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Sample records for nuclear company idaho

  1. Idaho National Laboratory - Nuclear Research Center

    International Nuclear Information System (INIS)

    Zaidi, M.K.

    2005-01-01

    Full text: The Idaho National Laboratory is committed to the providing international nuclear leadership for the 21st Century, developing and demonstrating compiling national security technologies, and delivering excellence in science and technology as one of the United States Department of Energy's (DOE) multiprogram national laboratories. INL runs three major programs - Nuclear, Security and Science. nuclear programs covers the Advanced test reactor, Six Generation technology concepts selected for R and D, Targeting tumors - Boron Neutron capture therapy. Homeland security - Homeland Security establishes the Control System Security and Test Center, Critical Infrastructure Test Range evaluates technologies on a scalable basis, INL conducts high performance computing and visualization research and science - INL facility established for Geocentrifuge Research, Idaho Laboratory, a Utah company achieved major milestone in hydrogen research and INL uses extremophile bacteria to ease bleaching's environmental cost. To provide leadership in the education and training, INL has established an Institute of Nuclear Science and Engineering (Inset). The institute will offer a four year degree based on a newly developed curriculum - two year of basic science course work and two years of participation in project planning and development. The students enrolled in this program can continue to get a masters or a doctoral degree. This summer Inset is the host for the training of the first international group selected by the World Nuclear University (WNU) - 75 fellowship holders and their 30 instructors from 40 countries. INL has been assigned to provide future global leadership in the field of nuclear science and technology. Here, at INL, we keep safety first above all things and our logo is 'Nuclear leadership synonymous with safety leadership'

  2. Nuclear reactor safety research in Idaho

    International Nuclear Information System (INIS)

    Zeile, H.J.

    1983-01-01

    Detailed information about the performance of nuclear reactor systems, and especially about the nuclear fuel, is vital in determining the consequences of a reactor accident. Fission products released from the fuel during accidents are the ultimate safety concern to the general public living in the vicinity of a nuclear reactor plant. Safety research conducted at the Idaho National Engineering Laboratory (INEL) in support of the U.S. Nuclear Regulatory Commission (NRC) has provided the NRC with detailed data relating to most of the postulated nuclear reactor accidents. Engineers and scientists at the INEL are now in the process of gathering data related to the most severe nuclear reactor accident - the core melt accident. This paper describes the focus of the nuclear reactor safety research at the INEL. The key results expected from the severe core damage safety research program are discussed

  3. Idaho national laboratory - a nuclear research center

    International Nuclear Information System (INIS)

    Zaidi Mohammed, K.

    2006-01-01

    Full text: The Idaho National Laboratory (INL) is committed to providing international nuclear leadership for the 21st Century, developing and demonstrating compelling national security technologies, and delivering excellence in science and technology as one of the United States Department of Energy's (DOE) multi program national laboratories. INL runs three major programs - Nuclear, Security and Science. Nuclear programs covers the Advanced test reactor, Six Generation IV technology concepts selected for Rand D, targeting tumors - Boron Neutron Capture therapy. Homeland Security establishes the Control System Security and Test Center, Critical Infrastructure Test Range evaluates technologies on a scalable basis, INL conducts high performance computing and visualization research and science. To provide leadership in the education and training, INL has established an Institute of Nuclear Science and Engineering (INSE) under the Center for Advanced Energy Studies (CAES) and the Idaho State University (ISU). INSE will offer a four year degree based on a newly developed curriculum - two year of basic science course work and two years of participation in project planning and development. The students enrolled in this program can continue to get a masters or a doctoral degree. This summer INSE is the host for the training of the first international group selected by the World Nuclear University (WNU) - 75 fellowship holders and their 30 instructors from 40 countries. INL has been assigned to provide future global leadership in the field of nuclear science and technology. Here, at INL, we keep safety first above all things and our logo is 'Nuclear leadership synonymous with safety leadership'. (author)

  4. Scottish Nuclear, the company

    International Nuclear Information System (INIS)

    Yeomans, R.M.

    1991-01-01

    A former chief executive of Scottish Nuclear, formed when United Kingdom electricity generation was privatized, describes the financial viability of the company and considers the future of nuclear power. Scottish Nuclear owns and operates the Advanced Gas Cooled (AGR) and Magnox reactors at Hunterston and the AGR reactor at Torness and is a separate company from those dealing with hydro-electric and non-nuclear generation of electricity. Costs of running the reactors is identified as a proportion of the whole for certain key issues such as station costs, depreciation, decommissioning and insurance. While nuclear power generation using outmoded Magnox reactors is costly, the ecological cost of global warming is seen as more of a problem. Future policy for nuclear power in Scotland must include new plant, probably pressurized water reactors and a clear policy of safety enhancement. (UK)

  5. Great Western Malting Company geothermal project, Pocatello, Idaho. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Christensen, N.T.; McGeen, M.A.; Corlett, D.F.; Urmston, R.

    1981-12-23

    The Great Western Malting Company recently constructed a barley malting facility in Pocatello, Idaho, designed to produce 6.0 million bushels per year of brewing malt. This facility uses natural gas to supply the energy for germination and kilning processes. The escalating cost of natural gas has prompted the company to look at alternate and more economical sources of energy. Trans Energy Systems has investigated the viabiity of using geothermal energy at the new barley processing plant. Preliminary investigations show that a geothermal resource probably exists, and payback on the installation of a system to utilize the resource will occur in under 2 years. The Great Western Malting plant site has geological characteristics which are similar to areas where productive geothermal wells have been established. Geological investigations indicate that resource water temperatures will be in the 150 to 200/sup 0/F range. Geothermal energy of this quality will supply 30 to 98% of the heating requirements currently supplied by natural gas for this malting plant. Trans Energy Systems has analyzed several systems of utilizing the geothermal resource at the Great Western barley malting facility. These systems included: direct use of geothermal water; geothermal energy heating process water through an intermediary heat exchanger; coal or gas boosted geothermal systems; and heat pump boosted geothermal system. The analysis examined the steps that are required to process the grain.

  6. 76 FR 28024 - Swan Falls Hydroelectric Project, Idaho Power Company; Notice of Teleconference

    Science.gov (United States)

    2011-05-13

    ... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Project No. 503-048-ID] Swan Falls Hydroelectric Project, Idaho Power Company; Notice of Teleconference a. Date and Time of Meeting: Tuesday, May 24, 2011 at 10 a.m. (Mountain Time). b. Place: By copy of this notice we are inviting all interested parties to attend a teleconference from...

  7. 76 FR 71014 - Idaho Power Company, IDACORP Energy, L.P., IDACORP, Inc.; Notice of Petition

    Science.gov (United States)

    2011-11-16

    ... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Docket No. IN03-9-000] Idaho Power Company, IDACORP Energy, L.P., IDACORP, Inc.; Notice of Petition Take notice that on September 9, 2011..., 2003,\\1\\ filed a petition to terminate Appendix B, Appendix C, and Appendix E to the Settlement...

  8. Training in nuclear engineering companies

    International Nuclear Information System (INIS)

    Perezagua, R. L.

    2013-01-01

    The importance of training is growing in all business areas and fields and especially in hi-tech companies like engineering firms. Nuclear projects are highly multidisciplinary and, even in the initial awarding and pre-construction phases, need to be staffed with personnel that is well-prepared and highly-qualified in areas that, in most cases, are not covered by university studies. This article examines the variables that influence the design of specific training for nuclear projects in engineering firms, along with new training technologies (e-learning) and new regulatory aspects (IS-12). (Author)

  9. Nuclear fuel reprocessing deactivation plan for the Idaho Chemical Processing Plant, Revision 1

    International Nuclear Information System (INIS)

    Patterson, M.W.

    1994-10-01

    The decision was announced on April 28, 1992 to cease all United States Department of Energy (DOE) reprocessing of nuclear fuels. This decision leads to the deactivation of all fuels dissolution, solvent extraction, krypton gas recovery operations, and product denitration at the Idaho Chemical Processing Plant (ICPP). The reprocessing facilities will be converted to a safe and stable shutdown condition awaiting future alternate uses or decontamination and decommissioning (D ampersand D). This ICPP Deactivation Plan includes the scope of work, schedule, costs, and associated staffing levels necessary to achieve a safe and orderly deactivation of reprocessing activities and the Waste Calcining Facility (WCF). Deactivation activities primarily involve shutdown of operating systems and buildings, fissile and hazardous material removal, and related activities. A minimum required level of continued surveillance and maintenance is planned for each facility/process system to ensure necessary environmental, health, and safety margins are maintained and to support ongoing operations for ICPP facilities that are not being deactivated. Management of the ICPP was transferred from Westinghouse Idaho Nuclear Company, Inc. (WINCO) to Lockheed Idaho Technologies Company (LITCO) on October 1, 1994 as part of the INEL consolidated contract. This revision of the deactivation plan (formerly the Nuclear Fuel Reprocessing Phaseout Plan for the ICPP) is being published during the consolidation of the INEL site-wide contract and the information presented here is current as of October 31, 1994. LITCO has adopted the existing plans for the deactivation of ICPP reprocessing facilities and the plans developed under WINCO are still being actively pursued, although the change in management may result in changes which have not yet been identified. Accordingly, the contents of this plan are subject to revision

  10. Nuclear Plant Analyzer development at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Laats, E.T.

    1986-10-01

    The Nuclear Plant Analyzer (NPA) is a state-of-the-art safety analysis and engineering tool being used to address key nuclear power plant safety issues. Under the sponsorship of the US Nuclear Regulatory Commission (NRC), the NPA has been developed to integrate the NRC's computerized reactor behavior simulation codes such as RELAP5, TRAC-BWR and TRAC-PWR, with well-developed computer color graphics programs and large repositories of reactor design and experimental data. An important feature of the NPA is the capability to allow an analyst to redirect a RELAP5 or TRAC calculation as it progresses through its simulated scenario. The analyst can have the same power plant control capabilities as the operator of an actual plant. The NPA resides on the dual Control Data Corporation Cyber 176 mainframe computers at the Idaho National Engineering Laboratory and Cray-1S computers at the Los Alamos National Laboratory (LANL) and Kirtland Air Force Weapons Laboratory (KAFWL)

  11. Nuclear utility structure. Use of nuclear service companies

    International Nuclear Information System (INIS)

    Ring, L.E.

    1980-01-01

    The feasibility of utilities incorporating service companies to construct and maintain nuclear power plants is analyzed. Responsibilities of the service companies and the public opinion of the concept are discussed

  12. Educating Next Generation Nuclear Criticality Safety Engineers at the Idaho National Laboratory

    International Nuclear Information System (INIS)

    Bess, J.D.; Briggs, J.B.; Garcia, A.S.

    2011-01-01

    One of the challenges in educating our next generation of nuclear safety engineers is the limitation of opportunities to receive significant experience or hands-on training prior to graduation. Such training is generally restricted to on-the-job-training before this new engineering workforce can adequately provide assessment of nuclear systems and establish safety guidelines. Participation in the International Criticality Safety Benchmark Evaluation Project (ICSBEP) and the International Reactor Physics Experiment Evaluation Project (IRPhEP) can provide students and young professionals the opportunity to gain experience and enhance critical engineering skills. The ICSBEP and IRPhEP publish annual handbooks that contain evaluations of experiments along with summarized experimental data and peer-reviewed benchmark specifications to support the validation of neutronics codes, nuclear cross-section data, and the validation of reactor designs. Participation in the benchmark process not only benefits those who use these Handbooks within the international community, but provides the individual with opportunities for professional development, networking with an international community of experts, and valuable experience to be used in future employment. Traditionally students have participated in benchmarking activities via internships at national laboratories, universities, or companies involved with the ICSBEP and IRPhEP programs. Additional programs have been developed to facilitate the nuclear education of students while participating in the benchmark projects. These programs include coordination with the Center for Space Nuclear Research (CSNR) Next Degree Program, the Collaboration with the Department of Energy Idaho Operations Office to train nuclear and criticality safety engineers, and student evaluations as the basis for their Master's thesis in nuclear engineering.

  13. Educating Next Generation Nuclear Criticality Safety Engineers at the Idaho National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    J. D. Bess; J. B. Briggs; A. S. Garcia

    2011-09-01

    One of the challenges in educating our next generation of nuclear safety engineers is the limitation of opportunities to receive significant experience or hands-on training prior to graduation. Such training is generally restricted to on-the-job-training before this new engineering workforce can adequately provide assessment of nuclear systems and establish safety guidelines. Participation in the International Criticality Safety Benchmark Evaluation Project (ICSBEP) and the International Reactor Physics Experiment Evaluation Project (IRPhEP) can provide students and young professionals the opportunity to gain experience and enhance critical engineering skills. The ICSBEP and IRPhEP publish annual handbooks that contain evaluations of experiments along with summarized experimental data and peer-reviewed benchmark specifications to support the validation of neutronics codes, nuclear cross-section data, and the validation of reactor designs. Participation in the benchmark process not only benefits those who use these Handbooks within the international community, but provides the individual with opportunities for professional development, networking with an international community of experts, and valuable experience to be used in future employment. Traditionally students have participated in benchmarking activities via internships at national laboratories, universities, or companies involved with the ICSBEP and IRPhEP programs. Additional programs have been developed to facilitate the nuclear education of students while participating in the benchmark projects. These programs include coordination with the Center for Space Nuclear Research (CSNR) Next Degree Program, the Collaboration with the Department of Energy Idaho Operations Office to train nuclear and criticality safety engineers, and student evaluations as the basis for their Master's thesis in nuclear engineering.

  14. MANAGING SPENT NUCLEAR FUEL WASTES AT THE IDAHO NATIONAL LABORATORY

    Energy Technology Data Exchange (ETDEWEB)

    Hill, Thomas J

    2005-09-01

    The Idaho National Engineering Laboratory (INL) has a large inventory of diverse types of spent nuclear fuel (SNF). This legacy is in part due to the history of the INL as the National Reactor Testing Station, in part to its mission to recover highly enriched uranium from SNF and in part to it’s mission to test and examine SNF after irradiation. The INL also has a large diversity of SNF storage facility, some dating back 50 years in the site history. The success of the INL SNF program is measured by its ability to: 1) achieve safe existing storage, 2) continue to receive SNF from other locations, both foreign and domestic, 3) repackage SNF from wet storage to interim dry storage, and 4) prepare the SNF for dispositioning in a federal repository. Because of the diversity in the SNF and the facilities at the INL, the INL is addressing almost very condition that may exist in the SNF world. Many of solutions developed by the INL are applicable to other SNF storage sites as they develop their management strategy. The SNF being managed by the INL are in a variety of conditions, from intact assemblies to individual rods or plates to powders, rubble, and metallurgical mounts. Some of the fuel has been in wet storage for over forty years. The fuel is stored bare, or in metal cans and either wet under water or dry in vaults, caissons or casks. Inspections have shown varying degrees of corrosion and degradation of the fuel and the storage cans. Some of the fuel has been recanned under water, and the conditions of the fuel inside the second or third can are unknown. The fuel has been stored in one of 10 different facilities: five wet pools and one casks storage pad, one vault, two generations of caisson facilities, and one modular Independent Spent Fuel Storage Installation (ISFSI). The wet pools range from forty years old to the most modern pool in the US Department of Energy (DOE) complex. The near-term objective is moving the fuel in the older wet storage facilities to

  15. Managing Spent Nuclear Fuel at the Idaho National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Thomas Hill; Denzel L. Fillmore

    2005-10-01

    The Idaho National Laboratory (INL) has a large inventory of diverse types of spent nuclear fuel (SNF). This legacy derives from the history of the INL as the National Reactor Testing Station, and from its mission to recover HEU from SNF and to test and examine SNF after irradiation. The INL also has a large diversity of SNF storage facilities, some 50 years old. SNF at INL has many forms—from intact assemblies down to metallurgical mounts, and some fuel has been wet stored for over 40 years. SNF is stored bare or in metal cans under water, or dry in vaults, caissons or casks. Inspection shows varying corrosion and degradation of the SNF and its storage cans. SNF has been stored in 10 different facilities: 5 pools, one cask storage pad, one vault, two generations of caisson facilities, and one modular Independent Spent Fuel Storage Installation (ISFSI). The pools range in age from 40 years old to the most modern in the US Department of Energy (DOE) complex. The near-term objective is to move SNF from older pools to interim dry storage, allowing shutdown and decommissioning of the older facilities. This move involves drying methods that are dependent on fuel type. The long-term objective is to have INL SNF in safe dry storage and ready to be shipped to the National Repository. The unique features of the INL SNF requires special treatments and packaging to meet the proposed repository acceptance criteria and SNF will be repackaged in standardized canisters for shipment and disposal in the National Repository. Disposal will use the standardized canisters that can be co-disposed with High Level Waste glass logs to limit the total fissile material in a repository waste package. The DOE standardized canister also simplifies the repository handling of the multitude of DOE SNF sizes and shapes.

  16. Calcined Waste Storage at the Idaho Nuclear Technology and Engineering Center

    Energy Technology Data Exchange (ETDEWEB)

    M. D. Staiger

    2007-06-01

    This report provides a quantitative inventory and composition (chemical and radioactivity) of calcined waste stored at the Idaho Nuclear Technology and Engineering Center. From December 1963 through May 2000, liquid radioactive wastes generated by spent nuclear fuel reprocessing were converted into a solid, granular form called calcine. This report also contains a description of the calcine storage bins.

  17. 75 FR 57266 - Idaho Power Company; Notice of Application for Amendment of License and Soliciting Comments...

    Science.gov (United States)

    2010-09-20

    ...) is located on the Snake River in Gooding, Twin Falls and Elmore Counties, Idaho. The Lower Salmon Falls Project (P-2061) is located on the Snake River in Gooding and Twin Falls Counties, Idaho. Both.... Locations of the Application: A copy of the application is available for inspection and reproduction at the...

  18. Piercing of corporate veil of nuclear companies

    International Nuclear Information System (INIS)

    Frenz, Walter

    2015-01-01

    The Federal Ministry of Economics plans that the nuclear companies with all their assets to cover disposal costs can be used where a power plant operator is governed by its parent company, hence the latter Capital or voting majority of the operators holding or these passes; To date, the parent company is liable only limited and not more than five years after the end of the domination of one Subsidiary, oparating a power plant. In this way, prevents ultimately the public sector and thus the Taxpayers have to pay for the long-term consequences of the use of nuclear energy. Until now ensured paragraph 303 AktG a group law Secondary liability the parent companies of the operating company in the case of of termination of the control and profit transfer agreements is very limited for the nuclear liabilities, namely in two ways: The claim is only focused on the backup performance and not at the expense of acquisition and Moreover, according to the case law limited of five years after its foundation; for the area of transformation law comparable rules are valid. thereby the dismantling of a nuclear power station takes just already for 20 years and a final repository is expected before 2050 not be available. [de

  19. Laboratory testing of glasses for Lockheed Idaho Technology Company: Final report

    International Nuclear Information System (INIS)

    Ellison, A.J.G.; Buck, E.C.; Dietz, N.L.; Ebert, W.L.; Luo, J.S.; Wolf, S.F.; Bates, J.K.

    1997-06-01

    Tests have been conducted at Argonne National Laboratory (ANL) in support of the efforts of Lockheed Idaho Technology Company (LITCO) to vitrify high-level waste calcines. Tests were conducted with three classes of LITCO glass formulations: Formula 127 (fluorine-bearing), Formula 532 (fluorine-free), and 630 series (both single- and mixed-alkali) glasses. The test matrices included, as appropriate, the Product Consistency Test Method B (PCT-B), the Materials Characterization Center Test 1 (MCC-1), and the Argonne vapor hydration test (VHT). Test durations ranged from 7 to 183 d. In 7-d PCT-Bs, normalized mass losses of major glass-forming elements for the LITCO glasses are similar to, or lower than, normalized mass losses obtained for other domestic candidate waste glasses. Formula 532 glasses form zeolite alteration phases relatively early in their reaction with water. The formation of those phases increased the dissolution rate. In contrast, the Formula 127 glass is highly durable and forms alteration phases only after prolonged exposure to water in tests with very high surface area to volume ratios; these alteration phases have a relatively small effect on the rate of glass corrosion. No alteration phases formed within the maximum test duration of 183 d in PCT-Bs with the 630 series glasses. The corrosion behavior of the mixed-alkali 630 series glasses is similar to that of 630 series glasses containing sodium alone. In VHTs, both single- and mixed-alkali glasses form zeolite phases that increase the rate of glass reaction. The original 630 series glasses and those based on a revised surrogate calcine formulation react at the same rate in PCT-Bs and form the same major alteration phases in VHTs

  20. Secondary cleanup of Idaho Chemical Processing Plant solvent

    International Nuclear Information System (INIS)

    Mailen, J.C.

    1985-01-01

    Solvent from the Idaho Chemical Processing Plant (ICPP) (operated by Westinghouse Idaho Nuclear Company, Inc.) has been tested to determine the ability of activated alumina to remove secondary degradation products - those degradation products which are not removed by scrubbing with sodium carbonate

  1. 77 FR 38620 - Idaho Power Company; Notice of Application for Amendment of License And Soliciting Comments...

    Science.gov (United States)

    2012-06-28

    ... Falls Hydroelectric Project. f. Location: The project is located in south-central Idaho on the Snake... reproduction at the Commission's Public Reference Room, located at 888 First Street NE., Room 2A, Washington... inspection and reproduction at the address in item (h) above. m. Individuals desiring to be included on the...

  2. 77 FR 38618 - Idaho Power Company; Notice of Application for Amendment of License and Soliciting Comments...

    Science.gov (United States)

    2012-06-28

    ... Hydroelectric Project. f. Location: The project is located in south-western Idaho on the Snake River from river... application is available for inspection and reproduction at the Commission's Public Reference Room, located at... available for inspection and reproduction at the address in item (h) above. m. Individuals desiring to be...

  3. 77 FR 38621 - Idaho Power Company; Notice of Application for Amendment of License and Soliciting Comments...

    Science.gov (United States)

    2012-06-28

    ... Hydroelectric Project. f. Location: The project is located in south-central Idaho on the Snake River from river... inspection and reproduction at the Commission's Public Reference Room, located at 888 First Street, NE., Room... inspection and reproduction at the address in item (h) above. m. Individuals desiring to be included on the...

  4. 77 FR 38619 - Idaho Power Company; Notice of Application for Amendment of License and Soliciting Comments...

    Science.gov (United States)

    2012-06-28

    ... Hydroelectric Project. f. Location: The project is located in south-central Idaho on the Snake River in Gooding... reproduction at the Commission's Public Reference Room, located at 888 First Street NE., Room 2A, [email protected] , for TTY, call (202) 502- 8659. A copy is also available for inspection and reproduction at...

  5. Initial evaluation of dry storage issues for spent nuclear fuels in wet storage at the Idaho Chemical Processing Plant

    Energy Technology Data Exchange (ETDEWEB)

    Guenther, R J; Johnson, Jr, A B; Lund, A L; Gilbert, E R [and others

    1996-07-01

    The Pacific Northwest Laboratory has evaluated the basis for moving selected spent nuclear fuels in the CPP-603 and CPP-666 storage pools at the Idaho Chemical Processing Plant from wet to dry interim storage. This work is being conducted for the Lockheed Idaho Technologies Company as part of the effort to determine appropriate conditioning and dry storage requirements for these fuels. These spent fuels are from 22 test reactors and include elements clad with aluminum or stainless steel and a wide variety of fuel materials: UAl{sub x}, UAl{sub x}-Al and U{sub 3}O{sub 8}-Al cermets, U-5% fissium, UMo, UZrH{sub x}, UErZrH, UO{sub 2}-stainless steel cermet, and U{sub 3}O{sub 8}-stainless steel cermet. The study also included declad uranium-zirconium hydride spent fuel stored in the CPP-603 storage pools. The current condition and potential failure mechanisms for these spent fuels were evaluated to determine the impact on conditioning and dry storage requirements. Initial recommendations for conditioning and dry storage requirements are made based on the potential degradation mechanisms and their impacts on moving the spent fuel from wet to dry storage. Areas needing further evaluation are identified.

  6. Initial evaluation of dry storage issues for spent nuclear fuels in wet storage at the Idaho Chemical Processing Plant

    International Nuclear Information System (INIS)

    Guenther, R.J.; Johnson, A.B. Jr.; Lund, A.L.; Gilbert, E.R.

    1994-11-01

    The Pacific Northwest Laboratory has evaluated the basis for moving selected spent nuclear fuels in the CPP-603 and CPP-666 storage pools at the Idaho Chemical Processing Plant from wet to dry interim storage. This work is being conducted for the Lockheed Idaho Technologies Company as part of the effort to determine appropriate conditioning and dry storage requirements for these fuels. These spent fuels are from 22 test reactors and include elements clad with aluminum or stainless steel and a wide variety of fuel materials: UAl x , UAl x -Al and U 3 O 8 -Al cermets, U-5% fissium, UMo, UZrH x , UErZrH, UO 2 -stainless steel cermet, and U 3 O 8 -stainless steel cermet. The study also included declad uranium-zirconium hydride spent fuel stored in the CPP-603 storage pools. The current condition and potential failure mechanisms for these spent fuels were evaluated to determine the impact on conditioning and dry storage requirements. Initial recommendations for conditioning and dry storage requirements are made based on the potential degradation mechanisms and their impacts on moving the spent fuel from wet to dry storage. Areas needing further evaluation are identified

  7. Westinghouse Idaho Nuclear Company, Inc. (WINCO) CAD activities at the Idaho Chemical Processing Plant (ICPP) (Idaho Engineering Laboratory)

    International Nuclear Information System (INIS)

    Jensen, B.

    1989-01-01

    June 1985 -- The drafting manager obtained approval to implement a cad system at the ICPP. He formed a committee to evaluate the various cad systems and recommend a system that would most benefit the ICPP. A ''PC'' (personal computer) based system using Autocad software was recommended in lieu of the much more expensive main frame based systems

  8. US company's new nuclear project progresses

    International Nuclear Information System (INIS)

    Archie, Jeffrey B.

    2011-01-01

    Operated by South Carolina Electric and Gas Company in the southeastern United States, V.C. Summer Nuclear Station has maintained a reputation of excellence for more than 25 years. The key to its success: placing safety as its first priority, keeping a keen focus on operations, establishing a culture of continuous learning, and embracing collaboration with industry peers. This philosophy guides its new nuclear project, which SCE and G has undertaken to meet the need for baseload generation in its service area in a manner that is clean, safe, reliable, and efficient. In the process, SCE and G is generating jobs and boosting the economy. Site preparation has been under way since 2009. SCE and G anticipates receiving its combined construction and operating license from the Nuclear Regulatory Commission, the independent, federal agency that oversees commercial nuclear power plants in the U.S., in late 2011 or early 2012, which will allow major construction to commence. The 2 new reactors are scheduled to begin commercial operation in 2016 and 2019, respectively, placing V.C. Summer at the forefront of a U.S. nuclear renaissance and carrying its legacy of excellence into the future. (orig.)

  9. Test Plan for Lockheed Idaho Technologies Company (LITCO), ARROW-PAK Packaging, Docket 95-40-7A, Type A Container

    International Nuclear Information System (INIS)

    Kelly, D.L.

    1995-01-01

    This report documents the U.S. Department of Transportation Specification 7A Type A (DOT-7A) compliance testing to be followed for qualification of the Lockheed Idaho Technologies Company, ARROW-PAK, for use as a Type A Packaging. The packaging configuration being tested is intended for transportation of radioactive solids, Form No. 1, Form No. 2, and Form No. 3

  10. Calcine Waste Storage at the Idaho Nuclear Technology and Engineering Center

    Energy Technology Data Exchange (ETDEWEB)

    M. D. Staiger

    1999-06-01

    A potential option in the program for long-term management of high-level wastes at the Idaho Nuclear Technology and Engineering Center (INTEC), at the Idaho National Engineering and Environmental Laboratory, calls for retrieving calcine waste and converting it to a more stable and less dispersible form. An inventory of calcine produced during the period December 1963 to May 1999 has been prepared based on calciner run, solids storage facilities operating, and miscellaneous operational information, which gives the range of chemical compositions of calcine waste stored at INTEC. Information researched includes calciner startup data, waste solution analyses and volumes calcined, calciner operating schedules, solids storage bin capacities, calcine storage bin distributor systems, and solids storage bin design and temperature monitoring records. Unique information on calcine solids storage facilities design of potential interest to remote retrieval operators is given.

  11. Nuclear Plant Analyzer development at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Laats, E.T.; Beelman, R.J.; Charlton, T.R.; Hampton, N.L.; Burtt, J.D.

    1985-01-01

    The Nuclear Plant Analyzer (NPA) is a state-of-the-art safety analysis and engineering tool being used to address key nuclear power plant safety issues. The NPA has been developed to integrate the NRC's computerized reactor behavior simulation codes such as RELAP5, TRAC-BWR, and TRAC-PWR, with well-developed computer graphics programs and large repositories of reactor design and experimental data. An important feature of the NAP is the capability to allow an analyst to redirect a RELAP5 or TRAC calculation as it progresses through its simulated scenario. The analyst can have the same power plant control capabilities as the operator of an actual plant. The NPA resides on the dual CDS Cyber-176 mainframe computers at the INEL and is being converted to operate on a Cray-1S computer at the LANL. The subject of this paper is the program conducted at the INEL

  12. Idaho Nuclear Technology and Engineering Center (INTEC) (formerly ICPP) ash reutilization study

    Energy Technology Data Exchange (ETDEWEB)

    Langenwalter, T.; Pettet, M.; Ochoa, R.; Jensen, S.

    1998-05-01

    Since 1984, the coal-fired plant at the Idaho Nuclear Technology and Engineering Center (INTEC, formerly Idaho Chemical Processing Plant) has been generating fly ash at a rate of approximately 1,000 tons per year. This ash is hydrated and placed in an ash bury pit near the coal-fired plant. The existing ash bury pit will be full in less than 1 year at its present rate of use. A conceptual design to build a new ash bury pit was completed, and the new pit is estimated to cost $1.7 million. This report evaluates ash reutilization alternatives that propose to eliminate this waste stream and save the $1.7 million required to build a new pit. The alternatives include using ash for landfill day cover, concrete admixture, flowable fill, soil stabilization, waste remediation, and carbon recovery technology. Both physical and chemical testing, under the guidance of the American Society for Testing and Materials, have been performed on ash from the existing pit and from different steps within the facility`s processes. The test results have been evaluated, compared to commercial ash, and are discussed as they relate to reutilization alternatives. This study recommends that the ash be used in flowable fill concrete for Deactivation and Demolition work at the Idaho National Engineering and Environmental Laboratory.

  13. Idaho Nuclear Technology and Engineering Center (INTEC) (formerly ICPP) ash reutilization study

    International Nuclear Information System (INIS)

    Langenwalter, T.; Pettet, M.; Ochoa, R.; Jensen, S.

    1998-05-01

    Since 1984, the coal-fired plant at the Idaho Nuclear Technology and Engineering Center (INTEC, formerly Idaho Chemical Processing Plant) has been generating fly ash at a rate of approximately 1,000 tons per year. This ash is hydrated and placed in an ash bury pit near the coal-fired plant. The existing ash bury pit will be full in less than 1 year at its present rate of use. A conceptual design to build a new ash bury pit was completed, and the new pit is estimated to cost $1.7 million. This report evaluates ash reutilization alternatives that propose to eliminate this waste stream and save the $1.7 million required to build a new pit. The alternatives include using ash for landfill day cover, concrete admixture, flowable fill, soil stabilization, waste remediation, and carbon recovery technology. Both physical and chemical testing, under the guidance of the American Society for Testing and Materials, have been performed on ash from the existing pit and from different steps within the facility's processes. The test results have been evaluated, compared to commercial ash, and are discussed as they relate to reutilization alternatives. This study recommends that the ash be used in flowable fill concrete for Deactivation and Demolition work at the Idaho National Engineering and Environmental Laboratory

  14. Idaho Nuclear Technology and Engineering Center Newly Generated Liquid Waste Demonstration Project Feasibility Study

    International Nuclear Information System (INIS)

    Herbst, A.K.

    2000-01-01

    A research, development, and demonstration project for the grouting of newly generated liquid waste (NGLW) at the Idaho Nuclear Technology and Engineering Center is considered feasible. NGLW is expected from process equipment waste, decontamination waste, analytical laboratory waste, fuel storage basin waste water, and high-level liquid waste evaporator condensate. The potential grouted waste would be classed as mixed low-level waste, stabilized and immobilized to meet RCRA LDR disposal in a grouting process in the CPP-604 facility, and then transported to the state

  15. Neutron Focusing Mirrors for Neutron Radiography of Irradiated Nuclear Fuel at Idaho National Laboratory

    Science.gov (United States)

    Rai, Durgesh K.; Wu, Huarui; Abir, Muhammad; Giglio, Jeffrey; Khaykovich, Boris

    Post irradiation examination (PIE) of samples irradiated in nuclear reactors is a challenging but necessary task for the development on novel nuclear power reactors. Idaho National Laboratory (INL) has neutron radiography capabilities, which are especially useful for the PIE of irradiated nuclear fuel. These capabilities are limited due to the extremely high gamma-ray radiation from the irradiated fuel, which precludes the use of standard digital detectors, in turn limiting the ability to do tomography and driving the cost of the measurements. In addition, the small 250 kW Neutron Radiography Reactor (NRAD) provides a relatively weak neutron flux, which leads to low signal-to-noise ratio. In this work, we develop neutron focusing optics suitable for the installation at NRAD. The optics would separate the sample and the detector, potentially allowing for the use of digital radiography detectors, and would provide significant intensity enhancement as well. The optics consist of several coaxial nested Wolter mirrors and is suited for polychromatic thermal neutron radiation. Laboratory Directed Research and Development program of Idaho National Laboratory.

  16. Idaho Chemical Processing Plant and Plutonium-Uranium Extraction Plant phaseout/deactivation study

    International Nuclear Information System (INIS)

    Patterson, M.W.; Thompson, R.J.

    1994-01-01

    The decision to cease all US Department of Energy (DOE) reprocessing of nuclear fuels was made on April 28, 1992. This study provides insight into and a comparison of the management, technical, compliance, and safety strategies for deactivating the Idaho Chemical Processing Plant (ICPP) at Westinghouse Idaho Nuclear Company (WINCO) and the Westinghouse Hanford Company (WHC) Plutonium-Uranium Extraction (PUREX) Plant. The purpose of this study is to ensure that lessons-learned and future plans are coordinated between the two facilities

  17. Termination of Safeguards for Accountable Nuclear Materials at the Idaho National Laboratory

    International Nuclear Information System (INIS)

    Holzemer, Michael; Carvo, Alan

    2012-01-01

    Termination of safeguards ends requirements of Nuclear Material Control and Accountability (MC and A) and thereby removes the safeguards basis for applying physical protection requirements for theft and diversion of nuclear material, providing termination requirements are met as described. Department of Energy (DOE) M 470.4 6 (Nuclear Material Control and Accountability [8/26/05]) stipulates: 1. Section A, Chapter I (1)( q) (1): Safeguards can be terminated on nuclear materials provided the following conditions are met: (a) 'If the material is special nuclear material (SNM) or protected as SNM, it must be attractiveness level E and have a measured value.' (b) 'The material has been determined by DOE line management to be of no programmatic value to DOE.' (c) 'The material is transferred to the control of a waste management organization where the material is accounted for and protected in accordance with waste management regulations. The material must not be collocated with other accountable nuclear materials.' Requirements for safeguards termination depend on the safeguards attractiveness levels of the material. For attractiveness level E, approval has been granted from the DOE Idaho Operations Office (DOE ID) to Battelle Energy Alliance, LLC (BEA) Safeguards and Security (S and S). In some cases, it may be necessary to dispose of nuclear materials of attractiveness level D or higher. Termination of safeguards for such materials must be approved by the Departmental Element (this is the DOE Headquarters Office of Nuclear Energy) after consultation with the Office of Security.

  18. Nuclear power company activity based costing management analysis

    International Nuclear Information System (INIS)

    Xu Dan

    2012-01-01

    With Nuclear Energy Industry development, Nuclear Power Company has the continual promoting stress of inner management to the sustainable marketing operation development. In view of this, it is very imminence that Nuclear Power Company should promote the cost management levels and built the nuclear safety based lower cost competitive advantage. Activity based costing management (ABCM) transfer the cost management emphases from the 'product' to the 'activity' using the value chain analysis methods, cost driver analysis methods and so on. According to the analysis of the detail activities and the value chains, cancel the unnecessary activity, low down the resource consuming of the necessary activity, and manage the cost from the source, achieve the purpose of reducing cost, boosting efficiency and realizing the management value. It gets the conclusion from the detail analysis with the nuclear power company procedure and activity, and also with the selection to 'pieces analysis' of the important cost related project in the nuclear power company. The conclusion is that the activities of the nuclear power company has the obviously performance. It can use the management of ABC method. And with the management of the procedure and activity, it is helpful to realize the nuclear safety based low cost competitive advantage in the nuclear power company. (author)

  19. Building an integrated nuclear engineering and nuclear science human resources pipeline at the Idaho National Engineering and Environmental Laboratory

    International Nuclear Information System (INIS)

    Sneed, A.; Sikorski, B.; Lineberry, M.; Jolly, J.

    2004-01-01

    In a joint effort with the Argonne National Laboratory - West (ANL-W), the Idaho National Engineering and Environmental Laboratory (INEEL) has assumed the lead role for nuclear energy reactor research for the United States Government. In 2005, these two laboratories will be combined into one entity, the Idaho National Laboratory (INL). There are two objectives for the INL: (1) to act as the lead systems integrator for the Department of Energy's Office of Nuclear Energy Science and Technology and, (2) to establish a Center for Advanced Energy Studies. Focusing on the Center for Advanced Energy Studies, this paper presents a Human Resources Pipeline Model outlining a nuclear educational pathway that leads to university and industry research partnerships. The pathway progresses from education to employment and into retirement. Key to the model is research and mentoring and their impact upon each stage. The Center's success will be the result of effective and advanced communications, faculty/student involvement, industry support, inclusive broadbased involvement, effective long-term partnering, and increased federal and state support. (author)

  20. 75 FR 16524 - FirstEnergy Nuclear Operating Company, Perry Nuclear Power Plant; Exemption

    Science.gov (United States)

    2010-04-01

    ... Company, Perry Nuclear Power Plant; Exemption 1.0 Background FirstEnergy Nuclear Operating Company (FENOC... the Perry Nuclear Power Plant, Unit 1 (PNPP). The license provides, among other things, that the... date for all operating nuclear power plants, but noted that the Commission's regulations provide...

  1. Preoperational Subsurface Conditions at the Idaho Nuclear Technology and Engineering Center Service Waste Disposal Facility

    Energy Technology Data Exchange (ETDEWEB)

    Ansley, Shannon Leigh

    2002-02-01

    The Idaho Nuclear Technology and Engineering Center (INTEC) Service Wastewater Discharge Facility replaces the existing percolation ponds as a disposal facility for the INTEC Service Waste Stream. A preferred alternative for helping decrease water content in the subsurface near INTEC, closure of the existing ponds is required by the INTEC Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Record of Decision (ROD) for Waste Area Group 3 Operable Unit 3-13 (DOE-ID 1999a). By August 2002, the replacement facility was constructed approximately 2 miles southwest of INTEC, near the Big Lost River channel. Because groundwater beneath the Idaho National Engineering and Environmental Laboratory (INEEL) is protected under Federal and State of Idaho regulations from degradation due to INEEL activities, preoperational data required by U.S. Department of Energy (DOE) Order 5400.1 were collected. These data include preexisting physical, chemical, and biological conditions that could be affected by the discharge; background levels of radioactive and chemical components; pertinent environmental and ecological parameters; and potential pathways for human exposure or environmental impact. This document presents specific data collected in support of DOE Order 5400.1, including: four quarters of groundwater sampling and analysis of chemical and radiological parameters; general facility description; site specific geology, stratigraphy, soils, and hydrology; perched water discussions; and general regulatory requirements. However, in order to avoid duplication of previous information, the reader is directed to other referenced publications for more detailed information. Documents that are not readily available are compiled in this publication as appendices. These documents include well and borehole completion reports, a perched water evaluation letter report, the draft INEEL Wellhead Protection Program Plan, and the Environmental Checklist.

  2. Preoperational Subsurface Conditions at the Idaho Nuclear Technology and Engineering Center Service Wastewater Discharge Facility; TOPICAL

    International Nuclear Information System (INIS)

    Ansley, Shannon L.

    2002-01-01

    The Idaho Nuclear Technology and Engineering Center (INTEC) Service Wastewater Discharge Facility replaces the existing percolation ponds as a disposal facility for the INTEC Service Waste Stream. A preferred alternative for helping decrease water content in the subsurface near INTEC, closure of the existing ponds is required by the INTEC Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Record of Decision (ROD) for Waste Area Group 3 Operable Unit 3-13 (DOE-ID 1999a). By August 2002, the replacement facility was constructed approximately 2 miles southwest of INTEC, near the Big Lost River channel. Because groundwater beneath the Idaho National Engineering and Environmental Laboratory (INEEL) is protected under Federal and State of Idaho regulations from degradation due to INEEL activities, preoperational data required by U.S. Department of Energy (DOE) Order 5400.1 were collected. These data include preexisting physical, chemical, and biological conditions that could be affected by the discharge; background levels of radioactive and chemical components; pertinent environmental and ecological parameters; and potential pathways for human exposure or environmental impact. This document presents specific data collected in support of DOE Order 5400.1, including: four quarters of groundwater sampling and analysis of chemical and radiological parameters; general facility description; site specific geology, stratigraphy, soils, and hydrology; perched water discussions; and general regulatory requirements. However, in order to avoid duplication of previous information, the reader is directed to other referenced publications for more detailed information. Documents that are not readily available are compiled in this publication as appendices. These documents include well and borehole completion reports, a perched water evaluation letter report, the draft INEEL Wellhead Protection Program Plan, and the Environmental Checklist

  3. Preoperational Subsurface Conditions at the Idaho Nuclear Technology and Engineering Center Service Wastewater Discharge Facility

    International Nuclear Information System (INIS)

    Ansley, Shannon L.

    2002-01-01

    The Idaho Nuclear Technology and Engineering Center (INTEC) Service Wastewater Discharge Facility replaces the existing percolation ponds as a disposal facility for the INTEC Service Waste Stream. A preferred alternative for helping decrease water content in the subsurface near INTEC, closure of the existing ponds is required by the INTEC Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Record of Decision (ROD) for Waste Area Group 3 Operable Unit 3-13 (DOE-ID 1999a). By August 2002, the replacement facility was constructed approximately 2 miles southwest of INTEC, near the Big Lost River channel. Because groundwater beneath the Idaho National Engineering and Environmental Laboratory (INEEL) is protected under Federal and State of Idaho regulations from degradation due to INEEL activities, preoperational data required by U.S. Department of Energy (DOE) Order 5400.1 were collected. These data include preexisting physical, chemical, and biological conditions that could be affected by the discharge; background levels of radioactive and chemical components; pertinent environmental and ecological parameters; and potential pathways for human exposure or environmental impact. This document presents specific data collected in support of DOE Order 5400.1, including: four quarters of groundwater sampling and analysis of chemical and radiological parameters; general facility description; site specific geology, stratigraphy, soils, and hydrology; perched water discussions; and general regulatory requirements. However, in order to avoid duplication of previous information, the reader is directed to other referenced publications for more detailed information. Documents that are not readily available are compiled in this publication as appendices. These documents include well and borehole completion reports, a perched water evaluation letter report, the draft INEEL Wellhead Protection Program Plan, and the Environmental Checklist

  4. Structural Materials for Innovative Nuclear Systems (SMINS-3) - Workshop Proceedings, Idaho National Laboratory, Idaho Falls, United States, 7-10 October 2013

    International Nuclear Information System (INIS)

    2015-01-01

    The development of innovative nuclear systems such as Gen IV reactors or critical and subcritical transmutation systems requires a good knowledge of the properties of the materials used for designing these reactors. A common feature in developing nuclear systems is the widely recognised need for experimental programmes to select and characterise structural materials. Structural materials research, both at national and international level, can significantly contribute to the future deployment of new systems. Since 2007, the OECD Nuclear Energy Agency Nuclear Science Committee organises a series of workshop on Structural Materials for Innovative Nuclear Systems (SMINS) to stimulate an exchange of information on current materials research programmes for innovative nuclear systems with a view to identifying and developing potential synergies. The third workshop was held on 7-10 October 2013 in Idaho Falls (United States) and organised through the collaboration of the Working Party on Scientific Issues of the Fuel Cycle (WPFC) and the Working Party on Multi-Scale Modelling of Fuels and Structural Materials for Nuclear Systems (WPMM) in co-operation with the European Community (EC) and the International Atomic Energy Agency (IAEA). A total of 74 abstracts were received for either an oral and poster presentation. These proceedings include the papers presented at the workshop

  5. Idaho Nuclear Technology and Engineering Center (INTEC) Sodium Bearing Waste - Waste Incidental to Reprocessing Determination

    International Nuclear Information System (INIS)

    Jacobson, Victor Levon

    2002-01-01

    U.S. Department of Energy Manual 435.1-1, Radioactive Waste Management, Section I.1.C, requires that all radioactive waste subject to Department of Energy Order 435.1 be managed as high-level radioactive waste, transuranic waste, or low-level radioactive waste. Determining the radiological classification of the sodium-bearing waste currently in the Idaho Nuclear Technology and Engineering Center Tank Farm Facility inventory is important to its proper treatment and disposition. This report presents the technical basis for making the determination that the sodium-bearing waste is waste incidental to spent fuel reprocessing and should be managed as mixed transuranic waste. This report focuses on the radiological characteristics of the sodium-bearing waste. The report does not address characterization of the nonradiological, hazardous constituents of the waste in accordance with Resource Conservation and Recovery Act requirements

  6. Technology Evaluations Related to Mercury, Technetium, and Chloride in Treatment of Wastes at the Idaho Nuclear Technology and Engineering Center of the Idaho National Engineering and Environmental Laboratory

    International Nuclear Information System (INIS)

    Barnes, C.M.; Taylor, D.D.; Ashworth, S.C.; Bosley, J.B.; Haefner, D.R.

    1999-01-01

    The Idaho High-Level Waste and Facility Disposition Environmental Impact Statement defines alternative for treating and disposing of wastes stored at the Idaho Nuclear Technology and Engineering Center. Development is required for several technologies under consideration for treatment of these wastes. This report contains evaluations of whether specific treatment is needed and if so, by what methods, to remove mercury, technetium, and chlorides in proposed Environmental Impact Statement treatment processes. The evaluations of mercury include a review of regulatory requirements that would apply to mercury wastes in separations processes, an evaluation of the sensitivity of mercury flowrates and concentrations to changes in separations processing schemes and conditions, test results from laboratory-scale experiments of precipitation of mercury by sulfide precipitation agents from the TRUEX carbonate wash effluent, and evaluations of methods to remove mercury from New Waste Calcining Facility liquid and gaseous streams. The evaluation of technetium relates to the need for technetium removal and alternative methods to remove technetium from streams in separations processes. The need for removal of chlorides from New Waste Calcining Facility scrub solution is also evaluated

  7. Technology Evaluations Related to Mercury, Technetium, and Chloride in Treatment of Wastes at the Idaho Nuclear Technology and Engineering Center of the Idaho National Engineering and Environmental Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    C. M. Barnes; D. D. Taylor; S. C. Ashworth; J. B. Bosley; D. R. Haefner

    1999-10-01

    The Idaho High-Level Waste and Facility Disposition Environmental Impact Statement defines alternative for treating and disposing of wastes stored at the Idaho Nuclear Technology and Engineering Center. Development is required for several technologies under consideration for treatment of these wastes. This report contains evaluations of whether specific treatment is needed and if so, by what methods, to remove mercury, technetium, and chlorides in proposed Environmental Impact Statement treatment processes. The evaluations of mercury include a review of regulatory requirements that would apply to mercury wastes in separations processes, an evaluation of the sensitivity of mercury flowrates and concentrations to changes in separations processing schemes and conditions, test results from laboratory-scale experiments of precipitation of mercury by sulfide precipitation agents from the TRUEX carbonate wash effluent, and evaluations of methods to remove mercury from New Waste Calcining Facility liquid and gaseous streams. The evaluation of technetium relates to the need for technetium removal and alternative methods to remove technetium from streams in separations processes. The need for removal of chlorides from New Waste Calcining Facility scrub solution is also evaluated.

  8. United States Nuclear Rocket Company (USNRC)

    Science.gov (United States)

    Hardin, L. A.

    2014-01-01

    Historically, the development of advanced space technology has been accomplished by the federal government providing funding to commercial companies through the standard contracting process. Although recently, commercial space ventures, such as Space X, have begun to develop enhanced commercial space launch capabilities, and many companies provide space related services - including satellite development and operations, advanced technology development still requires (and should require) participation by the federal agency assigned this role - the National Aeronautics and Space Administration (NASA). However, this standard funding model may not be the most efficient and stable means of developing the advanced technology systems. And while the federal government does not need to be involved in areas where private industry can reasonably operate, it should remain the leader in supporting the development of new and advanced space technologies to further increase our national capability. And as these technologies mature, then private industry can begin the commercialization process, freeing up resources and funds for NASA to develop the next generations of advanced space technology. In fact, simply examining the last decades of space technology development shows that there is room for improvement. Part of the problem is that there are realistically two space frontiers. There is the commercialization frontier (the realm of Space X and others) and the exploratory frontier (the realm of NASA.). Often technologies that can support the exploratory frontier can also immediately support the commercialization frontier. Yet, these technologies are still developed under the standard model of federal funding and contracting. Is that really the best way to proceed? In this paper, the argument is put forward that a new process is required, a new paradigm. A consortium of federal agencies as well as commercial companies is needed - in a collaborative rather than a contractual

  9. Nuclear Solid Waste Processing Design at the Idaho Spent Fuels Facility

    International Nuclear Information System (INIS)

    Dippre, M. A.

    2003-01-01

    A spent nuclear fuels (SNF) repackaging and storage facility was designed for the Idaho National Engineering and Environmental Laboratory (INEEL), with nuclear solid waste processing capability. Nuclear solid waste included contaminated or potentially contaminated spent fuel containers, associated hardware, machinery parts, light bulbs, tools, PPE, rags, swabs, tarps, weld rod, and HEPA filters. Design of the nuclear solid waste processing facilities included consideration of contractual, regulatory, ALARA (as low as reasonably achievable) exposure, economic, logistical, and space availability requirements. The design also included non-attended transfer methods between the fuel packaging area (FPA) (hot cell) and the waste processing area. A monitoring system was designed for use within the FPA of the facility, to pre-screen the most potentially contaminated fuel canister waste materials, according to contact- or non-contact-handled capability. Fuel canister waste materials which are not able to be contact-handled after attempted decontamination will be processed remotely and packaged within the FPA. Noncontact- handled materials processing includes size-reduction, as required to fit into INEEL permitted containers which will provide sufficient additional shielding to allow contact handling within the waste areas of the facility. The current design, which satisfied all of the requirements, employs mostly simple equipment and requires minimal use of customized components. The waste processing operation also minimizes operator exposure and operator attendance for equipment maintenance. Recently, discussions with the INEEL indicate that large canister waste materials can possibly be shipped to the burial facility without size-reduction. New waste containers would have to be designed to meet the drop tests required for transportation packages. The SNF waste processing facilities could then be highly simplified, resulting in capital equipment cost savings, operational

  10. Building an integrated nuclear engineering and nuclear science human resources pipeline at the Idaho National Engineering and Environmental Laboratory

    International Nuclear Information System (INIS)

    Sneed, A.; Sikorski, B.; Lineberry, M.; Jolly, J.

    2004-01-01

    Full text: In 2002, the US Department of Energy (US DOE) transferred sponsorship of the INEEL and ANL-W to the DOE Office of Nuclear Energy, Science and Technology and designated the INEEL and ANL-W as the nation's lead laboratories for nuclear reactor and nuclear fuel cycle research and development. This transfer acknowledged the laboratories' history, infrastructure, expertise and commitment to collaborate broadly in order to fulfill its assigned role as the nation's center for nuclear energy research and development. Key to this role is the availability of well-educated and trained nuclear engineers, professionals from other disciplines of engineering, nuclear scientists, and others with advanced degrees in supporting disciplines such as physics, chemistry, and math. In 2005 the INEEL and ANL-W will be combined into the Idaho National Laboratory (INL). One of US DOE's objectives for the INL will be for it to take a strong role in the revitalization of nuclear engineering and nuclear science education in the US. Responding to this objective for the INL and the national need to rejuvenate nuclear engineering and nuclear science research and education, ISU, University of Idaho (UI), Boise State University, the INEEL, and ANL-W are all supporting a new Institute of Nuclear Science and Engineering (INSE), initially proposed by and to be administered by ISU. The Institute will rely on the resources of both universities and the INL to create a US center for reactor and fuel cycle research to development and attract outstanding faculty and students to Idaho and to the INL. The Institute and other university based education development efforts represent only one component of a viable Human Resources Pipeline from university to leading edge laboratory researcher. Another critical component is the successful integration of new graduates into the laboratory research environment, the transfer of knowledge from senior researchers, and the development of these individuals into

  11. Structural Integrity Program for the Calcined Solids Storage Facilities at the Idaho Nuclear Technology and Engineering Center

    International Nuclear Information System (INIS)

    Bryant, J.W.; Nenni, J.A.

    2003-01-01

    This report documents the activities of the structural integrity program at the Idaho Nuclear Technology and Engineering Center relevant to the high-level waste Calcined Solids Storage Facilities and associated equipment, as required by DOE M 435.1-1, ''Radioactive Waste Management Manual.'' Based on the evaluation documented in this report, the Calcined Solids Storage Facilities are not leaking and are structurally sound for continued service. Recommendations are provided for continued monitoring of the Calcined Solids Storage Facilities

  12. Structural Integrity Program for the Calcined Solids Storage Facilities at the Idaho Nuclear Technology and Engineering Center

    International Nuclear Information System (INIS)

    Jeffrey Bryant

    2008-01-01

    This report documents the activities of the structural integrity program at the Idaho Nuclear Technology and Engineering Center relevant to the high-level waste Calcined Solids Storage Facilities and associated equipment, as required by DOE M 435.1-1, 'Radioactive Waste Management Manual'. Based on the evaluation documented in this report, the Calcined Solids Storage Facilities are not leaking and are structurally sound for continued service. Recommendations are provided for continued monitoring of the Calcined Solids Storage Facilities

  13. Establishment of professional nuclear power architectural engineering company

    International Nuclear Information System (INIS)

    Guo Dongli; Chen Hua

    2006-01-01

    The rapid development of nuclear power industry in China requires specialized management for the nuclear power engineering projects. It is necessary to establish the nuclear power architectural engineering company to meet the increasing market needs by providing the owner with specialized nuclear engineering project management and overall contracting services. It is imperative that the purpose of establishing the corporation and enterprise core competitiveness should be clearly identified when it is established. Its organizational structure should be geared to the enterprise operation management and development to facilitate the intensified project management and control, and improve its risk-proof ability. (authors)

  14. 75 FR 66746 - Idaho Power Company and Milner Dam, Inc; Notice of Application for Amendment of License, and...

    Science.gov (United States)

    2010-10-29

    .... Location: The project is located on the Snake River in Twin Falls and Cassia Counties, Idaho. g. Filed... the Upper Snake Water Supply Bank. l. Locations of the Application: A copy of the application is available for inspection and reproduction at the Commission's Public Reference Room, located at 888 First...

  15. 76 FR 20652 - Idaho Power Company; Notice of Application of Land Management Plan Update for the Bliss, Upper...

    Science.gov (United States)

    2011-04-13

    ... projects are located in south-central Idaho on the Snake River from river mile 551 near Bliss to river mile... and reproduction at the Commission's Public Reference Room, located at 888 First Street, NE., Room [email protected] , for TTY, call (202) 502-8659. A copy is also available for inspection and reproduction at...

  16. 75 FR 61459 - Idaho Power Company and Milner Dam, Inc.; Notice of Application for Amendment of License and...

    Science.gov (United States)

    2010-10-05

    ... located on the Snake River in Twin Falls and Cassia Counties, Idaho. g. Filed Pursuant to: Federal Power.... Locations of the Application: A copy of the application is available for inspection and reproduction at the... reproduction at the address in item (h) above. m. Individuals desiring to be included on the Commission's...

  17. Westinghouse Savannah River Company (WSRC) approach to nuclear facility maintenance

    International Nuclear Information System (INIS)

    Harrison, D.W.

    1991-01-01

    The Savannah River Site (SRS) in South Carolina is a 300+ square mile facility owned by the US Department of Energy (DOE) and operated by Westinghouse Savannah River Company (WSRC), the prime contractor; Bechtel Savannah River, Incorporated (BSRI) is a major subcontractor. The site has used all of the five nuclear reactors and it has the necessary nuclear materials processing facilities, as well as waste management and research facilities. The site has produced materials for the US nuclear arsenal and various isotopes for use in space research and nuclear medicine for more than 30 years. In 1989, WSRC took over as prime contractor, replacing E.I. du Pont de Nemours and Company. At this time, a concentrated effort began to more closely align the operating standards of this site with those accepted by the commercial nuclear industry of the United States. Generally, this meant acceptance of standards of the Institute of Nuclear Power Operations (INPO) for nuclear-related facilities at the site. The subject of this paper is maintenance of nuclear facilities and, therefore, excludes discussion of the maintenance of non-nuclear facilities and equipment

  18. Calcined Waste Storage at the Idaho Nuclear Technology and Engineering Center

    Energy Technology Data Exchange (ETDEWEB)

    Staiger, M. Daniel, Swenson, Michael C.

    2011-09-01

    This comprehensive report provides definitive volume, mass, and composition (chemical and radioactivity) of calcined waste stored at the Idaho Nuclear Technology and Engineering Center. Calcine composition data are required for regulatory compliance (such as permitting and waste disposal), future treatment of the caline, and shipping the calcine to an off-Site-facility (such as a geologic repository). This report also contains a description of the calcine storage bins. The Calcined Solids Storage Facilities (CSSFs) were designed by different architectural engineering firms and built at different times. Each CSSF has a unique design, reflecting varying design criteria and lessons learned from historical CSSF operation. The varying CSSF design will affect future calcine retrieval processes and equipment. Revision 4 of this report presents refinements and enhancements of calculations concerning the composition, volume, mass, chemical content, and radioactivity of calcined waste produced and stored within the CSSFs. The historical calcine samples are insufficient in number and scope of analysis to fully characterize the entire inventory of calcine in the CSSFs. Sample data exist for all the liquid wastes that were calcined. This report provides calcine composition data based on liquid waste sample analyses, volume of liquid waste calcined, calciner operating data, and CSSF operating data using several large Microsoft Excel (Microsoft 2003) databases and spreadsheets that are collectively called the Historical Processing Model. The calcine composition determined by this method compares favorably with historical calcine sample data.

  19. Calcined Waste Storage at the Idaho Nuclear Technology and Engineering Center

    International Nuclear Information System (INIS)

    Staiger, M. Daniel; Swenson, Michael C.

    2011-01-01

    This comprehensive report provides definitive volume, mass, and composition (chemical and radioactivity) of calcined waste stored at the Idaho Nuclear Technology and Engineering Center. Calcine composition data are required for regulatory compliance (such as permitting and waste disposal), future treatment of the caline, and shipping the calcine to an off-Site-facility (such as a geologic repository). This report also contains a description of the calcine storage bins. The Calcined Solids Storage Facilities (CSSFs) were designed by different architectural engineering firms and built at different times. Each CSSF has a unique design, reflecting varying design criteria and lessons learned from historical CSSF operation. The varying CSSF design will affect future calcine retrieval processes and equipment. Revision 4 of this report presents refinements and enhancements of calculations concerning the composition, volume, mass, chemical content, and radioactivity of calcined waste produced and stored within the CSSFs. The historical calcine samples are insufficient in number and scope of analysis to fully characterize the entire inventory of calcine in the CSSFs. Sample data exist for all the liquid wastes that were calcined. This report provides calcine composition data based on liquid waste sample analyses, volume of liquid waste calcined, calciner operating data, and CSSF operating data using several large Microsoft Excel (Microsoft 2003) databases and spreadsheets that are collectively called the Historical Processing Model. The calcine composition determined by this method compares favorably with historical calcine sample data.

  20. Plight of China nuclear liability law and solutions of nuclear operating companies

    International Nuclear Information System (INIS)

    Su Guangchao; Wang Yonggang; Tang Yangyang

    2010-01-01

    With the development of nuclear use for peaceful purposes and the intensification of international cooperation in the field of nuclear energy, many countries attach more and more importance to legal risks of nuclear liability, and the companies in nuclear industry also enhance research on restrictive articles of nuclear liability in their international businesses. However, because China has neither signed any international convention on civil liability for nuclear damage nor adopted any law on atomic energy and on compensation for nuclear damage, many impediments often occur in international cooperation and trade. This essay is trying to outline the status and structure of international nuclear liability, analyze nuclear liabilities in international procurement for nuclear operating companies and respective solutions. (authors)

  1. Managing key capabilities: A challenge for nuclear plant building companies

    International Nuclear Information System (INIS)

    Pascal Corbel

    2003-01-01

    The nuclear plant building industry faces a paradoxical situation. The use of nuclear reactors to produce energy for civil purposes is both a promising technology, with potentially huge outlets, and a technology facing declining demand. One of the key problems is then: how to maintain the capabilities necessary to benefit from the potential recovery? The resource-based view of strategic management has shown the importance of different types of resources and capabilities in gaining a sustainable competitive advantage. Successful incumbents in the market of nuclear station building have built those kinds of distinctive capabilities that give them a competitive advantage over potential new entrants. But we show that, without a permanent activity in plant building, preserving those capabilities necessitates specific strategic action. We firstly develop the argument that the nuclear plant building industry is in a paradoxical situation in terms of demand and technical performance trends. Secondly, we try to identify the key capabilities of the incumbents. We show that companies in that field use mainly three types of distinctive capabilities: pure technical and scientific knowledge in direct relation to the use of nuclear as an energy generator, competences in risk management and competences in large project management, including financing. Thirdly, we show that although some of those capabilities are used through other nuclear-related activities such as plant maintenance or fuel supply, some of them necessitate taking strategic actions in order to be preserved. We argue that this should be a priority of nuclear equipment company managers in the next few years. (author)

  2. 75 FR 6736 - FirstEnergy Nuclear Operating Company, FirstEnergy Nuclear Generation Corp., Ohio Edison Company...

    Science.gov (United States)

    2010-02-10

    ..., Beaver Valley Power Station, Unit Nos. 1 and 2; Environmental Assessment and Finding of No Significant Impact The U.S. Nuclear Regulatory Commission (NRC) is considering issuance of an exemption, pursuant to... Operating Company (licensee), for operation of the Beaver Valley Power Station, Unit Nos. 1 and 2 (BVPS-1...

  3. Company of the month: French EDF opts for nuclear power

    International Nuclear Information System (INIS)

    Jansen, Siw Linnea

    2006-01-01

    EDF is Europe's largest power company with 640 TWh produced in 2005 and 36,7 million customers in Europe. On a global scale the company has more than 40 million customers. EDF has significant positions in the four big energy markets in Europe: Germany, France, Great Britain and Italy. EDF has an ambitious investment program in the area of nuclear power, and holds that increased investments in this sector is the best and most beneficial way of keeping up with Europe's increasing energy demand (ml)

  4. Nuclear decontamination and decommissioning operations at the Idaho National Engineering and Environmental Laboratory (INEEL)

    International Nuclear Information System (INIS)

    Meservey, R.H.; Kenoyer, D.J.; Frazee, B.J.

    1997-01-01

    The Idaho National engineering and Environmental Laboratory (INEEL) is home of the largest concentration of nuclear reactors in the world. In addition to the reactors, many fuel reprocessing, laboratory, and other nuclear support facilities have been operated at the INEEL. Many have already been decontaminated and decommissioned (D and D) and many more are in the planning stages for such activities. A full time D and D program has been in existence at the INEEL for the past 20 years. Starting with a long range plan for D and D of all surplus contaminated facilities at the INEEL, and ending with the verification of the free release of those facilities after decommissioning, all aspects of D and D activities are covered. Topics covered in this paper include the INEEL D and D Long Range Plan, the D and D Porject Managers Handbook, the use of ASTM Standard Guides in decommissioning operations, and the INEEL D and D Technology Logic Diagrams. The identification and preparation of safety plans, environmental documentation, and operational procedures will also be covered in the presentation. The selection and use of advanced technologies to improve safety, reduce costs, and shorten D and D schedules is very important to the nuclear industry. In addition to a discussion of the D and D Technology Logic Diagrams, a discussion of new and improved technologies in use at the INEEL and other department of energy facilities will be presented. This will include brief discussions of work being performed at three Department of Energy Large Scale D and D Technology Demonstration projects. These include technology demonstrations at a Test Reactor, Uranium Fabrication Plant, and a large Production Reactor. Unique technologies which have been developed and tested at the INEEL will also be covered in the presentation. These include the biological decontamination of concrete, a laser enhanced zero added waste cutting, abraiding, and drilling technology, and the development of an

  5. Tiger Team assessment of the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    1991-08-01

    The Management Subteam conducted a management assessment of Environment, Safety, and Health (ES ampersand H) programs and their implementation of Idaho National Engineering Laboratory (INEL). The objectives of the assessment were to: (1) evaluate the effectiveness of existing management functions and processes in terms of ensuring environmental compliance, and the health and safety of workers and the general public; and (2) identify probable root causes for ES ampersand H findings and concerns. Organizations reviewed were DOE-Headquarters: DOE Field Offices, Chicago (CH) and Idaho (ID); Argonne Area Offices, East (AAO-E) and West (AAO-W); Radiological and Environmental Sciences Laboratory (RESL); Argonne National Laboratory (ANL); EG ampersand G Idaho, Inc. (EG ampersand G); Westinghouse Idaho Nuclear Company, Inc. (WINCO); Rockwell-INEL; MK-Ferguson of Idaho Company (MK-FIC); and Protection Technology of Idaho, Inc. (PTI). The scope of the assessment covered the following ES ampersand H management issues: policies and procedures; roles, responsibilities, and authorities; management commitment; communication; staff development, training, and certification; recruitment; compliance management; conduct of operations; emergency planning and preparedness; quality assurance; self assessment; oversight activities; and cost plus award fee processes

  6. Tiger Team assessment of the Idaho National Engineering Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Goldberg, Edward S.; Keating, John J.

    1991-08-01

    The Management Subteam conducted a management assessment of Environment, Safety, and Health (ES H) programs and their implementation of Idaho National Engineering Laboratory (INEL). The objectives of the assessment were to: (1) evaluate the effectiveness of existing management functions and processes in terms of ensuring environmental compliance, and the health and safety of workers and the general public; and (2) identify probable root causes for ES H findings and concerns. Organizations reviewed were DOE-Headquarters: DOE Field Offices, Chicago (CH) and Idaho (ID); Argonne Area Offices, East (AAO-E) and West (AAO-W); Radiological and Environmental Sciences Laboratory (RESL); Argonne National Laboratory (ANL); EG G Idaho, Inc. (EG G); Westinghouse Idaho Nuclear Company, Inc. (WINCO); Rockwell-INEL; MK-Ferguson of Idaho Company (MK-FIC); and Protection Technology of Idaho, Inc. (PTI). The scope of the assessment covered the following ES H management issues: policies and procedures; roles, responsibilities, and authorities; management commitment; communication; staff development, training, and certification; recruitment; compliance management; conduct of operations; emergency planning and preparedness; quality assurance; self assessment; oversight activities; and cost plus award fee processes.

  7. 'Nuclearelectrica' Company messages for a broadly acceptable nuclear power program

    International Nuclear Information System (INIS)

    Stiopol, Mihaela; Bilegan, C. Iosif

    2001-01-01

    Romania started the nuclear power program about 20 years ago, by a high level Government decision. After 1989 the former Ministry of Electrical Power was transformed into a state owned company, RENEL, in which nuclear activities were also included. RENEL was a monopoly system responsible for production, transport and distribution of electricity in Romania. The deregulation process in the power sector was many times asked by the World Bank and International Monetary Fund, to split this monopoly system in separately activities: Production, Transport and Distribution. The first step occurred in July 1998, when the nuclear activities were externalized from RENEL. In nuclear sector two new entities were created: SN 'Nuclearelectrica' SA, a state own company that includes three branches: - Nuclear Power Production - Cernavoda NPP Unit 1; - Nuclear Fuel Plant-Pitesti; - Project Development Branch - Cernavoda Units 2-5. The second entity is the so-called Romanian Authority (Autonomous Reggie) for Nuclear Activities (RAAN), including as branches the heavy water fabrication plant 'ROMAG PROD', the Nuclear Research Institute (ICN) Pitesti and the Nuclear Engineering and Design Institute (CITON) Bucharest. The rest of conventional power sector was renamed, namely, CONEL. The organization process continued and in August 2000, by a Government Ordinance the CONEL was split into the following companies: - one for hydropower production 'HIDROELECTRICA'; - one for thermal power production 'TERMOELECTRICA'; - one for transport 'TRANSELECTRICA'; - one for distribution 'ELECTRICA'. The goal of a third step of restructuring process is the privatization in the power field. The steps of Romanian Power Sector Restructuring are presented. Since 1991 a Public Information program has been established. Depending on the evolution of the construction of the first Romanian nuclear power station, during the years, the messages changed. Everybody working in the nuclear field knows how difficult is

  8. Department of Energy Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs draft environmental impact statement. Volume 1, Appendix B: Idaho National Engineering Laboratory Spent Nuclear Fuel Management Program

    Energy Technology Data Exchange (ETDEWEB)

    1994-06-01

    The US Department of Energy (DOE) has prepared this report to assist its management in making two decisions. The first decision, which is programmatic, is to determine the management program for DOE spent nuclear fuel. The second decision is on the future direction of environmental restoration, waste management, and spent nuclear fuel management activities at the Idaho National Engineering Laboratory. Volume 1 of the EIS, which supports the programmatic decision, considers the effects of spent nuclear fuel management on the quality of the human and natural environment for planning years 1995 through 2035. DOE has derived the information and analysis results in Volume 1 from several site-specific appendixes. Volume 2 of the EIS, which supports the INEL-specific decision, describes environmental impacts for various environmental restoration, waste management, and spent nuclear fuel management alternatives for planning years 1995 through 2005. This Appendix B to Volume 1 considers the impacts on the INEL environment of the implementation of various DOE-wide spent nuclear fuel management alternatives. The Naval Nuclear Propulsion Program, which is a joint Navy/DOE program, is responsible for spent naval nuclear fuel examination at the INEL. For this appendix, naval fuel that has been examined at the Naval Reactors Facility and turned over to DOE for storage is termed naval-type fuel. This appendix evaluates the management of DOE spent nuclear fuel including naval-type fuel.

  9. Idaho Nuclear Technology and Engineering Center Low-Activity Waste Process Technology Program FY-98 Status Report

    International Nuclear Information System (INIS)

    Herbst, A.K.; McCray, J.A.; Rogers, A.Z.; Simmons, R.F.; Palethrope, S.J.

    1999-01-01

    The Low-Activity Waste Process Technology Program at the Idaho Nuclear Technology and Engineering Center (INTEC) anticipates that large volumes of low-level/low-activity wastes will need to be grouted prior to near-surface disposal. During fiscal year 1998, three grout formulations were studied for low-activity wastes derived from INTEC liquid sodium-bearing waste. Compressive strength and leach results are presented for phosphate bonding cement, acidic grout, and alkaline grout formulations. In an additional study, grout formulations are recommended for stabilization of the INTEC underground storage tank residual heels

  10. Environmental radiation monitoring around Korea nuclear fuel company

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Myung Ho; Lee, Chang Woo; Choi, Gyun Sik; Lee, Won Yun; Park, Hyu Gok; Park, Do Won [Korea Atomic Energy Research Institute, Taejeon (Korea)

    2002-01-01

    Environmental Radiation Monitoring was carried out with measurement of environmental radiation and environmental radioactivity analysis around Korea Nuclear Fuel Company. Environmental Radiation rates measured by portable ERM and accumulated dose rates measured by TLD were on the same level as those measured in the previous years. Total alpha and beta concentrations in the air particulates showed the similar values in all sampling points. The concentration of uranium isotopes in soils and underground waters were measured similar to natural uranium values. The concentration of uranium isotopes in surface waters and sediments around the nuclear facilities were somewhat higher than those from reference site. The concentrations of uranium isotopes in rain water and foods such as rices and vegetables were similar to natural uranium level, the environment around the nuclear facilities has been contaminated only to an insignificant extent. It is estimated that the environmental impact resulting from the operation of KNFC in 2001 was negligible. 31 refs., 30 figs., 41 tabs. (Author)

  11. Developments of Spent Nuclear Fuel Pyroprocessing Technology at Idaho National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Michael F. Simpson

    2012-03-01

    This paper summarizes research in used fuel pyroprocessing that has been published by Idaho National Laboratory over the last decade. It includes work done both on treatment of Experimental Breeder Reactor-II and development of advanced technology for potential scale-up and commercialization. Collaborations with universities and other laboratories is included in the cited work.

  12. Piercing of corporate veil of nuclear companies; Durchgriffshaftung der Atomkonzerne

    Energy Technology Data Exchange (ETDEWEB)

    Frenz, Walter [RWTH Aachen Univ. (Germany). Lehr- und Forschungsgebiet Berg-, Umwelt- und Europarecht

    2015-11-15

    The Federal Ministry of Economics plans that the nuclear companies with all their assets to cover disposal costs can be used where a power plant operator is governed by its parent company, hence the latter Capital or voting majority of the operators holding or these passes; To date, the parent company is liable only limited and not more than five years after the end of the domination of one Subsidiary, oparating a power plant. In this way, prevents ultimately the public sector and thus the Taxpayers have to pay for the long-term consequences of the use of nuclear energy. Until now ensured paragraph 303 AktG a group law Secondary liability the parent companies of the operating company in the case of of termination of the control and profit transfer agreements is very limited for the nuclear liabilities, namely in two ways: The claim is only focused on the backup performance and not at the expense of acquisition and Moreover, according to the case law limited of five years after its foundation; for the area of transformation law comparable rules are valid. thereby the dismantling of a nuclear power station takes just already for 20 years and a final repository is expected before 2050 not be available. [German] Das Bundeswirtschaftsministerium plant, dass die Atomkonzerne mit ihrem ganzen Vermoegen zur Deckung der Entsorgungskosten herangezogen werden koennen, soweit ein Kraftwerksbetreiber von seinem Mutterkonzern beherrscht wird, mithin Letzterer die Kapital- oder Stimmrechtsmehrheit an dem Betreiber haelt bzw. diesen leitet; bislang haftet der Mutterkonzern nur eingeschraenkt und hoechstens fuenf Jahre nach Beendigung der Beherrschung einer Tochtergesellschaft, die ein Kraftwerk betreibt. Auf diese Weise wird verhindert, dass letztlich die oeffentliche Hand und damit der Steuerzahler fuer die Spaetfolgen der Kernenergienutzung zahlen muss. Bislang gewaehrleistet paragraph 303 AktG eine konzernrechtliche Nachhaftung der Muttergesellschaften der

  13. An overview of environmental surveillance of waste management activities at the Idaho National Engineering Laboratory

    Science.gov (United States)

    Smith, T.H.; Chew, E.W.; Hedahl, T.G.; Mann, L.J.; Pointer, T.F.; Wiersma, G.B.

    1986-01-01

    The Idaho National Engineering Laboratory (INEL), in southeastern Idaho, is a principal center for nuclear energy development for the Department of Energy (DOE) and the U.S. Nuclear Navy. Fifty-two reactors have been built at the INEL, with 15 still operable. Extensive environmental surveillance is conducted at the INEL by DOE's Radiological Environmental Sciences Laboratory (RESL), and the U.S. Geological Survey (USGS), the National Oceanic and Atmospheric Administration (NOAA), EG&G Idaho, Inc., and Westinghouse Idaho Nuclear Company (WINCO). Surveillance of waste management facilities radiation is integrated with the overall INEL Site surveillance program. Air, warer, soil, biota, and environmental radiation are monitored or sampled routinely at INEL. Results to date indicate very small or no impacts from INEL on the surrounding environment. Environmental surveillance activities are currently underway to address key environmental issues at the INEL.

  14. Overview of environmental surveillance of waste management activities at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Smith, T.H.; Hedahl, T.G.; Wiersma, G.B.; Chew, E.W.; Mann, L.J.; Pointer, T.F.

    1986-02-01

    The Idaho National Engineering Laboratory (INEL), in southeastern Idaho, is a principal center for nuclear energy development for the Department of Energy (DOE) and the US Nuclear Navy. Fifty-two reactors have been built at the INEL, with 15 still operable. Extensive environmental surveillance is conducted at the INEL by DOE's Radiological and Environmental Sciences Laboratory (RESL), the US Geological Survey (USGS), the National Oceanic and Atmospheric Administration (NOAA), EG and G Idaho, Inc., and Westinghouse Idaho Nuclear Company (WINCO). Surveillance of waste management facilities is integrated with the overall INEL Site surveillance program. Air, water, soil, biota, and environmental radiation are monitored or sampled routinely at the INEL. Results to date indicate very small or no impacts from the INEL on the surrounding environment. Environmental surveillance activities are currently underway to address key environmental issues at the INEL. 7 refs., 6 figs., 2 tabs

  15. 75 FR 11566 - Firstenergy Nuclear Operating Company, Firstenergy Nuclear Generation Corp., Ohio Edison Company...

    Science.gov (United States)

    2010-03-11

    ... deep drop and a fuel to fuel drop. The shallow drop postulates that the fuel assembly drops vertically... need for SUNSI, deadline for NRC staff to complete information processing and file motion for... Information AGENCY: Nuclear Regulatory Commission. ACTION: Order and notice of license amendment request...

  16. 75 FR 57299 - First Energy Nuclear Operating Company; Notice of Receipt and Availability of Application for...

    Science.gov (United States)

    2010-09-20

    ... NUCLEAR REGULATORY COMMISSION [NRC-2010-0298; Docket No. 50-346] First Energy Nuclear Operating Company; Notice of Receipt and Availability of Application for Renewal of Davis Besse Nuclear Power...Energy Nuclear Operating Company, filed pursuant to Section 104(b) of the Atomic Energy Act of 1954, as...

  17. Companies which maintain the nuclear fleet - Information note 2015

    International Nuclear Information System (INIS)

    2015-01-01

    This publication first recalls the reasons for subcontracting the maintenance of French nuclear plants (need of specialised expertise and abilities) even though EDF keeps an industrial and technical control. It describes the framework of these subcontracted activities (a long lasting collaboration, implementation of requirements), and how multi-annual markets are subcontracted to support the development of specialised companies. It outlines to which extent the selection and certification process is rigorous, that subcontractor salaried personnel is to be specifically trained, that radiation protection is performed under the same conditions for everybody. It indicates some specific measures which have been implemented to take subcontractor personnel working conditions into account. The updating of abilities for future activities is discussed. Some key data are provided regarding jobs, contracts, training, medical expenses, and fields of activity of subcontracting companies

  18. Environmental radiation monitoring around Korea Nuclear Fuel Company

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Myung Ho; Lee, Chang Woo; Choi, Yong Ho; Cho, Yueng Hyun; Choi, Gyun Sik [Korea Atomic Energy Research Institute, Taejon (Korea)

    1999-12-01

    Environmental Radiation Monitoring was carried out with measurement of environmental radiation and environmental radioactivity analysis around Korea Nuclear Fuel Company. Environmental Radiation rates measured by Portable ERM and accumulated dose rates measured by TLD were same level compared with past years. Total alpha and beta concentrations in the air particulates showed the similar values in all sampling points. The concentration of uranium isotopes in soils and underground waters were measured similar to natural uranium values. The concentration of uranium isotopes in surface waters and sediments decreased with increasing distances from the point of discharge. The concentrations of uranium isotopes in rain water and foods such as rices and vegetables were not detected or measured similar to natural uranium level. Hence, the environment around the nuclear facilities in Korea has been contaminated only to an insignificant extent, although a small amount of disequilibated uranium was detected within 4 km downstream of the point of discharge of KNFC. 31 refs., 26 figs., 42 tabs. (Author)

  19. Cultural Resource Investigations for the Resumption of Transient Testing of Nuclear Fuels and Material at the Idaho National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Pace, Brenda R. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Williams, Julie B. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2013-11-01

    The U. S. Department of Energy (DOE) has a need to test nuclear fuels under conditions that subject them to short bursts of intense, high-power radiation called ‘transient testing’ in order to gain important information necessary for licensing new nuclear fuels for use in U.S. nuclear power plants, for developing information to help improve current nuclear power plant performance and sustainability, for improving the affordability of new generation reactors, for developing recyclable nuclear fuels, and for developing fuels that inhibit any repurposing into nuclear weapons. To meet this mission need, DOE is considering alternatives for re-use and modification of existing nuclear reactor facilities to support a renewed transient testing program. One alternative under consideration involves restarting the Transient Reactor Test (TREAT) reactor located at the Materials and Fuels Complex (MFC) on the Idaho National Laboratory (INL) site in southeastern Idaho. This report summarizes cultural resource investigations conducted by the INL Cultural Resource Management Office in 2013 to support environmental review of activities associated with restarting the TREAT reactor at the INL. These investigations were completed in order to identify and assess the significance of cultural resources within areas of potential effect associated with the proposed action and determine if the TREAT alternative would affect significant cultural resources or historic properties that are eligible for nomination to the National Register of Historic Places. No archaeological resources were identified in the direct area of potential effects for the project, but four of the buildings proposed for modifications are evaluated as historic properties, potentially eligible for nomination to the National Register of Historic Places. This includes the TREAT reactor (building #), control building (building #), guardhouse (building #), and warehouse (building #). The proposed re-use of these historic

  20. Tiger Team assessment of the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    1991-08-01

    The purpose of the Safety and Health (S ampersand H) Subteam assessment was to determine the effectiveness of representative safety and health programs at the Idaho National Engineering Laboratory (INEL) site. Four Technical Safety Appraisal (TSA) Teams were assembled for this purpose by the US Department of Energy (DOE), Deputy Assistant Secretary for Safety and Quality Assurance, Office of Safety Appraisals (OSA). Team No. 1 reviewed EG ampersand G Idaho, Inc. (EG ampersand G Idaho) and the Department of Energy Field Office, Idaho (ID) Fire Department. Team No. 2 reviewed Argonne National Laboratory-West (ANL-W). Team No. 3 reviewed selected contractors at the INEL; specifically, Morrison Knudsen-Ferguson of Idaho Company (MK-FIC), Protection Technology of Idaho, Inc. (PTI), Radiological and Environmental Sciences Laboratory (RESL), and Rockwell-INEL. Team No. 4 provided an Occupational Safety and Health Act (OSHA)-type compliance sitewide assessment of INEL. The S ampersand H Subteam assessment was performed concurrently with assessments conducted by Environmental and Management Subteams. Performance was appraised in the following technical areas: Organization and Administration, Quality Verification, Operations, Maintenance, Training and Certification, Auxiliary Systems, Emergency Preparedness, Technical Support, Packaging and Transportation, Nuclear Criticality Safety, Security/Safety Interface, Experimental Activities, Site/Facility Safety Review, Radiological Protection, Personnel Protection, Worker Safety and Health (OSHA) Compliance, Fire Protection, Aviation Safety, Medical Services, and Firearms Safety

  1. Tiger Team assessment of the Idaho National Engineering Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    McKenzie, Barbara J.; West, Stephanie G.; Jones, Olga G.; Kerr, Dorothy A.; Bieri, Rita A.; Sanderson, Nancy L.

    1991-08-01

    The purpose of the Safety and Health (S H) Subteam assessment was to determine the effectiveness of representative safety and health programs at the Idaho National Engineering Laboratory (INEL) site. Four Technical Safety Appraisal (TSA) Teams were assembled for this purpose by the US Department of Energy (DOE), Deputy Assistant Secretary for Safety and Quality Assurance, Office of Safety Appraisals (OSA). Team No. 1 reviewed EG G Idaho, Inc. (EG G Idaho) and the Department of Energy Field Office, Idaho (ID) Fire Department. Team No. 2 reviewed Argonne National Laboratory-West (ANL-W). Team No. 3 reviewed selected contractors at the INEL; specifically, Morrison Knudsen-Ferguson of Idaho Company (MK-FIC), Protection Technology of Idaho, Inc. (PTI), Radiological and Environmental Sciences Laboratory (RESL), and Rockwell-INEL. Team No. 4 provided an Occupational Safety and Health Act (OSHA)-type compliance sitewide assessment of INEL. The S H Subteam assessment was performed concurrently with assessments conducted by Environmental and Management Subteams. Performance was appraised in the following technical areas: Organization and Administration, Quality Verification, Operations, Maintenance, Training and Certification, Auxiliary Systems, Emergency Preparedness, Technical Support, Packaging and Transportation, Nuclear Criticality Safety, Security/Safety Interface, Experimental Activities, Site/Facility Safety Review, Radiological Protection, Personnel Protection, Worker Safety and Health (OSHA) Compliance, Fire Protection, Aviation Safety, Medical Services, and Firearms Safety.

  2. Tiger Team assessment of the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    1991-08-01

    This report documents the Tiger Team Assessment of the Idaho National Engineering Laboratory (INEL) located in Idaho Falls, Idaho. INEL is a multiprogram, laboratory site of the US Department of Energy (DOE). Overall site management is provided by the DOE Field Office, Idaho; however, the DOE Field Office, Chicago has responsibility for the Argonne National Laboratory-West facilities and operations through the Argonne Area Office. In addition, the Idaho Branch Office of the Pittsburgh Naval Reactors Office has responsibility for the Naval Reactor Facility (NRF) at the INEL. The assessment included all DOE elements having ongoing program activities at the site except for the NRF. In addition, the Safety and Health Subteam did not review the Westinghouse Idaho Nuclear Company, Inc. facilities and operations. The Tiger Team Assessment was conducted from June 17 to August 2, 1991, under the auspices of the Office of Special Projects, Office of the Assistant Secretary for Environment, Safety and Health, Headquarters, DOE. The assessment was comprehensive, encompassing environmental, safety, and health (ES ampersand H) disciplines; management; and contractor and DOE self-assessments. Compliance with applicable federal, state, and local regulations; applicable DOE Orders; best management practices; and internal INEL site requirements was assessed. In addition, an evaluation of the adequacy and effectiveness of the DOE and the site contractors management of ES ampersand H/quality assurance programs was conducted

  3. Tiger Team assessment of the Idaho National Engineering Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    1991-08-01

    This report documents the Tiger Team Assessment of the Idaho National Engineering Laboratory (INEL) located in Idaho Falls, Idaho. INEL is a multiprogram, laboratory site of the US Department of Energy (DOE). Overall site management is provided by the DOE Field Office, Idaho; however, the DOE Field Office, Chicago has responsibility for the Argonne National Laboratory-West facilities and operations through the Argonne Area Office. In addition, the Idaho Branch Office of the Pittsburgh Naval Reactors Office has responsibility for the Naval Reactor Facility (NRF) at the INEL. The assessment included all DOE elements having ongoing program activities at the site except for the NRF. In addition, the Safety and Health Subteam did not review the Westinghouse Idaho Nuclear Company, Inc. facilities and operations. The Tiger Team Assessment was conducted from June 17 to August 2, 1991, under the auspices of the Office of Special Projects, Office of the Assistant Secretary for Environment, Safety and Health, Headquarters, DOE. The assessment was comprehensive, encompassing environmental, safety, and health (ES H) disciplines; management; and contractor and DOE self-assessments. Compliance with applicable federal, state, and local regulations; applicable DOE Orders; best management practices; and internal INEL site requirements was assessed. In addition, an evaluation of the adequacy and effectiveness of the DOE and the site contractors management of ES H/quality assurance programs was conducted.

  4. Department of Energy Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs Draft Environmental Impact Statement

    International Nuclear Information System (INIS)

    1994-06-01

    This volume contains the following attachments: transportation of Naval spent nuclear fuel; description of Naval spent nuclear receipt and handling at the Expended Core Facility at the Idaho National Engineering Laboratory; comparison of storage in new water pools versus dry container storage; description of storage of Naval spent nuclear fuel at servicing locations; description of receipt, handling, and examination of Naval spent nuclear fuel at alternate DOE facilities; analysis of normal operations and accident conditions; and comparison of the Naval spent nuclear fuel storage environmental assessment and this environmental impact statement

  5. Department of Energy Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs draft environmental impact statement

    International Nuclear Information System (INIS)

    1994-06-01

    This document analyzes at a programmatic level the potential environmental consequences over the next 40 years of alternatives related to the transportation, receipt, processing, and storage of spent nuclear fuel under the responsibility of the US Department of Energy. It also analyzes the site-specific consequences of the Idaho National Engineering Laboratory sitewide actions anticipated over the next 10 years for waste and spent nuclear fuel management and environmental restoration. For programmatic spent nuclear fuel management, this document analyzes alternatives of no action, decentralization, regionalization, centralization and the use of the plans that existed in 1992/1993 for the management of these materials. For the Idaho National Engineering Laboratory, this document analyzes alternatives of no action, ten-year plan, minimum and maximum treatment, storage, and disposal of US Department of Energy wastes

  6. Department of Energy Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs Draft Environmental Impact Statement

    International Nuclear Information System (INIS)

    1994-06-01

    This document analyzes at a pregrammatic level the potential environmental consequences over the next 40 years of alternatives related to the transportation, receipt, processing, and storage of spent nuclear fuel under the responsibility of the US Department of Energy. It also analyzes the site-specific consequences of the Idaho National Engineering Laboratory sitewide actions anticipated over the next 10 years for waste and spent nuclear fuel management and environmental restoration. For pregrammatic spent nuclear fuel management, this document analyzes alternatives of no action, decentralization, regionalization, centralization and the use of the plans that existed in 1992/1993 for the management of these materials. For the Idaho National Engineering Laboratory, this document analyzes alternatives of no action, ten-year plan, minimum and maximum treatment, storage, and disposal of US Department of Energy wastes

  7. Department of Energy Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs Draft Environmental Impact Statement. Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    1994-06-01

    This document analyzes at a pregrammatic level the potential environmental consequences over the next 40 years of alternatives related to the transportation, receipt, processing, and storage of spent nuclear fuel under the responsibility of the US Department of Energy. It also analyzes the site-specific consequences of the Idaho National Engineering Laboratory sitewide actions anticipated over the next 10 years for waste and spent nuclear fuel management and environmental restoration. For pregrammatic spent nuclear fuel management, this document analyzes alternatives of no action, decentralization, regionalization, centralization and the use of the plans that existed in 1992/1993 for the management of these materials. For the Idaho National Engineering Laboratory, this document analyzes alternatives of no action, ten-year plan, minimum and maximum treatment, storage, and disposal of US Department of Energy wastes.

  8. Department of Energy Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs Draft Environmental Impact Statement

    International Nuclear Information System (INIS)

    1994-06-01

    This document analyzes at a programmatic level the potential environmental consequences over the next 40 years of alternatives related to the transportation, receipt, processing, and storage of spent nuclear fuel under the responsibility of the US Department of Energy. It also analyzes the site-specific consequences of the Idaho National Engineering Laboratory sitewide actions anticipated over the next 10 years for waste and spent nuclear fuel management and environmental restoration. For programmatic spent nuclear fuel management this document analyzes alternatives of no action, decentralization, regionalization, centralization and the use of the plans that existed in 1992/1993 for the management of these materials. For the Idaho National Engineering Laboratory, this document analyzes alternatives of no action, ten-year plan, minimum and maximum and maximum treatment, storage, and disposal of US Department of Energy wastes

  9. Department of Energy Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs Draft Environmental Impact Statement. Volume 2, Part A

    Energy Technology Data Exchange (ETDEWEB)

    1994-06-01

    This document analyzes at a programmatic level the potential environmental consequences over the next 40 years of alternatives related to the transportation, receipt, processing, and storage of spent nuclear fuel under the responsibility of the US Department of Energy. It also analyzes the site-specific consequences of the Idaho National Engineering Laboratory sitewide actions anticipated over the next 10 years for waste and spent nuclear fuel management and environmental restoration. For programmatic spent nuclear fuel management this document analyzes alternatives of no action, decentralization, regionalization, centralization and the use of the plans that existed in 1992/1993 for the management of these materials. For the Idaho National Engineering Laboratory, this document analyzes alternatives of no action, ten-year plan, minimum and maximum and maximum treatment, storage, and disposal of US Department of Energy wastes.

  10. Kemeny commission report. Comments by NPC (Nuclear Power Company)

    Energy Technology Data Exchange (ETDEWEB)

    1979-01-01

    Following the accident at Three Mile island in March 1979 the Nuclear Power Company (NPC) has made evaluations of the available information and carried out preliminary investigations of the implications of the accident for all UK AGR's and for the PWR design. The results are summarized. Recommendations of the President's Commission are discussed with especial reference to those under the following headings: (1) The utility and its suppliers. (2) Training of operating personnel. (3) Technical assessment. It is concluded that while many of the relevant recommendations in the report of the President's Commission are already satisfied by UK practices for nuclear safety, and are being applied by NPC in their current programmes of work on AGR's and PWR's it is realised that it is of the utmost importance that complacent attitudes to safety are not allowed to develop. The accident at TMI and report of the Commision have provided a sharp reminder of the necessity to maintain unremitting vigilance in all aspects of design, construction and operation which are involved with the safety of the public and operators.

  11. Department of Energy Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs, Draft Environmental Impact Statement

    International Nuclear Information System (INIS)

    1994-06-01

    Volume 1 to the Department of Energy's Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Management Programs Environmental Impact Statement evaluates a range of alternatives for managing naval spent nuclear fuel expected to be removed from US Navy nuclear-powered vessels and prototype reactors through the year 2035. The Environmental Impact Statement (EIS) considers a range of alternatives for examining and storing naval spent nuclear fuel, including alternatives that terminate examination and involve storage close to the refueling or defueling site. The EIS covers the potential environmental impacts of each alternative, as well as cost impacts and impacts to the Naval Nuclear Propulsion Program mission. This Appendix covers aspects of the alternatives that involve managing naval spent nuclear fuel at four naval shipyards and the Naval Nuclear Propulsion Program Kesselring Site in West Milton, New York. This Appendix also covers the impacts of alternatives that involve examining naval spent nuclear fuel at the Expended Core Facility in Idaho and the potential impacts of constructing and operating an inspection facility at any of the Department of Energy (DOE) facilities considered in the EIS. This Appendix also considers the impacts of the alternative involving limited spent nuclear fuel examinations at Puget Sound Naval Shipyard. This Appendix does not address the impacts associated with storing naval spent nuclear fuel after it has been inspected and transferred to DOE facilities. These impacts are addressed in separate appendices for each DOE site

  12. Iodine-129 in rabbit thyroids near a nuclear fuel reprocessing plant in Idaho

    International Nuclear Information System (INIS)

    Fraley, L. Jr.; Bowman, G.C.; Markham, O.D.

    1982-01-01

    The 129 I/ 127 I atom ratios in rabbits collected on the INEL site were larger than ratios in rabbits from a control area. Maximum 129 I/ 127 I atom ratios (9.1 x 10 -4 ) occurred near the Idaho Chemical Processing Plant (ICPP). Based on rabbit thyroid concentrations, the 129 I appeared to be deposited primarily in the direction of the predominant winds from the ICPP, northeast and southwest. Dose rates from the 129 I to thyroids of INEL rabbits varied from 0.1 to 260 μGy/y (0.01 to 26 mrad/y). Iodine-129 atmospheric releases from the ICPP appeared to have increased the 129 I/ 127 I atom ratios on and near the INEL site. (author)

  13. Training in nuclear engineering companies; La formacion en las empresas de ingenieria del ambito nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Perezagua, R. L.

    2013-03-01

    The importance of training is growing in all business areas and fields and especially in hi-tech companies like engineering firms. Nuclear projects are highly multidisciplinary and, even in the initial awarding and pre-construction phases, need to be staffed with personnel that is well-prepared and highly-qualified in areas that, in most cases, are not covered by university studies. This article examines the variables that influence the design of specific training for nuclear projects in engineering firms, along with new training technologies (e-learning) and new regulatory aspects (IS-12). (Author)

  14. 75 FR 52045 - Arizona Public Service Company, Palo Verde Nuclear Generating Station, Unit 3; Environmental...

    Science.gov (United States)

    2010-08-24

    ... Company, Palo Verde Nuclear Generating Station, Unit 3; Environmental Assessment and Finding of No.... NPF-74, issued to Arizona Public Service Company (APS, the licensee), for operation of Palo Verde... Statement for the Palo Verde Nuclear Generating Station, NUREG-0841, dated February 1982. Agencies and...

  15. VALIDATION OF NUCLEAR MATERIAL CONTROL AND ACCOUNTABILITY (MC and A) SYSTEM EFFECTIVENESS TOOL (MSET) AT IDAHO NATIONAL LABORATORY (INL)

    International Nuclear Information System (INIS)

    Meppen, Bruce; Haga, Roger; Moedl, Kelley; Bean, Tom; Sanders, Jeff; Thom, Mary Alice

    2008-01-01

    A Nuclear Material Control and Accountability (MC and A) Functional Model has been developed to describe MC and A systems at facilities possessing Category I or II Special Nuclear Material (SNM). Emphasis is on achieving the objectives of 144 'Fundamental Elements' in key areas ranging from categorization of nuclear material to establishment of Material Balance Areas (MBAs), controlling access, performing quality measurements of inventories and transfers, timely reporting all activities, and detecting and investigating anomalies. An MC and A System Effectiveness Tool (MSET), including probabilistic risk assessment (PRA) technology for evaluating MC and A effectiveness and relative risk, has been developed to accompany the Functional Model. The functional model and MSET were introduced at the 48th annual International Nuclear Material Management (INMM) annual meeting in July, 20071,2. A survey/questionnaire is used to accumulate comprehensive data regarding the MC and A elements at a facility. Data is converted from the questionnaire to numerical values using the DELPHI method and exercises are conducted to evaluate the overall effectiveness of an MC and A system. In 2007 a peer review was conducted and a questionnaire was completed for a hypothetical facility and exercises were conducted. In the first quarter of 2008, a questionnaire was completed at Idaho National Laboratory (INL) and MSET exercises were conducted. The experience gained from conducting the MSET exercises at INL helped evaluate the completeness and consistency of the MC and A Functional Model, descriptions of fundamental elements of the MC and A Functional Model, relationship between the MC and A Functional Model and the MC and A PRA tool and usefulness of the MSET questionnaire data collection process

  16. Environmental radiation monitoring around Korea nuclear fuel company

    International Nuclear Information System (INIS)

    Choi, Yong Ho; Lee, C. W.; Choi, G. S.

    2004-12-01

    The environmental monitoring program for Korea Nuclear Fuel Company (KNFC) was implemented to investigate environmental radiation and radioactivity levels around the facilities. Accumulated environmental radiation doses were measured to be on almost the same level as those measured in the previous years. Total alpha and beta concentrations in air particulates were also similar to the past measurements. The concentrations of uranium isotopes in soil and underground water were investigated to be similar to natural levels. The concentrations of uranium isotopes in sediment around the facilities were not significantly different from those for the reference site. Surface water around the facilities showed somewhat higher uranium isotope concentrations than the reference samples but the activity levels were not much different from those reported before. The concentrations of uranium isotopes in rain water and foodstuffs such as rice seeds and Chinese cabbage were, on the whole, in the ranges of the previously reported levels. Based on the present results of the environmental monitoring, it can be estimated that the environmental impact resulting from the operation of KNFC in 2004 is negligible

  17. Secondary Waste Considerations for Vitrification of Sodium-Bearing Waste at the Idaho Nuclear Technology and Engineering Center FY-2001 Status Report

    International Nuclear Information System (INIS)

    Herbst, A.K.; Kirkham, R.J.; Losinski, S.J.

    2002-01-01

    The Idaho Nuclear Technology and Engineering Center (INTEC) is considering vitrification to process liquid sodium-bearing waste. Preliminary studies were completed to evaluate the potential secondary wastes from the melter off-gas clean up systems. Projected secondary wastes comprise acidic and caustic scrubber solutions, HEPA filters, activated carbon, and ion exchange media. Possible treatment methods, waste forms, and disposal sites are evaluated from radiological and mercury contamination estimates

  18. Secondary Waste Considerations for Vitrification of Sodium-Bearing Waste at the Idaho Nuclear Technology and Engineering Center FY-2001 Status Report

    Energy Technology Data Exchange (ETDEWEB)

    Herbst, A.K.; Kirkham, R.J.; Losinski, S.J.

    2002-09-26

    The Idaho Nuclear Technology and Engineering Center (INTEC) is considering vitrification to process liquid sodium-bearing waste. Preliminary studies were completed to evaluate the potential secondary wastes from the melter off-gas clean up systems. Projected secondary wastes comprise acidic and caustic scrubber solutions, HEPA filters, activated carbon, and ion exchange media. Possible treatment methods, waste forms, and disposal sites are evaluated from radiological and mercury contamination estimates.

  19. Secondary Waste Considerations for Vitrification of Sodium-Bearing Waste at the Idaho Nuclear Techology and Engineering Center FY-2001 Status Report

    Energy Technology Data Exchange (ETDEWEB)

    Herbst, Alan Keith; Kirkham, Robert John; Losinski, Sylvester John

    2001-09-01

    The Idaho Nuclear Technology and Engineering Center (INTEC) is considering vitrification to process liquid sodium-bearing waste. Preliminary studies were completed to evaluate the potential secondary wastes from the melter off-gas clean up systems. Projected secondary wastes comprise acidic and caustic scrubber solutions, HEPA filters, activated carbon, and ion exchange media. Possible treatment methods, waste forms, and disposal sites are evaluated from radiological and mercury contamination estimates.

  20. 75 FR 36700 - Exelon Generation Company, LLC; Three Mile Island Nuclear Station, Unit 1; Environmental...

    Science.gov (United States)

    2010-06-28

    ...; Three Mile Island Nuclear Station, Unit 1; Environmental Assessment and Finding of No Significant Impact... Company, LLC (the licensee), for operation of Three Mile Island Nuclear Station, Unit 1 (TMI-1), located... Three Mile Island Nuclear Station, Units 1 and 2, NUREG-0552, dated December 1972, and Generic...

  1. 76 FR 1197 - Arizona Public Service Company, Palo Verde Nuclear Generating Station; Notice of Availability of...

    Science.gov (United States)

    2011-01-07

    ... NUCLEAR REGULATORY COMMISSION [Docket Nos. 50-528, 50-529, 50-530; NRC-2009-0012] Arizona Public Service Company, Palo Verde Nuclear Generating Station; Notice of Availability of the Final Supplement 43... of operation for the Palo Verde Nuclear Generating Station (PVNGS). Possible alternatives to the...

  2. 76 FR 56242 - Duke Energy Carolinas, LLC; Southern Nuclear Operating Company; Establishment of Atomic Safety...

    Science.gov (United States)

    2011-09-12

    ... NUCLEAR REGULATORY COMMISSION [Docket Nos. 52-018-COL, 52-019-COL, 52-025-COL, 52-026-COL; ASLBP No. 11-913-01-COL-BD01] Duke Energy Carolinas, LLC; Southern Nuclear Operating Company; Establishment... following captioned cases: Duke Energy Carolinas, LLC, (William States Lee III Nuclear Station, Units 1 and...

  3. 75 FR 80547 - Carolina Power & Light Company, Shearon Harris Nuclear Power Plant, Unit No. 1; Exemption

    Science.gov (United States)

    2010-12-22

    ..., Shearon Harris Nuclear Power Plant, Unit No. 1; Exemption 1.0 Background Carolina Power & Light Company... operation of the Shearon Harris Nuclear Power Plant (HNP), Unit 1. The license provides, among other things... request to generically extend the rule's compliance date for all operating nuclear power plants, but noted...

  4. 78 FR 32278 - Vogtle Electric Generating Station, Units 3 and 4; Southern Nuclear Operating Company; Change to...

    Science.gov (United States)

    2013-05-29

    ... Generating Station, Units 3 and 4; Southern Nuclear Operating Company; Change to Information in Tier 1, Table... Nuclear Operating Company, Inc., and Georgia Power Company, Oglethorpe Power Corporation, Municipal... Table 3.3-1, ``Definition of Wall Thicknesses for Nuclear Island Buildings, Turbine Buildings, and Annex...

  5. Summary of ground water and surface water flow and contaminant transport computer codes used at the Idaho National Engineering Laboratory (INEL)

    International Nuclear Information System (INIS)

    Bandy, P.J.; Hall, L.F.

    1993-03-01

    This report presents information on computer codes for numerical and analytical models that have been used at the Idaho National Engineering Laboratory (INEL) to model ground water and surface water flow and contaminant transport. Organizations conducting modeling at the INEL include: EG ampersand G Idaho, Inc., US Geological Survey, and Westinghouse Idaho Nuclear Company. Information concerning computer codes included in this report are: agency responsible for the modeling effort, name of the computer code, proprietor of the code (copyright holder or original author), validation and verification studies, applications of the model at INEL, the prime user of the model, computer code description, computing environment requirements, and documentation and references for the computer code

  6. Discussion of nuclear science and technology information base on serving our company scientific research

    International Nuclear Information System (INIS)

    Wang Zhong; Liu Wenbin

    2010-01-01

    In the eleventh five-year, our company scientific research have a long way to go and preparatory work of commercial reprocessing has startup under digital information society. Fundamental change of existing content, model of nuclear science and technology information occurred to fit for new situation and new environment, and in order to service for our company scientific research. In this paper, we discuss the development of new services that fits for our company science and technology information. (authors)

  7. Department of Energy Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs, Draft Environmental Impact Statement. Volume 1, Appendix D: Part A, Naval Spent Nuclear Fuel Management

    Energy Technology Data Exchange (ETDEWEB)

    1994-06-01

    Volume 1 to the Department of Energy`s Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Management Programs Environmental Impact Statement evaluates a range of alternatives for managing naval spent nuclear fuel expected to be removed from US Navy nuclear-powered vessels and prototype reactors through the year 2035. The Environmental Impact Statement (EIS) considers a range of alternatives for examining and storing naval spent nuclear fuel, including alternatives that terminate examination and involve storage close to the refueling or defueling site. The EIS covers the potential environmental impacts of each alternative, as well as cost impacts and impacts to the Naval Nuclear Propulsion Program mission. This Appendix covers aspects of the alternatives that involve managing naval spent nuclear fuel at four naval shipyards and the Naval Nuclear Propulsion Program Kesselring Site in West Milton, New York. This Appendix also covers the impacts of alternatives that involve examining naval spent nuclear fuel at the Expended Core Facility in Idaho and the potential impacts of constructing and operating an inspection facility at any of the Department of Energy (DOE) facilities considered in the EIS. This Appendix also considers the impacts of the alternative involving limited spent nuclear fuel examinations at Puget Sound Naval Shipyard. This Appendix does not address the impacts associated with storing naval spent nuclear fuel after it has been inspected and transferred to DOE facilities. These impacts are addressed in separate appendices for each DOE site.

  8. French nuclear industry exportations: companies and organisations, achievements and projects

    International Nuclear Information System (INIS)

    Faudon, V.; Pailler, S.; Miniere, D.; Pouget-Abadie, X.; Journes, F.; Ouali, F.; Brochard, D.; Choho, T.; Lagarde, D.; Anglaret, P.; Kottman, G.; Mockly, D.; Ouzounian, G.; Cordier, P.Y.; Prenez, J.C.; Arpino, J.M.; Jaouen, C.; Jolly, B.

    2013-01-01

    This document gathers a series of short articles in which the following players: French Nuclear Safety Authority (ASN), Electricity of France (EdF), French Alternative Energies and Atomic Energy Commission (CEA), AREVA, ALSTOM, the Association of French Nuclear Industry Exporters (AIFEN), the National Radioactive Waste Management Agency (ANDRA) and the French Society of Nuclear Energy (SFEN) present their competencies in their respective fields and their strategies and commercial offers for exports. 2 articles are dedicated to the achievements of the French nuclear industry in China and another details the cooperation between SFEN and its foreign counterparts. Another article briefly presents the EPR and ATMEA reactors. (A.C.)

  9. 78 FR 70588 - STP Nuclear Operating Company; South Texas Project

    Science.gov (United States)

    2013-11-26

    ... hereby given that the U.S. Nuclear Regulatory Commission (NRC) has published the final, plant-specific..., U.S. Nuclear Regulatory Commission, Washington, DC 20555- 0001; telephone: 301-415-3617; email: Tam... efficiency; (8) wind power; (9) solar power; (10) hydroelectric power; (11) ocean wave and current energy...

  10. Structural Integrity Program for the 300,000-Gallon Radioactive Liquid Waste Storage Tanks at the Idaho Nuclear Technology and Engineering Center

    International Nuclear Information System (INIS)

    Bryant, J.W.; Nenni, J.A.; Yoder, T.S.

    2003-01-01

    This report provides a record of the Structural Integrity Program for the 300,000-gal liquid waste storage tanks and associated equipment at the Idaho Nuclear Technology and Engineering Center, as required by U.S. Department of Energy M 435.1-1, ''Radioactive Waste Management Manual.'' This equipment is known collectively as the Tank Farm Facility. The conclusion of this report is that the Tank Farm Facility tanks, vaults, and transfer systems that remain in service for storage are structurally adequate, and are expected to remain structurally adequate over the remainder of their planned service life through 2012. Recommendations are provided for continued monitoring of the Tank Farm Facility

  11. Owners of nuclear power plants: Percentage ownership of commercial nuclear power plants by utility companies

    International Nuclear Information System (INIS)

    Wood, R.S.

    1987-08-01

    The following list indicates percentage ownership of commercial nuclear power plants by utility companies as of June 1, 1987. The list includes all plants licensed to operate, under construction, docked for NRC safety and environmental reviews, or under NRC antitrust review. It does not include those plants announced but not yet under review or those plants formally canceled. In many cases, ownership may be in the process of changing as a result of altered financial conditions, changed power needs, and other reasons. However, this list reflects only those ownership percentages of which the NRC has been formally notified. Part I lists plants alphabetically with their associated applicants/licensees and percentage ownership. Part II lists applicants/licensees alphabetically with their associated plants and percentage ownership. Part I also indicates which plants have received operating licenses (OL's). Footnotes for both parts appear at the end of this document

  12. Department of Energy Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs draft environmental impact statement

    International Nuclear Information System (INIS)

    1994-06-01

    The US Department of Energy (DOE) has prepared this report to assist its management in making two decisions. The first decision, which is programmatic, is to determine the management program for DOE spent nuclear fuel. The second decision is on the future direction of environmental restoration, waste management, and spent nuclear fuel management activities at the Idaho National Engineering Laboratory. Volume 1 of the EIS, which supports the programmatic decision, considers the effects of spent nuclear fuel management on the quality of the human and natural environment for planning years 1995 through 2035. DOE has derived the information and analysis results in Volume 1 from several site-specific appendixes. Volume 2 of the EIS, which supports the INEL-specific decision, describes environmental impacts for various environmental restoration, waste management, and spent nuclear fuel management alternatives for planning years 1995 through 2005. This Appendix B to Volume 1 considers the impacts on the INEL environment of the implementation of various DOE-wide spent nuclear fuel management alternatives. The Naval Nuclear Propulsion Program, which is a joint Navy/DOE program, is responsible for spent naval nuclear fuel examination at the INEL. For this appendix, naval fuel that has been examined at the Naval Reactors Facility and turned over to DOE for storage is termed naval-type fuel. This appendix evaluates the management of DOE spent nuclear fuel including naval-type fuel

  13. Department of Energy Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs Draft Environmental Impact Statement

    International Nuclear Information System (INIS)

    1994-06-01

    The US Department of Energy (DOE) is engaged in two related decision making processes concerning: (1) the transportation, receipt, processing, and storage of spent nuclear fuel (SNF) at the DOE Idaho National Engineering Laboratory (INEL) which will focus on the next 10 years; and (2) programmatic decisions on future spent nuclear fuel management which will emphasize the next 40 years. DOE is analyzing the environmental consequences of these spent nuclear fuel management actions in this two-volume Environmental Impact Statement (EIS). Volume 1 supports broad programmatic decisions that will have applicability across the DOE complex and describes in detail the purpose and need for this DOE action. Volume 2 is specific to actions at the INEL. This document, which limits its discussion to the Savannah River Site (SRS) spent nuclear fuel management program, supports Volume 1 of the EIS. Following the introduction, Chapter 2 contains background information related to the SRS and the framework of environmental regulations pertinent to spent nuclear fuel management. Chapter 3 identifies spent nuclear fuel management alternatives that DOE could implement at the SRS, and summarizes their potential environmental consequences. Chapter 4 describes the existing environmental resources of the SRS that spent nuclear fuel activities could affect. Chapter 5 analyzes in detail the environmental consequences of each spent nuclear fuel management alternative and describes cumulative impacts. The chapter also contains information on unavoidable adverse impacts, commitment of resources, short-term use of the environment and mitigation measures

  14. NRC [Nuclear Regulatory Commission] staff evaluation of the General Electric Company Nuclear Reactor Study (''Reed Report'')

    International Nuclear Information System (INIS)

    1987-07-01

    In 1975, the General Electric Company (GE) published a Nuclear Reactor Study, also referred to as ''the Reed Report,'' an internal product-improvement study. GE considered the document ''proprietary'' and thus, under the regulations of the Nuclear Regulatory Commission (NRC), exempt from mandatory public disclosure. Nonetheless, members of the NRC staff reviewed the document in 1976 and determined that it did not raise any significant new safety issues. The staff also reached the same conclusion in subsequent reviews. However, in response to recent inquiries about the report, the staff reevaluated the Reed Report from a 1987 perspective. This re-evaluation, documented in this staff report, concluded that: (1) there are no issues raised in the Reed Report that support a need to curtail the operation of any GE boiling water reactor (BWR); (2) there are no new safety issues raised in the Reed Report of which the staff was unaware; and (3) although certain issues addressed by the Reed Report are still being studied by the NRC and the industry, there is no basis for suspending licensing and operation of GE BWR plants while these issues are being resolved

  15. 76 FR 24064 - Arizona Public Service Company, Palo Verde Nuclear Generating Station, Units 1, 2, and 3, Notice...

    Science.gov (United States)

    2011-04-29

    ... Service Company, Palo Verde Nuclear Generating Station, Units 1, 2, and 3, Notice of Issuance of Renewed... Company (licensee), the operator of the Palo Verde Nuclear Generating Station, Units 1, 2, and 3 (PVNGS... Plants: Supplement 43, Regarding Palo Verde Nuclear Generating Station,'' issued January 2011, discusses...

  16. Practical public acceptance activities in Japan Nuclear Fuel Company

    International Nuclear Information System (INIS)

    Ogawa, Junko

    1996-01-01

    JNF PA is characterized by 3 symbolic 'F's if concisely expressed. The first F comes from the Focus F, which stands for JNF's focused or customized attendance to what visitors want. The second F from Friendly F, which symbolizes JNF's simple and easy presentations in an amenable atmosphere without use of specialist language. The last F from First Hand, which means the visitors given the chance to experience themselves in actual touch with uranium. Our nuclear fuel manufacturing facility is one of the limited spots for such an experience. Their encounter with this 'actual reality' is worth a millions of words. Many citizens of Yokosuka have been invited to our facility at every summer holiday season for the past 6 years. 60% of them answered to our survey: 'Yes, I came here with fear in nuclear angry' but 75% admitted 'I now feel easy with it' after they listened to the issues of energy and environment, watched the animated nuclear fuel cycle and toured through our nuclear fuel manufacturing plant. This is an justified encouragement to what we devote in PA. What we should do is two fold. One is to address our PA to younger generations. Another is to support to those PA activities at newly-planned sites for nuclear power generation. For the former case, we now are approaching educational and tutorial personnel to provide pupils with opportunity of touring our facilities. For the latter, we sincerely endeavor to tune up to the visitors from such site areas, with elaboration based on advance information, rather than mere briefings. Like the Japanese tea ceremonial spirit of 'we happen to meet but once for all', why not fulfilling our role from the spot of a nuclear fuel manufacturing facility? (J.P.N.)

  17. Department of Energy Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs Draft Environmental Impact Statement

    International Nuclear Information System (INIS)

    1994-06-01

    The US Department of Energy (DOE) is currently deciding the direction of its environmental restoration and waste management programs at the Idaho National Engineering Laboratory (INEL) for the next 10 years. Pertinent to this decision is establishing policies for the environmentally sensitive and safe transport, storage, and management of spent nuclear fuels. To develop these policies, it is necessary to revisit or examine the available options. As a part of the DOE complex, the Hanford Site not only has a large portion of the nationwide DOE-owned inventory of spent nuclear fuel, but also is a participant in the DOE decision for management and ultimate disposition of spent nuclear fuel. Efforts in this process at Hanford include assessment of several options for stabilizing, transporting, and storing all or portions of DOE-owned spent nuclear fuel at the Hanford Site. Such storage and management of spent nuclear fuel will be in a safe and suitable manner until a final decision is made for ultimate disposition of spent nuclear fuel. Five alternatives involving the Hanford Site are being considered for management of the spent nuclear fuel inventory: (1) the No Action Alternative, (2) the Decentralization Alternative, (3) the 1992/1993 Planning Basis Alternative, (4) the Regionalization Alternative, and (5) the Centralization Alternative. AU alternatives will be carefully designed to avoid environmental degradation and to provide protection to human health and safety at the Hanford Site and surrounding region

  18. Framatome advanced nuclear power-benefits for our clients from the new company

    International Nuclear Information System (INIS)

    Weber, P.

    2001-01-01

    Framatome ANP (Advanced Nuclear Power) merges the complementary strengths of two global nuclear industry leaders Framatome and Siemens - offering clients the best technological solutions for safe, reliable and economical plant performance. With a combined workforce of 13,300 skilled individuals, Framatome ANP is now the nuclear industry's leading supplier. Serving as Original Equipment Manufacturer (OEM) for more than 90 reactors that provide about 30% of the world's total installed nuclear power capacity, our experienced resources remain focused on the local needs of individual clients, wherever in the world they may be. The Company main business used to be turnkey construction of complete Nuclear Power plants, BWR and PWR capabilities, heavy equipment manufacturing, comprehensive I and C capabilities, and also expertise and knowledge of VVER. Framatome ANP will benefit in all of its fields of activity of the experience gained through Framatome and Siemens' collaboration on the next generation reactor, the EPR, as well as on steam generators replacements and or modernization of VVER. Framatome ANP nuclear fuel designs for both PWR and BWR plants provide innovative features and world-leading performance. Framatome ANP is organized according a matrix organization with: - 4 Business Groups (Project and Engineering, Service, Nuclear Fuel, Mechanical Equipment) - 3 Regional Divisions (Framatome Advanced Nuclear Power S.A.S., France; Framatome Advanced Nuclear Power GmbH, Germany; Framatome Advanced Nuclear Power Inc., USA). By 30th January 2001 Siemens Nuclear Power GmbH, founded in 2000 as successor of the Nuclear Division of Siemens Power Generation Group (KWU), was renamed to Framatome Advanced Nuclear Power GmbH forming the German part of the world wide acting company. Over the past 40 years 23 nuclear power plants all around the world - not only pressurized and boiling water reactors, but also two heavy-watermoderated reactors have been designed, constructed and

  19. Westinghouse Hanford Company special nuclear material vault storage study

    International Nuclear Information System (INIS)

    Borisch, R.R.

    1996-01-01

    Category 1 and 2 Special Nuclear Materials (SNM) require storage in vault or vault type rooms as specified in DOE orders 5633.3A and 6430.1A. All category 1 and 2 SNM in dry storage on the Hanford site that is managed by Westinghouse Hanford Co (WHC) is located in the 200 West Area at Plutonium Finishing Plant (PFP) facilities. This document provides current and projected SNM vault inventories in terms of storage space filled and forecasts available space for possible future storage needs

  20. Maintenance of EDF nuclear power plants and servicing companies. Progress report

    International Nuclear Information System (INIS)

    Baize, Jean-Marc; Reveillon, Sylvie

    1997-01-01

    French Electricity Company (EDF - Electricite de France) and the associated servicing companies, engaged in maintenance partnership from 1991, reinforce and expand their policy by undersigning a progress charter, to cope with the safety and nuclear sector competition issues. This charter stipulates the mutual engagements in the following sectors: 1. Transparency in calling for servicing; 2. Development of the intervenors' professionalism; 3. Improvement in forecasting activity tasks; 4. Radioprotection; 5. Safety and working conditions. The 55 reactors of the EDF nuclear stock are stopped annually for around 6 weeks for refueling. On this occasion the essential maintenance works necessary to ensure the optimal safety of the installations are carried out. The maintenance requires the intervention of 30,000 employees, 10,000 EDF agents and 20,000 external intervenors and represents an amount of 14 million working hours. The full maintenance expenses amounts up to 11 billion FF in 1996, 6 billion of which are assigned to external companies

  1. 75 FR 13606 - Arizona Public Service Company, Palo Verde Nuclear Generating Station, Units 1, 2, and 3...

    Science.gov (United States)

    2010-03-22

    ... NUCLEAR REGULATORY COMMISSION [Docket Nos. STN 50-528, STN 50-529, and STN 50-530; NRC-2010-0114] Arizona Public Service Company, Palo Verde Nuclear Generating Station, Units 1, 2, and 3; Environmental...-74, issued to Arizona Public Service Company (APS, the licensee), for operation of the Palo Verde...

  2. 75 FR 8149 - Arizona Public Service Company, et al. Palo Verde Nuclear Generating Station, Units 1, 2, and 3...

    Science.gov (United States)

    2010-02-23

    ...] Arizona Public Service Company, et al. Palo Verde Nuclear Generating Station, Units 1, 2, and 3... NPF-74, issued to the Arizona Public Service Company (APS, or the licensee), for operation of the Palo Verde Nuclear Generating Station (PVNGS, the facility), Units 1, 2, and 3, respectively, located in...

  3. 75 FR 53985 - Arizona Public Service Company, et al., Palo Verde Nuclear Generating Station, Unit 3; Temporary...

    Science.gov (United States)

    2010-09-02

    ... NUCLEAR REGULATORY COMMISSION [Docket No. STN 50-530; NRC-2010-0281] Arizona Public Service Company, et al., Palo Verde Nuclear Generating Station, Unit 3; Temporary Exemption 1.0 Background Arizona Public Service Company (APS, the licensee) is the holder of Facility Operating License No. NPF-74, which...

  4. Idaho Nuclear Technology and Engineering Center Sodium-Bearing Waste Treatment Research and Development FY-2002 Status Report

    Energy Technology Data Exchange (ETDEWEB)

    Herbst, Alan Keith; Deldebbio, John Anthony; Mc Cray, John Alan; Kirkham, Robert John; Olson, Lonnie Gene; Scholes, Bradley Adams

    2002-09-01

    The Idaho National Engineering and Environmental Laboratory (INEEL) is considering several optional processes for disposal of liquid sodium-bearing waste. During fiscal year 2002, immobilization-related research included of grout formulation development for sodium-bearing waste, absorption of the waste on silica gel, and off-gas system mercury collection and breakthrough using activated carbon. Experimental results indicate that sodium-bearing waste can be immobilized in grout at 70 weight percent and onto silica gel at 74 weight percent. Furthermore, a loading of 11 weight percent mercury in sulfur-impregnated activated carbon was achieved with 99.8% off-gas mercury removal efficiency.

  5. Initial performance assessment of the disposal of spent nuclear fuel and high-level waste stored at Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Rechard, R.P.

    1993-12-01

    This performance assessment characterized plausible treatment options conceived by the Idaho National Engineering Laboratory (INEL) for its spent fuel and high-level radioactive waste and then modeled the performance of the resulting waste forms in two hypothetical, deep, geologic repositories: one in bedded salt and the other in granite. The results of the performance assessment are intended to help guide INEL in its study of how to prepare wastes and spent fuel for eventual permanent disposal. This assessment was part of the Waste Management Technology Development Program designed to help the US Department of Energy develop and demonstrate the capability to dispose of its nuclear waste. Although numerous caveats must be placed on the results, the general findings were as follows: Though the waste form behavior depended upon the repository type, all current and proposed waste forms provided acceptable behavior in the salt and granite repositories

  6. Initial performance assessment of the disposal of spent nuclear fuel and high-level waste stored at Idaho National Engineering Laboratory. Volume 1, Methodology and results

    Energy Technology Data Exchange (ETDEWEB)

    Rechard, R.P. [ed.

    1993-12-01

    This performance assessment characterized plausible treatment options conceived by the Idaho National Engineering Laboratory (INEL) for its spent fuel and high-level radioactive waste and then modeled the performance of the resulting waste forms in two hypothetical, deep, geologic repositories: one in bedded salt and the other in granite. The results of the performance assessment are intended to help guide INEL in its study of how to prepare wastes and spent fuel for eventual permanent disposal. This assessment was part of the Waste Management Technology Development Program designed to help the US Department of Energy develop and demonstrate the capability to dispose of its nuclear waste. Although numerous caveats must be placed on the results, the general findings were as follows: Though the waste form behavior depended upon the repository type, all current and proposed waste forms provided acceptable behavior in the salt and granite repositories.

  7. Idaho National Laboratory Ten-year Site Plan (2012 through 2021) -- DOE-NE's National Nuclear Capability -- Developing and Maintaining the INL Infrastructure

    Energy Technology Data Exchange (ETDEWEB)

    Cal Ozaki

    2010-06-01

    To meet long-term objectives to transform the Idaho National Laboratory (INL), we are providing an integrated, long-term vision of infrastructure requirements that support research, development and demonstration (RD&D) goals outlined in the DOE strategic plans, including the NE Roadmap and reports such as Facilities for the Future of Nuclear Energy Research: A Twenty-year Outlook. The goal of the INL Ten-year Site Plan (TYSP) is to clearly link RD&D mission goals and INL core capabilities with infrastructure requirements (single and multi-program), establish the 10-year end-state vision for INL complexes, identify and prioritize infrastructure and capability gaps, as well as the most efficient and economic approaches to closing those gaps.

  8. Technical safety appraisal of the Idaho Chemical Processing Plant

    International Nuclear Information System (INIS)

    1992-05-01

    On June 27, 1989, Secretary of Energy, Admiral James D. Watkins, US Navy (Retired), announced a 10-point initiative to strengthen environment, safety, and health (ES ampersand H) programs and waste management operations in the Department of Energy (DOE). One of the initiatives involved conducting independent Tiger Team Assessments (TTA) at DOE operating facilities. A TTA of the Idaho National Engineering Laboratory (INEL) was performed during June and July 1991. Technical Safety Appraisals (TSA) were conducted in conjunction with the TTA as its Safety and Health portion. However, because of operational constraints the the Idaho Chemical Processing Plant (ICPP), operated for the DOE by Westinghouse Idaho Nuclear Company, Inc. (WINCO), was not included in the Safety and Health Subteam assessment at that time. This TSA, conducted April 12 - May 8, 1992, was performed by the DOE Office of Performance Assessment to complete the normal scope of the Safety and Health portion of the Tiger Team Assessment of the Idaho National Engineering Laboratory. The purpose of TSAs is to evaluate and strengthen DOE operations by verifying contractor compliance with DOE Orders, to assure that lessons learned from commercial operations are incorporated into facility operations, and to stimulate and encourage pursuit of excellence; thus, the appraisal addresses more issues than would be addressed in a strictly compliance-oriented appraisal. A total of 139 Performance Objectives have been addressed by this appraisal in 19 subject areas. These 19 areas are: organization and administration, quality verification, operations, maintenance, training and certification, auxiliary systems, emergency preparedness, technical support, packaging and transportation, nuclear criticality safety, safety/security interface, experimental activities, site/facility safety review, radiological protection, worker safety and health compliance, personnel protection, fire protection, medical services and natural

  9. Department of Energy Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs Draft Environmental Impact Statement. Volume 1, Appendix C, Savannah River Site Spent Nuclear Fuel Mangement Program

    Energy Technology Data Exchange (ETDEWEB)

    1994-06-01

    The US Department of Energy (DOE) is engaged in two related decision making processes concerning: (1) the transportation, receipt, processing, and storage of spent nuclear fuel (SNF) at the DOE Idaho National Engineering Laboratory (INEL) which will focus on the next 10 years; and (2) programmatic decisions on future spent nuclear fuel management which will emphasize the next 40 years. DOE is analyzing the environmental consequences of these spent nuclear fuel management actions in this two-volume Environmental Impact Statement (EIS). Volume 1 supports broad programmatic decisions that will have applicability across the DOE complex and describes in detail the purpose and need for this DOE action. Volume 2 is specific to actions at the INEL. This document, which limits its discussion to the Savannah River Site (SRS) spent nuclear fuel management program, supports Volume 1 of the EIS. Following the introduction, Chapter 2 contains background information related to the SRS and the framework of environmental regulations pertinent to spent nuclear fuel management. Chapter 3 identifies spent nuclear fuel management alternatives that DOE could implement at the SRS, and summarizes their potential environmental consequences. Chapter 4 describes the existing environmental resources of the SRS that spent nuclear fuel activities could affect. Chapter 5 analyzes in detail the environmental consequences of each spent nuclear fuel management alternative and describes cumulative impacts. The chapter also contains information on unavoidable adverse impacts, commitment of resources, short-term use of the environment and mitigation measures.

  10. Development of management systems for nuclear power plant of Hokuriku Electric Power Company

    International Nuclear Information System (INIS)

    Nakamura, Tatsuaki; Hasunuma, Junichi; Suzuki, Shintaro

    2009-01-01

    Hokuriku Electric Power Company has been operating the Shika Nuclear Power Station that it constructed in Shika city, Ishikawa prefecture, for over 15 years since bringing Unit 1 of this plant online in July 1993. In addition to electricity generation, maintenance and inspection tasks constitute a big part of operating a large-scale nuclear power plant, and in recent years, problems at power stations in the nuclear power industry have led to several revisions of nationally regulated maintenance and inspection systems. This paper describes the background, objectives, development method, and features of the Maintenance Management System and Maintenance History Management System that make effective use of information technology to promote safer and more efficient maintenance work at large-scale nuclear power plants. (author)

  11. Human resource development for nuclear generation - from the perspective of a utility company

    Science.gov (United States)

    Kahar, Wan Shakirah Wan Abdul; Mostafa, Nor Azlan; Salim, Mohd Faiz

    2017-01-01

    Malaysia is currently in the planning phase of its nuclear power program, with the first unit targeted to be operational in 2030. Training of nuclear power plant (NPP) staffs are usually long and rigorous due to the complexity and safety aspects of nuclear power. As the sole electricity utility in the country, it is therefore essential that Tenaga Nasional Berhad (TNB) prepares early in developing its human resource and nuclear expertise as a potential NPP owner-operator. A utility also has to be prudent in managing its work force efficiently and effectively, while ensuring that adequate preparations are being made to acquire the necessary nuclear knowledge with sufficient training lead time. There are several approaches to training that can be taken by a utility company with no experience in nuclear power. These include conducting feasibility studies and benchmarking exercises, preparing long term human resource development, increasing the exposure on nuclear power technology to both the top management and general staff, and employing the assistance of relevant agencies locally and abroad. This paper discusses the activities done and steps taken by TNB in its human resource development for Malaysia's nuclear power program.

  12. Attitudes of the general public and electric power company employees toward nuclear power generation

    International Nuclear Information System (INIS)

    Komiyama, Hisashi

    1997-01-01

    We conducted an awareness survey targeted at members of the general public residing in urban areas and in areas scheduled for construction of nuclear power plants as well as employees of electric power company in order to determine the awareness and attitude structures of people residing near scheduled construction sites of nuclear power plants with respect to nuclear power generation, and to examine ways of making improvements in terms of promoting nuclear power plant construction sites. Analysis of those results revealed that there are no significant differences in the awareness and attitudes of people residing in urban areas and in areas near scheduled construction sites. On the contrary, a general sense of apprehension regarding the construction of nuclear power plants was observed common to both groups. In addition, significant differences in awareness and attitudes with respect to various factors were determined to exist between members of the general public residing in urban areas and scheduled construction sites and employees of electric power company. (author)

  13. The enhanced variance propagation code for the Idaho Chemical Processing Plant

    International Nuclear Information System (INIS)

    Kern, E.A.; Zack, N.R.; Britschgi, J.J.

    1992-01-01

    The Variance Propagation (VP) Code was developed by the Los Alamos National Laboratory's Safeguard's Systems Group to provide off-line variance propagation and systems analysis for nuclear material processing facilities. The code can also be used as a tool in the design and evaluation of material accounting systems. In this regard , the VP code was enhanced to incorporate a model of the material accountability measurements used in the Idaho Chemical Processing Plant operated by the Westinghouse Idaho Nuclear Company. Inputs to the code were structured to account for the dissolves/headend process, the waste streams, process performed to determine the sensitivity of measurement and sampling errors to the overall material balance error. We determined that the material balance error is very sensitive to changes in the sampling errors. 3 refs

  14. 78 FR 49305 - Luminant Generation Company LLC, Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 2...

    Science.gov (United States)

    2013-08-13

    ... NUCLEAR REGULATORY COMMISSION [Docket Nos. 50-445 and 50-446; NRC-2013-0182] Luminant Generation Company LLC, Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 2; Application for Amendment to Facility... Operating License Nos. NPF-87 and NPF-89 for the Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 2...

  15. 75 FR 75704 - Pacific Gas and Electric Company (Diablo Canyon Nuclear Power Plant, Units 1 And 2); Notice of...

    Science.gov (United States)

    2010-12-06

    ... NUCLEAR REGULATORY COMMISSION [Docket Nos. 50-275-LR; 50-323-LR] Pacific Gas and Electric Company (Diablo Canyon Nuclear Power Plant, Units 1 And 2); Notice of Appointment of Adjudicatory Employee... Seismologist, Office of Nuclear Material Safety and Safeguards, has been appointed as a Commission adjudicatory...

  16. 78 FR 14361 - In the Matter of Luminant Generation Company LLC, Comanche Peak Nuclear Power Plant, Units 1 and...

    Science.gov (United States)

    2013-03-05

    ... NUCLEAR REGULATORY COMMISSION [NRC-2012-0310; Docket Nos. 50-445 and 50-446; License Nos. NPF-87 and NPF-89] In the Matter of Luminant Generation Company LLC, Comanche Peak Nuclear Power Plant, Units... Nuclear Power Plant, Units 1 and 2 (CPNPP), and its Independent Spent Fuel Storage Installation Facility...

  17. In Situ Production of Chlorine-36 in the Eastern Snake River Plain Aquifer, Idaho: Implications for Describing Ground-Water Contamination Near a Nuclear Facility

    International Nuclear Information System (INIS)

    Cecil, L. D.; Knobel, L. L.; Green, J. R.; Frape, S. K.

    2000-01-01

    The purpose of this report is to describe the calculated contribution to ground water of natural, in situ produced 36Cl in the eastern Snake River Plain aquifer and to compare these concentrations in ground water with measured concentrations near a nuclear facility in southeastern Idaho. The scope focused on isotopic and chemical analyses and associated 36Cl in situ production calculations on 25 whole-rock samples from 6 major water-bearing rock types present in the eastern Snake River Plain. The rock types investigated were basalt, rhyolite, limestone, dolomite, shale, and quartzite. Determining the contribution of in situ production to 36Cl inventories in ground water facilitated the identification of the source for this radionuclide in environmental samples. On the basis of calculations reported here, in situ production of 36Cl was determined to be insignificant compared to concentrations measured in ground water near buried and injected nuclear waste at the INEEL. Maximum estimated 36Cl concentrations in ground water from in situ production are on the same order of magnitude as natural concentrations in meteoric water

  18. Preliminary Hanford technical input for the Department of Energy programmatic spent nuclear fuel management and Idaho National Engineering Laboratory environmental restoration and waste management programs environmental impact statement

    International Nuclear Information System (INIS)

    Bergsman, K.H.

    1995-03-01

    The US Department of Energy (DOE) is currently evaluating its programmatic options for the safe management of its diverse spent nuclear fuel (SNF) inventory in the Department of Energy Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs Environmental Impact Statement (SNF and INEL EIS). In the SNF and INEL EIS, the DOE is assessing five alternatives for SNF management, which consider at which of the DOE sites each of the various SNF types should be managed until ultimate disposition. The range of SNF inventories considered for management at the Hanford Site in the SNF and INEL EIS include the current Hanford Site inventory, only the current Hanford Site defense production SNF inventory, the DOE complex-wide SNF inventory, or none at all. Site-specific SNF management decisions will be evaluated in separate National Environmental Policy Act evaluations. Appendixes A and B include information on (1) additional facilities required to accommodate inventories of SNF within each management alternative, (2) existing and new SNF management facility descriptions, (3) facility costs for construction and operation, (4) facility workforce requirements for construction and operation, and (5) facility discharges. The information was extrapolated from existing analyses to the extent possible. New facility costs, manpower requirements, and similar information are based on rough-order-of-magnitude estimates

  19. Department of Energy Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs Draft Environmental Impact Statement

    International Nuclear Information System (INIS)

    1994-06-01

    Two types of projects in the spent nuclear fuel and environmental restoration and waste management activities at the Idaho National Engineering Laboratory (INEL) are described. These are: foreseeable proposed projects where some funding for preliminary planning and/or conceptual design may already be authorized, but detailed design or planning will not begin until the Department of Energy (DOE) has determined that the requirements of the National Environmental Policy Act process for the project have been completed; planned or ongoing projects not yet completed but whose National Environmental Policy Act documentation is already completed or is expected to be completed before the Record of Decision for this Envirorunental Impact Statement (EIS) is issued. The section on project summaries describe the projects (both foreseeable proposed and ongoing).They provide specific information necessary to analyze the environmental impacts of these projects. Chapter 3 describes which alternative(s) each project supports. Summaries are included for (a) spent nuclear fuel projects, (b) environmental remediation projects, (c) the decontamination and decommissioning of surplus INEL facilities, (d) the construction, upgrade, or replacement of existing waste management facilities, (e) infrastructure projects supporting waste management activities, and (f) research and development projects supporting waste management activities

  20. Department of Energy Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs Draft Environmental Impact Statement. Volume 2, Part B

    Energy Technology Data Exchange (ETDEWEB)

    1994-06-01

    Two types of projects in the spent nuclear fuel and environmental restoration and waste management activities at the Idaho National Engineering Laboratory (INEL) are described. These are: foreseeable proposed projects where some funding for preliminary planning and/or conceptual design may already be authorized, but detailed design or planning will not begin until the Department of Energy (DOE) has determined that the requirements of the National Environmental Policy Act process for the project have been completed; planned or ongoing projects not yet completed but whose National Environmental Policy Act documentation is already completed or is expected to be completed before the Record of Decision for this Envirorunental Impact Statement (EIS) is issued. The section on project summaries describe the projects (both foreseeable proposed and ongoing).They provide specific information necessary to analyze the environmental impacts of these projects. Chapter 3 describes which alternative(s) each project supports. Summaries are included for (a) spent nuclear fuel projects, (b) environmental remediation projects, (c) the decontamination and decommissioning of surplus INEL facilities, (d) the construction, upgrade, or replacement of existing waste management facilities, (e) infrastructure projects supporting waste management activities, and (f) research and development projects supporting waste management activities.

  1. Cost-time management for environmental restoration activities at the Department of Energy's Idaho National Engineering Laboratory, Idaho Chemical Processing Plant

    Energy Technology Data Exchange (ETDEWEB)

    Fourr, B.R.; Owen, A.H.; Williamson, D.J. (Westinghouse Idaho Nuclear Co., Inc., Idaho Falls, ID (United States)); Nash, C.L. (USDOE Idaho Field Office, Idaho Falls, ID (United States))

    1992-05-22

    Cost-time management methods have been developed by Westinghouse to examine business applications from a cost-time perspective. The initial application of cost-time management within Westinghouse was targeted at reducing cycle time in the manufacturing sector. As a result of the tremendous success of reduced cycle time in manufacturing, Westinghouse initiated application of the management technique to Environmental Restoration activities at its Government Owned Contractor Operated facilities. The Westinghouse initiative was proposed in support of the Department of Energy's goals for cost effective Environmental Restoration activities. This paper describes the application of the cost-time method to Environmental Restoration work currently being performed at the Idaho National Engineering Laboratory (INEL) for the Department of Energy (DOE) by Westinghouse Idaho Nuclear Company (WINCO).

  2. Cost-time management for environmental restoration activities at the Department of Energy`s Idaho National Engineering Laboratory, Idaho Chemical Processing Plant

    Energy Technology Data Exchange (ETDEWEB)

    Fourr, B.R.; Owen, A.H.; Williamson, D.J. [Westinghouse Idaho Nuclear Co., Inc., Idaho Falls, ID (United States); Nash, C.L. [USDOE Idaho Field Office, Idaho Falls, ID (United States)

    1992-05-22

    Cost-time management methods have been developed by Westinghouse to examine business applications from a cost-time perspective. The initial application of cost-time management within Westinghouse was targeted at reducing cycle time in the manufacturing sector. As a result of the tremendous success of reduced cycle time in manufacturing, Westinghouse initiated application of the management technique to Environmental Restoration activities at its Government Owned Contractor Operated facilities. The Westinghouse initiative was proposed in support of the Department of Energy`s goals for cost effective Environmental Restoration activities. This paper describes the application of the cost-time method to Environmental Restoration work currently being performed at the Idaho National Engineering Laboratory (INEL) for the Department of Energy (DOE) by Westinghouse Idaho Nuclear Company (WINCO).

  3. Cost-time management for environmental restoration activities at the Department of Energy's Idaho National Engineering Laboratory, Idaho Chemical Processing Plant

    International Nuclear Information System (INIS)

    Fourr, B.R.; Owen, A.H.; Williamson, D.J.; Nash, C.L.

    1992-01-01

    Cost-time management methods have been developed by Westinghouse to examine business applications from a cost-time perspective. The initial application of cost-time management within Westinghouse was targeted at reducing cycle time in the manufacturing sector. As a result of the tremendous success of reduced cycle time in manufacturing, Westinghouse initiated application of the management technique to Environmental Restoration activities at its Government Owned Contractor Operated facilities. The Westinghouse initiative was proposed in support of the Department of Energy's goals for cost effective Environmental Restoration activities. This paper describes the application of the cost-time method to Environmental Restoration work currently being performed at the Idaho National Engineering Laboratory (INEL) for the Department of Energy (DOE) by Westinghouse Idaho Nuclear Company (WINCO)

  4. 75 FR 15745 - Arizona Public Service Company, et al. Palo Verde Nuclear Generating Station, Units 1, 2, and 3...

    Science.gov (United States)

    2010-03-30

    ...] Arizona Public Service Company, et al. Palo Verde Nuclear Generating Station, Units 1, 2, and 3; Exemption 1.0 Background The Arizona Public Service Company (APS, the licensee) is the holder of Facility... Generating Station (PVNGS), Units 1, 2, and 3, respectively. The licenses provide, among other things, that...

  5. INL Site Portion of the April 1995 Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Mamagement Programmatic Final Environmental Impact Statement

    Energy Technology Data Exchange (ETDEWEB)

    N/A

    2005-06-30

    In April 1995, the Department of Energy (DOE) and the Department of the Navy, as a cooperating agency, issued the Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs Final Environmental Impact Statement (1995 EIS). The 1995 EIS analyzed alternatives for managing The Department's existing and reasonably foreseeable inventories of spent nuclear fuel through the year 2035. It also included a detailed analysis of environmental restoration and waste management activities at the Idaho National Engineering and Environmental Laboratory (INEEL). The analysis supported facility-specific decisions regarding new, continued, or planned environmental restoration and waste management operations. The Record of Decision (ROD) was signed in June 1995 and amended in February 1996. It documented a number of projects or activities that would be implemented as a result of decisions regarding INL Site operations. In addition to the decisions that were made, decisions on a number of projects were deferred or projects have been canceled. DOE National Environmental Policy Act (NEPA) implementing procedures (found in 10 CFR Part 1 021.330(d)) require that a Supplement Analysis of site-wide EISs be done every five years to determine whether the site-wide EIS remains adequate. While the 1995 EIS was not a true site-wide EIS in that several programs were not included, most notably reactor operations, this method was used to evaluate the adequacy of the 1995 EIS. The decision to perform a Supplement Analysis was supported by the multi-program aspect of the 1995 EIS in conjunction with the spirit of the requirement for periodic review. The purpose of the SA is to determine if there have been changes in the basis upon which an EIS was prepared. This provides input for an evaluation of the continued adequacy of the EIS in light of those changes (i.e., whether there are substantial changes in the proposed

  6. Initial performance assessment of the disposal of spent nuclear fuel and high-level waste stored at Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Rechard, R.P.

    1993-12-01

    This performance assessment characterized plausible treatment options conceived by the Idaho National Engineering Laboratory (INEL) for its spent fuel and high-level radioactive waste and then modeled the performance of the resulting waste forms in two hypothetical, deep, geologic repositories: one in bedded salt and the other in granite. The results of the performance assessment are intended to help guide INEL in its study of how to prepare wastes and spent fuel for eventual permanent disposal. This assessment was part of the Waste Management Technology Development Program designed to help the US Department of Energy develop and demonstrate the capability to dispose of its nuclear waste, as mandated by the Nuclear Waste Policy Act of 1982. The waste forms comprised about 700 metric tons of initial heavy metal (or equivalent units) stored at the INEL: graphite spent fuel, experimental low enriched and highly enriched spent fuel, and high-level waste generated during reprocessing of some spent fuel. Five different waste treatment options were studied; in the analysis, the options and resulting waste forms were analyzed separately and in combination as five waste disposal groups. When the waste forms were studied in combination, the repository was assumed to also contain vitrified high-level waste from three DOE sites for a common basis of comparison and to simulate the impact of the INEL waste forms on a moderate-sized repository, The performance of the waste form was assessed within the context of a whole disposal system, using the U.S. Environmental Protection Agency's Environmental Radiation Protection Standards for Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Wastes, 40 CFR 191, promulgated in 1985. Though the waste form behavior depended upon the repository type, all current and proposed waste forms provided acceptable behavior in the salt and granite repositories

  7. Initial performance assessment of the disposal of spent nuclear fuel and high-level waste stored at Idaho National Engineering Laboratory. Volume 2: Appendices

    Energy Technology Data Exchange (ETDEWEB)

    Rechard, R.P. [ed.

    1993-12-01

    This performance assessment characterized plausible treatment options conceived by the Idaho National Engineering Laboratory (INEL) for its spent fuel and high-level radioactive waste and then modeled the performance of the resulting waste forms in two hypothetical, deep, geologic repositories: one in bedded salt and the other in granite. The results of the performance assessment are intended to help guide INEL in its study of how to prepare wastes and spent fuel for eventual permanent disposal. This assessment was part of the Waste Management Technology Development Program designed to help the US Department of Energy develop and demonstrate the capability to dispose of its nuclear waste, as mandated by the Nuclear Waste Policy Act of 1982. The waste forms comprised about 700 metric tons of initial heavy metal (or equivalent units) stored at the INEL: graphite spent fuel, experimental low enriched and highly enriched spent fuel, and high-level waste generated during reprocessing of some spent fuel. Five different waste treatment options were studied; in the analysis, the options and resulting waste forms were analyzed separately and in combination as five waste disposal groups. When the waste forms were studied in combination, the repository was assumed to also contain vitrified high-level waste from three DOE sites for a common basis of comparison and to simulate the impact of the INEL waste forms on a moderate-sized repository, The performance of the waste form was assessed within the context of a whole disposal system, using the U.S. Environmental Protection Agency`s Environmental Radiation Protection Standards for Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Wastes, 40 CFR 191, promulgated in 1985. Though the waste form behavior depended upon the repository type, all current and proposed waste forms provided acceptable behavior in the salt and granite repositories.

  8. Incidence and mortality by cancer among French nuclear workers of contracting companies

    International Nuclear Information System (INIS)

    Guerin, S.; Haddy, N.; Giardini, M.; Paoletti, C.; De Vathaire, F.

    2006-01-01

    Full text of publication follows: Current radiation protection standards of occupationally exposed workers are based on an extrapolation of cancer risks estimates derived from studies of the survivors of atomic bombings in Hiroshima and Nagasaki. In order to confirm these standards, International Agency for Research Cancer coordinated a retrospective cohort study to estimate the risk of cancer death after low-level exposure to gamma-ray, in a worldwide population of 400 000 nuclear industry workers in 15 countries. Methods: The present study is part of the international study and includes about 13,000 French nuclear industry workers of 10 contracting companies and subsidiary companies. This study was restricted to workers who wore a radiation dosimeter or badge. Contracting companies were selected on the basis of at least 100 workers in activity in 1996. A retrospective cohort was constituted. For each worker, we collected data concerning personal identifiers, occupational history, exposure history, vital status and cause of death. In order to guarantee the reliability of dosimetry data, we confronted monthly doses of X and gamma rays obtained from each company with monthly doses obtained from the National Institute of Radio Protection (I.R.S.N.). The cut off date was the 31 December of 2000. An incidence study is running within this cohort. Data relatives to poly-exposures, incident cancers and other pathologies, have being collected through a questionnaire form. Results: A total of 12,690 workers were included in the cohort, 1,457 could not be identified. Among the 11,233 identified workers, 280 deaths were recorded and 36% of them were cancer. Most of the workers were men (96%) and the median age at cut off date was equal to 41 years old. Only 25% of workers were exposed seven years or more. The median cumulative dose was equal to 3.1 mSv and 25% of workers had a cumulative dose superior to 22 mSv. Conclusion: Median cumulative dose was lower than expected as

  9. Reorganization of the nuclear energy industry from the point of view of supply companies

    International Nuclear Information System (INIS)

    Holzer, J.

    1990-01-01

    The actual state of the waste management concept for low and medium level radioactive wastes from nuclear power plants, and the most important social components involved, are outlined and evaluated, the starting point of the developments being the occurrences related to the Transnuklear company, which escalated into a public scandal. A new waste management concept is presented which is marked above all by a clear separation of entrepreneurial responsibility, and by a strict application of clear guidelines. It is imperative to regain confidence in the branch in a joint effort. (UA) [de

  10. Blended learning concept for the support of know-how transfer in a nuclear company

    International Nuclear Information System (INIS)

    Langenberger, Nina

    2010-01-01

    AREVA is the largest growing nuclear company. Development and construction of new power plants, sustainment and maintenance of existing installations require many professionally trained personnel, more than 800 new appointments per year trigger the in-plant training and education. The AREVA NP Training Center is in charge of the education and training of the personnel. The contribution deals with the applied blended learning concept and the know-how transfer within AREVA NP. Web-based training and the virtual class room are part of the concept.

  11. The future of nuclear energy. Safety and nuclear power plants. Contribution of engineering companies

    International Nuclear Information System (INIS)

    Garcia Rodriguez, A.

    1995-01-01

    Risk, its consideration and its acceptance or rejection, are parameters which to a large extent are independent and sometimes difficult to interrelate. Nuclear energy, unlike motoring or civil aviation, has not gained sufficient public acceptance, this despite the fact that the risk to population is by far the least of the three. It is therefore necessary to continue with its improvement is an attempt to create the same confidence in the nuclear industry, as society has placed in civil aviation. Improvement in future nuclear power plants must be a combination of improved safety and a reduction in capital investment. This objective can only be reached through standardization and international cooperation. Engineering has a very important part to play in the standardization process. An increase in engineering input during the design, construction, operation and maintenance phases of future nuclear power plants, and the application of increasingly sophisticated analysis and management tools are anticipated. Nevertheless, the financial impact on the cost of each plant will fall as a result of increased input spread throughout the range of standard plants. Our current Advanced Reactor Power Plant Programme enables the Spanish industry to participate actively in the creation of future standards nuclear power plants. Having a presence in selected engineering activities, which guarantees access to the state of the art in this area, is one of our priorities, since it will facilitate the presence of the rest of the industry in future projects. If the objectives described above are to be reached, the present involvement of the spanish industry in this programme must be maintained in the medium and long term. (Author)

  12. 77 FR 74882 - STP Nuclear Operating Company, South Texas Project; Notice of Availability of Draft Supplement 48...

    Science.gov (United States)

    2012-12-18

    ... Operating Company, South Texas Project; Notice of Availability of Draft Supplement 48 to the Generic Environmental Impact Statement for License Renewal of Nuclear Plants and Public Meetings for the License Renewal of South Texas Project Notice is hereby given that the U.S. Nuclear Regulatory Commission (NRC) has...

  13. Stainless steel pool constructing technology and management of Fangjiashan Nuclear Power Company

    International Nuclear Information System (INIS)

    Wei Lianfeng; Wang Qun

    2013-01-01

    The construction of Fangjiashan nuclear power plant stainless steel cladding has been taken much attention. Based on the careful analysis of stainless steel cladding welding and construction main issues; Many measures have been taken such as welding technology, construction process, the stress control of welding deformation, the cleanliness control of construction process, install precision control, improvements of Non-destructive testing, product protection, etc. And installation methods and techniques have been improved and innovative, the installation quality of stainless steel cladding has been enhanced. At the same time, as owners of the plants, we explored the methods of quality supervision and control, together with the relevant units; and sense of quality management has been unified effectively, made stainless steel cladding quality getting better and better. Fangjiashan nuclear power stainless steel cladding construction quality and management experience has been highly recognized by every company. (authors)

  14. Westinghouse Electric Company experiences in chemistry on-line monitoring in Eastern European nuclear power plants

    International Nuclear Information System (INIS)

    Balavage, J.

    2001-01-01

    Westinghouse Electric Company has provided a number of Chemistry On-Line Monitoring (OLM) Systems to Nuclear Power Plants in Eastern Europe. Eleven systems were provided to the Temelin Nuclear Power Plant in the south of the Czech Republic. Four systems were provided to the Russian NPP at Novovoronezh. In addition, a system design was developed for primary side chemistry monitoring for units 5 and 6 of another eastern European VVER. The status of the Temelin OLM systems is discussed including updates to the Temelin designs, and the other Eastern European installations and designs are also described briefly. Some of the problems encountered and lessons learned from these projects are also discussed. (R.P.)

  15. Deployment of a Full-Scope Commercial Nuclear Power Plant Control Room Simulator at the Idaho National Laboratory

    International Nuclear Information System (INIS)

    Boring, Ronald; Persensky, Julius; Thomas, Kenneth

    2011-01-01

    The INL operates the HSSL to conduct research in the design and evaluation of advanced reactor control rooms, integration of intelligent support systems to assist operators, development and assessment of advanced human performance models, and visualizations to assess advanced operational concepts across various infrastructures. This advanced facility consists of a reconfigurable simulator and a virtual reality capability (known as the Computer-Aided Virtual Environment (CAVE)) (Figure 2). It supports human factors research, including human-in-the-loop performance, HSI, and analog and digital hybrid control displays. It can be applied to the development and evaluation of control systems and displays for complex systems such as existing and advanced NPP control rooms, command and control systems, and advance emergency operations centers. The HSSL incorporates a reconfigurable control room simulator, which is currently housed in the Center for Advanced Energy Studies (CAES), a joint venture of the DOE and the Idaho University System. The simulator is a platform- and plant-neutral environment intended for full-scope and part-task testing of operator performance in various control room configurations. The simulator is not limited to a particular plant or even simulator architecture. It can support engineering simulator platforms from multiple vendors using digital interfaces. Due to its ability to be reconfigured, it is possible to switch the HSI - not just to digital panels but also to different control modalities such as those using greater plant automation or intelligent alarm filtering. The simulator currently includes three operator workstations, each capable of driving up to eight 30-inch monitors. The size and number of monitors varies depending on the particular front-end simulator deployed for a simulator study. These operator workstations would typically be used for the shift supervisor or senior reactor operator, reactor operator, and assistant reactor

  16. Deployment of a Full-Scope Commercial Nuclear Power Plant Control Room Simulator at the Idaho National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Ronald Boring; Julius Persensky; Kenneth Thomas

    2011-09-01

    The INL operates the HSSL to conduct research in the design and evaluation of advanced reactor control rooms, integration of intelligent support systems to assist operators, development and assessment of advanced human performance models, and visualizations to assess advanced operational concepts across various infrastructures. This advanced facility consists of a reconfigurable simulator and a virtual reality capability (known as the Computer-Aided Virtual Environment (CAVE)) (Figure 2). It supports human factors research, including human-in-the-loop performance, HSI, and analog and digital hybrid control displays. It can be applied to the development and evaluation of control systems and displays for complex systems such as existing and advanced NPP control rooms, command and control systems, and advance emergency operations centers. The HSSL incorporates a reconfigurable control room simulator, which is currently housed in the Center for Advanced Energy Studies (CAES), a joint venture of the DOE and the Idaho University System. The simulator is a platform- and plant-neutral environment intended for full-scope and part-task testing of operator performance in various control room configurations. The simulator is not limited to a particular plant or even simulator architecture. It can support engineering simulator platforms from multiple vendors using digital interfaces. Due to its ability to be reconfigured, it is possible to switch the HSI - not just to digital panels but also to different control modalities such as those using greater plant automation or intelligent alarm filtering. The simulator currently includes three operator workstations, each capable of driving up to eight 30-inch monitors. The size and number of monitors varies depending on the particular front-end simulator deployed for a simulator study. These operator workstations would typically be used for the shift supervisor or senior reactor operator, reactor operator, and assistant reactor

  17. Cost structure analysis of commercial nuclear power plants in Japan based on corporate financial statements of electric utility companies

    International Nuclear Information System (INIS)

    Kunitake, Norifumi; Nagano, Koji; Suzuki, Tatsujiro

    1998-01-01

    In this paper, we analyze past and current cost structure of commercial nuclear power plants in Japan based on annual corporate financial statements published by the Japanese electric utility companies, instead of employing the conventional methodology of evaluating the generation cost for a newly constructed model plant. The result of our study on existing commercial nuclear plants reveals the increasing significance of O and M and fuel cycle costs in total generation cost. Thus, it is suggested that electric power companies should take more efforts to reduce these costs in order to maintain the competitiveness of nuclear power in Japan. (author)

  18. Idaho National Engineering Laboratory materials in inventory natural and enriched uranium management and storage costs

    International Nuclear Information System (INIS)

    Nebeker, R.L.

    1995-11-01

    On July 13, 1994, the Office of Environmental Management (EM) was requested to develop a planning process that would result in management policies for dealing with nuclear materials in inventory. In response to this request, EM launched the Materials In Inventory (MIN) Initiative. A Headquarters Working Group was established to develop the broad policy framework for developing MIN management policies. MIN activities cover essentially all nuclear materials within the DOE complex, including such items as spent nuclear fuel, depleted uranium, plutonium, natural and enriched uranium, and other materials. In August 1995, a report discussing the natural and enriched uranium portion of the Initiative for the Idaho National Engineering Laboratory (INEL) was published. That report, 'Idaho National Engineering Laboratory Materials-in-Inventory, Natural and Enriched Uranium'.' identified MIN under the control of Lockheed Idaho Technologies Company at the INEL. Later, additional information related to the costs associated with the storage of MIN materials was requested to supplement this report. This report provides the cost information for storing, disposing, or consolidating the natural and enriched uranium portion of the MIN materials at the INEL. The information consists of eight specific tables which detail present management costs and estimated costs of future activities

  19. The recent activities of nuclear power globalization. Our provision against global warming by global deployment of our own technologies as integrated nuclear power plant supply company'

    International Nuclear Information System (INIS)

    Yamauchi, Kiyoshi; Suzuki, Shigemitsu

    2008-01-01

    Mitsubishi Heavy Industries, Ltd. (MHI) is striving to expand and spread nuclear power plants as an 'Integrated Nuclear Power Plant Supply Company' based on its engineering, manufacturing, and technological support capabilities. The company also has ample experience in the export of major components. MHI is accelerating its global deployment through the market introduction of large-sized strategic reactor US-APWR, the joint development of a mid-sized strategic reactor ATMEA1 with AREVA, and a small strategic reactor PBMR. The company also plans to internationally deploy technologies for the nuclear fuel cycle. We present here the leading-edge trends in the global deployment of these nuclear businesses, all of which help to solve the energy and environmental issues in the world. (author)

  20. External attachment of titanium sheathed thermocouples to zirconium nuclear fuel rods for the LOFT reactor

    International Nuclear Information System (INIS)

    Welty, R.K.

    1980-01-01

    The Exxon Nuclear Company, Inc., acting as a Subcontractor to EG and G Idaho Inc., Idaho National Engineering Laboratory, Idaho Falls, Idaho, has developed a welding process to attach titanium sheathed thermocouples to the outside of the zircaloy clad fuel rods. The fuel rods and thermocouples are used to test simulated loss-of-coolant accident (LOCA) conditions in a pressurized water reactor (LOFT Reactor, Idaho National Laboratory). A laser beam was selected as the optimum welding process because of the extremely high energy input per unit volume that can be achieved allowing local fusion of a small area irrespective of the difference in material thickness to be joined. A commercial pulsed laser and energy control system was installed along with specialized welding fixtures. Laser room facility requirements and tolerances were established. Performance qualifications, and detailed welding procedures were also developed. Product performance tests were conducted to assure that engineering design requirements could be met on a production basis

  1. The role of Quality Oversight in nuclear and hazardous waste management and environmental restoration at Westinghouse Hanford Company

    International Nuclear Information System (INIS)

    Fouad, H.Y.

    1994-05-01

    The historical factors that led to the waste at Hanford are outlined. Westinghouse Hanford Company mission and organization are described. The role of the Quality Oversight organization in nuclear hazardous waste management and environmental restoration at Westinghouse Hanford Company is delineated. Tank Waste Remediation Systems activities and the role of the Quality Oversight organization are described as they apply to typical projects. Quality Oversight's role as the foundation for implementation of systems engineering and operation research principles is pointed out

  2. Department of Energy Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs. Final Environmental Impact Statement: Volume 1, Appendix L, Environmental Justice

    International Nuclear Information System (INIS)

    1995-04-01

    Appendix L provides an assessment of the areas surrounding the 10 sites under consideration for the management of spent nuclear fuels (SNF) under all programmatic alternatives considered in this volume. It is divided into two sections: (a) the five sites considered for the management of DOE naval SNF only (under the No Action and Decentralization alternatives, and (b) the five DOE sites being considered for the management of all types of DOE SNF under all alternatives. The five sites considered for the management of naval SNF only are the Norfolk Naval Shipyard, Portsmouth, Virginia; Portsmouth Naval Shipyard, Kittery, Maine; Pearl Harbor Naval Shipyard, Honolulu, Hawaii; Puget Sound Naval Shipyard, Bremerton, Washington; and Kesselring Site, West Milton, New York. The five DOE sites considered for the management of some portion or all DOE SNF are the Savannah River Site, Aiken, South Carolina; Oak Ridge Reservation, Oak Ridge, Tennessee; Idaho National Engineering Laboratory, Idaho Falls, Idaho; Hanford Site, Richland, Washington; and Nevada Test Site, Mercury, Nevada. This assessment includes potential adverse impacts resulting from both onsite activities and associated transportation of materials. Based on this assessment, it is concluded that none of the alternatives analyzed results in disproportionately high and adverse effects on minority populations or low-income communities surrounding any of the sites under consideration for the management of SNF or associated offsite transportation routes

  3. Quality assurance activities by the companies in the Mitsubishi group for nuclear power plants in Japan

    International Nuclear Information System (INIS)

    Fujiwara, K.; Moriyama, A.; Okabe, K.

    1982-01-01

    The paper summarizes the quality assurance (QA) activities of the Mitsubishi group regarding PWR plant construction. 1. To ensure a uniform approach to QA activities in the group, the Nuclear System Quality Assurance Administration Centre was established at the headquarters of Mitsubishi Heavy Industries. This Centre is engaged in establishing and promoting comprehensive QA plans, in supervising the interface control between the companies concerned, and in auditing each company's QA programme. 2. In parallel with endeavours to complete QA systems, a great effort has been made to instill consciousness of QA in everyone concerned with the work. It is emphasized that quality control (QC) circle activities play an important role in maintaining a high level of quality. An innovative system of design computerization coupled with model engineering is now being developed to improve design reliability and to prevent human error. Reliability improvement and preventive maintenance systems using computers are being introduced with the object of performing systematic corrective actions based on analyses of plant operation. (author)

  4. Special isotope separation project, Idaho National Engineering Laboratory, Idaho Falls, Idaho

    International Nuclear Information System (INIS)

    1988-02-01

    Construction and operation of a Special Isotope Separation (SIS) project using the Atomic Vapor Laser Isotope Separation (AVLIS) process technology at the Idaho National Engineering Laboratory (INEL) near Idaho Falls, Idaho are proposed. The SIS project would process fuel-grade plutonium administered by the Department of Energy (DOE) into weapon-grade plutonium using AVLIS and supporting chemical processes. The SIS project would require construction and operation of a Laser Support Facility to house the laser system and a Plutonium Processing Facility. The SIS project would be integrated with existing support and waste management facilities at the selected site. The SIS project would provide DOE with the capability of segregating the isotopes of DOE-owned plutonium into specific isotopic concentrations. This capability would provide redundancy in production capacity, technological diversity, and flexibility in DOE's production of nuclear materials for national defense. Use of the INEL site would impact 151,350 square meters (37.4 acres) of land, of which more than 70% has been previously disturbed. During construction, plant and animal habitat associated with a sagebrush vegetation community would be lost. During operation of the SIS facilities, unavoidable radiation exposures would include occupational exposures and exposures to the public from normal atmospheric releases of radioactive materials that would be minimal compared to natural background radiation

  5. Mission Need Statement: Idaho Spent Fuel Facility Project

    Energy Technology Data Exchange (ETDEWEB)

    Barbara Beller

    2007-09-01

    Approval is requested based on the information in this Mission Need Statement for The Department of Energy, Idaho Operations Office (DOE-ID) to develop a project in support of the mission established by the Office of Environmental Management to "complete the safe cleanup of the environmental legacy brought about from five decades of nuclear weapons development and government-sponsored nuclear energy research". DOE-ID requests approval to develop the Idaho Spent Fuel Facility Project that is required to implement the Department of Energy's decision for final disposition of spent nuclear fuel in the Geologic Repository at Yucca Mountain. The capability that is required to prepare Spent Nuclear Fuel for transportation and disposal outside the State of Idaho includes characterization, conditioning, packaging, onsite interim storage, and shipping cask loading to complete shipments by January 1,2035. These capabilities do not currently exist in Idaho.

  6. Idaho National Laboratory Mission Accomplishments, Fiscal Year 2015

    Energy Technology Data Exchange (ETDEWEB)

    Allen, Todd Randall [Idaho National Lab. (INL), Idaho Falls, ID (United States); Wright, Virginia Latta [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2015-09-01

    A summary of mission accomplishments for the research organizations at the Idaho National Laboratory for FY 2015. Areas include Nuclear Energy, National and Homeland Security, Science and Technology Addressing Broad DOE Missions; Collaborations; and Stewardship and Operation of Research Facilities.

  7. Study of the dynamic operational characteristics of the Taiwan Power Company system - a nuclear majority system

    International Nuclear Information System (INIS)

    Yu, I.H.

    1982-01-01

    All conclusions drawn in this dissertation are based on the results of about six hundred study cases. The dynamic characteristics of the present Taiwan Power Company system are very different not only from the characteristics of any other power system in the world but also from Taipower's own history characteristics. Based on the engineers' knowledge, this dissertation takes a calculation risk approach to deal with the problems in the energy systems. Chapter I introduces the information related with the stability of the present Taipower system. Taipower operating engineers are facing the problem of committing a large amount of nuclear generation at a low base load level. The general introduction of the stability program developed for this study is described in Chapter II. In Chapter III, the processes of performing the transient stability study are explained to show how this study was performed. Critical tie flows were suggested in Chapter IV, which might help balance the nuclear generation and thermal generation at the base load level and plan the unit maintenance schedule. Several operation modes which may increase the degree of stability or minimize the number unit trippings were discussed in Chapter V. In Chapter VI, how to adjust the load shedding policy to improve the stability are discussed. The remote tripping scheme which is effective in preventing massive system blackout was studied in Chapter VII. Some broader concepts in load management are presented in Chapter VII for Taipower's management decision

  8. An overview of training and technical communication of Chinese representative nuclear power engineering company of EPC mode

    International Nuclear Information System (INIS)

    Qi Ting; Zhang Xiangyu

    2015-01-01

    After the Fukushima severe accident, nuclear power development has been in stagnation in all over the world. The Chinese nuclear industry has a slowdown on new NPP construction. As a result, high level technique on safety and effective communication are required. For nuclear power engineering company with EPC mode, high quality on training and technical communication is the principal investment in order to achieve better service on engineering design, environmental impact assessment, environmental engineering design, and equipment supervision and so on. EPC mode requires wide range knowledge on almost every field related to nuclear on nuclear power engineering. In this paper, the author investigated the case of the only nuclear power engineering EPC company (CNPE) in China and present an overview on its training and technical communication both domestic and abroad. Basically, there are 4 main branches of training. The internal training focuses on specifically task (both management and technique), such as HSE training, QC training and quality and safety training. Long term education in the university is organized by cooperated mechanism. Code and platform training is partly carried out by international organization or company, and the experienced engineers coach makes up the other part. The communication is a large part since the EPC mode needs the information and requirements from the NPP entity, authority, and the other institutes, international organizations (like IAEA, NINE, IRSN, OECD, NRC and CEA etc.) and sometimes the public. The overview of the training and communication of the EPC company prevails the outline of its advantage on domestic communication and disadvantage on international technical communication. The paper can be a tool on the soft strength construction of company under EPC mode to broaden its business like consultation and training. Some advice is given by the author on the consultation and global communication in the future. (author)

  9. Service hall in Number 1 Fukushima Nuclear Power Station, Tokyo Electric Power Company, Inc

    International Nuclear Information System (INIS)

    Tawara, Shigesuke

    1979-01-01

    There are six BWR type nuclear power plants in the Number 1 Fukushima Nuclear Power Station, Tokyo Electric Power Company, Inc. The service hall of the station is located near the entrance of the station. In the center of this service hall, there is the model of a nuclear reactor of full scale. This mock-up shows the core region in the reactor pressure vessel for the number one plant. The diameter and the thickness of the pressure vessel are about 5 m and 16 cm, respectively. The fuel assemblies and control rods are set just like the actual reactor, and the start-up operation of the reactor is shown colorfully and dynamically by pushing a button. When the control rods are pulled out, the boiling of water is demonstrated. The 1/50 scale model of the sixth plant with the power generating capacity of 1100 MWe is set, and this model is linked to the mock-up of reactor written above. The operations of a recirculating loop, a turbine and a condenser are shown by switching on and off lamps. The other exhibitions are shielding concrete wall, ECCS model, and many kinds of panels and models. This service hall is incorporated in the course of study and observation of civics. The good environmental effects to fishes and shells are explained in this service hall. Official buildings and schools are built near the service hall utilizing the tax and grant concerning power generation. This service hall contributes to give much freedom from anxiety to the public by the tour. (Nakai, Y.)

  10. Interim report on the accident at Fukushima Nuclear Power Stations of Tokyo Electric Power Company

    International Nuclear Information System (INIS)

    2011-12-01

    The Investigation Committee on the Accident at the Fukushima Nuclear Power Stations (the Investigation Committee) of Tokyo Electric Power Company (TEPCO) was established by the Cabinet decision on May 24, 2011. Its objectives are: to conduct investigation for finding out the causes of accidents at the Fukushima Dai-ichi Nuclear Power Station (Fukushima Dai-ichi NPS) and Fukushima Dai-ni Nuclear Power Station (Fukushima Dai-ni NPS) of TEPCO as well as the causes of accident damage; and to make policy recommendations for limiting the expansion of damage and preventing reoccurrence of similar accidents. The Investigation Committee has conducted its investigation and evaluation since its first meeting on June 7, 2011. Its activities included: site visits to the Fukushima Dai-ichi and Dai-ni NPSs, as well as to other facilities; hearing of heads of local governments around the Fukushima Dai-ichi NPS; and hearing of people concerned through interviews mainly arranged by the Secretariat. As of December 16, 2011, the number of interviewees reached 456. The investigation and evaluation by the Investigation Committee are still ongoing and the Interim Report does not cover every item that the Committee aims at investigating and evaluating. Fact-finding of even some of those items discussed in the Interim Report are not yet completed. The Investigation Committee continues to conduct its investigation and evaluation and will issue its Final Report in the summer of 2012. This brief executive summary covers mainly considerations and evaluation of the issues in Chapter VII of the Interim Report, with brief reference to Chapters I to VI. The Investigation Committee recommendations are printed in bold. (author)

  11. 75 FR 44292 - Northern States Power Company; Prairie Island Nuclear Generating Plant, Units 1 and 2; Notice of...

    Science.gov (United States)

    2010-07-28

    ... and DPR-60] Northern States Power Company; Prairie Island Nuclear Generating Plant, Units 1 and 2... assessment, and behavioral observation) of the unescorted access authorization program when making the... under consideration to determine whether it met the criteria established in NRC Management Directive (MD...

  12. Nuclear emergency planning and response in industrial areas. Results of a qualitative study in 9 industrial companies

    International Nuclear Information System (INIS)

    Pauwels, N.; Hardeman, F.; Soudan, K.

    1998-11-01

    Substantial economic losses and potential dangerous situations may result when industrial companies unexpectedly have to shut down their activities in an abrupt way. With respect to the industrial companies located in the Antwerp harbour region, the reason for such an unplanned shut-down could be the decision to (preventively) evacuate their workers, or to have them sheltered, in case of an alarm situation at a nearby nuclear power plant of Doel or in any other adjacent industrial factory. Between January and August 1998, the prevention advisors of nine industrial companies have been interviewed to gain insight in the scale and relative importance of several economic costs and practical difficulties that may arise. Moreover, the appropriateness of the existing nuclear emergency response decision structure and intervention philosophy was investigated. The main conclusions drawn from the interviews are reported. Recommendations are made to increase the efficiency of implementing countermeasures in industrial areas

  13. Nuclear emergency planning and response in industrial areas. Results of a qualitative study in 9 industrial companies

    Energy Technology Data Exchange (ETDEWEB)

    Pauwels, N.; Hardeman, F.; Soudan, K

    1998-11-01

    Substantial economic losses and potential dangerous situations may result when industrial companies unexpectedly have to shut down their activities in an abrupt way. With respect to the industrial companies located in the Antwerp harbour region, the reason for such an unplanned shut-down could be the decision to (preventively) evacuate their workers, or to have them sheltered, in case of an alarm situation at a nearby nuclear power plant of Doel or in any other adjacent industrial factory. Between January and August 1998, the prevention advisors of nine industrial companies have been interviewed to gain insight in the scale and relative importance of several economic costs and practical difficulties that may arise. Moreover, the appropriateness of the existing nuclear emergency response decision structure and intervention philosophy was investigated. The main conclusions drawn from the interviews are reported. Recommendations are made to increase the efficiency of implementing countermeasures in industrial areas.

  14. Internal attachment of laser beam welded stainless steel sheathed thermocouples into stainless steel upper end caps in nuclear fuel rods for the LOFT Reactor

    International Nuclear Information System (INIS)

    Welty, R.K.; Reid, R.D.

    1980-01-01

    The Exxon Nuclear Company, Inc., acting as a subcontractor to EG and G Idaho Inc., Idaho National Engineering Laboratory, Idaho Falls, Idaho, conducted a laser beam welding study to attach internal stainless steel thermocouples into stainless steel upper end caps in nuclear fuel rods. The objective of this study was to determine the feasibility of laser welding a single 0.063 inch diameter stainless steel (304) sheathed thermocouple into a stainless steel (316) upper end cap for nuclear fuel rods. A laser beam was selected because of the extremely high energy input in unit volume that can be achieved allowing local fusion of a small area irrespective of the difference in material thickness to be joined. A special weld fixture was designed and fabricated to hold the end cap and the thermocouple with angular and rotational adjustment under the laser beam. A commercial pulsed laser and energy control system was used to make the welds

  15. Data logger system of Tokai (I) Nuclear Power Station, the Japan Atomic Power Company

    International Nuclear Information System (INIS)

    Machida, Akira; Chikahata, Kiyomitsu; Nakamura, Mamoru; Nanbu, Taketoshi; Kawakami, Hiroshi

    1977-01-01

    The Tokai(I) nuclear power station, the Japan Atomic Power Company, was commissioned in July, 1966. In this station, temperatures of about 700 points are monitored and recorded with a data logger. However, the logger was manufactured some 15 years ago, therefore it is now old-fashioned, and has caused frequent failures these 2 or 3 years. So it was decided to replace it with a new one, and the process control computer, U-300 system including CRT display, has been adopted considering the latest trend in U.K. The control and monitoring system in this station is not a centralized control system, but a distributed control system divided into three control rooms, namely main control room, turbine generator control room and fuel exchanger (cask machine) control room. Therefore for grasping the complete plant conditions at the main control room, the system has not been convenient, and the centralization of data processing has been desired from the viewpoint of operation. The new logger system is composed so as to facilitate the centralized monitoring in the main control room, considering the above requirement. It has been improved so as to have seven important functions in addition to the existing functions. Hardware and software of this system are briefly explained. The new system was started up in February 1977, and is now operating well, though some early failures were experienced. (Wakatsuki, Y.)

  16. Los Alamos MAWST software layered on Westinghouse Savannah River Company's nuclear materials accountability system

    International Nuclear Information System (INIS)

    Whitty, W.J.; Smith, J.E.; Davis, J.M. Jr.

    1995-01-01

    The Los Alamos Safeguards Systems Group's Materials Accounting With Sequential Testing (MAWST) computer program was developed to fulfill DOE Order 5633.3B requiring that inventory-difference control limits be based on variance propagation or any other statistically valid technique. Westinghouse Savannah River Company (WSRC) developed a generic computerized accountability system, NucMAS, to satisfy accounting and reporting requirements for material balance areas. NucMAS maintains the calculation methods and the measurement information required to compute nuclear material transactions in elemental and isotopic masses by material type code. The Safeguards Systems Group designed and implemented to WSRC's specifications a software interface application, called NucMASloe. It is a layered product for NucMAS that automatically formats a NucMAS data set to a format compatible with MAWST and runs MAWST. This paper traces the development of NucMASloe from the Software Requirements through the testing and demonstration stages. The general design constraints are described as well as the difficulties encountered on interfacing an external software product (MAWST) with an existing classical accounting structure (NucMAS). The lessons learned from this effort, the design, and some of the software are directly applicable to the Local Area Network Material Accountability System (LANMAS) being sponsored by DOE

  17. Idaho Power's reverses decline with employee increase

    International Nuclear Information System (INIS)

    Anon.

    1990-01-01

    Following several years of decline, the number of full-time Idaho Power employees increased to 1,528 at the end of 1989, up from 1,500 in 1988. The increase reversed a steady decline that began in 1984 when the company had a peak employment of 1,725. Last year's increase in the work force in part reflects recent additions in customers served and the electric demands of an expanding economy in the service area, as well as new regulatory requirements, the company said

  18. Idaho Chemical Processing Plant Site Development Plan

    International Nuclear Information System (INIS)

    Ferguson, F.G.

    1994-02-01

    The Idaho Chemical Processing Plant (ICPP) mission is to receive and store spent nuclear fuels and radioactive wastes for disposition for Department of Energy (DOE) in a cost-effective manner that protects the safety of Idaho National Engineering Laboratory (INEL) employees, the public, and the environment by: Developing advanced technologies to process spent nuclear fuel for permanent offsite disposition and to achieve waste minimization. Receiving and storing Navy and other DOE assigned spent nuclear fuels. Managing all wastes in compliance with applicable laws and regulations. Identifying and conducting site remediation consistent with facility transition activities. Seeking out and implementing private sector technology transfer and cooperative development agreements. Prior to April 1992, the ICPP mission included fuel reprocessing. With the recent phaseout of fuel reprocessing, some parts of the ICPP mission have changed. Others have remained the same or increased in scope

  19. Safety Management in Non-Nuclear Contexts. Examples from Swedish Railway Regulatory and Company Perspectives

    International Nuclear Information System (INIS)

    Salo, Ilkka; Svensson, Ola

    2005-06-01

    change, the regulatory and operational activities, safety objectives, threats to safety, and information management and feedback regarding both internal and external system feedback. The event reporting systems and how the organizations measure of safety was also reported and modeled according to the general framework. A number of tentative themes derived from the railway context that may be considered in a systems approach to safety management in nuclear (and other contexts) were suggested. However, the principles for knowledge-transfer between different areas are still under development, and will be concretized further in future contributions to this research area. Such general areas included, for example, facilitation of safety management in the interaction between authorities and companies, subsidiaries and temporary organizational units' contribution to the safety system, and clarification of criteria for event reporting in order to protect external feedback information to authorities. A number of suggestions for future research were outlined. First, two planned studies that partly constitute a continuation and a conclusion of the safety management project were presented. These studies involve the application of system safety management on the nuclear context, and include one organizational study, and one LER report study. Further, a number of interesting themes for further investigations, derived from the results, were presented

  20. 78 FR 77726 - Exelon Generation Company, LLC Three Mile Island Nuclear Station, Unit 1

    Science.gov (United States)

    2013-12-24

    ... Three Mile Island Nuclear Station, Unit 1 AGENCY: Nuclear Regulatory Commission. ACTION: Exemption... License No. DPR-50, which authorizes operation of the Three Mile Island Nuclear Station, Unit 1 (TMI-1... Facility Operating License No. DPR-50, which authorizes operation of the Three Mile Island Nuclear Station...

  1. Safety Management in Non-Nuclear Contexts. Examples from Swedish Railway Regulatory and Company Perspectives

    Energy Technology Data Exchange (ETDEWEB)

    Salo, Ilkka; Svensson, Ola (Risk Analysis, Social and Decision Research Unit, Dept. of Psychology, Stockholm Univ., Stockholm (Sweden))

    2005-06-15

    processes of organizational change, the regulatory and operational activities, safety objectives, threats to safety, and information management and feedback regarding both internal and external system feedback. The event reporting systems and how the organizations measure of safety was also reported and modeled according to the general framework. A number of tentative themes derived from the railway context that may be considered in a systems approach to safety management in nuclear (and other contexts) were suggested. However, the principles for knowledge-transfer between different areas are still under development, and will be concretized further in future contributions to this research area. Such general areas included, for example, facilitation of safety management in the interaction between authorities and companies, subsidiaries and temporary organizational units contribution to the safety system, and clarification of criteria for event reporting in order to protect external feedback.

  2. Current Reactor Physics Benchmark Activities at the Idaho National Laboratory

    International Nuclear Information System (INIS)

    Bess, John D.; Marshall, Margaret A.; Gorham, Mackenzie L.; Christensen, Joseph; Turnbull, James C.; Clark, Kim

    2011-01-01

    The International Reactor Physics Experiment Evaluation Project (IRPhEP) (1) and the International Criticality Safety Benchmark Evaluation Project (ICSBEP) (2) were established to preserve integral reactor physics and criticality experiment data for present and future research. These valuable assets provide the basis for recording, developing, and validating our integral nuclear data, and experimental and computational methods. These projects are managed through the Idaho National Laboratory (INL) and the Organisation for Economic Co-operation and Development Nuclear Energy Agency (OECD-NEA). Staff and students at the Department of Energy - Idaho (DOE-ID) and INL are engaged in the development of benchmarks to support ongoing research activities. These benchmarks include reactors or assemblies that support Next Generation Nuclear Plant (NGNP) research, space nuclear Fission Surface Power System (FSPS) design validation, and currently operational facilities in Southeastern Idaho.

  3. 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,…

  4. Idaho's Energy Options

    Energy Technology Data Exchange (ETDEWEB)

    Robert M. Neilson

    2006-03-01

    This report, developed by the Idaho National Laboratory, is provided as an introduction to and an update of the status of technologies for the generation and use of energy. Its purpose is to provide information useful for identifying and evaluating Idaho’s energy options, and for developing and implementing Idaho’s energy direction and policies.

  5. Pakistan's rise to nuclear power and the contribution of German companies

    Energy Technology Data Exchange (ETDEWEB)

    Ricke, Klaus-Peter

    2013-09-01

    The amendment of the Foreign Trade and Payments Act (Aussenwirtschaftsgesetz) has prompted the preparation of this paper because of concerns over potential setbacks in advances achieved over the past twenty years in regulating German exports to non-EU countries and shipments to member states of the EU and the watering down of export restrictions to correspond to the low standards in place at the EU level (with the objective of streamlining the Foreign Trade and Payments Act and nullifying special German requirements which place German exporters at a disadvantage compared with their European competitors, according to a spokesperson of the German Federal Ministry of Economics and Technology). This would send the wrong signal on combating proliferation. From the 1970s to 1990s the Federal Republic of Germany played an extremely negative role because it opened the doors wide to the proliferation of weapons of mass destruction through lax legislation and even more slipshod enforcement. Alarmed by several scandals, in recent years the German government has taken the lead regarding this issue and it would be appropriate for it to continue to fulfill this role. The attitude of the German governments in the 1970s to 1990s as well as the attitude of the key government authorities responsible for controlling exports becomes clear through the example of the cases of illegal exports of nuclear technology to Pakistan. Until the early 1990s the legal situation was such that some acts of proliferation could not even be prosecuted because the licensing regime included only goods listed in Part 1 of the Export Control List (Ausfuhrliste Teil I). The relevant authorities - the Bundesamt fuer Wirtschaft (Federal Office of Economics, BAW) and customs authorities - were neither in terms of personnel nor due to the deficiency of their computer equipment - in a position to carry out their legally prescribed duties. The maximum sentence for even the most serious proliferation violations

  6. Pakistan's rise to nuclear power and the contribution of German companies

    International Nuclear Information System (INIS)

    Ricke, Klaus-Peter

    2013-01-01

    The amendment of the Foreign Trade and Payments Act (Aussenwirtschaftsgesetz) has prompted the preparation of this paper because of concerns over potential setbacks in advances achieved over the past twenty years in regulating German exports to non-EU countries and shipments to member states of the EU and the watering down of export restrictions to correspond to the low standards in place at the EU level (with the objective of streamlining the Foreign Trade and Payments Act and nullifying special German requirements which place German exporters at a disadvantage compared with their European competitors, according to a spokesperson of the German Federal Ministry of Economics and Technology). This would send the wrong signal on combating proliferation. From the 1970s to 1990s the Federal Republic of Germany played an extremely negative role because it opened the doors wide to the proliferation of weapons of mass destruction through lax legislation and even more slipshod enforcement. Alarmed by several scandals, in recent years the German government has taken the lead regarding this issue and it would be appropriate for it to continue to fulfill this role. The attitude of the German governments in the 1970s to 1990s as well as the attitude of the key government authorities responsible for controlling exports becomes clear through the example of the cases of illegal exports of nuclear technology to Pakistan. Until the early 1990s the legal situation was such that some acts of proliferation could not even be prosecuted because the licensing regime included only goods listed in Part 1 of the Export Control List (Ausfuhrliste Teil I). The relevant authorities - the Bundesamt fuer Wirtschaft (Federal Office of Economics, BAW) and customs authorities - were neither in terms of personnel nor due to the deficiency of their computer equipment - in a position to carry out their legally prescribed duties. The maximum sentence for even the most serious proliferation violations

  7. Integrated Plant Safety Assessment: Systematic Evaluation Program. Millstone Nuclear Power Station, Unit 1, Northeast Nuclear Energy Company, Docket No. 50-245. Final report

    International Nuclear Information System (INIS)

    1983-02-01

    This report documents the review of the Millstone Nuclear Power Station, Unit 1, operated by Northeast Nuclear Energy Company (located in Waterford, Connecticut). Millstone Nuclear Power Station, Unit 1, is one of ten plants reviewed under Phase II of this program. This report indicates how 137 topics selected for review under Phase I of the program were addressed. Equipment and procedural changes have been identified as a result of the review. It is expected that this report will be one of the bases in considering the issuance of a full-term operating license in place of the existing provisional operating license. This report also addresses the comments and recommendations made by the Advisory Committee on Reactor Safeguards in connection with its review of the Draft Report, issued in November 1982

  8. Westinghouse electric company, LLC regulatory trends in the USA nuclear power industry

    International Nuclear Information System (INIS)

    Molnar, C. M.; Cheung, A. C.; Gresham, J. A.

    2007-01-01

    The United States (US) nuclear industry is in a dynamic, exciting, and challenging time. On one hand, since the mid 90s, the US nuclear utilities have continued to demonstrate improved safety, efficient and reliable operation for the whole nuclear fleet, thus making generation costs for nuclear energy extremely attractive. On the other hand the US utilities are projecting the need to add significant new generation capacities to replace the aging fleet and to sustain the expected economic growth. In addition to the demonstrated improved operation and financial performance, the financial incentives offered in the federal energy bill passed in 2005 enticed many utilities to actively consider the purchase of new nuclear power plants. This paper will highlight the regulatory trends in the USA, the major initiatives and improvements undertaken as well as other operation support issues faced by the US nuclear power industry

  9. Idaho Explosives Detection System

    International Nuclear Information System (INIS)

    Reber, Edward L.; Blackwood, Larry G.; Edwards, Andrew J.; Jewell, J. Keith; Rohde, Kenneth W.; Seabury, Edward H.; Klinger, Jeffery B.

    2005-01-01

    The Idaho Explosives Detection System was developed at the Idaho National Laboratory (INL) to respond to threats imposed by delivery trucks potentially carrying explosives into military bases. A full-scale prototype system has been built and is currently undergoing testing. The system consists of two racks, one on each side of a subject vehicle. Each rack includes a neutron generator and an array of NaI detectors. The two neutron generators are pulsed and synchronized. A laptop computer controls the entire system. The control software is easily operable by minimally trained staff. The system was developed to detect explosives in a medium size truck within a 5-min measurement time. System performance was successfully demonstrated with explosives at the INL in June 2004 and at Andrews Air Force Base in July 2004

  10. Idaho Explosives Detection System

    Energy Technology Data Exchange (ETDEWEB)

    Reber, Edward L. [Idaho National Laboratory, 2525 N. Freemont Ave., Idaho Falls, ID 83415-2114 (United States)]. E-mail: reber@inel.gov; Blackwood, Larry G. [Idaho National Laboratory, 2525 N. Freemont Ave., Idaho Falls, ID 83415-2114 (United States); Edwards, Andrew J. [Idaho National Laboratory, 2525 N. Freemont Ave., Idaho Falls, ID 83415-2114 (United States); Jewell, J. Keith [Idaho National Laboratory, 2525 N. Freemont Ave., Idaho Falls, ID 83415-2114 (United States); Rohde, Kenneth W. [Idaho National Laboratory, 2525 N. Freemont Ave., Idaho Falls, ID 83415-2114 (United States); Seabury, Edward H. [Idaho National Laboratory, 2525 N. Freemont Ave., Idaho Falls, ID 83415-2114 (United States); Klinger, Jeffery B. [Idaho National Laboratory, 2525 N. Freemont Ave., Idaho Falls, ID 83415-2114 (United States)

    2005-12-15

    The Idaho Explosives Detection System was developed at the Idaho National Laboratory (INL) to respond to threats imposed by delivery trucks potentially carrying explosives into military bases. A full-scale prototype system has been built and is currently undergoing testing. The system consists of two racks, one on each side of a subject vehicle. Each rack includes a neutron generator and an array of NaI detectors. The two neutron generators are pulsed and synchronized. A laptop computer controls the entire system. The control software is easily operable by minimally trained staff. The system was developed to detect explosives in a medium size truck within a 5-min measurement time. System performance was successfully demonstrated with explosives at the INL in June 2004 and at Andrews Air Force Base in July 2004.

  11. Idaho Chemical Processing Plant Process Efficiency improvements

    International Nuclear Information System (INIS)

    Griebenow, B.

    1996-03-01

    In response to decreasing funding levels available to support activities at the Idaho Chemical Processing Plant (ICPP) and a desire to be cost competitive, the Department of Energy Idaho Operations Office (DOE-ID) and Lockheed Idaho Technologies Company have increased their emphasis on cost-saving measures. The ICPP Effectiveness Improvement Initiative involves many activities to improve cost effectiveness and competitiveness. This report documents the methodology and results of one of those cost cutting measures, the Process Efficiency Improvement Activity. The Process Efficiency Improvement Activity performed a systematic review of major work processes at the ICPP to increase productivity and to identify nonvalue-added requirements. A two-phase approach was selected for the activity to allow for near-term implementation of relatively easy process modifications in the first phase while obtaining long-term continuous improvement in the second phase and beyond. Phase I of the initiative included a concentrated review of processes that had a high potential for cost savings with the intent of realizing savings in Fiscal Year 1996 (FY-96.) Phase II consists of implementing long-term strategies too complex for Phase I implementation and evaluation of processes not targeted for Phase I review. The Phase II effort is targeted for realizing cost savings in FY-97 and beyond

  12. A preliminary study on financial risk management of the uranium enrichment company, given China's fast development of nuclear power industry

    International Nuclear Information System (INIS)

    Sun Wumei

    2010-01-01

    In market economy, control and prevention of financial risk is a factual and urgent issue of financial management. As an independent legal identity, the enterprise strives to achieve business operations and developments while bearing risks. In an era of fast growth of China's nuclear power industry, uncertainties facing uranium enrichment companies are inevitable. Without being aware of financial risks, the enterprise could be driven to hopeless situation when catastrophe comes. Recognizing financial risk factors, knowing the cause and effect of risk events, building a mechanism to prevent and control financial risks, are the right approaches for building a robust enterprise. (author)

  13. The social and economic impact created by construction of a nuclear power station: the part played by local companies

    International Nuclear Information System (INIS)

    Rongere, H.

    1983-01-01

    The president of the Sedan Chamber of Commerce and Industry and managing director of a public works company indicates how local and regional firms involved in the construction of the Chooz B power plant in the Ardennes organized themselves to cater for the requirements of the EDF. The measures taken by these firms to adapt themselves to the demanding and complex nuclear power market are indicated and further the repercussions of the on site work on employment levels and business activity are indicated [fr

  14. Modification of reactor installation in the Genkai nuclear power plant No. 1 of Kyushu Electric Power Company, Inc

    International Nuclear Information System (INIS)

    1979-01-01

    The Nuclear Safety Commission recognized the adequacy concerning the inquiry which was offered from the Minister of International Trade and Industry on July 25, 1979, following the safety evaluation in the Ministry of International Trade and Industry, and decided to submit a report to the Minister of International Trade and Industry on July 26, 1979, about the modification of reactor installation in the Genkai nuclear power plant No. 1 of the Kyushu Electric Power Company, Inc. This is concerned to the application which was made from the president of the Kyushu Electric Power Company, Inc., to the Minister of International Trade and Industry on July 24, 1979. The content of the modification is to add a control circuit which is actuated by the signal of abnormal low pressure in a reactor to the circuit of actuating the emergency core cooling system of the plant. The influences on the safety protection system by the addition of the circuit transmitting safety injection signal and by the additions of an interlock circuit preventing the misoperation of pressurizer spray and of a block circuit of safety injection signal in case of the abnormal low pressure in a reactor were evaluated. The effects on the function and characteristics of the emergency core cooling system due to the addition of the control circuit were investigated, and it was recognized by the analysis that there is no effect in the pipe ruptures of both small and large scales. (Nakai, Y.)

  15. 77 FR 69506 - Exelon Generation Company, LLC., Oyster Creek Nuclear Generating Station; Exemption

    Science.gov (United States)

    2012-11-19

    ... unit'' to ``The closed head automatic sprinkler system in the condenser bay area was designed... the time of design.'' Dated in Rockville, Maryland, this 9th day of November 2012. For the Nuclear...

  16. 77 FR 64834 - Exelon Generation Company, LLC; Oyster Creek Nuclear Generating Station; Exemption

    Science.gov (United States)

    2012-10-23

    ... oil unit,'' to ``The closed head automatic sprinkler system in the condenser bay area was designed... the time of design.'' Dated in Rockville, Maryland, this 15th day of October 2012. For the Nuclear...

  17. 77 FR 55509 - Indiana Michigan Power Company; Donald C. Cook Nuclear Plant, Unit 2; Exemption

    Science.gov (United States)

    2012-09-10

    ... significant effect on the quality of the human environment and has published an environmental assessment for... Rockville, Maryland, this 23rd day of August, 2012. For the Nuclear Regulatory Commission. Michele Evans...

  18. 77 FR 135 - Exelon Generation Company, LLC, Oyster Creek Nuclear Generating Station; Exemption

    Science.gov (United States)

    2012-01-03

    ... not have a significant effect on the quality of the human environment (76 FR 79227, December 21, 2011.... For The Nuclear Regulatory Commission. Michele G. Evans, Director, Division of Operating Reactor...

  19. Integrated-plant-safety assessment Systematic Evaluation program. Millstone Nuclear Power Station, Unit 1, Northeast Nuclear Energy Company, Docket No. 50-245

    International Nuclear Information System (INIS)

    1982-11-01

    The Systematic Evaluation Program was initiated in February 1977 to review the designs of older operating nuclear reactor plants to reconfirm and document their safety. The review provides: (1) an assessment of how these plants compare with current licensing safety requirements relating to selected issues, (2) a basis for deciding on how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety. This report documents the review of the Millstone Nuclear Power Station, Unit 1, operated by Northeast Nuclear Energy Company (located in Waterford, Connecticut). Millstone Nuclear Power Station, Unit 1, is one of ten plants reviewed under Phase II of this program. This report indicates how 137 topics selected for review under Phase I of the program were addressed. Equipment and procedural changes have been identified as a result of the review. It is expected that this report will be one of the bases in considering the issuance of a full-term operating license in place of the existing provisional operating license

  20. Report from investigation committee on the accident at the Fukushima Nuclear Power Stations of Tokyo Electric Power Company

    International Nuclear Information System (INIS)

    Koshizuka, Seiichi

    2012-01-01

    Government's Investigation Committee on the Accident at Fukushima Nuclear Power Stations of Tokyo Electric Power Company published its final report on July 23, 2012. Results of investigation combined final report and interim report published on December 26, 2011. The author was head of accident accuse investigation team mostly in charge of site response, prior measure and plant behavior. This article reported author related technical investigation results focusing on site response and prior measures against tsunamis of units 1-3 of Fukushima Nuclear Power Stations. Misunderstanding of working state of isolation condenser of unit 1, unsuitability of alternative water injection at manual stop of high-pressure coolant injection (HPCI) system of unit 3 and improper prior measure against tsunami and severe accident were pointed out in interim report. Improper monitoring of suppression chamber of unit 2 and again unsuitable work for HPCI system of unit 3 were reported in final report. Thorough technical investigation was more encouraged to update safety measures of nuclear power stations. (T. Tanaka)

  1. 77 FR 13156 - Carolina Power & Light Company; Shearon Harris Nuclear Power Plant, Unit 1; Exemption

    Science.gov (United States)

    2012-03-05

    ... generation, and cladding oxidation from the metal/water reaction shall be calculated using the Baker-Just... boiling or pressurized light-water nuclear power reactor fueled with uranium oxide pellets within... spring 2012. The AREVA fuel design consists of low enriched uranium oxide fuel within M5 \\TM\\ zirconium...

  2. 75 FR 24993 - Southern Nuclear Operating Company; Notice of Consideration of Issuance of Amendment to Early...

    Science.gov (United States)

    2010-05-06

    ... entry into ADAMS, which provides text and image files of NRC's public documents. If you do not have... searching on Docket ID: NRC-2008-0252. SUPPLEMENTARY INFORMATION: 1. Introduction The U.S. Nuclear... Electric Generating Plant Units 3 and 4 ESP site safety analysis report (SSAR) to allow the use and...

  3. 75 FR 36446 - Southern Nuclear Operating Company et al.; Notice of Availability of Environmental Assessment and...

    Science.gov (United States)

    2010-06-25

    [email protected] . SUPPLEMENTARY INFORMATION: I. Introduction The Nuclear Regulatory Commission (NRC) is... Vogtle Electric Generating Plant ESP site safety analysis report (SSAR) to allow the use of Category 1... provides text and image files of NRC's public documents, may be accessed from this site. The ADAMS...

  4. 76 FR 55422 - Indiana Michigan Power Company; Donald C. Cook Nuclear Plant, Unit 1; Exemption

    Science.gov (United States)

    2011-09-07

    ... CFR 50.46, ``Acceptance criteria for emergency core cooling systems for light-water nuclear power... contain acceptance criteria for the emergency core cooling system (ECCS) for reactors fueled with zircaloy... CFR Part 50 (1) when the exemptions are authorized by law, will not present an undue risk to public...

  5. Design and construction of solidification and dewatering facility at Alabama Power Company's Farley Nuclear Plant

    International Nuclear Information System (INIS)

    Farnsworth, P.

    1988-01-01

    The approximate total cost of the structure and supporting piping systems is estimated to be 4.1 million dollars. Total dose savings per year could be as high as 70 man Rem for resin processing alone. The ability to store refueling equipment, process contaminated oils, load and unload trucks and containers regardless of weather conditions and support repair work on equipment greatly enhances the cost effectiveness of the project. It will take at least one year of operation of the facility to accurately assess the true cost savings to Alabama Power Company. The morale factor for the Waste and Decon Group has escalated measurably due to the dose reduction to our personnel. Plant and company management are well pleased due to the possibility of a spill or release to the environment has been eliminated which was on intangible cost. Facility construction has been completed as of this date and resin transfer anticipated within the next few days. Some of the problems encountered in planning and constructing this solidification and dewatering facility are presented. A safety evaluation for the facility is included in the appendix

  6. Amchitka Island Environmental Analysis at Idaho National Laboratory

    International Nuclear Information System (INIS)

    Gracy Elias; W. F. Bauer; J.G. Eisenmenger; C.C. Jensen; B.K. Schuetz; T. C. Sorensen; B.M. White; A. L. Freeman; M. E. McIlwain

    2005-01-01

    The Idaho National Laboratory (INL) provided support to Consortium for Risk Evaluation with Stakeholder Participation (CRESP) in their activities which is supported by the Department of Energy (DOE) to assess the impact of past nuclear testing at Amchitka Island on the ecosystem of the island and surrounding ocean. INL participated in this project in three phases, Phase 1, Phase 2 and Phase 3

  7. Effort to grapple with improvement of security and reliability of nuclear power plant. Actions of the Japan Atomic Power Company

    International Nuclear Information System (INIS)

    Ishiguma, Kazuo

    2012-01-01

    Following the Great Tohoku Earthquake in 2011, Tokai No.2 reactor was shut down automatically. Three of emergency diesel generators worked automatically at loss-of-offsite-power and began to work the cooling system of reactor. The reactor could be kept stable and safe in cold state by management of power from the gas turbine electric generator and power source car. Actions of Japan Atomic Power Company (JAPC) for cold shutdown and Tsunami were stated. Inspection results after the earthquake and testimony of staff was described. Countermeasure of improvement of safety of nuclear power station is explained by ensuring of power source and water supply, crisis management system, countermeasure of accident, ensuring, and training of workers, and action for better understanding of reliance. (S.Y.)

  8. Idaho National Laboratory Research & Development Impacts

    Energy Technology Data Exchange (ETDEWEB)

    Stricker, Nicole [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2015-01-01

    Technological advances that drive economic growth require both public and private investment. The U.S. Department of Energy’s national laboratories play a crucial role by conducting the type of research, testing and evaluation that is beyond the scope of regulators, academia or industry. Examples of such work from the past year can be found in these pages. Idaho National Laboratory’s engineering and applied science expertise helps deploy new technologies for nuclear energy, national security and new energy resources. Unique infrastructure, nuclear material inventory and vast expertise converge at INL, the nation’s nuclear energy laboratory. Productive partnerships with academia, industry and government agencies deliver high-impact outcomes. This edition of INL’s Impacts magazine highlights national and regional leadership efforts, growing capabilities, notable collaborations, and technology innovations. Please take a few minutes to learn more about the critical resources and transformative research at one of the nation’s premier applied science laboratories.

  9. Project for the adaptation of the Instituto Nacional de Investigaciones Nucleares (ININ) to work as companies incubator, and the business plan as support device in the achievement of successful base technological companies

    International Nuclear Information System (INIS)

    Rubio A, C.R.

    1996-01-01

    The purpose of this project is to study an option to reduce technology dependence by taking advantage of the technology based companies generated by the organisms called 'Companies Incubators'. The first point given, is an introduction about incubation applied to national companies and the experiences had about them. There are also suggested some indicators which can be used to develop the incubator tasks. Once it has been defined the topic about incubation in the country, it is provided information about the items determining the company performance within an incubator. In order to do this, it is shown the way the Instituto Nacional de Investigaciones Nucleares can provide not only its facilities but also qualified personnel working for them. Thus it is given a scheme along with a brief organization description and key personnel for the incubator, stating the functions and responsibilities per each one of the persons who are part of the project direction and leading. The bases for the incubator are stated, as well as the requirements to start-up a company being supported by a company incubator. The key points to have a succesful development for the incubator are: the service it can give as well as the guidelines for companies entrance, which are classified into two sorts of customers, external and internal. It is also included a market research about the main product derived from creating a company incubator, as well as the sub-products, the market area, this is directed to the people who will benefit from it, the supply and demand involved with ININ. The main tool used was Business Plan, which defines its importance within the organization and activities guide, it is also included the Business Plan structure

  10. The roles played by the Canadian General Electric Company's Atomic Power Department in Canada's nuclear power program: work, organization and success in APD, 1955-1995

    International Nuclear Information System (INIS)

    Cantello, G.W.

    2003-01-01

    This thesis explores the roles played by the Canadian General Electric Company's Atomic Power Department (APD) in Canada's distinctive nuclear power program. From the establishment of APD in 1955 until the completion of the KANUPP project in Pakistan in 1972, the company's strategy encompassed the design, manufacture, and commissioning of entire nuclear power projects in Canada and abroad. APD then developed a specialized role in the design and supply of complete nuclear fuel handling systems, nuclear fuel bundles, and service work, that sustained a thriving workplace. Five key factors are identified as the reasons behind the long and successful history of the department: (1) Strong, capable and efficient management from the start, (2) Flexible organizational structure, (3) Extremely competent design group, (4) Excellent manufacturing, test, commissioning and service capabilities, (5) Correctly identifying, at the right time, the best fields in which to specialize. (author)

  11. Nuclear-station post-accident liquid-sampling system: developed by Duke Power Company

    International Nuclear Information System (INIS)

    Burton, D.A.; Birch, M.L.; Orth, W.C.

    1981-01-01

    The accident at Three Mile Island showed that means must be provided to determine the radioactivity levels in high activity liquid and gaseous systems of a nuclear power plant without undue radiation exposure to personnel. The Duke Power Post Accident Liquid Sampling System provides the means for obtaining diluted liquid samples and diluted dissolved gas samples following a reactor accident involving substantial core damage. Their approach yields a straightforward engineering solution at a fraction of the cost of other systems. A description of the system, general design criteria, and color coded flow diagrams are included

  12. MSR redesign and reconstruction at Indiana Michigan Power Company's Donald C. Cook Nuclear Power Plant, Unit 1

    International Nuclear Information System (INIS)

    Yarden, A.L.; Tam, C.W.; Benes, J.D.; Arnold, W.E.

    1993-01-01

    When Indiana Michigan Power Company's (I and M) 1089- MWe, PWR, Donald C. Cook Nuclear Plant, Unit 1, (Cook 1) in Bridgeman, Michigan went into commercial operation in late 1975, its turbine generator included two Moisture Separator Reheater (MSR) vessels. Each of these original MSRs contained, in addition to the moisture separation section, a single stage 2-pass reheater consisting of 5/8 inch O.D., finned CuNi tubes with main heating steam as an energy source. The enormous size of the tube bank, with a vertical orientation of its tubes' U-bends, led the designer to choose two separate headers for the inlet side and outlet side of the tube bank. Over the years, these 2-pass reheaters had deteriorated mechanically such that maintenance costs had increased considerably. Also, the MSR performance in terms of MWe gain, had fallen off as a result of a gradual reduction of both superheat and moisture separation efficiency. In 1990, these MSRs were totally reconstructed with inherently different 4-pass reheaters and upgraded moisture separation systems. The performance and other direct parameters of these newly retrofitted and improved MSRs have exceeded original design specifications, and their operational stability has improved markedly. This MSR reconstruction at Cook 1 is the first of its kind to include a 4-pass reheater in association with a nuclear turbine generator of this design. This paper highlights the problems and solutions associated respectively with the original reheaters in the Cook 1 MSRs and their recent redesign, reconstruction, and performance

  13. The Idaho Spent Fuel Project Update-January, 2003

    International Nuclear Information System (INIS)

    Roberts, R.; Tulberg, D.; Carter, C.

    2003-01-01

    The Department of Energy awarded a privatized contract to Foster Wheeler Environmental Corporation in May 2000 for the design, licensing, construction and operation of a spent nuclear fuel repackaging and storage facility. The Foster Wheeler Environmental Team consists of Foster Wheeler Environmental Corp. (the primary contractor), Alstec, RWE-Nukem, RIO Technical Services, Winston and Strawn, and Utility Engineering. The Idaho Spent Fuel (ISF) facility is an integral part of the DOE-EM approach to accelerating SNF disposition at the Idaho National Engineering and Environmental Laboratory (INEEL). Construction of this facility is also important in helping DOE to meet the provisions of the Idaho Settlement Agreement. The ISF Facility is a substantial facility with heavy shielding walls in the repackaging and storage bays and state-of-the-art features required to meet the provisions of 10 CFR 72 requirements. The facility is designed for a 40-year life

  14. Distributed Wind Energy in Idaho

    Energy Technology Data Exchange (ETDEWEB)

    Gardner, John [Boise State Univ., ID (United States); Johnson, Kathryn [Colorado School of Mines, Golden, CO (United States); Haynes, Todd [Boise State Univ., ID (United States); Seifert, Gary [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2009-01-31

    This project is a research and development program aimed at furthering distributed wind technology. In particular, this project addresses some of the barriers to distributed wind energy utilization in Idaho.

  15. Installation modification of the reactor No.2 of Ikata nuclear power plant of Shikoku Electric Power Company, Inc

    International Nuclear Information System (INIS)

    1980-01-01

    The application was made on August 25, 1979, from the president of the Shikoku Electric Power Company, Inc., to the Minister of International Trade and Industry, relating to the installation modification of the reactor No. 2 in the Ikata nuclear power plant. The inquiry was submitted on September 28, 1979, from the Minister of International Trade and Industry to the Nuclear Safety Commission, after the safety evaluation in the Ministry of International Trade and Industry, and the investigation and deliberation were started on October 1, 1979, in the Nuclear Safety Commission. The content of the modification is to add the circuit actuated by the abnormal low pressure signal of the reactor to the actuating circuit of the emergency core cooling system (ECCS) and to increase the new fuel storage capacity from about 1/3 core to about 2/3 core. The additional signal circuit is composed of the logic circuit of ''2 out of 4'' and is multichannel design. The circuit is independent from the reactor control system and the conventional signal circuit of the concurrence of low pressure in the reactor and low level in the pressurizer. With the addition of the circuit of abnormal low pressure signal of the reactor, the countermeasures for preventing ECCS start by mistake are also added. These modifications give no influence to the functions of the reactor control system and reactor protection system. The function and the performance of ECCS were analyzed and evaluated accompanying these modifications assuming the loss of coolant accident. Concerning the new fuel storage capacity, the type of racks is modified from angle type to can type, and the subcriticality is kept even at the time of water flood. (Nakai, Y.)

  16. Solid cancer mortality associated with chronic external radiation exposure at the French atomic energy commission and nuclear fuel company.

    Science.gov (United States)

    Metz-Flamant, C; Samson, E; Caër-Lorho, S; Acker, A; Laurier, D

    2011-07-01

    Studies of nuclear workers make it possible to directly quantify the risks associated with ionizing radiation exposure at low doses and low dose rates. Studies of the CEA (Commissariat à l'Energie Atomique) and AREVA Nuclear Cycle (AREVA NC) cohort, currently the most informative such group in France, describe the long-term risk to nuclear workers associated with external exposure. Our aim is to assess the risk of mortality from solid cancers among CEA and AREVA NC nuclear workers and its association with external radiation exposure. Standardized mortality ratios (SMRs) were calculated and internal Poisson regressions were conducted, controlling for the main confounding factors [sex, attained age, calendar period, company and socioeconomic status (SES)]. During the period 1968-2004, there were 2,035 solid cancers among the 36,769 CEA-AREVA NC workers. Cumulative external radiation exposure was assessed for the period 1950-2004, and the mean cumulative dose was 12.1 mSv. Mortality rates for all causes and all solid cancers were both significantly lower in this cohort than in the general population. A significant excess of deaths from pleural cancer, not associated with cumulative external dose, was observed, probably due to past asbestos exposure. We observed a significant excess of melanoma, also unassociated with dose. Although cumulative external dose was not associated with mortality from all solid cancers, the central estimated excess relative risk (ERR) per Sv of 0.46 for solid cancer mortality was higher than the 0.26 calculated for male Hiroshima and Nagasaki A-bomb survivors 50 years or older and exposed at the age of 30 years or older. The modification of our results after stratification for SES demonstrates the importance of this characteristic in occupational studies, because it makes it possible to take class-based lifestyle differences into account, at least partly. These results show the great potential of a further joint international study of

  17. A company-wide activity to grow safety culture in a maintenance department of nuclear power plant

    International Nuclear Information System (INIS)

    Fukui, Hirokazu; Sugiman, Toshio

    2008-01-01

    This study aims to conduct a field survey to collect specific instances of 'learning activity' that would help develop a safety culture in a maintenance department of nuclear power plant, with 'activity theory' as a theoretical base, and to derive a conceptual model that portrays these instances as part of comprehensive organizational activities. First, the field survey found instances where an accident that occurred a few years ago provided momentum; a company-wide activity is being implemented in order to fulfill the requests of field workers so that their requests for improvements are positively honored and budgets are allocated to measures designed to accommodate these requests. This paper calls this company-wide activity 'an activity to materialize the requests for improvements in the workplace' and considers it to be a typical instance of learning activity. Second, the field survey found that, in the workplace under discussion, a daily meeting was held in a unique way and a study session was conducted frequently and regularly. Last, we came up with a conceptual model for the entire aspect of organizational activities in which we could position the above instances as well as the results of our past field surveys. This model conceptualizes organizational activities from the two aspects of 'learning activity (primary learning activity)' and 'management activity) and characterizes an activity that would transform the existing organizational activities into ones that could not be even predicted as 'secondary learning activity'. 'An activity to materialize the requests for improvement in the workplace' was taken as falling under the category of secondary learning activity. (author)

  18. Inquiry relating to modification of reactor installation of Hamaoka No. 2 nuclear power plant of Chubu Electric Power Company, Inc

    International Nuclear Information System (INIS)

    1979-01-01

    Application was made to the Minister of International Trade and Industry for the license relating to the modification of reactor installation of the Hamaoka No. 2 nuclear power plant, Chubu Electric Power Company, Inc., on February 8, 1979, from the president of the company. After the safety evaluation in the Ministry of International Trade and Industry was finished, inquiry was conducted to the head of the Atomic Energy Safety Commission (AESC) on May 25, 1979, from the Minister of International Trade and Industry. The investigation and discussion were commenced by the AESC on May 28, 1979. The modification of the reactor installation is the increase of spent fuel storage capacity from about 220% of in-core fuel at present to about 325%. The fundamental philosophy of the safety evaluation includes the following items; 1) the storage capacity of spent fuel is adequate, 2) the design is such that the criticality is prevented under any assumed condition, 3) the sufficient cooling capacity is kept for decay heat removal, 4) and others required for the safety. The contents of the safety examination for each philosophical item written above are presented. The increased spent fuel storage capacity is equivalent to the quantity produced in about eight years. The prevention of criticality in the spent fuel storage is carefully practiced by putting fuel assemblies in the stainless steel racks with large neutron absorption cross section and locating spent fuel assemblies at the proper distances. The effective multiplication factor is less than 0.95 at the most severe arrangement in the fuel pool. The water temperature in the pool is less than 65 deg C at about 325% core storage by operating the spent fuel pool water cooling system. The spent fuel storage racks are designed as the A class aseismatic structure. (Nakai, Y.)

  19. Duke Power Company - McGuire Nuclear Station: steam-generator hideout return and cleanup

    International Nuclear Information System (INIS)

    Anon.

    1986-01-01

    McGuire Nuclear Station steam generator hideout return and cleanup are discussed. Hideout return data are presented for Unit 1 shutdowns that occurred on November 23, 1984, and April 19, 1985, and a Unit 2 shutdown on January 25, 1985. The data are presented as the concentrations of various species as a function of time after power reduction and primary water temperature. The steam generator blowdown as a function of time after power reduction is also presented. The concentrations of sodium, potassium, calcium, magnesium, aluminum, iron, and copper cations, and chloride, fluoride, sulfate, phosphate and nitrite anions were monitored during the each shutdown. Silica was also measured in the two 1985 shutdowns. The return of sulfate, phosphate, calcium and magnesium showed retrograde solubility. Silica concentrations showed an increase as the temperature decreased to about 450 to 500 0 F and then they decreased as the temperature decreased. McGuire has a holf point at 300 at 350 0 F to clean up the steam generator secondary water. The return of sulfates should occur within 4 to 6 hours. The blowdown is maximized to reduce the secondary water impurity concentrations. Cleanup continues until the sulfate concentration is reduced to below 100 ppb. At that point cooldown is continued

  20. Procurement activities required by the nuclear program developed by nuclearelectrica national company- technical issues versus public acquisitions legal issues

    International Nuclear Information System (INIS)

    Vatamanu, Mariana

    2007-01-01

    Public procurement is one of the areas of the single market where the results of the liberalization drive have not yet measured up to expectations. This communication presents some technical issues versus public acquisition legal issues and suggests ways and means of improving contract award procedures. Procurement area includes the acquisition of goods, services and works, thus assumption not only for purchasing equipment, components, spare-parts or materials, but also hiring of the contractors or consultants to carry out services and works. Procurement is related to the function of management of supply, which encompasses aside range of planning function, coding and classification, stockholding policies, store-keeping, stores accounting, etc. but it is also related to the hiring of contractors or consultants for work or services. As an answer to the challenge of the increasing market globalization it has been developed the ISO quality system, within 9000 family of standards. The very intensive competition for all market clients, either locally or globally, encouraged development of a new concept of quality management systems. Due to its specificity of activity and with respect to the rules and legislation requirements imposed either by the internal Romanian Laws and Regulations or/and by international market rules and constrains, the development, construction and operation of a Nuclear Power Plant shall be performed in a controlled condition and based on specific authorizations obtained by the Owner of the NPP from the Romanian Regulatory Authorities. The experience, accumulated by over 10 years of operation of Cernavoda NPP Unit 1 by our company, demonstrates the high importance of the Quality Management System that imposes the quality of the components installed on the plant, the services and the works developed to assure a safety operation of the nuclear unit, with a strongly dependence by the procurement system established for purchasing of goods, services and

  1. Mortality in the cohort of nuclear workers of the French electricity company: 1968-2003 period

    International Nuclear Information System (INIS)

    Rogel, A.; Joly, K.; Metz-Flamant, C.; Laurier, D.; Tirmarche, M.; Hubert, D.; Garcier, Y.

    2008-01-01

    Full text: Background: We conducted a mortality study on a cohort of French nuclear workers employed at Electricite de France (EDF). A first mortality analysis relied on the period 1968-1994. Present results consider an updated mortality analysis including 9 additional years of follow-up and rely on the period 1968-2003. Methods: The cohort includes 22,393 workers, 96% of them are males. Employment data were updated using Personnel EDF file. Vital status was ascertained using the French National Registry of individual identification, and further completed using EDF personnel and pension files. Causes of death were obtained through the National file of causes of death. The observed mortality was compared with national rates by indirect standardisation and expressed by Standardised Mortality Ratios (SMR). All causes, all cancers and external causes SMRs were detailed according to sex, age and calendar year. Variations according to date of entry into cohort, duration of employment and socio-economic status (SES) were studied. Comparison with the earlier follow-up is presented. Results: At the present study end point (31/12/2003), 74% of workers are still in active service. Only 0.3% of workers are lost to follow up. The total number of person-years is nearly 450,000. Causes were ascertained for 96 % of deaths. The total number of deaths is 874: 307 are cancer deaths, including 16 leukaemia. SMRs for all causes of death and all cancers show a significant deficit compared to the French national mortality. Significant variations of all causes and all cancers SMRs according to SES were observed. No significant excess compared to French national mortality was observed for any of the 30 different cancer sites studied. Borderline significant excess were observed however for pancreatic, pleural, kidney and brain cancer. SMR for leukaemia is equal to unity. Conclusion: There is a clear evidence for an effect of selection of healthy individuals into the workforce. Although 9

  2. International Peer Review of Swedish Nuclear Fuel and Waste Management Company's SR-Can interim report

    International Nuclear Information System (INIS)

    Sagar, Budhi; Bailey, Lucy; Bennett, David G.; Egan, Mike; Roehlig, Klaus

    2004-12-01

    SKB has produced an interim safety assessment report as part of its work to develop a licence application for the construction of a spent nuclear fuel encapsulation plant. The purpose of the interim report is to set out and demonstrate SKB's proposed methodology for long-term safety assessment. The aim of producing an interim report is to allow the Swedish regulatory authorities (SKI and SSI) to review and comment on SKB's proposed methodology before it is used in support of a formal licence application. To help inform their review of SKB's proposed methodology, the authorities appointed an international review team (IRT) to carry out a review of SKB's interim safety assessment report. Comments from the IRT are presented in this document and will be considered by the regulatory authorities in developing their own view of SKB's proposed methodology. The IRT's review included examination of SKB's documentation (the 'Interim Main Report of the Safety Assessment SR-Can' and four supporting documents) and hearings with SKB staff and contractors. The hearings provided an opportunity for the IRT to discuss the SR-Can safety assessment with the authors and contributors to SKB's work. As directed by SKI and SSI, the IRT's review focused on methodological aspects and sought to determine whether SKB's proposed safety assessment methodology: (i) is fit for the purpose of supporting a licence application; (ii) has a reasonable prospect of leading to a safety assessment that is sufficiently comprehensive, reproducible, traceable and transparent; (iii) is compatible with the authorities' regulations and guidance. No evaluation of long term safety or site acceptability was attempted by the IRT. At the request of SKI and SSI, the IRT's review considered and made recommendations on the following issues: Description of the initial state of the repository and its components; Description of features, events and processes (FEPs) relevant to repository evolution; Strategy for safety

  3. Calculation of particulate dispersion in a design-basis tornadic storm from the Exxon Nuclear Company, Richland, Washington

    Energy Technology Data Exchange (ETDEWEB)

    Pepper, D.W.

    1978-07-01

    A three-dimensional numerical model is used to calculate ground-level air concentration and deposition (due to precipitation scavenging) after a hypothetical tornado strike at the Exxon Nuclear Company at Richland, Washington. Plutonium particles less than 20 ..mu..m in diameter are assumed to be lifted into the tornadic storm cell by the vortex. The rotational characteristics of the tornadic storm are embedded within the larger mesoscale flow of the storm system. The design-basis translational wind values are based on probabilities associated with existing records of tornado strikes in the vicinity of the plant site. Turbulence exchange coefficients are based on empirical values deduced from experimental data in severe storms and from theoretical assumptions obtained from the literature. The method of moments is used to incorporate subgrid-scale resolution of the concentration within a grid cell volume. This method is a quasi-Lagrangian scheme which minimizes numerical error associated with advection. In all case studies, the effects of updrafts and downdrafts, coupled with scavenging of the particulates by precipitation, account for most of the material being deposited within 20 to 45 km downwind of the plant site. Ground-level isopleths in the x-y plane show that most of the material is deposited behind and slightly to the left of the centerline trajectory of the storm. Approximately 5% of the material is dispersed into the stratosphere and anvil section of the storm.

  4. Calculation of particulate dispersion in a design-basis tornadic storm from the Exxon Nuclear Company, Richland, Washington

    International Nuclear Information System (INIS)

    Pepper, D.W.

    1978-07-01

    A three-dimensional numerical model is used to calculate ground-level air concentration and deposition (due to precipitation scavenging) after a hypothetical tornado strike at the Exxon Nuclear Company at Richland, Washington. Plutonium particles less than 20 μm in diameter are assumed to be lifted into the tornadic storm cell by the vortex. The rotational characteristics of the tornadic storm are embedded within the larger mesoscale flow of the storm system. The design-basis translational wind values are based on probabilities associated with existing records of tornado strikes in the vicinity of the plant site. Turbulence exchange coefficients are based on empirical values deduced from experimental data in severe storms and from theoretical assumptions obtained from the literature. The method of moments is used to incorporate subgrid-scale resolution of the concentration within a grid cell volume. This method is a quasi-Lagrangian scheme which minimizes numerical error associated with advection. In all case studies, the effects of updrafts and downdrafts, coupled with scavenging of the particulates by precipitation, account for most of the material being deposited within 20 to 45 km downwind of the plant site. Ground-level isopleths in the x-y plane show that most of the material is deposited behind and slightly to the left of the centerline trajectory of the storm. Approximately 5% of the material is dispersed into the stratosphere and anvil section of the storm

  5. Characterizing aquifer hydrogeology and anthropogenic chemical influences on groundwater near the Idaho Chemical Processing Plant, Idaho National Engineering Laboratory, Idaho

    International Nuclear Information System (INIS)

    Fromm, J.M.

    1995-01-01

    A conceptual model of the Eastern Snake River Plain aquifer in the vicinity of monitoring well USGS-44, downgradient of the Idaho Chemical Processing Plant (ICPP) on the Idaho National Engineering Laboratory (INEL), was developed by synthesis and comparison of previous work (40 years) and new investigations into local natural hydrogeological conditions and anthropogenic influences. Quantitative tests of the model, and other recommendations are suggested. The ICPP recovered fissionable uranium from spent nuclear fuel rods and disposed of waste fluids by release to the regional aquifer and lithosphere. Environmental impacts were assessed by a monitoring well network. The conceptual model identifies multiple, highly variable, interacting, and transient components, including INEL facilities multiple operations and liquid waste handling, systems; the anisotropic, in homogeneous aquifer; the network of monitoring and production wells, and the intermittent flow of the Big Lost River. Pre anthropogenic natural conditions and early records of anthropogenic activities were sparsely or unreliably documented making reconstruction of natural conditions or early hydrologic impacts impossible or very broad characterizations

  6. Research reactor usage at the Idaho National Engineering Laboratory in support of university research and education

    International Nuclear Information System (INIS)

    Woodall, D.M.; Dolan, T.J.; Stephens, A.G.

    1990-01-01

    The Idaho National Engineering Laboratory is a US Department of Energy laboratory which has a substantial history of research and development in nuclear reactor technologies. There are a number of available nuclear reactor facilities which have been incorporated into the research and training needs of university nuclear engineering programs. This paper addresses the utilization of the Advanced Reactivity Measurement Facility (ARMF) and the Coupled Fast Reactivity Measurement Facility (CFRMF) for thesis and dissertation research in the PhD program in Nuclear Science and Engineering by the University of Idaho and Idaho State University. Other reactors at the INEL are also being used by various members of the academic community for thesis and dissertation research, as well as for research to advance the state of knowledge in innovative nuclear technologies, with the EBR-II facility playing an essential role in liquid metal breeder reactor research. 3 refs

  7. Idaho Transportation Department 2016 Customer Communication Survey

    Science.gov (United States)

    2017-06-23

    In 2016, the Idaho Transportation Department contracted with the University of Idaho's Social Science Research Unit to conduct a survey on the general public's engagement and communication with the department. The goal of conducting this survey was t...

  8. Economic Cost of Crashes in Idaho

    Science.gov (United States)

    2016-06-01

    The Idaho Transportation Departments Office of Highway Safety contracted with Cambridge Systematics (CS) for an assessment of the feasibility of calculating the Idaho-specific economic and comprehensive costs associated with vehicle crashes. Resea...

  9. Idaho Transportation Department 2011 customer satisfaction survey.

    Science.gov (United States)

    2011-10-01

    In the spring and summer of 2011, the Idaho Transportation Department (ITD) commissioned a statewide customer satisfaction survey of Idaho residents to assess their perception of ITDs performance in several key areas of customer service. The areas...

  10. Idaho Transportation Department 2009 customer satisfaction survey.

    Science.gov (United States)

    2010-02-01

    In the summer and fall of 2009, the Idaho Transportation Department (ITD) commissioned a statewide customer satisfaction survey of Idaho residents in order to assess the overall level of satisfaction with several key areas of service provided by the ...

  11. 78 FR 23522 - Idaho Roadless Rule

    Science.gov (United States)

    2013-04-19

    ... occur in T47N, R6E, sections 29, 31, and 32, Boise Meridian and were part of the Lucky Swede Land... List of designated Idaho Roadless Areas. * * * * * Forest Idaho roadless area Number WLR Primitive BCR...

  12. Environmental resource document for the Idaho National Engineering Laboratory. Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    Irving, J.S.

    1993-07-01

    This document contains information related to the environmental characterization of the Idaho National Engineering Laboratory (INEL). The INEL is a major US Department of Energy facility in southeastern Idaho dedicated to nuclear research, waste management, environmental restoration, and other activities related to the development of technology. Environmental information covered in this document includes land, air, water, and ecological resources; socioeconomic characteristics and land use; and cultural, aesthetic, and scenic resources.

  13. Environmental resource document for the Idaho National Engineering Laboratory. Volume 2

    Energy Technology Data Exchange (ETDEWEB)

    Irving, J.S.

    1993-07-01

    This document contains information related to the environmental characterization of the Idaho National Engineering Laboratory (INEL). The INEL is a major US Department of Energy facility in southeastern Idaho dedicated to nuclear research, waste management, environmental restoration, and other activities related to the development of technology. Environmental information covered in this document includes land, air, water, and ecological resources; socioeconomic characteristics and land use; and cultural, aesthetic, and scenic resources.

  14. Department of Energy Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs Draft Environmental Impact Statement

    International Nuclear Information System (INIS)

    1994-06-01

    This volume addresses the interim storage of spent nuclear fuel (SNF) at two US Department of Energy sites, the Nevada Test Site (NTS) and the Oak Ridge Reservation (ORR). These sites are being considered to provide a reasonable range of alternative settings at which future SNF management activities could be conducted. These locations are not currently involved in management of large quantities of SNF; NTS has none, and ORR has only small quantities. But NTS and ORR do offer experience and infrastructure for the handling, processing and storage of radioactive materials, and they do exemplify a broad spectrum of environmental parameters. This broad spectrum of environmental parameters will provide, a perspective on whether and how such location attributes may relate to potential environmental impacts. Consideration of these two sites will permit a programmatic decision to be based upon an assessment of the feasible options without bias, to the current storage sites. This volume is divided into four parts. Part One is the volume introduction. Part Two contains chapters one through five for the NTS, as well as references contained in chapter six. Part Three contains chapters one through five for the ORR, as well as references contained in chapter six. Part Four is summary information including the list of preparers, organizations contacted, acronyms, and abbreviations for both the NTS and the ORR. A Table of Contents, List of Figures, and List of Tables are included in parts Two, Three, and Four. This approach permitted the inclusion of both sites in one volume while maintaining consistent chapter numbering

  15. Low level waste management at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Rodgers, A.D.; Truitt, D.J.; Logan, J.A.; Brown, R.M.

    1986-02-01

    EG and G Idaho, Inc. is the lead contractor for the Department of Energy (DOE) National Low Level Waste Management Program, established in 1979. In this role, the company uses its waste management expertise to provide management and technical direction to support the disposal of low-level waste (LLW) in a manner that protects the environment and the public health and safety while improving efficiency and cost-effectiveness. Program activities are divided into two areas: defense-related and commercial nuclear reactor programs. The defense program was established to develop technology improvements, provide technology transfer, and to ensure a more efficient and uniform system for low level waste disposal. To achieve the program's goals, it is necessary to improve, document, and, where necessary, develop new methods for waste generation reduction, waste treatment, shallow-land burial, greater confinement disposal, and measures to correct existing site deficiencies. The commercial low level waste management program provides support to assist the states in developing an effective national low level waste management system and provides technical assistance for siting of regional commercial LLW disposal sites. The program provides technical and informational support to state officials, low level waste generators, managers, and facility operators to resolve low level waste problems and to improve the systems' overall effectiveness. Procedures are developed and documented and made available to commercial users through this program. Additional work is being conducted to demonstrate the stabilization and closure of low level radioactive waste disposal sites and develop the criteria and procedures for acceptance of such sites by the Department of Energy after closure has been completed. 7 refs., 6 figs., 1 tab

  16. Die Energiewerke Nord GmbH. From operator of a decommissioned Russian nuclear power plant to one of Europe's leading decommissioning companies

    International Nuclear Information System (INIS)

    Philipp, Marlies

    2011-01-01

    EWN GmbH is a state-owned company with these duties: - decommissioning and demolition of the Greifswald and Rheinsberg nuclear power stations; - safe operation of the Zwischenlager Nord interim store; - development of the 'Lubminer Heide' industrial and commercial estate. Other projects for which EWN GmbH uses its know-how: - disposal of 120 decommissioned Russian nuclear submarines in Murmansk; - decommissioning and dismantling of the Juelich, NRW, AVR experimental reactor; - demolition of nuclear plants; running the Central Decontamination Operations Department at Karlsruhe, BW. Since 2008, EWN GmbH has held 25% of the shares of Deutsche Gesellschaft zum Bau- und Betrieb von Endlagern fuer Abfallstoffe mbH (DBE), a firm building and operating nuclear repositories. (orig.)

  17. Residential Energy Efficiency Potential: Idaho

    Energy Technology Data Exchange (ETDEWEB)

    Wilson, Eric J [National Renewable Energy Laboratory (NREL), Golden, CO (United States)

    2017-11-02

    Energy used by Idaho single-family homes that can be saved through cost-effective improvements. Prepared by Eric Wilson and Noel Merket, NREL, and Erin Boyd, U.S. Department of Energy Office of Energy Policy and Systems Analysis.

  18. Safety evaluation report: related to the operation of Perry Nuclear Power Plant, Units 1 and 2, Docket Nos. 50-440 and 50-441, Cleveland Electric Illuminating Company

    International Nuclear Information System (INIS)

    1982-08-01

    Supplement No. 1 to the Safety Evaluation Report on the application filed by the Cleveland Electric Illuminating Company on behalf of itself and as agent for the Duquesne Light Company, the Ohio Edison Company, the Pennsylvania Power Company, and the Toledo Edison Company (the Central Area Power Coordination Group, CAPCO), as applicants and owners, for a license to operate the Perry Nuclear Power Plant, Units 1 and 2 (Docket Nos. 50-440 and 441). The facility is located near Lake Erie in Lake County, Ohio. This supplement has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission and reports the status of certain items that had not been resolved at the time of publication of the Safety Evaluation Report

  19. Integrated Plant Safety Assessment: Systematic Evaluation Program. Yankee Nuclear Power Station, Yankee Atomic Electric Company, Docket No. 50-29. Final report

    International Nuclear Information System (INIS)

    1983-06-01

    The Systematic Evaluation program was initiated in February 1977 by the US Nuclear Regulatory Commission to review the designs of older operating nuclear reactor plants to confirm and document their safety. The review provides: (1) an assessment of how these plants compare with current licensing safety requirements relating to selected issues, (2) a basis for deciding on how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety. This report documents the review of Yankee Nuclear Power Station, operated by Yankee Atomic Electric Company. The Yankee plant is one of 10 plants reviewed under Phase II of this program. This report indicates how 137 topics selected for review under Phase I of the program were addressed. Equipment and procedural changes have been identified as a result of the review

  20. Integrated Plant Safety Assessment, Systematic Evaluation Program. Yankee Nuclear Power Station, Yankee Atomic Electric Company, Docket No. 50-29. Draft report

    International Nuclear Information System (INIS)

    1983-02-01

    The Systematic Evaluation Program was initiated in February 1977 by the US Nuclear Regulatory Commission to review the designs of older operating nuclear reactor plants to confirm and document their safety. The review provides (1) an assessment of how these plants compare with current licensing safety requirements relating to selected issues, (2) a basis for deciding on how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety. This report documents the review of Yankee Nuclear Power Station, operated by Yankee Atomic Electric Company. The Yankee plant is one of 10 plants reviewed under Phase II of this program. This report indicates how 137 topics selected for review under Phase I of the program were addressed. Equipment and procedural changes have been identified as a result of the review

  1. Development, Dedication and Application of an Automatic Seismic Trip System for Nuclear Power Plants of Taiwan Power Company

    International Nuclear Information System (INIS)

    Liao, Hsin-kai; Lee, Chung-lin; Chen, Chang-kuo; Hsu, Yao-tung; Shyu, Shian-shing

    2011-01-01

    This paper describes the setups of Automatic Seismic Trip System (ASTS), including development, dedication and implementation, for Nuclear Power Plants (NPPs) of Taiwan Power Company (TPC). The purposed ASTS was designed to trip the reactor when big earthquake occurs. These ASTS were classified as class 1E equipment. They were developed and dedicated for safety applications in accordance with IEEE 323-1983, IEEE 344-1987, IEEE 383-1974 and Reg. Guide 1.180 R1. In order to meet the technical specification required by TPC, three sub-units in the ASTS were developed: Earthquake sensors: Kinemetrices FBA-23 triaxial accelerometers are selected since they were successfully used in Taiwan for seismic monitoring for more than 10 years. Signal conditioning module: It is designed to reduce noise from motion accelerometer (FBA-23) and then transmit seismic signal to the set-point and trip unit via instrument amplify circuit, 0.1 to 10Hz band pass filter circuit, absolute-value converter and voltage to current converter. Trip control module: after comparing the seismic signal level and set-point, the result will decide whether to drive the output relay or not. The output relay is used as the interface between ASTS and the reactor protection system in NPP. For the commercial grade item dedication for safety application, five processes were conducted. Those processes are Seismic test: to use plant specific required response spectrum (RRS), the test required spectrum should envelop RRS: Seismic auto-trip accuracy test: must not trip when filtered PA below set point minus 0.05g, and must trip when filtered PA exceeds set point over 0.05g. Trip signals occurred within 10 second interval are considered as same events: NEMA4 water proof test for sensor box: Anti-radiation test: 8.76x100 rads over 40 years: EMI/EMC test: follow RG 1.180 requirement. The ASTS were installed in three NPPs, six units in total, without connection to RPS in 2006. After one year reliable operation, the

  2. Technical evaluation of Aerojet Energy Conversion Company's topical report on a mobile volume reduction system

    International Nuclear Information System (INIS)

    Henscheid, J.W.

    1984-01-01

    This report summarizes EG and G Idaho's review of Aerojet Energy Conversion Company's (AECC's) topical report on a Mobile Volume Reduction System. The review evaluated compliance with pertinent codes, standards and regulations. The initial review was discussed with AECC by EG and G Idaho and the NRC, and all outstanding issues resolved before this final evaluation was made

  3. New maintenance strategy of Tokyo Electric Power Company and Fukushima Dai-ichi Nuclear Power Plant for effective ageing management and safe long-term operation

    International Nuclear Information System (INIS)

    Inagaki, Takeyuki; Yamashita, Norimichi

    2009-01-01

    Fukushima Dai-ichi Nuclear Power Plant is the oldest among three nuclear power plants owned and operated by Tokyo Electric Power Company, which consists of six boiling water reactor units. The commercial operation of Unit 1 was commenced in 1971 (37 years old) and Unit 6 in 1978 (29 years old). Currently ageing degradations of systems, structures and components are managed through maintenance programs, component replacement/refurbishment programs and long-term maintenance plans. The long-term maintenance plans are established through ageing management component replacement/refurbishment programs reviews performed before the 30th year of operation and they are for safe and reliable operation after 30 years (long-term operation). However the past maintenance actions and past component replacement/refurbishment programs were not always proactive and past operational experience and maintenance practices suggest that effective/proactive ageing management programs be introduced in earlier stage of the plant operation. In this circumstance, Tokyo Electric Power Company and Fukushima Dai-ichi Nuclear Power Plant are setting up a new maintenance strategy that includes 1) improving the normal maintenance programs by using ageing degradation data, 2) effective use of information on internal/external operational experience and maintenance practices related to ageing, and 3) proactive component/equipment refurbishment programs during a refreshment outage for safe and reliable long-term operation. To accomplish the goal of this strategy, strengthening engineering capability of plant staff members is a crucial required for the plant. The objective of this paper is to briefly explain main results ageing management reviews, past and current significant ageing issues and management programs against them, and the new maintenance strategy established by Tokyo Electric Power Company and Fukushima Dai-ichi Nuclear Power Plant. (author)

  4. Idaho | Midmarket Solar Policies in the United States | Solar Research |

    Science.gov (United States)

    % interest for solar PV projects. Low-interest financing Idaho Energy Resources Authority Solar PV project for financing through the Idaho Governor's Office and the Idaho Energy Resources Authority. Latest -owned community solar project for Idaho Power. Net Metering Idaho does not have statewide net metering

  5. Decision no. 2011-DC-0219 of the French nuclear safety authority from May 5, 2011, ordering the SOCATRI company to proceed to a complementary safety evaluation of some of its basic nuclear facilities in the eyes of the Fukushima Daiichi nuclear power plant accident

    International Nuclear Information System (INIS)

    2011-01-01

    As a consequence of the accident of the Fukushima Daiichi nuclear power plant (Japan), the French Prime Minister entrusted the French nuclear safety authority (ASN) with the mission to carry out a safety analysis re-evaluation of the French nuclear facilities, and in particular the nuclear power plants. A decision has been addressed by the ASN to each nuclear operator with the specifications of this safety re-evaluation analysis and the list of facilities in concern. This document is the decision addressed to the SOCATRI company, operator of the nuclear dismantling and waste processing plants of the Tricastin site (France). (J.S.)

  6. Idaho National Engineering Laboratory: Annual report, 1986

    International Nuclear Information System (INIS)

    1986-01-01

    The INEL underwent a year of transition in 1986. Success with new business initiatives, the prospects of even better things to come, and increased national recognition provided the INEL with a glimpse of its promising and exciting future. Among the highlights were: selection of the INEL as the preferred site for the Special Isotope Separation Facility (SIS); the first shipments of core debris from the Three Mile Island Unit 2 reactor to the INEL; dedication of three new facilities - the Fluorinel Dissolution Process, the Remote Analytical Laboratory, and the Stored Waste Experimental Pilot Plant; groundbreaking for the Fuel Processing Restoration Facility; and the first IR-100 award won by the INEL, given for an innovative machine vision system. The INEL has been assigned project management responsibility for the SDI Office-sponsored Multimegawatt Space Reactor and the Air Force-sponsored Multimegawatt Terrestrial Power Plant Project. New Department of Defense initiatives have been realized in projects involving development of prototype defense electronics systems, materials research, and hazardous waste technology. While some of our major reactor safety research programs have been completed, the INEL continues as a leader in advanced reactor technologies development. In April, successful tests were conducted for the development of the Integral Fast Reactor. Other 1986 highlights included the INEL's increased support to the Office of Civilian Radioactive Waste Management for complying with the Nuclear Waste Policy Act of 1982. Major INEL activities included managing a cask procurement program, demonstrating fuel assembly consolidation, and testing spent fuel storage casks. In addition, the INEL supplied the Tennessee Valley Authority with management and personnel experienced in reactor technology, increased basic research programs at the Idaho Research Center, and made numerous outreach efforts to assist the economies of Idaho communities

  7. Aerial gamma ray and magnetic survey: Idaho Project, Idaho Falls quadrangle, Idaho. Final report

    International Nuclear Information System (INIS)

    1979-10-01

    The Idaho Falls quadrangle in southeastern Idaho lies at the juncture of the Snake River Plain, the Northern Rocky Mountains, and the Basin-Range Province. Quaternary basalts of the Snake River Plain occupy 70% of the quadrangle. The rest of the area is covered by uplifted Paleozoic, Mesozoic, and Cenozoic rocks of the Pre-Late Cenozoic Orogenic Complex. Magnetic data apparently show contributions from both shallow and deep sources. The apparent expression of intrusive and extrusive rocks of late Mesozoic and Cenozoic age tends to mask the underlying structural downtrap thought to exist under the Snake River Plain. The Idaho Falls quadrangle has been unproductive in terms of uranium mining. A single claim exists in the Sawtooth Mountains, but no information was found concerning its present status at the time of this study. A total of 169 anomalies are valid according to the criteria set forth in Volume I of this report. These anomalies are scattered throughout the quadrangle, though one large group appears to relate to unnatural radiation sources in the Reactor Test Site area. The most distinctive anomalies occur in the Permian Phosphoria Formation and the Starlight Volcanics in the Port Neuf Mountains

  8. The state of improvement of security management setup in the Japan Atomic Power Company and improvement of facilities in its Tsuruga Nuclear Power Station

    International Nuclear Information System (INIS)

    1982-01-01

    In connection with the series of accidents in the Tsuruga Nuclear Power Station of the Japan Atomic Power Company, the state of security management in JAPC and the safety of facilities in the Tsuruga Nuclear Power Station, which have resulted from improvement efforts, are described on the following items: security management setup - communication and reporting in emergency, the management of inspection and maintenance records, work control and supervision in repair, improvement, etc., functional authority and responsibility in maintenance management, operation management, radiation control, personnel education; improvement of facilities - feed water heaters, laundry waste-water filter room, radioactive waste treatment facility, general drainage, concentrated waste liquid storage tanks in newly-built waste treatment building, etc. (Mori, K.)

  9. Determination of compliance with PL 92-500 Section 316(b) for the Donald C. Cook Nuclear Power Plant of the Indiana and Michigan Power Company

    International Nuclear Information System (INIS)

    Sharma, R.K.; Freeman, R.F. III.

    1980-04-01

    Region III of the US Fish and Wildlife Service contracted with the Division of Environmental Impact Studies, Argonne National Laboratory, to make the 316(b) determination for the Donald C. Cook Nuclear Power Plant of the Indiana and Michigan Power Company and to make recommendations for improvement in intake design to facilitate compliance. To conduct this assessment, appropriate literature on screening systems and reports furnished by the applicant on intake design and operation and on ecological studies at the site were reviewed. Modifications of the location and design of the existing intake and possibilities of retrofitting with fine-mesh screening to screen larval forms of fishes were examined. It was determined that currently there is no dictated need for fine-mesh screening of intake flow at the D.C. Cook Nuclear Power Plant

  10. Decision no. 2011-DC-0222 of the French nuclear safety authority from May 5, 2011, ordering the Comurhex company to proceed to a complementary safety evaluation of some of its basic nuclear facilities in the eyes of the Fukushima Daiichi nuclear power plant accident

    International Nuclear Information System (INIS)

    2011-01-01

    As a consequence of the accident of the Fukushima Daiichi nuclear power plant (Japan), the French Prime Minister entrusted the French nuclear safety authority (ASN) with the mission to carry out a safety analysis re-evaluation of the French nuclear facilities, and in particular the nuclear power plants. A decision has been addressed by the ASN to each nuclear operator with the specifications of this safety re-evaluation analysis and the list of facilities in concern. This document is the decision addressed to Comurhex company, operator of the Tricastin uranium conversion plant (France). (J.S.)

  11. Decision no. 2011-DC-0223 of the French nuclear safety authority from May 5, 2011, ordering the MELOX SA company to proceed to a complementary safety evaluation of some of its basic nuclear facilities in the eyes of the Fukushima Daiichi nuclear power plant accident

    International Nuclear Information System (INIS)

    2011-01-01

    As a consequence of the accident of the Fukushima Daiichi nuclear power plant (Japan), the French Prime Minister entrusted the French nuclear safety authority (ASN) with the mission to carry out a safety analysis re-evaluation of the French nuclear facilities, and in particular the nuclear power plants. A decision has been addressed by the ASN to each nuclear operator with the specifications of this safety re-evaluation analysis and the list of facilities in concern. This document is the decision addressed to MELOX SA company, operator of the Melox MOX fuel fabrication plant of Marcoule (France). (J.S.)

  12. Decision no. 2011-DC-0218 of the French nuclear safety authority from May 5, 2011, ordering the EURODIF SA company to proceed to a complementary safety evaluation of some of its basic nuclear facilities in the eyes of the Fukushima Daiichi nuclear power plant accident

    International Nuclear Information System (INIS)

    2011-01-01

    As a consequence of the accident of the Fukushima Daiichi nuclear power plant (Japan), the French Prime Minister entrusted the French nuclear safety authority (ASN) with the mission to carry out a safety analysis re-evaluation of the French nuclear facilities, and in particular the nuclear power plants. A decision has been addressed by the ASN to each nuclear operator with the specifications of this safety re-evaluation analysis and the list of facilities in concern. This document is the decision addressed to the EURODIF SA company, operator of the George Besse I uranium enrichment plant of the Tricastin site (France). (J.S.)

  13. Decision no. 2011-DC-0214 of the French nuclear safety authority from May 5, 2011, ordering CIS bio international company to proceed to a complementary safety evaluation of its basic nuclear facility in the eyes of the Fukushima Daiichi nuclear power plant accident

    International Nuclear Information System (INIS)

    2011-01-01

    As a consequence of the accident of the Fukushima Daiichi nuclear power plant (Japan), the French Prime Minister entrusted the French nuclear safety authority (ASN) with the mission to carry out a safety analysis re-evaluation of the French nuclear facilities, and in particular the nuclear power plants. A decision has been addressed by the ASN to each nuclear operator with the specifications of this safety re-evaluation analysis and the list of facilities in concern. This document is the decision addressed to CIS bio international company, operator of the radiopharmaceuticals fabrication facility (INB 29) of Saclay (France). (J.S.)

  14. 76 FR 388 - Southern Nuclear Operating Company; Vogtle Electric Generating Plant, Unit Nos. 1 and 2; Notice...

    Science.gov (United States)

    2011-01-04

    ... Operating Company; Vogtle Electric Generating Plant, Unit Nos. 1 and 2; Notice of Consideration of Issuance... Web site http://www.regulations.gov . Because your comments will not be edited to remove any... will not edit their comments to remove any identifying or contact information, and therefore, they...

  15. 76 FR 30206 - Southern Nuclear Operating Company, Inc., Vogtle Electric Generating Plant, Unit 1 and 2; Notice...

    Science.gov (United States)

    2011-05-24

    ... Operating Company, Inc., Vogtle Electric Generating Plant, Unit 1 and 2; Notice of Consideration of Issuance..., http://www.regulations.gov . Because your comments will not be edited to remove any identifying or... received from other persons for submission to the NRC inform those persons that the NRC will not edit their...

  16. 77 FR 40914 - In the Matter of Indiana Michigan Power Company, D. C. Cook Nuclear Power Plant; Confirmatory...

    Science.gov (United States)

    2012-07-11

    ... Company met in an ADR session mediated by a professional mediator, arranged through Cornell University's... counsel or representative) to digitally sign documents and access the E-Submittal server for any... requirements for accessing the E-Submittal server are detailed in the NRC's ``Guidance for Electronic...

  17. Chlorine-36 in the Snake River Plain aquifer at the Idaho National Engineering Laboratory: Origin and implications

    International Nuclear Information System (INIS)

    Beasley, T.M.; Cecil, L.D.; Mann, L.J.; Sharma, P.; Fehn, U.; Gove, H.E.; Kubik, P.W.

    1993-01-01

    Between 1952 and 1984, low-level radioactive waste was introduced directly into the Snake River Plain aquifer at the Idaho National Engineering Laboratory (INEL), Idaho Falls, Idaho. These wastes were generated, principally, at the nuclear fuel reprocessing facility on the site. The measurements of 36 Cl in monitoring and production well waters, downgradient from disposal wells and seepage ponds, found easily detectable, nonhazardous concentrations of this radionuclide from the point of injection to the INEL southern site boundary. Comparisons are made between 3 H and 36 Cl concentrations in aquifer water and the advantages of 36 Cl as a tracer of subsurface-water dynamics at the site are discussed

  18. Chlorine-36 in the Snake River Plain Aquifer at the Idaho National Engineering Laboratory; origin and implications

    Science.gov (United States)

    Beasley, T.M.; Cecil, L.D.; Sharma, P.; Kubik, P.W.; Fehn, U.; Mann, L.J.; Gove, H.E.

    1993-01-01

    Between 1952 and 1984, low-level radioactive waste was introduced directly into the Snake River Plain aquifer at the Idaho National Engineering Laboratory (INEL), Idaho Falls, Idaho. These wastes were generated, principally, at the nuclear fuel reprocessing facility on the site. Our measurements of 36C1 in monitoring and production well waters, downgradient from disposal wells and seepage ponds, found easily detectable, nonhazardous concentrations of this radionuclide from the point of injection to the INEL southern site boundary. Comparisons are made between 3H and 36Cl concentrations in aquifer water and the advantages of 36C1 as a tracer of subsurface-water dynamics at the site are discussed.

  19. Electromagnetic pulse (EMP) survey of the Idaho State Emergency Operating Center, Boise, Idaho

    Energy Technology Data Exchange (ETDEWEB)

    Crutcher, R.I.; Buchanan, M.E.; Jones, R.W.

    1992-02-01

    The purpose of this report is to develop an engineering design package to protect the Federal Emergency Management Agency (FEMA) National Radio System (FNARS) facilities from the effects of high- altitude electromagnetic pulses (HEMPs). This report was developed specifically for the Idaho State Emergency Operating Center (EOC) in Boise, Idaho. It is highly probable that there will be a heavy dependence upon high-frequency (hf) radio communications for long- haul communications following a nuclear attack on the continental United States, should one occur. To maintain the viability of the FEMA hf radio network during such a situation, steps must be taken to protect the FNARS facilities against the effects of HEMP that are likely to be created in a nuclear confrontation. The solution must than be to reduce HEMP-induced stresses on the system by means of tailored retrofit hardening measures using commercial protection devices when available. It is the intent of this report to define the particular hardening measures that will minimize the susceptibility of system components to HEMP effects. To the extent economically viable, protective actions have been recommended for implementation, along with necessary changes or additions, during the period of the FNARS upgrade program. This report addresses electromagnetic pulse (EMP) effects only and disregards any condition in which radiation effects may be a factor. It has been established that, except for the source region of a surface burst, EMP effects of high-altitude bursts are more severe than comparable detonations in either air or surface regions. Any system hardened to withstand the more extreme EMP environment will survive the less severe EMP conditions. The threatening environment will therefore be limited to HEMP situations.

  20. Modification of reactor installation in the Takahama nuclear power plants No.1 and No.2 of Kansai Electric Power Company, Inc

    International Nuclear Information System (INIS)

    1979-01-01

    The Nuclear Safety Commission recognized the adequacy concerning the inquiry which was offered from the Minister of International Trade and Industry on July 24, 1979, following the safety evaluation in the Ministry of International Trade and Industry, and decided to submit a report to the Minister of International Trade and Industry on July 26, 1979, about the modification of reactor installation in the Takahama nuclear power plants No. 1 and No. 2 of the Kansai Electric Power Company, Inc. This is concerned to the application which was made from the president of the Kansai Electric Power Company, Inc., to the Minister of International Trade and Industry on July 23, 1979. The content of the modification is to add a control circuit which is actuated by the signal of abnormal low pressure in a reactor to the circuit of actuating the emergency core cooling system of the plant. The influences on the safety protection system by the addition of the circuit for transmitting safety injection signal and by the additions of an interlock circuit preventing the misoperation of pressurizer spray and of a block circuit of safety injection signal in case of the abnormal low pressure in a reactor were evaluated. The effects on the function and characteristics of the emergency core cooling system due to the addition of the control circuit were investigated, and it was recognized by the analysis that there is no effect in the pipe ruptures of both small and large scales. (Nakai, Y.)

  1. Weed hosts Globodera pallida from Idaho

    Science.gov (United States)

    The potato cyst nematode, Globodera pallida (PCN), a restricted pest in the USA, was first reported in Bingham and Bonneville counties of Idaho in 2006. The US government and Idaho State Department of Agriculture hope to eradicate it from infested fields. Eradicating PCN will require depriving the n...

  2. The Pocatello Valley, Idaho, earthquake

    Science.gov (United States)

    Rogers, A. M.; Langer, C.J.; Bucknam, R.C.

    1975-01-01

    A Richter magnitude 6.3 earthquake occurred at 8:31 p.m mountain daylight time on March 27, 1975, near the Utah-Idaho border in Pocatello Valley. The epicenter of the main shock was located at 42.094° N, 112.478° W, and had a focal depth of 5.5 km. This earthquake was the largest in the continental United States since the destructive San Fernando earthquake of February 1971. The main shock was preceded by a magnitude 4.5 foreshock on March 26. 

  3. 75 FR 12311 - FirstEnergy Nuclear Operating Company; Notice of Consideration of Issuance of Amendment to...

    Science.gov (United States)

    2010-03-15

    ... Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing; Correction AGENCY: Nuclear Regulatory Commission. ACTION: Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No...

  4. High Level Waste Tank Farm Replacement Project for the Idaho Chemical Processing Plant at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    1993-06-01

    The Department of Energy (DOE) has prepared an environmental assessment (EA), DOE/EA-0831, for the construction and operation of the High-Level Waste Tank Farm Replacement (HLWTFR) Project for the Idaho Chemical Processing Plant located at the Idaho National Engineering Laboratory (INEL). The HLWTFR Project as originally proposed by the DOE and as analyzed in this EA included: (1) replacement of five high-level liquid waste storage tanks with four new tanks and (2) the upgrading of existing tank relief piping and high-level liquid waste transfer systems. As a result of the April 1992 decision to discontinue the reprocessing of spent nuclear fuel at INEL, DOE believes that it is unlikely that the tank replacement aspect of the project will be needed in the near term. Therefore, DOE is not proposing to proceed with the replacement of the tanks as described in this-EA. The DOE's instant decision involves only the proposed upgrades aspect of the project described in this EA. The upgrades are needed to comply with Resource Conservation and Recovery Act, the Idaho Hazardous Waste Management Act requirements, and the Department's obligations pursuant to the Federal Facilities Compliance Agreement and Consent Order among the Environmental Protection Agency, DOE, and the State of Idaho. The environmental impacts of the proposed upgrades are adequately covered and are bounded by the analysis in this EA. If DOE later proposes to proceed with the tank replacement aspect of the project as described in the EA or as modified, it will undertake appropriate further review pursuant to the National Environmental Policy Act

  5. Idaho National Engineering Laboratory, Test Area North, Hangar 629 -- Photographs, written historical and descriptive data

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-12-31

    The report describes the history of the Idaho National Engineering Laboratory`s Hangar 629. The hangar was built to test the possibility of linking jet engine technology with nuclear power. The history of the project is described along with the development and eventual abandonment of the Flight Engine Test hangar. The report contains historical photographs and architectural drawings.

  6. Ecological risk assessment at the Idaho National Engineering Laboratory: Overview

    International Nuclear Information System (INIS)

    VanHorn, R.; Bensen, T.; Green, T.; Hampton, N.; Staley, C.; Morris, R.; Brewer, R.; Peterson, S.

    1994-01-01

    The paper will present an overview of the methods and results of the screening level ecological risk assessment (ERA) performed at the Idaho National Engineering Laboratory (INEL). The INEL is a site with some distinct characteristics. First it is a large Department of Energy (DOE) laboratory (2,300 km 2 ) having experienced 40 years of nuclear material production operations. Secondly, it is a relatively undisturbed cold desert ecosystem. Neither of these issues have been sufficiently addressed in previous ERAs. It was necessary in many instances to develop methods that differed from those used in other studies. This paper should provide useful methodologies for the ERAs performed at other similar sites

  7. Report on countermeasure to plant life management of the nuclear power plants at three electric power companies

    International Nuclear Information System (INIS)

    1999-01-01

    Three nuclear power reactors of the Fukushima-1 nuclear power plant, the Mihama-1 power plant and the Tsuruga-1 power plant were investigated according to the estimation plan shown in the Fundamental Concept on Plant Life Management of Agency of Natural Resources and Energy, Ministry of International Trade and Industry on April, 1996. Their reports contained the technical evaluation against, the responsive items to and the future examinations of the plant life management. In special, in the responsive items, some items to be added to the present maintenance process and some technical developmental problems are described in details and concretely. (G.K.)

  8. Applied Physics Research at the Idaho Accelerator Center

    International Nuclear Information System (INIS)

    Date, D. S.; Hunt, A. W.; Chouffani, K.; Wells, D. P.

    2011-01-01

    The Idaho Accelerator Center, founded in 1996 and based at Idaho State University, supports research, education, and high technology economic development in the United States. The research center currently has eight electron linear accelerators ranging in energy from 6 to 44 MeV with the latter linear accelerator capable of picosecond pulses, a 2 MeV positive-ion Van de Graaff, a 4 MV Nec tandem Pelletron, and a pulsed-power 8 k A, 10 MeV electron induction accelerator. Current research emphases include, accelerator physics research, accelerator based medical isotope production, active interrogation techniques for homeland security and nuclear nonproliferation applications, non destructive testing and materials science studies in support of industry as well as the development of advanced nuclear fuels, pure and applied radio-biology, and medical physics. This talk will highlight three of these areas including the production of the isotopes 99 Tc and 67 Cu for medical diagnostics and therapy, as well as two new technologies currently under development for nuclear safeguards and homeland security - namely laser Compton scattering and the polarized photofission of actinides

  9. Department of Energy Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs Draft Environmental Impact Statement; Volume 1, Appendix F, Nevada Test Site and Oak Ridge Reservation Spent Nuclear Fuel Management Programs

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-06-01

    This volume addresses the interim storage of spent nuclear fuel (SNF) at two US Department of Energy sites, the Nevada Test Site (NTS) and the Oak Ridge Reservation (ORR). These sites are being considered to provide a reasonable range of alternative settings at which future SNF management activities could be conducted. These locations are not currently involved in management of large quantities of SNF; NTS has none, and ORR has only small quantities. But NTS and ORR do offer experience and infrastructure for the handling, processing and storage of radioactive materials, and they do exemplify a broad spectrum of environmental parameters. This broad spectrum of environmental parameters will provide, a perspective on whether and how such location attributes may relate to potential environmental impacts. Consideration of these two sites will permit a programmatic decision to be based upon an assessment of the feasible options without bias, to the current storage sites. This volume is divided into four parts. Part One is the volume introduction. Part Two contains chapters one through five for the NTS, as well as references contained in chapter six. Part Three contains chapters one through five for the ORR, as well as references contained in chapter six. Part Four is summary information including the list of preparers, organizations contacted, acronyms, and abbreviations for both the NTS and the ORR. A Table of Contents, List of Figures, and List of Tables are included in parts Two, Three, and Four. This approach permitted the inclusion of both sites in one volume while maintaining consistent chapter numbering.

  10. Draft environmental statement: Related to operation of the Edwin I. Hatch Nuclear Plant Unit No. 2, Georgia Power Company: Docket No. 50-366

    International Nuclear Information System (INIS)

    1977-04-01

    The proposed action is the issuance of an operation license to the Georgia Power Company for the startup and operation of the Edwin I. Hatch Nuclear Plant, Unit No. 2 (Docket No. 50-366), located on the Altamaha River in Appling County, approximately 11 miles north from Baxley, Georgia. The information in this Statement represents the second, assessment of the environmental impact associated with the Edwin I. Hatch Nuclear Plant, Unit No. 2, pursuant to the guidelines of the National Environmental Policy Act of 1969 (NEPA) and 10 CFR Part 51 of the Commission's Regulations. After receipt of an application, in 1970, to construct this plant, the staff carried out a review of impact that would occur during the construction and operation of this plant. That evaluation was issued as a Final Environmental Statement in October 1972. As the result of that environmental review, a safety review, an evaluation by the Advisory Committee on Reactor Safeguards, and a public hearing in Baxley, Georgia and Washington, D.C., the AEC (now NRC) issued a permit in December 1972, for the construction of Unit No. 2 of the Edwin I. Hatch Nuclear Plant. As of February 1977, the construction of Unit No. 2 was 70% complete. With a proposed fuel-loading date of April 1978 for Unit No. 2, the applicant has petitioned for license to operate Unit No. 2 and has submitted (July 1975) the required safety and environmental reports to substantiate this petition. 97 refs., 18 figs., 37 tabs

  11. Integrated-plant-safety assessment Systematic Evaluation Program. Dresden Nuclear Power Station, Unit 2, Commonwealth Edison Company, Docket No. 50-237

    International Nuclear Information System (INIS)

    1982-10-01

    The Systematic Evaluation Program was initiated in February 1977 by the US Nuclear Regulatory Commission to review the designs of older operating nuclear reactor plants to reconfirm and document their safety. The review provides: (1) an assessment of how these plants compare with current licensing safety requirements relating to selected issues; (2) a basis for deciding on how these differences should be resolved in an integrated plant review; and (3) a documented evaluation of plant safety. This report documents the review of Dresden Nuclear Generating Station, Unit 2 owned and operated by the Commonwealth Edison Company and located in Grundy County, Illinois. Dresden Unit 2 is one of ten plants reviewed under Phase II of this program, which indicates how 137 topics selected for review under Phase I of the program were addressed. Equipment and procedural changes have been identified as a result of the review. It is expected that this report will be one of the bases in considering the issuance of a full-term operating license in place of the existing provisional operating license

  12. Smart Companies.

    Science.gov (United States)

    Galagan, Patricia A.

    1997-01-01

    Capturing and leveraging knowledge is an important new management trend that is as yet undefined. Some companies are accounting for their intellectual capital and applying it to the company balance sheets. (JOW)

  13. 75 FR 12312 - South Carolina Electric and Gas Company; Virgil C. Summer Nuclear Station, Unit 1; Exemption

    Science.gov (United States)

    2010-03-15

    ... cladding oxidation from the metal/water reaction shall be calculated using the Baker-Just equation. The... of energy release, hydrogen concentration, and cladding oxidation from the metal-water reaction shall... pressurized light-water nuclear power reactor fueled with uranium oxide pellets within cylindrical zircaloy or...

  14. 75 FR 9623 - Arizona Public Service Company, et al.; Palo Verde Nuclear Generating Station, Units 1, 2, and 3...

    Science.gov (United States)

    2010-03-03

    ... pressurized-water reactors located in Maricopa County, Arizona. 2.0 Request/Action Title 10 of the Code of... pressure boundary during normal operating and hydrostatic or leak rate testing conditions. Specifically, 10... NRC's March 16, 2001, SE, the staff noted, ``[t]he CE NSSS [nuclear steam supply system] methodology...

  15. Review of the upper Cenozoic stratigraphy overlying the Columbia River Basalt Group in western Idaho

    International Nuclear Information System (INIS)

    Strowd, W.B.

    1980-12-01

    This report is a synthesis of information currently available on the rocks that stratigraphically overlie the Columbia River Basalt Group in Idaho. The primary objective is to furnish a brief but comprehensive review of the literature available on upper Cenozoic rocks in western Idaho and to discuss their general stratigraphic relationships. This study also reviews the derivation of the present stratigraphy and notes weaknesses in our present understanding of the geology and the stratigraphy. This report was prepared in support of a study to evaluate the feasibility of nuclear waste storage in the Columbia River Basalt Group of the Pasco Basin, Washington

  16. A study on environmental pollution monitoring and occupational health in the Capital Iron and Steel Company, Beijing, China, using nuclear and related analytical techniques

    International Nuclear Information System (INIS)

    Chai Zhifang; Qian Qinfang; Feng Xiangqian; Ding Wenjun; Kuang Minxu; Wang Hongyu; Zhang Yongchen

    2000-01-01

    Since the First Research Coordination Meeting in Vienna, 20-24 October 1997, on the CRP on Assessment of Levels and Health-effects of Airborne Particulate Matter in Mining, Metal Refining and Metal Working Industries using Nuclear and related Analytical Techniques, our research group has completed the work plan defined by the contract with the Agency, including: (1) collection of airborne particulate, plant and soil samples from sites around the Capital Iron and Steel Company and of human hair, urine, and blood samples from the exposed workers and the control group; (2) validation of the analytical methods (NAA, XRF, SRXRF, JCP-AES etc.) by analyzing appropriate reference materials and by participating in relevant Agency's quality assurance exercises; and (3) analysis of part of the collected samples and preliminary discussion on the available analytical results. Finally, plan for future work was outlined as well. (author)

  17. Implemented organisation for subcontracting companies involved in the maintenance of the French nuclear stock - Sheet nr 39

    International Nuclear Information System (INIS)

    2011-01-01

    Every year, some 20,000 subcontracted salaried employees are mobilised for maintenance operations in the French nuclear reactors. Subcontracting is an answer to different needs: specific abilities, the short delay for maintenance during which a reactor is stopped, and which requires a very important contribution of labour, and specialised labour for some interventions. The document evokes a rigorous selection and certification process, and indicates the different specific training which are organised for anyone intervening in a nuclear power plant. It outlines that radiation protection and safety arrangements are the same for all (dosimetry), and that some measurements are performed on some temporary workers. Some data shows that these controls are efficient and that safety is improving

  18. Factors Associated with Maintaining the Mental Health of Employees after the Fukushima Nuclear Disaster: Findings from Companies Located in the Evacuation Area.

    Science.gov (United States)

    Orui, Masatsugu; Suzuki, Yuriko; Goto, Aya; Yasumura, Seiji

    2017-12-31

    After the nuclear disaster in Fukushima on 11 March 2011, some businesses were permitted to continue operating even though they were located in the evacuation area designated by the Japanese government. The aim of this study was to examine differences in the mental health status, workplace, living environment, and lifestyle of employees in the evacuation and non-evacuation areas. We also investigated factors related to their mental health status. Data for this cross-sectional study were collected from the questionnaire responses of 647 employees at three medium-sized manufacturing companies in the evacuation and non-evacuation areas. Through a cross-tabulation analysis, employees who worked at companies in the evacuation areas showed an increase in the duration of overtime work, work burden, and commute time, and had experienced separation from family members due to the radiation disaster and perceived radiation risks. The results of a multivariate logistic regression analysis showed that, even in a harsh workplace and living environment, being younger, participating regularly in physical activity, having a social network (Lubben Social Network Scale-6 ≤ 12), laughing frequently, and feeling satisfied with one's workplace and domestic life were significantly associated with maintaining a healthy mental health status after the disaster. These findings are applicable for workers' health management measures after disasters.

  19. Idaho Transportation Department 2009 partnership survey.

    Science.gov (United States)

    2010-06-01

    The report discusses the results of an electronic survey of 1,500 individual stakeholders of the Idaho Transportation Department (ITD). The purpose of this survey, which was conducted in August and September 2009, was to gauge stakeholders satisfa...

  20. Evaluation of seepage and discharge uncertainty in the middle Snake River, southwestern Idaho

    Science.gov (United States)

    Wood, Molly S.; Williams, Marshall L.; Evetts, David M.; Vidmar, Peter J.

    2014-01-01

    The U.S. Geological Survey, in cooperation with the State of Idaho, Idaho Power Company, and the Idaho Department of Water Resources, evaluated seasonal seepage gains and losses in selected reaches of the middle Snake River, Idaho, during November 2012 and July 2013, and uncertainty in measured and computed discharge at four Idaho Power Company streamgages. Results from this investigation will be used by resource managers in developing a protocol to calculate and report Adjusted Average Daily Flow at the Idaho Power Company streamgage on the Snake River below Swan Falls Dam, near Murphy, Idaho, which is the measurement point for distributing water to owners of hydropower and minimum flow water rights in the middle Snake River. The evaluated reaches of the Snake River were from King Hill to Murphy, Idaho, for the seepage studies and downstream of Lower Salmon Falls Dam to Murphy, Idaho, for evaluations of discharge uncertainty. Computed seepage was greater than cumulative measurement uncertainty for subreaches along the middle Snake River during November 2012, the non-irrigation season, but not during July 2013, the irrigation season. During the November 2012 seepage study, the subreach between King Hill and C J Strike Dam had a meaningful (greater than cumulative measurement uncertainty) seepage gain of 415 cubic feet per second (ft3/s), and the subreach between Loveridge Bridge and C J Strike Dam had a meaningful seepage gain of 217 ft3/s. The meaningful seepage gain measured in the November 2012 seepage study was expected on the basis of several small seeps and springs present along the subreach, regional groundwater table contour maps, and results of regional groundwater flow model simulations. Computed seepage along the subreach from C J Strike Dam to Murphy was less than cumulative measurement uncertainty during November 2012 and July 2013; therefore, seepage cannot be quantified with certainty along this subreach. For the uncertainty evaluation, average

  1. Human Factors Engineering Incorporated into the Carolina Power and Light company's nuclear power plant control panel modifications

    International Nuclear Information System (INIS)

    Beith, D.M.; Shoemaker, E.M.; Horn, K.; Boush, D.

    1988-01-01

    Maintaining human factors conventions/practices that were established during the Detailed Control Design Review (DCRDR), is difficult if Human Factors Engineering (HFE) is not incorporated into the plant modification process. This paper presents the approach used at Carolina Power and Light's nuclear power plants that has successfully incorporated human factors engineering into their plant modification process. An HFE Design Guide or HFE Specification was developed which is used by the design engineers or plant engineering support groups in the preparation of plant modifications

  2. Boise State's Idaho Eclipse Outreach Program

    Science.gov (United States)

    Davis, Karan; Jackson, Brian

    2017-10-01

    The 2017 total solar eclipse is an unprecedented opportunity for astronomical education throughout the continental United States. With the path of totality passing through 14 states, from Oregon to South Carolina, the United States is expecting visitors from all around the world. Due to the likelihood of clear skies, Idaho was a popular destination for eclipse-chasers. In spite of considerable enthusiasm and interest by the general population, the resources for STEM outreach in the rural Pacific Northwest are very limited. In order to help prepare Idaho for the eclipse, we put together a crowdfunding campaign through the university and raised over $10,000. Donors received eclipse shades as well as information about the eclipse specific to Idaho. Idaho expects 500,000 visitors, which could present a problem for the many small, rural towns scattered across the path of totality. In order to help prepare and equip the public for the solar eclipse, we conducted a series of site visits to towns in and near the path of totality throughout Idaho. To maximize the impact of this effort, the program included several partnerships with local educational and community organizations and a focus on the sizable refugee and low-income populations in Idaho, with considerable attendance at most events.

  3. Aerial gamma ray and magnetic survey: Idaho Project, Hailey, Idaho Falls, Elk City quadrangles of Idaho/Montana and Boise quadrangle, Oregon/Idaho. Final report

    International Nuclear Information System (INIS)

    1979-09-01

    During the months of July and August, 1979, geoMetrics, Inc. collected 11561 line mile of high sensitivity airborne radiometric and magnetic data in Idaho and adjoining portions of Oregon and Montana over four 1 0 x 2 0 NTMS quadrangles (Boise, Hailey, Idaho Falls, and Elk City) as part of the Department of Energy's National Uranium Resource Evaluation Program. All radiometric and magnetic data were fully corrected and interpreted by geoMetrics and are presented as five volumes (one Volume I and four Volume II's). Approximately 95 percent of the surveyed areas are occupied by exposures of intrusive and extrusive rocks. The Cretaceous-Tertiary Idaho Batholith dominates the Elk City and Hailey quadrangles. The Snake River volcanics of Cenozoic Age dominate the Idaho Falls quadrangle and southeast part of the Hailey sheet. Tertiary Columbia River basalts and Idaho volcanics cover the Boise quadrangle. There are only two uranium deposits within the four quadrangles. The main uranium producing areas of Idaho lie adjacent to the surveyed area in the Challis and Dubois quadrangles

  4. Report of the present state of nuclear fuel and the activities of the Swedish Nuclear Fuel Supply Company during October 1979 to September 1980

    International Nuclear Information System (INIS)

    1980-11-01

    A summary of the company's activities is presented. The world reserves of uranium are estimated to be enough for 100 years. The prospecting of uranium ores in Sweden is continued. The national requirements of natural uranium on to the year 2010 are estimated to 26000-39000 ton. A reserve storage of low enrichment uranium is being built up and so is a center for spent fuel storage near Oskarshamn. Contracts with Cogema concerning reprocessing have been entered into and a maritime transport system is being planned. The projects of the final disposal of radioactive waste are in progress. The research and development of the various aspects of the material science and geology in Connection with the final disposal is dealt with on both national and international basis. (G.B.)

  5. Integrated plant safety assessment: systematic evaluation program. Oyster Creek nuclear generating station. GPU Nuclear Corporation and Jersey Central Power and Light Company. Docket No. 50-219

    International Nuclear Information System (INIS)

    1982-09-01

    The Systematic Evaluation Program was initiated in February 1978 by the US Nuclear Regulatory Commission to review the designs of older operating nuclear reactor plants to reconfirm and document their safety. The review provides (1) an assessment of how these plants compare with current licensing safety requirements relating to selected issues, (2) a basis for deciding on how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety. This report documents the review of the Oyster Creek Nuclear Generating Station (located in Ocean County, New Jersey), one of ten plants reviewed under Phase II of this program, and indicates how 137 topics selected for review under Phase I of the program were addressed. Equipment and procedural changes have been identified as a result of the review. It is expected that this report will be one of the bases in considering the issuance of a full-term operating license in place of the existing provisional operating license

  6. Magnetotelluric soundings on the Idaho National Engineering Laboratory facility, Idaho

    International Nuclear Information System (INIS)

    Stanley, W.D.

    1982-01-01

    The magnetotelluric (MT) method was used as one of several geophysical tools to study part of the Idaho Engineering Laboratory (INEL) facility. The purpose of the geophysical study on INEL was to investigate the facility for a possible site to drill a geothermal exploration well. The initial interpretation of the MT sounding data was done with one-dimensional models consisting of four or five layers, the minimum number required to fit the data. After the test well (INEL-1) was completed, the electric log was used to guide an improved one-dimensional ID interpretation of the MT sounding data. Profile models derived from the well log provided good agreement with velocity models derived from refraction seismic data. A resolution study using generalized inverse techniques shows that the resolution of resistive layers in the lower part of the MT models is poor, as is the definition of a shallow, altered basalt unit. The only major structure observed on the MT data was the faulted contact between the SNRP and basin and range structures on the west. Modeling of the data near this structure with a two-dimensional computer program showed that the MT data near the fault require a model similar to the seismic refraction models and that structure on a deep crustal conductor is also required

  7. Hydrologic data for the Idaho National Engineering Laboratory site, Idaho

    International Nuclear Information System (INIS)

    Barraclough, J.T.; Jensen, R.G.

    1976-01-01

    The Idaho Chemical Processing Plant (ICPP) discharges low-level waste and chemical waste directly to the Snake River Plain aquifer through a 600-foot (180 meter) disposal well. Most of the radioactivity is removed by distillation and ion exchange prior to being discharged into the well. During 1971 to 1973, the well was used to dispose of 404 curies of radioactivity, of which 389 curies were tritium (96 percent). The average yearly discharge was about 300 million gallons (1.1 x 10 9 liters). The distribution of waste products in the Snake River Plain aquifer covers about 15 square miles (30 square kilometers). Since disposal began in 1952, the wastes have migrated about 5 miles (8 kilometers) downgradient from discharge points. The perched ground-water body contains tritium, chromium-51, cobalt-60, and strontium-90. Radionuclides are subject to radioactive decay, sorption, and dilution by dispersion in the aquifer. Chemical wastes are subject to sorption and dilution by dispersion. Waste plumes south of the ICPP containing tritium, sodium, and chloride have been mapped and all cover a similar area. The plumes follow generally southerly flow lines and are widely dispersed in the aquifer. The waste plume of strontium-90 covers a much smaller area of the aquifer, about 1.5 square miles (4 square kilometers). Based on the relatively small size of the plume, it would appear that the strontium-90 is sorbed from solution as it moves through the Snake River Plain aquifer

  8. 75 FR 32210 - United States v. Idaho Orthopaedic Society, Timothy Doerr, Jeffrey Hessing, Idaho Sports Medicine...

    Science.gov (United States)

    2010-06-07

    ..., Jeffrey Hessing, Idaho Sports Medicine Institute, John Kloss, David Lamey, and Troy Watkins; Proposed... Sports Medicine Institute, John Kloss, David Lamey, and Troy Watkins, Civil Case No. 10-268. On May 28..., Jeffrey Hessing, Idaho Sports Medicine Institute, John Kloss, David Lamey, and Troy Watkins, Defendants...

  9. We let the electricity giants shrink. Anti-nuclear activists can be successful even against the largest companies; Wir lassen die Stromriesen schrumpfen. AtomkraftgegnerInnen koennen sogar gegen die groessten Konzerne erfolgreich sein

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2015-12-15

    In the newsletter the authors discuss the issues economic situation of the large electricity companies in Germany, the governmental energy policy, the ongoing financial support by the government, and the possibility to shutdown all German nuclear power plants without electricity shortcomings.

  10. VUJE, Inc. Company mission

    International Nuclear Information System (INIS)

    2008-01-01

    VUJE is an engineering company that performs design, supply, implementation, research and training activities, particularly in the field of nuclear and conventional power generation. Our earlier research specialization in the field of nuclear power generation has gradually diversified into design and engineering activities during performing particular tasks. Nowadays we are able to provide all activities related to construction, operation, modernisation and finally termination of operation mainly of power generating facilities. Our objective is to offer complex, professional and quality solutions according to our customers' needs and thus assist to show real asset of nuclear energy generation. (author)

  11. Dubois Quadrangle, Idaho and Montana

    International Nuclear Information System (INIS)

    Wodzicki, A.; Krason, J.

    1981-06-01

    Within the Dubois Quadrangle (Idaho and Montana), environments favorable for uranium deposits, based on National Uranium Resource Evaluation criteria, occur in the McGowan Creek Formation and within some Tertiary sedimentary basins. The Mississippian McGowan Creek Formation consists of uraniferous, black, siliceous mudstone and chert with minor porous sedimentary channels. In the southern Beaverhead Mountains it has been fractured by a bedding-plane fault, and uranium has been further concentrated by circulating groundwater in the porous channels and brecciated zones, both of which contain about 200 ppM uranium. The northern parts of the Pahsimeroi River, Lemhi River, Medicine Lodge Creek, Horse Prairie, and Sage Creek Basins are considered favorable for sandstone-type uranium deposits. Evidence present includes suitable source rocks such as rhyolitic flow breccia, laharic deposits, or strongly welded tuffs; permeable sediments, including most sandstones and conglomerates, providing they do not contain devitrified glass; suitable reductants such as lignite, pyrite, or low-Eh geothermal water; and uranium occurrences

  12. Dillon quadrangle, Montana and Idaho

    International Nuclear Information System (INIS)

    Wodzicki, A.; Krason, J.

    1981-04-01

    All geologic conditions in the Dillon quadrangle (Montana and Idaho) have been thoroughly examined, and, using National Uranium Resource Evaluation criteria, environments are favorable for uranium deposits along fractured zones of Precambrian Y metasediments, in the McGowan Creek Formation, and in some Tertiary sedimentary basins. A 9-m-wide quartz-bearing fractured zone in Precambrian Y quartzites near Gibbonsville contains 175 ppM uranium, probably derived from formerly overlying Challis Volcanics by supergene processes. The Mississippian McGowan Creek Formation consists of uraniferous, black, siliceous mudstone and chert. In the Melrose district it has been fractured by a low-angle fault, and uranium has been further concentrated by circulating ground water in the 2- to 6-m-thick brecciated zones that in outcrop contain 90 to 170 ppM uranium. The Wise River, northern Divide Creek, Jefferson River, Salmon River, Horse Prairie, Beaverhead River, and upper Ruby River Basins are considered favorable for uranium deposits in sandstone. Present are suitable uraniferous source rocks such as the Boulder batholith, rhyolitic flow breccia, laharic deposits, or strongly welded tuffs; permeable sediments, including most sandstones and conglomerates, providing they do not contain devitrified glass; suitable reductants such as lignite, pyrite, or low-Eh geothermal water; and uranium occurrences

  13. A research company in transition

    International Nuclear Information System (INIS)

    Hatcher, S.R.

    1989-01-01

    The role of Atomic Energy of Canada Ltd's Research Company is to perform the research, development, demonstration and marketing needed to apply nuclear sciences and their associated technologies for the maximum benefit of Canada. This article by its president, Dr S R Hatcher, describes the Research Company as it attempts to fulfil its mission in very altered circumstances. (Author)

  14. Post Irradiation Capabilities at the Idaho National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Schulthess, J.L.

    2011-08-01

    The U.S. Department of Energy (DOE) Office of Nuclear Energy (NE) oversees the research, development, and demonstration activities that ensure nuclear energy remains a viable energy option for the United States. Fuel and material development through fabrication, irradiation, and characterization play a significant role in accomplishing the research needed to support nuclear energy. All fuel and material development requires the understanding of irradiation effects on the fuel performance and relies on irradiation experiments ranging from tests aimed at targeted scientific questions to integral effects under representative and prototypic conditions. The DOE recently emphasized a solution-driven, goal-oriented, science-based approach to nuclear energy development. Nuclear power systems and materials were initially developed during the latter half of the 20th century and greatly facilitated by the United States ability and willingness to conduct large-scale experiments. Fifty-two research and test reactors with associated facilities for performing fabrication and pre and post irradiation examinations were constructed at what is now Idaho National Laboratory (INL), another 14 at Oak Ridge National Laboratory (ORNL), and a few more at other national laboratory sites. Building on the scientific advances of the last several decades, our understanding of fundamental nuclear science, improvements in computational platforms, and other tools now enable technological advancements with less reliance on large-scale experimentation.

  15. Post Irradiation Capabilities at the Idaho National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Schulthess, J.L.; Robert D. Mariani; Rory Kennedy; Doug Toomer

    2011-08-01

    The U.S. Department of Energy (DOE) Office of Nuclear Energy (NE) oversees the research, development, and demonstration activities that ensure nuclear energy remains a viable energy option for the United States. Fuel and material development through fabrication, irradiation, and characterization play a significant role in accomplishing the research needed to support nuclear energy. All fuel and material development requires the understanding of irradiation effects on the fuel performance and relies on irradiation experiments ranging from tests aimed at targeted scientific questions to integral effects under representative and prototypic conditions. The DOE recently emphasized a solution-driven, goal-oriented, science-based approach to nuclear energy development. Nuclear power systems and materials were initially developed during the latter half of the 20th century and greatly facilitated by the United States’ ability and willingness to conduct large-scale experiments. Fifty-two research and test reactors with associated facilities for performing fabrication and pre and post irradiation examinations were constructed at what is now Idaho National Laboratory (INL), another 14 at Oak Ridge National Laboratory (ORNL), and a few more at other national laboratory sites. Building on the scientific advances of the last several decades, our understanding of fundamental nuclear science, improvements in computational platforms, and other tools now enable technological advancements with less reliance on large-scale experimentation.

  16. Inquiry relating to modifications of reactor installation in Ikata No. 1 and 2 nuclear power plants of Shikoku Electric Power Company, Inc

    International Nuclear Information System (INIS)

    1979-01-01

    Application was made to the Minister of International Trade and Industry for the license relating to the modifications of reactor installation in the Ikata No. 1 and 2 nuclear power plants of the Shikoku Electric Power Company, Inc., on February 13, 1979, from the president of the company. After the safety evaluation was finished by the Ministry of International Trade and Industry, inquiry was conducted to the Atomic Energy Safety Commission (AESC) on June 15, 1979, from the Minister of International Trade and Industry. The investigation and discussion were commenced by the AESC on June 19, 1979. The modifications of the reactor installation are the increase of new fuel storage capacity from about 1/3 to about 2/3 of in-core fuel for No. 1 plant and the modification of driving mechanism from the roller nut type to the magnetic jack type for the control rod cluster for adjusting power distribution in the No. 2 plant. The contents of the safety examination for each item written above are presented. The prevention of criticality is carefully practiced for the new fuel storage by putting fuel assemblies in stainless steel can type racks and locating the fuel assemblies at the proper distance. Relating to the driving mechanism for the control rod cluster adjusting power distribution, the driving speed is not modified and the reliability is kept by carrying out the continuous operation test and the electric power black out test as the demonstration test. The magnetic jack type mechanism has the locking device to prevent reactor tripping at the time of electric power black out, and the cluster is held at the location where the cluster existed at the time of black out. (Nakai, Y.)

  17. Inquiry relating to modifications of reactor installation in Genkai No. 1 and 2 nuclear power plants of Kyushu Electric Power Company, Inc

    International Nuclear Information System (INIS)

    1979-01-01

    Application was made to the Minister of International Trade and Industry for the license relating to the modifications of reactor installation in the Genkai No. 1 and 2 nuclear power plants, Kyushu Electric Power Company, Inc., on February 27, 1979, from the president of the company. After the safety evaluation was finished by the Ministry of International Trade and Industry, inquiry was conducted to the head of the Atomic Energy Safety Commission (AESC) on June 15, 1979 from the Minister of International Trade and Industry. The investigation and discussion were commenced by the AESC on June 19, 1979. The modifications of the reactor installation are the increase of new fuel storage capacity from about 1/3 to about 2/3 of in-core fuel for each plant, the new establishment of a miscellaneous solid waste incinerator which is common to both plants, and the enlargement of a solid waste storage which is also common to both plants. The contents of the safety examination for each item written above are presented. The prevention of criticality is carefully practiced for the new fuel storage by putting fuel assemblies in stainless steel can type racks and locating the fuel assemblies at the proper distance. The miscellaneous solid waste incinerator building is designed as the B class aseismatic structure and also as the controlled area with adequate shielding and ventilating facilities. The decontamination factor of the incinerator facility is more than 10 5 , and the necessary monitoring system is provided in the building. Concerning the solid waste storage, the additional storage area is about 1600 m 2 , and the storage capacity is about ten years quantity. This building is designed as the B class aseismatic structure. (Nakai, Y.)

  18. Exxon Nuclear Company WREM-based generic PWR ECCS evaluation model. Appendix C to Volume II. Yankee Rowe example problem

    International Nuclear Information System (INIS)

    1975-01-01

    Core 12, of the Yankee Rowe (YR), plant is to be licensed with the Exxon Nuclear Co. PWR Evaluation Model. This appendix presents methodology and results of an example calculation for the YR plant using the ENC Evaluation Model. This example problem is for the double-ended guillotine cold leg break with a discharge coefficient of 0.6 assuming loss of one emergency diesel. The NSSS supplier has determined this case to give the highest peak cladding temperature (PCT) for Core 11. The YR example problem was performed to determine the maximum acceptable local peak heating rate (Kw/ft). The blowdown was performed with beginning-of-cycle (BOC) ENC fuel at full power with the hot assembly power corresponding to the design peak rod heating rate of 12.9 Kw/ft. The HOT CHANNEL, TOODEE2, and RELAP4-FLOOD runs were made at several reduced hot assembly radial peaks, holding axial peaking constant, until an acceptable PCT was achieved. This procedure results in a PCT of 1834 0 F at a reduced peak linear heating rate of 10.5 Kw/ft for the ENC fuel at BOC. (auth)

  19. 76 FR 46854 - Hewlett Packard Company, Imaging and Printing Group, World Wide Product Data Management...

    Science.gov (United States)

    2011-08-03

    ..., Imaging and Printing Group, World Wide Product Data Management Operations, Including On-Site Leased... Company, Imaging and Printing Group, World Wide Products Data Management Operations, Boise, Idaho and Fort... of Hewlett Packard Company, Imaging and Printing Group, World Wide Product Data Management Operations...

  20. Safety evaluation report related to the operation of Grand Gulf Nuclear Station, Units 1 and 2. Dockets Nos. 50-416 and 50-417, Mississippi Power and Light Company; Middle South Energy, Inc., South Mississippi Electric Power Association

    International Nuclear Information System (INIS)

    1982-06-01

    Supplement 2 to the Safety Evaluation Report for Mississippi Power and Light Company, et. al, joint application for licenses to operate the Grand Gulf Nuclear Station, Units 1 and 2, located on the east bank of the Mississippi River near Port Gibson, in Claiborne County, Mississippi, has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement reports the status of certain items that had not been resolved at the time of publication of the Safety Evaluation Report

  1. Idaho CERCLA Disposal Facility Complex Waste Acceptance Criteria

    Energy Technology Data Exchange (ETDEWEB)

    W. Mahlon Heileson

    2006-10-01

    The Idaho Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Disposal Facility (ICDF) has been designed to accept CERCLA waste generated within the Idaho National Laboratory. Hazardous, mixed, low-level, and Toxic Substance Control Act waste will be accepted for disposal at the ICDF. The purpose of this document is to provide criteria for the quantities of radioactive and/or hazardous constituents allowable in waste streams designated for disposal at ICDF. This ICDF Complex Waste Acceptance Criteria is divided into four section: (1) ICDF Complex; (2) Landfill; (3) Evaporation Pond: and (4) Staging, Storage, Sizing, and Treatment Facility (SSSTF). The ICDF Complex section contains the compliance details, which are the same for all areas of the ICDF. Corresponding sections contain details specific to the landfill, evaporation pond, and the SSSTF. This document specifies chemical and radiological constituent acceptance criteria for waste that will be disposed of at ICDF. Compliance with the requirements of this document ensures protection of human health and the environment, including the Snake River Plain Aquifer. Waste placed in the ICDF landfill and evaporation pond must not cause groundwater in the Snake River Plain Aquifer to exceed maximum contaminant levels, a hazard index of 1, or 10-4 cumulative risk levels. The defined waste acceptance criteria concentrations are compared to the design inventory concentrations. The purpose of this comparison is to show that there is an acceptable uncertainty margin based on the actual constituent concentrations anticipated for disposal at the ICDF. Implementation of this Waste Acceptance Criteria document will ensure compliance with the Final Report of Decision for the Idaho Nuclear Technology and Engineering Center, Operable Unit 3-13. For waste to be received, it must meet the waste acceptance criteria for the specific disposal/treatment unit (on-Site or off-Site) for which it is destined.

  2. Operation of the Millstone Nuclear Power Station, Unit No. 3 (NRC Docket No. 50-423) Northeast Nuclear Energy Company et. al., Waterford, New London County, Connecticut

    International Nuclear Information System (INIS)

    1984-07-01

    A draft version of the environmental impact statement (EPA No. 840331D) concerns the proposal to issue an operating license for Unit 3 of the Millstone Nuclear Power Station on Connecticut. The plant would use a four-loop pressurized water reactor to produce up to 3579 MW of thermal energy and a calculated maximum electric output of 1209 MW of electric power. A new line would require clearing about 350 acres. Positive impacts include the addition of new capacity, which would benefit the area economically and employment opportunities. Negative impacts include the loss of some winter flounder, which would be minimized by a fish return system, and some increases in the concentration of chemical constituents that would enter Long Island Sound. Policies relating to coastal areas, water pollution, and reactor regulation provide a legal mandate for the impact statement

  3. A forward looking company

    International Nuclear Information System (INIS)

    Christian, David A.

    2004-01-01

    The article is an excerpt of an interview with David A. Christian, Senior Vice President-Nuclear and Chief Nuclear Officer, Dominion Generation conducted at NEI's Nuclear Energy Assembly in New Orleans, Louisiana on 13 May 2004. It highlights the company's energy diversity, and in particular, activities related to early-site permits and possible future plans for nuclear power plant development in the U.S. The interview touches on questions related to the Consortium (composed of Dominion, AECL Technologies, the U.S. subsidiary of AECL, Hatachi America and Bechtel Power Corp.) and the DOE financial support involved (approximately 50%) along with comments related to job impacts, energy security and climate change impacts, human resource issues (particularly about getting high school students interested in jobs related to the nuclear industry) and public policy. The interview ends with a discussion of investment interest and the state of standardization in the industry

  4. Assessing the Idaho Transportation Department's customer service performance.

    Science.gov (United States)

    2011-10-23

    This report assesses customer satisfaction with the Idaho Transportation Department. It also compares and contrasts the results of customer satisfaction surveys conducted for the Idaho Transportation Department with the results from other state trans...

  5. Growing the Idaho economy : moving into the future.

    Science.gov (United States)

    2010-08-13

    A report on transportation and the possible future economy of the State of Idaho from 2010 to 2030, including : current assets to leverage, driving forces shaping the future, long-range economic opportunities for Idaho including : four future scenari...

  6. Safety analysis report for the mixed waste storage facility and portable storage units at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Peatross, R.

    1997-01-01

    The Mixed Waste Storage Facility (MWSF) including the Portable Storage Units (PSUs) is a government-owned contractor-operated facility located at the Idaho National Engineering Laboratory (INEL). Lockheed Martin Idaho Technologies Company (LMITCO) is the current operating contractor and facility Architect/Engineer as of September 1996. The operating contractor is referred to as open-quotes the Companyclose quotes or open-quotes Companyclose quotes throughout this document. Oversight of MWSF is provided by the Department of Energy Idaho Operations Office (DOE-ID). The MWSF is located in the Power Burst Facility (PBF) Waste Reduction Operations Complex (WROC) Area, approximately 10.6 km (6.6 mi) from the southern INEL boundary and 4 km (2.5 mi) from U.S. Highway 20

  7. Price-Anderson Nuclear Safety Enforcement Program. 1997 annual report

    International Nuclear Information System (INIS)

    1998-01-01

    This report summarizes activities in the Department of Energy's Price-Anderson Amendments Act (PAAA) Enforcement Program in calendar year 1997 and highlights improvements planned for 1998. The DOE Enforcement Program involves the Office of Enforcement and Investigation in the DOE Headquarters Office of Environment, Safety and Health, as well as numerous PAAA Coordinators and technical advisors in DOE Field and Program Offices. The DOE Enforcement Program issued 13 Notices of Violation (NOV's) in 1997 for cases involving significant or potentially significant nuclear safety violations. Six of these included civil penalties totaling $440,000. Highlights of these actions include: (1) Brookhaven National Laboratory Radiological Control Violations / Associated Universities, Inc.; (2) Bioassay Program Violations at Mound / EG ampersand G, Inc.; (3) Savannah River Crane Operator Uptake / Westinghouse Savannah River Company; (4) Waste Calciner Worker Uptake / Lockheed-Martin Idaho Technologies Company; and (5) Reactor Scram and Records Destruction at Sandia / Sandia Corporation (Lockheed-Martin). Sandia / Sandia Corporation (Lockheed-Martin)

  8. Operational and Environmental Efficiencies of Japanese Electric Power Companies from 2003 to 2015: Influence of Market Reform and Fukushima Nuclear Power Accident

    Directory of Open Access Journals (Sweden)

    Mika Goto

    2017-01-01

    Full Text Available This study measures operational and environmental efficiencies of nine incumbent electric power companies (EPCos in Japan and examines an influence of market reform and Fukushima nuclear power plant accident on efficiencies using a data set from 2003 to 2015. This study applies output-oriented radial data envelopment analysis (DEA model to the measurement of efficiencies. Three inputs and three desirable outputs are used for the measurement of operational efficiency, and one undesirable output besides inputs and desirable outputs is used to measure environmental efficiency. EPCos produce not only desirable output, for example, electricity, but also undesirable output, for example, CO2, for their operations. For the measurement of environmental efficiency, this study uses a unique DEA model that assumes occurrence of ecotechnology innovation. The results reveal that environmental efficiency of EPCos is mostly invariant over the period of this study, while operational efficiency decreases in the same period. In addition, the results present that Japanese EPCos make efforts to reduce CO2 emissions by promoting ecotechnology innovation. The Kruskal–Wallis rank sum test indicates differences in operational and environmental efficiencies among EPCos. Such performance differences might become larger as market liberalization advances, which could lead to further structural changes of the industry.

  9. 'Passive fire protection in nuclear power plants' - German technologies of the company svt Brandschutz in future as well in Korean NPPs? -

    International Nuclear Information System (INIS)

    Bremer, Joerg; Kim, Duill; Wendt, Ruediger

    2002-01-01

    Fires in NPPs are unfortunately not avoidable and to consider during the planning and operation period of the plants. The multitude of combustible materials which are used especially cables, oils and other building materials describe a potential source of danger. In Germany recently a new planning guideline for the fire protection field in NPPs has been adopted: the nuclear guideline KTA 1401. This document certainly is one of the most progressive guidelines for the fire protection field and has united · structural engineering elements of fire protection · electrotechnical and machine components · as well as questions of fire alarm and organisation measures. Passive and active fire protection measures are explained and layed down in their complexity within this document. Our group of companies has realised quit a lot of fire protection projects in Europe during the last years, especially within retrofitting measures for NPPs in Germany, Switzerland, Russia, the Ukraine and Lithuania, the Czech and Slovak Republic as well as within decommissioning projects of NPPs. We have carried out international fire protection projects of the EBRD, London, and within the framework of TACIS projects of the European Commission, i. a. linked with the working out of fire protection analyses for NPPs realised in close co-operation with the Germanischer Lloyd, Hamburg. We especially have wide experiences in improving the fire protection of cable installations where a 100% separation of the different safety systems is not any longer possible

  10. 131I concentrations in air, milk and antelope thyroids in southeastern Idaho

    International Nuclear Information System (INIS)

    Markham, O.D.; Halford, D.K.; Bihl, D.E.

    1980-01-01

    Iodine-131 concentrations were determined in air, milk, and antelope (Antilocapra americana) thyroids from southeastern Idaho during 1972-77. Samples were collected in the vicinity of the Idaho National Engineering Laboratory Site which has 17 operating nuclear reactors, a fuel reprocessing plant, and a nuclear waste management facility. Samples were also collected from control areas. During the study, fallout occurred from five People's Republic of China above-ground nuclear weapon detonations. All 131 I detected in air and milk samples was attributed to fallout from the Chinese nuclear tests. 131 I was detected in low-volume air samples following only one of the five detonations while 131 I was detected in milk following four of the detonations. 131 I occurred in antelope thyroids during all five of the fallout periods and following at least one atmospheric release from facilities at the Idaho National Engineering Laboratory Site. Thyroids were the most sensitive indicators of 131 I in the environment followed by milk and then air. Maximum concentrations in thyroids, milk, and air were 400, 20 and 4 times higher respectively than their respective detection limits. (author)

  11. Idaho National Laboratory Cultural Resource Management Plan

    Energy Technology Data Exchange (ETDEWEB)

    Julie Braun Williams

    2013-02-01

    As a federal agency, the U.S. Department of Energy has been directed by Congress, the U.S. president, and the American public to provide leadership in the preservation of prehistoric, historic, and other cultural resources on the lands it administers. This mandate to preserve cultural resources in a spirit of stewardship for the future is outlined in various federal preservation laws, regulations, and guidelines such as the National Historic Preservation Act, the Archaeological Resources Protection Act, and the National Environmental Policy Act. The purpose of this Cultural Resource Management Plan is to describe how the Department of Energy, Idaho Operations Office will meet these responsibilities at Idaho National Laboratory in southeastern Idaho. The Idaho National Laboratory is home to a wide variety of important cultural resources representing at least 13,500 years of human occupation in the southeastern Idaho area. These resources are nonrenewable, bear valuable physical and intangible legacies, and yield important information about the past, present, and perhaps the future. There are special challenges associated with balancing the preservation of these sites with the management and ongoing operation of an active scientific laboratory. The Department of Energy, Idaho Operations Office is committed to a cultural resource management program that accepts these challenges in a manner reflecting both the spirit and intent of the legislative mandates. This document is designed for multiple uses and is intended to be flexible and responsive to future changes in law or mission. Document flexibility and responsiveness will be assured through regular reviews and as-needed updates. Document content includes summaries of Laboratory cultural resource philosophy and overall Department of Energy policy; brief contextual overviews of Laboratory missions, environment, and cultural history; and an overview of cultural resource management practices. A series of appendices

  12. Idaho National Engineering and Environmental Laboratory site environmental report for calendar year 1997

    Energy Technology Data Exchange (ETDEWEB)

    Evans, R.B.; Brooks, R.W.; Roush, D.; Martin, D.B. [Environmental Science and Research Foundation, Idaho Falls, ID (United States); Lantz, B.S. [Dept. of Energy, Idaho Falls, ID (United States). Idaho Operations Office

    1998-08-01

    To verify that exposures resulting from operations at Department of Energy (DOE) nuclear facilities remain very small, each site at which nuclear activities are conducted operates an environmental surveillance program to monitor the air, water and any other pathway whereby radionuclides from operations might conceivably reach workers and members of the public. Environmental surveillance and monitoring results are reported annually to the DOE-Headquarters. This report presents a compilation of data collected in 1997 for the routine environmental surveillance programs conducted on and around the Idaho National Engineering and Environmental Laboratory (INEEL). The results of the various monitoring programs for 1997 indicated that radioactivity from the INEEL operations could generally not be distinguished from worldwide fallout and natural radioactivity in the region surrounding the INEEL. Although some radioactive materials were discharged during INEEL operations, concentrations in the offsite environment and doses to the surrounding population were far less than state of Idaho and federal health protection guidelines.

  13. Idaho National Engineering and Environmental Laboratory site environmental report for calendar year 1997

    International Nuclear Information System (INIS)

    Evans, R.B.; Brooks, R.W.; Roush, D.; Martin, D.B.; Lantz, B.S.

    1998-08-01

    To verify that exposures resulting from operations at Department of Energy (DOE) nuclear facilities remain very small, each site at which nuclear activities are conducted operates an environmental surveillance program to monitor the air, water and any other pathway whereby radionuclides from operations might conceivably reach workers and members of the public. Environmental surveillance and monitoring results are reported annually to the DOE-Headquarters. This report presents a compilation of data collected in 1997 for the routine environmental surveillance programs conducted on and around the Idaho National Engineering and Environmental Laboratory (INEEL). The results of the various monitoring programs for 1997 indicated that radioactivity from the INEEL operations could generally not be distinguished from worldwide fallout and natural radioactivity in the region surrounding the INEEL. Although some radioactive materials were discharged during INEEL operations, concentrations in the offsite environment and doses to the surrounding population were far less than state of Idaho and federal health protection guidelines

  14. 78 FR 68466 - BLM Director's Response to the Idaho Governor's Appeal of the BLM Idaho State Director's Governor...

    Science.gov (United States)

    2013-11-14

    ... Bureau of Land Management (BLM) is publishing this notice to explain why the BLM Director is denying the...] BLM Director's Response to the Idaho Governor's Appeal of the BLM Idaho State Director's Governor's... (Finding) to the BLM Idaho State Director (State Director). The State Director determined the Governor's...

  15. 1996 LMITCO environmental monitoring program report for the Idaho National Engineering and Environmental Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-09-01

    This report describes the calendar year 1996 environmental surveillance and compliance monitoring activities of the Lockheed Martin Idaho Technologies Company Environmental Monitoring Program performed at the Idaho National Engineering and Environmental Laboratory (INEEL). Results of sampling performed by the Radiological Environmental Surveillance, Site Environmental Surveillance, Drinking Water, Effluent Monitoring, Storm Water Monitoring, Groundwater Monitoring, and Special Request Monitoring Programs are included in this report. The primary purposes of the surveillance and monitoring activities are to evaluate environmental conditions, to provide and interpret data, to verify compliance with applicable regulations or standards, and to ensure protection of human health and the environment. This report compares 1996 data with program-specific regulatory guidelines and past data to evaluate trends.

  16. 1996 LMITCO environmental monitoring program report for the Idaho National Engineering and Environmental Laboratory

    International Nuclear Information System (INIS)

    1997-09-01

    This report describes the calendar year 1996 environmental surveillance and compliance monitoring activities of the Lockheed Martin Idaho Technologies Company Environmental Monitoring Program performed at the Idaho National Engineering and Environmental Laboratory (INEEL). Results of sampling performed by the Radiological Environmental Surveillance, Site Environmental Surveillance, Drinking Water, Effluent Monitoring, Storm Water Monitoring, Groundwater Monitoring, and Special Request Monitoring Programs are included in this report. The primary purposes of the surveillance and monitoring activities are to evaluate environmental conditions, to provide and interpret data, to verify compliance with applicable regulations or standards, and to ensure protection of human health and the environment. This report compares 1996 data with program-specific regulatory guidelines and past data to evaluate trends

  17. Idaho National Engineering Laboratory site environmental report for calendar year 1995

    International Nuclear Information System (INIS)

    Mitchell, R.G.; Peterson, D.; Hoff, D.L.

    1996-08-01

    This report presents a compilation of data collected in 1995 for the routine environmental surveillance programs conducted on and around the Idaho National Engineering Laboratory (INEL). During 1995, the offsite surveillance program was conducted by the Environmental Science and Research Foundation. Onsite surveillance was performed by Lockheed Idaho Technologies Company (LITCO). Ground-water monitoring, both on and offsite, was performed by the US Geological Survey (USGS). This report also presents summaries of facility effluent monitoring data collected by INEL contractors. This report, prepared in accordance with the requirements in DOE Order 5400.1, is not intended to cover the numerous special environmental research programs being conducted at the INEL by the Foundation, LITCO, USGS, and others

  18. Idaho National Engineering Laboratory site environmental report for calendar year 1995

    Energy Technology Data Exchange (ETDEWEB)

    Mitchell, R.G.; Peterson, D.; Hoff, D.L.

    1996-08-01

    This report presents a compilation of data collected in 1995 for the routine environmental surveillance programs conducted on and around the Idaho National Engineering Laboratory (INEL). During 1995, the offsite surveillance program was conducted by the Environmental Science and Research Foundation. Onsite surveillance was performed by Lockheed Idaho Technologies Company (LITCO). Ground-water monitoring, both on and offsite, was performed by the US Geological Survey (USGS). This report also presents summaries of facility effluent monitoring data collected by INEL contractors. This report, prepared in accordance with the requirements in DOE Order 5400.1, is not intended to cover the numerous special environmental research programs being conducted at the INEL by the Foundation, LITCO, USGS, and others.

  19. North Idaho E. coli Infections Linked to Raw Clover Sprouts > Idaho

    Science.gov (United States)

    About Establishing Legal Fatherhood Genetic Testing Ending Services Fees for Services Child Support and Children's Special Health Program Genetic/Metabolic Services Genetic Condition Information Health Care Healthcare Associated Infections Antibiotic Resistance Epidemiology Idaho Disease Bulletin Data and

  20. Contribution of service companies

    International Nuclear Information System (INIS)

    Sole, L. M.; Cortes, A.

    2002-01-01

    The most influential aspect when choosing the model of contract between Client and Contractor relapses into the maturity reached by both parts. The service supplier will have to show his competence with his resume, not only technical, but also of actual actions concerning availability reliability, maintainability, security, environment and costs. That maturity may have been the reason why most of the service companies, of national scope, that carry out maintenance of nuclear power stations electricity and instrumentation nowadays, are present from the assembly and implementation phases of these nuclear power stations. (Author)

  1. Idaho National Engineering Laboratory irradiation facilities and their applications

    International Nuclear Information System (INIS)

    Gupta, V.P.; Herring, J.S.; Korenke, R.E.; Harker, Y.D.

    1986-05-01

    Although there is a growing need for neutron and gamma irradiation by governmental and industrial organizations in the United States and in other countries, the number of facilities providing such irradiations are limited. At the Idaho National Engineering Laboratory, there are several unique irradiation facilities producing high neutron and gamma radiation environments. These facilities could be readily used for nuclear research, materials testing, radiation hardening studies on electronic components/circuitry and sensors, and production of neutron transmutation doped (NTD) silicon and special radioisotopes. In addition, a neutron radiography unit, suitable for examining irradiated materials and assemblies, is also available. This report provides a description of the irradiation facilities and the neutron radiography unit as well as examples of their unique applications

  2. ICPP [Idaho Chemical Processing Plant] environmental monitoring report, CY-1988

    International Nuclear Information System (INIS)

    Krivanek, K.R.

    1989-08-01

    Summarized in this report are the data collected through Environmental Monitoring programs conducted at the Idaho Chemical Processing Plant (ICPP) by the Environmental Engineering (EE) Section of the Nuclear and Industrial Safety (N and IS) Department. The ICPP is responsible for complying with all applicable Federal, State, Local and DOE Rules, Regulations and Orders. Radiological effluent and emissions are regulated by the DOE. The Environmental Protection Agency (EPA) regulates all nonradiological waste resulting from the ICPP operations including all airborne, liquid, and solid waste. The EE subsection completed a Quality Assurance (QA) Plan for Environmental Monitoring activities during the third quarter of 1986. QA activities have resulted in the ICPP's implementation of the Environmental Protection Agency rules and guidelines pertaining to the collection, analyses, and reporting of environmentally related samples. Where no approved methods for analyses existed for radionuclides, currently used methods were submitted for the EPA approval. 33 figs., 14 tabs

  3. Idaho National Laboratory Cultural Resource Monitoring Report for FY 2009

    Energy Technology Data Exchange (ETDEWEB)

    Brenda R. Pace; Julie B. Braun

    2009-10-01

    This report describes the cultural resource monitoring activities of the Idaho National Laboratory’s (INL) Cultural Resource Management (CRM) Office during fiscal year 2009 (FY 2009). Throughout the year, thirty-eight cultural resource localities were revisited including: two locations with Native American human remains, one of which is a cave, two additional caves, twenty-two prehistoric archaeological sites, six historic homesteads, two historic stage stations, two historic trails, and two nuclear resources, including Experimental Breeder Reactor-I, which is a designated National Historic Landmark. Several INL project areas were also monitored in FY 2009 to assess project compliance with cultural resource recommendations and monitor the effects of ongoing project activities. Although impacts were documented at a few locations and trespassing citations were issued in one instance, no significant adverse effects that would threaten the National Register eligibility of any resources were observed. Monitoring also demonstrated that several INL projects generally remain in compliance with recommendations to protect cultural resources.

  4. Idaho Batholith Study Area Isostatic Gravity Grid

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — A 2 kilometer isostatic gravity grid for the Idaho batholith study area. Number of columns is 331 and number of rows is 285. The order of the data is from the lower...

  5. Performance evaluation of chip seals in Idaho.

    Science.gov (United States)

    2010-08-01

    The intent of this research project is to identify a wide variety of parameters that influence the performance of pavements treated via chip seals within the State of Idaho. Chip sealing is currently one of the most popular methods of maintenance for...

  6. Idaho Batholith Study Area Bouguer Gravity Grid

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — A 2 kilometer Bouguer gravity anomaly grid for the Idaho batholith study area. Number of columns is 331 and number of rows is 285. The order of the data is from the...

  7. Idaho Batholith Study Area Density Grid

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — A 2 kilometer terrace-density grid for the Idaho batholith study area. Number of columns is 331 and number of rows is 285. The order of the data is from the lower...

  8. Company analysis

    DEFF Research Database (Denmark)

    Jenster, Per V.; Hussey, David

    This volume looks at the company appraisal as a whole, examining the continuing need to appraise companies as part of the continuing strategy process. Building from a sound basis of theory, the text aims to be practical and to give guidance to senior managers and others involved in the strategy...... process. It is thus a book primarily aimed at managers, but should also be useful for MBA students undertaking strategy assignments It provides helpful, practical guidance and identifies weaknesses of traditional methods. It also presents a variety of tools which may be used in the appraisal process...

  9. Project for the adaptation of the Instituto Nacional de Investigaciones Nucleares (ININ) to work as companies incubator, and the business plan as support device in the achievement of successful base technological companies; Proyecto para la adecuacion del Instituto Nacional de Investigaciones Nucleares (ININ) para trabajar como incubadora de empresas y el plan de negocios como instrumento de apoyo en el logro de empresas de base tecnologicas exitosas

    Energy Technology Data Exchange (ETDEWEB)

    Rubio A, C R

    1996-09-01

    The purpose of this project is to study an option to reduce technology dependence by taking advantage of the technology based companies generated by the organisms called `Companies Incubators`. The first point given, is an introduction about incubation applied to national companies and the experiences had about them. There are also suggested some indicators which can be used to develop the incubator tasks. Once it has been defined the topic about incubation in the country, it is provided information about the items determining the company performance within an incubator. In order to do this, it is shown the way the Instituto Nacional de Investigaciones Nucleares can provide not only its facilities but also qualified personnel working for them. Thus it is given a scheme along with a brief organization description and key personnel for the incubator, stating the functions and responsibilities per each one of the persons who are part of the project direction and leading. The bases for the incubator are stated, as well as the requirements to start-up a company being supported by a company incubator. The key points to have a succesful development for the incubator are: the service it can give as well as the guidelines for companies entrance, which are classified into two sorts of customers, external and internal. It is also included a market research about the main product derived from creating a company incubator, as well as the sub-products, the market area, this is directed to the people who will benefit from it, the supply and demand involved with ININ. The main tool used was Business Plan, which defines its importance within the organization and activities guide, it is also included the Business Plan structure.

  10. Radiation risk perception by radiation professionals. Survey results just before the radiological accident at the Tokyo Electric Power Company Fukushima Daiichi nuclear power plant

    International Nuclear Information System (INIS)

    Miura, Miwa; Hayashida, Rika; Takao, Hideaki; Matsuda, Naoki; Ono, Koji

    2013-01-01

    From October to December 2010, just before the radiological accident at the Tokyo Electric Power Company Fukushima Daiichi nuclear power plant, 71 radiation professionals belonging to the radiation facilities in Japan were asked what they consider as a 'safe' dose of radiation for themselves, their spouse, parents, children, brothers and friends. Although the 'safe' dose varied widely from less than 1 mSv/y to higher than 100 mSv/y, the average dose was 35.6 mSv/y that was around the middle point between the exposure dose limits for annual average (20 mSv/y) and for any single year (50 mSv/y). Similar results were obtained from another surveys for the members of Japan Radioisotope Association (36.9 mSv/y) and for the Oita Prefectural Hospital (36.8 mSv/y). Among the family members and friends, the minimum average 'safe' dose was 8.5 mSv/y for children, to whom 50% of responders claimed the 'safe' dose less than 1 mSv. Gender, age and specialty of the responder also affected the 'safe' dose. These findings suggest that the perception of radiation risk varies widely and that the legal exposure dose limit derived from the regulatory science may act as an anchor of safety even in radiation professionals. The different level of risk perception for different target groups in radiation professionals appears similar to those in non-professional whole population. The gap between these characteristics of real radiation professionals and the generally accepted picture of radiation professionals might take a part in a state of confusion after the radiological accident. (author)

  11. Idaho National Laboratory Cultural Resource Management Plan

    Energy Technology Data Exchange (ETDEWEB)

    Lowrey, Diana Lee

    2009-02-01

    As a federal agency, the U.S. Department of Energy has been directed by Congress, the U.S. president, and the American public to provide leadership in the preservation of prehistoric, historic, and other cultural resources on the lands it administers. This mandate to preserve cultural resources in a spirit of stewardship for the future is outlined in various federal preservation laws, regulations, and guidelines such as the National Historic Preservation Act, the Archaeological Resources Protection Act, and the National Environmental Policy Act. The purpose of this Cultural Resource Management Plan is to describe how the Department of Energy, Idaho Operations Office will meet these responsibilities at the Idaho National Laboratory. This Laboratory, which is located in southeastern Idaho, is home to a wide variety of important cultural resources representing at least 13,500 years of human occupation in the southeastern Idaho area. These resources are nonrenewable; bear valuable physical and intangible legacies; and yield important information about the past, present, and perhaps the future. There are special challenges associated with balancing the preservation of these sites with the management and ongoing operation of an active scientific laboratory. The Department of Energy, Idaho Operations Office is committed to a cultural resource management program that accepts these challenges in a manner reflecting both the spirit and intent of the legislative mandates. This document is designed for multiple uses and is intended to be flexible and responsive to future changes in law or mission. Document flexibility and responsiveness will be assured through annual reviews and as-needed updates. Document content includes summaries of Laboratory cultural resource philosophy and overall Department of Energy policy; brief contextual overviews of Laboratory missions, environment, and cultural history; and an overview of cultural resource management practices. A series of

  12. Idaho National Laboratory Cultural Resource Management Plan

    Energy Technology Data Exchange (ETDEWEB)

    Lowrey, Diana Lee

    2011-02-01

    As a federal agency, the U.S. Department of Energy has been directed by Congress, the U.S. president, and the American public to provide leadership in the preservation of prehistoric, historic, and other cultural resources on the lands it administers. This mandate to preserve cultural resources in a spirit of stewardship for the future is outlined in various federal preservation laws, regulations, and guidelines such as the National Historic Preservation Act, the Archaeological Resources Protection Act, and the National Environmental Policy Act. The purpose of this Cultural Resource Management Plan is to describe how the Department of Energy, Idaho Operations Office will meet these responsibilities at the Idaho National Laboratory. This Laboratory, which is located in southeastern Idaho, is home to a wide variety of important cultural resources representing at least 13,500 years of human occupation in the southeastern Idaho area. These resources are nonrenewable; bear valuable physical and intangible legacies; and yield important information about the past, present, and perhaps the future. There are special challenges associated with balancing the preservation of these sites with the management and ongoing operation of an active scientific laboratory. The Department of Energy, Idaho Operations Office is committed to a cultural resource management program that accepts these challenges in a manner reflecting both the spirit and intent of the legislative mandates. This document is designed for multiple uses and is intended to be flexible and responsive to future changes in law or mission. Document flexibility and responsiveness will be assured through annual reviews and as-needed updates. Document content includes summaries of Laboratory cultural resource philosophy and overall Department of Energy policy; brief contextual overviews of Laboratory missions, environment, and cultural history; and an overview of cultural resource management practices. A series of

  13. Department of Energy, highly enriched uranium ES ampersand H vulnerability assessment, Idaho National Engineering Laboratory site assessment team report

    International Nuclear Information System (INIS)

    1996-01-01

    In accordance with the February 22, 1996 directive issued by Secretary of Energy O'Leary on the Vulnerability Assessment of Highly Enriched Uranium (HEU) Storage, the Idaho National Engineering Laboratory conducted an assessment of the site's HEU holdings and any associated vulnerabilities. The assessment was conducted between April 25 and May 24, 1996. The scope of this assessment, as defined in the Assessment Plan, included all HEU, and any spent fuel not evaluated in the Spent Fuel Vulnerability Assessment. Addressed in this assessment were all of the holdings at the Idaho National Engineering Laboratory (INEL) except any located at Argonne National Laboratory-West (ANL-W) and the Naval Reactors Facility. Excluded from the assessment were those HEU holdings previously assessed in the Idaho National Engineering Laboratory Spent Nuclear Fuel Inventory and Vulnerability Site Assessment Report and any HEU holdings evaluated in the Plutonium Vulnerability Assessment Report

  14. The CEA-Industrie Group of Companies

    International Nuclear Information System (INIS)

    1988-01-01

    The 1988 financial and technological status of the CEA-Industry Group of Companies is summarized. The activities, technological innovations, and areas of development perspectives of the CEA-Industry Group of Companies, chiefly concentrated in fields relating to nuclear energy, are described. The principal business sectors of the group involve nuclear fuel cycle, nuclear plants and maintenance, computer applications and life science. Some activities of the group are extended to management, construction and financial fields

  15. Mission Need Statement for the Idaho National Laboratory Remote-Handled Low-Level Waste Disposal Project

    International Nuclear Information System (INIS)

    Harvego, Lisa

    2009-01-01

    The Idaho National Laboratory proposes to establish replacement remote-handled low-level waste disposal capability to meet Nuclear Energy and Naval Reactors mission-critical, remote-handled low-level waste disposal needs beyond planned cessation of existing disposal capability at the end of Fiscal Year 2015. Remote-handled low-level waste is generated from nuclear programs conducted at the Idaho National Laboratory, including spent nuclear fuel handling and operations at the Naval Reactors Facility and operations at the Advanced Test Reactor. Remote-handled low-level waste also will be generated by new programs and from segregation and treatment (as necessary) of remote-handled scrap and waste currently stored in the Radioactive Scrap and Waste Facility at the Materials and Fuels Complex. Replacement disposal capability must be in place by Fiscal Year 2016 to support uninterrupted Idaho operations. This mission need statement provides the basis for the laboratory's recommendation to the Department of Energy to proceed with establishing the replacement remote-handled low-level waste disposal capability, project assumptions and constraints, and preliminary cost and schedule information for developing the proposed capability. Without continued remote-handled low-level waste disposal capability, Department of Energy missions at the Idaho National Laboratory would be jeopardized, including operations at the Naval Reactors Facility that are critical to effective execution of the Naval Nuclear Propulsion Program and national security. Remote-handled low-level waste disposal capability is also critical to the Department of Energy's ability to meet obligations with the State of Idaho

  16. Mission Need Statement for the Idaho National Laboratory Remote-Handled Low-Level Waste Disposal Project

    Energy Technology Data Exchange (ETDEWEB)

    Lisa Harvego

    2009-06-01

    The Idaho National Laboratory proposes to establish replacement remote-handled low-level waste disposal capability to meet Nuclear Energy and Naval Reactors mission-critical, remote-handled low-level waste disposal needs beyond planned cessation of existing disposal capability at the end of Fiscal Year 2015. Remote-handled low-level waste is generated from nuclear programs conducted at the Idaho National Laboratory, including spent nuclear fuel handling and operations at the Naval Reactors Facility and operations at the Advanced Test Reactor. Remote-handled low-level waste also will be generated by new programs and from segregation and treatment (as necessary) of remote-handled scrap and waste currently stored in the Radioactive Scrap and Waste Facility at the Materials and Fuels Complex. Replacement disposal capability must be in place by Fiscal Year 2016 to support uninterrupted Idaho operations. This mission need statement provides the basis for the laboratory’s recommendation to the Department of Energy to proceed with establishing the replacement remote-handled low-level waste disposal capability, project assumptions and constraints, and preliminary cost and schedule information for developing the proposed capability. Without continued remote-handled low-level waste disposal capability, Department of Energy missions at the Idaho National Laboratory would be jeopardized, including operations at the Naval Reactors Facility that are critical to effective execution of the Naval Nuclear Propulsion Program and national security. Remote-handled low-level waste disposal capability is also critical to the Department of Energy’s ability to meet obligations with the State of Idaho.

  17. Safety evaluation report related to the operation of Catawba Nuclear Station, Units 1 and 2. Docket Nos. 50-413 and 50-414, Duke Power Company, et al

    International Nuclear Information System (INIS)

    1983-02-01

    The Safety Evaluation Report for the application filed by Duke Power Company, North Carolina Municipal Power Agency Number 1, North Carolina Electric Membership Corporation, and Saluda River Electric Cooperative, Inc. as applicants and owners, for licenses to operate the Catawba Nuclear Station, Units 1 and 2 (Docket Nos. 50-413 and 50-414), has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located in York County, South Carolina, approximately 9.6 km (6 mi) north of Rock Hill and adjacent to Lake Wylie. Subject to favorable resolution of the items discussed in this report, the staff concludes that the facility can be operated by the applicant without endangering the health and safety of the public

  18. Fuel buyers guide: company data

    International Nuclear Information System (INIS)

    Anon.

    1991-01-01

    Four major listings relating to nuclear fuel services are provided. 1. A fuel buyer's guide listing companies under alphabetical order of country and giving addresses and an indication of the services offered. 2. A fuel buyers guide classifying companies in alphabetical order of the services offered. 3. A fuel and front end facility listing subdivided into companies involved in: uranium ore processing; uranium refining and conversion; enrichment; fuel fabrication; heavy water production; zirconium metal production; and zirconium tube production. 4. A fuel and front end facilities listing giving operators' addresses under alphabetical order of country. (UK)

  19. Development of waste chargeback systems at the Idaho National Engineering Laboratory (INEL)

    International Nuclear Information System (INIS)

    Piscitella, R.R.

    1996-02-01

    Chargeback systems have been discussed (and cussed), tried, modified, and in some cases, successfully implemented in the DOE complex over the years. With the current emphasis on ''Doing business like a private company,'' there has been renewed interest at the Idaho National Engineering Laboratory (INEL) in implementing chargeback systems for waste management activities. The most recent activities relating to chargeback at the INEL started the summer of 1995 with direction from waste operations management to develop and pilot test a chargeback system. This paper presents the results of this effort to date

  20. Idaho National Engineering Laboratory installation roadmap document

    International Nuclear Information System (INIS)

    1993-01-01

    The roadmapping process was initiated by the US Department of Energy's office of Environmental Restoration and Waste Management (EM) to improve its Five-Year Plan and budget allocation process. Roadmap documents will provide the technical baseline for this planning process and help EM develop more effective strategies and program plans for achieving its long-term goals. This document is a composite of roadmap assumptions and issues developed for the Idaho National Engineering Laboratory (INEL) by US Department of Energy Idaho Field Office and subcontractor personnel. The installation roadmap discusses activities, issues, and installation commitments that affect waste management and environmental restoration activities at the INEL. The High-Level Waste, Land Disposal Restriction, and Environmental Restoration Roadmaps are also included

  1. The Idaho Virtualization Laboratory 3D Pipeline

    Directory of Open Access Journals (Sweden)

    Nicholas A. Holmer

    2014-05-01

    Full Text Available Three dimensional (3D virtualization and visualization is an important component of industry, art, museum curation and cultural heritage, yet the step by step process of 3D virtualization has been little discussed. Here we review the Idaho Virtualization Laboratory’s (IVL process of virtualizing a cultural heritage item (artifact from start to finish. Each step is thoroughly explained and illustrated including how the object and its metadata are digitally preserved and ultimately distributed to the world.

  2. Pyrochemical treatment of Idaho Chemical Processing Plant high-level waste calcine

    International Nuclear Information System (INIS)

    Todd, T.A.; DelDebbio, J.A.; Nelson, L.O.; Sharpsten, M.R.

    1993-01-01

    The Idaho Chemical Processing Plant (ICPP), located at the Idaho National Engineering Laboratory (INEL), has reprocessed irradiated nuclear fuels for the US Department of Energy (DOE) since 1951 to recover uranium, krypton-85, and isolated fission products for interim treatment and immobilization. The acidic radioactive high-level liquid waste (HLLW) is routinely stored in stainless steel tanks and then, since 1963, calcined to form a dry granular solid. The resulting high-level waste (HLW) calcine is stored in seismically hardened stainless steel bins that are housed in underground concrete vaults. A research and development program has been established to determine the feasibility of treating ICPP HLW calcine using pyrochemical technology.This technology is described

  3. Bibliography of geologic studies: Columbia Plateau (Columbia River Basalt) and adjacent areas in Idaho

    International Nuclear Information System (INIS)

    Strowd, W.

    1978-11-01

    The objective of this compilation is to present a comprehensive listing of published, unpublished, and open-file references pertaining to the geology of the Columbia Plateau and adjacent areas in the State of Idaho. The bibliography was compiled in support of Rockwell's Basalt Waste Isolation Program that is evaluating the feasibility of nuclear waste storage in the Columbia River Basalt Group. The emphasis is on stratigraphy, structural geology, seismicity, and tectonics, although the nature of Columbia River Basalt distribution in Idaho has necessitated the inclusion of a sizeable collection of references on geology marginal to the Columbia Plateau and associated mineral resources. The bibliography is divided into two major sections, the alphabetical listing of all references and the subject index. The subject index is divided into 19 categories to facilitate locating a specific reference in the user's field of interest

  4. Management of radioactive liquid waste at the Idaho Chemical Processing Plant

    International Nuclear Information System (INIS)

    Bendixsen, C.L.

    1992-01-01

    Highly radioactive liquid wastes (HLLW) are routinely produced during spent nuclear fuel processing at the Idaho Chemical Processing Plant (ICPP), located at the Idaho National Engineering Laboratory (INEL). This paper discusses the processes and safe practices for management of the radioactive process waste streams, which processes include collection, concentration, interim storage, calcination to granular solids, and long-term intermediate storage. Over four million gallons of HLLW have been converted to a recoverable granular solid form through waste liquid injection into a high-temperature, fluidized bed wherein the wastes are converted to their respective solid oxides. The development of a glass ceramic solid for the long-term permanent disposal of the high level waste (HLW) solids is also described

  5. U.S. Geological Survey geohydrologic studies and monitoring at the Idaho National Laboratory, southeastern Idaho

    Science.gov (United States)

    Bartholomay, Roy C.

    2017-09-14

    BackgroundThe U.S. Geological Survey (USGS) geohydrologic studies and monitoring at the Idaho National Laboratory (INL) is an ongoing, long-term program. This program, which began in 1949, includes hydrologic monitoring networks and investigative studies that describe the effects of waste disposal on water contained in the eastern Snake River Plain (ESRP) aquifer and the availability of water for long-term consumptive and industrial use. Interpretive reports documenting study findings are available to the U.S. Department of Energy (DOE) and its contractors; other Federal, State, and local agencies; private firms; and the public at https://id.water.usgs.gov/INL/Pubs/index.html. Information contained within these reports is crucial to the management and use of the aquifer by the INL and the State of Idaho. USGS geohydrologic studies and monitoring are done in cooperation with the DOE Idaho Operations Office.

  6. Thickness of surficial sediment at and near the Idaho National Engineering Laboratory, Idaho

    International Nuclear Information System (INIS)

    Anderson, S.R.; Liszewski, M.J.; Ackerman, D.J.

    1996-06-01

    Thickness of surficial sediment was determined from natural-gamma logs in 333 wells at and near the Idaho National Engineering Laboratory in eastern Idaho to provide reconnaissance data for future site-characterization studies. Surficial sediment, which is defined as the unconsolidated clay, silt, sand, and gravel that overlie the uppermost basalt flow at each well, ranges in thickness from 0 feet in seven wells drilled through basalt outcrops east of the Idaho Chemical Processing Plant to 313 feet in well Site 14 southeast of the Big Lost River sinks. Surficial sediment includes alluvial, lacustrine, eolian, and colluvial deposits that generally accumulated during the past 200 thousand years. Additional thickness data, not included in this report, are available from numerous auger holes and foundation borings at and near most facilities

  7. Cost-Effectiveness Analysis of the Residential Provisions of the 2015 IECC for Idaho

    Energy Technology Data Exchange (ETDEWEB)

    Mendon, Vrushali V. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Zhao, Mingjie [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Taylor, Zachary T. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Poehlman, Eric A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2016-02-15

    The 2015 IECC provides cost-effective savings for residential buildings in Idaho. Moving to the 2015 IECC from the 2015 Idaho State Code base code is cost-effective for residential buildings in all climate zones in Idaho.

  8. The first Summer Institute of the World Nuclear University - a personal record

    International Nuclear Information System (INIS)

    Denk, W.; Fischer, C.; Seidl, M.

    2005-01-01

    The first World Nuclear University Summer Institute was held at Idaho Falls, USA, between July 9 and August 20, 2005. The event was hosted by the Institute of Nuclear Science and Engineering of Idaho State University (ISU) and by the Idaho National Laboratory (INL), which has been planned to be the central nuclear technology research institution in the United States. The World Nuclear University (WNU) was founded in 2003 by the International Atomic Energy Agency (IAEA), the OECD Nuclear Energy Agency (OECD-NEA), the World Association of Nuclear Operators (WANO), and the World Nuclear Association (WNA) as a global association fo scientific and educational institutions in the nuclear field. The first WNU Summer Institute was designed at IAEA in Vienna in the course of the following year and planned by the WNU Coordinating Centre in London. The six weeks of lectures and presentations arranged by the World nuclear University in Idaho Falls are described in detail from the participants' perspective. (orig.)

  9. Historic American Engineering Record, Idaho National Laboratory, Idaho Chemical Processing Plant, Fuel Reprocessing Complex

    Energy Technology Data Exchange (ETDEWEB)

    Susan Stacy; Julie Braun

    2006-12-01

    Just as automobiles need fuel to operate, so do nuclear reactors. When fossil fuels such as gasoline are burned to power an automobile, they are consumed immediately and nearly completely in the process. When the fuel is gone, energy production stops. Nuclear reactors are incapable of achieving this near complete burn-up because as the fuel (uranium) that powers them is burned through the process of nuclear fission, a variety of other elements are also created and become intimately associated with the uranium. Because they absorb neutrons, which energize the fission process, these accumulating fission products eventually poison the fuel by stopping the production of energy from it. The fission products may also damage the structural integrity of the fuel elements. Even though the uranium fuel is still present, sometimes in significant quantities, it is unburnable and will not power a reactor unless it is separated from the neutron-absorbing fission products by a method called fuel reprocessing. Construction of the Fuel Reprocessing Complex at the Chem Plant started in 1950 with the Bechtel Corporation serving as construction contractor and American Cyanamid Company as operating contractor. Although the Foster Wheeler Corporation assumed responsibility for the detailed working design of the overall plant, scientists at Oak Ridge designed all of the equipment that would be employed in the uranium separations process. After three years of construction activity and extensive testing, the plant was ready to handle its first load of irradiated fuel.

  10. SAFER - Company Snapshot - SAFER - Company Snapshot

    Data.gov (United States)

    Department of Transportation — The Company Snapshot is a concise electronic record of company identification, size, commodity information, and safety record, including the safety rating (if any),...

  11. Post Irradiation Capabilities at the Idaho National Laboratory

    International Nuclear Information System (INIS)

    Schulthess, J.L.; Rosenberg, K.E.

    2011-01-01

    The U.S. Department of Energy (DOE), Office of Nuclear Energy (NE) oversees the efforts to ensure nuclear energy remains a viable option for the United States. A significant portion of these efforts are related to post-irradiation examinations (PIE) of highly activated fuel and materials that are subject to the extreme environment inside a nuclear reactor. As the lead national laboratory, Idaho National Laboratory (INL) has a rich history, experience, workforce and capabilities for performing PIE. However, new advances in tools and techniques for performing PIE now enable understanding the performance of fuels and materials at the nano-scale and smaller level. Examination at this level is critical since this is the scale at which irradiation damage occurs. The INL is on course to adopt these advanced tools and techniques to develop a comprehensive nuclear fuels and materials characterization capability that is unique in the world. Because INL has extensive PIE capabilities currently in place, a strong foundation exist to build upon as new capabilities are implemented and work load increases. In the recent past, INL has adopted significant capability to perform advanced PIE characterization. Looking forward, INL is planning for the addition of two facilities that will be built to meet the stringent demands of advanced tools and techniques for highly activated fuels and materials characterization. Dubbed the Irradiated Materials Characterization Laboratory (IMCL) and Advanced Post Irradiation Examination Capability, these facilities are next generation PIE laboratories designed to perform the work of PIE that cannot be performed in current DOE facilities. In addition to physical capabilities, INL has recently added two significant contributors to the Advanced Test Reactor-National Scientific User Facility (ATR-NSUF), Oak Ridge National Laboratory and University of California, Berkeley.

  12. Confirmatory radiological survey of the BORAX-V turbine building Idaho National Engineering Laboratory, Idaho Falls, Idaho

    International Nuclear Information System (INIS)

    Stevens, G.H.; Coleman, R.L.; Jensen, M.K.; Pierce, G.A.; Egidi, P.V.; Mather, S.K.

    1993-01-01

    An independent assessment of the remediation of the BORAX-V (Boiling Water Reactor Experiment) turbine building at the Idaho National Engineering Laboratory (INEL), Idaho Falls, Idaho, was accomplished by the Oak Ridge National Laboratory Pollutant Assessments Group (ORNL/PAG). The purpose of the assessment was to confirm the site's compliance with applicable Department of Energy guidelines. The assessment included reviews of both the decontamination and decommissioning Plan and data provided from the pre- and post-remedial action surveys and an independent verification survey of the facility. The independent verification survey included determination of background exposure rates and soil concentrations, beta-gamma and gamma radiation scans, smears for detection of removable contamination, and direct measurements for alpha and beta-gamma radiation activity on the basement and mezzanine floors and the building's interior and exterior walls. Soil samples were taken, and beta-gamma and gamma radiation exposure rates were measured on areas adjacent to the building. Results of measurements on building surfaces at this facility were within established contamination guidelines except for elevated beta-gamma radiation levels located on three isolated areas of the basement floor. Following remediation of these areas, ORNL/PAG reviewed the remedial action contractor's report and agreed that remediation was effective in removing the source of the elevated direct radiation. Results of all independent soil analyses for 60 Co were below the detection limit. The highest 137 Cs analysis result was 4.6 pCi/g; this value is below the INEL site-specific guideline of 10 pCi/g

  13. Nuclear power plant analyzer

    International Nuclear Information System (INIS)

    Stritar, A.

    1986-01-01

    The development of Nuclear Power Plant Analyzers in USA is described. There are two different types of Analyzers under development in USA, the forst in Idaho and Los Alamos national Lab, the second in brookhaven National lab. That one is described in detail. The computer hardware and the mathematical models of the reactor vessel thermalhydraulics are described. (author)

  14. In summary: Idaho National Engineering Laboratory site environmental report for calendar year 1995

    International Nuclear Information System (INIS)

    Roush, D.; Mitchell, R.G.; Peterson, D.

    1996-08-01

    Every human is exposed to natural radiation. This exposure comes from many sources, including cosmic radiation from outer space, naturally-occurring radon, and radioactivity from substances in our bodies. In addition to natural sources of radiation, humans can also be exposed to man-made sources of radiation. Examples of man-made sources include nuclear medicine, X-rays, nuclear weapons testing, and accidents at nuclear power plants. The Idaho National Engineering Laboratory (INEL) is a U.S. Department of Energy (DOE) research facility that deals, in part, with studying nuclear reactors and storing radioactive materials. Careful handling and rigorous procedures do not completely eliminate the risk of releasing radioactivity. So, there is a remote possibility for a member of the public near the INEL to be exposed to radioactivity from the INEL. Extensive monitoring of the environment takes place on and around the INEL. These programs search for radionuclides and other contaminants. The results of these programs are presented each year in a site environmental report. This document summarizes the Idaho National Engineering Laboratory Site Environmental Report for Calendar Year 1995

  15. Spent fuel storage cask testing and operational experience at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Eslinger, L.E.; Schmitt, R.C.

    1989-01-01

    Spent-fuel storage cask research, development, and demonstration activities are being performed for the U.S. Department of Energy's (DOE's) Office of Civilian Radioactive Waste Management (OCRWM) as a part of the storage cask testing program. The cask testing program at federal sites and other locations supports the Nuclear Waste Policy Act (NWPA) and DOE objectives for cooperative demonstrations with the cask vendors and utilities for development of at-reactor dry cask storage capabilities for spent nuclear fuel assemblies. One research and development program for the storage cask performance testing of metal storage cask was initiated through a cooperative agreement between Virginia Power and DOE in 1984. The performance testing was conducted for the DOE and the Electric Power Research Institute by the Pacific Northwest laboratory, operated for DOE by Battelle Memorial Institute, and the Idaho National Engineering Laboratory (INEL), operated for DOE by EG ampersand G Idaho, Inc. In 1988 a cooperative agreement was entered into by DOE with Pacific Sierra Nuclear Associates (PSN) for performance testing of the PSN concrete Ventilated Storage Cask. Another closely related activity involving INEL is a transportable storage cask project identified as the Nuclear Fuel Services Spent-Fuel Shipping/Storage Cask Demonstration Project. The purpose of this project is to demonstrate the feasibility of packing, transporting, and storing commercial spent fuel in dual-purpose transport/storage casks

  16. Nuclear privatization

    International Nuclear Information System (INIS)

    Jeffs, E.

    1995-01-01

    The United Kingdom government announced in May 1995 plans to privatize the country's two nuclear generating companies, Nuclear Electric and Scottish Nuclear. Under the plan, the two companies will become operating divisions of a unified holding company, to be called British Electric, with headquarters in Scotland. Britain's nuclear plants were left out of the initial privatization in 1989 because the government believed the financial community would be unwilling to accept the open-ended liability of decommissioning the original nine stations based on the Magnox gas-cooled reactor. Six years later, the government has found a way around this by retaining these power stations in state ownership, leaving the new nuclear company with the eight Advanced Gas-cooled Reactor (AGR) stations and the recently completed Sizewell B PWR stations. The operating Magnox stations are to be transferred to BNFL, which operates two Magnox stations of their own at Calder Hall and Chapelcross

  17. The Status of Physical Activity Opportunities in Idaho Schools

    Science.gov (United States)

    Berei, Catherine P.; Karp, Grace Goc; Kauffman, Katie

    2018-01-01

    Recent literature indicates that low percentages of Idaho adolescents report being physically active on a daily basis. Research examines school PA, however, little focuses on Comprehensive School Physical Activity Programs (CSPAPs) from the perspectives of physical educators. This study explored Idaho physical educators' perceptions and…

  18. Insects of the Idaho National Laboratory: A compilation and review

    Science.gov (United States)

    Nancy Hampton

    2005-01-01

    Large tracts of important sagebrush (Artemisia L.) habitat in southeastern Idaho, including thousands of acres at the Idaho National Laboratory (INL), continue to be lost and degraded through wildland fire and other disturbances. The roles of most insects in sagebrush ecosystems are not well understood, and the effects of habitat loss and alteration...

  19. Idaho's forest products industry and timber harvest, 2011

    Science.gov (United States)

    Eric A. Simmons; Steven W. Hayes; Todd A. Morgan; Charles E. Keegan; Chris Witt

    2014-01-01

    This report traces the flow of Idaho’s 2011 timber harvest through the primary industries; provides a description of the structure, capacity, and condition of Idaho’s industry; and quantifies volumes and uses of wood fiber. Historical wood products industry trends are discussed, as well as changes in harvest, production, employment, and sales.

  20. 77 FR 54557 - Eastern Idaho Resource Advisory Committee

    Science.gov (United States)

    2012-09-05

    ... DEPARTMENT OF AGRICULTURE Forest Service Eastern Idaho Resource Advisory Committee AGENCY: Forest Service, USDA. ACTION: Notice of meeting. SUMMARY: The Easern Idaho Resource Advisory Committee will meet... between 8 a.m. and 8 p.m., Eastern Standard Time, Monday through Friday. SUPPLEMENTARY INFORMATION: The...

  1. Logging utilization in Idaho: Current and past trends

    Science.gov (United States)

    Eric A. Simmons; Todd A. Morgan; Erik C. Berg; Stanley J. Zarnoch; Steven W. Hayes; Mike T. Thompson

    2014-01-01

    A study of commercial timber-harvesting activities in Idaho was conducted during 2008 and 2011 to characterize current tree utilization, logging operations, and changes from previous Idaho logging utilization studies. A two-stage simple random sampling design was used to select sites and felled trees for measurement within active logging sites. Thirty-three logging...

  2. Role and Place of the Joint-Stock Company -ECOMET-S- in the System of Solid Radioactive Waste Treatment Generated at the Nuclear Power Plants of the Russian Federation

    International Nuclear Information System (INIS)

    Gelbutovski, A.B.; Troshev, A.V.; Cheremisin, P.I.

    2009-01-01

    In this work the existing situation and ways of solving the problem of solid radioactive waste (SRW) management, resulting from the nuclear power industry are considered. It is shown, that one of the ways to manage SRW is transferring the task to a specialized enterprise. Such an enterprise in Russia is the Joint-Stock Company (JSC) 'ECOMET-S', whose main activity is providing services for processing and disposal of radioactive metal waste. They reduce the volume of SRW, ship it for burial and return metal return to industry for unlimited use. The basic provisions of the system of radioactive metal waste (hereinafter RMW) management developed by JSC 'ECOMET-S' are given. Information referring to technology and enterprise industrial capacity is represented. The results of the JSC 'ECOMET-S' activity for processing and disposal of low-activity radioactive metal waste from the Nuclear Power Plant (hereinafter NPP) of the Russian Federation are shown. (authors)

  3. Idaho National Engineering Laboratory site development plan

    International Nuclear Information System (INIS)

    1994-09-01

    This plan briefly describes the 20-year outlook for the Idaho National Engineering Laboratory (INEL). Missions, workloads, worker populations, facilities, land, and other resources necessary to fulfill the 20-year site development vision for the INEL are addressed. In addition, the plan examines factors that could enhance or deter new or expanded missions at the INEL. And finally, the plan discusses specific site development issues facing the INEL, possible solutions, resources required to resolve these issues, and the anticipated impacts if these issues remain unresolved

  4. THE IDAHO NATIONAL LABORATORY BERYLLIUM TECHNOLOGY UPDATE

    International Nuclear Information System (INIS)

    Glen R. Longhurst

    2007-01-01

    A Beryllium Technology Update meeting was held at the Idaho National Laboratory on July 18, 2007. Participants came from the U.S., Japan, and Russia. There were two main objectives of this meeting. One was a discussion of current technologies for beryllium in fission reactors, particularly the Advanced Test Reactor and the Japan Materials Test Reactor, and prospects for material availability in the coming years. The second objective of the meeting was a discussion of a project of the International Science and Technology Center regarding treatment of irradiated beryllium for disposal. This paper highlights discussions held during that meeting and major conclusions reached

  5. EG and G Idaho Environmental Protection Implementation Plan (1991)

    Energy Technology Data Exchange (ETDEWEB)

    Graham, J.F.

    1991-11-01

    This report describes the EG G Idaho, Inc. strategy for implementation of the Department of Energy (DOE) Order 5400.1 (a DOE-Headquarters directive establishing environmental protection program requirements, authorities, and responsibilities). Preparation of this Environmental Protection Implementation Plan is a requirement of DOE Order 5400.1. Additionally, this report is intended to supplement the Department of Energy -- Field Office Idaho (DOE-ID) Environmental Protection Implementation Plan by detailing EG G Idaho Environmental Protection Program activities. This report describes the current status of the EG G Idaho Program, and the strategies for enhancing, as necessary, the current program to meet the requirements of DOE Order 5400.1. Aspects of the Environmental Protection Program included in this report are the assignment of responsibilities to specific EG G Idaho organizations, a schedule for completion of enhancements, if necessary, and requirements for documentation and reporting. 4 figs., 1 tab.

  6. EG and G Idaho Environmental Protection Implementation Plan (1991)

    International Nuclear Information System (INIS)

    Graham, J.F.

    1991-11-01

    This report describes the EG ampersand G Idaho, Inc. strategy for implementation of the Department of Energy (DOE) Order 5400.1 (a DOE-Headquarters directive establishing environmental protection program requirements, authorities, and responsibilities). Preparation of this Environmental Protection Implementation Plan is a requirement of DOE Order 5400.1. Additionally, this report is intended to supplement the Department of Energy -- Field Office Idaho (DOE-ID) Environmental Protection Implementation Plan by detailing EG ampersand G Idaho Environmental Protection Program activities. This report describes the current status of the EG ampersand G Idaho Program, and the strategies for enhancing, as necessary, the current program to meet the requirements of DOE Order 5400.1. Aspects of the Environmental Protection Program included in this report are the assignment of responsibilities to specific EG ampersand G Idaho organizations, a schedule for completion of enhancements, if necessary, and requirements for documentation and reporting. 4 figs., 1 tab

  7. Supplemental investigations in support of environmental assessments by the Idaho INEL Oversight Program at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    1992-01-01

    This document reports on the status of supplemental investigations in support of environmental assessments by the Idaho INEL Oversight Program at the Idaho National Engineering Laboratory. Included is information on hydrology studies in wells open through large intervals, unsaturated zone contamination and transport processes, surface water-groundwater interactions, regional groundwater flow, and independent testing of air quality data

  8. The Development of a Human Systems Simulation Laboratory at Idaho National Laoboratory: Progress, Requirements and Lessons Learned

    Energy Technology Data Exchange (ETDEWEB)

    David I Gertman; Katya L. LeBlanc; William phoenix; Alan R Mecham

    2010-11-01

    Next generation nuclear power plants and digital upgrades to the existing nuclear fleet introduce potential human performance issues in the control room. Safe application of new technologies calls for a thorough understanding of how those technologies affect human performance and in turn, plant safety. In support of advancing human factors for small modular reactors and light water reactor sustainability, the Idaho National Laboratory (INL) has developed a reconfigurable simulation laboratory capable of testing human performance in multiple nuclear power plant (NPP) control room simulations. This paper discusses the laboratory infrastructure and capabilities, the laboratory’ s staffing requirements, lessons learned, and the researcher’s approach to measuring human performance in the simulation lab.

  9. The Development of a Human Systems Simulation Laboratory at Idaho National Laoboratory: Progress, Requirements and Lessons Learned

    International Nuclear Information System (INIS)

    Gertman, David I.; LeBlanc, Katya L.; Phoenix, William; Mecham, Alan R.

    2010-01-01

    Next generation nuclear power plants and digital upgrades to the existing nuclear fleet introduce potential human performance issues in the control room. Safe application of new technologies calls for a thorough understanding of how those technologies affect human performance and in turn, plant safety. In support of advancing human factors for small modular reactors and light water reactor sustainability, the Idaho National Laboratory (INL) has developed a reconfigurable simulation laboratory capable of testing human performance in multiple nuclear power plant (NPP) control room simulations. This paper discusses the laboratory infrastructure and capabilities, the laboratory's staffing requirements, lessons learned, and the researcher's approach to measuring human performance in the simulation lab.

  10. The legal status of engineering companies

    International Nuclear Information System (INIS)

    1981-10-01

    It is assumed that the carrying out of research, also in the nuclear field should be entrusted to engineering companies, especially when dealing with the setting up of technological structures. This paper considers the problems of the legal status of such companies under Italian legislation. (NEA) [fr

  11. Nuclear

    International Nuclear Information System (INIS)

    2014-01-01

    This document proposes a presentation and discussion of the main notions, issues, principles, or characteristics related to nuclear energy: radioactivity (presence in the environment, explanation, measurement, periods and activities, low doses, applications), fuel cycle (front end, mining and ore concentration, refining and conversion, fuel fabrication, in the reactor, back end with reprocessing and recycling, transport), the future of the thorium-based fuel cycle (motivations, benefits and drawbacks), nuclear reactors (principles of fission reactors, reactor types, PWR reactors, BWR, heavy-water reactor, high temperature reactor of HTR, future reactors), nuclear wastes (classification, packaging and storage, legal aspects, vitrification, choice of a deep storage option, quantities and costs, foreign practices), radioactive releases of nuclear installations (main released radio-elements, radioactive releases by nuclear reactors and by La Hague plant, gaseous and liquid effluents, impact of releases, regulation), the OSPAR Convention, management and safety of nuclear activities (from control to quality insurance, to quality management and to sustainable development), national safety bodies (mission, means, organisation and activities of ASN, IRSN, HCTISN), international bodies, nuclear and medicine (applications of radioactivity, medical imagery, radiotherapy, doses in nuclear medicine, implementation, the accident in Epinal), nuclear and R and D (past R and D programmes and expenses, main actors in France and present funding, main R and D axis, international cooperation)

  12. Remedial action plan and site design for stabilization of the inactive uranium mill tailings site at Lowman, Idaho: Remedial action selection report for the Lowman UMTRA project site, Idaho

    International Nuclear Information System (INIS)

    Matthews, M.L.; Nagel, J.

    1991-09-01

    The inactive uranium mill tailings site near Lowman, Idaho, was designated as one of 24 abandoned uranium tailings sites to be remediated by the US Department of Energy (DOE) under the Uranium Mill Tailings Radiation Control Act of 1978 (UMTRCA). The UMTRCA requires that the US Nuclear Regulatory Commission (NRC) concur with the DOE's remedial action plan and certify that the remedial action complies with the standards promulgated by the US Environmental Protection Agency (EPA). The remedial action plan (RAP), which includes this remedial action selection report (RAS), has been developed to serve a two-fold purpose. First, it describes the activities that are proposed by the DOE to accomplish long-term stabilization and control of residual radioactive materials at the inactive uranium processing site near Lowman, Idaho. Second, this document and the remainder of the RAP, upon concurrence and execution by the DOE, the State of Idaho, and the NRC, becomes Appendix B of the Cooperative Agreement (No. DE-FC04-85AL20535) between the DOE and the State of Idaho

  13. A study on environmental pollution monitoring and occupational health in the capital iron and steel company, Beijing, China, using nuclear and related analytical techniques

    Energy Technology Data Exchange (ETDEWEB)

    Chifang, Chai; Xiaolin, Hou; Qinfang, Qian; Wenjun, Ding; Xiangqian, Feng [Institute of High Energy Physics and Laboratory of Nuclear Analysis Techniques, Academia Sinica, Beijing (China); Minxu, Kuang; Hongyu, Wang; Yongchen, Zhang [General Hospital of the Capital Iron and Steel Company, Beijing (China)

    1999-12-31

    The atmosphere pollution in some Chinese cities is becoming more and more serious with the industrial development in the past decades. The airborne particulate concentration in Beijing, the Capital of China, far exceeds the allowable level set by the Chinese government and by the related international organizations. The main contribution source for the Beijing atmospheric particulate is the Capital Iron and Steel Company, which constitutes 55% of total air-borne particulate in Beijing. In the framework of this CRP organized by IAEA, we select this company as a target workplace. The INAA (instrumental neutron activation analysis), PIXE (proton induced X-ray emission analysis), SRXRF (synchronous radiation X-ray fluorescence spectrometry) and other related techniques will be applied to determine the concentrations of some target elements, e.g. heavy metal and toxic elements, in environmental samples (including airborne particulate, soil and plants) and human samples (including head hair, urine and blood) collected from this company, its surrounding region and a non-polluted region as a control. The activity completed at the first year and the working plan for next year is outlined in this report. Other related information will be dealt with as well. (author) 7 refs, 1 tab

  14. A study on environmental pollution monitoring and occupational health in the capital iron and steel company, Beijing, China, using nuclear and related analytical techniques

    International Nuclear Information System (INIS)

    Chai Chifang; Hou Xiaolin; Qian Qinfang; Ding Wenjun; Feng Xiangqian; Kuang Minxu; Wang Hongyu; Zhang Yongchen

    1998-01-01

    The atmosphere pollution in some Chinese cities is becoming more and more serious with the industrial development in the past decades. The airborne particulate concentration in Beijing, the Capital of China, far exceeds the allowable level set by the Chinese government and by the related international organizations. The main contribution source for the Beijing atmospheric particulate is the Capital Iron and Steel Company, which constitutes 55% of total air-borne particulate in Beijing. In the framework of this CRP organized by IAEA, we select this company as a target workplace. The INAA (instrumental neutron activation analysis), PIXE (proton induced X-ray emission analysis), SRXRF (synchronous radiation X-ray fluorescence spectrometry) and other related techniques will be applied to determine the concentrations of some target elements, e.g. heavy metal and toxic elements, in environmental samples (including airborne particulate, soil and plants) and human samples (including head hair, urine and blood) collected from this company, its surrounding region and a non-polluted region as a control. The activity completed at the first year and the working plan for next year is outlined in this report. Other related information will be dealt with as well. (author)

  15. Idaho National Laboratory 2013-2022 Ten-Year Site Plan

    Energy Technology Data Exchange (ETDEWEB)

    Calvin Ozaki; Sheryl L. Morton; Elizabeth A. Connell; William T. Buyers; Craig L. Jacobson; Charles T. Mullen; Christopher P. Ischay; Ernest L. Fossum; Robert D. Logan

    2011-06-01

    The Idaho National Laboratory (INL) Ten-Year Site Plan (TYSP) describes the strategy for accomplishing the long-term objective of transforming the laboratory to meet Department of Energy (DOE) national nuclear research and development (R&D) goals, as outlined in DOE strategic plans. The plan links R&D mission goals and INL core capabilities with infrastructure requirements (single- and multi-program), establishs the 10-year end-state vision for INL complexes, and identifies and prioritizes infrastructure needs and capability gaps. The TYSP serves as the basis for documenting and justifying infrastructure investments proposed as part of the FY 2013 budget formulation process.

  16. New Nutrition Standards for Idaho School Meals. Nourishing News. Volume 4, Issue 1

    Science.gov (United States)

    Idaho State Department of Education, 2009

    2009-01-01

    Idaho Child Nutrition Programs (CNP) released the New Nutrition Standards for Idaho School Meals in January 2009 with the recommendation that all School Food Authorities fully implement the New Nutrition Standards for Idaho School Meals into their programs starting August 2009. Along with the release of the New Nutrition Standards for Idaho School…

  17. The Implementation of Pay for Performance in Idaho Schools: A Case Study of Teacher Perceptions

    Science.gov (United States)

    Staniec, Shelly Ann

    2013-01-01

    This is a qualitative narrative case study set in an Idaho high school where twelve educators offered their viewpoints on the implementation of Idaho's pay-for-performance legislation. In the spring of 2011, Idaho legislators passed laws aimed at increasing student performance and college or career readiness. These laws, known as Idaho's Students…

  18. Idaho National Engineering Laboratory release criteria for decontamination and decommissioning

    International Nuclear Information System (INIS)

    Dolenc, M.R.; Case, M.J.

    1986-01-01

    Criteria have been developed for release of Idaho National Engineering Laboratory (INEL) facilities and land areas following decontamination and decommissioning (D and D). Decommissioning release criteria in the form of dose guidelines were proposed by the US Nuclear Regulatory Commission as early as 1980. These criteria were used on an interim basis for INEL D and D projects. However, dose guidelines alone do not adequately cover the criteria necessary to release sites for unrestricted use. In actual practice, other parameters such as pathways analyses, sampling and instrumentation techniques, and implementation procedures are required to develop the basis for unrestricted release of a site. Thus, a rigorous approach for evaluating these other parameters is needed to develop acceptable D and D release criteria. Because of the complex and sensitive nature of the dose and pathways analyses work, a thorough review by experts in those respective fields was desired. Input and support in preparing or reviewing each part of the criteria development task was solicited from several DOE field offices. Experts were identified and contracted to assist in preparing portions of the release criteria, or to serve on a peer-review committee. Thus, the entire release criteria development task was thoroughly reviewed by recognized experts from each DOE field office, to validate technical content of the INEL site-specific document

  19. Idaho National Engineering and Environmental Laboratory institutional plan -- FY 2000--2004

    Energy Technology Data Exchange (ETDEWEB)

    Enge, R.S.

    1999-12-01

    In this first institutional plan prepared by Bechtel BWXT Idaho, LLC, for the Idaho National Engineering and Environmental Laboratory, the INEEL will focus its efforts on three strategic thrusts: (1) Environmental Management stewardship for DOE-EM, (2) Nuclear reactor technology for DOE-Nuclear Energy (NE), and (3) Energy R and D, demonstration, and deployment (initial focus on biofuels and chemicals from biomass). The first strategic thrust focuses on meeting DOE-EMs environmental cleanup and long-term stewardship needs in a manner that is safe, cost-effective, science-based, and approved by key stakeholders. The science base at the INEEL will be further used to address a grand challenge for the INEEL and the DOE complex--the development of a fundamental scientific understanding of the migration of subsurface contaminants. The second strategic thrust is directed at DOE-NEs needs for safe, economical, waste-minimized, and proliferation-resistant nuclear technologies. As NE lead laboratories, the INEEL and ANL will pursue specific priorities. The third strategic thrust focuses on DOE's needs for clean, efficient, and renewable energy technology. As an initial effort, the INEEL will enhance its capability in biofuels, bioprocessing, and biochemicals. The content of this institutional plan is designed to meet basic DOE requirements for content and structure and reflect the key INEEL strategic thrusts. Updates to this institutional plan will offer additional content and resource refinements.

  20. Aerial radiological survey of the Idaho National Engineering Laboratory, Idaho Falls, Idaho. Date of survey: June 1982

    International Nuclear Information System (INIS)

    1984-02-01

    An aerial radiological survey of the Idaho National Engineering Laboratory (INEL) was conducted during June 1982 by EG and G Energy Measurements, Inc. for the United States Department of Energy (DOE). The survey consisted of airborne measurements of both natural and man-made gamma radiation from the terrain surface in and around the INEL site. These measurements allowed an estimate of the distribution of isotopic concentrations in the survey area. Results are reported as isopleths superimposed on maps and photographs of the area. Gamma ray energy spectra are also presented for the net man-made radionuclides. The survey was designed to cover all of the area within a 2 mile radius of any facility at the INEL. Several areas of man-made activity were detected. These areas are all known working or storage areas which are associated with normal operations at the INEL. 3 references, 48 figures, 5 tables

  1. Environmental monitoring for EG and G Idaho facilities at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Tkachyk, J.W.; Wright, K.C.; Wilhelmsen, R.N.

    1990-08-01

    This report describes the 1989 environmental-monitoring activities of the Environmental Monitoring Unit of EG ampersand G Idaho, Inc., at EG ampersand G-operated facilities at the Idaho National Engineering Laboratory (INEL). The major facilities monitored include the Radioactive Waste Management Complex, the Waste Experimental Reduction Facility, the Mixed Waste Storage Facility, and two surplus facilities. Additional monitoring activities performed by Environmental Monitoring are also discussed, including drinking-water monitoring and nonradiological liquid-effluent monitoring, as well as data management. The primary purposes of monitoring are to evaluate environmental conditions and to provide and interpret data, in compliance with applicable regulations, to ensure protection of human health and the environment. This report compares 1989 environmental-monitoring data with derived concentration guides and with data from previous years. This report also presents results of sampling performed by the Radiological and Environmental Sciences Laboratory and by the United States Geological Survey. 17 refs., 49 figs., 11 tabs

  2. Nuclear Regulatory Commission Issuances, September 1981

    International Nuclear Information System (INIS)

    1981-01-01

    Contents include: Issuances of the Nuclear Regulatory Commission--Commonwealth Edison Company (Dresden Nuclear Power Station, Unit 1), Consolidated Edison Company of New York (Indian Point, Unit 2), Metropolitan Edison Company, et al. (Three Mile Island Nuclear Station, Unit 1), Pacific Gas and Electric Company (Diablo Canyon Nuclear Power Plant, Units 1 and 2), Pacific Gas and Electric Company (Diablo Canyon Nuclear Power Plant, Units 1 and 2), Power Authority of the State of New York (Indian Point, Unit 3), Texas Utilities Generating Company, et al. (Comanche Peak Steam Electric Station, Units 1 and 2); Issuances of Atomic Safety and Licensing Appeal Boards--Pacific Gas and Electric Company (Diablo Canyon Nuclear Power Plant, Units 1 and 2), Philadelphia Electric Company, et al. (Peach Bottom Atomic Power Statin, Units 2 and 3), Metropolitan Edison Company, et al. (Three Mile Island Nuclear Statin, Unit No. 2), Public Service Electric and Gas Company (Hope Creek Generating Station, Units 1 and 2), The Toledo Edison Company, et al. (Davis-Besse Nuclear Power Station, Units 2 and 3); Issuances of the Atomic Safety Licensing Boards--Cleveland Electric Illuminating Company, et al. (Perry Nuclear Power Plant, Units 1 and 2), Commonwealth Edison Company (Dresden Station, Units 2 and 3), Houston Lighting and Power Company (Allens Creek Nuclear Generating Station, Unit 1), Southern California Edison Company, et al. (San Onofre Nuclear Generating Station, Units 2 and 3), Texas Utilities Generating Company, et al. (Comanche Peak Steam Electric Station, Units 1 and 2), Texas Utilities Generating Company, et al

  3. Contaminant Monitoring Strategy for Henrys Lake, Idaho

    Energy Technology Data Exchange (ETDEWEB)

    John S. Irving; R. P. Breckenridge

    1992-12-01

    Henrys Lake, located in southeastern Idaho, is a large, shallow lake (6,600 acres, {approx} 17.1 feet maximum depth) located at 6,472 feet elevation in Fremont Co., Idaho at the headwaters of the Henrys Fork of the Snake River. The upper watershed is comprised of high mountains of the Targhee National Forest and the lakeshore is surrounded by extensive flats and wetlands, which are mostly privately owned. The lake has been dammed since 1922, and the upper 12 feet of the lake waters are allocated for downriver use. Henrys Lake is a naturally productive lake supporting a nationally recognized ''Blue Ribbon'' trout fishery. There is concern that increasing housing development and cattle grazing may accelerate eutrophication and result in winter and early spring fish kills. There has not been a recent thorough assessment of lake water quality. However, the Department of Environmental Quality (DEQ) is currently conducting a study of water quality on Henrys Lake and tributary streams. Septic systems and lawn runoff from housing developments on the north, west, and southwest shores could potentially contribute to the nutrient enrichment of the lake. Many houses are on steep hillsides where runoff from lawns, driveways, etc. drain into wetland flats along the lake or directly into the lake. In addition, seepage from septic systems (drainfields) drain directly into the wetlands enter groundwater areas that seep into the lake. Cattle grazing along the lake margin, riparian areas, and uplands is likely accelerating erosion and nutrient enrichment. Also, cattle grazing along riparian areas likely adds to nutrient enrichment of the lake through subsurface flow and direct runoff. Stream bank and lakeshore erosion may also accelerate eutrophication by increasing the sedimentation of the lake. Approximately nine streams feed the lake (see map), but flows are often severely reduced or completely eliminated due to irrigation diversion. In addition, subsurface

  4. Environmental Assessment of Alternate Training Area Jack Pine Flats Idaho Department of Lands Near Coolin, Idaho

    Science.gov (United States)

    2009-05-01

    habitats within the proposed permit/lease area are not suitable for full support of these species, particularly reproduction and are not considered...restricting harvest has a more substantial positive effect on bull trout reproduction and survival over any other factor. Hence, the proposed action will...growth mesic conifer forests. They are known to use other habitat types such as openings and riparian areas. Populations in Idaho have decreased from

  5. Portland General Electric Company report on the operating and startup experience with control and instrumentation and electrical systems at the Trojan Nuclear Plant

    International Nuclear Information System (INIS)

    Zimmerman, G.A.

    1977-01-01

    The Trojan Nuclear Plant is an 1178 MWe nuclear plant located on the Columbia River 40 miles northwest of Portland, Oregon. The Nuclear Stream Supply System vendor is Westinghouse with a General Electric turbine generator. The reactor is rated and licensed for 3423 MWt (1178 MWe) and the turbine generator is designed for 3570 MWt(1219 MWe). The startup phase testing of Trojan commenced on November 21, 1975, upon receipt of our NRC Operating License. The startup testing program was completed on May 22, 1976, following 100 hours of full-power operation, at which time a scheduled summer maintenance outage began. Some of the highlights and milestones of the startup testing program are described

  6. Aerial gamma ray and magnetic survey: Idaho Project, Hailey quadrangle of Idaho. Final report

    International Nuclear Information System (INIS)

    1979-12-01

    The Hailey quadrangle in central Idaho lies at the boundary between the Northern Rocky Mountains and the western Cordilleran Physiographic Provinces. The area is dominated by intrusives of the Idaho and Sawtooth Batholiths, but contains considerable exposures of Tertiary and Quaternary volcanics, and Paleozoic sedimentary rocks. Magnetic data apparently show some expression of the intrusives of the Idaho Batholith. Areas of faulted Paleozoic and Tertiary rocks appear to express themselves as roughly defined regions of high frequency/high amplitude wavelengths. The Hailey quadrangle has been unproductive in terms of uranium mining, though some prospects do exist south of the town of Hailey. The quadrangle contains significant exposures of the Tertiary Challis Formation (primarily volcanics) which has been productive in other areas to the north. A total of 161 anomalies are valid according to the criteria set forth in Volume I of this report. These anomalies are scattered throughout the quadrangle. The most distinctive groups of anomalies are associated with Tertiary igneous rocks in the mountainous areas

  7. Idaho National Engineering Laboratory Waste Management Operations Roadmap Document

    International Nuclear Information System (INIS)

    Bullock, M.

    1992-04-01

    At the direction of the Department of Energy-Headquarters (DOE-HQ), the DOE Idaho Field Office (DOE-ID) is developing roadmaps for Environmental Restoration and Waste Management (ER ampersand WM) activities at Idaho National Engineering Laboratory (INEL). DOE-ID has convened a select group of contractor personnel from EG ampersand G Idaho, Inc. to assist DOE-ID personnel with the roadmapping project. This document is a report on the initial stages of the first phase of the INEL's roadmapping efforts

  8. Idaho National Laboratory Environmental Monitoring Plan

    Energy Technology Data Exchange (ETDEWEB)

    Joanne L. Knight

    2008-04-01

    This plan describes environmental monitoring as required by U.S. Department of Energy (DOE) Order 450.1, “Environmental Protection Program,” and additional environmental monitoring currently performed by other organizations in and around the Idaho National Laboratory (INL). The objective of DOE Order 450.1 is to implement sound stewardship practices that protect the air, water, land, and other natural and cultural resources that may be impacted by DOE operations. This plan describes the organizations responsible for conducting environmental monitoring across the INL, the rationale for monitoring, the types of media being monitored, where the monitoring is conducted, and where monitoring results can be obtained. This plan presents a summary of the overall environmental monitoring performed in and around the INL without duplicating detailed information in the various monitoring procedures and program plans currently used to conduct monitoring.

  9. Idaho National Laboratory Quarterly Performance Analysis

    Energy Technology Data Exchange (ETDEWEB)

    Mitchell, Lisbeth [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2014-11-01

    This report is published quarterly by the Idaho National Laboratory (INL) Quality and Performance Management Organization. The Department of Energy (DOE) Occurrence Reporting and Processing System (ORPS), as prescribed in DOE Order 232.2, “Occurrence Reporting and Processing of Operations Information,” requires a quarterly analysis of events, both reportable and not reportable, for the previous 12 months. This report is the analysis of 60 reportable events (23 from the 4th Qtr FY14 and 37 from the prior three reporting quarters) as well as 58 other issue reports (including not reportable events and Significant Category A and B conditions) identified at INL from July 2013 through October 2014. Battelle Energy Alliance (BEA) operates the INL under contract DE AC07 051D14517.

  10. Idaho National Laboratory Site Environmental Monitoring Plan

    Energy Technology Data Exchange (ETDEWEB)

    Joanne L. Knight

    2012-08-01

    This plan describes environmental monitoring as required by U.S. Department of Energy (DOE) Order 450.1, “Environmental Protection Program,” and additional environmental monitoring currently performed by other organizations in and around the Idaho National Laboratory (INL). The objective of DOE Order 450.1 is to implement sound stewardship practices that protect the air, water, land, and other natural and cultural resources that may be impacted by DOE operations. This plan describes the organizations responsible for conducting environmental monitoring across the INL, the rationale for monitoring, the types of media being monitored, where the monitoring is conducted, and where monitoring results can be obtained. This plan presents a summary of the overall environmental monitoring performed in and around the INL without duplicating detailed information in the various monitoring procedures and program plans currently used to conduct monitoring.

  11. Idaho National Laboratory Quarterly Occurrence Analysis

    Energy Technology Data Exchange (ETDEWEB)

    Mitchell, Lisbeth Ann [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2015-11-01

    This report is published quarterly by the Idaho National Laboratory (INL) Quality and Performance Management Organization. The Department of Energy (DOE) Occurrence Reporting and Processing System (ORPS), as prescribed in DOE Order 232.2, “Occurrence Reporting and Processing of Operations Information,” requires a quarterly analysis of events, both reportable and not reportable, for the previous 12 months. This report is the analysis of 85 reportable events (18 from the 4th Qtr FY-15 and 67 from the prior three reporting quarters), as well as 25 other issue reports (including events found to be not reportable and Significant Category A and B conditions) identified at INL during the past 12 months (8 from this quarter and 17 from the prior three quarters).

  12. Idaho National Laboratory Site Environmental Monitoring Plan

    Energy Technology Data Exchange (ETDEWEB)

    Joanne L. Knight

    2010-10-01

    This plan describes environmental monitoring as required by U.S. Department of Energy (DOE) Order 450.1, “Environmental Protection Program,” and additional environmental monitoring currently performed by other organizations in and around the Idaho National Laboratory (INL). The objective of DOE Order 450.1 is to implement sound stewardship practices that protect the air, water, land, and other natural and cultural resources that may be impacted by DOE operations. This plan describes the organizations responsible for conducting environmental monitoring across the INL, the rationale for monitoring, the types of media being monitored, where the monitoring is conducted, and where monitoring results can be obtained. This plan presents a summary of the overall environmental monitoring performed in and around the INL without duplicating detailed information in the various monitoring procedures and program plans currently used to conduct monitoring.

  13. International Youth Nuclear Congress

    International Nuclear Information System (INIS)

    Fern, A.

    2017-01-01

    International Youth Nuclear Congress (IYNC) was Initiated by an international YG group of enthusiasts in 1997. Mission statement developed at ENC1998 in Nice, France Growth in enthusiasm and support: IAEA, Nuclear Societies, companies. IYNC run by the Young Generation with full support of experienced advisors, nuclear societies and companies. First came to African continent when IYNC 2010 was hosted by South Africa

  14. System of accounting and control of nuclear materials (MCA) relative to IAEA safeguards and improvement of radioecological situation of the Joint Stock Company ULBA Metallurgical Plant

    International Nuclear Information System (INIS)

    Kuznetsov, B.; Khadeev, V.; Antonov, N.; Gradelnikov, K.

    1996-01-01

    Following goals must be accomplished following this Project : - Develop computerized and automated MCA data system; - Provide up-to-date and reliable accounting and control of availability and transfer of nuclear materials, detect loss or theft of nuclear materials; - Improve book keeping of nuclear materials, provide paperwork for raw materials and finished products sales and purchase control, process nuclear materials shipment data; - Reduce sampling error and to obtain precise measure of nuclear materials to obtain ESADRA target values; - Thorium concentrates transfer preliminary released from raw Beryllium to the new storage to prevent environment radiation pollution and obvious fire accidents; - Improve radioecological situation of the territory caused by old storage dismantling and decontamination of site; - Improve accounting, storing and Physical Protection of Thorium Following is the proposal to obtain goals of the Project : - Develop accounting and control systems - Develop basic standards and procedures for MCA system - Develop users specifications of MCA data system - Develop software of MCA data system - Assembly and adjustment of local network at the production facilities - Automated MCA data system personnel training - Develop measurement system - Determination of the mistakes in sampling and measurement of Uranium and isotopes content - Develop the procedures of sampling and measurement of Uranium and isotopes content providing ESADRA target values - Develop measure control program covering scales and analytical equipment and measuring methods - Develop software for measure control program support - Thorium shipment, decontamination and improvement of Physical Protection of Thorium storage - Accounting of Thorium containing materials when transferring to the new storage - Arrange storage decontamination - Develop new systems of Thorium Containment/Surveillance and Physical Protection

  15. SAFER - Company Snapshot

    Data.gov (United States)

    Department of Transportation — The Company Snapshot is a concise electronic record of company identification, size, commodity information, and safety record, including the safety rating (if any),...

  16. Iodine-129 in the Snake River Plain Aquifer at and Near the Idaho National Laboratory, Idaho, 2003 and 2007

    Science.gov (United States)

    Bartholomay, Roy C.

    2009-01-01

    From 1953 to 1988, wastewater containing approximately 0.94 curies of iodine-129 (129I) was generated at the Idaho National Laboratory (INL) in southeastern Idaho. Almost all of this wastewater was discharged at or near the Idaho Nuclear Technology and Engineering Center (INTEC) on the INL site. Most of the wastewater was discharged directly into the eastern Snake River Plain aquifer through a deep disposal well until 1984; however, some wastewater also was discharged into unlined infiltration ponds or leaked from distribution systems below the INTEC. In 2003, the U.S. Geological Survey (USGS), in cooperation with the U.S. Department of Energy, collected samples for 129I from 36 wells used to monitor the Snake River Plain aquifer, and from one well used to monitor a perched zone at the INTEC. Concentrations of 129I in the aquifer ranged from 0.0000066 +- 0.0000002 to 0.72 +- 0.051 picocuries per liter (pCi/L). Many wells within a 3-mile radius of the INTEC showed decreases of as much as one order of magnitude in concentration from samples collected during 1990-91, and all of the samples had concentrations less than the Environmental Protection Agency's Maximum Contaminant Level (MCL) of 1 pCi/L. The average concentration of 129I in 19 wells sampled during both collection periods decreased from 0.975 pCi/L in 1990-91 to 0.249 pCi/L in 2003. These decreases are attributed to the discontinuation of disposal of 129I in wastewater after 1988 and to dilution and dispersion in the aquifer. Although water from wells sampled in 2003 near the INTEC showed decreases in concentrations of 129I compared with data collected in 1990-91, some wells south and east of the Central Facilities Area, near the site boundary, and south of the INL showed slight increases. These slight increases may be related to variable discharge rates of wastewater that eventually moved to these well locations as a mass of water from a particular disposal period. In 2007, the USGS collected samples for

  17. EG and G Idaho Environmental Protection Implementation Plan (1990)

    Energy Technology Data Exchange (ETDEWEB)

    Wickham, L.E.

    1990-11-01

    This report describes the EG G Idaho strategy for implementation of the Department of Energy (DOE) Order 5400.1 (a DOE-Headquarters directive establishing environmental protection program requirements, authorities, and responsibilities). Preparation of this Environmental Protection Implementation Plan is a requirement of DOE Order 5400.1. Additionally, this report is intended to supplement the Department of Energy--Idaho Operations Office (DOE-ID) Environmental Protection Implementation Plan by detailing EG G Idaho Environmental Protection Program activities. This report describes the current status of the EG G Idaho program, and the strategies for enhancing, as necessary, the current program to meet the requirements of DOE Order 5400.1. Aspects of the Environmental Protection Program included in this report are the assignment of responsibilities to specific EG G organizations, a schedule for completion of enhancements, if necessary, and requirements for documentation and reporting. 4 figs., 1 tab.

  18. Ergonomic assessments of three Idaho National Engineering Laboratory cafeterias

    Energy Technology Data Exchange (ETDEWEB)

    Ostrom, L.T.; Romero, H.A.; Gilbert, B.G.; Wilhelmsen, C.A.

    1993-01-01

    The Idaho National Engineering Laboratory is a Department of Energy facility that performs a variety of engineering and research projects. EG G Idaho is the prime contractor for the laboratory and, as such, performs the support functions in addition to technical, research, and development functions. As a part of the EG G Idaho Industrial Hygiene Initiative, ergonomic assessments were conducted at three Idaho National Engineering Laboratory Cafeterias. The purposes of the assessments were to determine whether ergonomic problems existed in the work places and, if so, to make recommendations to improve the work place and task designs. The study showed there were ergonomic problems in all three cafeterias assessed. The primary ergonomic stresses observed included wrist and shoulder stress in the dish washing task, postural stress in the dish washing and food preparation tasks, and back stress in the food handling tasks.

  19. Ergonomic assessments of three Idaho National Engineering Laboratory cafeterias

    Energy Technology Data Exchange (ETDEWEB)

    Ostrom, L.T.; Romero, H.A.; Gilbert, B.G.; Wilhelmsen, C.A.

    1993-05-01

    The Idaho National Engineering Laboratory is a Department of Energy facility that performs a variety of engineering and research projects. EG&G Idaho is the prime contractor for the laboratory and, as such, performs the support functions in addition to technical, research, and development functions. As a part of the EG&G Idaho Industrial Hygiene Initiative, ergonomic assessments were conducted at three Idaho National Engineering Laboratory Cafeterias. The purposes of the assessments were to determine whether ergonomic problems existed in the work places and, if so, to make recommendations to improve the work place and task designs. The study showed there were ergonomic problems in all three cafeterias assessed. The primary ergonomic stresses observed included wrist and shoulder stress in the dish washing task, postural stress in the dish washing and food preparation tasks, and back stress in the food handling tasks.

  20. EG and G Idaho environmental protection implementation plan

    International Nuclear Information System (INIS)

    Stump, R.C.

    1989-11-01

    This report describes the EG ampersand G Idaho strategy for implementation of the Department of Energy (DOE) Order 5400.1 (a DOE-Headquarters directive establishing environmental protection program requirements, authorities, and responsibilities). Preparation of this Environmental Protection Implementation Plan is a requirement of DOE Order 5400.0 Additionally, this report is intended to supplement the Department of Energy -- Idaho Operations Office (DOE-ID) Environmental Protection Implementation Plan by detailing EG ampersand G Idaho Environmental Protection Program activities. This report describes the current status of the EG ampersand G Idaho Program, and the strategies for enhancing, as necessary, the current program to meet the requirements of DOE Order 5400.1. Aspects of the Environmental Protection Program included in this report are the assignment of responsibilities to specific EG ampersand G organizations, a schedule for completion of enhancements, if necessary, and requirements for documentation and reporting. 3 figs., 1 tab

  1. Geothermal energy in Idaho: site data base and development status

    Energy Technology Data Exchange (ETDEWEB)

    1979-07-01

    The various factors affecting geothermal resource development are summarized for Idaho, including: resource data base, geological description, reservoir characteristics, environmental character, lease and development status, institutional factors, legal aspects, population and market, and development. (MHR)

  2. 75 FR 72719 - Approval and Promulgation of Implementation Plans; Idaho

    Science.gov (United States)

    2010-11-26

    ... result of implementing Idaho's PSD/NSR rules will be consistent with EPA's position on the Federal 2002... its NSR rules (Boise-Ada County CO, 67 FR 65713 (October 28, 2002; eff. December 27, 2002); Ada County...

  3. Issues behind Radiation management of workers at Fukushima Nuclear Power Plant of Tokyo Electric Power Company. From the viewpoint of radiation exposure of the ocular lens and the biological effects to the lens

    International Nuclear Information System (INIS)

    Hayashida, Toshiyuki; Sasaki, Hiroshi; Hatsusaka, Natsuko; Hamada, Nobuyuki; Tatsuzaki, Hideo; Akahane, Keiichi; Yokoyama, Sumi

    2017-01-01

    In March 2011, the accident occurred at the Fukushima Daiichi Nuclear Power Plant of Tokyo Electric Power Company. During recovery from critical situations, the radiation dose for some emergency workers exceeded the effective dose limit recommended for an emergency situation. A month after the accident, the International Commission on Radiological Protection issued a statement on tissue reactions recommending significant reduction of the equivalent dose limit to the lens of the eye. Many radiation workers will need to be involved in treatment of water contaminated with radionuclides, fuel debris retrieval, and decommissioning of reactors for a long period of time. Thus, the optimized radiation control in the fields, exposure reduction, prevention of tissue reactions, and reduction of stochastic risks for workers becomes necessary. This paper discusses issues in relation to radiation protection of the ocular lens in such recovery workers, from the viewpoint of radiation exposure of workers, its management, manifestations and mechanisms of the lens effects. (author)

  4. Final Environmental Statement related to the operation of Perry Nuclear Power Plant, Units 1 and 2 Docket Nos. 50-440 and 50-441, Cleveland Electric Illuminating Company

    International Nuclear Information System (INIS)

    1982-08-01

    The information in this Final Environmental Statement is the second assessment of the environmental impact associated with the construction and operation of the Perry Nuclear Power Plant, Units 1 and 2, located on Lake Erie in Lake County, about 11 km (7 mi) northeast of Painesville, Ohio. The first assessment was the Final Environmental Statement related to the construction of the plant issued in April 1974, prior to issuance of the construction permits (CPRR-148 and CPPR-149). Plant construction for Unit 1 is currently about 83% complete, and Unit 2 about 43% complete. Fuel loading for Units 1 and 2 currently estimated by the licensee (Cleveland Electric Illuminating Company) for November 1983, with Unit 2 fuel load scheduled for May 1987. The present assessment is the result of the NRC staff review of the activities associated with the proposed operation of the plant

  5. Decree no 96-761 from August 27, 1996 authorizing the company for industrial wastes and effluents conditioning to create a basic nuclear installation, named Centraco, in the town of Codolet (Gard department)

    International Nuclear Information System (INIS)

    Juppe, A.; Borotra, F.; Lepage, C.

    1996-01-01

    This decree from the French prime minister, the minister of environment and the minister of industry and postal services gives permission to the Socodei company to create a basic nuclear installation, named Centraco, in the town of Codolet (Gard department, France) for the selection, decontamination, valorization, treatment and conditioning of low radioactive effluents and wastes from French and foreign industries. The decree describes the Centraco installation (buildings, incineration and storage unit, maintenance unit). It summarizes the technical rules which must be applied concerning the quality assurance, the protection against risks of radioactive or chemical materials dissemination, the personnel and public protection against ionizing radiations, the control of environmental pollution with liquid and gaseous effluents, the reduction of volume and radioactivity of solid wastes, the transport and handling of radioactive materials, the protection against earthquakes and fire, the safety systems for plant operation, and the personnel training. (J.S.)

  6. Idaho National Laboratory FY12 Greenhouse Gas Report

    Energy Technology Data Exchange (ETDEWEB)

    Kimberly Frerichs

    2013-03-01

    A greenhouse gas (GHG) inventory is a systematic approach to account for the production and release of certain gases generated by an institution from various emission sources. The gases of interest are those that climate science has identified as related to anthropogenic global climate change. This document presents an inventory of GHGs generated during Fiscal Year (FY) 2012 by Idaho National Laboratory (INL), a Department of Energy (DOE) sponsored entity, located in southeastern Idaho.

  7. Idaho National Engineering Laboratory installation roadmap assumptions document

    International Nuclear Information System (INIS)

    1993-05-01

    This document is a composite of roadmap assumptions developed for the Idaho National Engineering Laboratory (INEL) by the US Department of Energy Idaho Field Office and subcontractor personnel as a key element in the implementation of the Roadmap Methodology for the INEL Site. The development and identification of these assumptions in an important factor in planning basis development and establishes the planning baseline for all subsequent roadmap analysis at the INEL

  8. Geothermal energy in Idaho: site data base and development status

    Energy Technology Data Exchange (ETDEWEB)

    McClain, D.V.

    1979-07-01

    A summary of known information about the nature of the resource, its potential for development, and the infrastructure of government which will guide future development is presented. Detailed site specific data regarding the commercialization potential of the proven, potential, and inferred geothermal resource areas in Idaho are included. Leasing and development status, institutional parameters, and a legal overview of geothermal resources in Idaho are given. (MHR)

  9. Review and evaluation of the Swedish Nuclear Fuel and Waste Management Company's RDandD Programme 2010. Statement to the Government and summary of the review report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-03-15

    SSM has reviewed and evaluated the RDandD programme 2010, in terms of planned research and development activity, reported research results, alternative handling and storage methods, and intended measures (Section 26 of the Nuclear Activities Ordinance). This report presents the results of the review and the evaluation. The RDandD programme 2010 has been circulated for national consultation by SSM to approximately 70 organisations.

  10. Review and evaluation of the Swedish Nuclear Fuel and Waste Management Company's RDandD Programme 2010. Statement to the Government and summary of the review report

    International Nuclear Information System (INIS)

    2011-03-01

    SSM has reviewed and evaluated the RDandD programme 2010, in terms of planned research and development activity, reported research results, alternative handling and storage methods, and intended measures (Section 26 of the Nuclear Activities Ordinance). This report presents the results of the review and the evaluation. The RDandD programme 2010 has been circulated for national consultation by SSM to approximately 70 organisations

  11. 1997 LMITCO Environmental Monitoring Program Report for the Idaho National Engineering and Environmental Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Andersen, B.; Street, L.; Wilhelmsen, R.

    1998-09-01

    This report describes the calendar year 1997 environmental surveillance and compliance monitoring activities of the Lockheed Martin Idaho Technologies Company Environmental Monitoring Program performed at the Idaho National Engineering and Environmental Laboratory. This report includes results of sampling performed by the Radiological Environmental Surveillance, Site Environmental Surveillance, Drinking Water, Effluent Monitoring, Storm Water Monitoring, Groundwater Monitoring, and Special Request Monitoring Programs and compares 1997 data with program-specific regulatory guidelines and past data to evaluate trends. The primary purposes of the surveillance and monitoring activities are to evaluate environmental conditions, to provide and interpret data, to verify compliance with applicable regulations or standard, and to ensure protection of human health and the environment. Surveillance of environmental media did not identify any previously unknown environmental problems or trends indicating a loss of control or unplanned releases from facility operations. With the exception of one nitrogen sample in the disposal pond effluent stream and iron and total coliform bacteria in groundwater downgradient from one disposal pond, compliance with permits and applicable regulations was achieved. Data collected by the Environmental Monitoring Program demonstrate that public health and the environment were protected.

  12. 1998 Environmental Monitoring Program Report for the Idaho National Engineering and Environmental Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    L. V. Street

    1999-09-01

    This report describes the calendar year 1998 compliance monitoring and environmental surveillance activities of the Lockheed Martin Idaho Technologies Company Environmental Monitoring Program performed at the Idaho National Engineering and Environmental Laboratory. This report includes results of sampling performed by the Drinking Water, Effluent, Storm Water, Groundwater Monitoring, and Environmental Surveillance Programs. This report compares the 1998 results to program-specific regulatory guidelines and past data to evaluate trends. The primary purposes of the monitoring and surveillance activities are to evaluate environmental conditions, to provide and interpret data, to verify compliance with applicable regulations or standards, and to ensure protection of public health and the environment. Surveillance of environmental media did not identify any previously unknown environmental problems or trends, which would indicate a loss of control or unplanned releases from facility operations. The INEEL complied with permits and applicable regulations, with the exception of nitrogen samples in a disposal pond effluent stream and iron and total coliform bacteria in groundwater downgradient from one disposal pond. Data collected by the Environmental Monitoring Program demonstrate that the public health and environment were protected.

  13. Nuclear news for all

    International Nuclear Information System (INIS)

    Anon.

    1981-01-01

    Fifty-seven percent of the employees of the Public Service Electric and Gas Company of Newark, NJ, answered No to the question: When people outside the company talk to you about nuclear power, do you feel you have enough information to adequately explain the company's position. Five booklets produced by the company's Advertising and Community Relations Department in July 1980 would have altered those results. The booklets (Nuclear Energy and the Environment, Low-Level Radiation, Nuclear Reactor Safety, Nuclear Waste Management and Disposal, and Alternative Energy Sources for Electric Generation) are summarized, and ordering information is given

  14. Environmental Survey preliminary report, Idaho National Engineering Laboratory, Idaho Falls, Idaho and Component Development and Integration Facility, Butte, Montana

    International Nuclear Information System (INIS)

    1988-09-01

    This report presents the preliminary findings of the first phase of the Environmental Survey of the United States Department of Energy's (DOE) Idaho National Engineering Laboratory (INEL) and Component Development and Integration Facility (CDIF), conducted September 14 through October 2, 1987. The Survey is being conducted by an interdisciplinary team of environmental specialists, led and managed by the Office of Environment, Safety and Health's Office of Environmental Audit. The team includes outside experts supplied by a private contractor. The objective of the Survey is to identify environmental problems and areas of environmental risk associated with the INEL and CDIF. The Survey covers all environmental media and all areas of environmental regulation. It is being performed in accordance with the DOE Environmental Survey Manual. The on-site phase of the Survey involves the review of existing site environmental data, observations of the operations' carried on at the INEL and the CDIF, and interviews with site personnel. The Survey team developed a Sampling and Analysis (S ampersand A) Plan to assist in further assessing certain of the environmental problems identified during its on-site activities. The S ampersand A Plan will be executed by the Oak Ridge National Laboratory. When completed, the S ampersand A results will be incorporated into the INEL/CDIF Survey findings for inclusion into the Environmental Survey Summary Report. 90 refs., 95 figs., 77 tabs

  15. Environmental Survey preliminary report, Idaho National Engineering Laboratory, Idaho Falls, Idaho and Component Development and Integration Facility, Butte, Montana

    Energy Technology Data Exchange (ETDEWEB)

    1988-09-01

    This report presents the preliminary findings of the first phase of the Environmental Survey of the United States Department of Energy's (DOE) Idaho National Engineering Laboratory (INEL) and Component Development and Integration Facility (CDIF), conducted September 14 through October 2, 1987. The Survey is being conducted by an interdisciplinary team of environmental specialists, led and managed by the Office of Environment, Safety and Health's Office of Environmental Audit. The team includes outside experts supplied by a private contractor. The objective of the Survey is to identify environmental problems and areas of environmental risk associated with the INEL and CDIF. The Survey covers all environmental media and all areas of environmental regulation. It is being performed in accordance with the DOE Environmental Survey Manual. The on-site phase of the Survey involves the review of existing site environmental data, observations of the operations' carried on at the INEL and the CDIF, and interviews with site personnel. The Survey team developed a Sampling and Analysis (S A) Plan to assist in further assessing certain of the environmental problems identified during its on-site activities. The S A Plan will be executed by the Oak Ridge National Laboratory. When completed, the S A results will be incorporated into the INEL/CDIF Survey findings for inclusion into the Environmental Survey Summary Report. 90 refs., 95 figs., 77 tabs.

  16. The results of an ecological risk assessment screening at the Idaho National Engineering`s waste area group 2

    Energy Technology Data Exchange (ETDEWEB)

    VanHorn, R.

    1995-11-01

    The Idaho National Engineering Laboratory (INEL) is a Department of Energy (DOE) facility located in southeastern Idaho and occupies approximately 890 square miles on the northwestern portion of the eastern Snake River Plain. INEL has been devoted to nuclear energy research and related activities since its establishment in 1949. In the process of fulfilling this mission, wastes were generated, including radioactive and hazardous materials. Most materials were effectively stored or disposed of, however, some release of contaminants to the environment has occurred. For this reason, the INEL was listed by the US environmental Protection Agency on the National Priorities List (NPL), in November, 1989. This report describes the results of an ecological risk assessment performed for the Waste Area Groups 2 (WAG 2) at the INEL. It also summarizes the performance of screening level ecological risk assessments (SLERA).

  17. The results of an ecological risk assessment screening at the Idaho National Engineering's waste area group 2

    International Nuclear Information System (INIS)

    VanHorn, R.

    1995-01-01

    The Idaho National Engineering Laboratory (INEL) is a Department of Energy (DOE) facility located in southeastern Idaho and occupies approximately 890 square miles on the northwestern portion of the eastern Snake River Plain. INEL has been devoted to nuclear energy research and related activities since its establishment in 1949. In the process of fulfilling this mission, wastes were generated, including radioactive and hazardous materials. Most materials were effectively stored or disposed of, however, some release of contaminants to the environment has occurred. For this reason, the INEL was listed by the US environmental Protection Agency on the National Priorities List (NPL), in November, 1989. This report describes the results of an ecological risk assessment performed for the Waste Area Groups 2 (WAG 2) at the INEL. It also summarizes the performance of screening level ecological risk assessments (SLERA)

  18. Idaho National Laboratory Site Pollution Prevention Plan

    International Nuclear Information System (INIS)

    E. D. Sellers

    2007-01-01

    It is the policy of the Department of Energy (DOE) that pollution prevention and sustainable environmental stewardship will be integrated into DOE operations as a good business practice to reduce environmental hazards, protect environmental resources, avoid pollution control costs, and improve operational efficiency and mission sustainability. In furtherance of this policy, DOE established five strategic, performance-based Pollution Prevention (P2) and Sustainable Environmental Stewardship goals and included them as an attachment to DOE O 450.1, Environmental Protection Program. These goals and accompanying strategies are to be implemented by DOE sites through the integration of Pollution Prevention into each site's Environmental Management System (EMS). This document presents a P2 and Sustainability Program and corresponding plan pursuant to DOE Order 450.1 and DOE O 435.1, Radioactive Waste Management. This plan is also required by the state of Idaho, pursuant to the Resource Conservation and Recovery Act (RCRA) partial permit. The objective of this document is to describe the Idaho National Laboratory (INL) Site P2 and Sustainability Program. The purpose of the program is to decrease the environmental footprint of the INL Site while providing enhanced support of its mission. The success of the program is dependent on financial and management support. The signatures on the previous page indicate INL, ICP, and AMWTP Contractor management support and dedication to the program. P2 requirements have been integrated into working procedures to ensure an effective EMS as part of an Integrated Safety Management System (ISMS). This plan focuses on programmatic functions which include environmentally preferable procurement, sustainable design, P2 and Sustainability awareness, waste generation and reduction, source reduction and recycling, energy management, and pollution prevention opportunity assessments. The INL Site P2 and Sustainability Program is administratively

  19. Idaho National Laboratory Site Pollution Prevention Plan

    Energy Technology Data Exchange (ETDEWEB)

    E. D. Sellers

    2007-03-01

    It is the policy of the Department of Energy (DOE) that pollution prevention and sustainable environmental stewardship will be integrated into DOE operations as a good business practice to reduce environmental hazards, protect environmental resources, avoid pollution control costs, and improve operational efficiency and mission sustainability. In furtherance of this policy, DOE established five strategic, performance-based Pollution Prevention (P2) and Sustainable Environmental Stewardship goals and included them as an attachment to DOE O 450.1, Environmental Protection Program. These goals and accompanying strategies are to be implemented by DOE sites through the integration of Pollution Prevention into each site's Environmental Management System (EMS). This document presents a P2 and Sustainability Program and corresponding plan pursuant to DOE Order 450.1 and DOE O 435.1, Radioactive Waste Management. This plan is also required by the state of Idaho, pursuant to the Resource Conservation and Recovery Act (RCRA) partial permit. The objective of this document is to describe the Idaho National Laboratory (INL) Site P2 and Sustainability Program. The purpose of the program is to decrease the environmental footprint of the INL Site while providing enhanced support of its mission. The success of the program is dependent on financial and management support. The signatures on the previous page indicate INL, ICP, and AMWTP Contractor management support and dedication to the program. P2 requirements have been integrated into working procedures to ensure an effective EMS as part of an Integrated Safety Management System (ISMS). This plan focuses on programmatic functions which include environmentally preferable procurement, sustainable design, P2 and Sustainability awareness, waste generation and reduction, source reduction and recycling, energy management, and pollution prevention opportunity assessments. The INL Site P2 and Sustainability Program is administratively

  20. Analysis of the General Electric Company swell tests with RELAP4/MOD7

    International Nuclear Information System (INIS)

    Fischer, S.R.; Hendrix, C.E.

    1979-01-01

    The RELAP4/MOD7 nuclear reactor transient analysis code, presently being developed by EG and G Idaho, Inc., will incorporate several significant improvements over earlier versions of RELAP4. As part of the development of RELAP4/MOD7, a thorough assessment of the capability of the code to simulate water reactor LOCA phenomena is being made. This assessment is accomplished in part by comparing results from code calculations with test data from experimental facilities. Simulations of the General Electric Company (GE) level swell tests were performed as part of the code checkout. In these tests, a pressurized vessel partially filled with nearly saturated water was blown down through a simulated break located near the top of the vessel. Comparison of RELAP4 calculations with data from these experiments indicates that the code has the capability to model the unequal phase velocity flow and resulting density gradients that might occur in a BWR steam line break transient. Comparisons of RELAP4 calculations with data from two level swell experiments are presented

  1. MERGER ACCOUTING FOR COMPANIES

    OpenAIRE

    SUCIU GHEORGHE

    2014-01-01

    Companies, especially nowadays, are characterized through great mobility, fast circulation of capital, occurring in their chase for profit. In this context, companies look for alliances, economical and political assistance. These objectives can materialize through merging of companies. The merger can be internal (between Romanian companies) or transboundary, which includes foreign companies. In order to correctly reflect these events, the merger operations must be regulated and mu...

  2. Idaho National Laboratory Cultural Resource Monitoring Report for 2013

    Energy Technology Data Exchange (ETDEWEB)

    Williams, Julie B. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2013-10-01

    This report describes the cultural resource monitoring activities of the Idaho National Laboratory’s (INL) Cultural Resource Management (CRM) Office during 2013. Throughout the year, thirty-eight cultural resource localities were revisited including: two locations with Native American human remains, one of which is also a cave; fourteen additional caves; seven prehistoric archaeological sites ; four historic archaeological sites; one historic trail; one nuclear resource (Experimental Breeder Reactor-I, a designated National Historic Landmark); and nine historic structures located at the Central Facilities Area. Of the monitored resources, thirty-three were routinely monitored, and five were monitored to assess project compliance with cultural resource recommendations along with the effects of ongoing project activities. On six occasions, ground disturbing activities within the boundaries of the Power Burst Facility/Critical Infrastructure Test Range Complex (PBF/CITRC) were observed by INL CRM staff prepared to respond to any additional finds of Native American human remains. In addition, two resources were visited more than once as part of the routine monitoring schedule or to monitor for additional damage. Throughout the year, most of the cultural resources monitored had no visual adverse changes resulting in Type 1determinations. However, Type 2 impacts were noted at eight sites, indicating that although impacts were noted or that a project was operating outside of culturally cleared limitations, cultural resources retained integrity and noted impacts did not threaten National Register eligibility. No new Type 3 or any Type 4 impacts that adversely impacted cultural resources and threatened National Register eligibility were observed at cultural resources monitored in 2013.

  3. Nuclear

    International Nuclear Information System (INIS)

    Anon.

    2000-01-01

    The first text deals with a new circular concerning the collect of the medicine radioactive wastes, containing radium. This campaign wants to incite people to let go their radioactive wastes (needles, tubes) in order to suppress any danger. The second text presents a decree of the 31 december 1999, relative to the limitations of noise and external risks resulting from the nuclear facilities exploitation: noise, atmospheric pollution, water pollution, wastes management and fire prevention. (A.L.B.)

  4. Idaho radionuclide exposure study: Literature review

    International Nuclear Information System (INIS)

    Baker, E.G.; Freeman, H.D.; Hartley, J.N.

    1987-10-01

    Phosphate ores contain elevated levels of natural radioactivity, some of which is released to the environment during processing or use of solid byproducts. The effect of radionuclides from Idaho phosphate processing operations on the local communities has been the subject of much research and study. The literature is reviewed in this report. Two primary radionuclide pathways to the environment have been studied in detail: (1) airborne release of volatile radionuclides, primarily 210 Po, from calciner stacks at the two elemental phosphorus plants; and (2) use of byproduct slag as an aggregate for construction in Soda Springs and Pocatello. Despite the research, there is still no clear understanding of the population dose from radionuclide emissions, effluents, and solid wastes from phosphate processing plants. Two other potential radionuclide pathways to the environment have been identified: radon exhalation from phosphogypsum and ore piles and contamination of surface and ground waters. Recommendations on further study needed to develop a data base for a complete risk assssment are given in the report

  5. Idaho Operations Office: Technology summary, June 1994

    International Nuclear Information System (INIS)

    1994-06-01

    This document has been prepared by the Department of Energy's (DOE) Environmental Management (EM) Office of Technology Development (OTD) in order to highlight research, development, demonstration, testing, and evaluation (RDDT ampersand E) activities funded through the Idaho Operations Office. Technologies and processes described have the potential to enhance DOE's cleanup and waste management efforts, as well as improve US industry's competitiveness in global environmental markets. OTD programs are designed to make new, innovative, and more cost-effective technologies available for transfer to DOE environmental restoration and waste management end-users. Projects are demonstrated, tested, and evaluated to produce solutions to current problems. Transition of technologies into more advanced stages of development is based upon technological, regulatory, economic, and institutional criteria. New technologies are made available for use in eliminating radioactive, hazardous, and other wastes in compliance with regulatory mandates. The primary goal is to protect human health and prevent further contamination. OTD's technology development programs address three major problem areas: (1) groundwater and soils cleanup; (2) waste retrieval and processing; and (3) pollution prevention. These problems are not unique to DOE, but are associated with other Federal agency and industry sites as well. Thus, technical solutions developed within OTD programs will benefit DOE, and should have direct applications in outside markets

  6. TAP Report - Southwest Idaho Juniper Working Group

    Energy Technology Data Exchange (ETDEWEB)

    Gresham, Garold Linn [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2015-09-01

    There is explicit need for characterization of the materials for possible commercialization as little characterization data exists. Pinyon-juniper woodlands are a major ecosystem type found in the Southwest and the Intermountain West regions of the United States including Nevada, Idaho and Oregon. These widespread ecosystems are characterized by the presence of several different species of pinyon and juniper as the dominant plant cover. Since the 1800s, pinyon-juniper woodlands have rapidly expanded their range at the expense of existing ecosystems. Additionally, existing woodlands have become denser, progressively creating potential fire hazards as seen in the Soda Fire, which burned more than 400 sq. miles. Land managers responsible for these areas often desire to reduce pinyon-juniper coverage on their lands for a variety of reasons, as stated in the Working Group objectives. However, the cost of clearing thinning pinyon-juniper stands can be prohibitive. One reason for this is the lack of utilization options for the resulting biomass that could help recover some of the cost of pinyon-juniper stand management. The goal of this TAP effort was to assess the feedstock characteristics of biomass from a juniper harvested from Owyhee County to evaluate possible fuel and conversion utilization options.

  7. Idaho National Laboratory Site Environmental Monitoring Plan

    Energy Technology Data Exchange (ETDEWEB)

    Nordstrom, Jenifer [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2014-02-01

    This plan provides a high-level summary of environmental monitoring performed by various organizations within and around the Idaho National Laboratory (INL) Site as required by U.S. Department of Energy (DOE) Order 435.1, Radioactive Waste Management, and DOE Order 458.1, Radiation Protection of the Public and the Environment, Guide DOE/EH-0173T, Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance, and in accordance with 40 Code of Federal Regulations (CFR) 61, National Emission Standards for Hazardous Air Pollutants. The purpose of these orders is to 1) implement sound stewardship practices that protect the air, water, land, and other natural and cultural resources that may be impacted by DOE operations, and 2) to establish standards and requirements for the operations of DOE and DOE contractors with respect to protection of the environment and members of the public against undue risk from radiation. This plan describes the organizations responsible for conducting environmental monitoring across the INL Site, the rationale for monitoring, the types of media being monitored, where the monitoring is conducted, and where monitoring results can be obtained. Detailed monitoring procedures, program plans, or other governing documents used by contractors or agencies to implement requirements are referenced in this plan. This plan covers all planned monitoring and environmental surveillance. Non-routine activities such as special research studies and characterization of individual sites for environmental restoration are outside the scope of this plan.

  8. Idaho Operations Office: Technology summary, June 1994

    Energy Technology Data Exchange (ETDEWEB)

    1994-06-01

    This document has been prepared by the Department of Energy`s (DOE) Environmental Management (EM) Office of Technology Development (OTD) in order to highlight research, development, demonstration, testing, and evaluation (RDDT&E) activities funded through the Idaho Operations Office. Technologies and processes described have the potential to enhance DOE`s cleanup and waste management efforts, as well as improve US industry`s competitiveness in global environmental markets. OTD programs are designed to make new, innovative, and more cost-effective technologies available for transfer to DOE environmental restoration and waste management end-users. Projects are demonstrated, tested, and evaluated to produce solutions to current problems. Transition of technologies into more advanced stages of development is based upon technological, regulatory, economic, and institutional criteria. New technologies are made available for use in eliminating radioactive, hazardous, and other wastes in compliance with regulatory mandates. The primary goal is to protect human health and prevent further contamination. OTD`s technology development programs address three major problem areas: (1) groundwater and soils cleanup; (2) waste retrieval and processing; and (3) pollution prevention. These problems are not unique to DOE, but are associated with other Federal agency and industry sites as well. Thus, technical solutions developed within OTD programs will benefit DOE, and should have direct applications in outside markets.

  9. Application of quality assurance to a company in change

    International Nuclear Information System (INIS)

    Churchill, G.F.; Smith, C.R.

    1994-01-01

    The effect of change, particularly in the field of quality assurance, is examined for NNC, an engineering design, project management and consultancy company formed from the industrial group responsible for nuclear power station construction in the United Kingdom. The role of the company has changed over the past six years moving from being a single supplier for turnkey cost-plus nuclear power station projects to competing in the open market for contracts in diverse nuclear and non-nuclear projects. Changes in working practices needed to accommodate new business roles has been driven, in part, by the development and application of the company's quality system, described in this article. (UK)

  10. Radioactivity leakage accidents in the feed water heater and the general drainage of the Tsuruga Nuclear Power Station of Japan Atomic Power Company

    International Nuclear Information System (INIS)

    1981-01-01

    In the Tsuruga Nuclear Power Station, JAPC on the shell on extracted-steam side in B system of No. 4 feed water heater, drain water leakage occurred twice in January, 1981. Then, 61 pCi/g cobalt-60 and 10 pCi/g manganese-54 were detected in soil at the outlet of general drainage on April 17, 1981. The cause was found to be the overflow of radioactive liquid waste in the filter sludge storage tank on March 8, the same year. On-the-spot inspection was subsequently made by the Agency of Natural Resources and Energy on both leakage accidents. The results of inspections are described as follows: the course of leakage accident, and also the measures taken to JAPC in connection with the two leakage accidents. (J.P.N.)

  11. 77 FR 39695 - Idaho Power Company; Notice of Availability of Draft Environmental Assessment

    Science.gov (United States)

    2012-07-05

    ...-102 and P-2061-086. For further information, contact Rachel Price by telephone at 202- 502-8907 or by email at Rachel[email protected] . Dated: June 26, 2012. Kimberly D. Bose, Secretary. [FR Doc. 2012-16367...

  12. 78 FR 53819 - Union Pacific Railroad Company-Abandonment Exemption-in Canyon County, Idaho

    Science.gov (United States)

    2013-08-30

    ... been met. As a condition to this exemption, any employee adversely affected by the abandonment shall be... protects affected employees, a petition for partial revocation under 49 U.S.C. 10502(d) must be filed... environment and historic resources. OEA will issue an environmental assessment (EA) by September 6, 2013...

  13. 75 FR 32450 - Idaho Power Company; Notice of Application for Amendment of License and Soliciting Comments...

    Science.gov (United States)

    2010-06-08

    .... Name of Project: C.J. Strike Hydroelectric Project. f. Location: The project is located on the Snake... Snake River. l. Locations of the Application: A copy of the application is available for inspection and reproduction at the Commission's Public Reference Room, located at 888 First Street, NE., Room 2A, Washington...

  14. 76 FR 51016 - Idaho Power Company; Notice of Application for Amendment of License and Soliciting Comments...

    Science.gov (United States)

    2011-08-17

    .... Name of Project: Twin Falls Hydroelectric Project. f. Location: This project is located on the Snake... application is available for inspection and reproduction at the Commission's Public Reference Room, located at... available for inspection and reproduction at the address in item (h) above. m. Individuals desiring to be...

  15. 78 FR 38872 - Approval and Promulgation of Air Quality Implementation Plans; Idaho Amalgamated Sugar Company...

    Science.gov (United States)

    2013-06-28

    ... be controlled with spray-dry flue gas desulfurization (spray-dry FGD); and NO x : 186 lbs/hr and...) Boilers 1 and 2, and the South, Center, and North Pulp dryers. The alternative measure replaces the spray...-BART units. The pulp dryers were shutdown because installation of a drying process using waste steam...

  16. Evaluation of the impact of technology transfers between public research laboratories and industrial companies. The case of the French nuclear authority

    International Nuclear Information System (INIS)

    Petit, Serge

    1999-12-01

    Public research institutions are increasingly expected to evaluate the economic impact of their research, but the generally available impact indicators are not satisfactory. This research develops indicators that grasp with greater detail the effects that are induced by R and D collaborations between a laboratory and a firm. Seven such indicators are being developed on the empirical evidence of twenty two R and D projects of the French Nuclear Authority (CEA). Functional relationships are being sought between these indicators and a couple of explanatory variables that stand for the profile of the innovating firm, the features of the collaboration and of the launched innovation. Kohonen's algorithm allows to extract robust associations between indicators and their determinants, thus founding a sort of 'mixed' methodology that relies on the principles of monograph observations and statistical data mining. Three kinds of results are derived from the empirical work: - the production of indicators that are complementary to the currently-used impact indicator, namely the innovation-induced turnover, and the definition of the scenarios in which they apply; - the evidence of a link between different ways of organising collaborative R and D projects and the underlying industrial objectives; - some guidelines for the construction of revenue-optimising contracts for the CEA. The results illustrate the immaterial dimension of technology and its importance in economic terms. The linear model, in spite of the criticism, is shown to produce interesting results in some cases. (author) [fr

  17. Idaho: basic data for thermal springs and wells as recorded in GEOTHERM, Part A

    Energy Technology Data Exchange (ETDEWEB)

    Bliss, J.D.

    1983-07-01

    All chemical data for geothermal fluids in Idaho available as of December 1981 is maintained on GEOTHERM, computerized information system. This report presents summaries and sources of records for Idaho. 7 refs. (ACR)

  18. 76 FR 10018 - Environmental Management Site-Specific Advisory Board, Idaho National Laboratory

    Science.gov (United States)

    2011-02-23

    ... Idaho's 2015 Cleanup Vision Government Budget Cycle American Recovery and Reinvestment Act Idaho Cleanup.... The Deputy Designated Federal Officer is empowered to conduct the meeting in a fashion that will...

  19. 75 FR 42432 - Northern Natural Gas Company, Southern Natural Gas Company, Florida Gas Transmission Company, LLC...

    Science.gov (United States)

    2010-07-21

    ... Natural Gas Company, Southern Natural Gas Company, Florida Gas Transmission Company, LLC, Transcontinental... abandonment of facilities by Northern Natural Gas Company, Southern Natural Gas Company, Florida Gas... resources, fisheries, and wetlands; Cultural resources; Vegetation and wildlife; Endangered and threatened...

  20. US DOE Idaho national laboratory reactor decommissioning

    International Nuclear Information System (INIS)

    Szilagyi, Andrew

    2012-01-01

    The United States Department of Energy (DOE) primary contractor, CH2M-WG Idaho was awarded the cleanup and deactivation and decommissioning contract in May 2005 for the Idaho National Lab (INL). The scope of this work included dispositioning over 200 Facilities and 3 Reactors Complexes (Engineering Test Reactor (ETR), Materials Test Reactor (MTR) and Power Burst Facility (PBF) Reactor). Two additional reactors were added to the scope of the contract during the period of performance. The Zero Power Physics Reactor (ZPPR) disposition was added under a separate subcontractor with the INL lab contractor and the Experimental Breeder Reactor II (EBR-II) disposition was added through American Recovery and Reinvestment Act (ARRA) Funding. All of the reactors have been removed and disposed of with the exception of EBR-II which is scheduled for disposition approximately March of 2012. A brief synopsis of the 5 reactors is provided. For the purpose of this paper the ZPPR reactor due to its unique design as compared to the other four reactors, and the fact that is was relatively lightly contaminated and irradiated will not be discussed with the other four reactors. The ZPPR reactor was readily accessible and was a relatively non-complex removal as compared to the other reactors. Additionally the EBR-II reactor is currently undergoing D and D and will have limited mention in this paper. Prior to decommissioning the reactors, a risk based closure model was applied. This model exercised through the Comprehensive Environmental Response, Compensation and Liability Act (CERCLA), Non-Time Critical Removal Action (NTCRA) Process which evaluated several options. The options included; No further action - maintain as is, long term stewardship and monitoring (mothball), entombment in place and reactor removal. Prior to commencing full scale D and D, hazardous constituents were removed including cadmium, beryllium, sodium (passivated and elemental), PCB oils and electrical components, lead

  1. Electric Holding Company Areas

    Data.gov (United States)

    Department of Homeland Security — Holding companies are electric power utilities that have a holding company structure. This vector polygon layer represents the area served by electric power holding...

  2. Nuclear energy in Spain

    International Nuclear Information System (INIS)

    Villota, C. de

    2007-01-01

    Carlos Villota. Director of Nuclear Energy of UNESA gave an overview of the Spanish nuclear industry, the utility companies and the relevant institutions. Companies of the nuclear industry include firms that produce heavy components or equipment (ENSA), manufacturers of nuclear fuel (ENUSA), engineering companies, the National Company for Radioactive Waste Management (ENRESA), and nuclear power plants (nine units at seven sites). Nuclear energy is a significant component of the energy mix in Spain: 11% of all energy produced in Spain is of nuclear origin, whilst the share of nuclear energy in the total electricity generation is approximately 23%. The five main players of the energy sector that provide for the vast majority of electricity production, distribution, and supply have formed the Spanish Electricity Industry Association (UNESA). The latter carries out co-ordination, representation, management and promotion tasks for its members, as well as the protection of their business and professional interests. In the nuclear field, UNESA through its Nuclear Energy Committee co-ordinates aspects related to nuclear safety and radiological protection, regulation, NPP operation and R and D. Regarding the institutional framework of the nuclear industry, ENSA, ENUSA and ENRESA are controlled by the national government through the Ministry of Economy and Finance and the Ministry of Science and Technology. All companies of the nuclear industry are licensed by the Ministry of Industry, Tourism and Trade (MITYC), while the regulatory body is the Nuclear Safety Council (CSN). It is noteworthy that CSN is independent of the government, as it reports directly to Parliament. (author)

  3. Idaho National Engineering and Environmental Laboratory Site Report on the Production and Use of Recycled Uranium

    Energy Technology Data Exchange (ETDEWEB)

    L. C. Lewis; D. C. Barg; C. L. Bendixsen; J. P. Henscheid; D. R. Wenzel; B. L. Denning

    2000-09-01

    Recent allegations regarding radiation exposure to radionuclides present in recycled uranium sent to the gaseous diffusion plants prompted the Department of Energy to undertake a system-wide study of recycled uranium. Of particular interest, were the flowpaths from site to site operations and facilities in which exposure to plutonium, neptunium and technetium could occur, and to the workers that could receive a significant radiation dose from handling recycled uranium. The Idaho National Engineering and Environmental Laboratory site report is primarily concerned with two locations. Recycled uranium was produced at the Idaho Chemical Processing Plant where highly enriched uranium was recovered from spent fuel. The other facility is the Specific Manufacturing Facility (SMC) where recycled, depleted uranium is manufactured into shapes for use by their customer. The SMC is a manufacturing facility that uses depleted uranium metal as a raw material that is then rolled and cut into shapes. There are no chemical processes that might concentrate any of the radioactive contaminant species. Recyclable depleted uranium from the SMC facility is sent to a private metallurgical facility for recasting. Analyses on the recast billets indicate that there is no change in the concentrations of transuranics as a result of the recasting process. The Idaho Chemical Processing Plant was built to recover high-enriched uranium from spent nuclear fuel from test reactors. The facility processed diverse types of fuel which required uniquely different fuel dissolution processes. The dissolved fuel was passed through three cycles of solvent extraction which resulted in a concentrated uranyl nitrate product. For the first half of the operating period, the uranium was shipped as the concentrated solution. For the second half of the operating period the uranium solution was thermally converted to granular, uranium trioxide solids. The dose reconstruction project has evaluated work exposure and

  4. Global oil company profiles

    International Nuclear Information System (INIS)

    1997-01-01

    Global Oil Company Profiles provides a comprehensive review of 50 of the top oil companies in the world. Each chapter is devoted to an individual company, providing an invaluable insight into the organisation, its structure and operations. Using the most recent data available, the report offers an up-to-date analysis of performance and future direction, as well as a unique benchmarking system for each company profiled. (author)

  5. Global gas company profiles

    International Nuclear Information System (INIS)

    1997-01-01

    This report provides a detailed assessment of 60 of the top gas companies form around the world, analysing them according to their internal dynamics and in relation to their competitors. It devotes each chapter to an individual company, providing invaluable insight into the organisation's operational background, financial performance and strategic goals. Using the most up-to-date information available, Global Gas Company Profiles allows you to make detailed analysis of each company's performance and future direction. (author)

  6. Occupational radiation exposure history of Idaho Field Office Operations at the INEL

    International Nuclear Information System (INIS)

    Horan, J.R.; Braun, J.B.

    1993-10-01

    An extensive review has been made of the occupational radiation exposure records of workers at the Idaho National Engineering Laboratory (INEL) over the period of 1951 through 1990. The focus has been on workers employed by contractors and employees of the Idaho Field Operations Office (ID) of the United States Department of Energy (USDOE) and does not include the Naval Reactors Facility (NRF), the Argonne National Laboratory (ANL), or other operations field offices at the INEL. The radiation protection guides have decreased from 15 rem/year to 5 rem/year in 1990 for whole body penetrating radiation exposure. During these 40 years of nuclear operations (in excess of 200,000 man-years of work), a total of twelve individuals involved in four accidents exceeded the annual guidelines for exposure; nine of these exposures were received during life saving efforts on January 3, 1961 following the SL-1 reactor accident which killed three military personnel. These exposures ranged from 8 to 27 rem. Only one individual has exceeded the annual whole body penetrating radiation protection guidelines in the last 29 years

  7. Long-term surveillance plan for the Lowman, Idaho, disposal site

    International Nuclear Information System (INIS)

    1993-09-01

    The long-term surveillance plan (LTSP) for the Lowman, Idaho, Uranium Mill Tailings Remedial Action (UMTRA) Project disposal site describes the surveillance activities for the Lowman disposal cell. The US Department of Energy (DOE) will carry out these activities to ensure that the disposal cell continues to function as designed. This preliminary final LTSP is being submitted to the US Nuclear Regulatory Commission (NRC) as a requirement for issuance of a general license for custody and long-term care for the disposal site. The general license requires that the disposal cell be cared for in accordance with the provisions of this LTSP. The LTSP documents whether the land and interests are owned by the United States or an Indian tribe, and describes, in detail, how the long-term care of the disposal site will be carried out through the UMTRA Project long-term surveillance program. The Lowman, Idaho, LTSP is based on the DOE's Guidance for Implementing the UMTRA Project Long-term Surveillance Program, (DOE, 1992)

  8. A case study for evaluating ecological risks at the Idaho National Engineering Laboratory (INEL)

    International Nuclear Information System (INIS)

    Peterson, S.; Brewer, R.; Morris, R.; VanHorn, R.

    1994-01-01

    A case study was conducted as a component of the development of guidance for ecological risk assessment at the Department of Energy's Idaho National Engineering Laboratory (INEL). The INEL is a large facility in southeastern Idaho, encompassing expanses of sagebrush-steppe that harbor numerous wildlife species. Nuclear research and waste disposal activities have resulted in releases of radionuclides at various sites. Due to the size and number of potentially contaminated areas, a cost-effective method was needed to evaluate ecological risks and to identify data needs for remedial investigations. Screening-level assessment approaches were developed to evaluate data collected from previous site investigations. Above-background concentrations of radionuclides and other contaminants in media were compared to risk-based criteria, which were derived from sources such as recent publications of the International Atomic Energy Agency (IAEA) and National Council on Radiation Protection and Measurements (NCRP). Site-specific risks to plants and wildlife were estimated for contaminants exceeding criteria. Dose rates derived using various estimation methods were compared to reference doses for wildlife obtained from IAEA, NCRP, and other publications

  9. A survey of process control computers at the Idaho Chemical Processing Plant

    International Nuclear Information System (INIS)

    Dahl, C.A.

    1989-01-01

    The Idaho Chemical Processing Plant (ICPP) at the Idaho National Engineering Laboratory is charged with the safe processing of spent nuclear fuel elements for the United States Department of Energy. The ICPP was originally constructed in the late 1950s and used state-of-the-art technology for process control at that time. The state of process control instrumentation at the ICPP has steadily improved to keep pace with emerging technology. Today, the ICPP is a college of emerging computer technology in process control with some systems as simple as standalone measurement computers while others are state-of-the-art distributed control systems controlling the operations in an entire facility within the plant. The ICPP has made maximal use of process computer technology aimed at increasing surety, safety, and efficiency of the process operations. Many benefits have been derived from the use of the computers for minimal costs, including decreased misoperations in the facility, and more benefits are expected in the future

  10. Occupational radiation exposure history of Idaho Field Office Operations at the INEL

    Energy Technology Data Exchange (ETDEWEB)

    Horan, J.R.; Braun, J.B.

    1993-10-01

    An extensive review has been made of the occupational radiation exposure records of workers at the Idaho National Engineering Laboratory (INEL) over the period of 1951 through 1990. The focus has been on workers employed by contractors and employees of the Idaho Field Operations Office (ID) of the United States Department of Energy (USDOE) and does not include the Naval Reactors Facility (NRF), the Argonne National Laboratory (ANL), or other operations field offices at the INEL. The radiation protection guides have decreased from 15 rem/year to 5 rem/year in 1990 for whole body penetrating radiation exposure. During these 40 years of nuclear operations (in excess of 200,000 man-years of work), a total of twelve individuals involved in four accidents exceeded the annual guidelines for exposure; nine of these exposures were received during life saving efforts on January 3, 1961 following the SL-1 reactor accident which killed three military personnel. These exposures ranged from 8 to 27 rem. Only one individual has exceeded the annual whole body penetrating radiation protection guidelines in the last 29 years.

  11. Industrial application of geothermal energy in Southeast Idaho

    Energy Technology Data Exchange (ETDEWEB)

    Batdorf, J.A.; McClain, D.W.; Gross, M.; Simmons, G.M.

    1980-02-01

    Those phosphate related and food processing industries in Southeastern Idaho are identified which require large energy inputs and the potential for direct application of geothermal energy is assessed. The total energy demand is given along with that fractional demand that can be satisfied by a geothermal source of known temperature. The potential for geothermal resource development is analyzed by examining the location of known thermal springs and wells, the location of state and federal geothermal exploration leases, and the location of federal and state oil and gas leasing activity in Southeast Idaho. Information is also presented regarding the location of geothermal, oil, and gas exploration wells in Southeast Idaho. The location of state and federal phosphate mining leases is also presented. This information is presented in table and map formats to show the proximity of exploration and development activities to current food and phosphate processing facilities and phosphate mining activities. (MHR)

  12. Field review of fish habitat improvement projects in central Idaho

    International Nuclear Information System (INIS)

    Beschta, R.L.; Griffith, J.; Wesche, T.A.

    1993-05-01

    The goal of this field review was to provide information to the Bonneville Power Administration (BPA) regarding previous and ongoing fish habitat improvement projects in central Idaho. On July 14, 1992, the review team met at the Sawtooth National Recreation Area office near Ketchum, Idaho, for a slide presentation illustrating several habitat projects during their construction phases. Following the slide presentation, the review team inspected fish habitat projects that have been implemented in the last several years in the Stanley Basin and adjacent valleys. At each site the habitat project was described to the field team and a brief period for project inspection followed. The review team visited approximately a dozen sites on the Challis, Sawtooth, and Boise National Forests over a period of approximately two and a half days. There are two objectives of this review namely to summarize observations for specific field sites and to provide overview commentary regarding the BPA habitat improvement program in central Idaho

  13. Geothermometric evaluation of geothermal resources in southeastern Idaho

    Science.gov (United States)

    Neupane, G.; Mattson, E. D.; McLing, T. L.; Palmer, C. D.; Smith, R. W.; Wood, T. R.; Podgorney, R. K.

    2016-01-01

    Southeastern Idaho exhibits numerous warm springs, warm water from shallow wells, and hot water from oil and gas test wells that indicate a potential for geothermal development in the area. We have estimated reservoir temperatures from chemical composition of thermal waters in southeastern Idaho using an inverse geochemical modeling technique (Reservoir Temperature Estimator, RTEst) that calculates the temperature at which multiple minerals are simultaneously at equilibrium while explicitly accounting for the possible loss of volatile constituents (e.g., CO2), boiling and/or water mixing. The temperature estimates in the region varied from moderately warm (59 °C) to over 175 °C. Specifically, hot springs near Preston, Idaho, resulted in the highest reservoir temperature estimates in the region.

  14. Section 1: Company directory

    International Nuclear Information System (INIS)

    Anon.

    1991-01-01

    This is a 1992 directory of those companies doing business in all areas of the independent power producers industry. The listing includes the company name, address, telephone and FAX numbers, and the name of a company contact. The listing is international in scope

  15. Idaho Marketing Education Core Curriculum. Career Sustaining Level, Specialist Level, Supervisory Level, Entrepreneurial Level.

    Science.gov (United States)

    Miller, Linda Wise; Winn, Richard

    This document contains Idaho's marketing education (ME) core curriculum. Presented first are a list of 22 ME strategies that are aligned with the Idaho State Division of Vocational-Technical Education's strategic plan and a chart detailing the career pathways of ME in Idaho (arts and communication, business and management, health services, human…

  16. Results of special security inspection on improvement of security management setup in Head Office and Tsuruga Nuclear Power Station of the Japan Atomic Power Company and improvement of facilities in Tsuruga Nuclear Power Station

    International Nuclear Information System (INIS)

    1982-01-01

    In connection with the series of accidents in the Tsuruga Nuclear Power Station, the Agency of Natural Resources and Energy had instructed JAPC to make comprehensive inspection on the security management setup and to take improvement measures in the nuclear power station. The results of the subsequent inspection by ANRE confirmed that the improvements made by JAPC are adequate, and the following items are described: improvement of security management setup - communication and reporting in emergency, the management of inspection and maintenance records, work control and supervision in repair, improvement, etc., functional authority and responsibility in maintenance management, operation management, radiation control, personnel education; improvement of facilities - feed water heaters, laundry waste-water filter room, radioactive waste treatment facility, general drainage, concentrated waste liquid storage tanks in newly-built waste treatment building, etc. (J.P.N.)

  17. Mixed waste treatment at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Larsen, M.M.; Hunt, L.F.; Sanow, D.J.

    1988-01-01

    The Idaho Operations Office of the Department of Energy (DOE) made the decision in 1984 to prohibit the disposal of mixed waste (MW) (combustible waste-toxic metal waste) in the Idaho National Engineering Laboratory (INEL) low-level radioactive waste (LLW) disposal facility. As a result of this decision and due to there being no EPA-permitted MW treatment/storage/disposal (T/S/D) facilities, the development of waste treatment methods for MW was initiated and a storage facility was established to store these wastes while awaiting development of treatment systems. This report discusses the treatment systems developed and their status. 3 refs., 2 figs., 1 tab

  18. Idaho National Laboratory Emergency Readiness Assurance Plan - Fiscal Year 2015

    Energy Technology Data Exchange (ETDEWEB)

    Farmer, Carl J. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2015-09-01

    Department of Energy Order 151.1C, Comprehensive Emergency Management System requires that each Department of Energy field element documents readiness assurance activities, addressing emergency response planning and preparedness. Battelle Energy Alliance, LLC, as prime contractor at the Idaho National Laboratory (INL), has compiled this Emergency Readiness Assurance Plan to provide this assurance to the Department of Energy Idaho Operations Office. Stated emergency capabilities at the INL are sufficient to implement emergency plans. Summary tables augment descriptive paragraphs to provide easy access to data. Additionally, the plan furnishes budgeting, personnel, and planning forecasts for the next 5 years.

  19. Geochemistry of groundwater in the eastern Snake River Plain aquifer, Idaho National Laboratory and vicinity, eastern Idaho

    Science.gov (United States)

    Rattray, Gordon W.

    2018-05-30

    Nuclear research activities at the U.S. Department of Energy (DOE) Idaho National Laboratory (INL) in eastern Idaho produced radiochemical and chemical wastes that were discharged to the subsurface, resulting in detectable concentrations of some waste constituents in the eastern Snake River Plain (ESRP) aquifer. These waste constituents may pose risks to the water quality of the aquifer. In order to understand these risks to water quality the U.S. Geological Survey, in cooperation with the DOE, conducted a study of groundwater geochemistry to improve the understanding of hydrologic and chemical processes in the ESRP aquifer at and near the INL and to understand how these processes affect waste constituents in the aquifer.Geochemistry data were used to identify sources of recharge, mixing of water, and directions of groundwater flow in the ESRP aquifer at the INL. The geochemistry data were analyzed from 167 sample sites at and near the INL. The sites included 150 groundwater, 13 surface-water, and 4 geothermal-water sites. The data were collected between 1952 and 2012, although most data collected at the INL were collected from 1989 to 1996. Water samples were analyzed for all or most of the following: field parameters, dissolved gases, major ions, dissolved metals, isotope ratios, and environmental tracers.Sources of recharge identified at the INL were regional groundwater, groundwater from the Little Lost River (LLR) and Birch Creek (BC) valleys, groundwater from the Lost River Range, geothermal water, and surface water from the Big Lost River (BLR), LLR, and BC. Recharge from the BLR that may have occurred during the last glacial epoch, or paleorecharge, may be present at several wells in the southwestern part of the INL. Mixing of water at the INL primarily included mixing of surface water with groundwater from the tributary valleys and mixing of geothermal water with regional groundwater. Additionally, a zone of mixing between tributary valley water and

  20. Iodine-129 in the eastern Snake River Plain aquifer at and near the Idaho National Laboratory, Idaho, 2010-12

    Science.gov (United States)

    Bartholomay, Roy C.

    2013-01-01

    From 1953 to 1988, approximately 0.941 curies of iodine-129 (129I) were contained in wastewater generated at the Idaho National Laboratory (INL) with almost all of this wastewater discharged at or near the Idaho Nuclear Technology and Engineering Center (INTEC). Most of the wastewater containing 129I was discharged directly into the eastern Snake River Plain (ESRP) aquifer through a deep disposal well until 1984; lesser quantities also were discharged into unlined infiltration ponds or leaked from distribution systems below the INTEC. During 2010–12, the U.S. Geological Survey in cooperation with the U.S. Department of Energy collected groundwater samples for 129I from 62 wells in the ESRP aquifer to track concentration trends and changes for the carcinogenic radionuclide that has a 15.7 million-year half-life. Concentrations of 129I in the aquifer ranged from 0.0000013±0.0000005 to 1.02±0.04 picocuries per liter (pCi/L), and generally decreased in wells near the INTEC, relative to previous sampling events. The average concentration of 129I in groundwater from 15 wells sampled during four different sample periods decreased from 1.15 pCi/L in 1990–91 to 0.173 pCi/L in 2011–12. All but two wells within a 3-mile radius of the INTEC showed decreases in concentration, and all but one sample had concentrations less than the U.S. Environmental Protection Agency maximum contaminant level of 1 pCi/L. These decreases are attributed to the discontinuation of disposal of 129I in wastewater and to dilution and dispersion in the aquifer. The decreases in 129I concentrations, in areas around INTEC where concentrations increased between 2003 and 2007, were attributed to less recharge near INTEC either from less flow in the Big Lost River or from less local snowmelt and anthropogenic sources. Although wells near INTEC sampled in 2011–12 showed decreases in 129I concentrations compared with previously collected data, some wells south and east of the Central Facilities Area

  1. Hydrologic testing in wells near the Idaho Chemical Processing Plant at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Johnson, G.S.; Olsen, J.H.; Ralston, D.R.

    1994-01-01

    The Snake River Plain aquifer beneath the INEL is often viewed as a 2-dimensional system, but may actually possess 3-dimensional properties of concern. A straddle-packer system is being used by the State's INEL Oversight Program to isolate specific aquifer intervals and define the 3-dimensional chemical and hydrologic characteristics of the aquifer. The hydrologic test results from wells USGS 44, 45, and 46 near the Idaho Chemical Processing Plant indicate that: (1) Vertical variation in static head is less than 0.3 feed, (2) barometric efficiencies are between 25 and 55 percent, and (3) the system responds to distant pumping as a multi-layered, but interconnected system. 3 refs., 7 figs., 3 tabs

  2. Safety research experiment facilities, Idaho National Engineering Laboratory, Idaho. Final environmental impact statement

    International Nuclear Information System (INIS)

    Liverman, J.L.

    1977-09-01

    This environmental statement was prepared for the Safety Research Experiment Facilities (SAREF) Project. The purpose of the proposed project is to modify some existing facilities and provide a new test facility at the Idaho National Engineering Laboratory (INEL) for conducting fast breeder reactor (FBR) safety experiments. The SAREF Project proposal has been developed after an extensive study which identified the FBR safety research needs requiring in-reactor experiments and which evaluated the capability of various existing and new facilities to meet these needs. The proposed facilities provide for the in-reactor testing of large bundles of prototypical FBR fuel elements under a wide variety of conditions, ranging from those abnormal operating conditions which might be expected to occur during the life of an FBR power plant to the extremely low probability, hypothetical accidents used in the evaluation of some design options and in the assessment of the long-term potential risk associated with wide-acale deployment of the FBR

  3. Mineralogy of selected sedimentary interbeds at or near the Idaho National Engineering Laboratory, Idaho

    International Nuclear Information System (INIS)

    Reed, M.F.; Bartholomay, R.C.

    1994-08-01

    The US Geological Survey's (USGS) Project Office at the Idaho National Engineering Laboratory (INEL) analyzed 66 samples from sedimentary interbed cores during a 38-month period beginning in October 1990 to determine bulk and clay mineralogy. These cores had been collected from 19 sites in the Big Lost River Basin, 2 sites in the Birch Creek Basin, and 1 site in the Mud Lake Basin, and were archived at the USGS lithologic core library at the INEL. Mineralogy data indicate that core samples from the Big Lost River Basin have larger mean and median percentages of quartz, total feldspar, and total clay minerals, but smaller mean and median percentages of calcite than the core samples from the Birch Creek Basin. Core samples from the Mud Lake Basin have abundant quartz, total feldspar, calcite, and total clay minerals. Identification of the mineralogy of the Snake River Plain is needed to aid in the study of the hydrology and geochemistry of subsurface waste disposal

  4. MERGER ACCOUTING FOR COMPANIES

    Directory of Open Access Journals (Sweden)

    SUCIU GHEORGHE

    2014-05-01

    Full Text Available Companies, especially nowadays, are characterized through great mobility, fast circulation of capital, occurring in their chase for profit. In this context, companies look for alliances, economical and political assistance. These objectives can materialize through merging of companies. The merger can be internal (between Romanian companies or transboundary, which includes foreign companies. In order to correctly reflect these events, the merger operations must be regulated and must respect national and international regulations. One important request concerning the merger operations is that the accounting values of the assets, debts and ownership equity must be brought to the present financial value.

  5. Hydrologic conditions at the Idaho National Engineering Laboratory, Idaho - emphasis: 1974-1978

    International Nuclear Information System (INIS)

    Barraclough, J.T.; Lewis, B.D.; Jensen, R.G.

    1982-09-01

    The Idaho National Engineering Laboratory (INEL) site covers about 890 square miles of the eastern Snake River Plain and overlies the Snake River Plain aquifer. Low concentrations of aqueous chemical and radioactive wastes have been discharged to shallow ponds and to shallow or deep wells on the site since 1952. A large body of perched ground water has formed in the basalt underlying the waste disposal ponds in the Test Reactor Area. This perched zone contains tritium, chromium-51, cobalt-60, strontium-90, and several nonradioactive ions. Tritium is the only mappable waste constituent in that portion of the Snake River Plain aquifer directly underlying this perched zone. Low concentrations of chemical and low-level radioactive wastes enter directly into the Snake River Plain aquifer through the Idaho Chemical Processing Plant (ICPP) disposal well. Tritium has been discharged to the well since 1953 and has formed the largest waste plume, about 28 square miles in area, in the regional aquifer, and minute concentrations have migrated downgradient a horizontal distance of 7.5 miles. Other waste plumes south of the ICPP contain sodium, chloride, nitrate, and the resultant specific conductance. These plumes have similar configurations and flow southward; the contaminants are in general laterally dispersed in that portion of the aquifer underlying the INEL. Other waste plumes, containing strontium-90 and iodine-129, cover small areas near their points of discharge because strontium-90 is sorbed from solution as it moves through the aquifer and iodine-129 is discharged in very low quantities. Cesium-137 is also discharged through the well but it is strongly sorbed from solution and has never been detected in a sample of ground water at the INEL

  6. Environmental surveillance for EG ampersand G Idaho Waste Management facilities at the Idaho National Engineering Laboratory. 1993 annual report

    International Nuclear Information System (INIS)

    Wilhelmsen, R.N.; Wright, K.C.; McBride, D.W.; Borsella, B.W.

    1994-08-01

    This report describes calendar year 1993 environmental surveillance activities of Environmental Monitoring of EG ampersand G Idaho, Inc., performed at EG ampersand G Idaho operated Waste Management facilities at the Idaho National Engineering Laboratory (INEL). The major facilities monitored include the Radioactive Waste Management Complex, the Waste Experimental Reduction Facility, the Mixed Waste Storage Facility, and two surplus facilities. Included are results of the sampling performed by the Radiological and Environmental Sciences Laboratory and the United States Geological Survey. The primary purposes of monitoring are to evaluate environmental conditions, to provide and interpret data, to ensure compliance with applicable regulations or standards, and to ensure protection of human health and the environment. This report compares 1993 environmental surveillance data with US Department of Energy derived concentration guides and with data from previous years

  7. Annual report -- 1992: Environmental surveillance for EG ampersand G Idaho Waste Management Facilities at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Wilhelmsen, R.N.; Wright, K.C.; McBride, D.W.

    1993-08-01

    This report describes the 1992 environmental surveillance activities of the Environmental Monitoring Unit of EG ampersand G Idaho, Inc., at EG ampersand G Idaho-operated Waste Management facilities at the Idaho National Engineering Laboratory (INEL). The major facilities monitored include the Radioactive Waste Management Complex, the Waste Experimental Reduction Facility, the Mixed Waste Storage Facility, and two surplus facilities. Included are some results of the sampling performed by the Radiological and Environmental Sciences Laboratory and the United States Geological Survey. The primary purposes of monitoring are to evaluate environmental conditions, to provide and interpret data, to ensure compliance with applicable regulations or standards, and to ensure protection of human health and the environment. This report compares 1992 environmental surveillance data with DOE derived concentration guides, and with data from previous years

  8. Aerial gamma ray and magnetic survey: Idaho Project, Elk City quadrangle of Idaho/Montana. Final report

    International Nuclear Information System (INIS)

    1979-11-01

    The Elk City quadrangle in north central Idaho and western Montana lies within the Northern Rocky Mountain province. The area is dominated by instrusives of the Idaho and Sawtooth Batholiths, but contains significant exposures of Precambrian metamorphics and Tertiary volcanics. Magnetic data apparently show some expression of the intrusives of the Idaho Batholith. Areas of faulted Precambrian and Tertiary rocks appear to express themselves as well defined regions of high frequency and high amplitudes wavelengths. The Elk City quadrangle has been unproductive in terms of uranium mining, though it contains significant exposures of the Challis Formation, which has been productive in other areas south of the quadrangle. A total of 238 anomalies are valid according to the criteria set forth in Volume I of this report. These anomalies are scattered throughout the quadrangle. The most distinctive group of anomalies with peak apparent uranium concentrations of 10.0 ppM eU or greater

  9. Process Description and Operating History for the CPP-601/-640/-627 Fuel Reprocessing Complex at the Idaho National Engineering and Environmental Laboratory

    International Nuclear Information System (INIS)

    Wagner, E.P.

    1999-01-01

    The Fuel Reprocessing Complex (FRC) at the Idaho Nuclear Technology and Engineering Center at the Idaho National Engineering and Environmental Laboratory was used for reprocessing spent nuclear fuel from the early 1950's until 1992. The reprocessing facilities are now scheduled to be deactivated. As part of the deactivation process, three Resource Conservation and Recovery Act (RCRA) interim status units located in the complex must be closed. This document gathers the historical information necessary to provide a rational basis for the preparation of a comprehensive closure plan. Included are descriptions of process operations and the operating history of the FRC. A set of detailed tables record the service history and present status of the process vessels and transfer lines

  10. The CEFRI and radiological protection certification of French companies

    International Nuclear Information System (INIS)

    Marillier, J.C.

    1992-01-01

    In 1990, French nuclear operators and the nuclear industry set up a system for certifying the companies involved in industrial work with exposure to ionizing radiation and the concerned training organizations. Inspectors have been recruited and trained. The first certificates were issued during the past few months. The extension of this certification to cover all work on nuclear sites is being envisaged. (author)

  11. Company profile VUJE

    International Nuclear Information System (INIS)

    Anon

    2007-01-01

    At the present time the whole world realizes the serious need for energy for the preservation of perpetually sustainable development. A distinctive place in the life of modern society belongs to electric energy,its safe production and reliable delivery according high standards of quality. When our company was established 30 years ago, we assumed research and development challenges directly related to the safe, reliable and economical production of electric energy from nuclear power plants, as well as the elimination of potential negative influences on the environment and employees. During our existence, we have gradually expanded our activities and specializations. Our first job was ti train plant personnel. We trained specialists to meet the needs not only of (what was then) Czechoslovakia, but also of Germany and Hungary. Gradually, we also met the problems of processing and storing radioactive waste, maintaining the service-life of our equipment and deactivating and disposing of contaminated devices at the end their operating lives. Industry requirements and concerns led us to broaden our services in energy production to include renewable sources of energy. Our youngest division of activity deals with the distribution of hydro-electrical energy via the electric grid. By continually updating the specialized skills of our elmasil and by investing in the latest equipment, our challenges and operational issues in the energy sector. Responding to developmental trends and the requirements of our consumers, we have established a system of quality management, which complies with the ISO 9001 and 14001 standards certified by the LRQA Corporation of Great Britain. Throughout the years, our company has been consistently proving to the operators of power facilities, both in Slovakia and abroad, our viability and high, innovative potential, in recognition of this, in 2005, when we participated in the sixth EU Framework Programme in R and D, the Slovak Ministry of Education

  12. Company profile VUJE

    International Nuclear Information System (INIS)

    Anon

    2007-01-01

    At the present time the whole world realizes the serious need for energy for the preservation of perpetually sustainable development. A distinctive place in the life of modern society belongs to electric energy,its safe production and reliable delivery according high standards of quality. When our company was established 30 years ago, we assumed research and development challenges directly related to the safe, reliable and economical production of electric energy from nuclear power plants, as well as the elimination of potential negative influences on the environment and employees. During our existence, we have gradually expanded our activities and specializations. Our first job was ti train plant personnel. We trained specialists to meet the needs not only of (what was then) Czechoslovakia, but also of Germany and Hungary. Gradually, we also met the problems of processing and storing radioactive waste, maintaining the service-life of our equipment and deactivating and disposing of contaminated devices at the end their operating lives. Industry requirements and concerns led use to broaden our services in energy production to include renewable sources of energy. Our youngest division of activity deals with the distribution of hydro-electrical energy via the electric grid. By continually updating the specialized skills of our employees and by investing in the latest equipment, our challenges and operational issues in the energy sector. Responding to developmental trends and the requirements of our consumers, we have established a system of quality management, which complies with the ISO 9001 and 14001 standards certified by the LRQA Corporation of Great Britain. Throughout the years, our company has been consistently proving to the operators of power facilities, both in Slovakia and abroad, our viability and high, innovative potential, in recognition of this, in 2005, when we participated in the sixth EU Framework Programme in R and D, the Slovak Ministry of

  13. Open Source Telecommunication Companies

    Directory of Open Access Journals (Sweden)

    Peter Liu

    2007-08-01

    Full Text Available Little is known about companies whose core business is selling telecommunications products that lever open source projects. Open source telecommunications (OST companies operate in markets that are very different from typical software product markets. The telecommunications market is regulated, vertically integrated, and proprietary designs and special chips are widely used. For a telecommunications product to be useful, it must interact with both access network products and core network products. Due to specifications in Service Agreements Levels, penalties for failures of telecommunications products are very high. This article shares information that is not widely known, including a list of OST companies and the open source projects on which they depend, the size and diversity of venture capital investment in OST companies, the nature of the commercial product-open source software and company-project relationships, ways in which OST companies make money, benefits and risks of OST companies, and competition between OST companies. Analysis of this information provides insights into the ways in which companies can build business models around open source software. These findings will be of interest to entrepreneurs, top management teams of incumbent companies that sell telecommunications products, and those who care about Ontario's ability to compete globally.

  14. In summary: Idaho National Engineering and Environmental Laboratory site environmental report for calendar year 1997

    International Nuclear Information System (INIS)

    Mitchell, R.G.; Roush, D.E. Jr.; Evans, R.B.

    1998-10-01

    Every human is exposed to natural radiation. This exposure comes from many sources, including cosmic radiation from outer space, naturally-occurring radon, and radioactivity from substances in the body. In addition to natural sources of radiation, humans can also be exposed to human-generated sources of radiation. Some examples of these sources include nuclear medicine, X-rays, nuclear weapons testing, and accidents at nuclear power plants. The Idaho National Engineering and Environmental Laboratory (INEEL) is a US Department of Energy (DOE) research facility that deals, in part, with studying nuclear reactors and the storage and cleanup of radioactive materials. Careful handling and rigorous procedures do not completely eliminate the risk of releasing radioactivity. So, there is a possibility for a member of the public near the INEEL to be exposed to radioactivity from the INEEL. Extensive monitoring of the environment takes place one and around the INEEL. These programs search for radionuclides and other contaminants. The results of these programs are presented each year in a site environmental report. This document summarizes the INEEL site environmental report for 1997

  15. THE HIGH-TEMPERATURE ELECTROLYSIS PROGRAM AT THE IDAHO NATIONAL LABORATORY: OBSERVATIONS ON PERFORMANCE DEGRADATION

    Energy Technology Data Exchange (ETDEWEB)

    J. E. O' Brien; C. M. Stoots; J. S. Herring; K. G. Condie; G. K. Housley

    2009-06-01

    This paper presents an overview of the high-temperature electrolysis research and development program at the Idaho National Laboratory, with selected observations of electrolysis cell degradation at the single-cell, small stack and large facility scales. The objective of the INL program is to address the technical and scale-up issues associated with the implementation of solid-oxide electrolysis cell technology for hydrogen production from steam. In the envisioned application, high-temperature electrolysis would be coupled to an advanced nuclear reactor for efficient large-scale non-fossil non-greenhouse-gas hydrogen production. The program supports a broad range of activities including small bench-scale experiments, larger scale technology demonstrations, detailed computational fluid dynamic modeling, and system modeling. A summary of the current status of these activities and future plans will be provided, with a focus on the problem of cell and stack degradation.

  16. Boiling water reactor containment modeling and analysis at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Holcomb, E.E. III; Wilson, G.E.

    1984-01-01

    Under the auspices of the United States Nuclear Regulatory Commission, severe accidents are being studied at the Idaho National Engineering Laboratory. The boiling water reactor (BWR) studies have focused on postulated anticipated transients without scram (ATWS) accidents which might contribute to severe core damage or containment failure. A summary of the containment studies is presented in the context of the analytical tools (codes) used, typical transient simulation results and the need for prototypical containment data. All of these are related to current and future analytical capabilities. It is shown that torus temperatures during the ATWS depart from limiting conditions for BWR T-quencher operation, outside of which stable steam condensation has not been proven

  17. Market research for Idaho Transportation Department linear referencing system.

    Science.gov (United States)

    2009-09-02

    For over 30 years, the Idaho Transportation Department (ITD) has had an LRS called MACS : (MilePoint And Coded Segment), which is being implemented on a mainframe using a : COBOL/CICS platform. As ITD began embracing newer technologies and moving tow...

  18. Idaho National Engineering Laboratory decontamination and decommissioning summary

    International Nuclear Information System (INIS)

    Chapin, J.A.

    1981-01-01

    Topics covered concern the decontamination and decommissioning (D and D) work performed at the Idaho National Engineering Laboratory (INEL) during FY 1979 and include both operations and development projects. Briefly presented are the different types of D and D projects planned and the D and D projects completed. The problems encountered on these projects and the development program recommended are discussed

  19. Effects of snow on fisher and marten distributions in Idaho

    Science.gov (United States)

    Nathan Albrecht; C. Heusser; M. Schwartz; J. Sauder; R. Vinkey

    2013-01-01

    Studies have suggested that deep snow may limit fisher (Martes pennanti) distribution, and that fisher populations may in turn limit marten (Martes americana) distribution. We tested these hypotheses in the Northern Rocky Mountains of Idaho, a region which differs from previous study areas in its climate and relative fisher and marten abundance, but in which very...

  20. Digital Learning Compass: Distance Education State Almanac 2017. Idaho

    Science.gov (United States)

    Seaman, Julia E.; Seaman, Jeff

    2017-01-01

    This brief report uses data collected under the U.S. Department of Education's National Center for Educational Statistics (NCES) Integrated Postsecondary Education Data System (IPEDS) Fall Enrollment survey to highlight distance education data in the state of Idaho. The sample for this analysis is comprised of all active, degree-granting…

  1. Successful neural network projects at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Cordes, G.A.

    1991-01-01

    This paper presents recent and current projects at the Idaho National Engineering Laboratory (INEL) that research and apply neural network technology. The projects are summarized in the paper and their direct application to space reactor power and propulsion systems activities is discussed. 9 refs., 10 figs., 3 tabs

  2. Characteristics of persons with repeat syphilis - Idaho, 2011-2015.

    Science.gov (United States)

    Kassem, Ahmed M; Bartschi, Jared; Carter, Kris K

    2018-03-14

    During 2011-2015 in Idaho, 14 (7%) of 193 persons with early syphilis had repeat syphilis. Persons with repeat infections were more likely to have had secondary or early latent syphilis (P = 0.037) and be infected with HIV (P < 0.001) compared with those having one infection.

  3. WARM SPRINGS CREEK GEOTHERMAL STUDY, BLAIN COUNTY IDAHO, 1987

    Science.gov (United States)

    In the Warm Springs Creek drainage near Ketchum, Idaho (17040219), a leaking pipeline coveys geothermal water through the valley to heat nearby homes as well as to supply a resorts swimming pool. Several domestic wells in close proximity to this line have exhibited increasing fl...

  4. Water information bulletin No. 30 geothermal investigations in Idaho

    Energy Technology Data Exchange (ETDEWEB)

    Mitchell, J.C.; Johnson, L.L.; Anderson, J.E.; Spencer, S.G.; Sullivan, J.F.

    1980-06-01

    There are 899 thermal water occurrences known in Idaho, including 258 springs and 641 wells having temperatures ranging from 20 to 93/sup 0/C. Fifty-one cities or towns in Idaho containing 30% of the state's population are within 5 km of known geothermal springs or wells. These include several of Idaho's major cities such as Lewiston, Caldwell, Nampa, Boise, Twin Falls, Pocatello, and Idaho Falls. Fourteen sites appear to have subsurface temperatures of 140/sup 0/C or higher according to the several chemical geothermometers applied to thermal water discharges. These include Weiser, Big Creek, White Licks, Vulcan, Roystone, Bonneville, Crane Creek, Cove Creek, Indian Creek, and Deer Creek hot springs, and Raft River, Preston, and Magic Reservoir areas. These sites could be industrial sites, but several are in remote areas away from major transportation and, therefore, would probably be best utilized for electrical power generation using the binary cycle or Magma Max process. Present uses range from space heating to power generation. Six areas are known where commercial greenhouse operations are conducted for growing cut and potted flowers and vegetables. Space heating is substantial in only two places (Boise and Ketchum) although numerous individuals scattered throughout the state make use of thermal water for space heating and private swimming facilities. There are 22 operating resorts using thermal water and two commercial warm-water fish-rearing operations.

  5. Program Management Educational Needs of Idaho Business and Marketing Teachers

    Science.gov (United States)

    Kitchel, Allen; Cannon, John; Duncan, Dennis

    2009-01-01

    The purpose of this study was to determine the perceived program management professional development needs of Idaho secondary business/marketing teachers (N = 233) in order to guide pre-service curriculum development and in-service training activities. Sixty-two percent (n = 146) of the 233 teachers completed a modified version of Joerger's (2002)…

  6. Institutional Plan, FY 1993--1998, Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    1993-01-01

    This document presents the plans and goals of the Idaho National Engineering Laboratory for FY 1993--1998. Areas discussed in this document include: INEL strategic view; initiatives; scientific and technical programs; environmental, safety, and health management, technology transfer, science and math education, and community affairs; human resources; site and facilities; and resource projections

  7. Selected hydrologic data, Camas Prairie, south-central Idaho

    Science.gov (United States)

    Young, H.W.; Backsen, R.L.; Kenyon, K.S.

    1978-01-01

    This report presents data collected during a 1-year study of the water resources of Camas Prairie, Idaho. Included are records of wells, discharge measurements of streams, hydrographs of water levels in wells, water-quality data, and drillers ' logs of wells. The data are conveniently made available to supplement an interpretive report, which will be published separately. (Woodard-USGS)

  8. Analysis of ARAC participation in the Idaho field experiment

    International Nuclear Information System (INIS)

    Rosen, L.C.; Hill, K.L.

    1986-02-01

    The 1981 Idaho Field Experiment to coordinate data sets and evaluate model and computer facilities is summarized herein. Participation of the Atmospheric Release Advisory Capability (ARAC) of the Lawrence Livermore National Laboratory in the field experiment is discussed. The computed ARAC results are compared with the observational data sets and analyzed. 12 refs., 44 figs., 3 tabs

  9. Larry Echo Hawk: A Rising Star from Idaho.

    Science.gov (United States)

    Wisecarver, Charmaine

    1993-01-01

    Larry Echo Hawk, Idaho attorney general and former state legislator, discusses success factors in college and law school; early experiences as an Indian lawyer; first election campaign; and his views on tribal sovereignty, state-tribal relationship, gambling, and his dual responsibility to the general public and Native American issues. (SV)

  10. Field guide to forest plants of northern Idaho

    Science.gov (United States)

    Patricia A. Patterson; Kenneth E. Neiman; Jonalea K. Tonn

    1985-01-01

    This field guide -- designed for use by people with minimal botanical training -- is an identification aid for nearly 200 plant species having ecological indicator value in northern Idaho forest habitat types. It contains line drawings, simplified taxonomic descriptions , characteristics tables, conspectuses, and keys. It emphasizes characteristics useful for field...

  11. Public Shareholdership Energy Companies

    International Nuclear Information System (INIS)

    Kist, A.W.; Crone, F.J.M.; Hudig, D.F.; Ketting, N.G.; De Swaan, T.; Willems, R.

    2008-06-01

    National and international developments on the energy markets and changes in legislation and regulation require a renewed strategic orientation of energy companies and their shareholders. Decentralized authorities will have to reconsider their position as a shareholder in energy companies carefully. This report provides an overview of the recommendations of the Kist Commission on how provinces and municipalities can make a well-considered choice as shareholder of energy companies. [mk] [nl

  12. Privatised companies and market

    International Nuclear Information System (INIS)

    Salini, M. P.

    2001-01-01

    The Italian Government decided to adopt the public company structure where a little group of medium-term investors had the task of supporting the transition of the privatised companies to the market. The article examines the reasons for this decision and its failure in attaining the purpose, not excluding the possibility for the public company of imposing itself in the long period and in a context of a minor legislative intervention and more effective Corporate Governance rules [it

  13. The Danish East India Company

    DEFF Research Database (Denmark)

    Sørensen, Karsten Engsig

    2005-01-01

    The article analysis the first Danish East India Company incorporated in 1616, which was the first Danish Stock Company and which has impacts even on modern Danish company la......The article analysis the first Danish East India Company incorporated in 1616, which was the first Danish Stock Company and which has impacts even on modern Danish company la...

  14. A prehistory of nuclear energy development

    International Nuclear Information System (INIS)

    Yoshikawa, Hideo

    2007-01-01

    Evolutionary progress of the LWR plants in the last half-century was reviewed in series. As a prehistory of nuclear energy development, this first lecture presented (1) discovery of nuclear energy and development of the atomic bomb and (2) development of the reactor system using nuclear energy for making electricity and for naval propulsion. The first nuclear reactor to produce electricity was the small Experimental Breeder Reactor (EBR-1) in Idaho, in the USA, which started up in December 1951. The Pressurized Water Reactor (PWR) for naval use was developed under Hyman Rickover in the USA. The Mark I prototype naval reactor started up in March 1953 in Idaho, and the first nuclear-powered submarine, NS Nautilus, with the Mark II reactor was put into service in January 1955. (T. Tanaka)

  15. Nuclear energy

    International Nuclear Information System (INIS)

    1996-01-01

    Several issues concerning nuclear energy in France during 1996 are presented: permission of a demand for installing underground laboratories in three sites (Marcoule, Bure and Chapelle-Baton); a report assessing the capacity of Superphenix plant to operate as a research tool; the project of merging between Framatome and Gec-Alsthom companies; the revision of a general report on nuclear energy in France; the issue of military plutonium management

  16. Miniplates irradiation in the ATR (Idaho, USA)

    International Nuclear Information System (INIS)

    Pasqualini, Enrique E.

    2007-01-01

    High density U Mo alloys are promising for its utilization in the reconversion of HEU fuels to LEU for research nuclear reactors. Ought to the thermomechanical properties of the alloy U Mo and its interaction with aluminium it is necessary to develop new technologies and fabrication procedures to qualify this material as a nuclear fuel. In this work a review is made about the evolution of the idea and PIE experiments of monolithic LEU U 7 Mo fuel with Zr-4 cladding. The irradiation took place in the frame of international qualification efforts of dispersed and monolithic U Mo fuels. Dispersed and monolithic fuels, elaborated and in intermediate steps of development, are discussed. (author) [es

  17. Georgia Power Company's college degree program

    International Nuclear Information System (INIS)

    Coggin, C.L.

    1988-01-01

    The purpose of this paper is to describe Georgia Power Company's on-site college degree program for nuclear power plant personnel. In February 1986, the US Nuclear Regulatory Commission issued a policy statement concerning engineering expertise on shift (Generic Letter 86-04), which appeared in Volume 50, Number 208 of the October 28, 1985 Federal Register. One of the options available to nuclear power plant personnel to meet the requirement was the combined senior reactor operator/shift technical adviser position. One of the methods for meeting the option included a bachelor's degree in engineering technology for an accredited institution, including course work in the physical, mathematical, or engineering sciences

  18. Carolina Power and Light Company's computerized Radiological Information Management System

    International Nuclear Information System (INIS)

    Meyer, B.A.

    1987-01-01

    Carolina Power and Lignt Company has recently implement a new version of their computerized Radiological Information management System. The new version was programmed in-house and is run on the Company's mainframe computers. In addition to providing radiation worker dose histories and current dose updates, the system provides real-time access control for all three of the Company's nuclear plants such as respirator and survey equipment control and inventory, TLD QC records, and many other functions

  19. 75 FR 8150 - STP Nuclear Operating Company

    Science.gov (United States)

    2010-02-23

    ... be no change to radioactive effluents that affect radiation exposures to plant workers and members of... resources. There would be no impact to socioeconomic resources. Therefore, no changes to or different types...

  20. Safety Research Experiment Facilities, Idaho National Engineering Laboratory, Idaho. Draft environmental statement

    International Nuclear Information System (INIS)

    1977-01-01

    This environmental statement was prepared in accordance with the National Environmental Policy Act of 1969 (NEPA) in support of the Energy Research and Development Administration's (ERDA) proposal for legislative authorization and appropriations for the Safety Research Experiment Facilities (SAREF) Project. The purpose of the proposed project is to modify some existing facilities and provide a new test facility at the Idaho National Engineering Laboratory (INEL) for conducting fast breeder reactor (FBR) safety experiments. The SAREF Project proposal has been developed after an extensive study which identified the FBR safety research needs requiring in-reactor experiments and which evaluated the capability of various existing and new facilities to meet these needs. The proposed facilities provide for the in-reactor testing of large bundles of prototypical FBR fuel elements under a wide variety of conditions, ranging from those abnormal operating conditions which might be expected to occur during the life of an FBR power plant to the extremely low probability, hypothetical accidents used in the evalution of some design options and in the assessment of the long-term potential risk associated with wide-scale deployment of the FBR