Sample records for cherokee nuclear station

  1. Study of the Cherokee Nuclear Station: projected impacts, monitoring plan, and mitigation options for Cherokee County, South Carolina

    This report inventories Cherokee County's capabilities and CNS project characteristics, projects expected impacts from the interaction of the two defines four options for Cherokee County decision makers, and presents a range of possible mitigation and monitoring plans for dealing with the problems identified. The four options and general implementation guidelines for each are presented after reviewing pertinent features of other mitigation and monitoring plans. The four options include (1) no action, (2) preventing impacts by preventing growth, (3) selective growth in designated areas as services can be supplied, and (4) maximum growth designed to attract as many in-movers as possible through a major program of capital investiments in public and private services. With the exception of the no action option, all plans deal with impacts according to some strategy determined by how the County wishes to manage growth. Solutions for impact problems depend on which growth strategy is selected and what additional resources are secured during the impact period. A monitoring program deals with the problems of data and projections uncertainty, while direct action is proposed to deal with the institutional problems of delay of the needed access road, timeing and location problems from the tax base mismatch, and lack of local planning capability

  2. Cherokees.

    Arnow, Pat, Ed.; Chiltoskey, Mary, Ed.


    This issue of "Now and Then" focuses on Cherokee Indians in Appalachia. It includes poetry, articles, fiction, book reviews, and photos. Articles include "The Story of My Life as Far Back as I Remember" by Aggie Ross Lossiah and edited by Joan Greene; "Goingback Chiltoskey, Master Carver," by Joan Greene; "Daughter of Tahlequah," a profile of…

  3. Final environmental statement related to construction of Cherokee Nuclear Station, Units 1, 2, and 3: (Docket Nos. STN 50-491, STN 50-492, and STN 50-493)

    The proposed action is the issuance of a construction permit to the Duke Power Company for the construction of the Cherokee Nuclear Station (CNS) Units 1, 2, and 3 located in Cherokee County, South Carolina. A total of 2263 acres will be removed from public use for the CNS site. Construction-related activities on the site will disturb about 751 acres. Approximately 654 acres of land will be required for transmission line right-of-way, and a railroad spur will affect 83 acres. This constitutes a minor regional impact. No significant environmental impacts are anticipated from normal operational releases of radioactive materials. The total annual dose to the US population (total body plus thyroid) from operation of the plant is 210 man-rems which is less than the normal fluctuations in the background dose this population would receive. The occupational dose is approximately 1400 man-rems/year. The heat dissipation system will require a maximum water makeup of 55,814 gpm, of which 50,514 gpm will be consumed due to drift and evaporative losses. This amount represents 4.5% of the mean monthly flow and 23.8% of the low flow of the Broad River. The cooling tower blowdown and chemical effluents from the station will increase the dissolved solids concentration in the river by a maximum of 44 ppM. The thermal alterations and increases in total dissolved solids concentration will not significantly affect the aquatic productivity of the river. 114 refs., 25 figs., 46 tabs

  4. Nuclear power stations licensing

    The judicial aspects of nuclear stations licensing are presented. The licensing systems of the United States, Spain, France and Federal Republic of Germany are focused. The decree n0 60.824 from July 7 sup(th), 1967 and the following legislation which define the systematic and area of competence in nuclear stations licensing are analysed

  5. The nuclear power station

    The processes taking place in a nuclear power plant and the dangers arising from a nuclear power station are described. The means and methods of controlling, monitoring, and protecting the plant and things that can go wrong are presented. There is also a short discourse on the research carried out in the USA and Germany, aimed at assessing the risks of utilising nuclear energy by means of the incident tree analysis and probability calculations. (DG)

  6. Biblis nuclear power station

    A short constructive description of the components of the Biblis nuclear power station is given here. In addition to the heat flow diagram, the coolant cycle and the turbine control system, some details of construction and reactor safety are presented. (TK/AK)

  7. Fessenheim nuclear power station

    The Fessenheim nuclear power plant includes two PWR type units each with net electrical output of 890MW(e). The site and layout of the station, geological features and cooling water characteristics are described. Reference is made to other aspects of the environment such as population density and agronomy. (U.K.)

  8. Family and Nation: Cherokee Orphan Care, 1835-1903

    Reed, Julie L.


    On November 17, 1903, fifteen miles from the nearest railway station and fifty miles northwest of the capital of the Cherokee Nation in Tahlequah, a fire engulfed the Cherokee Orphan Asylum. After the fire the Cherokee Nation relocated the homeless children to the nation's Insane Asylum in Tahlequah, where Sequoyah School stands today. The…

  9. Cherokee and the Tourists.

    Now and Then, 1991


    Describes tourist season in Cherokee (North Carolina), near the Qualla Boundary (a small Cherokee reservation). Discusses the appearance and attitudes of the tourists, the endurance and salesmanship of the Cherokees, and possible means of increasing the tourist trade. (SV)

  10. Discharges from nuclear power stations

    HM Inspectorate of Pollution commissioned, with authorising responsibilities in England and Wales, a study into the discharges of radioactive effluents from Nuclear Power Stations. The study considered arisings from nuclear power stations in Europe and the USA and the technologies to treat and control the radioactive discharges. This report contains details of the technologies used at many nuclear power stations to treat and control radioactive discharges and gives, where information was available, details of discharges and authorised discharge limits. (author)

  11. Islands for nuclear power stations

    The safety principles, design criteria and types of artificial island for an offshore nuclear power station are discussed with particular reference to siting adjacent to an industrial island. The paper concludes that the engineering problems are soluble and that offshore nuclear power stations will eventually be built but that much fundamental work is still required. (author)

  12. The Cherokee Challenge.

    Hill, Tom


    Describes an adventure program operated on the Qualla Boundary Cherokee reservation that serves Cherokee youth and outside groups interested in Cherokee culture. Aspects of Cherokee culture, such as talking circles and storytelling, are incorporated into the program. A sidebar recounts the story of a bear encounter that is used to begin many…

  13. Checking nuclear power station safety

    The paper describes the test facilities and research projects for Sizewell-B and other nuclear power stations, directed by the National Nuclear Corporation (NNC). The NNC is Britain's nuclear power station design and construction company, and is currently carrying out commissioning on both the Heysham and Torness AGRs. A description is given of NNC's nuclear research and development work, which includes: the production of Cobalt-free alloy, coatings for the primary containment shell, and ''fitness for purpose'' tests on reactor components using its 'Loki' rig to put the equipment through postulated accident conditions. NNC also has a rig to test structural features under extreme thermal shock conditions. (U.K.)

  14. Balakovo nuclear power station

    A key means of improving the safety and reliability of nuclear power plants is through effective training of plant personnel. The goal of this paper is to show the progress of the training at the Balakovo Nuclear Power Plant, and the important role that international cooperation programs have played in that progress

  15. Safeguarding nuclear power stations

    The basic features of nuclear fuel accounting and control in present-day power reactors are considered. Emphasis is placed on reactor operations and spent-fuel characteristics for Light-Water Reactors (LWRs) and Heavy-Water Reactors (HWRs)

  16. Bibliography of the Cherokees.

    Hoyt, Anne K.

    An extensive bibliography of books, government publications, periodical articles, and theses published between 1832 and 1968 has been collected on all phases of Cherokee Indian life. Although the major portion of the listings are concerned with Cherokee history, the document also presents extensive sections on Cherokee foklore (folkways, arts,…

  17. The Cherokee Perspective: Written by Eastern Cherokees.

    French, Laurence, Ed.; Hornbuckle, Jim, Ed.

    Cherokee students at the Qualla Boundary started a student organization in 1973 to improve educational prospects among Native Americans attending non-Indian colleges and universities. Because cultural conflict was perceived as playing a crucial role in the failure of Cherokee students in higher education, a major objective of the group was to…

  18. Reviewing nuclear power station achievement

    For measurement of nuclear power station achievement against original purchase the usual gross output figures are of little value since the term loosely covers many different definitions. An authentically designed output figure has been established which relates to net design output plus house load at full load. Based on these figures both cumulative and moving annual load factors are measured, the latter measuring the achievement over the last year, thus showing trends with time. Calculations have been carried out for all nuclear stations in the Western World with 150 MW(e) gross design output and above. From these are shown: moving annual load factor indicating relative station achievements for all the plants; cumulative load factors from which return of investment can be calculated; average moving annual load factors for the four types of system Magnox, PWR, HWR, and BWR; and a relative comparison of achievement by country in a few cases. (U.K.)

  19. Pumps for nuclear power stations

    16 nuclear power plants are in commercial operation in Japan, and nuclear power generation holds the most important position among various substitute energies. Hereafter also, it is expected that the construction of nuclear power stations will continue because other advantageous energy sources are not found. In this paper, the outline of the pumps used for BWR plants is described. Nuclear power stations tend to be large scale to reduce the construction cost per unit power output, therefore the pumps used are those of large capacity. The conditions to be taken in consideration are high temperature, high pressure, radioactive fluids, high reliability, hydrodynamic performances, aseismatic design, relevant laws and regulations, and quality assurance. Pumps are used for reactor recirculation system, control rod driving hydraulic system, boric acid solution injecting system, reactor coolant purifying system, fuel pool cooling and purifying system, residual heat removing system, low pressure and high pressure core spraying systems, and reactor isolation cooling system, for condensate, feed water, drain and circulating water systems of turbines, for fresh water, sea water, make-up water and fire fighting services, and for radioactive waste treating system. The problems of the pumps used for nuclear power stations are described, for example, the requirement of high reliability, the measures to radioactivity and the aseismatic design. (Kako, I.)

  20. Construction costs - nuclear power stations

    According to present development plans in the western industrial nations nuclear power will be able to cover 35 to 45% of power requirements in the mid 1980's. Although specific investment costs are higher for nuclear power plants than for other thermal power stations, nuclear plants are in a position today to generate power more economically than fossil fired plants into the upper part of the middle load sector. The relatively high proportion of fixed costs of the total power generation costs, and a still considerable potential to exploit the economy of scale, will contribute to minimize the inflationary burden on electric power generation. Nevertheless price development of nuclear power plants should be watched attentively, rapid price escalation for components, extremely long planning and construction times and exaggerated environmental protection requirements which serve no real purpose may reduce the economic benefit gained by nuclear energy. Electrical utilities will try to hold investment cost down by all means; for instance they will encourage standardization of nuclear power plants or order twin stations. For long term utilization of nuclear energy the development of high temperature reactors and fast breeders is a logical step forward. (author)

  1. Insurance of nuclear power stations

    Electrical utility companies have invested large sums in the establishment of nuclear facilities. For this reason it is normal for these companies to attempt to protect their investments as much as possible. One of the methods of protection is recourse to insurance. For a variety of reasons traditional insurance markets are unable to function normally for a number of reasons including, the insufficient number of risks, an absence of meaningful accident statistics, the enormous sums involved and a lack of familiarity with nuclear risks on the part of insurers, resulting in a reluctance or even refusal to accept such risks. Insurers have, in response to requests for coverage from nuclear power station operators, established an alternative system of coverage - insurance through a system of insurance pools. Insurers in every country unite in a pool, providing a net capacity for every risk which is a capacity covered by their own funds, and consequently without reinsurance. All pools exchange capacity. The inconvenience of this system, for the operators in particular, is that it involves a monopolistic system in which there are consequently few possibilities for the negotiation of premiums and conditions of coverage. The system does not permit the establishment of reserves which could, over time, reduce the need for insurance on the part of nuclear power station operators. Thus the cost of nuclear insurance remains high. Alternatives to the poor system of insurance are explored in this article. (author)

  2. Cherokee self-reliance.

    Lowe, John


    This qualitative study was conducted using ethnography to identify how (a) self-reliance is conceptualized by the Cherokee; (b) the adult male Cherokee perceives, achieves, and demonstrates self-reliance; and (c) nurses can incorporate the Cherokee concept of self-reliance into health care of the Cherokee. The goal of self-reliance was included in the following mission statement of the 1976 Cherokee Nation constitution: "The mission of the government of the Cherokee Nation is to promote and sustain the self-reliance of its members" (Resolution No. 28-85, 1976). The conceptualization and perspective of self-reliance by the Cherokee must be understood to assist effectively in the development and promotion of self-reliance in the Cherokee, especially the male Cherokee. The cultural domain of self-reliance that emerged from the data is a composite of three categories that include being responsible, being disciplined, and being confident. Cutting across all three categories are the two themes of being true to onself and being connected. PMID:12325243

  3. Traditional Cherokee Food.

    Hendrix, Janey B.

    A collection for children and teachers of traditional Cherokee recipes emphasizes the art, rather than the science, of cooking. The hand-printed, illustrated format is designed to communicate the feeling of Cherokee history and culture and to encourage readers to collect and add family recipes. The cookbook could be used as a starting point for…

  4. Improving nuclear power station output

    The total annual output of Nuclear Electric's five advanced gas cooled reactor (AGR) stations has increased by more than 80% from 21.7 to 39.3 TW·h over the last four years since the company was formed. This has been achieved through increasing both the capability (maximum power output) and the availability of the reactors. The successive stages of technical modifications, testing and safety case preparation and approval by which the capability of each of the reactor units was raised, whilst ensuring safety, are detailed and the further stages that are planned for the future are outlined. The availability of the reactors has been increased by removing the constraints associated with refuelling operations, reducing statutory overhaul lengths and frequency, and reducing unplanned losses. In 1990, the fuel routes at four of the five stations operated too slowly to supply the fuel needed by the reactors and also required substantial periods of outage of the fuel route for modifications in order to consolidate their off-load refuelling safety cases. The programmes of work undertaken are outlined and the improved performance of the fuel route operations to match the increased output of reactor units is detailed. The future developments, particularly of on-load refuelling, are outlined. The lengths of statutory outages have been reduced by improved management and performance of plant operations and maintenance, and permission has also been received to extend the period between overhauls from 24 to 36 months. Unplanned losses have also been reduced. The improvements in output have not been achieved at the expense of safety nor by increasing the resources deployed. Indeed the reverse is true; key safety indicators show an improvement in both nuclear and industrial safety; and the manpower employed at the AGRs and the total annual expenditure in real terms have both decreased over the past four years. (author). 7 figs, 1 tab

  5. Simulators of nuclear power stations

    The report deals with the simulators of nuclear power stations used for the training of operators and for the analysis of operations. It reviews the development of analogical, hybrid and digital simulators up to the present, indicating the impact resulting from the TMI-2 accident. It indicates, the components of simulators and the present accepted terminology for a classification of the various types of simulators. It reviews the present state of the art of the technology: how a basic mathematical model of a nuclear power system is worked out and what are the technical problems associated with more accurate models. Examples of elaborate models are given: for a PWR pressurizer, for an AGR steam generator. It also discusses certain problems of hardware technology. Characteristics of present replica simulators are given with certain details: simulated transient evolutions and malfunctions, accuracy of simulation. The work concerning the assessment of the validity of certain simulators is reported. A list of simulator manufacturers and a survey of the principal simulators in operation in the countries of the European Community, in the United States, and in certain other countries are presented. Problem associated with the use of simulators as training facilities, and their use as operational devices are discussed. Studies and research in progress for the expected future development of simulators are reviewed

  6. Safety of Russia's nuclear power stations

    Currently, 29 nuclear power plant units are in operation in Russia. The units 2, respectively, of both the Novovoronesh and Belojarsk nuclear power stations are shut down for decommissioning. In judjing the safety of the units of the first and second generation, GOSATOMNAZDOR applies very strict standards. For several nuclear power stations this entailed restraints on their power output as well as upgrading and retrofitting measures (Kurk, Balakovo, Kalinin, Leningrade 1 and 2, and Kola). (DG)

  7. Socioeconomic impacts: nuclear power station siting

    The rural industrial development literature is used to gain insights on the socioeconomic effects of nuclear power stations. Previous studies of large industrial facilities in small towns have important implications for attempts to understand and anticipate the impacts of nuclear stations. Even a cursory review of the nuclear development literature, however, reveals that industrialization research in rural sociology, economic geography and agricultural economics has been largely ignored

  8. Guangdong Daya Bay nuclear power station project

    Daya Bay Nuclear Power Station is the largest joint-venture project which is also the largest commercial nuclear power plant currently under construction in China mainland. Organized and executed strictly in accordance with international standards, the Daya Bay project is seen as the first step taken by China in the development programme of large-capacity commercial nuclear power units

  9. Cherokee Culture across the Curriculum.

    Larch, Lillie


    A teacher describes how she integrated Cherokee culture and folklore with the required curriculum at Cherokee Elementary School (Cherokee, North Carolina). Includes an annotated list of 22 Native American cultural resources and a list of 30 books and journal articles on folk games and toys and their uses in education. (LP)

  10. 77 FR 18271 - Terrestrial Environmental Studies for Nuclear Power Stations


    ... COMMISSION Terrestrial Environmental Studies for Nuclear Power Stations AGENCY: Nuclear Regulatory Commission... revision to Regulatory Guide (RG) 4.11, ``Terrestrial Environmental Studies for Nuclear Power Stations... environmental studies and analyses supporting licensing decisions for nuclear power reactors. ADDRESSES:...

  11. Nuclear Generating Stations and Transmission Grid Reliability

    Nuclear generating stations have historically been susceptible to transmission system voltage excursions. When nuclear plants trip due to voltage excursions, the resulting loss of real and reactive power support can make grid events worse. New standards are being prepared which may help to improve nuclear plant and transmission system reliability. A brief historical perspective is provided. Another reliability issue is the fact that nuclear plants do not provide automatic generation control in response to frequency decay. As 28 new nuclear plants are being considered for connection to an already highly stressed transmission grid, consideration must be given to nuclear plant design features which will enhance, not degrade, transmission system reliability

  12. Underground location of nuclear power stations

    In Japan where the population is dense and the land is narrow, the conventional location of nuclear power stations on the ground will become very difficult sooner or later. At this time, it is very important to establish the new location method such as underground location, Quaternary ground location and offshore location as the method of expanding the location for nuclear power stations from the viewpoint of the long term demand and supply of electric power. As for underground location, the technology of constructing an underground cavity has been already fostered basically by the construction of large scale cavities for underground pumping-up power stations in the last 20 years. In France, Norway and Sweden, there are the examples of the construction of underground nuclear power stations. In this way, the opportunity of the underground location and construction of nuclear power stations seems to be sufficiently heightened, and the basic research has been carried out also in the Central Research Institute of Electric Power Industry. In this paper, as to underground nuclear power stations as one of the forms of utilizing underground space, the concept, the advantage in aseismatic capability, the safety at the time of a supposed accident, and the economical efficiency are discussed. (Kako, I.)

  13. Starting of nuclear power stations

    The procedure is briefly characterized of jobs in nuclear power plant start-up and the differences are pointed out from those used in conventional power generation. Pressure tests are described oriented to tightness, tests of the secondary circuit and of the individual nodes and facilities. The possibility is shown of increased efficiency of such jobs on an example of the hydraulic tests of the second unit of the Dukovany nuclear power plant where the second and the third stages were combined in the so-colled integrated hydraulic test. (Z.M.). 5 figs

  14. Series: Information pavilions of nuclear power stations

    The information pavilion of the Leibstadt nuclear power station is featured. Some 10,000 people visit annually the pavilion, 1/3rd of which are school pupils, and 30% to 40% are German nationals. The pavilion is open to visitors and individuals seven days/week and tours cover the actual installations of which the cooling tower is very popular. Seating space is available for discussions. Some 165,000 people have visited the Leibstadt nuclear power station since 1974. (P.F.K.)

  15. Studying dynamics of indicators of nuclear power stations exploitation (the case of US nuclear power stations)

    Varshavsky, Leonid


    Analysis of external and internal factors influencing significant improvement of economic indicators of US nuclear power stations in the 1990s is carried out. Approaches to modeling dynamics of capacity factors of nuclear power stations are proposed. Comparative analysis of dynamics of capacity factors and occupational radiation exposure for various generations of US nuclear power plants is carried out. Dynamical characteristics of «learning by doing» effects for analyzed indicators are measu...

  16. Principles of nuclear power station control

    Lecture notes are presented which were first distributed as part of a UKAEA introductory course on reactor technology held during November 1975. The material is presented in a manner which hopefully will enable recent graduates in science and technology to obtain a broad overall picture of the problems involved. A nuclear power station is only one element of a dispersed interconnected arrangement of other nuclear and fossil-fired units which together constitute the national 'grid'. Thus the control of any one station must relate to the objectives of the grid network as a whole. Economic and technological factors are shown to lead to a national power supply operating around 50 Hz. A precise control of the supply frequency is also motivated by economic and technological considerations, and it is achieved by regulating the output power of individual stations. In order to make the whole grid network stable in following the load, it is shown that a satisfactory practical criterion is for each station to be stable when operating in isolation with a variable load. As regards individual stations, several special control problems concerned with individual plant items are discussed; these include controlled reactivity insertions, temperature reactivity time constants and flow instability. A simplified analysis establishes a fundamental relationship between the stored thermal energy of a boiler unit (a function of mechanical construction) and the flexibility of the heat source (nuclear or fossil-fired) if the station is to cope satisfactorily with demands arising from unscheduled losses of other generating sets or transmission capacity. Finally, two basic control schemes for power station operation are described, known as coupled and decoupled control. Each of the control modes has its own merits, which depend on the proposed station operating strategy (base-load or load-following) and the nature of the heat source. (author)

  17. Comissioning of Fessenheim nuclear power station

    Fessenheim Nuclear Power Station comprises two power plant units of the same design each with a net electrical rated capacity of 890 MW. Each unit comprises a nuclear steam generator system of the pressurized water type and the associated turbine-generator. Successive commissioning procedures extended over a period of three years from initial functional tests to commercial operation of the steam generator system. (orig.)

  18. Staff Organization in Nuclear Power Stations

    This paper deals with the organization of operating and maintenance staff at nuclear power stations in Italy and manpower variations, either because the plants themselves differ or are organized in some special way. Staff doing jobs for which a specific training is required are given special consideration in the paper. (author)

  19. 75 FR 75706 - Dresden Nuclear Power Station, Units 2 and 3 and Quad Cities Nuclear Power Station, Unit Nos. 1...


    ... Power Station, Units 2 and 3 and Quad Cities Nuclear Power Station, Unit Nos. 1 and 2; Notice of... Nuclear Power Station, Units 2 and 3, respectively, located in Grundy County, Illinois, and to Renewed Facility Operating License Nos. DPR-29 and DPR-30 for Quad Cities Nuclear Power Station, Unit Nos. 1 and...

  20. Distributed systems for protecting nuclear power stations

    The advantages of distributed control systems for the control of nuclear power stations are obviously of great interest. Some years ago, EPRI, (Electric Power Research Institute) showed that multiplexing the signals is technically feasible, that it enables the availability specifications to be met and costs to be reduced. Since then, many distributed control systems have been proposed by the manufacturers. This note offers some comments on the application of the distribution concept to protection systems -what should be distributed- and ends with a brief description of a protection system based on microprocessors for the pressurized power stations now being built in France

  1. Cherokee Stickball: A Changing Tradition.

    Olson, Ted


    Discusses the history of Cherokee stickball, a ball game dating back at least to the 1500s that was once used (as an alternative to war) for resolving grievances between tribes and townships. Describes traditional aspects of Cherokee stickball and notes the steady decline of the game and its traditional rules and ceremonies. (LP)

  2. Cherokee Stories of the Supernatural.

    Scancarelli, Janine


    Stories of personal experience of supernatural events are a highly-valued form of verbal art for Cherokee speakers. Both the people who tell them and those who listen regard such stories as entertaining and instructional. These stories even reflect some of the tensions that exist between traditional Cherokee culture and modern American social…

  3. Sequoyah and the Cherokee Syllabary.

    Thomas, Joy

    Since the early nineteenth century, scholars have marveled at the unlettered Cherokee native named Sequoyah--or Sikwaya--and also known as John Guess--or Guest or Gist--who, unassisted, developed a medium for the written expression of the Cherokee language that was uniquely appropriate to the peculiarities of the spoken language. There is much…

  4. Phasing out Britain's nuclear power stations

    This report examines the technical and economic feasibility of phasing-out Britain's nuclear power stations. It considers a range of strategies, from complete closure by 1990, to allowing them to run the full course of their planned lives, which for some reactors would be well into the next century. For reasons stated, closure of all Britain's nuclear power stations by 1990 or shortly afterwards would be likely to lead to a shortfall in generating capacity. Sufficient new generating capacity could not be provided quickly enough to avoid this shortfall, so power cuts at times of winter peak demand would probably occur. However, the older Magnox reactors, which comprise nine of the sixteen nuclear power stations, could be closed by the end of the present decade without risking power cuts. The seven AGRs, which are all newer, could be closed between 1995 and 2000, as replacement capacity was completed. 6 GW of new capacity, equivalent to three coal-fired power stations of standard design, would be needed for this purpose. The phasing out of nuclear power would add to the electricity industry operating costs. Taking all costs together - decommissioning, operating costs and the capital cost of replacement - the increase in electricity price is unlikely to exceed 10%. It is essential that the phasing-out of nuclear power is supported by new investment in the UK coal industry. Given the long time lag in completing new developments, it would be wise to make an early start on this new capacity in order to avoid large coal imports in the 1990s. (author)

  5. Catawba nuclear station preoperational ALARA review

    This paper describes the particular emphasis placed on preoperational as los as reasonably achievable (ALARA) considerations at Duke Power's Catawba Nuclear Station. A strong station commitment to the ALARA philosophy, and review of existing capabilities, led to development of an aggressive two-part ALARA program. Capabilities consisted of sufficient numbers of available personnel, lengthy lead time during construction, a very detailed plastic model, and a sister plant of similar design. The program, as developed, consisted of a preoperational program, which looked at design and construction aspects of ALARA, and the operational program, dealing with the ALARA committee and operational problems. MAnagement's philosophy of holding everyone responsible for ALARA provided the motivation to organize the preoperational program to use that resource. The Health Physics group accepted responsibility for development, coordination, and reviewer training. The problem provided a base to build on as station personnel gained experience in their own crafts and radiation protection in general

  6. Technological development of Guangdong nuclear power station

    After over 5 years of operations, the Guangdong Nuclear Power Station (GNPS) has achieved good results both economically and in operational safety performance. The main attributes to the success of the plant operational performances include the equipment reliability, the technical capability and management efficiency. To that the key strategy has been to adopt know-how and technological transfer and encourage self-innovation, aiming to strive for the long-term self-reliance in design, manufacturing and operating the plant. (author)

  7. Robot equipment for nuclear power stations

    A cassette transfer device produced at GANZ-MAVAG, to be installed at the Paks nuclear power station has been previously reported. Further on the requirements set against the robot equipment are described with special regard to safety and economic aspects. Besides the cassette transfer devices designed to tend reactors of an output of 440 MW, information is given on the cassette transfer devices intended for reactors having an output of 1000 MW, actually under development. (author)

  8. Requirement profile for nuclear power station personnel

    The starting point in deriving the requirement profile for the shift personnel in the control rooms of nuclear power stations is information of a technical, organisational and ergonomic kind. The technique used, the distribution of work to different work areas and the configuration of the workplace is determined by the tasks and the environmental conditions in which they have to be done. (orig./DG)

  9. Report on Darlington nuclear generating station

    The Select Committee on Energy was appointed on July 10, 1985 by the Legislative Assembly of the Province of Ontario in order to inquire into and report on Ontario Hydro affairs within ten months. Two sessions were planned the first of which was a review of the Darlington Nuclear Generating Station. Darlington is a large, 4 unit nuclear-powered electricity generating station currently under construction on the shore of Lake Ontario in the town of Newcastle. At the time the Committee met, construction had been underway for over four years. The first two units are scheduled to become operational in 1988 and 1989 with the second two scheduled to become operational in 1991 and 1992. The total estimated cost of the station is $10.895 billion of which $3.66 billion has been spent and $3.385 billion has been committed. Though the nuclear industry has been a major area of investment in Ontario over the past decade, the demand for electrical power from nuclear stations has been significantly decreased. This report focusses on the need for Darlington and public policy issues involved in planning and completing it. The Committee proposed the following recommendations: 1) The relationship between the Government of Ontario and Ontario Hydro and their individual responsibilities should be clarified. 2) An independent review of the Ontario Hydro demand/supply options should be carried out. 3) No further significant contracts for Darlington units 3 and 4 should be let for materials not required for construction during the next 6 months while the Committee studies demand and supply options

  10. Multivariable control in nuclear power stations

    Multivariable methods have the potential to improve the control of large systems such as nuclear power stations. Linear-quadratic optimal control is a multivariable method based on the minimization of a cost function. A related technique leads to the Kalman filter for estimation of plant state from noisy measurements. A design program for optimal control and Kalman filtering has been developed as part of a computer-aided design package for multivariable control systems. The method is demonstrated on a model of a nuclear steam generator, and simulated results are presented

  11. Assimilationist Language in Cherokee Women's Petitions: A Political Call to Reclaim Traditional Cherokee Culture

    Bennion, Jillian Moore


    Twenty-one years before the forced-removal of Cherokee people from their native lands east of the Mississippi, Cherokee people fought peacefully to maintain ownership of Cherokee-owned lands and attempted to preserve, at least in part, traditional Cherokee culture. Through the drafting of petitions, specifically written between 1817-19, Cherokee women pushed back against pressure to assimilate to Anglo-American culture and to cede Cherokee land to the United States Government. The five petiti...

  12. 78 FR 35646 - Byron Nuclear Station, Units 1 and 2, and Braidwood Nuclear Station, Units 1 and 2


    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Byron Nuclear Station, Units 1 and 2, and Braidwood Nuclear Station, Units 1 and 2 AGENCY: Nuclear... U.S. Nuclear Regulatory Commission (NRC) has received an application, dated May 29, 2013,...

  13. Status of Cherokee Reservoir


    This is the first in a series of reports prepared by Tennessee Valley Authority (TVA) for those interested in the conditions of TVA reservoirs. This overviews of Cherokee Reservoir summarizes reservoir and watershed characteristics, reservoir uses and use impairments, water quality and aquatic biological conditions, and activities of reservoir management agencies. This information was extracted from the most current reports, publications, and data available, and interviews with water resource professionals in various Federal, state, and local agencies and in public and private water supply and wastewater treatment facilities. 11 refs., 4 figs., 1 tab.

  14. Commentary: childhood cancer near nuclear power stations

    Fairlie Ian


    Full Text Available Abstract In 2008, the KiKK study in Germany reported a 1.6-fold increase in solid cancers and a 2.2-fold increase in leukemias among children living within 5 km of all German nuclear power stations. The study has triggered debates as to the cause(s of these increased cancers. This article reports on the findings of the KiKK study; discusses past and more recent epidemiological studies of leukemias near nuclear installations around the world, and outlines a possible biological mechanism to explain the increased cancers. This suggests that the observed high rates of infant leukemias may be a teratogenic effect from incorporated radionuclides. Doses from environmental emissions from nuclear reactors to embryos and fetuses in pregnant women near nuclear power stations may be larger than suspected. Hematopoietic tissues appear to be considerably more radiosensitive in embryos/fetuses than in newborn babies. Recommendations for advice to local residents and for further research are made.

  15. Tethered nuclear power for the space station

    A nuclear space power system the SP-100 is being developed for future missions where large amounts of electrical power will be required. Although it is primarily intended for unmanned spacecraft, it can be adapted to a manned space platform by tethering it above the station through an electrical transmission line which isolates the reactor far away from the inhabited platform and conveys its power back to where it is needed. The transmission line, used in conjunction with an instrument rate shield, attenuates reactor radiation in the vicinity of the space station to less than one-one hundredth of the natural background which is already there. This combination of shielding and distance attenuation is less than one-tenth the mass of boom-mounted or onboard man-rated shields that are required when the reactor is mounted nearby. This paper describes how connection is made to the platform (configuration, operational requirements) and introduces a new element the coaxial transmission tube which enables efficient transmission of electrical power through long tethers in space. Design methodology for transmission tubes and tube arrays is discussed. An example conceptual design is presented that shows SP-100 at three power levels 100 kWe, 300 kWe, and 1000 kWe connected to space station via a 2 km HVDC transmission line/tether. Power system performance, mass, and radiation hazard are estimated with impacts on space station architecture and operation. 23 references

  16. Underground construction of nuclear power stations

    In the discussions about the safety of nuclear installations the question of building nuclear power stations below ground is being raised again and again. Almost all the experts in the field regard further investigations of underground construction as necessary or desirable. Although in present above-ground plant designs safety measures must ensure that the consequences of hypothetical accidents will in any case be accommodated without involving any hazard to the public, there are some question marks when it comes to ensuring protection against acts of war and sabotage. This contribution outlines the variants of underground designs of nuclear power stations and their feasibility at the present state of the art. The question is studied whether underground construction will increase the safety of the public as against present above-ground designs. Another problem considered is the question of whether the extensive protective measures required under the present licensing procedures and implemented in these plants already preclude any real hazard to the environment with a high degree of certainty, which would leave no necessity for underground constructions. (orig.)

  17. Delayed Station Blackout Event and Nuclear Safety

    Andrija Volkanovski; Andrej Prošek


    The loss of off-site power (LOOP) event occurs when all electrical power to the nuclear power plant from the power grid is lost. Complete failure of both off-site and on-site alternating current (AC) power sources is referred to as a station blackout (SBO). Combined LOOP and SBO events are analyzed in this paper. The analysis is done for different time delays between the LOOP and SBO events. Deterministic safety analysis is utilized for the assessment of the plant parameters for different tim...

  18. Limerick Nuclear Generating Station vibration monitoring system

    Philadelphia Electric Company utilizes a vibration monitoring computer system at its Limerick Nuclear Generating Station to evaluate machine performance. Performance can be evaluated through instantaneous sampling, online static and transient data. The system functions as an alarm monitor, displaying timely alarm data to the control area. The passage of time since the system's inception has been a learning period. Evaluation through continuous use has led to many enhancements in alarm handling and in the acquisition and display of machine data. Due to the system's sophistication, a routine maintenance program is a necessity. This paper describes the system's diagnostic tools and current utilization. System development and maintenance techniques will also be discussed

  19. Trustworthiness test of nuclear power station employees

    The trustworthiness test is an important part of securing nuclear facilities against internal offenders. For performing such a test the supervisory authority, which is the State's physical protection authority, contacts the security offices or authorities regarding persons who work inside the sensitive areas of nuclear power stations - areas containing nuclear material. The trustworthiness test covers the present activities of the employees and gives a prediction for the following five years; after this time the test must be repeated. The trustworthiness test is a prerequisite for a facility to obtain a licence for the use of nuclear material, to hire persons for work in the inner area of a nuclear facility or the hire persons for leading positions. In Germany the content and form of the test as well as the evaluation of the results are regulated in a guideline of the Federal Ministry for the Environment, Nature Conservation and Reactor Safety (BMU) (latest edition in June 1996). The test is performed by the licensing authority or the supervisory authority. the basis of the test is a declaration by the employee concerned, containing personal data and the agreement of the person to the use of the data files by the safety authorities. It the results of the test are positive, the person tested has the possibility to comment on differences or to explain certain facts. The paper presents details of the BMU guideline. (author)

  20. Being influenced: a Cherokee way of mentoring.

    Lowe, John


    This article reports research findings related to how the Cherokee male achieves self-reliance and how health care professionals can facilitate and incorporate the Cherokee concept of self-reliance into heath care of the Cherokee. Self-reliance to the Cherokee has been defined as a cultural domain with a composite of the three categories: (a) being responsible, (b) being disciplined, and (c) being confident (Lowe, 2002, 2003). Two sample groups of 12 to 14 Cherokee adults were interviewed and observed. The results reveal that mentor-type relationships influenced the participants in the development of Cherokee self-reliance. PMID:16028448

  1. Forecasting Canadian nuclear power station construction costs

    Because of the huge volume of capital required to construct a modern electric power generating station, investment decisions have to be made with as complete an understanding of the consequences of the decision as possible. This understanding must be provided by the evaluation of future situations. A key consideration in an evaluation is the financial component. This paper attempts to use an econometric method to forecast the construction costs escalation of a standard Canadian nuclear generating station (NGS). A brief review of the history of Canadian nuclear electric power is provided. The major components of the construction costs of a Canadian NGS are studied and summarized. A database is built and indexes are prepared. Based on these indexes, an econometric forecasting model is constructed using an apparently new econometric methodology of forecasting modelling. Forecasts for a period of 40 years are generated and applications (such as alternative scenario forecasts and range forecasts) to uncertainty assessment and/or decision-making are demonstrated. The indexes, the model, and the forecasts and their applications, to the best of the author's knowledge, are the first for Canadian NGS constructions. (author)

  2. Living near a nuclear power station

    The need to expand nuclear power and its advantages are discussed publicly nearly each week. According to politicians and the nuclear lobby investing tens of billions Sk at Mochovce will bring Slovakia the often cited 'independence and energy self-sufficiency'. It will also mean profit for Slovenske elektrarne and the company's shareholders - the state and Italian company, Enel. In addition to the lively discussion on the pros and cons of nuclear energy, TREND was also interested in the living conditions around the concrete and strictly guarded, potentially dangerous plants and in the opinion of the people most affected by Mochovce and Jaslovske Bohunice on expansion of the existing and the building of new nuclear power plants. The construction of nuclear powers stations in these regions was not only about new jobs. The state 'prescribed' iodine pills and did not allow any construction in the region and, in the case of Mochovce, ordered the complete demolition of a village. The only thing that remained from Mochovce village was the church. 'And when it was found that the power plant would not reach it, it was even given a new roof. Former inhabitants, especially the older ones that had problems accepting the evacuation, used to visit it often,' explained Jan Foldy, the head of the local municipality in Kalna nad Hronom. After many years, life in the neighbouring villages is not bad. Their budgets are overflowing and so they can afford to spoil their inhabitants with free cable TV and high standard sport facilities, which should partly compensate for the fact that the people are living so close to a nuclear facility. (authors)

  3. Engineering blasting and vibration monitor near nuclear power station

    The record of earth and stone work blasting test near the Daya bay nuclear power station is presented. Through the test, the schemes of earth and stone work blasting excavation and vibration monitor are gained, ensuring not only the safe operation of Daya bay nuclear power station but also the progress of Lingao nuclear power station engineering. Practice indicates that the two schemes are feasible

  4. Nuclear weapons and nuclear power stations: what is the connection

    From the start of the nuclear age with the dropping of two atom bombs on Japan in 1945 it has been known that this new source of primary energy could be exploited for weapons or for replacing coal or oil in electricity-generating stations. Nuclear energy is made from two elements: naturally occurring uranium and man-made plutonium. Their processing differs according to the intended end-use. Great efforts have been and still are made to disguise the close connection between nuclear energy for war and for power stations. Two reasons are suggested for this: political conveniences in avoiding additional informed protests against nuclear weapon production and industrial convenience in carrying on without public protest what has become a very profitable industry. It is argued that medical doctors, because of their professional prestige, can speak and be listened to on the risks of continuing to exploit this newly discovered form of energy. Furthermore, this industry is uniquely hazardous to the health of its workers, to the public generally and possibly to the procreation and genetic health of future generations. (author)

  5. 77 FR 50460 - Cherokee Resource Advisory Committee


    ... Forest Service Cherokee Resource Advisory Committee AGENCY: Forest Service, USDA. ACTION: Notice of meeting. SUMMARY: The Cherokee Resource Advisory Committee will meet in Knoxville, Tennessee. The... Coordinator, Cherokee National Forest, 423-476-9729, . Individuals who...

  6. Cherokee History: An Analysis of Recent Studies.

    Williams, Walter L.


    Comments on recent studies on the Cherokee Nation which emphasize the profound differences of traditional Cherokee culture from White society, the deep factionalism that has plagued the Cherokees since the emergence of a mixed-blood group, and the remarkable persistence of native values and social forms despite two centuries of acculturation. (NEC)

  7. Developmental state and perspectives of USSR power stations, espec. nuclear power stations

    According to the resolutions of the 25th and 26th party congresses of the CPSU, the Soviet electric and thermal energy economy envisages as the mainstreams in development: Energy projects based on nuclear fuel, i.e. nuclear power stations (NPS), nuclear heat- and -power stations (NHPS) and nuclear heat stations (NHS); fuel-energy complexes: Ekibastuz, Kansk-Achinsk, West-Siberian complex (Tyumen); power stations utilizing non-conventional regenerative energy sources, i.e. solar, geothermal, MHD power stations. Further down, an overview is given on the developmental perspectives of nuclear-heat and nuclear-power economy and on the development of energy management based on fossil fuels. (orig./UA)

  8. Nuclear power stations located around Latvia

    The paper consider technical parameters of the nuclear power stations (NPPs) located around Latvia at a distance up to 1500 km. On this territory 163 NPPs were built meant for commercial use. They gave up to 123535 M We(net) in total. At the end of the twentieth century from the mentioned number there remained 141 functioning NPPs yielding totally 115327 M We(net). From these latter the majority (67.4 %) are water-cooled type reactors, half of them, 47, having been built after the projects by specialists of the former US. On the neighbouring territories (Russia, Ukraine, Romania, Czech and Slovak Republics) 18 NPPs are currently under construction, which are envisaged to yield about 14089 M We in total. (author)

  9. Grohnde nuclear power station in operation

    The Grohnde Nuclear Power Station in Hamelin on the river Weser is equipped with a pressurized water reactor in the 1,300 MWe power category. The plant was built by Kraftwerk Union AG (KWU) for Gemeinschaftskernkraftwerk Grohnde GmbH (KWG), in which Preussische Elektrizitaets-AG and Gemeinschaftskraftwerk Weser GmbH (Stadtwerke Bielefeld GmbH, Elektrizitaetswerk Minden-Ravensberg GmbH, Elektrizitaetswerk Wesertal GmbH) each hold 50%. Including the preplanning phase begun 1972, twelve years and a half passed until the complete plant was delivered to the operator. This is an extension of the planning and construction period by five and a half years compared to the original completion date of mid-1979. The delay was caused especially by the well-known licensing problems in the seventies and by a court order interrupting construction work. (orig./GL)

  10. Aging assessment of nuclear generating station cables

    A number of diagnostic techniques requiring small samples (e.g. shavings) for monitoring the condition of nuclear generating station cables have been identified. The cables studied were insulated with cross-linked or unmodified polyethylene, ethylene propylene rubber, butyl rubber, styrene butadiene rubber, and polyvinyl chloride. Specimens were aged at elevated temperatures, or gamma irradiated up to 120 Mrad. The degradation was assessed by conventional elongation measurements, differential scanning calorimetry (DSC), oxidation induction time, DSC oxidation induction temperature (under high oxygen pressure), infrared carbonyl absorption, density, and swelling measurements. The sensitivities of the diagnostic techniques in measuring oxidation and embrittlement were compared with the elongation results, and a criterion for monitoring the cable degradation was developed. Some results presented illustrate the use of the diagnostic techniques in monitoring degradation. 13 refs., 2 tabs., 24 figs

  11. Location and security of nuclear power stations

    Starting from recent court decisions, the author highlights environmental safety in regard to operation according to regulations and to accidents, and the excludability of an uncontrollable, catastrophic accident. He discusses the site issue under the legal aspect of protecting the individual, of reducing the residual risk, of an international process of consultations on nuclear power stations situated near to frontiers. A decision on sites by parliament and the setting of dose limits by law are rejected by the author who advocates further government provisions to reduce the residual risk. He comes to the conclusion that the site problem and the problems of legal decision-making are shrinking with the achieved safety, test and control techniques. This is also demonstrated to an increasing extent by legal proceedings at administrative courts. Despite many difficulties occurring in this proceedings - stringent decisions made very quickly, long duration of proceedings - it seems useless to shift the competence of decision-making elsewhere. (HSCH)

  12. Ardennes nuclear power station. Annual report, 1976

    The Ardennes nuclear power station suffered two serious production setbacks in 1976 in spite of the satisfactory behavior of the equipment. The first is due to exceptionally unfavorable temperature and flow-rate conditions of the river Meuse, which caused a loss of production of about 300 million kWh. The second arises from the application of the Service des Mines regulations (decree of February 26th 1974) which in 1976 entailed the thorough inspection of the primary circuit and the ten-yearly hydraulic trial during the routine shutdown. This shutdown, intended for three months, in fact lasted an extra two weeks. Calculating the immobilization necessary for a general revision of the material, the production loss ascribable to statutory inspection may also estimated to 300 GWh. The net energy produced was 1362 GWh, the number of hours connected 5536h, the availability coefficient in time 62%, the total number of shutdowns 14. The equipment as a whole works very well. The tests carried out on the occasion of the ten-yearly trial showed the state of the main circuit to be perfectly satisfactoy, while inspections during the hydraulic trial at 207 bar revealed no anomalies. Where the behavior of the steam generators is concerned, only 20 tubes over a total of 6500 have been obstructed since the unit was started up in 1967. The cost per kWh electric of the station is 8.82 French centimes

  13. Water chemistry in nuclear power station

    The nuclear power generation in Japan takes about 30 % of the total generated electric power, and the stable operation and the improvement of the rate of operation are anticipated. In such situation, the water quality control in nuclear power stations aims at the prevention of the corrosion damage of structural materials in the plants, the grasp of the behavior of corrosion products of infinitesimal amount and the countermeasures for reducing them as the important subjects. At the beginning of the operation of LWRs in Japan, stress corrosion cracking and the rise of plant dose rate in BWRs and the corrosion damage of steam generator tubes in PWRs occurred, and the importance of water quality control was recognized. The water quality control standard and the materials for BWRs are shown. In BWRs, the maintenance of the purity of water is the primary subject. The quantity of dissolved oxygen is properly adjusted, and the reduction of generation and removal of iron crud are carried out. Also the water quality control standard and the materials for PWRs are shown. In the primary system, the concentrations of boric acid and lithium hydroxide are controlled, and the pH of coolant is an adjustment factor. In the secondary system, all volatile treatment and condensate desalting equipment are used. (Kako, I.)

  14. 75 FR 2164 - Entergy Nuclear Operations, Inc.; Pilgrim Nuclear Power Station; Environmental Assessment and...


    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Entergy Nuclear Operations, Inc.; Pilgrim Nuclear Power Station; Environmental Assessment and Finding of No Significant Impact The U.S. Nuclear Regulatory Commission (NRC) is considering issuance...

  15. Human reliability analysis of Lingao Nuclear Power Station

    The necessity of human reliability analysis (HRA) of Lingao Nuclear Power Station are analyzed, and the method and operation procedures of HRA is briefed. One of the human factors events (HFE) is analyzed in detail and some questions of HRA are discussed. The authors present the analytical results of 61 HFEs, and make a brief introduction of HRA contribution to Lingao Nuclear Power Station

  16. Computer management of refueling for nuclear power station

    The author analyzes the disadvantages of refueling management for nuclear power station at present. A method of computer management of refueling for nuclear power station is put forward and the main functions of the system are explained. The implementation method of the system is also discussed. Finally the expanded prospect is given

  17. 77 FR 5265 - Eastern Band of Cherokee Indians-Cherokee Code Chapter 18B, Regulation of Alcoholic Beverages


    ... Bureau of Indian Affairs Eastern Band of Cherokee Indians--Cherokee Code Chapter 18B, Regulation of... publishes the Amendment to the Eastern Band of Cherokee Indians--Cherokee Code Chapter 18B, Regulation of... within the Eastern Band of Cherokee Indians' Reservation. This Ordinance will increase the ability of...

  18. Delayed Station Blackout Event and Nuclear Safety

    Andrija Volkanovski


    Full Text Available The loss of off-site power (LOOP event occurs when all electrical power to the nuclear power plant from the power grid is lost. Complete failure of both off-site and on-site alternating current (AC power sources is referred to as a station blackout (SBO. Combined LOOP and SBO events are analyzed in this paper. The analysis is done for different time delays between the LOOP and SBO events. Deterministic safety analysis is utilized for the assessment of the plant parameters for different time delays of the SBO event. Obtained plant parameters are used for the assessment of the probabilities of the functional events in the SBO event tree. The results show that the time delay of the SBO after the LOOP leads to a decrease of the core damage frequency (CDF from the SBO event tree. The reduction of the CDF depends on the time delay of the SBO after the LOOP event. The results show the importance of the safety systems to operate after the plant shutdown when the decay heat is large. Small changes of the basic events importance measures are identified with the introduction of the delay of the SBO event.

  19. Corrosion protection at a nuclear power station

    Early in the 1970's, the Electricity Supply Commission (Eskom) in South Africa took the decision to construct South Africa's first nuclear fuelled power station. The environment at Koeberg, however, was determined as being particularly corrosive. Eskom was thus faced with the task of selecting corrosion resistant materials and protective coating systems that would provide the required performance in the hostile marine environment. In order to select the correct coating, it was decided to conduct an investigation into the behaviour of various coating systems. All the major coating suppliers in South Africa were invited to provide wet samples of the coating systems that they would recommend. These coatings were applied to mild steel panels which had been prepared in accordance with the coating manufacturer's specification. The panels were then mounted on exposure test racks at various sites. The results of this coating exposure programme were used in the compilation of the corrosion protection specifications for plant and components exposed to the atmosphere at Koeberg. 1 ill

  20. Review of radioactive discharges from nuclear power stations

    HM Inspectorate of Pollution commissioned, with authorising responsibilities in England and Wales, a study into the discharges of radioactive effluents from Nuclear Power Stations. The study considered arisings from nuclear power stations in Europe and the USA and the technologies to treat and control the radioactive discharges. This report is a review of the arisings and concludes that suitable technologies exist, which if applied, could reduce discharges from nuclear power plants in England and Wales in line with the rest of Europe. (author)

  1. Cherokee Culture and School Achievement.

    Brown, Anthony D.


    Compares the effect of cooperative and competitive behaviors of Cherokee and Anglo American elementary school students on academic achievement. Suggests changes in teaching techniques and lesson organization that might raise academic achievement while taking into consideration tribal traditions that limit scholastic achievement in an…

  2. The safety reinforcement measures at Shika Nuclear Power Station

    The Fukushima Daiichi nuclear disaster was initiated by the Tohoku earthquake and subsequent massive tsunami on 11 March 2011. To prevent the event as the Fukushima Daiichi nuclear disaster, we had implemented the necessary safety reinforcement measures in Shika Nuclear Power Stations. In this paper, we are going to introduce the flood prevention measures that prevent seawater from entering the power stations. And we also secured emergency power supplies for the case of loss of all AC power supplies. In addition, we secured the function of coolant systems by diversifying water sources and deployment of fire engines and so forth. As the next step, including the adaptation of Shika Nuclear Power Stations for the new regulations that are going to be forced on next July, not staying the existing state, we are going to study and implement the further measures to improve safety and reliability of Shika Nuclear Power Stations. (author)

  3. 76 FR 50274 - Terrestrial Environmental Studies for Nuclear Power Stations


    ...The U.S. Nuclear Regulatory Commission (NRC or the Commission) is issuing for public comment draft regulatory guide (DG), DG-4016, ``Terrestrial Environmental Studies for Nuclear Power Stations.'' This guide provides technical guidance that the NRC staff considers acceptable for terrestrial environmental studies and analyses supporting licensing decisions for nuclear power...

  4. Cherokee Practice, Missionary Intentions: Literacy Learning among Early Nineteenth-Century Cherokee Women

    Moulder, M. Amanda


    This article discusses how archival documents reveal early nineteenth-century Cherokee purposes for English-language literacy. In spite of Euro-American efforts to depoliticize Cherokee women's roles, Cherokee female students adapted the literacy tools of an outsider patriarchal society to retain public, political power. Their writing served…

  5. "Our Beloved Cherokee": A Naturalistic Study of Cherokee Preschool Language Immersion

    Peter, Lizette


    This article contributes to our knowledge of endangered language revitalization by offering a case study of a Cherokee Nation (CN) preschool immersion program named Tsalagi Ageyui, "Our Beloved Cherokee." A naturalistic inquiry into the micro- and macrosociocultural dimensions of reversing Cherokee language shift reveals that, of all CN language…

  6. Electrical wire for use in nuclear generating stations

    Electrical wire and cable suitable for use in nuclear generating stations, having at least one electrical conductor, a micaceous insulating layer surrounding the conductor and a layer of fluoropolymer insulation surrounding the micaceous layer are described

  7. Reload Startup Physics Tests for Tianwan Nuclear Power station

    This paper briefly describes the test purposes, test items, test schedules and test equipment's for reload startup physics test's on Unit 1 and 2 of Tianwan Nuclear Power station. Then, an overview of the previous thrice tests and evaluations on the tests results are presented. In the end, the paper shows the development and work direction of optimization project for reload startup physics tests on Unit 1 and 2 of Tianwan Nuclear Power station. (Authors)

  8. Application of additional diesel generators in nuclear power stations

    In order to enlarge the nuclear safety margin, ensure safe shutdown of nuclear reactors under loss of on-site and offsite power supply, and raise the unit availability through elongation of diesel fallback time under unavailability of emergency diesel generators, at present, nuclear power stations of most countries and zones in the world such as France, the U.S., south Africa, South Korea and Taiwan have been equipped with additional diesel generators, making the safety performance of above-mentioned nuclear power stations advanced in the world. The wiring procedures, power supply mode, testing methods and the power supply and connection schemes of motor control center are described

  9. Planning and preparedness for radiological emergencies at nuclear power stations

    The Radiological Emergency Preparedness (REP) Program was created after the March 1979 accident at the Three Mile Island nuclear power station. The Federal Emergency Management Agency (FEMA) assists state and local governments in reviewing and evaluating state and local REP plans and preparedness for accidents at nuclear power plants, in partnership with the US Nuclear Regulatory Commission (NRC), which evaluates safety and emergency preparedness at the power stations themselves. Argonne National Laboratory provides support and technical assistance to FEMA in evaluating nuclear power plant emergency response exercises, radiological emergency plans, and preparedness

  10. Inspection program for Embalse Nuclear Generating Station

    Embalse Nuclear Generating Station (ENGS), a CANDU 6 type with 648 MWe output, started operating in 1983. In the last 10 years it has shown an excellent performance with an average 88.25 % capacity factor. In order to maintain the safety and operation levels at economically convenient levels, an efficient management of the effects of aging of Critical Systems, Structures and Components is required. In this regard, Nucleoelectrica Argentina S.A.-ENGS's operator- has initiated a Plant Life Management (PLiM) program focused on reaching its design life and establishing the requirements for its life extension. Within the framework of this program, a series of reviews of the existing Operation and Maintenance programs is scheduled with the aim of establishing the bases for potential life extension. A work team has been designated to this effect and the team has received training in the PLiM methodologies by AECL. In this paper an analysis of the Inspection Program for ENGS is presented. Also, the areas to be reinforced for the Systems, Structures and Components identified as critical are identified based on the SAM (Systematic Assessment of Maintenance) methodologies. The ENGS Engineering Procedures form the basis for the inspection program along with the records of the inspections performed. The inspection program will be the object of analysis, as the starting point of the PLiM of ENGS. There are also other programs, for example those for preventive / predictive maintenance, routine testing, which focus on maintaining a high reliability of the safety as well as the process systems. All plant systems are taken into account with a list of inspections based on recommendations by the plant designer (AECL). It is continuously modified according to the results thereof and the experience of other plants, and revised within the framework of the SAM of the most important systems. Within this program, the ENGS chemistry laboratory and CNEA's (Comision Nacional Energia Atomica

  11. Station blackout at nuclear power plants: Radiological implications for nuclear war

    Recent work on station blackout is reviewed its radiological implications for a nuclear war scenario is explored. The major conclusion is that the effects of radiation from many nuclear weapon detonations in a nuclear war would swamp those from possible reactor accidents that result from station blackout

  12. 77 FR 35080 - Entergy Nuclear Operations, Inc., Pilgrim Nuclear Power Station; Record of Decision and Issuance...


    ... fossil fuel generation, renewable energy sources, demand-side measures such as energy conservation, and... COMMISSION Entergy Nuclear Operations, Inc., Pilgrim Nuclear Power Station; Record of Decision and Issuance... Operations Inc. (the licensee), the operator of the Pilgrim Nuclear Power Station (PNPS). Renewed...

  13. Erection all risks insurance for nuclear power station

    Nuclear power stations are built and installed with components and facilities highly sophisticated on the basis of modern science and technology. Therefore, it has various features in both risks and insurance provision. In considering the damage insurance for nuclear installations, the insurance for nuclear power stations is the most characteristic, and further, the outline can be grasped relatively easily. Among the various damage insurances for nuclear power stations, an insurance for all risks during their erection is described: risk-covering method, the objects of insurance, insurance-contracting particles, damages compensated by the insurance, damages and expenses not compensated, the amounts covered and the limits in damage compensation, the term of insurance, the burden charges of the insured party, the amounts of damage and the amounts covered, adjustment with a nuclear-power property insurance. (Mori, K.)

  14. Nuclear power generation modern power station practice


    Nuclear Power Generation focuses on the use of nuclear reactors as heat sources for electricity generation. This volume explains how nuclear energy can be harnessed to produce power by discussing the fundamental physical facts and the properties of matter underlying the operation of a reactor. This book is comprised of five chapters and opens with an overview of nuclear physics, first by considering the structure of matter and basic physical concepts such as atomic structure and nuclear reactions. The second chapter deals with the requirements of a reactor as a heat source, along with the diff

  15. 78 FR 61400 - Entergy Nuclear Operations, Inc., Pilgrim Nuclear Power Station, Issuance of Director's Decision


    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Entergy Nuclear Operations, Inc., Pilgrim Nuclear Power Station, Issuance of Director's Decision Notice is hereby given that the Director, Office of Nuclear Reactor Regulation, U.S. Nuclear...

  16. 77 FR 76541 - Entergy Nuclear Operations, Inc.; Pilgrim Nuclear Power Station


    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Entergy Nuclear Operations, Inc.; Pilgrim Nuclear Power Station AGENCY: Nuclear Regulatory.... Introduction The U.S. Nuclear Regulatory Commission (NRC) is considering issuance of an exemption from Title...

  17. A Dictionary of the Cherokee Indian Language.

    Alexander, J. T., Comp.

    This dictionary is divided into two main sections, each containing approximately 9,000 entries. In the first section, English to Cherokee, the information is organized in 3 columns. In column 1 are found English words in standard English orthography and in alphabetical order, in column 2 the romanized representation of the Cherokee translation and…

  18. Terminus Amnesia: Cherokee Freedmen, Citizenship, and Education

    Chin, Jeremiah; Bustamante, Nicholas; Solyom, Jessica Ann; Brayboy, Bryan McKinley Jones


    In 2007, the Cherokee Nation of Oklahoma amended its constitution to limit membership to only those who can trace lineal descent to an individual listed as "Cherokee by Blood" on the final Dawes Rolls. This exercise of sovereignty paradoxically ties the Dawes Rolls, the colonial instruments used to divide the lands and peoples of the…

  19. Collaborative Documentation and Revitalization of Cherokee Tone

    Herrick, Dylan; Berardo, Marcellino; Feeling, Durbin; Hirata-Edds, Tracy; Peter, Lizette


    Cherokee, the sole member of the southern branch of Iroquoian languages, is a severely endangered language. Unlike other members of the Iroquoian family, Cherokee has lexical tone. Community members are concerned about the potential loss of their language, and both speakers and teachers comment on the difficulty that language learners have with…

  20. Limits of Legal Action: The Cherokee Cases

    Norgren, Jill L.; Shattuck, Petra T.


    The article examines the limits of legal action in light of the experience of the Cherokee Nation in the nineteenth century. Their lawsuits, the cause of national controversy and ultimately detrimental to the Cherokee, raise questions about the effectiveness of litigation in solving divisive political conflict. (Author/NQ)

  1. Cherokees and Missionaries, 1789-1839.

    McLoughlin, William G.

    This book describes the crucial role missionaries played in the acculturation and "Americanization" of the Cherokee Indians from 1789 to 1839. The book compares the methods, successes, and failures of the Moravians, Presbyterians, Congegrationalists, Baptists, and Methodists in their attempts to Christianize the Cherokees. Each missionary society…

  2. The risks at nuclear power stations and their insurance

    Insurance can offer an uninterrupted insurance cover from start-up-to shut-down of a nuclear power station. This is assured by the insurance for the erection, for the nuclear liability, for the nuclear/fire, for the engines, for operational interruptions and for the transport. For each of the above mentioned insurance branches, essential characteristic features, such as risk carrier, protection range and insurance costs, are given. (orig.)

  3. A Series Dissertation on Tianwan Nuclear Power Station--Summary of Tianwan Nuclear Power Station Project

    Li Qiankun


    This is a summary in relation to the construction and operation of Tianwan Nuclear Power Station (the Project) at Lianyungang, Jiangsu Province, the People' s Republic of China. The breakdown specialty topic shall been given in times to come. In this report, the author attempted to give some general description of the Project, including the Project site' s general layout and geographical conditions. A description of its exposure to the elements is also provided, supported by some data made available to us. The key component parts of the Project are described, namely, the nuclear island which includes the reactor, steam generator and so on; the conventional island and the balance of plant. Wherever possible, the improvements to the reactor design over the operating V320 are highlighted, which result in the V428 reactor model. The supplier and contractor for the major equipment such as the reactor and the turbine is the Russian company, namely Atomstroyexport (ASE). There are third country suppliers who provide other equipment. For instance, Siemens supplies the full digital I&C system and Framatome ANP supplies the emergency diesel generators; the metal-clad switchgear cabinet by ABB of Australia; the main steam isolation valve unit by CCI AG of Switzerland. All these foreign suppliers are well known globally. Their experience and quality of the equipment supplied by them are well recognized by the people in the respective fields. As for the civil work and erection work, the most experienced and trustworthy local contractors have been selected. These contractors have proven their competence in similar contract work before. For the testing of the equipment, stringent and proper procedures which meet international standards are adopted. Finally, the author wished on this report could provide the world a safety and advanced Nuclear Project building in China.

  4. Activity transport in nuclear generating stations

    The objective of this paper is to give a basic understanding of the operational limitations caused by radiation fields in the present design of CANDU-PHW reactors. A simple model of activity transport is described, and the significance of various radioisotopes identified. The impact which radiation fields have at the Divisional, Station Manager and Operation levels, is outlined in the context of typical work situations. (author)

  5. Construction of Dukovany nuclear power station

    A brief list is given of basic data on the construction of the third Czechoslovak nuclear power plant at Dukovany with four WWER-440 reactors. The technical specifications of the reactors are given as are the specifications of steam generators and of the main circulating pumps. The layout is given of the nuclear power plant designed with regard to operating efficiency, urban integration, fire protection, safety and hygiene control. (J.C.)

  6. 75 FR 38147 - FirstEnergy Nuclear Operating Company; Davis-Besse Nuclear Power Station; Exemption


    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION FirstEnergy Nuclear Operating Company; Davis-Besse Nuclear Power Station; Exemption 1.0 Background FirstEnergy Nuclear Operating Company (FENOC, the licensee) is the holder of Facility Operating...

  7. 77 FR 47680 - Entergy Nuclear Operations, Inc.; Pilgrim Nuclear Power Station Receipt of Request for Action


    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Entergy Nuclear Operations, Inc.; Pilgrim Nuclear Power Station Receipt of Request for Action... Regulations (10 CFR) 2.206, ``Requests for Action under this Subpart,'' the U.S. Nuclear Regulatory...

  8. Preventive maintenance activities for nuclear power station

    The supply of stable electric power by getting rid of the failures of nuclear power plants is an important factor for obtaining reliance and social acceptance for nuclear power plants as power sources. Electric power companies have improved their installations as well as carried out maintenance during operation, regular inspection and arrangement. Nuclear plant manufacturers not only implement maintenance and facility-improving works at the request of electric power companies, but also have charge of cooperation in maintenance planning, maintenance engineering services such as operation and repair data analysis and the development of working robots for maintenance. This paper introduces the maintenance activities presently performed by Hitachi Ltd., that is (1) servicing activities for supporting maintenance centering around the Nuclear Plant Service Center; (2) maintenance works in regular inspection; (3) maintenance engineering services to offer preventive maintenance data; and (4) the automation of maintenance works and the development of working robots for reducing exposure to radiation. The robots for nuclear plants are roughly divided into the following four types, and the results of using robots are described. They are exchange machines for replacing reactor or auxiliary components; inspection machines for monitoring plant conditions during reactor operation and for inspection works during shutdown; decontamination machines for reducing radiation dose of reactor equipment; and machining robots for reactor equipment reconstruction or repairing works. (Wakatsuki, Y.)

  9. Nuclear power station and environmental protection

    Environmental pollution has become a major problem of the present times. In addition to the pollution of air, water, noise and food, there is pollution by industries and factories. Nuclear power plant is the best option to meet the increasing demand for power and to make use of available uranium and thorium in the country. It is generally believed that nuclear power plants increase pollution and are hazardous and not safe. An attempt has been made to analyse these beliefs on a scientific basis. (author). 5 refs., 3 figs

  10. Work sampling studies: Bruce Nuclear Generating Stations 'A' and 'B'

    Work sampling in Ontario Hydro's Nuclear Operations Branch is one of the programs that address questions of human performance. The work sampling methodology was designed to measure actual 'hands on tool' time (wrench time), and other activities associated with station maintenance staff. This paper describes the methodology and discusses the results of wrench time studies conducted at Bruce Nuclear Generating Stations 'A' and 'B'. On the basis of the data collected, conclusions are drawn as to the usefulness of the work sampling technique. 4 refs., 13 tabs., 1 fig., 1 appendix

  11. Bid invitations for nuclear power stations

    Types of bid invitations, basic requirements on bid invitation documents, basic content of a turnkey bid invitation (bid invitation letter, instructions to the bidders, terms and conditions of the draft contract, technical specifications, site data and information), nuclear fuel procurement, differences turnkey - non-turnkey, legal, commerical, and technical matters concerning the contract document. (HP)

  12. Renewal of a nuclear power station using the nuclear power station. Proposal to the energy policy by British Energy, Co

    British Energy, Co. (BE) carried out a proposal containing the titled content on review of energy policy promoted by the English Government. At present, in England, as about one fourth of total power generation is supplied by nuclear power generation, because of no construction plan of a new nuclear power station, no unit will be operated on 2025 except the Sizewell Nuclear Power Station. Now, BE proposed that from a viewpoint of energy security in England and the Earth environment, shares of power generation on 2025 should be 15 % in coal heat, 40 % in gas heat, 20 % in reusable energy, and 25 % in nuclear power generations. Therefore, it is said that about ten units of 1.0 to 1.2 million kW output of nuclear power station must be constructed and begun to operate from 2010 to 2025. However, as at present power market price in England, new construction of a nuclear power station will not be payable, together with proposing a carbon-free obligation system where a part of power is obtained from a source without emission of CO2, BE claims to have a negotiation to exempt disposal responsibility on used fuels and radioactive wastes of neck in BE's yield to enforce equity finance ability of BE. Here was introduced on outlines of the proposal. (G.K.)

  13. Surry nuclear power station: 25th anniversary

    Virginia Power is one of the ten biggest electricity utilities in the United States of America. In 1972, the Surry-1 nuclear generating unit, equipped with an 850 MWe pressurized water reactor from Westinghouse, was accepted into commercial operation. Unit-2 followed in 1973. The North Anna plant is equipped with two 950 MWe PWR commissioned in 1978 and 1980, respectively. The four units together supply roughly one third of the electric power of the grid system in Virginia. They convert nuclear energy into electric power in an economic way: capacity utilization averaged over five years amounted to 90%, and the generating costs were 1.2 cents per kilowatthour. In 1996, the operator began to make use of the experience accumulated in running his plants when backfitting the three generating units on the Millstone site, which are currently out of operation. An agreement on cooperation to this effect was signed by the two utilities, Virginia Power and Northeast Nuclear Energy Company. As a consequence of deregulation of the US electricity market it may be economically preferable to buy electric power instead of generating it in-house. (orig.)

  14. Model of a nuclear power station

    A model reduced in scale compared to the original of a nuclear powerstation including its buildings, including the reactor building and turbine hall, the plant, components, machines and pipework as components to be cut out with appropriate sticky edges for the individual model components to be glued on sheets, particularly of strong paper or cardboard, is shown. By folding and/or bending the cutout components and glueing the sticky edges, the model parts with edged or curved surfaces can be produced. (orig./HP)

  15. Tritium releases and impact about EDF nuclear power stations

    After a description of the different ways of formation of tritium in the nuclear power stations (either by fission or by activation), the authors discuss the levels of tritium releases by these power stations, indicate the tritium average activities in liquid and gaseous radioactive releases in 2008. They indicate the choices made by EDF and the actions performed to control these releases. They describe how the presence of tritium in the environment is monitored and how measurements are published. They discuss the interpretation of these measurements (in water streams, water sheets, sediments, along the Channel French coasts), and the impact of the tritium released by the nuclear power stations. They evoke modelling studies and researches supported by EDF on the impact of tritium on mankind

  16. Mobile incineration services at Commonwealth Edison's nuclear stations

    As the costs for low-level waste disposal escalate, and as the January 1, 1986 date draws nearer, utilities throughout the United States are formulating and implementing plans to reduce the volumes of the low-level radioactive waste being generated at their nuclear power stations. Techniques being used to accomplish this goal range from sorting of dry active waste to complete volume reduction systems, like the Aerojet VR Systems being installed at Commonwealth Edison's Byron and Braidwood Stations. In between these extremes are partial solutions to the problem, including compaction, shredding and compaction, super-compaction, resin dewatering, liquid drying, and now, mobile incineration. In June, 1983, Commonwealth Edison Company (CECO) of Chicago, Illinois, contracted Aerojet Energy Conversion Company (AECC) of Sacramento, California, to supply mobile VR services to the Dresden, La Salle, Quad Cities, and Zion Nuclear Stations. Per the contract, AECC is responsible for the design, fabrication, delivery, operation, and maintenance of a Mobile Volume Reduction System (MVRS) capable of processing combustible dry active waste and contaminated oil generated at these Com-Ed facilities. Initial commercial operation of the MVRS is planned for the Dresden Nuclear Power Station in May, 1985. This paper is intended to summarize some of the key elements resulting from the design, fabrication, and testing of the MVRS. In addition, it is intended to identify the tasks a potential user of the MVRS service must complete in order to receive permission from the Nuclear Regulatory Commission to operate the MVRS at their site

  17. The Staffing of Central Electricity Generating Board Nuclear Power Stations

    An account is given of the staffing requirements and organization at a CEBG nuclear power station. The training of staff and licensing requirements for reactoroperating staff are discussed. Experience gained to data of the outcome of pre-operating training and detailed planning in the operational sphere is given. (author)

  18. Ozone for purification of water in nuclear power stations

    Visibility problems are uncommon in BWR reactors of the German type but they do occur occasionally. At KRB A nuclear power station, the water in the storage pond became turbid in shutdown conditions, which slowed down the work. The authors describe attempts to solve the problem. Ozone treatment was successful

  19. Experience in increasing power at Grohnde nuclear power station

    Steps to improve performance were taken at Grohnde nuclear power station in the years 1986-1990. These are described, together with details of operation since. Also covered are the main factors in calculating plant data as part of monitoring performance. 4 tabs

  20. Safety of CANDU nuclear power stations

    A nuclear plant contains a large amount of radioactive material which could be a potential threat to public health. The plant is therefore designed, built and operated so that the risk to the public is low. Careful design of the normal reactor systems is the first line of defense. These systems are highly resistant to an accident happening in the first place, and can also be effective in stopping it if it does happen. Independent and redundant safety sytems minimize the effects of an accident, or stop it completely. They include shutdown systems, emergency core cooling systems, and containment systems. Massive impairment of any one safety system together with an accident can be tolerated. This 'defence in depth' approach recognizes that men and machines are imperfect and that the unexpected happens. The nuclear power plant need not be perfect to be safe. To allow meaningful judgements we must know how safe the plant is. The Atomic Energy Control Board guidelines give one such measure, but they may overestimate the true risk. We interpret these guidelines as an upper limit to the total risk, and trace their evolution. (author)

  1. Feasibility study on floating nuclear power station

    It is stipulated that nuclear power plants are to be built on solid rock bases on land in Japan. However, there are a limited number of appropriate siting grounds. The Central Research Institute of Electric Power Industry has engaged since 1981 in the studies on the construction technology of power plants, aiming at establishing new siting technology to expand the possible siting areas for nuclear power plants. Underground siting is regarded as a proven technology due to the experience in underground hydroelectric power plants. The technology of siting on quaternary ground is now at the stage of verification. In this report, the outline of floating type offshore/inshore siting technology is introduced, which is considered to be feasible in view of the technical and economical aspects. Three fixed structure types were selected, of which the foundations are fixed to seabed, plant superstructures are above sea surface, and which are floating type. Aiming at ensuring the aseismatic stability of the plant foundations, the construction technology is studied, and the structural concept omitting buoyancy is possible. The most practical water depth is not more than 20 m. The overall plant design, earthquake isolation effect and breakwater are described. (Kako, I.)

  2. 75 FR 14209 - Entergy Nuclear Operations, Inc.; Vermont Yankee Nuclear Power Station; Exemption


    ... environment (75 FR 12311; dated March 15, 2010). This exemption is effective upon issuance. Dated at Rockville... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Entergy Nuclear Operations, Inc.; Vermont Yankee Nuclear Power Station; Exemption 1.0...

  3. 75 FR 14208 - Entergy Nuclear Operations, Inc.; Pilgrim Nuclear Power Station; Exemption


    ... on the quality of the human environment (75 FR 11205; dated March 10, 2010). This exemption is... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Entergy Nuclear Operations, Inc.; Pilgrim Nuclear Power Station; Exemption 1.0 Background...

  4. 75 FR 16523 - FirstEnergy Nuclear Operating Company; Davis-Besse Nuclear Power Station; Exemption


    ... FR 14635). This exemption is effective upon issuance. Dated at Rockville, Maryland, this 26th day of... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION FirstEnergy Nuclear Operating Company; Davis-Besse Nuclear Power Station; Exemption 1.0...

  5. 75 FR 80549 - FirstEnergy Nuclear Operating Company, Davis-Besse Nuclear Power Station; Exemption


    ... exemption will not have a significant effect on the quality of the human environment (75 FR 76498). This... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION FirstEnergy Nuclear Operating Company, Davis-Besse Nuclear Power Station; Exemption 1.0...

  6. U. S. Central Station Nuclear Power Plants: operating history


    The information assembled in this booklet highlights the operating history of U. S. Central Station nuclear power plants through December 31, 1976. The information presented is based on data furnished by the operating electric utilities. The information is presented in the form of statistical tables and computer printouts of major shutdown periods for each nuclear unit. The capacity factor data for each unit is presented both on the basis of its net design electrical rating and its net maximum dependable capacity, as reported by the operating utility to the Nuclear Regulatory Commission.

  7. U.S. Central Station Nuclear Power Plants: operating history

    The information assembled in this booklet highlights the operating history of U. S. Central Station nuclear power plants through December 31, 1976. The information presented is based on data furnished by the operating electric utilities. The information is presented in the form of statistical tables and computer printouts of major shutdown periods for each nuclear unit. The capacity factor data for each unit is presented both on the basis of its net design electrical rating and its net maximum dependable capacity, as reported by the operating utility to the Nuclear Regulatory Commission

  8. Station blackout core damage frequency in an advanced nuclear reactor

    Even though nuclear reactors are provided with protection systems so that they can be automatically shut down in the event of a station blackout, the consequences of this event can be severe. This is because many safety systems that are needed for removing residual heat from the core and for maintaining containment integrity, in the majority of the nuclear power plants, are AC dependent. In order to minimize core damage frequency, advanced reactor concepts are being developed with safety systems that use natural forces. This work shows an improvement in the safety of a small nuclear power reactor provided by a passive core residual heat removal system. Station blackout core melt frequencies, with and without this system, are both calculated. The results are also compared with available data in the literature. (author)

  9. Report on the accident at the Chernobyl Nuclear Power Station

    This report presents the compilation of information obtained by various organizations regarding the accident (and the consequences of the accident) that occurred at Unit 4 of the nuclear power station at Chernobyl in the USSR on April 26, 1986. The various authors are identified in a footnote to each chapter. An overview of the report is provided. Very briefly the other chapters cover: the design of the Chernobyl nuclear station Unit 4; safety analyses for Unit 4; the accident scenario; the role of the operator; an assessment of the radioactive release, dispersion, and transport; the activities associated with emergency actions; and information on the health and environmental consequences from the accident. These subjects cover the major aspects of the accident that have the potential to present new information and lessons for the nuclear industry in general

  10. The infant caring process among Cherokee mothers.

    Nichols, Lee Anne


    The purpose of this study was to identify the social process of infant care among Cherokee mothers. Nineteen informants, who had an infant less than 2 years of age, were interviewed. The data were analyzed using the technique of constant comparative analysis. A social process of Indian infant care among Cherokee mothers was identified. Eight concepts emerged from data analysis. The first and principal concept, being a Cherokee mother, describes the functions of being an Indian mother in Cherokee society. The other seven concepts describe the patterns of cultural care the mothers provided to their infants. These included accommodating everyday infant care, accommodating health perspectives, building a care-providing consortium, living spiritually, merging the infant into Indian culture, using noncoercive discipline techniques, and vigilantly watching for the natural unfolding of the infant. Trustworthiness and credibility of the generated theory were evaluated through multiple measures. PMID:15296577

  11. 2008 South Carolina Lidar: Cherokee County

    National Oceanic and Atmospheric Administration, Department of Commerce — The project area is composed of 16 counties in the State of South Carolina - Cherokee, Union, Laurens, Greenwood, Newberry, Chester, Fairfield, Lancaster,...

  12. Large containment vessel for nuclear power station

    Reactor containment vessels are installed for preventing scattering radioactive substances at the time of breaking of nuclear equipments, and they have grown large with the increase of reactor power output. As for the types of containment vessels, self-supporting type, concrete liner type, and hybrid type are named, and there are cylindrical, conical, spherical, and electric bulb forms. Reactor pressure vessels and important equipments and pipings are contained in containment vessels, and the measures for safety and in-service inspection are the factors enlarging the containment vessels. The present tendency is to enlarge containment vessels so as to obtain large free space for taking sufficient safety measures and carrying out in-service inspection. The steels for contruction self-supporting containment vessels must be tough enough at low temperature, have good weldability, not require stress relief annealing in field welding, and have stable quality. In case of using SPV-50, the plate thickness required is smaller than 38 mm, the limit that annealing is not required, even when the internal pressure and earthquake load are taken into account. Spherical containment vessels used for small output so far became to be used also for large power output because the plate thickness required is relatively small, sufficient working space can be obtained, and the manufacture is easy. (Kako, I.)

  13. Transwaal - economic district heat from the Beznau nuclear power station

    Initial study phases of the Transwaal project for distribution of heat from the Beznau nuclear power station via pipe lines to Aare and Limmat valley regions in Switzerland are presented. 500 MW heat availability through heat exchangers providing forward flow water temperature of 1200C, pipe line network and pumping station aspects, and the system energy flow diagram, are described. Considerations based on specific energy requirements in the year 2000 including alternative schemes showed economic viability. Investment and consumer costs and savings compared with oil and gas heating are discussed. Heat supply is guaranteed well into the 21st century and avoids environmental disadvantages. (H.V.H.)

  14. Computer based training simulator for Hunterston Nuclear Power Station

    For reasons which are stated, the Hunterston-B nuclear power station automatic control system includes a manual over-ride facility. It is therefore essential for the station engineers to be trained to recognise and control all feasible modes of plant and logic malfunction. A training simulator has been built which consists of a replica of the shutdown monitoring panel in the Central Control Room and is controlled by a mini-computer. This paper highlights the computer aspects of the simulator and relevant derived experience, under the following headings: engineering background; shutdown sequence equipment; simulator equipment; features; software; testing; maintenance. (U.K.)

  15. The practical implementation of the nuclear safety culture drive at Koeberg nuclear power station

    This paper details some of the actions which were taken to introduce the recommendations of the INSAG 4 'Safety Culture' document at a nuclear power station. The station has experienced a much improved performance turnaround during the period of implementation, and although one cannot say that this is as a result of these interventions - maybe it is. (author) figs

  16. The Technical Training Programme for Nuclear Power Station Personnel

    Canada's Nuclear Power Demonstration station (NPD), initiated by the federal agency Atomic Energy of Canada Limited, is operated and staffed by the Hydro-Electric Power Commission of Ontario, a provincial public utility. Obtaining and training staff for the station was hampered by the fact that until recently most of Ontario's electricity requirements were supplied by the abundant hydro-electric resources of the province. Increasing use of thermal-electric energy since 1950 created an extreme shortage of staff experienced in the operation of thermal stations. To meet this situation, trained manpower for nuclear generating stations was developed by the following steps: (1) An initial group of professional engineers was selected from among persons with considerable experience in nuclear work, thermal stations and electrical operation; (2) Another group of highly experienced operators and maintainers was selected; (3) The selected groups were given a rigorous training programme involving operation of both nuclear and coal-fired stations, instruction from the designers of NPD and training in the classroom and on the job; and (4) A nuclear training centre was established to select and train additional staff, conduct formal examinations and be generally responsible for personnel quality standards. Independent examinations of personnel were conducted by the Atomic Energy Control Board, a separate federal regulatory agency. Five general categories of personnel are being developed: (1) Supervisors: professional engineers responsible for operation, maintenance and administrative supervision, rotated periodically to increase their versatility; (2) Operators: four levels of qualification depending on the requirements of the job; (3) Control maintainers: four levels of qualification, responsible for maintenance of all instruments, control equipment and electrical equipment; (4) Mechanical maintainers: various levels and combinations of skills (welding, machining, fitting, etc

  17. Peculiar Features of Nuclear Power and Steam and Gas Plant of Thermal Power Station

    I. A. Bokoun


    The paper reveals peculiar features concerning of power generation at a nuclear power station and a steam and gas plant of a thermal power station. According to technical and economical indices a nuclear power station is at a disadvantage in relation to a steam and gas plant of a thermal power station.

  18. Organization of radiation protection in German nuclear power stations

    Using the operating handbooks of the nuclear power stations in West Germany, an examination was carried out of how far the existing organisational structure for radiation protection fulfils the requirements for protection and whether a standardisation of the organisation would provide improvements for the protection of the personnel and for the practicability of the radiation protection organisation. In particular, the parts 'Personnel operating organisation', 'Radiation protection order' and 'Maintenance order' of the operating handbook were evaluated and an audit was made of the radiation protection organisation. In general, the result of the assessment is that the organisation of radiation protection does not contradict the orders, guidelines and regulations in any of the nuclear power stations examined. Corresponding to the possibilities of regulating details of the radiation protection organisation within the undertaking, the target of 'protection of the personnel against radioactive irradiation' is achieved by the various organisation structures which are largely equal to the given example. (orig./HP)

  19. Port construction works in the Sendai Nuclear Power Station

    Sendai Nuclear Power Station is the second nuclear power station of Kyushu Electric Power Co., Inc., with two PWR plants of 890 MW each, and the operation of No.1 plant will be started in July, 1984, and that of No.2 plant in March, 1986. The civil engineering works for both plants were started in June, 1978, and March, 1981, respectively, and the rate of progress as of the end of September, 1982, was 97 % and 66 %, respectively. In the construction of this power station, the port facility was provided for the transport of construction materials and spent fuel, and for the intake of condenser cooling water. In order to make the construction by dry work, the double cofferdam structures with steel sheet piles were made offshore. The use of the wharf was started in March, 1980, though typhoons hit the area several times, and the dredging in the port was completed in May, 1982. The outline of the plan of this power station, the state of affairs before the start of construction, the outline of the port construction works, the topography, geological features and sea conditions, the design of the port such as breakwaters, unloading wharf and water intake, the manufacture and installation of caissons, dredging, and the temporary cofferdam works for water intake are described. (author)

  20. 76 FR 82201 - General Site Suitability Criteria for Nuclear Power Stations


    ... regulatory guide DG-4021, ``General Site Suitability Criteria for Nuclear Power Stations.'' This guide... for nuclear power stations. DATES: Submit comments by February 25, 2012. Comments received after this... Site Suitability Criteria for Nuclear Power Stations,'' is temporarily identified by its task...

  1. Emergency evacuation around nuclear power stations :a systems approach

    Kari, Uday Shankar


    Prior to this work, MASSVAC (MASS eVACuation) had evolved as a micro-computer simulation model for analysis and evaluation of areas facing natural disasters (hurricanes and floods). Conceptual and technical enhancements have been made to procedures within MASSVAC to deal with the special problems of evacuating around nuclear power stations. Its incorporation into TEDSS-3 (Transportation-Evacuation Decision Support System) has resulted in a powerful tool to assist development...

  2. Distributed systems for the protection of nuclear stations

    The advantages of distributed control systems usually mentioned are improved exploitation, cost reduction, and adaptation to changes in technology. These advantages are obviously very interesting for nuclear power plant applications, and many such systems have been proposed. This note comments on the application of the distributed system concept to protection systems - what should be distributed - and closes with a brief description of a protection system based on microprocessors for pressurized water stations being built in France. (auth)

  3. Special address: Fukushima Dai-Ichi Nuclear Power Station update

    This paper discusses the Fukushima Dai-ichi Nuclear Power Station event and progression. It discusses the recovery road map and the IAEA fact finding mission which provides important preliminary results. It concludes that the response of the expert and dedicated staff in extreme conditions resulted in the best possible response given the exceptional circumstances. The Japanese government's response to protect the public including evacuation has been impressive and well organized. The hazards for several sites has been underestimated.

  4. Nuclear power stations: uneasiness about them and democracy

    A report following a press conference at which the author, in discussing the state of the Graben 1140 MW BWR station project, also made some general observations about nuclear energy problems in Switzerland. Matters raised in the paper include legal requirements, safety and health, waste disposal problems, transportation of fuel for reprocessing and finance. The paper is intended to allay public anxiety. (S.W.)

  5. Online control loop tuning in Pickering Nuclear Generating Stations

    Most analog controllers in the Pickering B Nuclear Generating Stations adopted PID control scheme. In replacing the analog controllers with digital controllers, the PID control strategies, including the original tuning parameters were retained. The replacement strategy resulted in minimum effort on control loop tuning. In a few cases, however, it was found during commissioning that control loop tuning was required as a result of poor control loop performance, typically due to slow response and controlled process oscillation. Several factors are accounted for the necessities of control loop re-tuning. Our experience in commissioning the digital controllers showed that online control tuning posted some challenges in nuclear power plant. (author)

  6. Benefits from self-assessments in nuclear stations

    Effective self-assessment is an essential characteristic of any top-performing organization. It is vital to the success of a commercial nuclear facility. It must be challenging. When done well, it clearly contributes to continuous improvement. A focus on self-assessments in nuclear stations helps define the terminology. An assessment done by an external organization usually fails to provide the added benefits and learning that result from actually performing the self-assessment, from actually experiencing the challenges of a critical self-examination

  7. Joint nuclear/pumped hydro station: ultimate energy center

    Commercial startup of initial hydro units at the Joint Nuclear /Pumped Hydro Energy Center, Fairfield/Summer, represents another positive step by the utility industry toward electric power generation that is both environmentally and fiscally acceptable. Nuclear base load and pumped hydro cycling power are unique in their application to system loads and complement each other very well. South Carolina Electric and Gas Co. expects to utilize off-peak nuclear power for pumping at the Fairfield pumped hydro station much of the time. Other base load plants in the system will also provide off-peak pumping power. Thus, Fairfield is basically an extensiion of the Summer nuclear plant, allowing it to operate more effectively as a base load plant while Fairfield, using primarily the off-peak nuclear energy, operates on peak. Bringing these two stations together into one energy center permits this complementary exchange of energy and joint utilization of water to be accomplished with significant financial savaings and a minimum of environmental impact

  8. CAE - nuclear engineering analysis on work-station computers

    Emergence of the inexpensive and widely available 32-bit-work-station computer is revolutionizing the scientific and engineering computing environment. These systems reach or exceed threshold for many midscale nuclear applications and bridge the gap between the era of expensive computing: cheap people and the era of cheap computing: expensive people. Experience at the Idaho National Engineering Laboratory (INEL) has demonstrated the efficacy of this new computer technology. For the past 1 1/2 yr, a Hewlett-Packard 9000/540 32-bit multi-user microcomputer has been used to perform many calculations typical of a nuclear design effort. This system is similar with respect to performance and memory to such work stations as the SUN-3, HP-9000/32, or the Apollo DN-3000 that are available for under $20,000 for a fully configured single-user station. The system is being used for code development, model setup and checkout, and a full range of nuclear applications. Various one- and two-dimensional discrete ordinates transport codes are used on a routine basis. These include the well-known ANISN code as well as locally developed transport models. Typical one-dimensional multigroup calculations can be executed in clock times <10 min

  9. Nuclear power program and performance of existing nuclear stations in India

    India is a developing country that is very anxious to achieve self-reliance in all facets of nuclear power generation. Its nuclear power program, conceived in 1954, was a three-stage long-term plant that included eventual utilization of India's large supplies of thorium. India now has the satisfaction that it has developed all the infrastructures needed for setting up and operating nuclear power stations. it is now poised for rapid growth and has set a target of 10,000 MW(electric) by the turn of this century, although some problems have significantly affected the operation of the units. Performance of the Tarapur atomic power station, the Rajasthan atomic power station, and the Madras atomic power station is discussed

  10. Design Provisions for Withstanding Station Blackout at Nuclear Power Plants

    International operating experience has shown that the loss of off-site power supply concurrent with a turbine trip and unavailability of the standby alternating current power system is a credible event. Lessons learned from the past and recent station blackout events, as well as the analysis of the safety margins performed as part of the ‘stress tests’ conducted on European nuclear power plants in response to the Fukushima Daiichi accident, have identified the station blackout event as a limiting case for most nuclear power plants. The magnitude 9.0 earthquake and consequential tsunami which occurred in Fukushima, Japan, in March 2011, led to a common cause failure of on-site alternating current electrical power supply systems at the Fukushima Daiichi nuclear power plant as well as the off-site power grid. In addition, the resultant flooding caused the loss of direct current power supply, which further exacerbated an already critical situation at the plant. The loss of electrical power resulted in the meltdown of the core in three reactors on the site and severely restricted heat removal from the spent fuel pools for an extended period of time. The plant was left without essential instrumentation and controls, and this made accident management very challenging for the plant operators. The operators attempted to bring and maintain the reactors in a safe state without information on the vital plant parameters until the power supply was eventually restored after several days. Although the Fukushima Daiichi accident progressed well beyond the expected consequences of a station blackout, which is the complete loss of all alternating current power supplies, many of the lessons learned from the accident are valid. A failure of the plant power supply system such as the one that occurred at Fukushima Daiichi represents a design extension condition that requires management with predesigned contingency planning and operator training. The extended loss of all power at a

  11. 75 FR 76483 - Land Acquisitions; Cherokee Nation of Oklahoma


    ... Bureau of Indian Affairs Land Acquisitions; Cherokee Nation of Oklahoma AGENCY: Bureau of Indian Affairs... Cherokee Nation of Oklahoma on November 10, 2010. FOR FURTHER INFORMATION CONTACT: Paula L. Hart, Director... approximately 16.61 acres of land into trust for the Cherokee Nation of Oklahoma under the authority of...

  12. Daya Bay Nuclear Power Station operation and management indicators system

    Ever since the commercial operation of Daya Bay Nuclear Power Station (GNPS), dynamic objective management concept that features modern enterprises has been adopted by the station to manage all operational activities with the guidance of business plan. And some quantitative indicators have been employed in order to measure effectively the progress status of these operational activities. After several years' evolvement, a hierarchical and standard performance indicators system has been developed and is playing an active part in the plant's efforts towards top quartile of world nuclear power industry. Structured hierarchically with higher levels resolving into lower levels and lower levels committing to higher levels, the indicator system represents the corporate vision, WANO (World Association of Nuclear Operators) performance indicators, plant integrated indicators and departmental key indicators, covering such areas as safety, production, environment, human resource and cost control. The indicator system not only reflects performance-centered management concept, but also shows the controllability of the whole operational process of the station. Indicators of a certain level serve as both early warnings to superior indicators (lagging indicators in this case) and effects to inferior indicators (leading indicators in this case). The dynamic status of these indicators, numbered more than 230, will eventually be fed back to the business plan and realized through daily work of every branch, and even every member of the workforce. With the indicator system as a quantitative management tool, and an effective tracking system, GNPS has achieved great success in self-assessment, objective definition, improvement follow up, resource re-allocation, and management-staff communication. Periodic plant performance assessment is performed through spider chart and other pictorial diagrams. Indicators are displayed at the plant entrance, offices, Main Control Room and SIS network

  13. 75 FR 10833 - In the Matter of Entergy Nuclear Operations; Vermont Yankee Nuclear Power Station; Demand for...


    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION In the Matter of Entergy Nuclear Operations; Vermont Yankee Nuclear Power Station; Demand for.... The license authorizes the operation of the Vermont Yankee Nuclear Power Station (Vermont Yankee)...

  14. Automatic defect identification on PWR nuclear power station fuel pellets

    This article presents a new automatic identification technique of structural failures in nuclear green fuel pellet. This technique was developed to identify failures occurred during the fabrication process. It is based on a smart image analysis technique for automatic identification of the failures on uranium oxide pellets used as fuel in PWR nuclear power stations. In order to achieve this goal, an artificial neural network (ANN) has been trained and validated from image histograms of pellets containing examples not only from normal pellets (flawless), but from defective pellets as well (with the main flaws normally found during the manufacturing process). Based on this technique, a new automatic identification system of flaws on nuclear fuel element pellets, composed by the association of image pre-processing and intelligent, will be developed and implemented on the Brazilian nuclear fuel production industry. Based on the theoretical performance of the technology proposed and presented in this article, it is believed that this new system, NuFAS (Nuclear Fuel Pellets Failures Automatic Identification Neural System) will be able to identify structural failures in nuclear fuel pellets with virtually zero error margins. After implemented, the NuFAS will add value to control quality process of the national production of the nuclear fuel.

  15. Expansion potential for existing nuclear power station sites

    This report is a preliminary analysis of the expansion potential of the existing nuclear power sites, in particular their potential for development into nuclear energy centers (NECs) of 10 (GW(e) or greater. The analysis is based primarily on matching the most important physical characteristics of a site against the dominating site criteria. Sites reviewed consist mainly of those in the 1974 through 1976 ERDA Nuclear Power Stations listings without regard to the present status of reactor construction plans. Also a small number of potential NEC sites that are not associated with existing power stations were reviewed. Each site was categorized in terms of its potential as: a dispersed site of 5 GW(e) or less; a mini-NEC of 5 to 10 GW(e); NECs of 10 to 20 GW(e); and large NECs of more than 20 GW(e). The sites were categorized on their ultimate potential without regard to political considerations that might restrain their development. The analysis indicates that nearly 40 percent of existing sites have potential for expansion to nuclear energy centers

  16. Biblis A nuclear power station: commissioning and first operating experience

    The Biblis A Nuclear Power Station, one of the world's largest nuclear power plants, has fulfilled all expectations in its commissioning phase and the subsequent power operation extending over more then eighteen months and has proved that it is possible to operate generating units of this size perfectly safely. The nuclear power station, which is equipped with a pressurized water reactor and a single shaft turbogenerator set and has an electric power of 1,200 MW, had been started up in the summer of 1974, after a construction period of four years, and accepted by RWE on schedule in February 1975. The outages which have occurred since the acceptance date, which are covered in more detail in this report, were caused primarily by the conventional part of the plant. Cases of this type include defects and maloperation of the mechanical cooling water clean-up system, the instrument transformers of the generator, the high pressure casing of the turbine, and the secondary feed water tank. In the nuclear part of the plant the outages were due mainly to defects of the hydrodynamic shaft seals of the main coolant pumps. All defects were safely controlled by the control and regulating systems of the plant. The behavior of the fuel elements has been normal so far. The radioactivity levels released into the environment were far below the limits prescribed by the licensing authorities. (orig.)

  17. Heat from nuclear power stations of Nordwestdeutsche Kraftwerke AG (NWK)

    Because of dramatically increased prices, especially for conventional fuels, the feasibility of supplying heat from condensation power plants, constructed solely for generating electric power, has been examined at NWK. In this report, a brief outline is given of the nuclear power stations with which NWK is involved, the main focal point being the heat output derivation from the nuclear power station at Stade. From the end of 1983, 60 tonnes of steam per hour, at a pressure of 8 bar and a temperature of 270 deg. C, will be supplied mainly for the production and heating requirements of an industrial firm which boils salt. Background factors which have led to the realization of this project, as well as the technology and its economy, are discussed. The secondary circulatory system of the nuclear power station and the 'external steam system' are separated from one another by surface heat exchangers. The steam converter required for generating external steam is heated by steam derived from tap A6 of the turbine. When the power station is operated at partial load, the heating steam pressure can be boosted by a reduction of live steam. The external steam is then conveyed to the saline via an approximately 1.5 km conduit pipe, and about 95% of it returns in the form of the condensation product. By releasing the steam, the electric capacity of the power station, available for generating electricity, is reduced by about 10 MW. The external steam-generating plant will be installed in an annex to the engine room. Taking into account the additional investments of almost DM 20 million, as well as the costs of providing a substitute for the shortfall of electric energy actually produced by the power station, even today steam can be supplied more cheaply than by the conventional process of using heavy fuel oil. In addition, the price of steam will change solely according to cost factors related to electricity generation, i.e. it will not be dependent on developments in the sphere

  18. 78 FR 71675 - License Amendment Application for Vermont Yankee Nuclear Power Station


    ... COMMISSION License Amendment Application for Vermont Yankee Nuclear Power Station AGENCY: Nuclear Regulatory... Operating License No. DPR-28 for the Vermont Yankee Nuclear Power Station, located in Windham County, VT... proposed amendment to Facility Operating License No. DPR-28 for the Vermont Yankee Nuclear Power...

  19. Tone and prosodic organization in Cherokee nouns

    Johnson, Keith; Haag, Marcia


    Preliminary observations in the speech of one speaker of Cherokee led us to postulate three factors affecting tone in Cherokee. (1) Tone may be lexically specified with distinctive low, low fall, low rise, and high tones. (2) There is a metrically determined high fall pattern which may be distributed over not more than 2 syllables from the right edge of a prosodic domain. (3) Intonational domains may be associated with discourse functions, marked by high fall, or by pitch range upstep. This paper tests these observations in recordings of word lists and sentences produced by five additional speakers. The analysis we give, positing both lexical tone and metrical prosodic accent, is not unique in descriptions of language, but is different from the usual description of Cherokee. [Work supported by NSF.

  20. Report on the accident at the Chernobyl Nuclear Power Station

    This report presents the compilation of information obtained by various organizations regarding the accident (and the consequences of the accident) that occurred at Unit 4 of the nuclear power station at Chernobyl in the USSR on April 26, 1986. Each organization has independently accepted responsibility for one or more chapters. The specific responsibility of each organization is indicated. The various authors are identified in a footnote to each chapter. Very briefly the other chapters cover: the design of the Chernobyl nuclear station Unit 4; safety analyses for Unit 4; the accident scenario; the role of the operator; an assessment of the radioactive release, dispersion, and transport; the activities associated with emergency actions; and information on the health and environmental consequences from the accident. These subjects cover the major aspects of the accident that have the potential to present new information and lessons for the nuclear industry in general. The task of evaluating the information obtained in these various areas and the assessment of the potential implications has been left to each organization to pursue according to the relevance of the subject to their organization. Those findings will be issued separately by the cognizant organizations. The basic purpose of this report is to provide the information upon which such assessments can be made

  1. Turbo-generator sets in conventional and nuclear power stations

    The development of unit power in conventional and nuclear power stations in Germany and the USA - the development of design criteria for conventional and reheat turbines - a survey of constructional types and problems of conventional reheat turbines by the example of turbine types for 150, 300, 600 and 1,200 MW - saturated steam turbines for boiling-water and pressurized-water reactors - maintenance, automatics, and turbine protection systems - reliability and availability - common turbine defects: outlook on limiting outputs of turbines and generators with different cooling systems and low-pressure parts. (orig./AK)

  2. Technical specifications for cold shutdown (Barsebaeck nuclear power station)

    From a reactor safety point of view, it is clear that the conditions at power operation and at cold shutdown are quite different. Because of this a special set of regulations, i.e. Technical Specifications for Cold Shutdown (TSCS), has been prepared for the Barseback nuclear power station. This paper gives a short description of these TSCS. Background, general principles, history, preparation, structure and experiences of TSCS are discussed. In order to provide some deeper information about some part of TSCS, a specific example has been chosen, namely the TSCS concerning the residual heat removal systems

  3. Automatic plant start-up system for nuclear power station

    An automatic plant start-up system using a process computer has been applied to the unit No. 1 of Onagawa Nuclear Power Station, Tohoku Electric Power Co., Inc. This is the world's first commercial-base system for LWRs. Turbine start-up and power control by reactor recirculation flow are automated to reduce operator's labor and to improve the efficiency and accuracy of plant operation. The test data and the results of practical operation have proved the performance of the system is satisfactory. Major functions, configuration, and the results of performance tests at factory and at site are represented here. (author)

  4. Human-factor operating concept for Borssele Nuclear Power Station

    The safety level in the operation of a reactor is determined basically by human beings. The Borssele Nuclear Power Station has carried out measures for improving the man-machine interface through training and operating instructions for the shift personnel. The retrofitting of control technology relevant to safety engineering should avoid operating instructions which can cause potential failures. A safety study has shown that the remaining risk following all retrofitting measures remains dependent to the extent of 80% on human factors and that human factors as a whole have a positive effect on reactor safety. (orig.)

  5. Devices (manipulators) particularly for ultrasonic tests in nuclear power stations

    The manipulator devices for internal and external tests described in this article, were used successfully in the basic and repeat tests for nearly all West German, Swiss and Austrian nuclear power stations. For older reactors or for reactors originating from abroad one did not take sufficient account of the required accessibility to the test location in the configuration of the reactor pressure vessel, which led to complicated special manipulation devices. The handling of which at site requires a great deal of time. The more modern types of reactors are laid out so as to be easier to test and make a better manipulation test system and better test results possible. (orig./RW)

  6. Representations and types of organizational errors in nuclear power station

    The aim of this study is to explore the organizational errors that affect the safety of the nuclear power station,with the methods of interview and events re-analysis. Coding method has been used to change the qualitative data to quantitative data. After cluster analysis, five organizational factors in nuclear power field have been obtained, including technical management factors, non-technical management factors, information interface, organizational planning, and lack of holistic thinking. The study also finds that compared to the technical management factors, non-technical management factors have greater affects on the safety of the system. So the non-technical training is essential to insure the safety of the system

  7. The Gundremmingen B and C nuclear power station

    The Gundremmingen II Nuclear Power Station, KRB II, was built at Gundremmingen on the river Danube by the KWU/Hochtief consortium with KWU as the reactor manufacturer, for the Rheinisch-Westfaelisches Elektrizitaetswerk AG and Bayernwerk AG utilities. Each of the two units has been equipped with a boiling water reactor of the KWU 72 line of 1310 MWe gross power each. Construction of the main buildings of units B and C was started simultaneously on July 20, 1976 after the first partial construction, including the speedy commissioning phase unit B was delivered to the operator on July 19, 1984. Unit C will be able to complete the nuclear commissioning phase probably by early 1985 and then start power operation. The raise in quality standards led to considerable delays in the preliminary testing and fabrication of components and installations. Those delays were counteracted by the advantages inherent in the dual-unit principle, which helped to save time. (orig./GL)

  8. The role of the State Nuclear Safety Authority during nuclear power station construction and operation in Czechoslovakia

    The author describes the main elements of the State Nuclear Safety Authority's work and discusses its role in legislation as well as its working methods. Information is provided on the practical experience of the Authority with nuclear power station site selection in Czechoslovakia, and the quality control measures applied to the power-producing components of nuclear power stations are elucidated. (author)

  9. 78 FR 66965 - In the Matter of Exelon Generation Company, LLC; Dresden Nuclear Power Station Confirmatory Order...


    ... of Exelon Generation Company, LLC; Dresden Nuclear Power Station Confirmatory Order Modifying License... operation of the Dresden Nuclear Power Station (Dresden Station) in accordance with conditions specified... taken at Dresden Nuclear Power Station and other nuclear plants in Exelon's fleet and that License...

  10. Radioactive graphite management at UK Magnox nuclear power stations

    The UK nuclear power industry is predominantly based on gas-cooled, graphite moderated reactors with their being 20 operating and 6 shutdown Magnox reactors. The radioactive graphite issues associated with the Magnox reactors relate mainly to the reactor core graphite but, at two of the stations, there is also another graphite waste stream which results from the handling of their particular design of fuel elements which incorporate graphite fittings. The decommissioning plan for the Magnox reactors is to apply the Safestore strategy in which the defuelled reactors will be maintained in a quiescent state, e.g. to gain benefit from radioactive decay, with their dismantling being deferred for a period of time. In preparing for and developing the decommissioning strategy detailed studies have been undertaken on all relevant aspects. These have resulted in, for example, extensive information on the graphite radioactive inventories, the condition of the graphite throughout the quiescent deferral period, safety assessment, and, dismantling, waste management and disposal plans. Significant work has also been undertaken on the management of the graphite fuel element debris that has accumulated at the two stations. For example, work is well advanced at one of the stations to install equipment to retrieve this waste and package it in a form suitable for eventual deep geological disposal. (author)

  11. Optimization of air ducts for nuclear reactor power generation station

    In the optimization study on the heating, ventilating and air conditions system in Nuclear Reactor Power Generation Station, proper arrangement of air ducts has been studied using the experimental and analytical investigation from a viewpoint of duct arrangement optimization. This study consists of two parts. Part I is optimization of air ducts in the corridors and Part II is optimization of air duct in each room. In part I, from viewpoints of confinement of radioactive materials in facilities having possible radioactive contamination and improvement of thermal environment for workers, the authors have studied air ducts system in which fresh air is supplied to corridors and heat removal and ventilation for each room are performed by transferring air from the corridors, instead of current ducts system with supply duct to each room. In part II, the condenser room with complex configuration and large space, and the electrical equipment room with simple space are selected for model areas. Based on these studies, experimental and analytical investigation (using a three-dimensional thermal hydraulic analysis) technique has been established, and the effective design method for duct arrangement of HVAC design has been verified for Boiling Water Reactor Power Station. The air-duct arrangements optimized in this study are applied to an Advanced Boiling Water Reactor Power Station in trial and reduction of the air-duct quantity is confirmed

  12. Cost of delays in the construction of nuclear power stations

    The serious delays in construction suffered by a number of German nuclear power stations are the consequence mainly of the sluggish way in which the licensing procedure is carried out by the public authorities and, more recently, also of administrative court actions with a suspensive effect. The delays brought about by the licensing procedure are due to many causes, among them the uncertainties associated with the decision making process because of objections, the time required for expertises on possible environmental impacts, delays with authorities and experts as a result of the demand for more and more differentiated investigations and the insufficient number of personnel available to the licensing authorities and experts, the delays in the preparation of documents by the manufacturers, and the bachfitting of recent findings to plants already in the licensing phase or licensed. While the negative effect of delays in the construction period upon the electricity supply situation gives rise to less difficulties, because of the economic recession, repercussions on cost are all the more severe. In extreme cases, the extra costs generated over a period of three years may reach the level of the cost of the nuclear power station proper. (orig.)

  13. Nuclear Stations of Low Power (SMR): Past, Present, Future

    Interest to SMR has arisen from the very beginning of atomic energy development. It is caused by independent energy resource creation for deleted and hard-to-reach areas, where the use of traditional organic sources of energy is impossible or complicated, and electric power lines are absent. Development of small nuclear energy in USA began in 50s of last century and it was subordinated to the tasks of Department of Defense. To solve these tasks 8 experimental SMR of electric power from 0,3 up to 3 ?W were manufactured and put into operation. In 60s these stations were decommissioned. Floating nuclear power plant SMR Sturgis (MN-1A) was in operation since August 1968 till July 1976 in Panama canal region (on lake Gatun). In the USSR design and calculation of SMR were made from the beginning of 50s of last century. The purpose of these researches was to reveal the most perspective SMR projects for implementation as demonstration and industrial samples. It has been worked about 20 variants of SMR with electric power of 1-1,5 ?W with various reactors (on thermal, intermediate and fast neutrons) and different types of execution (stationary, unit-transportable, mobile and floating stations). This work provides the implemented and modern, innovational projects in Russia and in the world. (author)

  14. Recent trends of hydraulic snubbers for nuclear power station

    One of the important safety measures for nuclear power stations is aseismatic measure. The vibration due to earthquakes, the pulsation of fluid, the blow-off of safety valves, the whipping of pipes due to break and so on should be taken into consideration. The recent trends of the hydraulic vibration dampers for pipings are described. The vibration dampers must not restrain the gradual move due to thermal expansion, but exert restraining force to violent move due to earthquakes and others. Fixed restrainers and spring type restrainers are simple and sure, but there is some fear of restraining thermal expansion with them. In nuclear power stations, hydraulic suppressors are mostly employed. The poppet valves in a control valve box do not close in case of the motion slower than 0.1 cm/sec, therefore resistance does not arise. In case of the motion of 0.1 - 0.4 cm/sec, the poppet valves close and stop the motion of a piston. In the motion faster than 0.4 cm/sec, the poppet valves close without fail, and the resistance of nominal capacity is produced. The hydraulic vibration dampers are prescribed in the subsection NF, Section III, ASME Boiler and Pressure Vessel Code. The problems are the radiation resistance and the degeneration due to temperature and secular change of actuating oil and seal material. The bleed rate of the hydraulic vibration dampers is important for preventing the troubles. (Kako, I.)

  15. Challenges to fire protection measures at Hamaoka Nuclear Power Station

    New regulatory standards for fire protection at nuclear power plants have been established by the Nuclear Regulation Authority. This paper introduces the measures taken by the Hamaoka Nuclear Power Station for the following four items, which were especially big changes. (1) To install a combination of sensors of different types or instruments with equivalent functions so as to be able to emit unique signals to inform a fire in the early stage. (2) To conduct 'UL vertical burn test' as the demonstration test for self-extinguishing performance as the condition for flame-retardant cable. (3) To install automatic fire-extinguishers or fixed fire-extinguishing devices of manual type at the spots where fire-fighting is difficult due to the filling of smoke in a fire or the effect of radiation. (4) To separate the system for purpose of ensuring safety function to attain the high-temperature shutdown and cold-temperature shutdown of a reactor whatever fire may happen at the nuclear facilities. The examples of the installation of fire-extinguishers as the measures for the above Item (3) are as follows; (A) as for the devices containing oil, a foam-extinguishing agent is released against each target device from the nozzle, and (B) for large vertical pump motors indoors and relatively small pump motors, IA type automatic foam extinguishing systems are installed. (A.O.)

  16. The regional income and employment impacts of nuclear power stations

    This paper attempts quantitatively to assess the income and employment impacts associated with two nuclear establishments in Scotland: the United Kingdom Atomic Energy Authority (U.K.A.E.A.) nuclear power establishment at Dounreay in Caithness and the South of Scotland Electricity Board (S.S.E.B.) nuclear power station presently under construction at Torness in the Lothian region. The model used is a basic Keynesian income multiplier model refined to allow detailed analysis of income and employment impacts at a local level. As used in this study it allows the identification of the increase in income and the associated increase in employment relating to the siting of a nuclear power plant in a particular locality. Results are given. The employment multipliers are estimated to be in the range 1.236 to 1.535 for Dounreay and 1.294 to 1.675 for the operational phase of the Torness plant. It is concluded that although the absolute income increases in the respective subregions are significant, compared to the total annual expenditure of the establishments these figures indicate high leakage from the subregions. (UK)

  17. 76 FR 39134 - ZIONSOLUTIONS, LLC; Zion Nuclear Power Station, Units 1 and 2 Exemption From Recordkeeping...


    ... COMMISSION ZIONSOLUTIONS, LLC; Zion Nuclear Power Station, Units 1 and 2 Exemption From Recordkeeping Requirements 1.0 Background Zion Nuclear Power Station (ZNPS or Zion), Unit 1, is a Westinghouse 3250 MWt... licensing basis requirements previously applicable to the nuclear power units and associated...

  18. Tone and Accent in Oklahoma Cherokee

    Uchihara, Hiroto


    This dissertation is a study of the tonal and accentual system of Oklahoma Cherokee, which has six possible pitch patterns occurring on a syllable: low, high, low-high, high-low, lowfall and superhigh. This study attempts to provide a comprehensive description and analyses of these patterns: their distribution, their source, the principles which…

  19. Fukushima Daini Nuclear Power Station Unit No. 3 nuclear reactor recirculation pump incident

    This paper describes the incident and investigation of excessive mechanical vibration of the unit 3 recirculation pump of the Fukushima Daini Nuclear Power Station. The topics include equipment damage, failure analysis, operational issues, actions to prevent reoccurrence, metallic particle contamination and cleanup and recovery of the cooling system, and future monitoring of recirculation pumps

  20. Reliability estimation for important nuclear power station safety equipment

    Complicated engineering in nuclear power leads to systems in which faults cause unpredictable consequences. To prevent hazardous situations in such systems, one uses safety systems, and when these fail, the operation presents risks. On the one hand, adding a safety system increases the complexity and does not raise the reliability but actually reduced it because of spurious failures, while on the other hand it substantially influence the safety in operating the system. This aspect of safety systems required detailed attention from designers and manufacturers. There are numerous papers on reliability in safety systems; the expected total economic losses have been calculated due to failure in protected equipment and protection systems, studies were made on how periodic monitoring of safety system correctness affects the probability that it will meet all demands during the operating time for the protected object, and in the probability of a safety system failing per demand was determined. The World Association of Nuclear Operation (WANO) recommendations are reflected in open-quotes Nuclear Power Station Parameter Programs,close quotes and to estimate safety system performance one should use the nonworking interval or nonworking time. The nonworking time in that method is in general a random quantity, so one needs methods of estimating the mean nonworking time during continuous system operation. The method described in this article enables one to calculate the mean nonworking time for important safety systems on the basis of the structure and the relationship to the protected object and enables one to determine the working-time significance characteristics for safety system components. Sample calculations are presented for estimating the reliability of an emergency cooling system in the Chernobyl Power Station

  1. 76 FR 54196 - Public Meeting, Cherokee National Forest Secure Rural Schools Resource Advisory Committee


    ... Forest Service Public Meeting, Cherokee National Forest Secure Rural Schools Resource Advisory Committee..., Forest Service, Cherokee National Forest Secure Rural Schools Resource Advisory Committee will meet as indicated below. DATES: The Cherokee National Forest Secure Rural Schools Resource Advisory...

  2. Experience gained in the operation of the Beznau nuclear power station

    The 24th December 1969, when the Beznau 1 nuclear power station was placed in commercial operation, marked the beginning of electricity production from nuclear energy in Switzerland. Beznau 2 followed on the 15th March 1972. Together with the Muehleberg nuclear power station, nuclear energy accounts for approximately 20 percent of the total electricity production in Switzerland. Until the end of 1975, Switzerland's three nuclear power stations had a mean energy utilisation factor of 71.3 percent which, as compared with a mean energy utilization factor of 60.5 percent for all the nuclear power stations in the West, suggests fairly good operational results. Problems that arose during operation are discussed in detail. By way of summary it is stated that the operation of the Beznau nuclear power station has so far proved a success. The production of electrical energy has always remained within the limits imposed by the law and by the safety aspects. (Auth.)

  3. Foreign Material Exclusion Program at CNE Cernavoda Nuclear Generating Station

    In the face of a continuing attention to operations and maintenance costs at nuclear power plants, the future of the industry depends largely upon increasing plant availability and improving operating efficiency. The success in achieving these objectives is dependent upon the success of each plant's equipment maintenance program. Preventing the introduction of foreign materials into a nuclear power plant system or component requires a careful, thoughtful, and professional approach by all site personnel. This paper describes a proactive approach to prevent the introduction of foreign material into systems and components, by providing an overview of technical considerations required to develop, implement, and manage a foreign material exclusion program at CNE Cernavoda Unit 1 and 2 Nuclear Power Station. It is also described an example of Foreign Material Intrusion which happened during the 2003 planned maintenance outage at Cernavoda Unit no.1. This paper also defines personnel responsibilities and key nomenclature and a means for evaluating prospective work tasks and activities against standardized criteria, in order to identify the appropriate level of the required FME controls. (author)

  4. Upgrading of HP turbines for nuclear power stations

    Many papers have been written on the upgrading of nuclear plant LP turbines but there are also strong reasons for the upgrading of the HP turbines. Two principal reasons are discussed in this paper. Fouling by deposition on the feedwater side of the stream generator tubes, frequently results in a reduction of pressure at the turbine stop valve and a consequent loss of power output. This loss of power can be largely offset by fitting increased capacity blading in part of the HP turbine which increases the swallowing capacity of the turbine. It is necessary to consider the increased capacity blading, bypassing of heaters and future fouling to arrive at an optimum solution. Since the design of the operating nuclear stations GEC ALSTHOM have made very significant advances in the design of steam turbine HP blading and it is now possible to upgrade the HP turbine with blades of modern design to give a substantial increase in power output. The pay back period for such a upgrade is short and the paper describes some of the Company's successful nuclear HP upgrading in the UK. The two actions described above can be combined, or indeed, be carried out in conjunction with an LP upgrade

  5. Radwaste assessment program for nuclear station modifications by design engineering

    Radwaste burial for Duke Power Company's (DPC's) seven nuclear units has become a complicated and costly process. Burial costs are based on overall volume, surcharges for radioactivity content and weight of containers, truck and cask rental, driver fees, and state fees and taxes. Frequently, radwaste costs can be as high as $500 per drum. Additionally, DPC is limited on the total burial space allocated for each plant each year. The thrust of this program is to reduce radwaste volumes needing burial at either Barnwell, South Carolina, or Richland, Washington. A limited number of options are available at our sites: (a) minimization of radwaste volume production, (b) segregation of contamination and noncontaminated trash, (c) decontamination of small hardware, (d) volume reduction of compatible trash, (e) incineration of combustible trash (available at Oconee in near future), and (f) burial of below-regulatory-concern very low level waste on site. Frequently, costs can be reduced by contracting services outside the company, i.e., supercompaction, decontamination, etc. Information about radwaste volumes, activities, and weight, however, must be provided to the nuclear production department (NPD) radwaste group early in the nuclear station modification (NSM) process to determine the most cost-effective method of processing radwaste. In addition, NSM radwaste costs are needed for the NPD NSM project budget. Due to the advanced planning scope of this budget, NSM construction costs must be estimated during the design-phase proposal

  6. Foreign Material Exclusion Program at CNE Cernavoda Nuclear Generating Station

    Urjan, Daniel [S.N. ' Nuclearelectrica' SA, CNE Cernavoda Nuclear Power Plant, Medgidiei 2 Street, 905200 Cernavoda, Constanta (Romania)


    In the face of a continuing attention to operations and maintenance costs at nuclear power plants, the future of the industry depends largely upon increasing plant availability and improving operating efficiency. The success in achieving these objectives is dependent upon the success of each plant's equipment maintenance program. Preventing the introduction of foreign materials into a nuclear power plant system or component requires a careful, thoughtful, and professional approach by all site personnel. This paper describes a proactive approach to prevent the introduction of foreign material into systems and components, by providing an overview of technical considerations required to develop, implement, and manage a foreign material exclusion program at CNE Cernavoda Unit 1 and 2 Nuclear Power Station. It is also described an example of Foreign Material Intrusion which happened during the 2003 planned maintenance outage at Cernavoda Unit no.1. This paper also defines personnel responsibilities and key nomenclature and a means for evaluating prospective work tasks and activities against standardized criteria, in order to identify the appropriate level of the required FME controls. (author)

  7. Quality control of Ling'ao nuclear power station civil construction

    Based on the quality control model adopted during Ling'ao Nuclear Power Station construction, the author briefly introduces quality control process of some main civil construction activities (reinforced concrete, steel liner, steel works and prestressing force) of nuclear power station, and makes some descriptions on non-conformance control of civil works. These quality control processes described come from the concrete practice during civil construction of Ling'ao Nuclear Power Station, and are based on Daya Bay Nuclear Power Station construction experience

  8. The effects of the nuclear disaster at Fukushima Daiichi Nuclear Power Station on local governments

    All Japan council of local governments with atomic power stations consisted of 24 reactor site and 6 neighboring local governments to solve reactor site related problems. Nuclear disaster at Fukushima Daiichi Nuclear Power Station affected member local governments to be forced in severe conditions such as 'removal of administrative function' or 'refuge over a wide district beyond local government area', not imagined before. The council set up working group for thirteen local governments themselves to investigate this disaster and find safety and prevention of disaster measures to be deployed in nuclear administration, which published report in March 2012. This article described outline of investigation and derived problems and direction of their solution. Main items were related with communication, resident evacuation, prevention of disaster system, and management of refuge site. (T. Tanaka)

  9. The nuclear accident emergency and preparation activities of Zhejiang Province emergency committee for nuclear power station accident

    The offsite accident emergency preparation for coordinating operation of Qinshan Nuclear Power Station by Zhijiang province people government since 1989 has carried out. The emergency and preparation consist of the following activities: 1. Setting up the organization; 2. Drawing the offsite emergency plan and establishing the emergency system; 3. Enforcing the nuclear accident offsite emergency exercise before operation of the nuclear power station; 4. Holding the nuclear accident emergency staff training course and conducting safety education for the public around the nuclear power station

  10. Demonstration of zinc injection technique in Fugen Nuclear Power Station

    Applicability of the zinc injection technique for reducing the equivalent dose of annual inspection workers has been cleared and confirmed by several out-of-pile tests at Fugen Nuclear Power Station. A trial, which aimed at compressing the dose rate increase, was developed by BWR and was carried out in several plants from 1986. And then, regular zinc injections were started from Aug. 1999 after the start up of the 15th annual inspection. As a result of this injection, the 60Co ion concentration in reactor has been reduced by the order of about 30%, and a radioactivity reduction effect has also been confirmed. Also, the rebuild up rate of 60Co on piping surfaces has been drastically reduced from about 60% to about 12% after system decontamination. According to an analysis of the practical method, the adhesive rate coefficient of 60Co to metal oxide film is compressed to about 1/3. (author)

  11. Medical Actions in Emergencies at Nuclear Power Stations

    Casualties which could occur as a result of accidents at nuclear power stations can be categorized as follows. Those due to: (a) Over-exposure to external radiation; or (b) Excessive contamination of body surfaces with radioactive materials with, possibly, absorption of toxic quantities of these materials; (c) Combinations of (a) and (b) complicated by conventional injuries. This paper discusses the arrangements made within the Central Electricity Generating Board for dealing with casualties, taking account of the limited medical and nursing facilities. These arrangements can be summarized as follows: (a) Immediate actions on site, including first aid and rescue; (b) Plans have been agreed with the medical staff of appropriate hospitals for dealing with eventualities of this nature; (c) Adequate training programs have been instituted to include nursing and first-aid teams; (d) Rehabilitation and reemployment of injured personnel. Details of dosimetry both physical and biological which would be used to assess the extent of radioactive exposure are described. (author)

  12. Aging assessment of electrical cables from NPD nuclear generating station

    Degradation of NPD Nuclear Generating Station control and power cables after approximately 25 years of service was assessed. The PVC and SBR insulated cables were also exposed to radiation, accident and post-accident conditions, and accelerated aging to simulate extended service life. The degradation of the samples from the containment boiler room was minimal, caused mainly by thermal conditions rather than radiation. Although irradiation to 55 Mrad, simulating normal operation and accident radiation levels, caused degradation, the cables could still function during accident and post-accident conditions. Accelerated thermal aging to simulate an additional 10 years of service at 45 degrees C caused embrittlement of the PVC and a 60% decrease in elongation of the SBR. Comparison of test results of aged NPD cables with newer PVC cables obtained from Pickering NGS 'A' shows that the newer cables have improved aging stability and therefore should provide adequate service during their design life of 31 years

  13. Moderator inlet line hanger replacement for Pickering nuclear power station

    Ontario Hydro's Pickering Nuclear Generating Station (PNGS), Units 1 and 2 were shutdown for large scale fuel channel replacement. Other nonroutine inspection and maintenance activities were performed to determine the overall condition of the units and it was seen that a moderator inlet line hanger (identified as HR-29) had failed in both units. Subsequent inspections during planned maintenance outages of Pickering NGS Units 3 and 4 revealed that hanger HR-29 had failed and required replacement. A research program was conducted to find a suitable technique. These problems included accessing tooling through small inspection ports, manipulating tooling from a significant distance and the high radiation fields within the vault. This paper describes the program undertaken to replace hanger HR-29. (author)

  14. Nuclear instrument upgrade at Connecticut Yankee Atomic Power Station

    After 20 years of commercial operation, the Connecticut Yankee Atomic Power Station decided to replace the original nuclear instrument system. The plant was motivated primarily by reliability and maintainability problems, the former attributed to equipment wearout and discrete component failure, and the latter to the unavailability of qualified spare parts, another effect of the equipment's age. In replacing the system, the plant also had to address current regulatory, design, and plant technical specification requirements, including physical separation, signal isolation, and changes in equipment qualification. This paper discusses the motivation for the system's replacement, the challenges to the plant engineers and equipment designers, the ways in which the new design met the challenges, the test results of the new system, and other potential benefits supported by the test results

  15. Probabilistic safety analysis for the Unterweser Nuclear Power Station

    In October last year, a plant-specific probabilistic safety analysis (PSA) was conducted for the Unterweser Nuclear Power Station as part of the periodic safety review (PSR). As a living PSA, the probabilistic safety analysis was based on the first analysis conducted in 1995; its scope was extended in accordance with the 1996 PSA guideline. Besides the in-plant initiating events in the power mode, which were considered already in the 1995 PSA, the current PSA included external impacts, fires in the plant, and events occurring during plant outages as well as plant-specific data. Also findings of current research were incorporated. The results obtained show the KKU plant to enjoy a high level of safety and allow the PSA to be used alongside plant operation. (orig.)

  16. Low level waste management developments in UK nuclear power stations

    This paper discusses how the UK definition of low-level waste (LLW) as agreed between the Government regulating departments and the nuclear industry differs from that in the US and elsewhere. It is that the material is not suitable for disposal as ordinary refuse and that it has a specific activity level below 12 GBq/te beta-gamma and 4 GBq/te alpha. In other words it generally covers the low activity trash produced by the industry. The LLW produced as a result of power station operations can be grouped as drummable/non-drummable, compactable/non-compactable using low force compaction technology, and as burnable/non-burnable depending on the management practices locally

  17. Performance of Durasil 70 media Salem Nuclear Generating Station

    The use of Duratek's EVR (Enhanced Volume Reduction) Demineralization System employing sluiceable pressure vessels and improved operational techniques has generated operational efficiencies including volume reduction (VR), reduced personnel labor and exposure, higher flowrates and improved decontamination factors (DF) for cleanup of liquid radwaste streams at the Salem Nuclear Generating Station. Further significant VR improvements have been achieved utilizing Duratek's Durasil D-70 process media. This proprietary media has demonstrated the ability to process the high conductivity wastestreams found at the Salem facility. Earlier lab and on-site testing projections of throughputs of a magnitude 15 times higher than organic resin have been confirmed. A long-term problem, cobalt species removal in a high sodium environment, has been mitigated by this media

  18. Waste minimization successes at McGuire Nuclear Station

    McGuire Nuclear Station is a two unit, 1125 MWe PWR located 25 miles north of Charlotte, North Carolina. It is a Westinghouse Ice Condenser plant that is owned and operated by Duke Power Company. At Duke Power, open-quotes Culture Changeclose quotes is a common term that we have used to describe the incredible transformation that we are making to become a cost conscious, customer driven, highly competitive business. Nowhere has this change been more evident then in the way we process and disposed of our solid radioactive waste. With top-down management support, we have used team-based, formalized, problem solving methods and have implemented many successful waste minimization programs. Through these programs, we have dramatically increased employees close-quote awareness of the importance of waste minimization. As a result, we have been able to reduce both our burial volumes and our waste processing and disposal costs

  19. Accounting and cost control of a nuclear power station

    1) chart or classification of accounts, 2) all plant expenses, 3) cost control, 4) storage of spare parts and supplies, 5) control of applicable dose rate, 6) charges for insurance. The accuracy of accounting and cost control is a primary thing for the efficiency in a nuclear power station. The much more important factor is the availability. It is necessary to save costs by a more effective storage or a more detailed and automatic process of single jobs in the workshop. But a very definite experience made in Obrigheim is the fact that not only commercial people know which financial loss will occur if the plant is out of operation one hour. This knowledge is also important for the technical people and for the workers in the workshops. The technical responsibility and the security in operation of the plant and the commercial understanding for the risk of non-availability do not exclude each other. (HP)

  20. Reliable, fault tolerant control systems for nuclear generating stations

    Two operational features of CANDU Nuclear Power Stations provide for high plant availability. First, the plant re-fuels on-line, thereby eliminating the need for periodic and lengthy refuelling 'outages'. Second, the all plants are controlled by real-time computer systems. Later plants are also protected using real-time computer systems. In the past twenty years, the control systems now operating in 21 plants have achieved an availability of 99.8%, making significant contributions to high CANDU plant capacity factors. This paper describes some of the features that ensure the high degree of system fault tolerance and hence high plant availability. The emphasis will be placed on the fault tolerant features of the computer systems included in the latest reactor design - the CANDU 3 (450MWe). (author)

  1. Influence of radiation on maintenance in a nuclear power station

    Maintenance in nuclear power plant differs from that in fossil fuel power plant in many aspects because the maintenance in the former has to be carried out in radiation area. These aspects are : (1) manpower planning to minimise time of repair in order to reduce the radiation dose received by the maintenance crew, (2) difficulties in isolating components to be repaired from reactor which is normally filled with water, (3) shielding and decontamination to reduce radiation fields around equipment and (4) need to write the detailed procedures and use special tools, brief and train personnel before-hand on similar equipment or mock-ups. These aspects are discussed. Two of the major repair jobs carried out at the Tarapur Atomic Power Station are described in brief. The jobs were : (1) tube plugging of secondary steam generators and (2) repair to the guide brackets of dryer -separator assembly in the reactor vessel. (M.G.B.)

  2. Response robot and Fukushima Daiichi Nuclear Power Station

    When we remote control the robot in the Fukushima Daiichi Nuclear Power Station reactor building, in addition to the environmental conditions narrow, stairs, rubble, such as high temperature, high humidity, there is a problem which we have not experienced. One is the radiation resistance of the robotic system, and the other is a matter of remote communication. Robot must be active under a hight radiation in behalf of person, a method that can reduce the exposure a radiation is only shielding. It causes increase of the weight of the robot, shielding worsen the exercise performance of small robot. In addition, thick concrete structures to block reactor building is the failure of the radio communications. (author)

  3. Liquid radwaste process optimization at Catawba Nuclear Station

    Since commercial operation in 1985, Catawba Nuclear Station has experienced significant filtration problems with the radioactive liquid waste system. The performance of the filtration and ion exchange equipment has been significantly worse than other Duke Power stations. Full scale tests have been performed to investigate the causes and potential solutions to the waste processing difficulties. The initial waste stream characterization study revealed a large percentage of sub-micron particles. This information immediately suggested that the existing filtration equipment was not adequately sized to effectively process the waste stream. New technologies which would effectively enhance the performance of the processing system and reduce both operating and maintenance costs were researched. This included bag filters, depth filtration, custom designed ion exchange vessels and radionuclide specific ion exchange media. The subsequent full scale testing resulted in a processing scheme which resulted in extended filter life, over 100 percent increase in ion exchange bed life, 90 percent reduction in filter media costs and improved radionuclide removal. 4 refs., 4 figs., 1 tab

  4. Excavation without blasting in extension works for nuclear power station

    In Genkai Nuclear Power Station, Kyushu Electric Power Co., Inc., the excavation for foundations and cooling water tunnel of No.2 plant was carried out while No.1 plant was in operation, so that harmful effect was not exerted on No.1 plant. This paper reports on this work. The selection of excavation method according to the amount and speed of works and the class of base rocks is very difficult in such cases as mentioned above. First, the effect of blasting method with explosives was studied throughly regarding the excavation for foundations, and the effective method without blasting was adopted in order to make the effect small. The circumstances and the practical works are described. The geological features of the station site are explained. The limiting value of oscillation at which various equipments in No.1 plant cause misbehavior was determined by blasting test, and the amount of explosives which does not exert any effect on No.1 plant was found. Seven kinds of excavation method were picked up, and their effect of reducing oscillation, reliability and economy were compared. Finally, ripping method for soft and medium rocks, rock breaker method for hard rocks, and boom header method for tunnel excavation were selected. The actual results of the excavating works by these methods are reported. (Kako, I.)

  5. Evaluation of Gas Reburning & Low NOx Burners on a Wall Fired Boiler Performance and Economics Report Gas Reburning-Low NOx Burner System Cherokee Station Unit 3 Public Service Company of Colorado

    None, None


    Under the U.S. Department of Energy's Clean Coal Technology Program (Round 3), a project was completed to demonstrate control of boiler NOX emissions and to a lesser degree, due to coal replacement, SO2 emissions. The project involved combining Gas Reburning with Low NOX Burners (GR-LNB) on a coal-fired electric utility boiler to determine if high levels of NOX reduction (70%) could be achieved. Sponsors of the project included the U.S. Department of Energy, the Gas Research Institute, Public Service Company of Colorado, Colorado Interstate Gas, Electric Power Research Institute, and the Energy and Environmental Research Corporation. The GR-LNB demonstration was performed on Public Service Company of Colorado's (PSCO) Cherokee Unit #3, located in Denver, Colorado. This unit is a 172 MW~ wall-fired boiler that uses Colorado Bituminous, low-sulfur coal. It had a baseline NOX emission level of 0.73 lb/106 Btu using conventional burners. Low NOX burners are designed to yield lower NOX emissions than conventional burners. However, the NOX control achieved with this technique is limited to 30-50%. Also, with LNBs, CO emissions can increase to above acceptable standards. Gas Reburning (GR) is designed to reduce NOX in the flue gas by staged fuel combustion. This technology involves the introduction of natural gas into the hot furnace flue gas stream. When combined, GR and LNBs minimize NOX emissions and maintain acceptable levels of CO emissions. A comprehensive test program was completed, operating over a wide range of boiler conditions. Over 4,000 hours of operation were achieved, providing substantial data. Measurements were taken to quantify reductions in NOX emissions, the impact on boiler equipment and operability and factors influencing costs. The GR-LNB technology achieved good NOX emission reductions and the goals of the project were achieved. Although the performance of the low NOX burners (supplied by others) was less than expected, a NOX reduction of

  6. Design Provisions for Station Blackout at Nuclear Power Plants

    A station blackout (SBO) is generally known as 'a plant condition with complete loss of all alternating current (AC) power from off-site sources, from the main generator and from standby AC power sources important to safety to the essential and nonessential switchgear buses. Direct current (DC) power supplies and un-interruptible AC power supplies may be available as long as batteries can supply the loads. Alternate AC power supplies are available'. A draft Safety Guide DS 430 'Design of Electrical Power Systems for Nuclear Power Plants' provides recommendations regarding the implementation of Specific Safety Requirements: Design: Requirement 68 for emergency power systems. The Safety Guide outlines several design measures which are possible as a means of increasing the capability of the electrical power systems to cope with a station blackout, without providing detailed implementation guidance. A committee of international experts and advisors from numerous countries is currently working on an IAEA Technical Document (TECDOC) whose objective is to provide a common international technical basis from which the various criteria for SBO events need to be established, to support operation under design basis and design extension conditions (DEC) at nuclear power plants, to document in a comprehensive manner, all relevant aspects of SBO events at NPPs, and to outline critical issues which reflect the lessons learned from the Fukushima Dai-ichi accident. This paper discusses the commonly encountered difficulties associated with establishing the SBO criteria, shares the best practices, and current strategies used in the design and implementation of SBO provisions and outline the structure of the IAEA's SBO TECDOC under development. (author)

  7. Safety aspects of station blackout at nuclear power plants

    The principal focus of this report is on existing light water reactor nuclear power plants. However, many of the considerations discussed herein can be equally applied to new plants, i.e. those not yet in construction. This report is organized to provide a description of design and procedural factors which safety assessments and reviews of operating experience have shown to be important. These are divided into the off-site power system, the on-site AC power systems and alternate (or nearby) sources of power. The latter may be used in the unlikely event that both normal off-site and on-site sources fail. It must be emphasized that first priority should be placed on designing and maintaining high reliability of both the off-site and on-site AC power systems. This basic concept also applies to the capabilities for restoring power sources which failed and making use of all available alternative and nearby power sources during an emergency, to restore AC power in a prompt manner. Discussions on these aspects are provided in chapters 2 and 3 of this report. Because the expected event frequency and associated confidence in such estimations of station blackout are uncertain, preparations should be made to deal with a station blackout. The nature of those preparations, whether they be optimizing emergency procedures to use existing equipment, modifying this equipment to enhance capabilities, or adding new components or systems to cope with station blackout, must be made in light of plant-specific assessments and regulatory safety philosophies/requirements. Discussions on these matters are provided in chapter 4. General and specific conclusions and recommendations are provided in chapter 5. Appendix A provides a description of several case studies on station blackout and loss of off-site power. Abstracts of papers and presentations are provided in Appendix B with authors and affiliations identified to facilitate personal contact. The References and Bibliography contain a

  8. Lionel Larré, Histoire de la nation cherokee

    Berthier-Foglar, Susanne


    Histoire de la nation cherokee est un ouvrage original qui traite du peuple cherokee depuis son apparition dans le sud-est des États-Unis jusqu’à l’époque contemporaine. L’originalité de cette Histoire vient du choix des documents, en version longue, qui accompagnent chaque chapitre et qui font partie des sources sur lesquelles se base sa rédaction. On y lit la voix des explorateurs en terre cherokee, de l’administration américaine, mais aussi du peuple cherokee lui-même. C’est en effet le pr...

  9. Prevention of human errors in nuclear power stations

    It is indispensable to decrease human errors as far as possible in view of the importance of nuclear power generation for Japan. From the viewpoint like this, the Central Research Institute of Electric Power Industry organized Human Factor Research Center in 1987, and the research on the prevention of human errors in nuclear power stations has been advanced together with electric power companies. For initial five years, the research centering around individual human behavior was advanced, and the establishment of the technique for the analysis of the cause and the plan of countermeasures on the occurred accidents and troubles from the aspect of human factors, the development of human behavior prediction system, the collection of the data on the state of research regarding human factors, the proposal of the concrete supporting technology for reducing human errors in maintenance works, the development of the technique for determining the probability of trouble occurrence, the development of the equipment for measuring and analyzing human visual sense, behavior and physiology, and the proposal of the technology for supporting the formation of knowledge and education system were carried out. In the second five-year period to 1996, the team errors in operation and maintenance, the development of a man-machine simulator, the practical use of the concrete supporting technology and so on are taken up. The human behavior prediction system is explained. (K.I.)

  10. Operating Experience at the Aagesta Nuclear Power Station

    Sweden's first nuclear power reactor Agesta, achieved criticality on July 17, 1963. Full power (65 MWt) was attained on March 20, 1964. Aagesta is a heavy water cooled and moderated pressure vessel reactor used for production of electricity as well as for district heating. The design, assembly and construction etc, of the reactor was described in detail in a staff report by AB Atomenergi, 'The Aagesta Nuclear Power Station' edited by B McHugh, which was published in September, 1964. In the book experiences from the commissioning and the first operation of the reactor were reported as well as findings from the extensive reactor physics studies made during this period. The report now presented is written by members of the operating team at Aagesta since its start. It reflects in general the experiences up to the end of 1965. The Aagesta Log, however, covers the period up to the normal summer stop 1966. The reactor has hitherto produced 506,000 MWh power of which 48,700 MWh have been electric power. In July 1965 the responsibility for the reactor operation was taken over by the Swedish State Power Board from AB Atomenergi, which company had started the reactor and operated it until the summer break 1965

  11. Multivariable control in nuclear power stations -survey of design methods

    The development of larger nuclear generating stations increases the importance of dynamic interaction between controllers, because each control action may affect several plant outputs. Multivariable control provides the techniques to design controllers which perform well under these conditions. This report is a foundation for further work on the application of multivariable control in AECL. It covers the requirements of control and the fundamental mathematics used, then reviews the most important linear methods, based on both state-space and frequency-response concepts. State-space methods are derived from analysis of the system differential equations, while frequency-response methods use the input-output transfer function. State-space methods covered include linear-quadratic optimal control, pole shifting, and the theory of state observers and estimators. Frequency-response methods include the inverse Nyquist array method, and classical non-interactive techniques. Transfer-function methods are particularly emphasized since they can incorporate ill-defined design criteria. The underlying concepts, and the application strengths and weaknesses of each design method are presented. A review of significant applications is also given. It is concluded that the inverse Nyquist array method, a frequency-response technique based on inverse transfer-function matrices, is preferred for the design of multivariable controllers for nuclear power plants. This method may be supplemented by information obtained from a modal analysis of the plant model. (auth)

  12. Climatographic analysis of the Zion Nuclear Power Station site

    The computerized emergency response dose assessment codes (ERDACs) used in the nuclear industry commonly rely on Gaussian plume dispersion techniques. In coastal zones, particularly within 15 km of the shoreline, complex four-dimensional mesoscale meteorological regimes often violate some of the basic assumptions of Gaussian dispersion. For example a land breeze will initially advect materials offshore into unpopulated areas. Such effluents may pool over water only to return to land in the next morning's onshore flow, but in locations and concentrations unknown and undeterminable from on-site data and standard Gaussian modeling techniques. Improving the performance of ERDACs for a given coastal site requires a climatographic inventory of that site and its surroundings. This involves identifying the coastal mesoscale regimes (CMRs) that affect the site, including their annual frequencies of occurrence and the meteorological conditions that characterize them. Such a climatographic analysis has been performed for the Zion nuclear power station (NPS), which is located just north of Chicago, Illinois, on the western shore of southern Lake Michigan. The purpose of this papers is to summarize the results of this study and its implications for radiological emergency response activities. A conceptual framework for allocating resources in developing an adequate emergency response system includes three major factors: (1) frequency of the mesoscale regimes; (2) extent to which the regime can result in high concentrations/doses; (3) ease with which it can be modeled, with due consideration given for input data requirements

  13. Climatographic analysis of the Zion nuclear power station site

    The computerized emergency response dose assessment codes (ERDACs) used in the nuclear industry commonly rely on Gaussian plume dispersion techniques. In coastal zones, particularly within 15 km of the shoreline, complex four-dimensional mesoscale meteorological regimes often violate some of the basic assumptions of Gaussian dispersion. For example, a land breeze will initially advect materials offshore into unpopulated areas. Such effluents may pool over water only to return to land in the next morning's onshore flow, but in locations and concentrations unknown and undeterminable from on-site data and standard Gaussian modeling techniques. Improving the performance of ERDACs for a given coastal site requires a climatographic inventory of that site and its surroundings. This involves identifying the coastal mesoscale regimes (CMRs) that affect the site, including their annual frequencies of occurrence and the meteorological conditions that characterize them. Such a climatographic analysis has been performed for the Zion nuclear power station (NPS), which is located just north of Chicago, Illinois, on the western shore of southern Lake Michigan. The purpose of this paper is to summarize the results of this study and its implications for radiological emergency response activities

  14. Balakovo - Biblis nuclear power stations WANO partnership 20 years

    The WANO partnership of the Balakovo, Russia, and Biblis, Germany, nuclear power stations, which was initiated in 1989 within the framework of the agreements and objectives of the WANO Centers in Paris and Moscow, can be called a success story. Since 1990, a total of 78 meetings have been arranged within the WANO partnership for projects exchanging experience in seminars, workshops and on-site tours, which served for increased safety, availability, and safety culture in line with the objectives of WANO. The technical discussions within WANO projects often led to possibilities for technical modifications which were put into effect in more than 30 projects financed, as a rule, by the European Union. A total of 153 experts and senior staff from the Balakovo nuclear power plant travelled to Germany, while 90 persons went from Biblis to Russia for these exchanges. Both sides have agreed to continue their close cooperation also in the future and exchange information and experience at the high level reached. This WANO partnership is also supported by overarching international events organized by VGB with WANO MC, such as the annual meetings of power plant executives, and specialized seminars on a variety of subjects. (orig.)

  15. Development situation about the Canadian CANDU Nuclear Power Generating Stations

    The CANDU reactor is the most versatile commercial power reactor in the world. The acronym 'CANDU', a registered trademark of Atomic Energy of Canada Limited, stands for 'CANada Deuterium Uranium'. CANDU uses heavy water as moderator and uranium (originally, natural uranium) as fuel. All current power reactors in Canada are of the CANDU type. Canada exports CANDU type reactor in abroad. CANDU type is used as the nuclear power plants to produce electrical. Today, there are 41 CANDU reactors in use around the world, and the design has continuously evolved to maintain into unique technology and performance. The CANDU-6 power reactor offers a combination of proven, superior and state-of-the-art technology. CANDU-6 was designed specifically for electricity production, unlike other major reactor types. One of its characteristics is a very high operating and fuel efficiency. Canada Nuclear Power Generating Stations were succeeded in a commercial reactor of which the successful application of heavy water reactor, natural uranium method and that on-power fuelling could be achieved. It was achieved through the joint development of a major project by strong support of the federal government, public utilities and private enterprises. The potential for customization to any country's needs, with competitive development and within any level of domestic industrial infrastructure, gives CANDU technology strategic importance in the 21st century

  16. Construction of Kashiwazaki Kariwa Nuclear Power Station unit No.5

    No.5 plant in Kashiwazaki Kariwa Nuclear Power Station is a BWR type nuclear power plant of 1100 MWe capacity, the construction of which was begun in October, 1983, and the commercial operation was started on April 10, 1990. This plant is the first plant in which the results of the secondary improvement and standardization were fully adopted, and it the latest facilities aiming at the further improvement of reliability and the reduction of the radiation dose to which workers are exposed. By the adoption of the improved technology for systems, machinery and equipment, such as the core with zirconium-lined fuel and the installation of the pumps in reactor coolant purification system in low temperature zone, the objective of improving the plant performance was attained. In the construction, the improvement of construction techniques using large mobile cranes for the first time in Japan and the promotion of the trial operation based on the activities of promoting high reliability enabled the completion of construction within the predetermined period. The construction processes and techniques, the new technology adopted in the plant system, the layout, the activities of promoting high reliability and the start-up test are reported. (K.I.)

  17. Nuclear generating station and heavy water plant cost estimates for strategy studies

    Nuclear generating station capital, operating and maintenance costs are basic input data for strategy analyses of alternate nuclear fuel cycles. This report presents estimates of these costs for natural uranium CANDU stations, CANDU stations operating on advanced fuel cycles, and liquid metal fast breeder reactors. Cost estimates for heavy water plants are also presented. The results show that station capital costs for advanced fuel cycles are not expected to be significantly greater than those for natural uranium stations. LMFBR capital costs are expected to be 25-30 percent greater than for CANDU's. (auth)

  18. Lessons learned from our accident at Fukushima nuclear power stations

    This paper is given in order to share the detailed information on the Fukushima Accident which occurred on March 11, 2011, and the lessons learned from it which worldwide nuclear experts might currently have more interest in. The paper first reflects how the facilities were damaged by a very strong earthquake and a series of beyond design-basis tsunamis. The earthquake caused loss of all off-site electric power at Fukushima Daiichi Nuclear Power Station (1F), and the following series of tsunami made all emergency diesel generators except one for Unit 6 and most of DC batteries inoperable and severely damaged most of the facilities located on the ocean side. Thus all the units at 1F resulted in the loss of cooling function and ultimate heat sink for a long time period. TEPCO focused on restoration of the instruments and lights in the Main Control Room (MCR), preparation of alternative water injection and venting of Primary Containment Vessel (PCV) in the recovery process. However, the workers faced a lot of difficulties such as total darkness, repeated aftershocks, high radiation dose, a lot of debris on the ground, loss of communication means, etc. Massive damages by the tsunami and lack of necessary equipments and resources hampered a quick recovery. It eventually resulted in the severe core damage of Unit 1, 2, and 3 and also the hydrogen explosions in the reactor buildings of Unit 1, 3, and 4. This paper finally extracts the lessons learned from the accident and proposes the countermeasures, such as flood protection for essential facilities, preparation of practical and effective tools, securing communication means and so on. These would help the people involved in the nuclear industries all over the world properly understand the accident and develop their own countermeasures appropriately. (authors)

  19. Study of wet blasting of components in nuclear power stations

    This report looks at the method of wet blasting radioactive components in nuclear power stations. The wet blaster uses pearl shaped glass beads with the dimensions of 150-250 μm mixed with water as blasting media. The improved design, providing outer operator's positions with proper radiation protection and more efficient blasting equipment has resulted in a lesser dose taken by the operators. The main reason to decontaminate components in nuclear power plants is to enable service on these components. On components like valves, pump shafts, pipes etc. oxides form and bind radiation. These components are normally situated at some distance from the reactor core and will mainly suffer from radiation from so called activation products. When a component is to be decontaminated it can be decontaminated to a radioactive level where it will be declassified. This report has found levels ranging from 150-1000 Bq/kg allowing declassification of radioactive materials. This difference is found between different countries and different organisations. The report also looks at the levels of waste generated using wet blasting. This is done by tracking the contamination to determine where it collects. It is either collected in the water treatment plant or collected in the blasting media. At Barsebaeck the waste levels, from de-contaminating nearly 800 components in one year, results in a waste volume of about 0,250 m3. This waste consists of low and medium level waste and will cost about 3 600 EURO to store. The conclusions of the report are that wet blasting is an indispensable way to treat contaminated components in modern nuclear power plants. The wet blasting equipment can be improved by using a robot enabling the operators to remotely treat components from the outer operator's positions. There they will benefit from better radiation protection thus further reduce their taken dose. The wet blasting equipment could also be used to better control the levels of radioactivity on

  20. Recent advances in radiation monitoring systems for nuclear power stations

    Present projections indicate that by 1990 a minimum of 700 nuclear power stations will be in operation in at least 42 different countries. The health physics' profession is confronted, therefore, with a massive effort to control the radiological consequences of these operations. Regulations have been adopted or are being considered by the various governments to guide the health physicist. It is apparent that the necessary radiological measurements will become increasingly complex, require improved sensitivity and accuracy, increase in frequency, and demand more attention from the health physics staff. Computerized systems offer a cost-effective solution to keep these expanding requirements within manageable limits. The technology of computers, minicomputers and microcomputers is one of the most dynamic developments occurring in today's society. It has a history of doing 'more-for-less' as each new advancement reaches the commercial market. In the face of constant cost escalation in nuclear plant construction, the opportunity to provide more-for-less is a most welcome change. In anticipation of expanded radiological requirements and the availability of a compatible technology to meet them, the next step is to design and test a total system to be responsive to regulatory guidelines. Such a system will be described with appropriate emphases on both the data acquisition and data management subsystems. As the system evolves, it is logical to view its full purpose as a health physics operations center more than just another monitoring tool. Here the data vital to the decision-making processes are displayed rapidly and intelligently for interpretation by the operators. Overall, system design and operation should provide the health physicist with credible data to reflect favorably on the environmental and public acceptability of nuclear power

  1. Selecting main technical solutions for heat supply systems equipped with nuclear cogeneration stations

    Smirnov, I. A.; Svetlov, K. S.; Khrilev, L. S.


    Methodical principles for determining the yearly quantities of heat supplied from a nuclear cogeneration station are described, results from an analysis for selecting the optimal design cogeneration ratio and the parameters of heat carrier are presented, and matters pertinent to the operational reliability and safety of heat supply systems equipped with nuclear cogeneration stations are considered.

  2. Seismic margin assessment of the Catawba Nuclear Station: Volume 2, Appendixes: Final report

    Campbell, R.D.; Henley, B.F.; Shoemaker, W.; Kulla, D.; Buttemer, D.R.; McIntyre, T.; Moriwaki, Y.; Idriss, I.M.


    A seismic margin assessment of the Duke Power Company Catawba unit 2 nuclear station showed the practicality of an EPRI-developed methodology for demonstrating the ability of nuclear plants to withstand earthquakes beyond design basis. The assessment established that the Catawba station would survive earthquake loads up to twice its design basis.

  3. 76 FR 44376 - Vermont Yankee Nuclear Power Station; Notice of Withdrawal of Application for Amendment to...


    ... COMMISSION Vermont Yankee Nuclear Power Station; Notice of Withdrawal of Application for Amendment to... request of Vermont Yankee Nuclear Power Station (the licensee) to withdraw its August 19, 2010, application for proposed amendment to Facility Operating License No. DPR-28 for the Vermont Yankee...

  4. Exploration and practice on contract management of Daya Bay Nuclear Power Station

    In the market economy, Daya Bay Nuclear Power Station needs to out source or allow to suppliers among industries, while concentrating its core competitive capability, for safely and stable operation. By evaluating the features of contract management in Daya Bay Nuclear Power Station, set up the organization and process of the supply management

  5. Nuclear power station with nuclear reactor accommodated largely secure against catastrophes

    If the nuclear reactor is installed underground near the power station unit, then danger to the environment due to radiation contamination can be largely or nearly completely prevented by a covering of constant thickness or by a covering which can be installed by a catastrophic accident. The extinguishing of a burning reactor is also relatively simple for a reactor accommodated in a pit. The above-mentioned measures can be used individually or combined. (orig./HP)

  6. Algological studies on the site of the Fessenheim nuclear power station

    Systematic study of the algal flora at five stations situated on both sides of the nuclear power station at Fessenheim (department of Haut-Rhin, France). The analysis of the diatomaceae populations in 1977 and 1978, i.e. before and after the start of the reactors, does not indicate, in the composition and abundance of algae, any modifications susceptible to be directly connected to the implantation of the nuclear power station

  7. Radiocarbon mass balance for a Magnox nuclear power station

    Highlights: • First comprehensive assessment of C-14 arisings in a Magnox nuclear power station. • C-14 production in graphite and coolant gas quantified by activation modelling. • Principal C-14 production pathway is via C-13 with a small contribution from N-14. • C-14 mass balance model provides a basis for analyses on other reactors. - Abstract: Nuclear power generation in the United Kingdom is based principally on graphite-moderated gas-cooled reactors. The mass of irradiated graphite associated with these reactors, including material from associated experimental, prototype and plutonium production reactors, exceeds 96,000 tonnes. One of the principal long-lived radionuclides produced during graphite irradiation is radiocarbon (C-14). Its potential as a hazard must be taken into account in decommissioning and graphite waste management strategies. While C-14 production processes are well-understood, radionuclide distributions and concentrations need to be characterised. A common misconception is that generic statements can be made about C-14 precursors and their location. In fact, the composition of the original manufactured material, the chemical environment of the graphite during service and its irradiation history will all influence C-14 levels. The analysis presented here provides the first assessment of the principal C-14 activation pathways for a UK Magnox reactor. Activation modelling has been used to predict C-14 production rates in both the graphite core and the carbon dioxide coolant over a selected period of operation and the results compared with monitored site C-14 discharges. Principal activation routes have been identified, which should inform future graphite waste management strategies relating to radiocarbon

  8. Safety culture program for the Cofrentes nuclear power station

    IBERDROLA (who is the owner of the Cofrentes NPS and shared other Spanish nuclear units) has paid careful attention through his nuclear safety and quality unit to safety and quality culture concepts and methodologies developed during the second half of the past decade and the beginning of the 90's. Moreover, a good management as well as work-men responsability and motivation should conform a good level of safety culture. We thus felt that we needed to combine a safety culture plan and a continuous quality improvement program so as to obtain the best possible safety and culture results. Consequently, IBERDROLA established a pilot program for his Cofrentes NPS in 1992 to drive for quality, as a top management policy, actively pursued by corporate and station managers. In summary, the pilot program consists of a 'Safety Culture Plan' which establishes the vision, mission, principles, global obj ectives and especific obj ectives and tasks, and of a 'continuous quality improvement plan' in which three phases have been set ut: phase I - learn to work as a team, fix the methodology and look for results; phase II - focused toward objectives, simplification and improvement of work processes, phase III - look toward supporting recommendations and achieving the policy goals. However, we may already say that we have preceived greater management and workmen involvement, better planning of significant issues and an improvement in the team-work environment. Nevertheless, we are in the process of changing certain mechanisms and ways of behaviour that we have detected as drawbacks in the past, in order to further improve in this area. (author)

  9. Economic and financial benefits as a compensation for living near a nuclear power station. A case study of Kashiwazaki-Kariwa Nuclear Power Station

    Although dwellers living near a nuclear power station are entitled to economic/financial benefits such as increased job opportunities and local tax revenues pertaining to the power station, it is not clear whether such benefits are appreciated by the dwellers. Two findings of this study based upon a social survey of local dwellers living near the Kashiwazaki-Kariwa Nuclear Power Station are summarized as follows. First, an increase in the per capita sizes of the local tax revenue and national subsidies resulted in a larger share of respondents who thought that those revenues are beneficial. Therefore, local dwellers are aware of the sizes of economic/financial benefits. Second, given the same risk level of nuclear disaster, a larger per capita financial benefit resulted in a larger share of respondents who felt compensated for the nuclear risk. However, this increase in the number of compensated respondents is low relative to the increase in the amount of financial benefits. (author)

  10. Torness nuclear power station. From folly to fiasco

    The subject is covered in chapters, entitled: introduction; the Torness story; electricity demand; the real cost of nuclear power; Torness - employment delusion; nuclear waste; nuclear power and nuclear weapons; domestic energy conservation; combined heat and power; conclusion. (U.K.)

  11. Completion of Kashiwazaki Kariwa Nuclear Power Station Unit No. 4

    No. 4 plant in Kashiwazaki Kariwa Nuclear Power Station, Tokyo Electric Power Co., Inc. is a BWR plant in which the results of the LWR improvement and standardization project by Japanese independent technology were adopted. Hitachi Ltd. has applied the experiences of construction and operation obtained so far, the improved technology based on research and development and the latest technologies to it, in addition to the technology which was verified in the preceding No. 5 plant. In the aspect of the systems and facilities, the various improvements based on the experience in past plants were reflected from the initial stage of design. Also in the design techniques, the three-dimensional CAD system using the newest computer technology was applied to the layout and piping design, and the quality and efficiency of design were improved. In the aspect of construction, a crawler crane with the largest lifting capacity in the world was used, and the large section module method, by which large prefabricated machinery, equipment and piping are directly lifted in, was applied. By these means, the safety of workings was secured, the construction period was shortened, and the plant showed good, stable results in the trial, and started the commercial operation in August, 1994. No. 4 plant is a BWR plant of 1100 MW output. The applied new technologies and the contents of the improvement of the design and facilities are shown. The outline and the features of the construction works and the trial operation are reported. (K.I.)

  12. Simulator training and licensing examination for nuclear power station operator

    For the recruitment, training and position qualification of the simulator instructors and feedback of training effect, the management approaches are formulated in 'The System for Simulator Training and Licensing Examination of Daya Bay Nuclear Power Station Operators'. The concrete requirements on the professional knowledge, work experience and foreign language ability of a simulator instructor are put forward. The process of instructor training is designed. The training items include the trainer training, pedagogy training, time management training, operation activities training during outage of unit, 'shadow' training and on-the-jot training on simulator courses. Job rotation is realized between simulator instructor and licensing personnel on site. New simulator instructor must pass the qualification identification. After a duration of 2 years, re-qualification has to be carried out. On the basis of the operator training method introduced from EDF (electricite De France), some new courses are developed and the improvement on the initial training, retaining courses, the technical support and the experience feedback by using the simulator is done also. (authors)

  13. The Fukushima Nuclear Power Station incident and marine pollution

    Based on the facts relating to the radioactive wastewater discharged by the Fukushima Nuclear Power Station in Japan, this paper intends to explore the international legal obligations for Japan from three perspectives, namely, the immediate notification, the prevention of transboundary harm and the prevention of dumping. Furthermore, this article defines and compares two types of international legal liabilities, the traditional state responsibility and the responsibility for transboundary harm. Through comparison, the international legal liability of Japan is discussed. After detailed analysis, the conclusion is that Japan should be responsible for the obligation of immediate notification and since Japan unilaterally discharge the wastes without prior specific permits of other contracting countries, it should also be responsible for the violation of prevention of dumping. Since so far, no material injury has emerged and there would appear to be no culpability as regards the prevention of transboundary harm. Finally, this paper stresses the necessity to develop a worldwide agreement concerning the liability for transboundary harm and to establish an institutional framework for the enforcement of a state’s obligations, and also the great significance of international cooperation between nations and organisations in relation to marine environmental protection.

  14. Creating user-friendly emergency procedures at Catawba nuclear station

    Catawba nuclear station has recently begun an emergency operating procedures upgrade program with the goal of creating procedures that are user-friendly and promote good communications between operators. Initial upgrade efforts have dealt specifically with the entry procedure, which is used in implementing the emergency procedures at Catawba. This procedure is named EP/01 Reactor Trip or Safety Injection and is based on the Westinghouse emergency response guidelines. It is used to perform two major functions. The first is to verify that all automatic system actuations have occurred following a reactor trip or safety injection. The second is to diagnose the specific event and provide a transition to the appropriate recovery procedure. Observations of shift personnel during simulator exercises indicated that there was an interface problem between the operators and the procedure. It appeared that the wording and format of the procedure did not allow for good communications between the operators. During some scenarios, the actions taken by the operators indicated that they regarded the procedure as a hindrance instead of a tool to be used in combatting the accident. The purpose of this upgrade program is to address the problems cited above so that procedures can be created that are both user-friendly and technically correct. To accomplish this goal, the procedure was rewritten with a new approach, and the positive results are described

  15. The economic consequences of the Sizewell 'B' nuclear power station

    The subject is covered in chapters, entitled: introduction (the background to Sizewell 'B'); policy options (Sizewell 'B'; a new coal-fired station; the no-new-station option; a PWR programme); economic framework (direct effects; financing; final macroeconomic effects); the construction phase (capital costs; direct effects; final effects; summary); the operating phase (a new power station as a replacement for older stations; the period of base-load operation; the later years of operation; summary); conclusions and policy recommendations. The first recommendation is that if a new power station is built it should be a coal-fired station rather than a PWR. The second recommendation is that if a new coal station is built there is a case for building it early, ahead of demand. (U.K.)

  16. Will Rogers's Radio: Race and Technology in the Cherokee Nation

    Ware, Amy M.


    While radio personality Will Rogers's pioneering role in radio is obvious (he worked in the medium during its earliest years), its connections to Cherokee and other tribal technologies have been neglected. This failure to recognize Rogers's part in this particular strain of Cherokee history is a symptom of a larger cultural illness in the United…

  17. Rural Cherokee Children with Disabilities: Parental Stories of Special Education

    Jandura, Collette


    Parents of Cherokee children with disabilities encounter educational agencies from their child's birth to adulthood. Living rurally within the Cherokee Nation's jurisdictional boundaries, these indigenous families engage with a myriad of special education agencies and subsequent policies. This qualitative study explores parental…

  18. The Cherokee Syllabary: A Writing System in Its Own Right

    Cushman, Ellen


    Informally recognized by the tribal council in 1821, the 86-character Cherokee writing system invented by Sequoyah was learned in manuscript form and became widely used by the Cherokee within the span of a few years. In 1827, Samuel Worcester standardized the arrangement of characters and print designs in ways that differed from Sequoyah's…

  19. Walker Calhoun: Cherokee Song and Dance Man. Interview.

    Olson, Ted


    Born in 1918, the youngest of 12 children, Walker Calhoun describes growing up on the Cherokee Reservation in North Carolina. The schools turned the Cherokee against their old ways, but Walker learned many old songs and dances from his uncle, Will West. Since retirement, Walker has taught the dances and songs to children. His material has been…

  20. Young People Take the Lead: Cherokee Nation's Approach to Leadership.

    Hall, McClellan; Kielsmeier, James A.


    Oklahoma's Cherokee Nation Youth Leadership Program (CNYLP) began in 1982 with the vision of drawing elements of the tribe together through an innovative youth program designed to instill self-confidence, positive regard for Cherokee identity, and a sense of community spirit through service to others. Patterned after the National Youth Leadership…

  1. Study of wet blasting of components in nuclear power stations

    Hall, J


    This report looks at the method of wet blasting radioactive components in nuclear power stations. The wet blaster uses pearl shaped glass beads with the dimensions of 150-250 {mu}m mixed with water as blasting media. The improved design, providing outer operator's positions with proper radiation protection and more efficient blasting equipment has resulted in a lesser dose taken by the operators. The main reason to decontaminate components in nuclear power plants is to enable service on these components. On components like valves, pump shafts, pipes etc. oxides form and bind radiation. These components are normally situated at some distance from the reactor core and will mainly suffer from radiation from so called activation products. When a component is to be decontaminated it can be decontaminated to a radioactive level where it will be declassified. This report has found levels ranging from 150-1000 Bq/kg allowing declassification of radioactive materials.This difference is found between different countries and different organisations. The report also looks at the levels of waste generated using wet blasting. This is done by tracking the contamination to determine where it collects. It is either collected in the water treatment plant or collected in the blasting media. At Barsebaeck the waste levels, from de-contaminating nearly 800 components in one year, results in a waste volume of about 0,250 m{sup 3}. This waste consists of low and medium level waste and will cost about 3 600 EURO to store. The conclusions of the report are that wet blasting is an indispensable way to treat contaminated components in modern nuclear power plants. The wet blasting equipment can be improved by using a robot enabling the operators to remotely treat components from the outer operator's positions. There they will benefit from better radiation protection thus further reduce their taken dose. The wet blasting equipment could also be used to better control the levels of

  2. 78 FR 22347 - GPU Nuclear Inc., Three Mile Island Nuclear Power Station, Unit 2, Exemption From Certain...


    ... licensees, was revised on March 27, 2009, with compliance required by March 31, 2010 (74 FR 13926). The NRC... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION GPU Nuclear Inc., Three Mile Island Nuclear Power Station, Unit 2, Exemption From Certain...

  3. Commerical electric power cost studies. Capital cost addendum multi-unit coal and nuclear stations

    This report is the culmination of a study performed to develop designs and associated capital cost estimates for multi-unit nuclear and coal commercial electric power stations, and to determine the distribution of these costs among the individual units. This report addresses six different types of 2400 MWe (nominal) multi-unit stations as follows: Two Unit PWR Station-1139 MWe Each, Two Unit BWR Station-1190 MWe Each, Two Unit High Sulfur Coal-Fired Station-1232 MWe Each, Two Unit Low Sulfur Coal-Fired Station-1243 MWe Each, Three Unit High Sulfur Coal-Fired Station-794 MWe Each, Three Unit Low Sulfur Coal-Fired Station-801 MWe Each. Recent capital cost studies performed for ERDA/NRC of single unit nuclear and coal stations are used as the basis for developing the designs and costs of the multi-unit stations. This report includes the major study groundrules, a summary of single and multi-unit stations total base cost estimates, details of cost estimates at the three digit account level and plot plan drawings for each multi-unit station identified

  4. Modern power station practice: incorporating modern power system practice. V. J: Nuclear power generation. 3. ed.

    The contents of this new edition of the nuclear volume of Modern Power Station Practice reflect the considerable expansion and development of nuclear power generation in the UK since the initial volume was published in 1964. During that period the Advanced Gas-cooled Reactor (AGR) programme has been completed, the approval of Sizewell B launches a new generation of Pressurized Water Reactor (PWR) stations and the first of the Magnox has completed its useful life. Thus the current volume presents a comprehensive picture of the design, development and operation of the majority of the nuclear station designs currently being operated throughout the world. Four independent but complementary chapters cover Nuclear physics and basic technology; Nuclear station design; Nuclear station operation and Nuclear safety. Although each chapter is complete within itself, some overlap of technical matter between the chapters is inevitable and indeed essential, reflecting the co-operation of widely differing technical disciplines necessary to ensure the safe and economic design and operation of nuclear stations. (Author)

  5. Cherokee Self-Reliance and Word-Use in Stories of Stress

    Lowe, John; Riggs, Cheryl; Henson, Jim; Liehr, Patricia


    This study examined the relationship between Cherokee self-reliance and related values expressed through word-use in stories of stress written by Cherokee adolescents. The overall aim of this pilot study was to test the feasibility of using cultural appropriate measurements for a larger intervention study of substance abuse prevention in Cherokee adolescents. A sample of 50 Cherokee adolescent senior high school students completed the Cherokee Self-Reliance Questionnaire and wrote their story...

  6. Ethanolamine experience at Koeberg nuclear power station, South Africa

    Following testing of ethanolamine as an alternative to ammonia on Unit 2 in 1997, Unit 1 of the Koeberg Nuclear Power Station was converted to ethanolamine in 1998. The Unit has now operated for just over one and a half cycle on ETA. The decision to change to ETA was made to achieve further reductions in feedwater iron transport. Koeberg has always operated ammonia/hydrazine AVT control and ran the feedwater pH at 9.6-9.7 before the changeover. The original pH levels were increased in response to concerns over flow-accelerated corrosion. A by product of reducing the FAC rates is a reduction in iron transport. Although nominally all-ferrous, there are a number of small copper-containing components and the Koeberg Engineering Department would not countenance a further increase in ammonia concentrations in case of copper transport to the SGs. This led to ethanolamine being selected as an alternative to ammonia. The Koeberg condensate polishing plant has been modified, largely to accommodate ETA operation, but is not currently operable in the modified configuration. It is therefore on standby while ETA is implemented. The SG blowdown demineralizers have begun to be operated past ammonia/ETA break, but optimisation is largely dependent on CPP availability in the modified configuration. This paper documents the Koeberg experience to date of operation under an ethanolamine-AVT regime. As one of the few plants outside of the USA to have changed to ethanolamine, it is hoped we can make a valuable contribution for other non-US plants considering such a move. (authors)

  7. Steam generator of Vandellos nuclear power station: Operational experience

    The Central Nuclear de Vandellos power station at Hospitalet del Infante, Spain, is a 500 MWe gas graphite moderated natural uranium reactor. The plant has generated over 46,000 million KWh over the past thirteen years of service. Throughout this service, the plant has suffered from THO phase erosion-corrosion damage in the steam generator sections of the system. The Vandellos steam generators are once-through units constructed of 1386 mild steel tubing (panels) each fabricated into a serpentine containing 83 horizontal passes. Four independent steam generator circuits are combined to feed two, 250 MWe turbines. Erosion-corrosion damage has caused panel element leakage in the evaporation of some tubing elements. The rate of erosion-corrosion damage has been modified through different operational changes since damage was first detected in 1975. This paper describes the different operating behavior of the four steam generators and an evaluation of damage through the expertise of different technical resource groups. The changes in plant operating technique discussed include hydrodynamic conditions and chemical treatment parameters. One of the most important changes in plant operation has been in the use of amines as alkaline agents. Solutions of ammonia were initially used for pH control of feedwater. In an effort to reduce erosion-corrosion levels below rates experienced using ammonia, a change was made to the use of morpholine, and more recently, a change to the use of AMP(2 amino-2-methyl-1-propanol) has shown favorable results. The paper outlines the overall behavior of steam generator function under plant transition conditions, and contrasts that behavior with current chemical parameters experienced using AMP treatment. Water chemistry characteristics are used to present an evaluation of the development of erosion-corrosion damages from 1976 through present operating conditions. (author)

  8. Standard concerning the design of nuclear power stations in earthquake-prone districts

    The measures of security assurance against the effect of radioactive contamination has become more and more complex due to the construction of nuclear power stations of diverse types. The aseismatic measures for the nuclear power stations built in the districts where earthquakes of different intensity occur are important problems. All main machinery and equipments and emergency systems in power stations must be protected from earthquakes, and this makes the solution of problems difficult. At present in USSR, the provisional standard concerning the design of atomic energy facilities built in earthquake-prone districts is completed. The basic philosophy of the standard is to decide the general requirements as the conditions for the design of nuclear power stations built in earthquake-prone districts. The lowest earthquake activity in the construction districts is considered as magnitude 4, and in the districts where earthquake activity is magnitude 9 or more, the construction of nuclear power stations is prohibited. Two levels of earthquake action are specified for the design: design earthquake and the largest design earthquake. The construction sites of nuclear power stations must be 15 to 150 km distant from the potential sources of earthquakes. Nuclear power stations are regarded as the aseismatically guaranteed type when the safety of reactors is secured under the application of the standard. The buildings and installations are classified into three classes regarding the aseismatic properties. (Kako, I.)

  9. 75 FR 52014 - Notice of Inventory Completion: U.S. Department of Agriculture, Forest Service, Cherokee National...


    ..., Cherokee National Forest, Cleveland, TN AGENCY: National Park Service, Interior. ACTION: Notice. Notice is... control of the U.S. Department of Agriculture, Forest Service, Cherokee National Forest, Cleveland, TN... with the Cherokee Tribes. The Cherokee are represented by the Cherokee Nation, Oklahoma; Eastern...

  10. AECB staff annual assessment of the Darlington Nuclear Generating Station for the year 1996

    The Atomic Energy Control Board is the independent federal agency that controls all nuclear activities in Canada. A major use of nuclear energy in Canada is electricity production. The AECB assesses every station's performance against legal requirements, including the conditions in the operating licence. Each station is inspected and all aspects of the station's operation and management is reviewed. This report is the AECB staff assessment of safety at the Darlington Nuclear Generating Station for 1996. Ontario Hydro operated the station in a safe manner in 1996. All four special safety systems were fully available 100 percent of the time. There were more problems that affected the safety support systems in 1996 than in the previous year