA)- engineered caps is costly, it is prudent to evaluate the effectiveness of this procedure for hydrologically isolating contaminants. The objective for installation of five-part engineered caps at the Y-12 Plant was to (1) satisfy the regulatory compliance issues, (2) minimize the risk of direct contact with the wastes, and (3) reduce rainfall infiltration. Although the original objectives of installing the caps were not to alter groundwater flow, a potential effect of reducing infiltration is to minimize leaching, thus retarding groundwater contaminant migration from the site. Hence, cap effectiveness with respect to reduced groundwater contaminant migration is evaluated using groundwater data in this report. Based on the available data at the Y-12 capped areas, evaluation of cap effectiveness includes studying water level and chemical variability in nearby monitoring wells. Three caps installed during 1989 are selected for evaluation in this report. These caps are located in three significantly different hydrogeologic settings: overlying a karst aquifer (Chestnut Ridge Security Pits [CRSP]), overlying shales located on a hill slope (Oil Landfarm Waste Management Area [OLWMA]), and overlying shales in a valley floor which is a site of convergent groundwater flow (New Hope Pond [NHP]). Presumably, the caps have been effective in minimizing risk of direct contact with the wastes and halting direct rainfall infiltration into the sites over the extent of the capped areas, but no evidence is presented in this report to directly demonstrate this. The caps installed over the three sites appear to have had a minimal effect on groundwater contaminant migration from the respective sites. Following cap construction, no changes in the configuration of the water table were observed. Migration of contaminant plumes occurred at all three sites, apparently without regard to the timing of cap installation.

  15. CSTEM User Manual

    Science.gov (United States)

    Hartle, M.; McKnight, R. L.

    2000-01-01

    This manual is a combination of a user manual, theory manual, and programmer manual. The reader is assumed to have some previous exposure to the finite element method. This manual is written with the idea that the CSTEM (Coupled Structural Thermal Electromagnetic-Computer Code) user needs to have a basic understanding of what the code is actually doing in order to properly use the code. For that reason, the underlying theory and methods used in the code are described to a basic level of detail. The manual gives an overview of the CSTEM code: how the code came into existence, a basic description of what the code does, and the order in which it happens (a flowchart). Appendices provide a listing and very brief description of every file used by the CSTEM code, including the type of file it is, what routine regularly accesses the file, and what routine opens the file, as well as special features included in CSTEM.

  16. Estimation of inspection effort

    International Nuclear Information System (INIS)

    Mullen, M.F.; Wincek, M.A.

    1979-06-01

    An overview of IAEA inspection activities is presented, and the problem of evaluating the effectiveness of an inspection is discussed. Two models are described - an effort model and an effectiveness model. The effort model breaks the IAEA's inspection effort into components; the amount of effort required for each component is estimated; and the total effort is determined by summing the effort for each component. The effectiveness model quantifies the effectiveness of inspections in terms of probabilities of detection and quantities of material to be detected, if diverted over a specific period. The method is applied to a 200 metric ton per year low-enriched uranium fuel fabrication facility. A description of the model plant is presented, a safeguards approach is outlined, and sampling plans are calculated. The required inspection effort is estimated and the results are compared to IAEA estimates. Some other applications of the method are discussed briefly. Examples are presented which demonstrate how the method might be useful in formulating guidelines for inspection planning and in establishing technical criteria for safeguards implementation

  17. Fuel inspection device

    International Nuclear Information System (INIS)

    Tsuji, Tadashi.

    1990-01-01

    The fuel inspection device of the present invention has a feature of obtaining an optimum illumination upon fuel rod interval inspection operation in a fuel pool. That is, an illumination main body used underwater is connected to a cable which is led out on a floor. A light control device is attached to the other end of the cable and an electric power cable is connected to the light control device. A light source (for example, incandescent lamp) is incorporated in the casing of the illumination main body, and a diffusion plate is disposed at the front to provide a plane light source. The light control device has a light control knob capable of remote-controlling the brightness of the light of the illumination main body. In the fuel inspection device thus constituted, halation is scarcely caused on the image screen upon inspection of fuels by a submerged type television camera to facilitate control upon inspection. Accordingly, efficiency of the fuel inspection can be improved to shorten the operation time. (I.S.)

  18. Radiological Control Manual

    Energy Technology Data Exchange (ETDEWEB)

    1993-04-01

    This manual has been prepared by Lawrence Berkeley Laboratory to provide guidance for site-specific additions, supplements, and clarifications to the DOE Radiological Control Manual. The guidance provided in this manual is based on the requirements given in Title 10 Code of Federal Regulations Part 835, Radiation Protection for Occupational Workers, DOE Order 5480.11, Radiation Protection for Occupational Workers, and the DOE Radiological Control Manual. The topics covered are (1) excellence in radiological control, (2) radiological standards, (3) conduct of radiological work, (4) radioactive materials, (5) radiological health support operations, (6) training and qualification, and (7) radiological records.

  19. EMSL Operations Manual

    Energy Technology Data Exchange (ETDEWEB)

    Foster, Nancy S.

    2009-06-18

    This manual is a general resource tool to assist EMSL users and Laboratory staff within EMSL locate official policy, practice and subject matter experts. It is not intended to replace or amend any formal Battelle policy or practice. Users of this manual should rely only on Battelle’s Standard Based Management System (SBMS) for official policy. No contractual commitment or right of any kind is created by this manual. Battelle management reserves the right to alter, change, or delete any information contained within this manual without prior notice.

  20. EMSL Operations Manual

    Energy Technology Data Exchange (ETDEWEB)

    Foster, Nancy S.

    2009-03-25

    This manual is a general resource tool to assist EMSL users and Laboratory staff within EMSL locate official policy, practice and subject matter experts. It is not intended to replace or amend any formal Battelle policy or practice. Users of this manual should rely only on Battelle’s Standard Based Management System (SBMS) for official policy. No contractual commitment or right of any kind is created by this manual. Battelle management reserves the right to alter, change, or delete any information contained within this manual without prior notice.

  1. Radiological Control Manual

    International Nuclear Information System (INIS)

    1993-04-01

    This manual has been prepared by Lawrence Berkeley Laboratory to provide guidance for site-specific additions, supplements, and clarifications to the DOE Radiological Control Manual. The guidance provided in this manual is based on the requirements given in Title 10 Code of Federal Regulations Part 835, Radiation Protection for Occupational Workers, DOE Order 5480.11, Radiation Protection for Occupational Workers, and the DOE Radiological Control Manual. The topics covered are (1) excellence in radiological control, (2) radiological standards, (3) conduct of radiological work, (4) radioactive materials, (5) radiological health support operations, (6) training and qualification, and (7) radiological records

  2. HASL procedures manual

    International Nuclear Information System (INIS)

    Harley, J.H.

    1977-08-01

    Additions and corrections to the following sections of the HASL Procedures Manual are provided: General, Sampling, Field Measurements; General Analytical Chemistry, Chemical Procedures, Data Section, and Specifications

  3. PCs The Missing Manual

    CERN Document Server

    Karp, David

    2005-01-01

    Your vacuum comes with one. Even your blender comes with one. But your PC--something that costs a whole lot more and is likely to be used daily and for tasks of far greater importance and complexity--doesn't come with a printed manual. Thankfully, that's not a problem any longer: PCs: The Missing Manual explains everything you need to know about PCs, both inside and out, and how to keep them running smoothly and working the way you want them to work. A complete PC manual for both beginners and power users, PCs: The Missing Manual has something for everyone. PC novices will appreciate the una

  4. RCRA facility investigation/corrective measures study work plan for the 100-HR-3 operable unit, Hanford Site, Richland, Washington

    International Nuclear Information System (INIS)

    1992-09-01

    Four areas of the Hanford Site (the 100, 200, 300, and 1100 Areas) have been included on the US Environmental Protection Agency's (EPA's) National Priorities List (NPL) under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). Under the Hanford Federal Facility Agreement and Consent Order, signed by the Washington State Department of Ecology (Ecology), EPA, and the US Department of Energy (DOE), more than 1000 inactive waste disposal and unplanned release sites on the Hanford Site have been grouped into a number of source and groundwater operable units. These operable units contain contamination in the form of hazardous waste, radioactive/hazardous mixed waste, and other CERCLA hazardous substances. Also included in the Tri-Party Agreement are 55 Resource Conservation and Recovery Act (RCRA) treatment, storage, or disposal (TSD) facilities that will be closed or permitted to operate in accordance with RCRA regulations, under the authority of Chapter 173-303 Washington Administrative Code (WAC). Some of the TSD facilities are included in the operable units. This work plan and the attached supporting project plans establish the operable unit setting and the objectives, procedures, tasks, and schedule for conducting the RCRA facility investigation/corrective measures study (RFI/CMS) for the 100-HR-3 operable unit. The 100-HR-3 operable unit underlies the D/DR and H Areas, the 600 Area between them, and the six source operable units these areas contain. The 100-HR-3 operable unit includes all contamination found in the aquifer soils and water within its boundary. Source operable units include facilities and unplanned release sites that are potential sources of contamination. Separate work plans have been initiated for the 100-DR-1 (DOE-RL 1992a) and 100-HR-1 (DOE-RL 1992b) source operable units

  5. Requirements to be met by the operation manual

    International Nuclear Information System (INIS)

    1981-03-01

    The rule applies to the contents and the lay-out of the operating manual for stationary nuclear power plants. The draft contains: 1. General requirement to be met by the contents of the operating manual. The operating manual to be arranged in 4 parts (part 1: internal rules and regulations; part 2: operation overall plant; part 3: incidents; part 4: operation systems). Safety specifications to be included in the manual, the exemption being the system of technical documentation. 2. General requirements to be met by the lay-out of the operating manual. Comprehensibility; legibility; structure and subdivisions; arrangement of the instructions and design of the manuals cover. 3. Requirements to be met by part 1. Defining the various internal rules and regulations (personnel management); rules and regulations concerning inspections and shift work; maintenance and repair; radiation protection; guard duty and admission; alarm; fire protection; first aid. 4. Requirements to be met by part 2. Provisions and operational limitations; limit values important from the point of view of safety; normal operation; anomalous operation; in-service inspections. 6. Requirements to be met by part 3. 7. Annex: Rules, regulations and stipulations mentioned in the rule draft. (orig.)

  6. Recent advances in automated ultrasonic inspection of Magnox power stations

    International Nuclear Information System (INIS)

    Wooldridge, A.B.

    2006-01-01

    Magnox Electric operates a number of Magnox nuclear power stations, some of which have presented difficult inspection challenges. This paper will describe recent advances in automated ultrasonic techniques which have enabled additional, fully effective and qualified inspections to be introduced. The examples chosen involve phased array inspection of fillet welds and the introduction of 3D data display and analysis using NDT Workbench. Ultrasonic phased arrays have been optimised for inspection of fillet welded structures where physical access for the operator is very awkward and the surfaces available for probe scanning are very restricted. In addition to controlling the beam direction and focus depth, the systems have also optimised the depth of field by varying the number of phased array elements fired at a given time. These phased array inspections are substantially superior in quality, reliability and speed compared with that achievable by conventional manual inspection. Analysis of automated ultrasonic data can be very time-consuming if defects are complex. NDT Workbench significantly improves data analysis for complex geometries and defects primarily because of the 3D data displays of multiple beams and automated logging of measurements. This system has been used in 2005 for data analysis of complex defects where sizing accuracy was particularly important. Both these inspection procedures have been formally qualified using the ENIQ (European Network for Inspection Qualification) Methodology. Such qualification was achieved more easily because of the rigorous in house training programmes established in each case and because the Technical Justifications referred to evidence from previous related qualifications whenever appropriate. The timely achievement of inspection qualification demonstrates that the new systems have reached sufficient maturity to be used with confidence for high quality inspections. (orig.)

  7. On the development of the METAR family of inspection tools

    Energy Technology Data Exchange (ETDEWEB)

    Lavoie, E. [Inst. de recherche d' Hydro-Quebec, Varennes, Quebec (Canada)]. E-mail: lavoie.eric@ireq.ca; Rousseau, G. [Hydro-Quebec, Central Nucleaire Gentilly-2, Gentilly, Quebec (Canada); Reynaud, L. [Inst. de recherche d' Hydro-Quebec, Varennes, Quebec (Canada)

    2003-07-01

    Since 1998, Hydro Quebec Research Centre (IREQ), in collaboration with Gentilly-2, has been working on the development of inspection devices for the feeder tubes of CANDU power plants. The first tool to come out of this work was the Metar bracelet, now used throughout the CANDU utilities, consisting of 14 ultrasonic probes held in place in a rigid bracelet to measure the thickness of the pipes and moved around manually along the pipe. Following the success of the Metar, a motorized version, i.e. the Crawler, has been developed to inspect beyond the operator arm's reach to access hard to reach place or further down the pipes in the reactor. This new system has been tested at 3 different stations and will be commercially available soon. Finally, the same technology was used to develop a motorized 2-axis crack detection device to answer new concerns about the feeder. Other configurations, depending on the demands from the industry, could also be developed for specific inspection needs, for example; inspection of the graylock welds, 360{sup o} inspection of feeders, or multitasking inspection on a single frame, etc. Most of the designs shown in this article have been or will be patented and are, or will be, licensed to a partner company to make them commercially available to the industry. This paper gives a brief history of the project and a description of the technologies developed in the last 5 years concerning feeder inspection. (author)

  8. RCRA Part B permit modifications for cost savings and increased flexibility at the Rocky Flats Environmental Technology Site

    International Nuclear Information System (INIS)

    Jierree, C.; Ticknor, K.

    1996-10-01

    With shrinking budgets and downsizing, a need for streamlined compliance initiatives became evident at the Rocky Flats Environmental Technology Site (RFETS). Therefore, Rocky Mountain Remediation Services (RMRS) at the RFETS successfully and quickly modified the RFETS RCRA Part B Permit to obtain significant cost savings and increased flexibility. This 'was accomplished by requesting operations personnel to suggest changes to the Part B Permit which did not diminish overall compliance and which would be most. cost beneficial. The U.S. Department of Energy (DOE) subsequently obtained approval of those changes from the Colorado Department of Public Health and the Environment (CDPHE)

  9. Molten salt oxidation of mixed wastes: Separation of radioactive materials and Resource Conservation and Recovery Act (RCRA) materials

    International Nuclear Information System (INIS)

    Bell, J.T.; Haas, P.A.; Rudolph, J.C.

    1995-01-01

    The Oak Ridge National Laboratory (ORNL) is participating in a program to apply a molten salt oxidation (MSO) process to treatment of mixed (radioactive and RCRA) wastes. The salt residues from the MSO treatment will require further separations or other processing to prepare them for final disposal. A bench-scale MSO apparatus is being installed at ORNL and will be operated on real Oak Ridge wastes. The treatment concepts to be tested and demonstrated on the salt residues from real wastes are described

  10. Mobilization plan for the Y-12 9409-5 tank storage facility RCRA closure plan. Final report. Revision 1

    International Nuclear Information System (INIS)

    1993-11-01

    This mobilization plan identifies the activities and equipment necessary to begin the field sampling for the Oak Ridge Y-12 9409-5 Diked Tank Storage Facility (DTSF) Resource Conservation and Recovery Act (RCRA) closure. Elements of the plan outline the necessary components of each mobilization task and identify whether SAIC or the Martin Marietta Energy Systems, Inc. Y-12 Environmental Restoration Division will be responsible for task coordination. Field work will be conducted in two phases: mobilization phase and soil sampling phase. Training and medical monitoring, access, permits and passes, decontamination/staging area, equipment, and management are covered in this document

  11. 1993 RCRA Part B permit renewal application, Savannah River Site: Volume 10, Consolidated Incineration Facility, Section C, Revision 1

    International Nuclear Information System (INIS)

    Molen, G.

    1993-08-01

    This section describes the chemical and physical nature of the RCRA regulated hazardous wastes to be handled, stored, and incinerated at the Consolidated Incineration Facility (CIF) at the Savannah River Site. It is in accordance with requirements of South Carolina Hazardous Waste Management Regulations R.61-79.264.13(a) and(b), and 270.14(b)(2). This application is for permit to store and teat these hazardous wastes as required for the operation of CIF. The permit is to cover the storage of hazardous waste in containers and of waste in six hazardous waste storage tanks. Treatment processes include incineration, solidification of ash, and neutralization of scrubber blowdown

  12. 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.)

  13. Automated reticle inspection data analysis for wafer fabs

    Science.gov (United States)

    Summers, Derek; Chen, Gong; Reese, Bryan; Hutchinson, Trent; Liesching, Marcus; Ying, Hai; Dover, Russell

    2009-04-01

    To minimize potential wafer yield loss due to mask defects, most wafer fabs implement some form of reticle inspection system to monitor photomask quality in high-volume wafer manufacturing environments. Traditionally, experienced operators review reticle defects found by an inspection tool and then manually classify each defect as 'pass, warn, or fail' based on its size and location. However, in the event reticle defects are suspected of causing repeating wafer defects on a completed wafer, potential defects on all associated reticles must be manually searched on a layer-by-layer basis in an effort to identify the reticle responsible for the wafer yield loss. This 'problem reticle' search process is a very tedious and time-consuming task and may cause extended manufacturing line-down situations. Often times, Process Engineers and other team members need to manually investigate several reticle inspection reports to determine if yield loss can be tied to a specific layer. Because of the very nature of this detailed work, calculation errors may occur resulting in an incorrect root cause analysis effort. These delays waste valuable resources that could be spent working on other more productive activities. This paper examines an automated software solution for converting KLA-Tencor reticle inspection defect maps into a format compatible with KLA-Tencor's Klarity Defect(R) data analysis database. The objective is to use the graphical charting capabilities of Klarity Defect to reveal a clearer understanding of defect trends for individual reticle layers or entire mask sets. Automated analysis features include reticle defect count trend analysis and potentially stacking reticle defect maps for signature analysis against wafer inspection defect data. Other possible benefits include optimizing reticle inspection sample plans in an effort to support "lean manufacturing" initiatives for wafer fabs.

  14. 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.

  15. Inspection Strategies for Concrete Bridges

    DEFF Research Database (Denmark)

    Sørensen, John Dalsgaard; Thoft-Christensen, Palle

    1989-01-01

    In this paper an optimal inspection strategy for concrete bridges based on periodic routine and detailed inspections is presented. The failure mode considered is corrosion of the reinforcement due to chlorides. A simple modelling of the corrosion and of the inspection strategy is presented....... The optimal inspection strategy is determined from an optimization problem, where the design variables are time intervals between detailed inspections and the concrete cover. The strategy is illustrated on a simple structure, namely a reinforced concrete beam....

  16. Resource Conservation and Recovery Act (RCRA) general contingency plan for hazardous waste treatment, storage, and disposal units at the Oak Ridge Y-12 Plant

    International Nuclear Information System (INIS)

    Skaggs, B.E.

    1993-11-01

    The Y-12 RCRA Contingency Plan will be continually reviewed and revised if any of the following occur: the facility permit is revised, the plan is inadequate in an emergency, the procedures herein can be improved, the operations of the facility change in a way that alters the plan, the emergency coordinator changes, or the emergency equipment list changes. Copies of the Y-12 Emergency Management Plan are available at the Plant Shift Superintendent's Office and the Emergency Management Office. This document serves to supplement the Y-12 Emergency Management Plan to be appropriate for all RCRA hazardous waste treatment, storage, or disposal units. The 90-day accumulation areas at the Y-12 Plant have a separate contingency supplement as required by RCRA and are separate from this supplement

  17. Resource Conservation and Recovery Act (RCRA) contingency plan for hazardous waste treatment, storage, and disposal units at the Oak Ridge Y-12 Plant

    International Nuclear Information System (INIS)

    1994-08-01

    The Y-12 RCRA Contingency Plan will be continually reviewed and revised if any of the following occur: the facility permit is revised, the plan is inadequate in an emergency, the procedures can be improved, the operations of the facility change in a way that alters the plan, the emergency coordinator changes, or the emergency equipment list changes. Copies of the Y-12 Emergency Management Plan are available at the Plant Shift Superintendent's Office and the Emergency Management Office. This document serves to supplement the Y-12 Emergency Management Plan to be appropriate for all RCRA hazardous waste treatment, storage, or disposal units. The 90-day accumulation areas at the Y-12 Plant have a separate contingency supplement as required by RCRA and are separate from this supplement

  18. Quality Assurance Project Plan for the HWMA/RCRA Closure Certification of the TRA-731 Caustic and Acid Storage Tank System - 1997 Notice of Violation Consent Order; TOPICAL

    International Nuclear Information System (INIS)

    Evans, S.K.

    2002-01-01

    This Quality Assurance Project Plan for the HWMA/RCRA Closure Certification of the TRA- 731 Caustic and Acid Storage Tank System is one of two documents that comprise the Sampling and Analysis Plan for the HWMA/RCRA closure certification of the TRA-731 caustic and acid storage tank system at the Idaho National Engineering and Environmental Laboratory. This plan, which provides information about the project description, project organization, and quality assurance and quality control procedures, is to be used in conjunction with the Field Sampling Plan for the HWMA/RCRA Closure Certification of the TRA-731 Caustic and Acid Storage Tank System. This Quality Assurance Project Plan specifies the procedures for obtaining the data of known quality required by the closure activities for the TRA-731 caustic and acid storage tank system

  19. Ultrasonic boiler inspection and economic analysis guidelines

    International Nuclear Information System (INIS)

    Anon.

    1987-01-01

    Boiler tube failures cause approximately 6% availability loss of large fossil-fired power generating plants. This loss can be reduced by systematic approaches using ultrasonic examination and root cause failure analysis methods. Two projects sponsored by EPRI have provided utility engineers with guidelines for performing ultrasonic examinations and with details on 22 types of tube failure mechanisms. A manual has been published that provides descriptions of typical locations, superficial appearances, damage mechanisms, metallurgy, microstructural changes, likely root causes, and potential corrective actions. Application of the principles in the manual is being demonstrated in an EPRI-funded project at 10 electric utilities over the next two years. Guidelines have been published that prescribe the activities necessary for ultrasonic examinations of boiler tubes. Eight essential elements of a boiler examination should be performed to assure that possible economic benefits are obtained. Work was supported by EPRI under RP 1890 and RP 1865. A software package has been developed for effectively planning inspections for wall thinning in fossil-fired boiler tubing. The software assists in minimizing costs associated with maintenance, such as inspection and repair, while the life of the boiler is maximized

  20. Oil Spill Response Manual

    NARCIS (Netherlands)

    Marieke Zeinstra; Sandra Heins; Wierd Koops

    2014-01-01

    A two year programme has been carried out by the NHL University of Applied Sciences together with private companies in the field of oil and chemical spill response to finalize these manuals on oil and chemical spill response. These manuals give a good overview of all aspects of oil and chemical

  1. Technical Manual. The ACT®

    Science.gov (United States)

    ACT, Inc., 2014

    2014-01-01

    This manual contains technical information about the ACT® college readiness assessment. The principal purpose of this manual is to document the technical characteristics of the ACT in light of its intended purposes. ACT regularly conducts research as part of the ongoing formative evaluation of its programs. The research is intended to ensure that…

  2. Eco-Innovation Manual

    DEFF Research Database (Denmark)

    O'Hare, Jamie Alexander; McAloone, Tim C.; Pigosso, Daniela Cristina Antelmi

    Aim of this manual is to introduce a methodology for the implementation of eco‐innovation within small and medium sized companies in developing and emerging economies. The intended audience of this manual is organizations that provide professional services to guide and support manufacturing compa...... companies to improve their sustainability performance....

  3. Marketing Research. Instructor's Manual.

    Science.gov (United States)

    Small Business Administration, Washington, DC.

    Prepared for the Administrative Management Course Program, this instructor's manual was developed to serve small-business management needs. The sections of the manual are as follows: (1) Lesson Plan--an outline of material covered, which may be used as a teaching guide, presented in two columns: the presentation, and a step-by-step indication of…

  4. Indoor Air Quality Manual.

    Science.gov (United States)

    Baldwin Union Free School District, NY.

    This manual identifies ways to improve a school's indoor air quality (IAQ) and discusses practical actions that can be carried out by school staff in managing air quality. The manual includes discussions of the many sources contributing to school indoor air pollution and the preventive planning for each including renovation and repair work,…

  5. GERTS GQ User's Manual.

    Science.gov (United States)

    Akiba, Y.; And Others

    This user's manual for the simulation program Graphical Evaluation and Review Technique (GERT) GQ contains sections on nodes, branches, program input description and format, and program output, as well as examples. Also included is a programmer's manual which contains information on scheduling, subroutine descriptions, COMMON Variables, and…

  6. CRISP instrument manual

    International Nuclear Information System (INIS)

    Bucknall, D.G.; Langridge, Sean

    1997-05-01

    This document is a user manual for CRISP, one of the two neutron reflectomers at ISIS. CRISP is highly automated allowing precision reproducible measurements. The manual provides detailed instructions for the setting-up and running of the instrument and advice on data analysis. (UK)

  7. Piping inspection round robin

    International Nuclear Information System (INIS)

    Heasler, P.G.; Doctor, S.R.

    1996-04-01

    The piping inspection round robin was conducted in 1981 at the Pacific Northwest National Laboratory (PNNL) to quantify the capability of ultrasonics for inservice inspection and to address some aspects of reliability for this type of nondestructive evaluation (NDE). The round robin measured the crack detection capabilities of seven field inspection teams who employed procedures that met or exceeded the 1977 edition through the 1978 addenda of the American Society of Mechanical Engineers (ASME) Section 11 Code requirements. Three different types of materials were employed in the study (cast stainless steel, clad ferritic, and wrought stainless steel), and two different types of flaws were implanted into the specimens (intergranular stress corrosion cracks (IGSCCs) and thermal fatigue cracks (TFCs)). When considering near-side inspection, far-side inspection, and false call rate, the overall performance was found to be best in clad ferritic, less effective in wrought stainless steel and the worst in cast stainless steel. Depth sizing performance showed little correlation with the true crack depths

  8. Inspection device in liquid

    International Nuclear Information System (INIS)

    Nagaoka, Etsuo.

    1996-01-01

    The present invention provides an inspection device in PWR reactor core in which inspection operations are made efficient by stabilizing a posture of the device in front-to-back, vertical and left-to-right directions by a simple structure. When the device conducts inspection while running in liquid, the front and the back directions of the device main body are inspected using a visual device while changing the posture by operating a front-to-back direction propulsion device and a right-to-left direction propulsion device, and a vertical direction propulsion device against to rolling, pitching and yawing of the device main body. In this case, a spherical magnet moves freely in the gravitational direction in a vibration-damping fluid in a non-magnetic spherical shell following the change of the posture of the device main body, in which the vibrations due to the movement of the spherical magnet is settled by the vibration-damping fluid thereby stabilizing the posture of the device main body. At a typical inspection posture, the settling effect is enhanced by the attraction force between the spherical magnets in the spherical shell and each of magnetic force-attracted magnetic members disposed to the outer circumference of the shell, and the posture of the device main body can be confirmed in front-to-back, right-to-left and vertical directions by each of the posture confirming magnetic sensors. (N.H.)

  9. P-scan, a new system for ultrasonic weld inspection

    International Nuclear Information System (INIS)

    Lund, S.A.; Iversen, S.E.; Holst, H.

    1978-01-01

    The P-scan method is explained. It is described how the new P-scan system improves the ultrasonic method by adding means for visualization, data storage and documentation. Three different scanners are described: One designed for manual operation, another for automatic operation and a third for semiautomatic operation. The p'scan image of an ultrasonically examined test plate is presented and discussed. The variable Display Level (i.e. the inspection sensitivity) facility is described. The main advantage of this facility is the fact that the level can be varied at any time after the inspection. (orig.) [de

  10. Robots in pipe and vessel inspection: past, present, and future

    International Nuclear Information System (INIS)

    Mueller, T.A.; Tyndall, J.F.

    1984-01-01

    Over the past several decades, remotely operated scanners have been employed to inspect piping and pressure vessels. These devices in their early forms were manually controlled manipulators functioning as mere extensions of the operator. With the addition of limit sensing, speed control, and positional feedback and display, the early manipulators became primitive robots. By adding computer controls with their degree of intelligence to the devices, they achieved the status of robots. Future applications of vision, adaptive control, proximity sensing, and pattern recognition will bring these devices to a level of intelligence that will make automated robotic inspection of pipes and pressure vessels a true reality

  11. RCRA Part A Permit Application for Waste Management Activities at the Nevada Test Site, Part B Permit Application Hazardous Waste Storage Unit, Nevada Test Site, and Part B Permit Application - Explosives Ordnance Disposal Unit (EODU)

    International Nuclear Information System (INIS)

    2010-01-01

    The Area 5 Hazardous Waste Storage Unit (HWSU) was established to support testing, research, and remediation activities at the Nevada Test Site (NTS), a large-quantity generator of hazardous waste. The HWSU, located adjacent to the Area 5 Radioactive Waste Management Site (RWMS), is a prefabricated, rigid steel-framed, roofed shelter used to store hazardous nonradioactive waste generated on the NTS. No offsite generated wastes are managed at the HWSU. Waste managed at the HWSU includes the following categories: Flammables/Combustibles; Acid Corrosives; Alkali Corrosives; Oxidizers/Reactives; Toxics/Poisons; and Other Regulated Materials (ORMs). A list of the regulated waste codes accepted for storage at the HWSU is provided in Section B.2. Hazardous wastes stored at the HWSU are stored in U.S. Department of Transportation (DOT) compliant containers, compatible with the stored waste. Waste transfer (between containers) is not allowed at the HWSU and containers remain closed at all times. Containers are stored on secondary containment pallets and the unit is inspected monthly. Table 1 provides the metric conversion factors used in this application. Table 2 provides a list of existing permits. Table 3 lists operational Resource Conservation and Recovery Act (RCRA) units at the NTS and their respective regulatory status.

  12. RCRA Part A Permit Application for Waste Management Activities at the Nevada Test Site, Part B Permit Application Hazardous Waste Storage Unit, Nevada Test Site, and Part B Permit Application - Explosives Ordnance Disposal Unit (EODU)

    Energy Technology Data Exchange (ETDEWEB)

    NSTec Environmental Programs

    2010-06-17

    The Area 5 Hazardous Waste Storage Unit (HWSU) was established to support testing, research, and remediation activities at the Nevada Test Site (NTS), a large-quantity generator of hazardous waste. The HWSU, located adjacent to the Area 5 Radioactive Waste Management Site (RWMS), is a prefabricated, rigid steel-framed, roofed shelter used to store hazardous nonradioactive waste generated on the NTS. No offsite generated wastes are managed at the HWSU. Waste managed at the HWSU includes the following categories: Flammables/Combustibles; Acid Corrosives; Alkali Corrosives; Oxidizers/Reactives; Toxics/Poisons; and Other Regulated Materials (ORMs). A list of the regulated waste codes accepted for storage at the HWSU is provided in Section B.2. Hazardous wastes stored at the HWSU are stored in U.S. Department of Transportation (DOT) compliant containers, compatible with the stored waste. Waste transfer (between containers) is not allowed at the HWSU and containers remain closed at all times. Containers are stored on secondary containment pallets and the unit is inspected monthly. Table 1 provides the metric conversion factors used in this application. Table 2 provides a list of existing permits. Table 3 lists operational Resource Conservation and Recovery Act (RCRA) units at the NTS and their respective regulatory status.

  13. MARS CODE MANUAL VOLUME III - Programmer's Manual

    International Nuclear Information System (INIS)

    Chung, Bub Dong; Hwang, Moon Kyu; Jeong, Jae Jun; Kim, Kyung Doo; Bae, Sung Won; Lee, Young Jin; Lee, Won Jae

    2010-02-01

    Korea Advanced Energy Research Institute (KAERI) conceived and started the development of MARS code with the main objective of producing a state-of-the-art realistic thermal hydraulic systems analysis code with multi-dimensional analysis capability. MARS achieves this objective by very tightly integrating the one dimensional RELAP5/MOD3 with the multi-dimensional COBRA-TF codes. The method of integration of the two codes is based on the dynamic link library techniques, and the system pressure equation matrices of both codes are implicitly integrated and solved simultaneously. In addition, the Equation-Of-State (EOS) for the light water was unified by replacing the EOS of COBRA-TF by that of the RELAP5. This programmer's manual provides a complete list of overall information of code structure and input/output function of MARS. In addition, brief descriptions for each subroutine and major variables used in MARS are also included in this report, so that this report would be very useful for the code maintenance. The overall structure of the manual is modeled on the structure of the RELAP5 and as such the layout of the manual is very similar to that of the RELAP. This similitude to RELAP5 input is intentional as this input scheme will allow minimum modification between the inputs of RELAP5 and MARS3.1. MARS3.1 development team would like to express its appreciation to the RELAP5 Development Team and the USNRC for making this manual possible

  14. Egyptian Mythological Manuals

    DEFF Research Database (Denmark)

    Jørgensen, Jens Kristoffer Blach

    From the hands of Greek mythographers a great number of myths have survived along with philosophical discussions of their meaning and relevance for the Greeks. It is little known that something similar existed in ancient Egypt where temple libraries and archives held scholarly literature used...... by the native priesthood, much of which has only been published in recent years. As part of this corpus of texts, the ancient Egyptian mythological manuals offer a unique perspective on how the Egyptian priesthood structured and interpreted Egyptian myths. The thesis looks at the different interpretative...... techniques used in the Tebtunis Mythological Manual (Second century CE) and the Mythological Manual of the Delta (Sixth century BCE) and the place of these manuals within the larger corpus of priestly scholarly literature from ancient Egypt. To organize the wealth of local myths the manuals use model...

  15. Fuel Element Technical Manual

    Energy Technology Data Exchange (ETDEWEB)

    Burley, H.H. [ed.

    1956-08-01

    It is the purpose of the Fuel Element Technical Manual to Provide a single document describing the fabrication processes used in the manufacture of the fuel element as well as the technical bases for these processes. The manual will be instrumental in the indoctrination of personnel new to the field and will provide a single data reference for all personnel involved in the design or manufacture of the fuel element. The material contained in this manual was assembled by members of the Engineering Department and the Manufacturing Department at the Hanford Atomic Products Operation between the dates October, 1955 and June, 1956. Arrangement of the manual. The manual is divided into six parts: Part I--introduction; Part II--technical bases; Part III--process; Part IV--plant and equipment; Part V--process control and improvement; and VI--safety.

  16. Issues in radioactive mixed waste compliance with RCRA [Resource Conservation and Recovery Act]: Some examples from ongoing operations at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Eaton, D.L.; Smith, T.H.; Clements, T.L. Jr.; Hodge, V.

    1990-01-01

    Radioactive mixed waste is subject to regulation under both the Resource Conservation and Recovery Act (RCRA) and the Atomic Energy Act (AEA). The regulation of such waste is the responsibility of the Environmental Protection Agency (EPA) and either the Nuclear Regulatory Commission (NRC) or the Department of Energy (DOE), depending on whether the waste is commercially generated or defense-related. The recent application of the RCRA regulations to ongoing operations at the DOE's Idaho National Engineering Laboratory (INEL) are described in greater detail. 8 refs., 2 figs

  17. Plant abnormality inspection device

    International Nuclear Information System (INIS)

    Takenaka, Toshio.

    1990-01-01

    The present invention concerns a plant abnormality inspection device for conducting remote or automatic patrolling inspection in a plant and, more particularly, relates to such a device as capable of detecting abnormal odors. That is, the device comprises a moving device for moving to a predetermined position in the plant, a plurality of gas sensors for different kind of gases to be inspected mounted thereon, a comparator for comparing the concentration of a gas detected by the gas sensor with the normal gas concentration at the predetermined position and a judging means for judging the absence or presence of abnormality depending on the combination of the result of the comparison and deliverying a signal if the state is abnormal. As a result, a slight amount of gas responsible to odors released upon abnormality of the plant can be detected by a plurality of gas sensors for different kinds gases to rapidly and easily find abnormal portions in the plant. (I.S.)

  18. 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.

  19. A novel inspection system for cosmetic defects

    Science.gov (United States)

    Hazra, S.; Roy, R.; Williams, D.; Aylmore, R.; Hollingdale, D.

    2013-12-01

    The appearance of automotive skin panels creates desirability for a product and differentiates it from the competition. Because of the importance of skin panels, considerable care is taken in minimizing defects such as the 'hollow' defect that occur around door-handle depressions. However, the inspection process is manual, subjective and time-consuming. This paper describes the development of an objective and inspection scheme for the 'hollow' defect. In this inspection process, the geometry of a panel is captured using a structured lighting system. The geometry data is subsequently analyzed by a purpose-built wavelet-based algorithm to identify the location of any defects that may be present and to estimate the perceived severity of the defects without user intervention. This paper describes and critically evaluates the behavior of this physically-based algorithm on an ideal and real geometry and compares its result to an actual audit. The results show that the algorithm is capable of objectively locating and classifying 'hollow' defects in actual panels.

  20. 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...

  1. Inspection and test planning

    International Nuclear Information System (INIS)

    Miller, T.

    1980-01-01

    Purpose of Quality Plan - arrangement of all necessary tests or inspections as far as possible filted to certain components or systems. Subject of Quality Plan - precise determination of tests or inspections and - according to the actual safety significance - the certificates to be done. Disposition of Quality Plan - accommodation of tests to the actual state of fabrication. Application of Quality Plan - to any component or system that is regarded. Supervision of Employment - by authorized personnel of manufacturer, customer or authority providing exact employment of quality plan. Overservance of Instructions - certificates given by authorized personnel. (orig./RW)

  2. RCRA corrective measures using a permeable reactive iron wall US Coast Guard Support Center, Elizabeth City, North Carolina

    International Nuclear Information System (INIS)

    Schmithors, W.L.; Vardy, J.A.

    1997-01-01

    A chromic acid release was discovered at a former electroplating shop at the U.S. Coast Guard Support Center in Elizabeth City, North Carolina. Initial investigative activities indicated that chromic acid had migrated into the subsurface soils and groundwater. In addition, trichloroethylene (TCE) was also discovered in groundwater during subsequent investigations of the hexavalent chromium (Cr VI) plume. Corrective measures were required under the Resource Conservation and Recovery Act (RCRA). The in-situ remediation method, proposed under RCRA Interim Measures to passively treat the groundwater contaminants, uses reactive zero-valent iron to reductively dechlorinate the chlorinated compounds and to mineralize the hexavalent chromium. A 47 meter by 0.6 meter subsurface permeable iron wall was installed downgradient of the source area to a depth of 7 meters using a direct trenching machine. The iron filings were placed in the ground as the soils were excavated from the subsurface. This is the first time that direct trenching was used to install reactive zero-valent iron filings. Over 250 metric tons of iron filings were used as the reactive material in the barrier wall. Installation of the iron filings took one full day. Extensive negotiations with regulatory agencies were required to use this technology under the current facility Hazardous Waste Management Permit. All waste soils generated during the excavation activities were contained and treated on site. Once contaminant concentrations were reduced the waste soils were used as fill material

  3. RCRA Facility investigation report for Waste Area Grouping 6 at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1991-09-01

    This report provides a detailed summary of the activities carried out to sample groundwater at Waste Area Grouping (WAG) 6. The analytical results for samples collected during Phase 1, Activity 2 of the WAG 6 Resource Conservation and Recovery Act Facility Investigation (RFI) are also presented. In addition, analytical results for Phase 1, activity sampling events for which data were not previously reported are included in this TM. A summary of the groundwater sampling activities of WAG 6, to date, are given in the Introduction. The Methodology section describes the sampling procedures and analytical parameters. Six attachments are included. Attachments 1 and 2 provide analytical results for selected RFI groundwater samples and ORNL sampling event. Attachment 3 provides a summary of the contaminants detected in each well sampled for all sampling events conducted at WAG 6. Bechtel National Inc. (BNI)/IT Corporation Contract Laboratory (IT) RFI analytical methods and detection limits are given in Attachment 4. Attachment 5 provides the Oak Ridge National Laboratory (ORNL)/Analytical Chemistry Division (ACD) analytical methods and detection limits and Resource Conservation and Recovery Act (RCRA) quarterly compliance monitoring (1988--1989). Attachment 6 provides ORNL/ACD groundwater analytical methods and detection limits (for the 1990 RCRA semi-annual compliance monitoring)

  4. User`s guide for the Augmented Computer Exercise for Inspection Training (ACE-IT), Version 2.0 software

    Energy Technology Data Exchange (ETDEWEB)

    Dobranich, P.R. [Sandia National Labs., Albuquerque, NM (United States); Horak, K.E.; Evanko, D.A. [Excel Tactical Staffing, Albuquerque, NM (United States)] [and others

    1998-04-01

    The on-site inspection provisions in many current and proposed arms control agreements require extensive preparation and training on the part of both the Inspection Teams (inspectors) and Inspected Parties (hosts). Traditional training techniques include lectures, table-top inspections, and practice inspections. The Augmented Computer Exercise for Inspection Training (ACE-IT), an interactive computer training tool, increases the utility of table-top inspections. ACE-IT is used for training both inspectors and hosts to conduct a hypothetical challenge inspection under the Chemical Weapons Convention (CWC). The training covers the entire sequence of events in the challenge inspection regime, from initial notification of an inspection through post-inspection activities. The primary emphasis of the training tool is on conducting the inspection itself, and in particular, implementing the concept of managed access. (Managed access is a technique used to assure the inspectors that the facility is in compliance with the CWC, while at the same time protecting sensitive information unrelated to the CWC.) Information for all of the activities is located in the electronic {open_quotes}Exercise Manual.{close_quotes} In addition, interactive menus are used to negotiate access to each room and to alternate information during the simulated inspection. ACE-IT also demonstrates how various inspection provisions impact compliance determination and the protection of sensitive information.

  5. Inspection of Emergency Arrangements

    International Nuclear Information System (INIS)

    2013-01-01

    The Working Group on Inspection Practices (WGIP) was tasked by the NEA CNRA to examine and evaluate the extent to which emergency arrangements are inspected and to identify areas of importance for the development of good inspection practices. WGIP members shared their approaches to the inspection of emergency arrangements by the use of questionnaires, which were developed from the requirements set out in IAEA Safety Standards. Detailed responses to the questionnaires from WGIP member countries have been compiled and are presented in the appendix to this report. The following commendable practices have been drawn from the completed questionnaires and views provided by WGIP members: - RBs and their Inspectors have sufficient knowledge and information regarding operator's arrangements for the preparedness and response to nuclear emergencies, to enable authoritative advice to be given to the national coordinating authority, where necessary. - Inspectors check that the operator's response to a nuclear emergency is adequately integrated with relevant response organisations. - Inspectors pay attention to consider the integration of the operator's response to safety and security threats. - The efficiency of international relations is checked in depth during some exercises (e.g. early warning, assistance and technical information), especially for near-border facilities that could lead to an emergency response abroad. - RB inspection programmes consider the adequacy of arrangements for emergency preparedness and response to multi-unit accidents. - RBs assess the adequacy of arrangements to respond to accidents in other countries. - The RB's role is adequately documented and communicated to all agencies taking part in the response to a nuclear or radiological emergency. - Inspectors check that threat assessments for NPPs have been undertaken in accordance with national requirements and that up-to-date assessments have been used as the basis for developing emergency plans for

  6. Salinas : theory manual.

    Energy Technology Data Exchange (ETDEWEB)

    Walsh, Timothy Francis; Reese, Garth M.; Bhardwaj, Manoj Kumar

    2004-08-01

    This manual describes the theory behind many of the constructs in Salinas. For a more detailed description of how to use Salinas , we refer the reader to Salinas, User's Notes. Many of the constructs in Salinas are pulled directly from published material. Where possible, these materials are referenced herein. However, certain functions in Salinas are specific to our implementation. We try to be far more complete in those areas. The theory manual was developed from several sources including general notes, a programer-notes manual, the user's notes and of course the material in the open literature.

  7. Fire Protection Program Manual

    Energy Technology Data Exchange (ETDEWEB)

    Sharry, J A

    2012-05-18

    This manual documents the Lawrence Livermore National Laboratory (LLNL) Fire Protection Program. Department of Energy (DOE) Orders 420.1B, Facility Safety, requires LLNL to have a comprehensive and effective fire protection program that protects LLNL personnel and property, the public and the environment. The manual provides LLNL and its facilities with general information and guidance for meeting DOE 420.1B requirements. The recommended readers for this manual are: fire protection officers, fire protection engineers, fire fighters, facility managers, directorage assurance managers, facility coordinators, and ES and H team members.

  8. Pipework inspection apparatus

    International Nuclear Information System (INIS)

    Wrigglesworth, K.J.; Knowles, J.F.

    1987-01-01

    The patent concerns a pipework inspection apparatus, which is capable of negotiating bends in pipework. The apparatus comprises a TV camera system, which contains an optical section and an electronics section, which are connected by a flexible coupling. The system can be pulled or pushed along the bore of the pipework. (U.K.)

  9. Fuel assembly inspection device

    International Nuclear Information System (INIS)

    Yaginuma, Yoshitaka

    1998-01-01

    The present invention provides a device suitable to inspect appearance of fuel assemblies by photographing the appearance of fuel assemblies. Namely, the inspection device of the present invention measures bowing of fuel assembly or each of fuel rods or both of them based on the partially photographed images of fuel assembly. In this case, there is disposed a means which flashily projects images in the form of horizontal line from a direction intersecting obliquely relative to a horizontal cross section of the fuel assembly. A first image processing means separates the projected image pictures including projected images and calculates bowing. A second image processing means replaces the projected image pictures of the projected images based on projected images just before and after the photographing. Then, images for the measurement of bowing and images for inspection can be obtained simultaneously. As a result, the time required for the photographing can be shortened, the time for inspection can be shortened and an effect of preventing deterioration of photographing means by radiation rays can be provided. (I.S.)

  10. HASL procedures manual

    International Nuclear Information System (INIS)

    1980-08-01

    Addition and corrections to the following sections of the HASL Procedures Manual are provided: Table of Contents; Bibliography; Fallout Collection Methods; Wet/Dry Fallout Collection; Fluoride in Soil and Sediment; Strontium-90; Natural Series; Alpha Emitters; and Gamma Emitters

  11. SEVERO code - user's manual

    International Nuclear Information System (INIS)

    Sacramento, A.M. do.

    1989-01-01

    This user's manual contains all the necessary information concerning the use of SEVERO code. This computer code is related to the statistics of extremes = extreme winds, extreme precipitation and flooding hazard risk analysis. (A.C.A.S.)

  12. The organizational measurement manual

    National Research Council Canada - National Science Library

    Wealleans, David

    2001-01-01

    ... Relationship of process to strategic measurements Summary 37 36Contents 19/10/2000 1:23 pm Page vi vi THE ORGANIZATIONAL MEASUREMENT MANUAL 4 PART 2 ESTABLISHING A PROCESS MEASUREMENT PROGRAMME...

  13. Geochemical engineering reference manual

    Energy Technology Data Exchange (ETDEWEB)

    Owen, L.B.; Michels, D.E.

    1984-01-01

    The following topics are included in this manual: physical and chemical properties of geothermal brine and steam, scale and solids control, processing spent brine for reinjection, control of noncondensable gas emissions, and goethermal mineral recovery. (MHR)

  14. NCDC Archive Documentation Manuals

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — The National Climatic Data Center Tape Deck Documentation library is a collection of over 400 manuals describing NCDC's digital holdings (both historic and current)....

  15. EMAP Users Manual.

    Science.gov (United States)

    Kotz, Arnold; Redondo, Rory

    Presented is the user's manual for the Educational Manpower Information Sources Project (EMAP), an information file containing approximately 325 document abstracts related to the field of educational planning. (The EMAP file is described in document SP 006 747.) (JB)

  16. FINAS. Example manual. 2

    International Nuclear Information System (INIS)

    Iwata, Koji; Tsukimori, Kazuyuki; Ueno, Mutsuo

    2003-12-01

    FINAS is a general purpose structural analysis computer program which was developed by Japan Nuclear Cycle Development Institute for the analysis of static, dynamic and thermal responses of elastic and inelastic structures by the finite element method. This manual contains typical analysis examples that illustrate applications of FINAS to a variety of structural engineering problems. The first part of this manual presents fundamental examples in which numerical solutions by FINAS are compared with some analytical reference solutions, and the second part of this manual presents more complex examples intended for practical application. All the input data images and principal results for each problem are included in this manual for beginners' convenience. All the analyses are performed by using the FINAS Version 13.0. (author)

  17. Development of Inspection Technique for Socket Weld of Small Bore Piping in Nuclear Power Plant

    International Nuclear Information System (INIS)

    Yoon, Byungsik; Kim, Yongsik; Lee, Jeongseok

    2013-01-01

    The losses incurred by unplanned shutdowns are significant; consequently, early crack initiation and crack detection, including the detection of fillet weld manufacturing defects, is of the utmost importance. Current inspection techniques are not capable of reliably inspecting socket welds; therefore, new approaches are needed. The new technique must be sensitive to socket weld cracking, which usually initiates from the root, in order to detect the cracking during the early failure phase. In 2008, Kori unit 3 experienced leakage from the drain line socket weld of a steam generator. From this experience, KHNP enforced a management program to focus on enhancing the reliability of small bore socket weld piping inspections. Currently, conventional manual ultrasonic inspection techniques are used to detect service induced fatigue cracks. But there was uncertainty on manual ultrasonic inspection because of limited access to the welds and difficulties with contact between the ultrasonic probe and the OD surface of small bore piping. In this study, phased array ultrasonic inspection techniques are applied to increase inspection speed and reliability. Additionally a manually encoded scanner has been developed to enhance contact conditions and maintain constant signal quality. A phased array UT technique and system was developed to inspect small bore socket welds. The experimental results show all artificial flaws in the specimen were detected and measured. These experimental results show, that the newly developed inspection system, has improved the reliability and speed of small bore socket weld inspection. Based on these results, future works shall focus on additional experiments, with more realistic flaw responses. By applying this technique to the field, we expect that it can improve the integrity of small bore piping in nuclear power plants

  18. Peace Corps Aquaculture Training Manual. Training Manual T0057.

    Science.gov (United States)

    Peace Corps, Washington, DC. Information Collection and Exchange Div.

    This Peace Corps training manual was developed from two existing manuals to provide a comprehensive training program in fish production for Peace Corps volunteers. The manual encompasses the essential elements of the University of Oklahoma program that has been training volunteers in aquaculture for 25 years. The 22 chapters of the manual are…

  19. National spent fuel program preliminary report RCRA characteristics of DOE-owned spent nuclear fuel DOE-SNF-REP-002. Revision 3

    International Nuclear Information System (INIS)

    1995-07-01

    This report presents information on the preliminary process knowledge to be used in characterizing all Department of Energy (DOE)-owned Spent Nuclear Fuel (SNF) types that potentially exhibit a Resource Conservation and Recovery Act (RCRA) characteristic. This report also includes the process knowledge, analyses, and rationale used to preliminarily exclude certain SNF types from RCRA regulation under 40 CFR section 261.4(a)(4), ''Identification and Listing of Hazardous Waste,'' as special nuclear and byproduct material. The evaluations and analyses detailed herein have been undertaken as a proactive approach. In the event that DOE-owned SNF is determined to be a RCRA solid waste, this report provides general direction for each site regarding further characterization efforts. The intent of this report is also to define the path forward to be taken for further evaluation of specific SNF types and a recommended position to be negotiated and established with regional and state regulators throughout the DOE Complex regarding the RCRA-related policy issues

  20. Resource conversation and recovery act (RCRA) Contingency Plan for interim status or permitted units at the Oak Ridge Y-12 Plant

    International Nuclear Information System (INIS)

    1992-08-01

    The official mission of the Y-12 Plant is to serve as a manufacturing technology center for key processes such that capabilities are maintained for safe, secure, reliable, and survivable nuclear weapons systems and other applications of national importance. The Y-12 RCRA Contingency Plan will be reviewed and revised if necessary if the facility RCRA operating permits are revised, the plan is inadequate in an emergency, the procedures herein can be improved, the facility's operations change in a manner that alters the plan, the emergency coordinator changes, or the emergency equipment list changes. Copies of the Y-12 Emergency Management Plan are available at the Plant Shift Superintendent's Office and the Emergency Preparedness Office. This document serves to supplement the Y-12 Emergency Management Plan to be appropriate for all RCRA hazardous waste interim status or permitted treatment, storage, or disposal facilities. The 90-day storage areas at the Y-12 Plant have a separate contingency supplement as required by RCRA and are separate from this supplement

  1. National spent fuel program preliminary report RCRA characteristics of DOE-owned spent nuclear fuel DOE-SNF-REP-002. Revision 3

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-07-01

    This report presents information on the preliminary process knowledge to be used in characterizing all Department of Energy (DOE)-owned Spent Nuclear Fuel (SNF) types that potentially exhibit a Resource Conservation and Recovery Act (RCRA) characteristic. This report also includes the process knowledge, analyses, and rationale used to preliminarily exclude certain SNF types from RCRA regulation under 40 CFR {section}261.4(a)(4), ``Identification and Listing of Hazardous Waste,`` as special nuclear and byproduct material. The evaluations and analyses detailed herein have been undertaken as a proactive approach. In the event that DOE-owned SNF is determined to be a RCRA solid waste, this report provides general direction for each site regarding further characterization efforts. The intent of this report is also to define the path forward to be taken for further evaluation of specific SNF types and a recommended position to be negotiated and established with regional and state regulators throughout the DOE Complex regarding the RCRA-related policy issues.

  2. Annual report, RCRA post-closure monitoring and inspections for the mercury landfill hazardous waste trenches for the period October 1995--October 1996

    Energy Technology Data Exchange (ETDEWEB)

    Emer, D.F.; Smith, J.L.

    1997-01-01

    The Area 23 Hazardous Waste Trenches were closed in-place in September 1993. Post-closure monitoring of the Area 23 Hazardous Waste Trenches began in October 1993. The post-closure monitoring program is used to verify that the Area 23 Hazardous Waste Trench covers are performing properly, and that there is no water infiltrating into the waste trenches. The performance of the Area 23 Hazardous Waste Trenches is currently monitored using 30 neutron access tubes positioned on and along the margins of the covers. Soil moisture measurements are obtained in the soils directly beneath the trenches and compared to baseline conditions from the first year of post-closure operation. This report documents the post-closure activities between October 1995 and October 1996.

  3. Annual report, RCRA post-closure monitoring and inspections for the mercury landfill hazardous waste trenches for the period October 1995--October 1996

    International Nuclear Information System (INIS)

    Emer, D.F.; Smith, J.L.

    1997-01-01

    The Area 23 Hazardous Waste Trenches were closed in-place in September 1993. Post-closure monitoring of the Area 23 Hazardous Waste Trenches began in October 1993. The post-closure monitoring program is used to verify that the Area 23 Hazardous Waste Trench covers are performing properly, and that there is no water infiltrating into the waste trenches. The performance of the Area 23 Hazardous Waste Trenches is currently monitored using 30 neutron access tubes positioned on and along the margins of the covers. Soil moisture measurements are obtained in the soils directly beneath the trenches and compared to baseline conditions from the first year of post-closure operation. This report documents the post-closure activities between October 1995 and October 1996

  4. 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)

  5. Demonstration test of in-service inspection methods

    International Nuclear Information System (INIS)

    Takumi, Kenji

    1987-01-01

    The major objectives of the project are: (1) to demonstrate the reliability of a manual ultrasonic flaw detector and techniques that are used in operating light water reactor plants and (2) to demonstrate the performance and reliability of an automatic ultrasonic flaw detector that is designed to shorten the time required for ISI work and reduce the exposure risk of inspection personnel. The test project consists of three stages. In the first stage, which ended in 1982, defects were added intentionally to a model structure the same in size as a typical 1.1 million kW BWR plant and manual ultrasonic flaw detection tensting was performed. In the second stage, completed in 1984, automatic eddy-current flaw detection testing was carried out for defects in heat transfer piping of a PWP steam generator. In the third stage, which started in 1981 and ended in March 1987, a newly developed automatic ultrasonic flaw detector is applied to testing of defects used for the manual detector performance evaluation. Results have shown that the automatic eddy-current flaw detector under test has an adequately stable performance for practical uses, with a very high reproducibility to permit close inspection of secular deterioration in heat transfer pipes. It has also revealed that both the manual and automatic ultrasonic flaw detectors under test can detect all defects that do not comply with the ASME standards. (Nogami, K.)

  6. Overview of the software inspection process

    Energy Technology Data Exchange (ETDEWEB)

    Lane, G.L.; Dabbs, R. [Sandia National Labs., Albuquerque, NM (United States)

    1997-11-01

    This tutorial introduces attendees to the Inspection Process and teaches them how to organize and participate in a software inspection. The tutorial advocates the benefits of inspections and encourages attendees to socialize the inspection process in their organizations.

  7. SHARP User Manual

    Energy Technology Data Exchange (ETDEWEB)

    Yu, Y. Q. [Argonne National Lab. (ANL), Argonne, IL (United States); Shemon, E. R. [Argonne National Lab. (ANL), Argonne, IL (United States); Thomas, J. W. [Argonne National Lab. (ANL), Argonne, IL (United States); Mahadevan, Vijay S. [Argonne National Lab. (ANL), Argonne, IL (United States); Rahaman, Ronald O. [Argonne National Lab. (ANL), Argonne, IL (United States); Solberg, Jerome [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2016-03-31

    SHARP is an advanced modeling and simulation toolkit for the analysis of nuclear reactors. It is comprised of several components including physical modeling tools, tools to integrate the physics codes for multi-physics analyses, and a set of tools to couple the codes within the MOAB framework. Physics modules currently include the neutronics code PROTEUS, the thermal-hydraulics code Nek5000, and the structural mechanics code Diablo. This manual focuses on performing multi-physics calculations with the SHARP ToolKit. Manuals for the three individual physics modules are available with the SHARP distribution to help the user to either carry out the primary multi-physics calculation with basic knowledge or perform further advanced development with in-depth knowledge of these codes. This manual provides step-by-step instructions on employing SHARP, including how to download and install the code, how to build the drivers for a test case, how to perform a calculation and how to visualize the results. Since SHARP has some specific library and environment dependencies, it is highly recommended that the user read this manual prior to installing SHARP. Verification tests cases are included to check proper installation of each module. It is suggested that the new user should first follow the step-by-step instructions provided for a test problem in this manual to understand the basic procedure of using SHARP before using SHARP for his/her own analysis. Both reference output and scripts are provided along with the test cases in order to verify correct installation and execution of the SHARP package. At the end of this manual, detailed instructions are provided on how to create a new test case so that user can perform novel multi-physics calculations with SHARP. Frequently asked questions are listed at the end of this manual to help the user to troubleshoot issues.

  8. SHARP User Manual

    International Nuclear Information System (INIS)

    Yu, Y. Q.; Shemon, E. R.; Thomas, J. W.; Mahadevan, Vijay S.; Rahaman, Ronald O.; Solberg, Jerome

    2016-01-01

    SHARP is an advanced modeling and simulation toolkit for the analysis of nuclear reactors. It is comprised of several components including physical modeling tools, tools to integrate the physics codes for multi-physics analyses, and a set of tools to couple the codes within the MOAB framework. Physics modules currently include the neutronics code PROTEUS, the thermal-hydraulics code Nek5000, and the structural mechanics code Diablo. This manual focuses on performing multi-physics calculations with the SHARP ToolKit. Manuals for the three individual physics modules are available with the SHARP distribution to help the user to either carry out the primary multi-physics calculation with basic knowledge or perform further advanced development with in-depth knowledge of these codes. This manual provides step-by-step instructions on employing SHARP, including how to download and install the code, how to build the drivers for a test case, how to perform a calculation and how to visualize the results. Since SHARP has some specific library and environment dependencies, it is highly recommended that the user read this manual prior to installing SHARP. Verification tests cases are included to check proper installation of each module. It is suggested that the new user should first follow the step-by-step instructions provided for a test problem in this manual to understand the basic procedure of using SHARP before using SHARP for his/her own analysis. Both reference output and scripts are provided along with the test cases in order to verify correct installation and execution of the SHARP package. At the end of this manual, detailed instructions are provided on how to create a new test case so that user can perform novel multi-physics calculations with SHARP. Frequently asked questions are listed at the end of this manual to help the user to troubleshoot issues.

  9. Waste Inspection Tomography (WIT)

    International Nuclear Information System (INIS)

    Bernardi, R.T.

    1995-01-01

    Waste Inspection Tomography (WIT) provides mobile semi-trailer mounted nondestructive examination (NDE) and assay (NDA) for nuclear waste drum characterization. WIT uses various computed tomography (CT) methods for both NDE and NDA of nuclear waste drums. Low level waste (LLW), transuranic (TRU), and mixed radioactive waste can be inspected and characterized without opening the drums. With externally transmitted x-ray NDE techniques, WIT has the ability to identify high density waste materials like heavy metals, define drum contents in two- and three-dimensional space, quantify free liquid volumes through density and x-ray attenuation coefficient discrimination, and measure drum wall thickness. With waste emitting gamma-ray NDA techniques, WIT can locate gamma emitting radioactive sources in two- and three-dimensional space, identify gamma emitting isotopic species, identify the external activity levels of emitting gamma-ray sources, correct for waste matrix attenuation, provide internal activity approximations, and provide the data needed for waste classification as LLW or TRU. The mobile feature of WIT allows inspection technologies to be brought to the nuclear waste drum storage site without the need to relocate drums for safe, rapid, and cost-effective characterization of regulated nuclear waste. The combination of these WIT characterization modalities provides the inspector with an unprecedented ability to non-invasively characterize the regulated contents of waste drums as large as 110 gallons, weighing up to 1,600 pounds. Any objects that fit within these size and weight restrictions can also be inspected on WIT, such as smaller waste bags and drums that are five and thirty-five gallons

  10. Recurrent inspection of tubes

    International Nuclear Information System (INIS)

    Andersson, S.

    1984-01-01

    Recommendations concerning the selection of areas for the inspection of tubes have been outlined. The aim is to focus the control on the regions which are important for the safety and where damage is supposed to take place. The number of zones will depend on the risk factors as judged by experts. The localizing will be based upon probable damaging mechanisms. A certain number of areas should be chosen at random. (G.B.)

  11. Regulatory inspection in Spain

    International Nuclear Information System (INIS)

    Alvarez de Buergo, L.

    1977-01-01

    The 1964 Act on Nuclear Energy lays down that the Junta de Energia Nuclear is responsible for assessing the hazards of and inspecting nuclear power plants as well as for the transport of nuclear fuel for these plants. The Junta de Energia Nuclear has a specialised service, the Nuclear Safety Department in charge of performing these duties. Experience acquired from work in this field is analysed in this paper. (NEA) [fr

  12. Infrared microscope inspection apparatus

    Science.gov (United States)

    Forman, Steven E.; Caunt, James W.

    1985-02-26

    Apparatus and system for inspecting infrared transparents, such as an array of photovoltaic modules containing silicon solar cells, includes an infrared microscope, at least three sources of infrared light placed around and having their axes intersect the center of the object field and means for sending the reflected light through the microscope. The apparatus is adapted to be mounted on an X-Y translator positioned adjacent the object surface.

  13. OSE inspections: A different perspective

    International Nuclear Information System (INIS)

    Ware, J.H.

    1987-01-01

    The Office of Security Evaluation (OSE) is a staff activity of the Assistant Secretary for Defense Programs (ASDP) and is responsible for the conduct of an inspection and evaluation program. The OSE Inspection Division conducts assessments of the effectiveness of Department of Energy (DOE) Safeguards and Security policies and protection programs. The inspections are conducted by OSE Inspectors and Support Specialists. Prior to the author's participation in the inspection of the San Francisco Operations Office, a DOE Field Office employee had never played an active role in an OSE Inspection of another field office. This paper discloses his experience as an OSE Inspector

  14. 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.

  15. Analysis of Radiation Accident of Non-destructive Inspection and Rational Preparing Bills

    International Nuclear Information System (INIS)

    Bae, Junwoo; Yoo, Donghan; Kim, Hee Reyoung

    2013-01-01

    After 2006, according to enactment of Non-destructive Inspection Promotion Act, the number of non-destructive inspection companies and corresponding accident is increased sharply. In this research, it includes characteristic analysis of field of the non-destructive inspection. And from the result of analysis, the purpose of this research is discovering reason for 'Why there is higher accident ratio in non-destructive inspection field, relatively' and preparing effective bill for reducing radiation accidents. The number of worker for non-destructive inspect is increased steadily and non-destructive inspect worker take highest dose. Corresponding to these, it must be needed to prepare bills to protect non-destructive inspect workers. By analysis of accident case, there are many case of carelessness that tools are too heavy to carry it everywhere workers go. And there are some cases caused by deficiency of education that less understanding of radiation and poor operation by less understanding of structure of tools. Also, there is no data specialized to non-destructive inspect field. So, it has to take information from statistical data. Because of this, it is hard to analyze nondestructive inspect field accurately. So, it is required to; preparing rational bills to protect non-destructive inspect workers nondestructive inspect instrument lightening and easy manual which can understandable for low education background people accurate survey data from real worker. To accomplish these, we needs to do; analyze and comprehend the present law about non-destructive inspect worker understand non-destructive inspect instruments accurately and conduct research for developing material developing rational survey to measuring real condition for non-destructive inspect workers

  16. Phase 1 RCRA Facility Investigation/Corrective Measures Study Work Plan for Single-Shell Tank (SST) Waste Management Areas

    International Nuclear Information System (INIS)

    MCCARTHY, M.M.

    1999-01-01

    This document is the master work plan for the Resource Conservation and Recovery Act of 1976 (RCRA) Corrective Action Program (RCAP) for single-shell tank (SST) farms at the US. Department of Energy's (DOE'S) Hanford Site. The DOE Office of River Protection (ORP) initiated the RCAP to address the impacts of past and potential future tank waste releases to the environment. This work plan defines RCAP activities for the four SST waste management areas (WMAs) at which releases have contaminated groundwater. Recognizing the potential need for future RCAP activities beyond those specified in this master work plan, DOE has designated the currently planned activities as ''Phase 1.'' If a second phase of activities is needed for the WMAs addressed in Phase 1, or if releases are detected at other SST WMAs, this master work plan will be updated accordingly

  17. RCRA Facility Investigation/Remedial Investigation Report for Gunsite 720 Rubble Pit Unit (631-16G) - March 1996

    Energy Technology Data Exchange (ETDEWEB)

    Palmer, E. [Westinghouse Savannah River Company, AIKEN, SC (United States)

    1996-03-01

    Gunsite 720 Rubble Pit Unit is located on the west side of SRS. In the early to mid 1980`s, while work was being performed in this area, nine empty, partially buried drums, labeled `du Pont Freon 11`, were found. As a result, Gunsite 720 became one of the original waste units specified in the SRS RCRA Facility Assessment (RFA). The drums were excavated on July 30, 1987 and placed on a pallet at the unit. Both the drums and pallet were removed and disposed of in October 1989. The area around the drums was screened during the excavation and the liquid (rainwater) that collected in the excavated drums was sampled prior to disposal. No evidence of hazardous materials was found. Based on the review of the analytical data and screening techniques used to evaluate all the chemicals of potential concern at Gunsite 720 Rubble Pit Unit, it is recommended that no further remedial action be performed at this unit.

  18. RCRA Facility Investigation/Remedial Investigation Report for Gunsite 720 Rubble Pit Unit (631-16G) - March 1996

    International Nuclear Information System (INIS)

    Palmer, E.

    1996-03-01

    Gunsite 720 Rubble Pit Unit is located on the west side of SRS. In the early to mid 1980's, while work was being performed in this area, nine empty, partially buried drums, labeled 'du Pont Freon 11', were found. As a result, Gunsite 720 became one of the original waste units specified in the SRS RCRA Facility Assessment (RFA). The drums were excavated on July 30, 1987 and placed on a pallet at the unit. Both the drums and pallet were removed and disposed of in October 1989. The area around the drums was screened during the excavation and the liquid (rainwater) that collected in the excavated drums was sampled prior to disposal. No evidence of hazardous materials was found. Based on the review of the analytical data and screening techniques used to evaluate all the chemicals of potential concern at Gunsite 720 Rubble Pit Unit, it is recommended that no further remedial action be performed at this unit

  19. 75 FR 984 - Draft Recommended Interim Preliminary Remediation Goals for Dioxin in Soil at CERCLA and RCRA Sites

    Science.gov (United States)

    2010-01-07

    ...The Environmental Protection Agency (EPA or the Agency) is announcing a 50-day public comment period for draft recommended interim preliminary remediation goals (PRGs) developed in the Draft Recommended Interim Preliminary Remediation Goals for Dioxin in Soil at Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) and Resource Conservation and Recovery Act (RCRA) Sites. EPA's Office of Solid Waste and Emergency and Emergency Response (OSWER) has developed the draft recommended interim PRGs for dioxin in soil. These draft recommended interim PRGs were calculated using existing, peer- reviewed toxicity values and current EPA equations and default exposure assumptions. This Federal Register notice is intended to provide an opportunity for public comment on the draft recommended interim PRGs. EPA will consider any public comments submitted in accordance with this notice and may revise the draft recommended interim PRGs thereafter.

  20. Phase 1 RCRA Facility Investigation & Corrective Measures Study Work Plan for Single Shell Tank (SST) Waste Management Areas

    Energy Technology Data Exchange (ETDEWEB)

    MCCARTHY, M.M.

    1999-08-01

    This document is the master work plan for the Resource Conservation and Recovery Act of 1976 (RCRA) Corrective Action Program (RCAP) for single-shell tank (SST) farms at the US. Department of Energy's (DOE'S) Hanford Site. The DOE Office of River Protection (ORP) initiated the RCAP to address the impacts of past and potential future tank waste releases to the environment. This work plan defines RCAP activities for the four SST waste management areas (WMAs) at which releases have contaminated groundwater. Recognizing the potential need for future RCAP activities beyond those specified in this master work plan, DOE has designated the currently planned activities as ''Phase 1.'' If a second phase of activities is needed for the WMAs addressed in Phase 1, or if releases are detected at other SST WMAs, this master work plan will be updated accordingly.

  1. Molten salt oxidation of mixed wastes: Separation of radioactive materials and Resource Conservation and Recovery Act (RCRA) materials

    International Nuclear Information System (INIS)

    Bell, J.T.; Haas, P.A.; Rudolph, J.C.

    1993-01-01

    The Oak Ridge National Laboratory (ORNL) is involved in a program to apply a molten salt oxidation (MSO) process to the treatment of mixed wastes at Oak Ridge and other Department of Energy (DOE) sites. Mixed wastes are defined as those wastes that contain both radioactive components, which are regulated by the atomic energy legislation, and hazardous waste components, which are regulated under the Resource Conservation and Recovery Act (RCRA). A major part of our ORNL program involves the development of separation technologies that are necessary for the complete treatment of mixed wastes. The residues from the MSO treatment of the mixed wastes must be processed further to separate the radioactive components, to concentrate and recycle residues, or to convert the residues into forms acceptable for final disposal. This paper is a review of the MSO requirements for separation technologies, the information now available, and the concepts for our development studies

  2. Pressurized water reactor inspection procedures

    International Nuclear Information System (INIS)

    Heinrich, D.; Mueller, G.; Otte, H.J.; Roth, W.

    1998-01-01

    Inspections of the reactor pressure vessels of pressurized water reactors (PWR) so far used to be carried out with different central mast manipulators. For technical reasons, parallel inspections of two manipulators alongside work on the refueling cavity, so as to reduce the time spent on the critical path in a revision outage, are not possible. Efforts made to minimize the inspection time required with one manipulator have been successful, but their effects are limited. Major reductions in inspection time can be achieved only if inspections are run with two manipulators in parallel. The decentralized manipulator built by GEC Alsthom Energie and so far emmployed in boiling water reactors in the USA, Spain, Switzerland and Japan allows two systems to be used in parallel, thus reducing the time required for standard inspection of a pressure vessel from some six days to three days. These savings of approximately three days are made possible without any compromises in terms of positioning by rail-bound systems. During inspection, the reactor refueling cavity is available for other revision work without any restrictions. The manipulator can be used equally well for inspecting standard PWR, PWR with a thermal shield, for inspecting the land between in-core instrumentation nozzles, BWR with and without jet pumps (complementary inspection), and for inspecting core support shrouds. (orig.) [de

  3. Identification, classification and management of industrial waste in Kavir steel complex according to the Bazel convention and RCRA

    Directory of Open Access Journals (Sweden)

    Mohammad Hasan Ehrampoush

    2016-06-01

    Full Text Available Introduction: Requiring industries for implementing industrial waste management programs and planning for proper waste disposal is essential in order to achieve sustainable development. Therefore, industrial waste management program was done in Kavir Steel Complex, in Aran va Bidgol region to identify and classify industrial waste and also to present solutions for improving waste management. In this complex, production process is hot rolling steel and the product is rebar. Material and Method: The preset study was conducted in Kavir Steel Complex. Following survey of production process and sources of waste, the type and volume of produced waste were identified and measured during 3 months. Then, the classification of wastes was done according to the Bazel Convention and Resource Conservation and Recovery Act (RCRA, and finally new industrial & health solid waste management program was presented. Result: Considering the volume, industrial waste of production process in Kavir Steel Complex was between 130 to 180 grams per each ton of rebar. Main industrial waste included oxide of steel billet, industrial sludge, used oil and lubricant which were classified according to the RCRA: 8 materials with T code, 1 with C code, 5 with I code and 3 materials with C code. Conclusion: The results revealed that the most amount of industrial waste in Kavir Steel Complex is the waste of steel billet and industrial sludge, and more than 90% of Kavir steel industrial waste were reused and recycled inside or outside of this complex. It is recommended that used oil to be transport and maintain in the safe containers.

  4. Aircraft operations management manual

    Science.gov (United States)

    1992-01-01

    The NASA aircraft operations program is a multifaceted, highly diverse entity that directly supports the agency mission in aeronautical research and development, space science and applications, space flight, astronaut readiness training, and related activities through research and development, program support, and mission management aircraft operations flights. Users of the program are interagency, inter-government, international, and the business community. This manual provides guidelines to establish policy for the management of NASA aircraft resources, aircraft operations, and related matters. This policy is an integral part of and must be followed when establishing field installation policy and procedures covering the management of NASA aircraft operations. Each operating location will develop appropriate local procedures that conform with the requirements of this handbook. This manual should be used in conjunction with other governing instructions, handbooks, and manuals.

  5. EML procedures manual

    International Nuclear Information System (INIS)

    Volchok, H.L.; de Planque, G.

    1982-01-01

    This manual contains the procedures that are used currently by the Environmental Measurements Laboratory of the US Department of Energy. In addition a number of analytical methods from other laboratories have been included. These were tested for reliability at the Battelle, Pacific Northwest Laboratory under contract with the Division of Biomedical and Environmental Research of the AEC. These methods are clearly distinguished. The manual is prepared in loose leaf form to facilitate revision of the procedures and inclusion of additional procedures or data sheets. Anyone receiving the manual through EML should receive this additional material automatically. The contents are as follows: (1) general; (2) sampling; (3) field measurements; (4) general analytical chemistry; (5) chemical procedures; (6) data section; (7) specifications

  6. Nuclear material operations manual

    International Nuclear Information System (INIS)

    Tyler, R.P.

    1981-02-01

    This manual provides a concise and comprehensive documentation of the operating procedures currently practiced at Sandia National Laboratories with regard to the management, control, and accountability of nuclear materials. The manual is divided into chapters which are devoted to the separate functions performed in nuclear material operations-management, control, accountability, and safeguards, and the final two chapters comprise a document which is also issued separately to provide a summary of the information and operating procedures relevant to custodians and users of radioactive and nuclear materials. The manual also contains samples of the forms utilized in carrying out nuclear material activities. To enhance the clarity of presentation, operating procedures are presented in the form of playscripts in which the responsible organizations and necessary actions are clearly delineated in a chronological fashion from the initiation of a transaction to its completion

  7. Salinas : theory manual.

    Energy Technology Data Exchange (ETDEWEB)

    Walsh, Timothy Francis; Reese, Garth M.; Bhardwaj, Manoj Kumar

    2011-11-01

    Salinas provides a massively parallel implementation of structural dynamics finite element analysis, required for high fidelity, validated models used in modal, vibration, static and shock analysis of structural systems. This manual describes the theory behind many of the constructs in Salinas. For a more detailed description of how to use Salinas, we refer the reader to Salinas, User's Notes. Many of the constructs in Salinas are pulled directly from published material. Where possible, these materials are referenced herein. However, certain functions in Salinas are specific to our implementation. We try to be far more complete in those areas. The theory manual was developed from several sources including general notes, a programmer notes manual, the user's notes and of course the material in the open literature.

  8. Nuclear material operations manuals

    International Nuclear Information System (INIS)

    Tyler, R.P.

    1979-06-01

    This manual is intended to provide a concise and comprehensive documentation of the operating procedures currently practiced at Sandia Laboratories with regard to the management, control, and accountability of radioactive and nuclear materials. The manual is divided into chapters which are devoted to the separate functions performed in nuclear material operations-management, control, accountability, and safeguards, and the final two chapters comprise a document which is also issued separately to provide a summary of the information and operating procedures relevant to custodians and users of radioactive and nuclear materials. The manual also contains samples of the forms utilized in carrying out nuclear material activities. To enhance the clarity of presentation, operating procedures are presented in the form of playscripts in which the responsible organizations and necessary actions are clearly delineated in a chronological fashion from the initiation of a transaction to its completion

  9. Nuclear material operations manual

    International Nuclear Information System (INIS)

    Tyler, R.P.; Gassman, L.D.

    1978-04-01

    This manual is intended to provide a concise and comprehensive documentation of the operating procedures currently practiced at Sandia Laboratories with regard to the management, control, and accountability of radioactive and nuclear materials. The manual is divided into chapters which are devoted to the separate functions performed in nuclear material operations--management, control, accountability, and safeguards, and the final two chapters comprise a document which is also issued separately to provide a summary of the information and operating procedures relevant to custodians and users of radioactive and nuclear materials. The manual also contains samples of the forms utilized in carrying out nuclear material activities. To enhance the clarity of presentation, operating procedures are presented in the form of ''play-scripts'' in which the responsible organizations and necessary actions are clearly delineated in a chronological fashion from the initiation of a transaction to its completion

  10. MANUAL LOGIC CONTROLLER (MLC)

    OpenAIRE

    Claude Ziad Bayeh

    2015-01-01

    The “Manual Logic Controller” also called MLC, is an electronic circuit invented and designed by the author in 2008, in order to replace the well known PLC (Programmable Logic Controller) in many applications for its advantages and its low cost of fabrication. The function of the MLC is somewhat similar to the well known PLC, but instead of doing it by inserting a written program into the PLC using a computer or specific software inside the PLC, it will be manually programmed in a manner to h...

  11. Beyond the Manual Channel

    DEFF Research Database (Denmark)

    , the main focus there is on spoken languages in their written and spoken forms. This series of workshops, however, offers a forum for researchers focussing on sign languages. For the fourth time, the workshop had sign language corpora as its main topic. This time, the focus was on any aspect beyond...... the manual channel. Not surprisingly, most papers deal with non-manuals on the face. Once again, the papers at this workshop clearly identify the potentials of even closer cooperation between sign linguists and sign language engineers, and we think it is events like this that contribute a lot to a better...

  12. Radar and ARPA manual

    CERN Document Server

    Bole, A G

    2013-01-01

    Radar and ARPA Manual focuses on the theoretical and practical aspects of electronic navigation. The manual first discusses basic radar principles, including principles of range and bearing measurements and picture orientation and presentation. The text then looks at the operational principles of radar systems. Function of units; aerial, receiver, and display principles; transmitter principles; and sitting of units on board ships are discussed. The book also describes target detection, Automatic Radar Plotting Aids (ARPA), and operational controls of radar systems, and then discusses radar plo

  13. TRUBA User Manual

    Energy Technology Data Exchange (ETDEWEB)

    Tereshchenko, M. A.; Castejon, F.; Cappa, A.

    2008-04-25

    The TRUBA (pipeline in Russian) code is a computational tool for studying the propagation of Gaussian-shaped microwave beams in a prescribed equilibrium plasma. This manual covers the basic material handed to use the implementation of TRUBA (version 3,4) interfaced with the numerical library of the TJ-II stellarator. The manual provides a concise theoretical background of the problem, specifications for setting up the input files and interpreting the output of the code, and some information useful in modifying TRUBA. (Author) 13 refs.

  14. TRUBA User Manual

    International Nuclear Information System (INIS)

    Tereshchenko, M. A.; Castejon, F.; Cappa, A.

    2008-01-01

    The TRUBA (pipeline in Russian) code is a computational tool for studying the propagation of Gaussian-shaped microwave beams in a prescribed equilibrium plasma. This manual covers the basic material handed to use the implementation of TRUBA (version 3,4) interfaced with the numerical library of the TJ-II stellarator. The manual provides a concise theoretical background of the problem, specifications for setting up the input files and interpreting the output of the code, and some information useful in modifying TRUBA. (Author) 13 refs

  15. Netbooks The Missing Manual

    CERN Document Server

    Biersdorfer, J

    2009-01-01

    Netbooks are the hot new thing in PCs -- small, inexpensive laptops designed for web browsing, email, and working with web-based programs. But chances are you don't know how to choose a netbook, let alone use one. Not to worry: with this Missing Manual, you'll learn which netbook is right for you and how to set it up and use it for everything from spreadsheets for work to hobbies like gaming and photo sharing. Netbooks: The Missing Manual provides easy-to-follow instructions and lots of advice to help you: Learn the basics for using a Windows- or Linux-based netbookConnect speakers, printe

  16. Security electronics circuits manual

    CERN Document Server

    MARSTON, R M

    1998-01-01

    Security Electronics Circuits Manual is an invaluable guide for engineers and technicians in the security industry. It will also prove to be a useful guide for students and experimenters, as well as providing experienced amateurs and DIY enthusiasts with numerous ideas to protect their homes, businesses and properties.As with all Ray Marston's Circuits Manuals, the style is easy-to-read and non-mathematical, with the emphasis firmly on practical applications, circuits and design ideas. The ICs and other devices used in the practical circuits are modestly priced and readily available ty

  17. RELAP-7 Theory Manual

    Energy Technology Data Exchange (ETDEWEB)

    Berry, Ray Alden [Idaho National Lab. (INL), Idaho Falls, ID (United States); Zou, Ling [Idaho National Lab. (INL), Idaho Falls, ID (United States); Zhao, Haihua [Idaho National Lab. (INL), Idaho Falls, ID (United States); Zhang, Hongbin [Idaho National Lab. (INL), Idaho Falls, ID (United States); Peterson, John William [Idaho National Lab. (INL), Idaho Falls, ID (United States); Martineau, Richard Charles [Idaho National Lab. (INL), Idaho Falls, ID (United States); Kadioglu, Samet Yucel [Idaho National Lab. (INL), Idaho Falls, ID (United States); Andrs, David [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2016-03-01

    This document summarizes the physical models and mathematical formulations used in the RELAP-7 code. In summary, the MOOSE based RELAP-7 code development is an ongoing effort. The MOOSE framework enables rapid development of the RELAP-7 code. The developmental efforts and results demonstrate that the RELAP-7 project is on a path to success. This theory manual documents the main features implemented into the RELAP-7 code. Because the code is an ongoing development effort, this RELAP-7 Theory Manual will evolve with periodic updates to keep it current with the state of the development, implementation, and model additions/revisions.

  18. 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...

  19. 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.

  20. Safeguards management inspection procedures

    International Nuclear Information System (INIS)

    Barth, M.J.; Dunn, D.R.

    1984-08-01

    The objective of this inspection module is to independently assess the contributions of licensee management to overall safeguards systems performance. The inspector accomplishes this objective by comparing the licensee's safeguards management to both the 10 CFR, parts 70 and 73, requirements and to generally accepted management practices. The vehicle by which this comparison is to be made consists of assessment questions and key issues which point the inspector to areas of primary concern to the NRC and which raise additional issues for the purpose of exposing management ineffectiveness. Further insight into management effectiveness is obtained through those assessment questions specifically directed toward the licensee's safeguards system performance. If the quality of the safeguards is poor, then the inspector should strongly suspect that management's role is ineffective and should attempt to determine management's influence (or lack thereof) on the underlying safeguards deficiencies. (The converse is not necessarily true, however.) The assessment questions in essence provide an opportunity for the inspector to identify, to single out, and to probe further, questionable management practices. Specific issues, circumstances, and concerns which point to questionable or inappropriate practices should be explicitly identified and referenced against the CFR and the assessment questions. The inspection report should also explain why the inspector feels certain management practices are poor, counter to the CFR, and/or point to ineffecive management. Concurrent with documenting the inspection results, the inspector should provide recommendations for alleviating observed management practices that are detrimental to effective safeguards. The recommendations could include: specific changes in the practices of the licensee, followup procedures on the part of NRC, and proposed license changes

  1. 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

  2. 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.

  3. Development of the radiation inspection system for food materials

    Energy Technology Data Exchange (ETDEWEB)

    Min, Sujung; Kim, Heeyoung; Kim, Myungjin; Lee, Unjang [ORIONENC Co., Seoul (Korea, Republic of)

    2015-10-15

    Radioactive contamination of processed foodstuffs, livestock, marine products, farm products imported from Japan and fishes caught in coastal waters of Korea has become an important social issue. Recently, there are also needs of inspection system for monitoring of public meals such like school feedings of kindergarten, elementary school, middle school, high school and university. Radioactivity inspections of those foods are executed manually with portable measuring instruments or at labs using their samples. But, radioactivity inspections of those foods should execute field survey in real time. In consequence, there are some problem of time delay and low reliability. To protect the health of citizens from radioactivity contained in Japanese marine products imported to Korea, a system to inspect radioactivity in real time is developed. The system is to measure the radioactivity level of farm and marine products and public meals continuously and automatically at inspection sites of an agency checking radiation of imported foodstuffs to determine radioactive contamination. Performance was identified through the performance test (Cs-137 30, 50, 300, 900Bq/kg) at Korea Research Institute of Standards and Science (KRISS). NaI(Tl) detector was satisfied the performance for measurement.

  4. Computer-aided ultrasonic inspection of steam turbine rotors

    Energy Technology Data Exchange (ETDEWEB)

    Mayer, K.H.; Weber, M.; Weiss, M. [GEC ALSTHOM Energie GmbH, Nuremberg (Germany)

    1998-12-31

    As the output and economic value of power plants increase, the detection and sizing of the type of flaws liable to occur in the rotors of turbines using ultrasonic methods assumes increasing importance. An ultrasonic inspection carried out at considerable expense is expected to bring to light all safety-relevant flaws and to enable their size to be determined so as to permit a fracture-mechanics analysis to assess the reliability of the rotor under all possible stresses arising in operation with a high degree of accuracy. The advanced computer-aided ultrasonic inspection of steam turbine rotors have improved reliability, accuracy and reproducibility of ultrasonic inspection. Further, there has been an improvement in the resolution of resolvable group indications by applying reconstruction and imagine methods. In general, it is also true for the advanced computer-aided ultrasonic inspection methods that, in the case of flaw-affected forgings, automated data acquisition provides a substantial rationalization and a significant documentation of the results for the fracture mechanics assessment compared to manual inspection. (orig.) 8 refs.

  5. Computer-aided ultrasonic inspection of steam turbine rotors

    Energy Technology Data Exchange (ETDEWEB)

    Mayer, K H; Weber, M; Weiss, M [GEC ALSTHOM Energie GmbH, Nuremberg (Germany)

    1999-12-31

    As the output and economic value of power plants increase, the detection and sizing of the type of flaws liable to occur in the rotors of turbines using ultrasonic methods assumes increasing importance. An ultrasonic inspection carried out at considerable expense is expected to bring to light all safety-relevant flaws and to enable their size to be determined so as to permit a fracture-mechanics analysis to assess the reliability of the rotor under all possible stresses arising in operation with a high degree of accuracy. The advanced computer-aided ultrasonic inspection of steam turbine rotors have improved reliability, accuracy and reproducibility of ultrasonic inspection. Further, there has been an improvement in the resolution of resolvable group indications by applying reconstruction and imagine methods. In general, it is also true for the advanced computer-aided ultrasonic inspection methods that, in the case of flaw-affected forgings, automated data acquisition provides a substantial rationalization and a significant documentation of the results for the fracture mechanics assessment compared to manual inspection. (orig.) 8 refs.

  6. Development of the radiation inspection system for food materials

    International Nuclear Information System (INIS)

    Min, Sujung; Kim, Heeyoung; Kim, Myungjin; Lee, Unjang

    2015-01-01

    Radioactive contamination of processed foodstuffs, livestock, marine products, farm products imported from Japan and fishes caught in coastal waters of Korea has become an important social issue. Recently, there are also needs of inspection system for monitoring of public meals such like school feedings of kindergarten, elementary school, middle school, high school and university. Radioactivity inspections of those foods are executed manually with portable measuring instruments or at labs using their samples. But, radioactivity inspections of those foods should execute field survey in real time. In consequence, there are some problem of time delay and low reliability. To protect the health of citizens from radioactivity contained in Japanese marine products imported to Korea, a system to inspect radioactivity in real time is developed. The system is to measure the radioactivity level of farm and marine products and public meals continuously and automatically at inspection sites of an agency checking radiation of imported foodstuffs to determine radioactive contamination. Performance was identified through the performance test (Cs-137 30, 50, 300, 900Bq/kg) at Korea Research Institute of Standards and Science (KRISS). NaI(Tl) detector was satisfied the performance for measurement

  7. Acoustic inspection device

    Energy Technology Data Exchange (ETDEWEB)

    Diaz, Aaron A.; Burghard, Brion J.; Skorpik, James R.; Pappas, Richard A.; Mullen, O. Dennis; Samuel, Todd J.; Reid, Larry D.; Harris, Joe C.; Valencia, Juan D.; Smalley, Jonathan T.; Shepard, Chester L.; Taylor, Theodore T.

    2005-09-06

    An ultrasound inspection apparatus particularly adapted to examine containers (sealed or unsealed) containing a liquid or solid bulk material. The apparatus has an overall configuration of a hand held pistol with a front transducer contact surface that is positioned against a front wall of the container. An ultrasound pulse is transmitted from the apparatus to be reflected from a back wall of a container being investigated. The received echo pulse is converted to a digital waveform. The waveform is analyzed relative to temperature, travel distance of the pulse(s), and time of travel to ascertain characteristics of the liquid or other materials and to provide identification of the same.

  8. Regulatory inspection of the implementation of quality assurance programmes

    International Nuclear Information System (INIS)

    1989-01-01

    This Manual provides guidance to Member States in the organization and performance of their regulatory inspection functions regarding the implementation of nuclear power plant quality assurance programmes. It addresses the interface between, and is consistent with, the IAEA Nuclear Safety Standards (NUSS programme) documents on quality assurance and governmental organization. The Manual offers a practical model and examples for performing regulatory inspections to ensure that the quality assurance programme is operating satisfactorily in the siting, design, manufacturing, construction, commissioning, operation and decommissioning of nuclear power plants. The primary objective is to confirm that the licensee has the capability to manage and control the effective performance of all quality assurance responsibilities during all phases of a nuclear power project. The guidance provided through this Manual for proper establishment and execution of the regulatory inspections helps to enforce the effective implementation of the quality assurance programme as a management control system that the nuclear industry should establish and use in attaining the safety and reliability objectives for nuclear installations. This enforcement action by national regulatory bodies and the emphasis on the purposes and advantages of quality assurance as an important management tool integrated within the total project task have been recommended by the IAEA International Nuclear Safety Advisory Group (INSAG). The primary intended users of this Manual are the management personnel and high level staff from regulatory bodies but it will also be helpful to management personnel from nuclear utilities and vendors. They all are inevitable partners in a nuclear power project and this document offers all of them valuable information on the better accomplishment of quality assurance activities to ensure the common objective of safe and reliable nuclear power production

  9. 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)

  10. INSPECT: a package of computer programs for planning safeguards inspections

    International Nuclear Information System (INIS)

    Wincek, M.A.; Mullen, M.F.

    1979-04-01

    As part of the U.S. program to provide technical assistance to the International Atomic Energy Agency, a package of computer programs was developed for use in planning safeguards inspections of various types of nuclear facilities. The INSPECT software package is a set of five interactive FORTRAN programs which can be used to calculate the variance components of the MUF (Material Unaccounted For) statistic, the variance components of the D (difference) statistic, attribute and variables sampling plans, a measure of the effectiveness of the inspection, and a measurement of the cost of implementing the inspection plan. This report describes the programs and explains how to use them

  11. 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

  12. IFSS: The IAEA's inspection field support system

    International Nuclear Information System (INIS)

    Muller, R.; Heinonen, O.J.; Schriefer, D.

    1990-01-01

    Recently, highly automated nuclear facilities with enormous volumes of nuclear material accounting data have come into operation. A few others will become operational shortly. Analysis and verification of the data for safeguards purposes is manageable only with improved computer support in the field. To assist its safeguards inspectors, the IAEA has developed the Inspection Field Support System (IFSS). It allows safeguards inspectors to collect, maintain, analyse, and evaluate inspection data on site at nuclear facilities. Previously, field computer support to safeguards inspectors concentrated on providing measurement instrumentation with data storage, but data analysis capabilities were elementary. Also, generic statistical tools were available to handle data that inspectors could (usually manually) input into a computer. Electronic links between these two directions were rudimentary. IFSS integrates the data required for verification and accounting so that inspectors will be able to devote more time to measurements and to derive conclusions at the site in a more timely manner. The system operates on stationary personal computers as well as on portable ones. Its introduction reflects the IAEA Department of Safeguards determination to further improve operational efficiency. It should be emphasized that IFSS implementation is still under development. Several field installations have been made to obtain practical experience and to determine the system's effectiveness

  13. A novel visual pipework inspection system

    Science.gov (United States)

    Summan, Rahul; Jackson, William; Dobie, Gordon; MacLeod, Charles; Mineo, Carmelo; West, Graeme; Offin, Douglas; Bolton, Gary; Marshall, Stephen; Lille, Alexandre

    2018-04-01

    The interior visual inspection of pipelines in the nuclear industry is a safety critical activity conducted during outages to ensure the continued safe and reliable operation of plant. Typically, the video output by a manually deployed probe is viewed by an operator looking to identify and localize surface defects such as corrosion, erosion and pitting. However, it is very challenging to estimate the nature and extent of defects by viewing a large structure through a relatively small field of view. This work describes a new visual inspection system employing photogrammetry using a fisheye camera and a structured light system to map the internal geometry of pipelines by generating a photorealistic, geometrically accurate surface model. The error of the system output was evaluated through comparison to a ground truth laser scan (ATOS GOM Triple Scan) of a nuclear grade split pipe sample (stainless steel 304L, 80mm internal diameter) containing defects representative of the application - the error was found to be submillimeter across the sample.

  14. Latest developments in on- and off-line inspection of bank notes during production

    Science.gov (United States)

    Brown, Stephen C.

    2004-06-01

    The inspection of bank notes is a highly labour intensive process where traditionally every note on every sheet is inspected manually. However with the advent of more and more sophisticated security features, both visible and invisible, and the requirement of cost reduction in the printing process, it is clear that automation is required. Machines for the automatic inspection of bank notes have been on the market for the past 10 to 12 years, but recent developments in technology have enabled a new generation of detectors and machines to be developed. This paper focuses on the latest developments in both the off-line and on-line inspection of bank notes covering not only the visible spectrum but also a new range of detectors for inspection some of the more common invisible features used as covert features in today's bank notes.

  15. Activities for turbine maintenance: planning, implementation and evaluation of inspection results

    International Nuclear Information System (INIS)

    Azcue, J.; Sanchez, M. A.; Alvaro, M.

    2014-01-01

    The article will cover the most significant aspects of how Tecnatom carry out the turbine maintenance work, both from the point of view of the inspection itself as the pre-and post tasks associated. Thus, the issues that will be part of the article are the Manual Inspection Service (MISI) and the inspection database, ISI WEB. These tools are essential for planning field work and serve as a guide to run later turbine inspections in different plants. Following this introduction the inspection teams and the techniques used by Tecnatom will be described. finally, the article will contain a small mention about management studies of life and integrity analysis of the turbine that can be performed, as well as involvement in its safe operation that is derived from them. Ultimately, the intention is to provide a comprehensive approach to the issue in question, the turbine maintenance work, so that the reader can get an ideal of the whole process. (Author)

  16. Enhanced defect of interest [DOI] monitoring by utilizing sensitive inspection and ADRTrue SEM review

    Science.gov (United States)

    Kirsch, Remo; Zeiske, Ulrich; Shabtay, Saar; Beyer, Mirko; Yerushalmi, Liran; Goshen, Oren

    2011-03-01

    As semiconductor process design rules continue to shrink, the ability of optical inspection tools to separate between true defects and nuisance becomes more and more difficult. Therefore, monitoring Defect of Interest (DOI) become a real challenge (Figure 1). This phenomenon occurs due to the lower signal received from real defects while noise levels remain almost the same, resulting in inspection high nuisance rate, which jeopardizes the ability to provide a meaningful, true defect Pareto. A non-representative defect Pareto creates a real challenge to a reliable process monitoring (Figure 4). Traditionally, inspection tool recipes were optimized to keep data load at a manageable level and provide defect maps with ~10% nuisance rate, but as defects of interest get smaller with design rule shrinkage, this requirement results in a painful compromise in detection sensitivity. The inspection is usually followed by defect review and classification using scanning electron microscope (SEM), the classification done manually and it is performed on a small sample of the inspection defect map due to time and manual resources limitations. Sample is usually 50~60 randomly selected locations, review is performed manually most of the times, and manual classification is performed for all the reviewed locations. In the approach described in this paper, the inspection tool recipe is optimized for sensitivity rather than low nuisance rate (i.e. detect all DOI with compromising on a higher nuisance rate). Inspection results with high nuisance rate introduce new challenges for SEM review methodology & tools. This paper describe a new approach which enhances process monitoring quality and the results of collaborative work of the Process Diagnostic & Control Business Unit of Applied Materials® and GLOBALFOUNDRIES® utilizing Applied Materials ADRTrueTM & SEMVisionTM capabilities. The study shows that the new approach reveals new defect types in the Pareto, and improves the ability to

  17. Nuclear electronics laboratory manual

    International Nuclear Information System (INIS)

    1984-05-01

    The Nuclear Electronics Laboratory Manual is a joint product of several electronics experts who have been associated with IAEA activity in this field for many years. The manual does not include experiments of a basic nature, such as characteristics of different active electronics components. It starts by introducing small electronics blocks, employing one or more active components. The most demanding exercises instruct a student in the design and construction of complete circuits, as used in commercial nuclear instruments. It is expected that a student who completes all the experiments in the manual should be in a position to design nuclear electronics units and also to understand the functions of advanced commercial instruments which need to be repaired or maintained. The future tasks of nuclear electronics engineers will be increasingly oriented towards designing and building the interfaces between a nuclear experiment and a computer. The manual pays tribute to this development by introducing a number of experiments which illustrate the principles and the technology of interfacing

  18. General Drafting. Technical Manual.

    Science.gov (United States)

    Department of the Army, Washington, DC.

    The manual provides instructional guidance and reference material in the principles and procedures of general drafting and constitutes the primary study text for personnel in drafting as a military occupational specialty. Included is information on drafting equipment and its use; line weights, conventions and formats; lettering; engineering charts…

  19. Manual for subject analysis

    International Nuclear Information System (INIS)

    2002-01-01

    This document is one in a series of publications known as the ETDE/INIS Joint Reference Series and also constitutes a part of the ETDE Procedures Manual. It presents the rules, guidelines and procedures to be adopted by centers submitting input to the International Nuclear Information System (INIS) or the Energy Technology Data Exchange (ETDE). It is a manual for the subject analysis part of input preparation, meaning the selection, subject classification, abstracting and subject indexing of relevant publications, and is to be used in conjunction with the Thesauruses, Subject Categories documents and the documents providing guidelines for the preparation of abstracts. The concept and structure of the new manual are intended to describe in a logical and efficient sequence all the steps comprising the subject analysis of documents to be reported to INIS or ETDE. The manual includes new chapters on preparatory analysis, subject classification, abstracting and subject indexing, as well as rules, guidelines, procedures, examples and a special chapter on guidelines and examples for subject analysis in particular subject fields. (g.t.; a.n.)

  20. Aquatic Microbiology Laboratory Manual.

    Science.gov (United States)

    Cooper, Robert C.; And Others

    This laboratory manual presents information and techniques dealing with aquatic microbiology as it relates to environmental health science, sanitary engineering, and environmental microbiology. The contents are divided into three categories: (1) ecological and physiological considerations; (2) public health aspects; and (3)microbiology of water…

  1. Tokai densitometer manual

    International Nuclear Information System (INIS)

    Sprinkle, J.K. Jr.; Hsue, S.T.; Junck, K.

    1987-01-01

    In 1979, the Tokai densitometer was installed at the Tokai Reprocessing Plant in Tokai, Japan. It uses a nondestructive active technique (K-edge absorption densitometry) to assay solutions for plutonium content. The original hardware was upgraded in 1984 and 1985. This manual describes the instrument's operation after the upgrade. 2 refs

  2. Political Education Manual.

    Science.gov (United States)

    League of United Latin American Citizens, Washington, DC.

    Written to help Hispanics understand the electoral process more thoroughly and to encourage them to participate more actively in the political arena, this manual begins by describing the present status of the Hispanic electorate and then explains how laws are made, how Hispanics can influence legislation, and how to organize a voter registration…

  3. Coulometer operator's manual

    International Nuclear Information System (INIS)

    Criscuolo, A.L.

    1977-07-01

    The coulometer control system automates the titration of uranium and plutonium as performed by the CMB-1 group. The system consists of a printer, microcontroller, and coulometer, all of which are controlled by an algorithm stored in the microcontroller read-only memory. This manual describes the titration procedure using the coulometer control system, its theory and maintenance

  4. Regulations and Procedures Manual

    Energy Technology Data Exchange (ETDEWEB)

    Young, Lydia J. [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States)

    2011-07-25

    The purpose of the Regulations and Procedures Manual (RPM) is to provide LBNL personnel with a reference to University and Lawrence Berkeley National Laboratory (LBNL or Laboratory) policies and regulations by outlining normal practices and answering most policy questions that arise in the day-to-day operations of Laboratory organizations. Much of the information in this manual has been condensed from detail provided in LBNL procedure manuals, Department of Energy (DOE) directives, and Contract DE-AC02-05CH11231. This manual is not intended, however, to replace any of those documents. RPM sections on personnel apply only to employees who are not represented by unions. Personnel policies pertaining to employees represented by unions may be found in their labor agreements. Questions concerning policy interpretation should be directed to the LBNL organization responsible for the particular policy. A link to the Managers Responsible for RPM Sections is available on the RPM home page. If it is not clear which organization is responsible for a policy, please contact Requirements Manager Lydia Young or the RPM Editor.

  5. Regulations and Procedures Manual

    Energy Technology Data Exchange (ETDEWEB)

    Young, Lydia [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States)

    2010-09-30

    The purpose of the Regulations and Procedures Manual (RPM) is to provide Laboratory personnel with a reference to University and Lawrence Berkeley National Laboratory policies and regulations by outlining the normal practices and answering most policy questions that arise in the day-to-day operations of Laboratory departments. Much of the information in this manual has been condensed from detail provided in Laboratory procedure manuals, Department of Energy (DOE) directives, and Contract DE-AC02-05CH11231. This manual is not intended, however, to replace any of those documents. The sections on personnel apply only to employees who are not represented by unions. Personnel policies pertaining to employees represented by unions may be found in their labor agreements. Questions concerning policy interpretation should be directed to the department responsible for the particular policy. A link to the Managers Responsible for RPM Sections is available on the RPM home page. If it is not clear which department should be called, please contact the Associate Laboratory Director of Operations.

  6. ABCC publication manual

    Energy Technology Data Exchange (ETDEWEB)

    1959-01-01

    The reporting policy of the Atomic Bomb Casualty Commission is described in detail in this manual. Specific topics covered are: research project register; research publication policy; USA publication procedures; Japan publication procedures, report preparation instructions; and a glossary of institutions terms, phrases, and symbols. 15 figures. (DMC)

  7. Matematica 3. Manual.

    Science.gov (United States)

    D'Alu, Maria Jose Miranda de Sousa

    This teachers manual accompanies a mathematics textbook, written in Portuguese, for third graders. It closely follows the objectives and methodology of the major curricula used throughout the schools in the United States. The 11 chapters deal with: numeration (0-999,999); addition with and without regrouping; subtraction with and without…

  8. Manual on industrial radiography

    International Nuclear Information System (INIS)

    1981-08-01

    This manual is intended as a source of educational material to personnel seeking certification as industrial radiographers, and as a guide and reference text for educational organizations that are providng courses in industrial radiography. It covers the basic principles of x-ray and gamma radiation, radiation safety, films and film processing, welding, casting and forging, aircraft structures and components, radiographic techniques, and records

  9. Idaho Safety Manual.

    Science.gov (United States)

    Idaho State Dept. of Education, Boise. Div. of Vocational Education.

    This manual is intended to help teachers, administrators, and local school boards develop and institute effective safety education as a part of all vocational instruction in the public schools of Idaho. This guide is organized in 13 sections that cover the following topics: introduction to safety education, legislation, levels of responsibility,…

  10. Functional Assessment Inventory Manual.

    Science.gov (United States)

    Crewe, Nancy M.; Athelstan, Gary T.

    This manual, which provides extensive new instructions for administering the Functional Assessment Inventory (FAI), is intended to enable counselors to begin using the inventory without undergoing any special training. The first two sections deal with the need for functional assessment and issues in the development and use of the inventory. The…

  11. Manual Hydraulic Structures

    NARCIS (Netherlands)

    Molenaar, W.F.; Voorendt, M.Z.

    This manual is the result of group work and origins in Dutch lecture notes that have been used since long time. Amongst the employees of the Hydraulic Engineering Department that contributed to this work are dr.ir. S. van Baars, ir.K.G.Bezuijen, ir.G.P.Bourguignon, prof.ir.A.Glerum,

  12. SNL Abuse Testing Manual.

    Energy Technology Data Exchange (ETDEWEB)

    Orendorff, Christopher [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Lamb, Joshua [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Steele, Leigh Anna Marie [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2017-07-01

    This report describes recommended abuse testing procedures for rechargeable energy storage systems (RESSs) for electric vehicles. This report serves as a revision to the FreedomCAR Electrical Energy Storage System Abuse Test Manual for Electric and Hybrid Electric Vehicle Applications (SAND2005-3123).

  13. Sexism in Parenting Manuals

    Science.gov (United States)

    DeFrain, John D.

    1977-01-01

    Parental roles, as delineated in many of the popular parenting manuals on the market, are reviewed and assessed. It is concluded that the vast majority of authors of child-rearing guides implicity or explicitly endorse the traditional roles of father as the dominant breadwinner and mother as the nurturant caretaker. (Author)

  14. Rescue Manual. Module 6.

    Science.gov (United States)

    Ohio State Univ., Columbus. Instructional Materials Lab.

    This learner manual for rescuers covers the current techniques or practices required in the rescue service. The sixth of 10 modules contains 4 chapters: (1) industrial rescue; (2) rescue from a confined space; (3) extrication from heavy equipment; and (4) rescue operations involving elevators. Key points, an introduction, and conclusion accompany…

  15. Manually operated coded switch

    International Nuclear Information System (INIS)

    Barnette, J.H.

    1978-01-01

    The disclosure related to a manually operated recodable coded switch in which a code may be inserted, tried and used to actuate a lever controlling an external device. After attempting a code, the switch's code wheels must be returned to their zero positions before another try is made

  16. Waste Management Technical Manual

    Energy Technology Data Exchange (ETDEWEB)

    Buckingham, J.S. [ed.

    1967-08-31

    This Manual has been prepared to provide a documented compendium of the technical bases and general physical features of Isochem Incorporated`s Waste Management Program. The manual is intended to be used as a means of training and as a reference handbook for use by personnel responsible for executing the Waste Management Program. The material in this manual was assembled by members of Isochem`s Chemical Processing Division, Battelle Northwest Laboratory, and Hanford Engineering Services between September 1965 and March 1967. The manual is divided into the following parts: Introduction, contains a summary of the overall Waste Management Program. It is written to provide the reader with a synoptic view and as an aid in understanding the subsequent parts; Feed Material, contains detailed discussion of the type and sources of feed material used in the Waste Management Program, including a chapter on nuclear reactions and the formation of fission products; Waste Fractionization Plant Processing, contains detailed discussions of the processes used in the Waste Fractionization Plant with supporting data and documentation of the technology employed; Waste Fractionization Plant Product and Waste Effluent Handling, contains detailed discussions of the methods of handling the product and waste material generated by the Waste Fractionization Plant; Plant and Equipment, describes the layout of the Waste Management facilities, arrangement of equipment, and individual equipment pieces; Process Control, describes the instruments and analytical methods used for process control; and Safety describes process hazards and the methods used to safeguard against them.

  17. Southern Ductile Training Manual.

    Science.gov (United States)

    Alabama State Dept. of Education, Montgomery.

    This instructor's manual contains the materials required to conduct the competency-based workplace literacy program that was developed to help employees at a foundry that has evolved from a small, family-owned business into a major foundry group with several automated production systems. The workplace literacy program consists of 24 lessons in…

  18. NDS EXFOR Manual

    International Nuclear Information System (INIS)

    Lemmel, H.D.

    1979-06-01

    This manual contains the coding rules and formats and NDS internal compilation rules for the exchange format (EXFOR) for the transmission of nuclear reaction data between national and international nuclear data centres, and for the data storage and retrieval system of the IAEA Nuclear Data Section

  19. Consumer Decisions. Student Manual.

    Science.gov (United States)

    Florida State Dept. of Education, Tallahassee. Div. of Vocational Education.

    This student manual covers five areas relating to consumer decisions. Titles of the five sections are Consumer Law, Consumer Decision Making, Buying a Car, Convenience Foods, and Books for Preschool Children. Each section may contain some or all of these materials: list of objectives, informative sections, questions on the information and answers,…

  20. NACS Store Planning Manual.

    Science.gov (United States)

    College Store Journal, 1979

    1979-01-01

    Topics discussed by the NACS Store Planning/Renovation Committees in this updated version of the college store renovation manual include: short- and long-range planning, financial considerations, professional planning assistance, the store's image and business character, location considerations, building requirements, space requirements, fixtures,…

  1. Default Management Manual.

    Science.gov (United States)

    Dent, Richard A.

    This manual is designed to instruct administrators of the Guaranteed Student Loan (GSL) Program in how to take every step possible to administer the program effectively and to minimize the program costs of serving the high risk student. It shows schools how to work with students throughout their time in school, create ownership of the loan(s) by…

  2. RRFC hardware operation manual

    International Nuclear Information System (INIS)

    Abhold, M.E.; Hsue, S.T.; Menlove, H.O.; Walton, G.

    1996-05-01

    The Research Reactor Fuel Counter (RRFC) system was developed to assay the 235 U content in spent Material Test Reactor (MTR) type fuel elements underwater in a spent fuel pool. RRFC assays the 235 U content using active neutron coincidence counting and also incorporates an ion chamber for gross gamma-ray measurements. This manual describes RRFC hardware, including detectors, electronics, and performance characteristics

  3. CANAL user's manual

    International Nuclear Information System (INIS)

    Faya, A.; Wolf, L.; Todreas, N.

    1979-11-01

    CANAL is a subchannel computer program for the steady-state and transient thermal hydraulic analysis of BWR fuel rod bundles. The purpose of this manual is to introduce the user into the mechanism of running the code by providing information about the input data and options

  4. AELIB user's manual

    International Nuclear Information System (INIS)

    Evans, L.E.; Klawitter, G.L.

    1981-05-01

    This report is an updatable manual for users of AELIB, the AECL Library of FORTRAN-callable routines for the CRNL CDC 6600/CYBER 170 system. It provides general advice on the use of this library and detailed information on the selection and usage of particular library routines

  5. Water Quality Monitoring Manual.

    Science.gov (United States)

    Mason, Fred J.; Houdart, Joseph F.

    This manual is designed for students involved in environmental education programs dealing with water pollution problems. By establishing a network of Environmental Monitoring Stations within the educational system, four steps toward the prevention, control, and abatement of water pollution are proposed. (1) Train students to recognize, monitor,…

  6. Robotics Inspection Vehicle for Advanced Storages

    Energy Technology Data Exchange (ETDEWEB)

    Ruiz, Emilio; Renaldi, Graziano; Puig, David; Franzetti, Michele; Correcher, Carlos [European Commission, Ispra (Italy). Inst. for the Protection and Security of the Citizen

    2003-05-01

    After the dismantling of nuclear weapons and the probable release of large quantities of weapon graded materials under international verification regimes, there will be a wide interest in unmanned, highly automated and secure storage areas. In such circumstances, robotics technologies can provide an effective answer to the problem of securing, manipulating and inventorying all stored materials. In view of this future application JRC's NPNS started the development and construction of an advanced robotics prototype and demonstration system, named Robotics Inspection Vehicle (RIV), for remote inspection, surveillance and remote handling in those areas. The system was designed to meet requirements of reliability, security, high availability, robustness against radiation effects, self-maintainability (i.e., auto-repair capability), and easy installation. Due to its innovative holonomic design, RIV is a highly maneuverable and agile platform able to move in any direction, including sideways. The platform carries on-board a five degree of freedom manipulator arm. The high maneuverability and operation modes take into account the needs for accessing in the most easy way materials in the storage area. The platform is prepared to operate in one of three modes: i) manual tele-operation, ii) semiautonomous and iii) fully autonomous. The paper describes RIV's main design features, and details its GENERIS based control software [JRC's software architecture for robotics] and embedded sensors (i.e., 3D laser range, transponder antenna, ultra-sound, vision-based robot guidance, force-torque sensors, etc.). RIV was designed to incorporate several JRC innovative surveillance and inspection technologies and reveals that the current state of technology is mature to effectively provide a solution to novel storage solutions. The system is available for demonstration at JRC's Rialto Laboratory.

  7. Waste inspection tomography (WIT)

    Energy Technology Data Exchange (ETDEWEB)

    Bernardi, R.T. [Bio-Imaging Research, Inc., Lincolnshire, IL (United States)

    1995-10-01

    Waste Inspection Tomography (WIT) provides mobile semi-trailer mounted nondestructive examination (NDE) and assay (NDA) for nuclear waste drum characterization. WIT uses various computed tomography (CT) methods for both NDE and NDA of nuclear waste drums. Low level waste (LLW), transuranic (TRU), and mixed radioactive waste can be inspected and characterized without opening the drums. With externally transmitted x-ray NDE techniques, WIT has the ability to identify high density waste materials like heavy metals, define drum contents in two- and three-dimensional space, quantify free liquid volumes through density and x-ray attenuation coefficient discrimination, and measure drum wall thickness. With waste emitting gamma-ray NDA techniques, WIT can locate gamma emitting radioactive sources in two- and three-dimensional space, identify gamma emitting, isotopic species, identify the external activity levels of emitting gamma-ray sources, correct for waste matrix attenuation, provide internal activity approximations, and provide the data needed for waste classification as LLW or TRU.

  8. Waste inspection tomography (WIT)

    International Nuclear Information System (INIS)

    Bernardi, R.T.

    1995-01-01

    Waste Inspection Tomography (WIT) provides mobile semi-trailer mounted nondestructive examination (NDE) and assay (NDA) for nuclear waste drum characterization. WIT uses various computed tomography (CT) methods for both NDE and NDA of nuclear waste drums. Low level waste (LLW), transuranic (TRU), and mixed radioactive waste can be inspected and characterized without opening the drums. With externally transmitted x-ray NDE techniques, WIT has the ability to identify high density waste materials like heavy metals, define drum contents in two- and three-dimensional space, quantify free liquid volumes through density and x-ray attenuation coefficient discrimination, and measure drum wall thickness. With waste emitting gamma-ray NDA techniques, WIT can locate gamma emitting radioactive sources in two- and three-dimensional space, identify gamma emitting, isotopic species, identify the external activity levels of emitting gamma-ray sources, correct for waste matrix attenuation, provide internal activity approximations, and provide the data needed for waste classification as LLW or TRU

  9. Inspections - a cost effective approach

    International Nuclear Information System (INIS)

    Joseph, C.

    1981-01-01

    This paper describes a cost effective approach for inspections of Computerized Nuclear Materials Control and Accounting Systems (CNMCAS). Highlighted is the capability to conduct an inspection program via portable telephone terminals from off-site locations. The program can be applied to various materials management functions including materials control, quality assurance, and materials accounting. The system is designed to facilitate inspections by both external and internal groups

  10. A smart ROV solution for ship hull and harbor inspection

    Science.gov (United States)

    Reed, Scott; Wood, Jon; Vazquez, Jose; Mignotte, Pierre-Yves; Privat, Benjamin

    2010-04-01

    Hull and harbor infrastructure inspections are frequently performed manually and involve quite a bit of risk and human and monetary resources. In any kind of threat and resource constrained environment, this involves unacceptable levels of risk and cost. Modern Remotely Operated Vehicles are highly refined machines that provide features and capabilities previously unavailable. Operations once carried out by divers can now be carried out more quickly, efficiently and safely by smart enabled ROVs. ROVs are rapidly deployable and capable of continuous, reliable operations in adverse conditions. They also provide a stable platform on which multiple sensors may be mounted and utilized to meet the harbor inspection problem. Automated Control software provides ROV's and their pilots with the capability to inspect complex, constrained environments such as those found in a harbor region. This application and the user interface allow the ROV to automatically conduct complex maneuvers relative to the area being inspected and relieves the training requirements and work load for the pilot, allowing he or she to focus on the primary task of survey, inspection and looking for possible threats (such as IEDs, Limpet Mines, signs of sabotage, etc). Real-time sensor processing tools can be integrated into the smart ROV solution to assist the operator. Automatic Target Recognition (ATR) algorithms are used to search through the sensor data collected by the ROV in real time. These algorithms provide immediate feedback on possible threats and notify the operator of regions that may require manual verification. Sensor data (sonar or video) is also mosaiced, providing the operator with real-time situational awareness and a coverage map of the hull or seafloor. Detected objects may also be placed in the context of the large scale characteristics of the hull (or bottom or pilings) and localized. Within the complex areas such as the harbor pier pilings and the running gear of the ship, real

  11. Inspection system performance test procedure

    International Nuclear Information System (INIS)

    Jensen, C.E.

    1995-01-01

    This procedure establishes requirements to administer a performance demonstration test. The test is to demonstrate that the double-shell tank inspection system (DSTIS) supplied by the contractor performs in accordance with the WHC-S-4108, Double-Shell Tank Ultrasonic Inspection Performance Specification, Rev. 2-A, January, 1995. The inspection system is intended to provide ultrasonic (UT) and visual data to determine integrity of the Westinghouse Hanford Company (WHC) site underground waste tanks. The robotic inspection system consists of the following major sub-systems (modules) and components: Mobile control center; Deployment module; Cable management assembly; Robot mechanism; Ultrasonic testing system; Visual testing system; Pneumatic system; Electrical system; and Control system

  12. Experience on inspection at PFPF

    International Nuclear Information System (INIS)

    Aoki, I.; Yamamoto, Y.; Takahashi, Saburo; Ooshima, Hirofumi; Kuniyasu, Kazufusa.

    1993-01-01

    In order to reduce a personal radiation exposure, Plutonium Fuel Production Facility (PFPF) introduced an automated MOX fabrication technology. Safeguards system for the PFPF was designed and installed so as to be compatible with automated process operation as much as possible. Introduction of these system in PFPF made possible to do the inspection measurements with unattended mode and Near Real Time Material Accountancy (NRTA), consequently inspection has been carrying out effectively and efficiently. This paper describes the new Inspection activities as a comparison with old Inspection activities based on our experience. (author)

  13. PWR vessel inspection performance improvements

    International Nuclear Information System (INIS)

    Blair Fairbrother, D.; Bodson, Francis

    1998-01-01

    A compact robot for ultrasonic inspection of reactor vessels has been developed that reduces setup logistics and schedule time for mandatory code inspections. Rather than installing a large structure to access the entire weld inspection area from its flange attachment, the compact robot examines welds in overlapping patches from a suction cup anchor to the shell wall. The compact robot size allows two robots to be operated in the vessel simultaneously. This significantly reduces the time required to complete the inspection. Experience to date indicates that time for vessel examinations can be reduced to fewer than four days. (author)

  14. Missouri Highway Safety Manual Recalibration

    Science.gov (United States)

    2018-05-01

    The Highway Safety Manual (HSM) is a national manual for analyzing the highway safety of various facilities, including rural roads, urban arterials, freeways, and intersections. The HSM was first published in 2010, and a 2014 supplement addressed fre...

  15. Developing a Pupil Transportation Manual.

    Science.gov (United States)

    Douglas, Dave

    1987-01-01

    District-level pupil transportation manuals that contain clear, concise information about objectives, policies, and regulations are a must. These manuals should also specify procedures concerning evaluation processes, personnel recruitment and selection, and the driver training program. (MLH)

  16. 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

  17. Effective and efficient optics inspection approach using machine learning algorithms

    International Nuclear Information System (INIS)

    Abdulla, G.; Kegelmeyer, L.; Liao, Z.; Carr, W.

    2010-01-01

    The Final Optics Damage Inspection (FODI) system automatically acquires and utilizes the Optics Inspection (OI) system to analyze images of the final optics at the National Ignition Facility (NIF). During each inspection cycle up to 1000 images acquired by FODI are examined by OI to identify and track damage sites on the optics. The process of tracking growing damage sites on the surface of an optic can be made more effective by identifying and removing signals associated with debris or reflections. The manual process to filter these false sites is daunting and time consuming. In this paper we discuss the use of machine learning tools and data mining techniques to help with this task. We describe the process to prepare a data set that can be used for training and identifying hardware reflections in the image data. In order to collect training data, the images are first automatically acquired and analyzed with existing software and then relevant features such as spatial, physical and luminosity measures are extracted for each site. A subset of these sites is 'truthed' or manually assigned a class to create training data. A supervised classification algorithm is used to test if the features can predict the class membership of new sites. A suite of self-configuring machine learning tools called 'Avatar Tools' is applied to classify all sites. To verify, we used 10-fold cross correlation and found the accuracy was above 99%. This substantially reduces the number of false alarms that would otherwise be sent for more extensive investigation.

  18. Proposed modifications to the RCRA post-closure permit for the Bear Creek Hydrogeologic Regime at the US Department of Energy Y-12 Plant, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1997-05-01

    This report presents proposed modifications to several conditions of the Resource Conservation and Recovery Act (RCRA) Post-Closure Permit (PCP) for the Bear Creek Hydrogeologic Regime (BCHR). These permit conditions define the requirements for RCRA post-closure corrective action groundwater monitoring at the S-3 Ponds, the Oil Landfarm, and the Bear Creek Burial Grounds (units A, C-West, and Walk-in Pits). Modification of these PCP conditions is requested to: (1) clarify the planned integration of RCRA post-closure corrective action groundwater monitoring with the monitoring program to be established in the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Record of Decision (ROD) for the Bear Creek Valley (BCV) Watershed, (2) revise several of the current technical requirements for groundwater monitoring based on implementation of the RCRA post-closure corrective action monitoring program during 1996, and (3) update applicable technical procedures with revised versions recently issued by the Y-12 Plant Groundwater Protection Program (GWPP). With these modifications, the Y-12 Plant will continue to meet the full intent of all regulatory obligations for post-closure care of these facilities. Section 2.0 provides the technical justification for each proposed permit modification. The proposed changes to permit language are provided in Section 3.0 (S-3 Ponds), Section 4.0 (Oil Landfarm), and Section 5.0 (Bear Creek Burial Grounds). Sections 6.0 and 7.0 reference updated and revised procedures for groundwater sampling, and monitoring well plugging and abandonment, respectively. Appendix A includes all proposed revisions to the PCP Attachments

  19. Proposed modifications to the RCRA post-closure permit for the Bear Creek Hydrogeologic Regime at the US Department of Energy Y-12 Plant, Oak Ridge, Tennessee

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-05-01

    This report presents proposed modifications to several conditions of the Resource Conservation and Recovery Act (RCRA) Post-Closure Permit (PCP) for the Bear Creek Hydrogeologic Regime (BCHR). These permit conditions define the requirements for RCRA post-closure corrective action groundwater monitoring at the S-3 Ponds, the Oil Landfarm, and the Bear Creek Burial Grounds (units A, C-West, and Walk-in Pits). Modification of these PCP conditions is requested to: (1) clarify the planned integration of RCRA post-closure corrective action groundwater monitoring with the monitoring program to be established in the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Record of Decision (ROD) for the Bear Creek Valley (BCV) Watershed, (2) revise several of the current technical requirements for groundwater monitoring based on implementation of the RCRA post-closure corrective action monitoring program during 1996, and (3) update applicable technical procedures with revised versions recently issued by the Y-12 Plant Groundwater Protection Program (GWPP). With these modifications, the Y-12 Plant will continue to meet the full intent of all regulatory obligations for post-closure care of these facilities. Section 2.0 provides the technical justification for each proposed permit modification. The proposed changes to permit language are provided in Section 3.0 (S-3 Ponds), Section 4.0 (Oil Landfarm), and Section 5.0 (Bear Creek Burial Grounds). Sections 6.0 and 7.0 reference updated and revised procedures for groundwater sampling, and monitoring well plugging and abandonment, respectively. Appendix A includes all proposed revisions to the PCP Attachments.

  20. Resource Conservation and Recovery Act (RCRA) Part B Permit Application for Production Associated Units at the Oak Ridge Y-12 Plant

    Energy Technology Data Exchange (ETDEWEB)

    1994-09-01

    This is the RCRA required permit application for Radioactive and Hazardous Waste Management at the Oak Ridge Y-12 Plant for the following units: Building 9206 Container Storage Unit; Building 9212 Container Storage Unit; Building 9720-12 Container Storage Unit; Cyanide Treatment Unit. All four of these units are associated with the recovery of enriched uranium and other metals from wastes generated during the processing of nuclear materials.

  1. Revised RCRA closure plan for the Interim Drum Yard (S-030) at the Oak Ridge Y-12 Plant, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    Smith, C.M.

    1994-09-01

    The Interim Drum Yard (IDY) facility is a containerized waste storage area located in the Y-12 exclusion area. It was used to store waste materials which are regulated by RCRA (Resource Conservation and Recovery Act); uranyl nitrate solutions were also stored there. The closure plan outlines the actions required to achieve closure of IDY and is being submitted in accordance with TN Rule 1200-1-11.05(7) and 40 CFR 265.110

  2. Resource Conservation and Recovery Act (RCRA) Part B Permit Application for Production Associated Units at the Oak Ridge Y-12 Plant

    International Nuclear Information System (INIS)

    1994-09-01

    This is the RCRA required permit application for Radioactive and Hazardous Waste Management at the Oak Ridge Y-12 Plant for the following units: Building 9206 Container Storage Unit; Building 9212 Container Storage Unit; Building 9720-12 Container Storage Unit; Cyanide Treatment Unit. All four of these units are associated with the recovery of enriched uranium and other metals from wastes generated during the processing of nuclear materials

  3. Detailed analysis of a RCRA landfill for the United Nuclear Corporation Disposal Site at the Oak Ridge Y-12 Plant, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1991-04-01

    The purpose of this detailed analysis is to provide a preliminary compilation of data, information, and estimated costs associated with a RCRA landfill alternative for UNC Disposal Site. This is in response to Environmental Protection Agency (EPA) comment No. 6 from their review of a open-quotes Feasibility Study for the United Nuclear Corporation Disposal Site at the Oak Ridge Y-12 Plant, Oak Ridge, Tennessee.close quotes

  4. Short notice inspections

    International Nuclear Information System (INIS)

    Pouchkarev, V.

    1998-01-01

    For 30 years the IAEA safeguards system have evolved and have been strengthened by the regular introduction of new methods and techniques, improving both its effectiveness and efficiency. The member States of the IAEA have indicated their willingness to accept new obligations and associated technical measure that greatly strengthen the nuclear safeguards system. One element of this is the extent to which the IAEA inspectors have physical access to relevant locations for the purpose of providing independent verification of the exclusively peaceful intent of a State nuclear program. The Protocol to Safeguards granted new legal authority with respect to information on, and short notice inspector access to, all buildings on a nuclear site and administrative agreements that improve the process of designating inspectors and IAEA access to modern means of communication. This report is a short description of unannounced or short notice inspections as measures on which the new strengthened and cost efficient system will be based

  5. Large Hadron Collider manual

    CERN Document Server

    Lavender, Gemma

    2018-01-01

    What is the universe made of? How did it start? This Manual tells the story of how physicists are seeking answers to these questions using the world’s largest particle smasher – the Large Hadron Collider – at the CERN laboratory on the Franco-Swiss border. Beginning with the first tentative steps taken to build the machine, the digestible text, supported by color photographs of the hardware involved, along with annotated schematic diagrams of the physics experiments, covers the particle accelerator’s greatest discoveries – from both the perspective of the writer and the scientists who work there. The Large Hadron Collider Manual is a full, comprehensive guide to the most famous, record-breaking physics experiment in the world, which continues to capture the public imagination as it provides new insight into the fundamental laws of nature.

  6. NDS EXFOR manual

    International Nuclear Information System (INIS)

    Lemmel, H.D.

    1996-01-01

    EXFOR is the agreed exchange format for the transmission of nuclear reaction data between national and international nuclear data centers for the benefit of nuclear data users in all countries. The IAEA Nuclear Data Section uses the EXFOR system not only for the center-to-center data exchange but also as its data storage and retrieval system. This NDS EXFOR MANUAL therefore contains the agreed EXFOR coding rules and format, supplemented by NDS internal compilation rules. The EXFOR system and the EXFOR nuclear data library with several million data records originate from the cooperation of an increasing number of data centers whose names and addresses can be found inside the Manual. Their contributions and cooperative efforts are gratefully acknowledged. (author)

  7. Radiation protection manual

    International Nuclear Information System (INIS)

    Spang, A.

    1983-01-01

    According to the Radiation Protection Ordinance, radiation protection experts directing or supervising the handling of radioactive materials must have expert knowledge. The concept of expert knowledge has been clearly defined by the Fachverband e.V. in a catalogue of instruction goals. The manual follows the principles of this catalogue; it presents the expert knowledge required in a total of 15 subject groups. There is an index which helps the reader to find his specific subject group and the knowledge required of him in this subject group. However, the manual gives only an outline of the subject matter in many instances and should therefore not be regarded as a textbook in the proper sense. (orig./HP) [de

  8. REBA experimenters' manual

    International Nuclear Information System (INIS)

    Schuch, R.L.

    1977-04-01

    The REBA is a high-energy, pulsed electron beam or bremsstrahlung x-ray generator whose operational purpose is to provide an energy source of short duration for conducting experiments, primarily to determine material responses to rapid surface and in-depth deposition of energy. The purpose of this manual is to serve as a basic source of information for prospective users of REBA. Included is a brief discussion of the design and operation of the facility as well as a summary of output characteristics for electron beam modes and environmental data for x-ray operation. The manual also contains a description of the REBA experimental facilities, including geometry of the test cell, instrumentation and data collection capabilities, and services and support available to experimenters

  9. The environmental survey manual

    International Nuclear Information System (INIS)

    1987-08-01

    The purpose of this manual is to provide guidance to the Survey and Sampling and Analysis teams that conduct the one-time Environmental Survey of the major US Department of Energy (DOE) operating facilities. This manual includes a discussion of DOE's policy on environmental issues, a review of statutory guidance as it applies to the Survey, the procedures and protocols to be used by the Survey teams, criteria for the use of the Survey teams in evaluating existing environmental data for the Survey effort, generic technical checklists used in every Survey, health and safety guidelines for the personnel conducting the Survey, including the identification of potential hazards, prescribed protective equipment, and emergency procedures, the required formats for the Survey reports, guidance on identifying environmental problems that need immediate attention by the Operations Office responsible for the particular facility, and procedures and protocols for the conduct of sampling and analysis

  10. NDS EXFOR manual

    International Nuclear Information System (INIS)

    Lemmel, H.D.

    1985-08-01

    EXFOR is the agreed exchange format for the transmission of nuclear reaction data between national and international nuclear data centers for the benefit of nuclear data users in all countries. The IAEA Nuclear Data Section uses the EXFOR system not only for the center-to-center data exchange but also as its data storage and retrieval system. This NDS EXFOR MANUAL therefore contains the agreed EXFOR coding rules and format, supplemented by NDS internal compilation rules. The EXFOR system and the EXFOR nuclear data library with several million data records originate from the cooperation of an increasing number of data centers whose names and addresses can be found inside the Manual. Their contributions and cooperative efforts are gratefully acknowledged. (author)

  11. MINTEQ user's manual

    International Nuclear Information System (INIS)

    Peterson, S.R.; Hostetler, C.J.; Deutsch, W.J.; Cowan, C.E.

    1987-02-01

    This manual will aid the user in applying the MINTEQ geochemical computer code to model aqueous solutions and the interactions of aqueous solutions with hypothesized assemblages of solid phases. The manual will provide a basic understanding of how the MINTEQ computer code operates and the important principles that are incorporated into the code and instruct a user of the MINTEQ code on how to create input files to simulate a variety of geochemical problems. Chapters 2 through 8 are for the user who has some experience with or wishes to review the principles important to geochemical computer codes. These chapters include information on the methodology MINTEQ uses to incorporate these principles into the code. Chapters 9 through 11 are for the user who wants to know how to create input data files to model various types of problems. 35 refs., 2 figs., 5 tabs

  12. Auxiliary mine ventilation manual

    International Nuclear Information System (INIS)

    Workplace Safety North

    2010-01-01

    An adequate ventilation system is needed for air quality and handling in a mine and is comprised of many different pieces of equipment for removing contaminated air and supplying fresh air and thereby provide a satisfactory working environment. This manual highlights auxiliary ventilation systems made up of small fans, ducts, tubes, air movers, deflectors and additional air flow controls which distribute fresh air delivered by the primary system to all areas. A review of auxiliary ventilation is provided. Design, operation and management issues are discussed and guidelines are furnished. This manual is limited to underground hard rock operations and does not address directly other, specific auxiliary systems, either in underground coal mines or uranium mines.

  13. Auxiliary mine ventilation manual

    Energy Technology Data Exchange (ETDEWEB)

    Workplace Safety North

    2010-07-01

    An adequate ventilation system is needed for air quality and handling in a mine and is comprised of many different pieces of equipment for removing contaminated air and supplying fresh air and thereby provide a satisfactory working environment. This manual highlights auxiliary ventilation systems made up of small fans, ducts, tubes, air movers, deflectors and additional air flow controls which distribute fresh air delivered by the primary system to all areas. A review of auxiliary ventilation is provided. Design, operation and management issues are discussed and guidelines are furnished. This manual is limited to underground hard rock operations and does not address directly other, specific auxiliary systems, either in underground coal mines or uranium mines.

  14. Laboratory biosafety manual

    Energy Technology Data Exchange (ETDEWEB)

    1983-01-01

    This book is in three sections; basic standards of laboratory design and equipment; procedures for safe laboratory practice; and the selection and use of essential biosafety equipment. The intention is that the guidance given in the book should have a broad basis and international application, and that it should be a source from which manuals applicable to local and special conditions can be usefully derived.

  15. Oil trading manual

    International Nuclear Information System (INIS)

    Long, D.

    1995-01-01

    This manual provides basic information on all aspects of oil trading. Topics reviewed in Part 1 include physical characteristics and refining and oil pricing arrangements. Part 2 on instruments and markets contains chapters on crude oil markets, product markets, forward and futures contracts, forward paper markets, oil future exchanges, options, swaps and long term oil markets. Part 3 deals with administration and has chapters on operations and logistics, credit control, accounting, taxation of oil trading, contracts and legal and regulatory issues. (UK)

  16. Manual of Radiation Protection

    International Nuclear Information System (INIS)

    Gambini, D.J.; Granier, R.; Boisserie, G.

    1992-01-01

    This manual explains the principles and practice of radiation protection for those whose work in research, in the field of medicine or in the industry requires the use of radiation sources. It provides the information radiation users need to protect themselves and others and to understand and comply with international recommendations, regulations and legislation regarding the use of radionuclides and radiation machines. It is designed to teach a wide audience of doctors, biologists, research scientists, technicians, engineers, students and others

  17. IAC user manual

    Science.gov (United States)

    Vos, R. G.; Beste, D. L.; Gregg, J.

    1984-01-01

    The User Manual for the Integrated Analysis Capability (IAC) Level 1 system is presented. The IAC system currently supports the thermal, structures, controls and system dynamics technologies, and its development is influenced by the requirements for design/analysis of large space systems. The system has many features which make it applicable to general problems in engineering, and to management of data and software. Information includes basic IAC operation, executive commands, modules, solution paths, data organization and storage, IAC utilities, and module implementation.

  18. Probabilistic methodology for assessing steam generator tube inspection - Phase II: CANTIA - a probabilistic method for assessing steam generator tube inspections

    International Nuclear Information System (INIS)

    Harris, J.E.; Gorman, J.A.; Turner, A.P.L.

    1997-03-01

    The objectives of this project were to develop a computer-based method for probabilistic assessment of inspection strategies for steam generator tubes, and to document the source code and to provide a user's manual for it. The program CANTIA was created to fulfill this objective, and the documentation and verification of the code is provided in this volume. The user's manual for CANTIA is provided as a separate report. CANTIA uses Monte Carlo techniques to determine approximate probabilities of steam generator tube failures under accident conditions and primary-to-secondary leak rates under normal and accident conditions at future points in time. The program also determines approximate future flaw distributions and non-destructive examination results from the input data. The probabilities of failure and leak rates and the future flaw distributions can be influenced by performing inspections of the steam generator tubes at some future points in time, and removing defective tubes from the population. The effect of different inspection and maintenance strategies can therefore be determined as a direct effect on the probability of tube failure and primary-to-secondary leak rate

  19. Inspection of disposal canisters components

    International Nuclear Information System (INIS)

    Pitkaenen, J.

    2013-12-01

    This report presents the inspection techniques of disposal canister components. Manufacturing methods and a description of the defects related to different manufacturing methods are described briefly. The defect types form a basis for the design of non-destructive testing because the defect types, which occur in the inspected components, affect to choice of inspection methods. The canister components are to nodular cast iron insert, steel lid, lid screw, metal gasket, copper tube with integrated or separate bottom, and copper lid. The inspection of copper material is challenging due to the anisotropic properties of the material and local changes in the grain size of the copper material. The cast iron insert has some acoustical material property variation (attenuation, velocity changes, scattering properties), which make the ultrasonic inspection demanding from calibration point of view. Mainly three different methods are used for inspection. Ultrasonic testing technique is used for inspection of volume, eddy current technique, for copper components only, and visual testing technique are used for inspection of the surface and near surface area

  20. MTR fuel inspection at CERCA

    International Nuclear Information System (INIS)

    Fanjas, Y.

    1992-01-01

    The stringent specifications for MTR fuel plates and fuel elements require various sophisticated inspection techniques. In particular, the development of low enriched silicide fuels made it necessary to adapt these techniques to high density plates. This paper presents the status of inspection technology at CERCA. (author)

  1. 1990 waste tank inspection program

    International Nuclear Information System (INIS)

    McNatt, F.G.

    1990-01-01

    Aqueous radioactive wastes from Savannah River Site separations processes are contained in large underground carbon steel tanks. Tank conditions are evaluated by inspection using periscopes, still photography, and video systems for visual imagery. Inspections made in 1990 are the subject of this report

  2. 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

  3. Program Management System manual

    International Nuclear Information System (INIS)

    1986-01-01

    The Program Management System (PMS), as detailed in this manual, consists of all the plans, policies, procedure, systems, and processes that, taken together, serve as a mechanism for managing the various subprograms and program elements in a cohesive, cost-effective manner. The PMS is consistent with the requirements of the Nuclear Waste Policy Act of 1982 and the ''Mission Plan for the Civilian Radioactive Waste Management Program'' (DOE/RW-0005). It is based on, but goes beyond, the Department of Energy (DOE) management policies and procedures applicable to all DOE programs by adapting these directives to the specific needs of the Civilian Radioactive Waste Management program. This PMS Manual describes the hierarchy of plans required to develop and maintain the cost, schedule, and technical baselines at the various organizational levels of the Civilian Radioactive Waste Management Program. It also establishes the management policies and procedures used in the implementation of the Program. These include requirements for internal reports, data, and other information; systems engineering management; regulatory compliance; safety; quality assurance; and institutional affairs. Although expanded versions of many of these plans, policies, and procedures are found in separate documents, they are an integral part of this manual. The PMS provides the basis for the effective management that is needed to ensure that the Civilian Radioactive Waste Management Program fulfills the mandate of the Nuclear Waste Policy Act of 1982. 5 figs., 2 tabs

  4. ETAP user's manual

    International Nuclear Information System (INIS)

    Watanabe, Norio; Higuchi, Suminori.

    1990-11-01

    The event tree analysis technique has been used in Probabilistic Safety Assessment for LWRs to delineate various accident scenarios leading to core melt or containment failure and to evaluate their frequencies. This technique often requires manual preparation of event trees with iterative process and time-consuming work in data handling. For the purpose of reducing manual efforts in event tree analysis, we developed a new software package named ETAP (Event Tree Analysis Supporting Program) for event tree analysis. ETAP is an interactive PC-based program which has the ability to construct, update, document, and quantify event trees. Because of its fast running capability to quantify event trees, use of the EATP program can make it easy to perform the sensitivity studies on a variety of system/containment performance issues. This report provides a user's manual for ETAP, which describes the structure, installation, and use of EATP. This software runs on NEC/PC-9800 or compatible PCs that have a 640 KB memory and MS-DOS 2.11 or higher. (author)

  5. Sodium safety manual

    International Nuclear Information System (INIS)

    Hayes, D.J.; Gardiner, R.L.

    1980-09-01

    The sodium safety manual is based upon more than a decade of experience with liquid sodium at Berkeley Nuclear Laboratories (BNL). It draws particularly from the expertise and experience developed in the course of research work into sodium fires and sodium water reactions. It draws also on information obtained from the UKAEA and other sodium users. Many of the broad principles will apply to other Establishments but much of the detail is specific to BNL and as a consequence its application at other sites may well be limited. Accidents with sodium are at best unpleasant and at worst lethal in an extremely painful way. The object of this manual is to help prevent sodium accidents. It is not intended to give detailed advice on specific precautions for particular situations, but rather to set out the overall strategy which will ensure that sodium activities will be pursued safely. More detail is generally conveyed to staff by the use of local instructions known as Sodium Working Procedures (SWP's) which are not reproduced in this manual although a list of current SWP's is included. Much attention is properly given to the safe design and operation of larger facilities; nevertheless evidence suggests that sodium accidents most frequently occur in small-scale work particularly in operations associated with sodium cleaning and special care is needed in all such cases. (U.K.)

  6. OASIS User Manual

    CERN Document Server

    Bojtar, L

    2009-01-01

    The OASIS system has been operational for years now. After a long development the project has reached a state where the number of features it provides exceeds largely what most of its users knows about. The author felt it was time to write a user manual explaining all the functionality of the viewer application. This document is a user manual, concentrating on the functionality of the viewer from the user’s point of view. There are already documents available on the project’s web site about the technical aspects at http://project-oasis.web.cern.ch/project-oasis/presentations.htm . There was an attempt to produce a tutorial on the viewer, but it didn’t get much further than the table of contents, that however is well thought. The structure of this user manual follows the same principle, the basic and most often used features are grouped together. Advanced or less often used features are described in a separate chapter. There is a second organizational principle, features belong to different levels: chann...

  7. 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...

  8. 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...

  9. 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)

  10. Detailed simulation of ultrasonic inspections

    International Nuclear Information System (INIS)

    Chaplin, K.R.; Douglas, S.R.; Dunford, D.

    1997-01-01

    Simulation of ultrasonic inspection of engineering components have been performed at the Chalk River Laboratories of AECL for over 10 years. The computer model, called EWE for Elastic Wave Equations, solves the Elastic Wave Equations using a novel finite difference scheme. It simulates the propagation of an ultrasonic wave from the transducer to a flaw, the scatter of waves from the flaw, and measurement of signals at a receive transducer. Regions of different materials, water and steel for example, can be simulated. In addition, regions with slightly different material properties from the parent material can be investigated. The two major types of output are displays of the ultrasonic waves inside the component and the corresponding A-scans. EPRI and other organizations have used ultrasonic models for: defining acceptable ultrasonic inspection procedures, designing and evaluating inspection techniques, and for quantifying inspection reliability. The EWE model has been applied to the inspection of large pipes in a nuclear plant, gas pipeline welds and steam generator tubes. Most recent work has dealt with the ultrasonic inspection of pressure tubes in CANDU reactors. Pressure tube inspections can reliably detect and size defects; however, there are improvements that can be made. For example, knowing the sharpness of a flaw-tip is crucial for fitness for service assessments. Computer modelling of the ultrasonic inspection of flaws with different root radius has suggested inspection techniques that provide flaw tip radius information. A preliminary investigation of these methods has been made in the laboratory. The basis for the model will be reviewed at the presentation. Then the results of computer simulations will be displayed on a PC using an interactive program that analyzes simulated A-scans. This software tool gives inspection staff direct access to the results of computer simulations. (author)

  11. Borehole Data Package for Calendar Year 2001 RCRA Wells at Single-Shell Tank Waste Management Area U

    International Nuclear Information System (INIS)

    Horton, Duane G.

    2002-01-01

    This document provides information on the construction of three new RCRA wells at Waste Management Area U in September 2001. These wells were constructed to the specifications and requirements described in Washington Administrative Codes 173-160 and 173-303. Grab samples for geological description and archive were collected every 5 ft throughout the wells. Borehole and drill cuttings were monitored regularly for organic vapors and radionuclide contaminants. At well 299-W18-40, beta-gamma activity was found to be slightly above background at 120 ft below ground surface. All other measurements were below background. Cesium-137 was found at the ground surface and at 3 ft below ground surface (bgs). No other manmade contamination was found. At well 299-W19-44, no radionuclide contamination was found, but several intervals of high carbon monoxide were detected. Cesium-137 was detected at 3 ft bgs at 0.4 pCi/g. At well 299-W19-45, no radionuclide contamination was found, but several intervals of high carbon monoxide were detected. Cesium-137 was detected near the surface at 0.4 pCi/g. No other manmade radionuclide was detected. At well 299-W19-45, samples for geological description and archive were collected every 5 ft throughout the well. No contamination was noted. Cesium-137 was detected near the surface at 0.4 to 1.4 pCi/g. No other manmade radionuclide was detected

  12. The elimination of chlorinated, chlorofluorocarbon, and other RCRA hazardous solvents from the Y-12 Plant's enriched uranium operations

    International Nuclear Information System (INIS)

    Johnson, D.H.; Patton, R.L.; Thompson, L.M.

    1990-01-01

    A major driving force in waste minimization within the plant is the reduction of mixed radioactive wastes associated with operations on highly enriched uranium. High enriched uranium has a high concentration of the uranium-235 isotope (up to 97.5% enrichment) and is radioactive, giving off alpha and low level gamma radiation. The material is fissionable with as little as two pounds dissolved in water being capable of producing a spontaneous chain reaction. For these reasons the material is processed in small batches or small geometries. Additionally, the material is completely recycled because of its strategic and monetary value. Since the early eighties, the plant has had an active waste minimization program which has concentrated on substitution of less hazardous solvents wherever possible. The following paper summarizes efforts in two areas - development of a water-based machining coolant to replace perchloroethylene and substitution of an aliphatic solvent to replace solvents producing hazardous wastes as defined by the Resource, Conservation, and Recovery Act (RCRA)

  13. RCRA Facility Investigation report for Waste Area Grouping 6 at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1991-09-01

    WAG 6 comprises a shallow land burial facility used for disposal of low-level radioactive wastes (LLW) and, until recently, chemical wastes. As such, the site is subject to regulation under RCRA and the Comprehensive Environmental Response Compensation and Liability Act (CERCLA). To comply with these regulations, DOE, in conjunction with the Environmental Protection Agency (EPA) and the Tennessee Department of Environment and Conservation (TDEC), developed a strategy for closure and remediation of WAG 6 by 1997. A key component of this strategy was to complete an RFI by September 1991. The primary objectives of the RFI were to evaluate the site's potential human health and environmental impacts and to develop a preliminary list of alternatives to mitigate these impacts. The WAG 6 one of three solid waste management units evaluated Oak Ridge National Laboratory (ORNL) existing waste disposal records and sampling data and performed the additional sampling and analysis necessary to: describe the nature and extent of contamination; characterize key contaminant transport pathways; and assess potential risks to human health and the environment by developing and evaluating hypothetical receptor scenarios. Estimated excess lifetime cancer risks as a result for exposure to radionuclides and chemicals were quantified for each hypothetical human receptor. For environmental receptors, potential impacts were qualitatively assessed. Taking into account regulatory requirements and base line risk assessment results, preliminary site closure and remediation objectives were identified, and a preliminary list of alternatives for site closure and remediation was developed

  14. RCRA facility investigation/corrective measures study work plan for the 100-HR-1 operable unit, Hanford Site, Richland, Washington

    International Nuclear Information System (INIS)

    1992-09-01

    Four areas of the Hanford Site (the 100, 200, 300, and 1100 Areas) have been included on the US. Environmental Protection Agency's (EPA's) National Priorities List (NPL) under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). Under the Hanford Federal Facility Agreement and Consent Order, signed by the Washington State Department of Ecology (Ecology), EPA, and the US Department of Energy (DOE), more than 1,000 inactive waste disposal and unplanned release sites on the Hanford Site have been grouped into a number of source and groundwater operable units. These operable units contain contamination in the form of hazardous waste, radioactive/hazardous mixed waste, and other CERCLA hazardous substances. This work plan and the attached supporting project plans establish the operable unit setting and the objectives, procedures, tasks, and schedule for conducting the RCRA facility investigation/corrective measures study (RFI/CMS) for the 100-HR-1 source operable unit. Source operable units include facilities and unplanned release sites that are potential sources of contamination. The 100-HR-3 operable unit underlies the D/DR and H Areas, the 600 Area between them, and the six source operable units these areas contain. The 100-HR-3 operable unit includes all contamination found in the aquifer soils and water within its boundary. Separate work plans have been initiated for the 100-HR-3 groundwater operable unit (DOE-RL 1992a) and the 100-DR-1 (DOE-RL 1992b) source operable units

  15. Development of innovative inspection tools for higher reliability of PHWR fuel

    International Nuclear Information System (INIS)

    Kamalesh Kumar, B.; Viswanathan, B.; Laxminarayana, B.; Ganguly, C.

    2003-01-01

    'Full text:' Advent of Computer aided manufacturing systems has led to very high rate of production with greater reliability. The conventional inspection tools and systems, which are often manual based do not complement with output of highly automated production line. In order to overcome the deficiency, a strategic plan was developed for having automated inspection facility for PHWR fuel assembly line. Laser based systems with their inherently high accuracy and quick response times are a favorite for metrology purpose. Non-contact nature of laser-based measurement ensures minimal contamination, low wear and tear and good repeatability. So far two laser-based systems viz. Pellet density measurement systems and triangulation sensors have been developed. Laser based fuel pellet inspection system and PHWR fuel bundle metric station are under development. Machine vision-based systems have been developed to overcome certain limitations when inspection has to be carried out on such a large scale manually. These deficiencies arise from limitations of resolution, accessibility, fatigue and absence of quantification ability. These problems get further compounded in inspection of fuel components because of their relatively small sizes, close tolerances required and the reflective surfaces. PC based vision system has been developed for inspecting components and fuel assemblies. The paper would touch upon the details of the various laser systems and vision systems that have been indigenously developed for PHWR Fuel Metrology and their impact on the assembly production line. (author)

  16. 40 CFR 60.536 - Permanent label, temporary label, and owner's manual.

    Science.gov (United States)

    2010-07-01

    ... combustor, which needs periodic inspection and replacement for proper operation. Consult owner's manual for... this section. Such information shall be adequate to enable consumers to achieve optimal emissions...) Proper use of air controls, (iv) Ash removal procedures, (v) Instructions on gasket replacement, (vi) For...

  17. Licensee contractor and vendor inspection status report

    International Nuclear Information System (INIS)

    1991-02-01

    This periodical covers the results of inspections performed by the NRC's Vendor Inspection Branch that have been distributed to the inspected organizations during the period from October 1990 through December 1990

  18. Licensee contractor and vendor inspection status report

    International Nuclear Information System (INIS)

    1993-05-01

    This periodical covers the results of inspections performed by the NRC's Vendor Inspection Branch that have been distributed to the inspected organizations during the period from January 1993 through March 1993

  19. Licensee contractor and vendor inspection status report

    International Nuclear Information System (INIS)

    1991-05-01

    This periodical covers the results of inspections performed by the NRC's Vendor Inspection Branch that have been distributed to the inspected organization during the period from January 1991 through March 1991

  20. Licensee contractor and Vendor Inspection status report

    International Nuclear Information System (INIS)

    1993-01-01

    This periodical covers the results of inspections performed by the NRC's Vendor Inspection Branch that have been distributed to the inspected organizations during the period from October 1992 through December 1992

  1. Licensee contractor and vendor inspection status report

    International Nuclear Information System (INIS)

    1989-12-01

    This periodical covers the results of inspections performed by the NRC's Vendor Inspection Branch that have been distributed to the inspected organizations during the period from July 1989 through September 1989

  2. Lean Construction Applications for Bridge Inspection

    Science.gov (United States)

    2017-10-01

    Lean philosophy was used to analyze the efficiency of bridge inspection. Emphasis was put on identifying activities that add value to the final output, an owner approved bridge inspection report. 26 bridge inspections were shadowed. Time spent on bri...

  3. Licensee Contractor and vendor inspection status report

    International Nuclear Information System (INIS)

    1992-01-01

    This periodical covers the results of inspections performed by the NRC's Vendor Inspection Branch that have been distributed to the inspected organization during the period from October through December 1991

  4. Licensee contractor and vendor inspection status report

    International Nuclear Information System (INIS)

    1993-08-01

    This periodical covers the results of inspections performed by the NRC's Vendor Inspection Branch that have been distributed to the inspected organizations during the period from April through June 1993

  5. Licensee contractor and vendor inspection status report

    International Nuclear Information System (INIS)

    1991-09-01

    This periodical covers the results of inspections performed by the NRC's Vendor Inspection Branch that have been distributed to the inspected organization during the period from April 1991 through June 1991

  6. Automated visual inspection of moving custom parts

    CSIR Research Space (South Africa)

    Davrajh, S

    2008-01-01

    Full Text Available frequencies than batched produced parts. This higher frequency of inspection significantly impacts inspection times, and inherently, production rates. An effective, diverse, accurate, robust, and time efficient method for inspecting custom parts is therefore...

  7. Licensee contractor and Vendor Inspection status report

    International Nuclear Information System (INIS)

    1992-05-01

    This periodical covers the results of inspections performed by the NRC's Vendor Inspection Branch that have been distributed to the inspected organizations during the period from January through March 1992

  8. Licensee contractor and vendor inspection status report

    International Nuclear Information System (INIS)

    1990-07-01

    This periodical covers the results of inspections performed by the NRC's Vendor Inspection Branch that have been distributed to the inspected organization during the period from January 1990 through March 1990

  9. Licensee contractor and vendor inspection status report

    International Nuclear Information System (INIS)

    1990-01-01

    This periodical covers the results of inspections performed by the NRC's Vendor Inspection Branch that have been distributed to the inspected organizations during the period from October 1989 through December 1989

  10. Licensee contractor and vendor inspection status report

    International Nuclear Information System (INIS)

    1992-11-01

    This periodical covers the results of inspections performed by the NRC's Vendor Inspection Branch that have been distributed to the inspected organization during the period from July 1992 through September 1992

  11. Licensee contractor and vendor inspection status report

    International Nuclear Information System (INIS)

    1991-10-01

    This periodical covers the results of inspections performed by the NRC's Vendor Inspection Branch that have been distributed to the inspected organization during the period from July 1991 through September 1991

  12. Licensee contractor and vendor inspection status report

    International Nuclear Information System (INIS)

    1990-11-01

    This periodical covers the results of inspections performed by the NRC's Vendor Inspection Branch that have been distributed to the inspected organization during the period from April 1990 through June 1990

  13. Improving inspection reliability through operator selection and training

    International Nuclear Information System (INIS)

    McGrath, Bernard; Carter, Luke

    2013-01-01

    A number of years ago the UK's Health and Safety Executive sponsored a series of three PANI projects investigating the application of manual ultrasonics, which endeavoured to establish the necessary steps that ensure a reliable inspection is performed. The results of the three projects were each reported separately on completion and also presented at number of international conferences. This paper summarises the results of these projects from the point of view of operator performance. The correlation of operator ultrasonic performance with results of aptitude tests is presented along with observations on the impact of training and qualifications of the operators. The results lead to conclusions on how the selection and training of operators could be modified to improve reliability of inspections.

  14. Deployment Plan for Small Roving Annulus Inspection Vehicle

    International Nuclear Information System (INIS)

    Minichan, R.

    2002-01-01

    The Small Roving Annulus Inspection Vehicle (SRAIV) is a modified commercially available wall crawler designed to supplement the In-Service Inspection (ISI) of Savannah River Site (SRS) Waste tanks. The SRAIV provides an improved capability to achieve a more complete inspection of the tank walls than existing methods. The SRAIV will be deployed through annulus risers in the tank to gain access to tank walls requiring inspection. The SRAIV will be deployed using a manually operated deployment pole and will be coupled to the wall using permanent magnet wheels. Navigation will be performed from the remote console where pictorial views can be displayed from the on-board cameras. The unit will incorporate multiple UT transducers for traditional weld examination. In addition, a specially developed Tandem Synthetic Aperture Focusing Technique (TSAFT) UT scanning bridge can be attached to provide further investigation of the knuckle region while the vehicle remains on the vertical surface of the tank wall. In summary, the SRAIV will provide features that enhance and expand the capability of the SRS ISI program

  15. Development of In-situation radioactivity Inspection system

    International Nuclear Information System (INIS)

    Min, Sujung; Lee, Sanghun; Kim, Miyoung; Kim, Myungjin; Lee, Unjang; Park, Jungkyun

    2015-01-01

    Many Korean people worry about radioactive contamination of Japanese and Korean marine products. Radioactive contamination of processed foodstuffs, livestock, marine products, farm products imported from Japan and fishes caught in coastal waters of Korea has become an important social issue. Radioactivity inspections of those foods are executed manually with portable measuring instruments or at labs using their samples. In consequence, there are some problem of time delay and low reliability. To protect the health of citizens from radioactivity contained in Japanese marine products imported to Korea, a system to inspect radioactivity in real time will be developed. The system is to measure the radioactivity level of farm and marine products continuously and automatically at inspection sites of an agency checking radiation of imported foodstuffs to determine radioactive contamination. Product performance assessment and tests will be conducted later. When the system develops and its commercialization begins, people's anxiety about radioactive contamination of foods after the Fukushima nuclear accident will be eased and people will be able to trust the radioactive inspection

  16. Development of In-situation radioactivity Inspection system

    Energy Technology Data Exchange (ETDEWEB)

    Min, Sujung; Lee, Sanghun; Kim, Miyoung; Kim, Myungjin; Lee, Unjang [ORIONENC Co., Seoul (Korea, Republic of); Park, Jungkyun [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-05-15

    Many Korean people worry about radioactive contamination of Japanese and Korean marine products. Radioactive contamination of processed foodstuffs, livestock, marine products, farm products imported from Japan and fishes caught in coastal waters of Korea has become an important social issue. Radioactivity inspections of those foods are executed manually with portable measuring instruments or at labs using their samples. In consequence, there are some problem of time delay and low reliability. To protect the health of citizens from radioactivity contained in Japanese marine products imported to Korea, a system to inspect radioactivity in real time will be developed. The system is to measure the radioactivity level of farm and marine products continuously and automatically at inspection sites of an agency checking radiation of imported foodstuffs to determine radioactive contamination. Product performance assessment and tests will be conducted later. When the system develops and its commercialization begins, people's anxiety about radioactive contamination of foods after the Fukushima nuclear accident will be eased and people will be able to trust the radioactive inspection.

  17. Fully Employing Software Inspections Data

    Science.gov (United States)

    Shull, Forrest; Feldmann, Raimund L.; Seaman, Carolyn; Regardie, Myrna; Godfrey, Sally

    2009-01-01

    Software inspections provide a proven approach to quality assurance for software products of all kinds, including requirements, design, code, test plans, among others. Common to all inspections is the aim of finding and fixing defects as early as possible, and thereby providing cost savings by minimizing the amount of rework necessary later in the lifecycle. Measurement data, such as the number and type of found defects and the effort spent by the inspection team, provide not only direct feedback about the software product to the project team but are also valuable for process improvement activities. In this paper, we discuss NASA's use of software inspections and the rich set of data that has resulted. In particular, we present results from analysis of inspection data that illustrate the benefits of fully utilizing that data for process improvement at several levels. Examining such data across multiple inspections or projects allows team members to monitor and trigger cross project improvements. Such improvements may focus on the software development processes of the whole organization as well as improvements to the applied inspection process itself.

  18. Advanced ultrasonic inspections

    International Nuclear Information System (INIS)

    Ghia, S.

    1990-08-01

    Acoustic Emission (AE) continuous monitoring and periodical inspections by advanced ultrasonic have been applied to evaluate defect evolution within a PWR reduced scale (1:5) pressure vessel subjected to cyclic mechanical fatigue test. This experimental activity has been carried out in the frame of the Primary Circuit Component Life Prediction programme. In the time period covered by this report actions were performed as following: (1) Ultrasonic examination by multifrequency acoustic holography to evaluate defect evolution subsequently repair and heat treatment of the R2 vessel carried out in March 1988. For the purpose, measurements were performed both at 0 and 200 bar of internal pressure. As uniformity of the procedures adopted, for calibration and testing, made the results comparable with the previous ones no evidence for significant growing of the examined defects has been found. (2) Acoustic emission monitoring has then been carried out during fatigue test from 416000 to 565000 fatigue cycles. Analysis of a large amount of data has been performed paying particular attention to the distinction between friction phenomena and crack growth in order to obtain a correct diagnosis of flaw evolution. The signal duration distribution and the correlation of AE appearance time versus load cycle phase were considered to characterise stick-slip processes. A general intensification of AE activity has been recorded during this last period of monitoring and previous known AE sources were confirmed together with the appearance of new AE sources some of them correlable with real defects

  19. From PISC to risk informed inspection

    International Nuclear Information System (INIS)

    Crutzen, S.; Lemaitre, P.; Fabbri, L.

    1998-01-01

    In this paper the correlation between inspection effectiveness, inspection qualification and risk informed inspection will be treated in view of harmonisation of inspection of nuclear plant components. Through the different phases of the PISC programme the necessity has been demonstrated to show the effectiveness of the inspection through a formal process of qualification in order to ensure that a certain level of effectiveness has been reached. Inspection qualification is indeed the way to quantify the capability level of inspection techniques used. The targets to be met by the inspection is information which should be obtained from risk based analyses. (author)

  20. INIS: Database manual

    International Nuclear Information System (INIS)

    2003-01-01

    This document is one in a series of publications known as the INIS Reference Series. It is intended for users of INIS (International Nuclear Information System) output data on various media (FTP file, CD-ROM, e-mail file, earlier magnetic tape, cartridge, etc.). This manual provides a description of each data element including information on contents, structure and usage as well as historical overview of additions, deletions and changes of data elements and their contents that have taken place over the years. Each record contains certain control data fields (001-009), one, two or three bibliographic levels, a set of descriptors, and zero, one or more abstracts, one in English and optionally one or more in another language. In order to facilitate the description of the system, the sequence of data elements is based on the input or, as it is internally called, worksheet format which differs from the exchange format described in the manual IAEA-INIS-7. A separate section is devoted to each data element and deviations from the exchange format are indicated whenever present. As the Record Leader and the Directory are sufficiently explained in Chapter 3.1 of IAEA-INIS-7, the contents of this manual are limited to control fields and data fields; the detailed explanations are intended to supplement the basic information given in Chapter 3.2 of IAEA-INIS-7. Bibliographic levels are used to identify component parts of a publication, i.e. chapters in a book, articles in a journal issue, conference papers in a proceedings volume. All bibliographic levels contained in a record are given in a control data field. Each bibliographic level identifier appears in the subdirectory with a pointer to its position in the record

  1. MAP user's manual copyright

    International Nuclear Information System (INIS)

    Pillsbury, R.D. Jr.

    1991-12-01

    The program MITMAP represents a set of general purpose, two- dimensional, finite element programs for the calculation of magnetic fields. It consists of the program MAP and MAP2DJ. The two programs are used to solve different electromagnetic problems, but they have a common set of subrountines for pre- and postprocessing. Originally separate programs, they have been combined to make modification easier. The manuals, however, will remain separate. The program MAP is described in this manual. MAP is applicable to the class of problems with two-dimensional-planar or axisymmetric - geometries, in which the current density and the magnetic vector potential have only a single nonvanishing component. The single component is associated with the direction that is perpendicular to the plane of the problem and is invariant with respect to that direction. Maxwell's equations can be reduced to a solver diffusion equation in terms of the single, nonvanishing component of the magnetic vector potential for planar problems and to a single component of a vector potential for planar problems and to a single component of a vector diffusion equation for axisymmetric problems. The magnetic permeability appears in the governing equation. The permeability may be a function of the magnetic flux density. In addition, any electrically conducting material present will have eddy currents induced by a time varying magnetic field. These eddy currents must be included in the solution process. This manual provides a description of the structure of the input data and output for the program. There are several example problems presented that illustrate the major program features. Appendices are included that contain a derivation of the governing equations and the application of the finite element method to the solution of the equations

  2. Modern TTL circuits manual

    CERN Document Server

    Marston, R M

    2013-01-01

    Modern TTL Circuits Manual provides an introduction to the basic principles of Transistor-Transistor Logic (TTL). This book outlines the major features of the 74 series of integrated circuits (ICs) and introduces the various sub-groups of the TTL family.Organized into seven chapters, this book begins with an overview of the basics of digital ICs. This text then examines the symbology and mathematics of digital logic. Other chapters consider a variety of topics, including waveform generator circuitry, clocked flip-flop and counter circuits, special counter/dividers, registers, data latches, com

  3. Manual of Decolonization

    DEFF Research Database (Denmark)

    Gigone, Fabio

    2010-01-01

    During a residency in Bethlehem, Venice-based design and research studio Salottobuono formulated a 'strategy of subversion' for Israeli settlements in the West Bank. From this comes the elegant Manual of Decolonization; a generic but detailed resource for all post-occupation scenarios. Assessing...... how evacuated and imposed structures can be transformed in collaboration with local stakeholders, the book's plans, models and projections are divided into themes like 'De-parcelling', 'Re-combining' and 'Un-roofing'; landscape, nature and materials are considered at length. The outcome is an open...

  4. CMOS circuits manual

    CERN Document Server

    Marston, R M

    1995-01-01

    CMOS Circuits Manual is a user's guide for CMOS. The book emphasizes the practical aspects of CMOS and provides circuits, tables, and graphs to further relate the fundamentals with the applications. The text first discusses the basic principles and characteristics of the CMOS devices. The succeeding chapters detail the types of CMOS IC, including simple inverter, gate and logic ICs and circuits, and complex counters and decoders. The last chapter presents a miscellaneous collection of two dozen useful CMOS circuits. The book will be useful to researchers and professionals who employ CMOS circu

  5. Coal marketing manual 1987

    Energy Technology Data Exchange (ETDEWEB)

    1987-01-01

    This manual provides information on the international coal market in tabulated format. Statistics are presented for the Australian coal industry, exports, currency movements, world coal production, coal and coke imports and exports. Detailed information is provided on the Australian coal industry including mine specific summaries. Pricing summaries for thermal and coking coal in 1987, coal quality standards and specifications, trends in coal prices and stocks. Imports and exports for World coal and coke, details of shipping, international ports and iron and steel production. An exporters index of Australian and overseas companies with industry and government contacts is included. 15 figs., 67 tabs.

  6. Optoelectronics circuits manual

    CERN Document Server

    Marston, R M

    2013-01-01

    Optoelectronics Circuits Manual covers the basic principles and characteristics of the best known types of optoelectronic devices, as well as the practical applications of many of these optoelectronic devices. The book describes LED display circuits and LED dot- and bar-graph circuits and discusses the applications of seven-segment displays, light-sensitive devices, optocouplers, and a variety of brightness control techniques. The text also tackles infrared light-beam alarms and multichannel remote control systems. The book provides practical user information and circuitry and illustrations.

  7. Timergenerator circuits manual

    CERN Document Server

    Marston, R M

    2013-01-01

    Timer/Generator Circuits Manual is an 11-chapter text that deals mainly with waveform generator techniques and circuits. Each chapter starts with an explanation of the basic principles of its subject followed by a wide range of practical circuit designs. This work presents a total of over 300 practical circuits, diagrams, and tables.Chapter 1 outlines the basic principles and the different types of generator. Chapters 2 to 9 deal with a specific type of waveform generator, including sine, square, triangular, sawtooth, and special waveform generators pulse. These chapters also include pulse gen

  8. Health physics instrument manual

    International Nuclear Information System (INIS)

    Gupton, E.D.

    1978-08-01

    The purpose of this manual is to provide apprentice health physics surveyors and other operating groups not directly concerned with radiation detection instruments a working knowledge of the radiation detection and measuring instruments in use at the Laboratory. The characteristics and applications of the instruments are given. Portable instruments, stationary instruments, personnel monitoring instruments, sample counters, and miscellaneous instruments are described. Also, information sheets on calibration sources, procedures, and devices are included. Gamma sources, beta sources, alpha sources, neutron sources, special sources, a gamma calibration device for badge dosimeters, and a calibration device for ionization chambers are described

  9. IMAGE User Manual

    Energy Technology Data Exchange (ETDEWEB)

    Stehfest, E; De Waal, L; Oostenrijk, R.

    2010-09-15

    This user manual contains the basic information for running the simulation model IMAGE ('Integrated Model to Assess the Global Environment') of PBL. The motivation for this report was a substantial restructuring of the source code for IMAGE version 2.5. The document gives concise content information about the submodels, tells the user how to install the program, describes the directory structure of the run environment, shows how scenarios have to be prepared and run, and gives insight in the restart functionality.

  10. Radioanalytical methods manual

    International Nuclear Information System (INIS)

    Chiu, N.W.; Dean, J.R.

    1986-01-01

    This Radioanalytical Methods manual is comprised of 12 chapters. It includes a review of the pertinent literature up to the end of 1982 pertaining to the measurement of the radioactive species listed under the terms of the contract. Included is methodology recommended for the decompositions of soils, tailings, ores, biological samples and air filters. Detailed analytical methodology for the measurement of gross alpha, gross beta, gross gamma, uranium, radium-226, radium-228, lead-210, thorium-232, thorium-230, thorium-228, total thorium, radon-222, radon-220 and radon-219 is presented

  11. ASSERT-4 user's manual

    International Nuclear Information System (INIS)

    Judd, R.A.; Tahir, A.; Carver, M.B.; Stewart, D.G.; Thibeault, P.R.; Rowe, D.S.

    1984-09-01

    ASSERT-4 is an advanced subchannel code being developed primarily to model single- and two-phase flow and heat transfer in horizontal rod bundles. This manual is intended to facilitate the application of this code to the analysis of flow in reactor fuel channels. It contains a brief description of the thermalhydraulic model and ASSERT-4 solution scheme, and other information required by users. This other information includes a detailed discussion of input data requirements, a sample problem and solution, and information describing how to access and run ASSERT-4 on the Chalk River computers

  12. Rural Gas Program manual

    Energy Technology Data Exchange (ETDEWEB)

    1987-11-01

    The intent and purpose of this manual is to describe the various guideliness and administrative procedures associated with the Alberta Rural Gas Program and to consolidate and expand upon the legislation under which the Program has been developed. It is intended primarily for the use and information of rural gas distributors, their agents, and other private or government parties having an interest in the Rural Gas Program. Information is presented on: rural gas franchises, technical applications, contracts and tenders, determination of system capital costs for grant support, grants, Gas Alberta brokerage arrangements, insurance coverage, utility rights-of-way, and lien notes.

  13. Health and safety manual

    International Nuclear Information System (INIS)

    1980-02-01

    The manual consists of the following chapters: general policies and administration; the Environmental Health and Safety Department; the Medical Services Department: biological hazards; chemical safety; confined space entry; cryogenic safety; electrical safety; emergency plans; engineering and construction; evacuations, trenching, and shoring; fire safety; gases, flammable and compressed; guarding, mechanical; ladders and scaffolds, work surfaces; laser safety; materials handling and storage; noise; personal protective equipment; pressure safety; radiation safety, ionizing and non-ionizing; sanitation; seismic safety; training, environmental health and safety; tools, power and hand-operated; traffic and transportation; and warning signs and devices

  14. Astronaut training manual

    Science.gov (United States)

    Coleman, E. A.

    1980-01-01

    Scientific information from previous space flights, space medicine, exercise physiology, and sports medicine was used to prepare a physical fitness manual suitable for use by members of the NASA astronaut population. A variety of scientifically valid exercise programs and activities suitable for the development of physical fitness are provided. Programs, activities, and supportive scientific data are presented in a concise, easy to read format so as to permit the user to select his or her mode of training with confidence and devote time previously spent experimenting with training routines to preparation for space flight. The programs and activities included were tested and shown to be effective and enjoyable.

  15. RADTRAN 6 Technical Manual

    Energy Technology Data Exchange (ETDEWEB)

    Weiner, Ruth F. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Neuhauser, Karen Sieglinde [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Heames, Terence John [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); O' Donnell, Brandon M. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Dennis, Matthew L. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2014-01-01

    This Technical Manual contains descriptions of the calculation models and mathematical and numerical methods used in the RADTRAN 6 computer code for transportation risk and consequence assessment. The RADTRAN 6 code combines user-supplied input data with values from an internal library of physical and radiological data to calculate the expected radiological consequences and risks associated with the transportation of radioactive material. Radiological consequences and risks are estimated with numerical models of exposure pathways, receptor populations, package behavior in accidents, and accident severity and probability.

  16. RADTRAN 6 technical manual.

    Energy Technology Data Exchange (ETDEWEB)

    Weiner, Ruth F.; Neuhauser, Karen Sieglinde; Heames, Terence John; O' Donnell, Brandon M.; Dennis, Matthew L.

    2014-01-01

    This Technical Manual contains descriptions of the calculation models and mathematical and numerical methods used in the RADTRAN 6 computer code for transportation risk and consequence assessment. The RADTRAN 6 code combines user-supplied input data with values from an internal library of physical and radiological data to calculate the expected radiological consequences and risks associated with the transportation of radioactive material. Radiological consequences and risks are estimated with numerical models of exposure pathways, receptor populations, package behavior in accidents, and accident severity and probability.

  17. FISPACT 97: user manual

    International Nuclear Information System (INIS)

    Forrest, R.A.; Sublet, J.-Ch.

    1997-05-01

    FISPACT is the inventory code included in the European Activation System (EASY). A new version of FISPACT: FISPACT-97 has been developed and this report is the User manual for the code. It explains the use of all the code words used in the input file to specify a FISPACT run and describes how all the data files are connected. A series of appendices cover the working of the code and the physical and mathematical details. Background information on the data files and extensive examples of input files suitable for various applications are included. (Author)

  18. Timber designers' manual

    CERN Document Server

    Ozelton, E C

    2008-01-01

    This major reference manual covers both overall and detail design of structural timber, including aspects such as shear deflection, creep, dynamic and lateral stability considerations for flexural members.Available for the first time in paperback, the Third Edition was substantially revised to take account of the many changes since the previous edition was published in 1984. It is based on British Standard BS 5268-2: 2002, which brought design concepts closer to European practice and Eurocode 5.Features of the Third Edition include:* information on bolt values including

  19. NASCAP programmer's reference manual

    Science.gov (United States)

    Mandell, M. J.; Stannard, P. R.; Katz, I.

    1993-05-01

    The NASA Charging Analyzer Program (NASCAP) is a computer program designed to model the electrostatic charging of complicated three-dimensional objects, both in a test tank and at geosynchronous altitudes. This document is a programmer's reference manual and user's guide. It is designed as a reference to experienced users of the code, as well as an introduction to its use for beginners. All of the many capabilities of NASCAP are covered in detail, together with examples of their use. These include the definition of objects, plasma environments, potential calculations, particle emission and detection simulations, and charging analysis.

  20. Percept User Manual.

    Energy Technology Data Exchange (ETDEWEB)

    Carnes, Brian [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Kennon, Stephen Ray [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2017-05-01

    This document is the main user guide for the Sierra/Percept capabilities including the mesh_adapt and mesh_transfer tools. Basic capabilities for uniform mesh refinement (UMR) and mesh transfers are discussed. Examples are used to provide illustration. Future versions of this manual will include more advanced features such as geometry and mesh smoothing. Additionally, all the options for the mesh_adapt code will be described in detail. Capabilities for local adaptivity in the context of offline adaptivity will also be included. This page intentionally left blank.

  1. Optoelectronics circuits manual

    CERN Document Server

    Marston, R M

    1999-01-01

    This manual is a useful single-volume guide specifically aimed at the practical design engineer, technician, and experimenter, as well as the electronics student and amateur. It deals with the subject in an easy to read, down to earth, and non-mathematical yet comprehensive manner, explaining the basic principles and characteristics of the best known devices, and presenting the reader with many practical applications and over 200 circuits. Most of the ICs and other devices used are inexpensive and readily available types, with universally recognised type numbers.The second edition

  2. Plant inspection and maintenance technology

    International Nuclear Information System (INIS)

    Miyahara, Masatoshi; Kanazawa, Masafumi

    1995-01-01

    The article reports on information systems and related tools that support routine inspection and preventive maintenance activities, which contribute to safer plant operation and increase plant operating duty. Tools include the Mitsubishi Electric Reliability and Availability Upgrade Program-Nuclear (MELRAP-N), which supports the general evolution of industry operating experiences, periodic component replacement management, management of discontinued and modified components, periodic inspection item management, and periodic inspection workplace management. The article also introduces a comprehensive preventive maintenance management system currently under development. (author)

  3. Non-destructive inservice inspections

    International Nuclear Information System (INIS)

    Kauppinen, P.; Sarkimo, M.; Lahdenperae, K.

    1998-01-01

    In order to assess the possible damages occurring in the components and structures of operating nuclear power plants during service the main components and structures are periodically inspected by non-destructive testing techniques. The reliability of non-destructive testing techniques applied in these inservice inspections is of major importance because the decisions concerning the needs for repair of components are mainly based on the results of inspections. One of the targets of this research program has been to improve the reliability of non-destructive testing. This has been addressed in the sub-projects which are briefly summarised here. (author)

  4. Radiological control manual. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Kloepping, R.

    1996-05-01

    This Lawrence Berkeley National Laboratory Radiological Control Manual (LBNL RCM) has been prepared to provide guidance for site-specific additions, supplements and interpretation of the DOE Radiological Control Manual. The guidance provided in this manual is one methodology to implement the requirements given in Title 10 Code of Federal Regulations Part 835 (10 CFR 835) and the DOE Radiological Control Manual. Information given in this manual is also intended to provide demonstration of compliance to specific requirements in 10 CFR 835. The LBNL RCM (Publication 3113) and LBNL Health and Safety Manual Publication-3000 form the technical basis for the LBNL RPP and will be revised as necessary to ensure that current requirements from Rules and Orders are represented. The LBNL RCM will form the standard for excellence in the implementation of the LBNL RPP.

  5. Radiological control manual. Revision 1

    International Nuclear Information System (INIS)

    Kloepping, R.

    1996-05-01

    This Lawrence Berkeley National Laboratory Radiological Control Manual (LBNL RCM) has been prepared to provide guidance for site-specific additions, supplements and interpretation of the DOE Radiological Control Manual. The guidance provided in this manual is one methodology to implement the requirements given in Title 10 Code of Federal Regulations Part 835 (10 CFR 835) and the DOE Radiological Control Manual. Information given in this manual is also intended to provide demonstration of compliance to specific requirements in 10 CFR 835. The LBNL RCM (Publication 3113) and LBNL Health and Safety Manual Publication-3000 form the technical basis for the LBNL RPP and will be revised as necessary to ensure that current requirements from Rules and Orders are represented. The LBNL RCM will form the standard for excellence in the implementation of the LBNL RPP

  6. BBC users manual

    International Nuclear Information System (INIS)

    Ltterst, R.F.; Sutcliffe, W.G.; Warshaw, S.I.

    1977-11-01

    BBC is a two-dimensional, multifluid Eulerian hydro-radiation code based on KRAKEN and some subsequent ideas. It was developed in the explosion group in T-Division as a basic two-dimensional code to which various types of physics can be added. For this reason BBC is a FORTRAN (LRLTRAN) code. In order to gain the 2-to-1 to 4-to-1 speed advantage of the STACKLIB software on the 7600's and to be able to execute at high speed on the STAR, the vector extensions of LRLTRAN (STARTRAN) are used throughout the code. Either cylindrical- or slab-type problems can be run on BBC. The grid is bounded by a rectangular band of boundary zones. The interfaces between the regular and boundary zones can be selected to be either rigid or nonrigid. The setup for BBC problems is described in the KEG Manual and LEG Manual. The difference equations are described in BBC Hydrodynamics. Basic input and output for BBC are described

  7. SYVAC3 manual

    International Nuclear Information System (INIS)

    Andres, T.H.

    2000-01-01

    SYVAC3 (Systems Variability Analysis Code, generation 3) is a computer program that implements a method called systems variability analysis to analyze the behaviour of a system in the presence of uncertainty. This method is based on simulating the system many times to determine the variation in behaviour it can exhibit. SYVAC3 specializes in systems representing the transport of contaminants, and has several features to simplify the modelling of such systems. It provides a general tool for estimating environmental impacts from the dispersal of contaminants. This report describes the use and structure of SYVAC3. It is intended for modellers, programmers, operators and reviewers who deal with simulation codes based on SYVAC3. From this manual they can learn how to link a model with SYVAC3, how to set up an input file, and how to extract results from output files. The manual lists the subroutines of SYVAC3 that are available for use by models, and describes their argument lists. It also gives an overview of how routines in the File Reading Package, the Parameter Sampling Package and the Time Series Package can be used by programs outside of SYVAC3. (author)

  8. Energy statistics manual

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-01

    The Manual is written in a question-and-answer format. The points developed are introduced with a basic question, such as: What do people mean by 'fuels' and 'energy'? What units are used to express oil? How are energy data presented? Answers are given in simple terms and illustrated by graphs, charts and tables. More technical explanations are found in the annexes. The Manual contains seven chapters. The first one presents the fundamentals of energy statistics, five chapters deal with the five different fuels (electricity and heat; natural gas; oil; solid fuels and manufactured gases; renewables and waste) and the last chapter explains the energy balance. Three technical annexes and a glossary are also included. For the five chapters dedicated to the fuels, there are three levels of reading: the first one contains general information on the subject, the second one reviews issues which are specific to the joint IEA/OECD-Eurostat-UNECE questionnaires and the third one focuses on the essential elements of the subject. 43 figs., 22 tabs., 3 annexes.

  9. MELCOR computer code manuals

    Energy Technology Data Exchange (ETDEWEB)

    Summers, R.M.; Cole, R.K. Jr.; Smith, R.C.; Stuart, D.S.; Thompson, S.L. [Sandia National Labs., Albuquerque, NM (United States); Hodge, S.A.; Hyman, C.R.; Sanders, R.L. [Oak Ridge National Lab., TN (United States)

    1995-03-01

    MELCOR is a fully integrated, engineering-level computer code that models the progression of severe accidents in light water reactor nuclear power plants. MELCOR is being developed at Sandia National Laboratories for the U.S. Nuclear Regulatory Commission as a second-generation plant risk assessment tool and the successor to the Source Term Code Package. A broad spectrum of severe accident phenomena in both boiling and pressurized water reactors is treated in MELCOR in a unified framework. These include: thermal-hydraulic response in the reactor coolant system, reactor cavity, containment, and confinement buildings; core heatup, degradation, and relocation; core-concrete attack; hydrogen production, transport, and combustion; fission product release and transport; and the impact of engineered safety features on thermal-hydraulic and radionuclide behavior. Current uses of MELCOR include estimation of severe accident source terms and their sensitivities and uncertainties in a variety of applications. This publication of the MELCOR computer code manuals corresponds to MELCOR 1.8.3, released to users in August, 1994. Volume 1 contains a primer that describes MELCOR`s phenomenological scope, organization (by package), and documentation. The remainder of Volume 1 contains the MELCOR Users Guides, which provide the input instructions and guidelines for each package. Volume 2 contains the MELCOR Reference Manuals, which describe the phenomenological models that have been implemented in each package.

  10. CTF Theory Manual

    Energy Technology Data Exchange (ETDEWEB)

    Avramova, Maria N. [Pennsylvania State Univ., University Park, PA (United States); Salko, Robert K. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2016-05-25

    Coolant-Boiling in Rod Arrays|Two Fluids (COBRA-TF) is a thermal/ hydraulic (T/H) simulation code designed for light water reactor (LWR) vessel analysis. It uses a two-fluid, three-field (i.e. fluid film, fluid drops, and vapor) modeling approach. Both sub-channel and 3D Cartesian forms of 9 conservation equations are available for LWR modeling. The code was originally developed by Pacific Northwest Laboratory in 1980 and had been used and modified by several institutions over the last few decades. COBRA-TF also found use at the Pennsylvania State University (PSU) by the Reactor Dynamics and Fuel Management Group (RDFMG) and has been improved, updated, and subsequently re-branded as CTF. As part of the improvement process, it was necessary to generate sufficient documentation for the open-source code which had lacked such material upon being adopted by RDFMG. This document serves mainly as a theory manual for CTF, detailing the many two-phase heat transfer, drag, and important accident scenario models contained in the code as well as the numerical solution process utilized. Coding of the models is also discussed, all with consideration for updates that have been made when transitioning from COBRA-TF to CTF. Further documentation outside of this manual is also available at RDFMG which focus on code input deck generation and source code global variable and module listings.

  11. LCS Users Manual

    International Nuclear Information System (INIS)

    Redd, A.J.; Ignat, D.W.

    1998-01-01

    The Lower Hybrid Simulation Code (LSC) is a computational model of lower hybrid current drive in the presence of an electric field. Details of geometry, plasma profiles, and circuit equations are treated. Two-dimensional velocity space effects are approximated in a one-dimensional Fokker-Planck treatment. The LSC was originally written to be a module for lower hybrid current drive called by the Tokamak Simulation Code (TSC), which is a numerical model of an axisymmetric tokamak plasma and the associated control systems. The TSC simulates the time evolution of a free boundary plasma by solving the MHD equations on a rectangular computational grid. The MHD equations are coupled to the external circuits (representing poloidal field coils) through the boundary conditions. The code includes provisions for modeling the control system, external heating, and fusion heating. The LSC module can also be called by the TRANSP code. TRANSP represents the plasma with an axisymmetric, fixed-boundary model and focuses on calculation of plasma transport to determine transport coefficients from data on power inputs and parameters reached. This manual covers the basic material needed to use the LSC. If run in conjunction with TSC, the ''TSC Users Manual'' should be consulted. If run in conjunction with TRANSP, on-line documentation will be helpful. A theoretical background of the governing equations and numerical methods is given. Information on obtaining, compiling, and running the code is also provided

  12. MELCOR computer code manuals

    International Nuclear Information System (INIS)

    Summers, R.M.; Cole, R.K. Jr.; Smith, R.C.; Stuart, D.S.; Thompson, S.L.; Hodge, S.A.; Hyman, C.R.; Sanders, R.L.

    1995-03-01

    MELCOR is a fully integrated, engineering-level computer code that models the progression of severe accidents in light water reactor nuclear power plants. MELCOR is being developed at Sandia National Laboratories for the U.S. Nuclear Regulatory Commission as a second-generation plant risk assessment tool and the successor to the Source Term Code Package. A broad spectrum of severe accident phenomena in both boiling and pressurized water reactors is treated in MELCOR in a unified framework. These include: thermal-hydraulic response in the reactor coolant system, reactor cavity, containment, and confinement buildings; core heatup, degradation, and relocation; core-concrete attack; hydrogen production, transport, and combustion; fission product release and transport; and the impact of engineered safety features on thermal-hydraulic and radionuclide behavior. Current uses of MELCOR include estimation of severe accident source terms and their sensitivities and uncertainties in a variety of applications. This publication of the MELCOR computer code manuals corresponds to MELCOR 1.8.3, released to users in August, 1994. Volume 1 contains a primer that describes MELCOR's phenomenological scope, organization (by package), and documentation. The remainder of Volume 1 contains the MELCOR Users Guides, which provide the input instructions and guidelines for each package. Volume 2 contains the MELCOR Reference Manuals, which describe the phenomenological models that have been implemented in each package

  13. ARDS User Manual

    Science.gov (United States)

    Fleming, David P.

    2001-01-01

    Personal computers (PCs) are now used extensively for engineering analysis. their capability exceeds that of mainframe computers of only a few years ago. Programs originally written for mainframes have been ported to PCs to make their use easier. One of these programs is ARDS (Analysis of Rotor Dynamic Systems) which was developed at Arizona State University (ASU) by Nelson et al. to quickly and accurately analyze rotor steady state and transient response using the method of component mode synthesis. The original ARDS program was ported to the PC in 1995. Several extensions were made at ASU to increase the capability of mainframe ARDS. These extensions have also been incorporated into the PC version of ARDS. Each mainframe extension had its own user manual generally covering only that extension. Thus to exploit the full capability of ARDS required a large set of user manuals. Moreover, necessary changes and enhancements for PC ARDS were undocumented. The present document is intended to remedy those problems by combining all pertinent information needed for the use of PC ARDS into one volume.

  14. Electronic Commerce user manual

    Energy Technology Data Exchange (ETDEWEB)

    1992-04-10

    This User Manual supports the Electronic Commerce Standard System. The Electronic Commerce Standard System is being developed for the Department of Defense of the Technology Information Systems Program at the Lawrence Livermore National Laboratory, operated by the University of California for the Department of Energy. The Electronic Commerce Standard System, or EC as it is known, provides the capability for organizations to conduct business electronically instead of through paper transactions. Electronic Commerce and Computer Aided Acquisition and Logistics Support, are two major projects under the DoD`s Corporate Information Management program, whose objective is to make DoD business transactions faster and less costly by using computer networks instead of paper forms and postage. EC runs on computers that use the UNIX operating system and provides a standard set of applications and tools that are bound together by a common command and menu system. These applications and tools may vary according to the requirements of the customer or location and may be customized to meet the specific needs of an organization. Local applications can be integrated into the menu system under the Special Databases & Applications option on the EC main menu. These local applications will be documented in the appendices of this manual. This integration capability provides users with a common environment of standard and customized applications.

  15. Electronic Commerce user manual

    Energy Technology Data Exchange (ETDEWEB)

    1992-04-10

    This User Manual supports the Electronic Commerce Standard System. The Electronic Commerce Standard System is being developed for the Department of Defense of the Technology Information Systems Program at the Lawrence Livermore National Laboratory, operated by the University of California for the Department of Energy. The Electronic Commerce Standard System, or EC as it is known, provides the capability for organizations to conduct business electronically instead of through paper transactions. Electronic Commerce and Computer Aided Acquisition and Logistics Support, are two major projects under the DoD's Corporate Information Management program, whose objective is to make DoD business transactions faster and less costly by using computer networks instead of paper forms and postage. EC runs on computers that use the UNIX operating system and provides a standard set of applications and tools that are bound together by a common command and menu system. These applications and tools may vary according to the requirements of the customer or location and may be customized to meet the specific needs of an organization. Local applications can be integrated into the menu system under the Special Databases Applications option on the EC main menu. These local applications will be documented in the appendices of this manual. This integration capability provides users with a common environment of standard and customized applications.

  16. SYVAC3 manual

    Energy Technology Data Exchange (ETDEWEB)

    Andres, T.H

    2000-07-01

    SYVAC3 (Systems Variability Analysis Code, generation 3) is a computer program that implements a method called systems variability analysis to analyze the behaviour of a system in the presence of uncertainty. This method is based on simulating the system many times to determine the variation in behaviour it can exhibit. SYVAC3 specializes in systems representing the transport of contaminants, and has several features to simplify the modelling of such systems. It provides a general tool for estimating environmental impacts from the dispersal of contaminants. This report describes the use and structure of SYVAC3. It is intended for modellers, programmers, operators and reviewers who deal with simulation codes based on SYVAC3. From this manual they can learn how to link a model with SYVAC3, how to set up an input file, and how to extract results from output files. The manual lists the subroutines of SYVAC3 that are available for use by models, and describes their argument lists. It also gives an overview of how routines in the File Reading Package, the Parameter Sampling Package and the Time Series Package can be used by programs outside of SYVAC3. (author)

  17. Lessons learned from the PISC III study of the influence on human factors on inspection reliability

    International Nuclear Information System (INIS)

    Murgatroyd, R.A.; Worrall, G.M.; Crutzen, S.

    1995-01-01

    Results from the PISC II Programme suggested that differences existed between manual inspectors in terms of their skills, knowledge and working practices which could exert a significant influence on the reliability on an inspection. Therefore, a programme of work on human reliability studies was initiated in the PISC III Programme as Action 7, with the objectives of studying and identifying causes of variability in inspection activities, and identifying some of the factors influencing the reliability of inspection in industrial conditions. It was foreseen that the information from Action 7 would aid in the development of methods for reducing the incidence of human error in inspection activities. This paper gives a brief summary of the programme and describes the lessons learned as a result of the work. A considerably more detailed description of the work is available as a PISC report. 3 refs, 3 figs

  18. Multifamily Housing Physical Inspection Scores

    Data.gov (United States)

    Department of Housing and Urban Development — HUD's Real Estate Assessment Center conducts physical property inspections of properties that are owned, insured or subsidized by HUD, including public housing and...

  19. Incore inspection and repairing device

    International Nuclear Information System (INIS)

    Ito, Arata; Kimura, Motohiko

    1998-01-01

    The present invention provides a device for inspecting and repairing the inside of a reactor container even if it is narrow, with no trouble by using a swimming-type operation robot. Namely, the device of the present invention conducts inspection and repairing operations for the inside of the reactor by introducing a swimming type operation robot into the reactor container. The swimming-type operation robot comprises a robot main body having a propeller, a balancer operably disposed to the robot main body and an inspection and repairing unit attached detachable to the balancer. In the device of the present invention, since the inspection and preparing unit is attached detachably to the swimming robot, a robot which transports tools is formed as a standard product. As a result, the production cost can be reduced, and the reliability of products can be improved. Appropriate operations can be conducted by using best tools. (I.S.)

  20. In-service inspection techniques

    International Nuclear Information System (INIS)

    Backfisch, W.; Zipser, R.R.

    1980-01-01

    The owner of a nuclear power plant (NPP) is obligated and interested to maintain - by regular maintenance and in-service inspections - the operational safety and availability of the plant for the subsequent operating period in a condition, as is specified as the basis of the erection and the last operational permits. In-service inspections are performed to verify the operational safety, and maintenance work is performed to guarantee the availability. Below, the typical in-service inspections of a light-water reactor NPP (operated on a pressurized-water reactor or on a boiling-water reactor) are described with details and examples of typical inspections, especially of recurrent performance tests of the systems. (orig./RW)