WorldWideScience

Sample records for station operations

  1. Space station operations management

    Science.gov (United States)

    Cannon, Kathleen V.

    1989-01-01

    Space Station Freedom operations management concepts must be responsive to the unique challenges presented by the permanently manned international laboratory. Space Station Freedom will be assembled over a three year period where the operational environment will change as significant capability plateaus are reached. First Element Launch, Man-Tended Capability, and Permanent Manned Capability, represent milestones in operational capability that is increasing toward mature operations capability. Operations management concepts are being developed to accomodate the varying operational capabilities during assembly, as well as the mature operational environment. This paper describes operations management concepts designed to accomodate the uniqueness of Space Station Freedoom, utilizing tools and processes that seek to control operations costs.

  2. Space Station Freedom operations costs

    Science.gov (United States)

    Accola, Anne L.; Williams, Gregory J.

    1988-01-01

    Measures to reduce the operation costs of the Space Station which can be implemented in the design and development stages are discussed. Operational functions are described in the context of an overall operations concept. The provisions for operations cost responsibilities among the partners in the Space Station program are presented. Cost estimating methodologies and the way in which operations costs affect the design and development process are examined.

  3. Automating Space Station operations planning

    Science.gov (United States)

    Ziemer, Kathleen A.

    1989-01-01

    The development and implementation of the operations planning processes for the Space Station are discussed. A three level planning process, consisting of strategic, tactical, and execution level planning, is being developed. The integration of the planning procedures into a tactical planning system is examined and the planning phases are illustrated.

  4. Space station operating system study

    Science.gov (United States)

    Horn, Albert E.; Harwell, Morris C.

    1988-01-01

    The current phase of the Space Station Operating System study is based on the analysis, evaluation, and comparison of the operating systems implemented on the computer systems and workstations in the software development laboratory. Primary emphasis has been placed on the DEC MicroVMS operating system as implemented on the MicroVax II computer, with comparative analysis of the SUN UNIX system on the SUN 3/260 workstation computer, and to a limited extent, the IBM PC/AT microcomputer running PC-DOS. Some benchmark development and testing was also done for the Motorola MC68010 (VM03 system) before the system was taken from the laboratory. These systems were studied with the objective of determining their capability to support Space Station software development requirements, specifically for multi-tasking and real-time applications. The methodology utilized consisted of development, execution, and analysis of benchmark programs and test software, and the experimentation and analysis of specific features of the system or compilers in the study.

  5. Space Station Freedom operations planning

    Science.gov (United States)

    Accola, Anne L.; Keith, Bryant

    1989-01-01

    The Space Station Freedom program is developing an operations planning structure which assigns responsibility for planning activities to three tiers of management. The strategic level develops the policy, goals and requirements for the program over a five-year horizon. Planning at the tactical level emphasizes program integration and planning for a two-year horizon. The tactical planning process, architecture, and products have been documented and discussed with the international partners. Tactical planning includes the assignment of user and system hardware as well as significant operational events to a time increment (the period of time from the arrival of one Shuttle to the manned base to the arrival of the next). Execution-level planning emphasizes implementation, and each organization produces detailed plans, by increment, that are specific to its function.

  6. Space Station overall management approach for operations

    Science.gov (United States)

    Paules, G.

    1986-01-01

    An Operations Management Concept developed by NASA for its Space Station Program is discussed. The operational goals, themes, and design principles established during program development are summarized. The major operations functions are described, including: space systems operations, user support operations, prelaunch/postlanding operations, logistics support operations, market research, and cost/financial management. Strategic, tactical, and execution levels of operational decision-making are defined.

  7. Operation feedback of hydrogen filling station

    International Nuclear Information System (INIS)

    Pregassame, S.; Barral, K.; Allidieres, L.; Charbonneau, T.; Lacombe, Y.

    2004-01-01

    One of the technical challenges of hydrogen technology is the development of hydrogen infrastructures which satisfy either safety requirements and reliability of filling processes. AIR LIQUIDE realized an hydrogen filling station in Sassenage (France) operational since September 2003. This station is able to fill 3 buses a day up to 350bar by equilibrium with high pressure buffers. In parallel with commercial stations, the group wanted to create a testing ground in real conditions running with several objectives: validate on a full scale bench a simulation tool able to predict the temperature of both gas and cylinder's materials during filling processes; define the best filling procedures in order to reach mass, temperature and filling time targets; analyse the temperature distribution and evolution inside the cylinder; get a general knowledge about hydrogen stations from safety and reliability point of view; operate the first full scale refuelling station in France. The station is also up-graded for 700bar filling from either a liquid hydrogen source or a gas booster, with cold filling possibility. This paper presents the results concerning 350bar filling : thermal effects, optimal filling procedures and influence of parameters such as climatic conditions are discussed. (author)

  8. Operating experience at Scottish Nuclear's power stations

    International Nuclear Information System (INIS)

    Blackburn, P.

    1991-01-01

    A brief history is presented of the design and operation of the four Scottish nuclear power stations currently run by Scottish Nuclear, namely Hunterston 'A' and 'B' and the Torness reactors. A design flaw in the Magnox reactor at Hunterston 'A' led to it being operated at lower than optimal temperature and hence producing less power. For Hunterston 'B' reactor the Advanced Gas Cooled design prototype was used. Operating setbacks and successes are noted. The design chosen for Torness embraced all the good points of Hunterston 'B' but sought to eliminate its faults. After 26 years of successful operation Hunterston 'A' is now being decommissioned, while the other three stations continue to generate electricity successfully. (UK)

  9. Instructor/Operator Station (IOS) Design Guide.

    Science.gov (United States)

    1988-02-01

    INSTRUTOR /OPERATOR STATION (IOS) AI O...The three functional categories also define three different users in terms of jobs and qualifications (if the functions have been allocated to manual ...function manually (e.g., collect the data S required from schedules, printed course outlines and telephone calls to training and facility managers).

  10. KSC ground operations planning for Space Station

    Science.gov (United States)

    Lyon, J. R.; Revesz, W., Jr.

    1993-01-01

    At the Kennedy Space Center (KSC) in Florida, processing facilities are being built and activated to support the processing, checkout, and launch of Space Station elements. The generic capability of these facilities will be utilized to support resupply missions for payloads, life support services, and propellants for the 30-year life of the program. Special Ground Support Equipment (GSE) is being designed for Space Station hardware special handling requirements, and a Test, Checkout, and Monitoring System (TCMS) is under development to verify that the flight elements are ready for launch. The facilities and equipment used at KSC, along with the testing required to accomplish the mission, are described in detail to provide an understanding of the complexity of operations at the launch site. Assessments of hardware processing flows through KSC are being conducted to minimize the processing flow times for each hardware element. Baseline operations plans and the changes made to improve operations and reduce costs are described, recognizing that efficient ground operations are a major key to success of the Space Station.

  11. Distributed operating system for NASA ground stations

    Science.gov (United States)

    Doyle, John F.

    1987-01-01

    NASA ground stations are characterized by ever changing support requirements, so application software is developed and modified on a continuing basis. A distributed operating system was designed to optimize the generation and maintenance of those applications. Unusual features include automatic program generation from detailed design graphs, on-line software modification in the testing phase, and the incorporation of a relational database within a real-time, distributed system.

  12. Research on station management in subway operation safety

    Science.gov (United States)

    Li, Yiman

    2017-10-01

    The management of subway station is an important part of the safe operation of urban subway. In order to ensure the safety of subway operation, it is necessary to study the relevant factors that affect station management. In the protection of subway safety operations on the basis of improving the quality of service, to promote the sustained and healthy development of subway stations. This paper discusses the influencing factors of subway operation accident and station management, and analyzes the specific contents of station management security for subway operation, and develops effective suppression measures. It is desirable to improve the operational quality and safety factor for subway operations.

  13. Operating experience of Fugen Nuclear Power Station

    International Nuclear Information System (INIS)

    Ohteru, Shigeru; Kaneko, Jun; Kawahara, Toshio; Matsumoto, Mitsuo

    1987-01-01

    The prototype ATR 'Fugen' developed as one of the national project has verified the performance and reliability of the advanced thermal reactor system through the operation for about eight years since 1979, and the elucidation of the characteristics in plutonium utilization and the development and verification of the tuilizing techniques have been advanced. Besides, the operational results and the achievement of the technical development are successively reflected to the design of a demonstration reactor. In this paper, the outline of Fugan and the operational results are reported. The ATR Fugen Power Station is that of the prototype reactor of heavy water moderated, boiling light water cooled, pressure tube type, having the electric output of 165 MW. It started the full scale operation on March 20, 1979, and as of January, 1987, the total generated electric power reached about 7 billion kWh, the time of power generation was about 43,000 h, and the average capacity factor was 60.6 %. Plutonium utilization techniques, the flow characteristics and the dynamic plant characteristics of a pressure tube type reactor, the operational characteristics of a heavy water system and the techniques of handling heavy water containing tritium, and the operational reliability and maintainability of the machinery and equipment installed have been studied. (Kako, I.)

  14. Operations Data Files, driving force behind International Space Station operations

    Science.gov (United States)

    Hoppenbrouwers, Tom; Ferra, Lionel; Markus, Michael; Wolff, Mikael

    2017-09-01

    Almost all tasks performed by the astronauts on-board the International Space Station (ISS) and by ground controllers in Mission Control Centre, from operation and maintenance of station systems to the execution of scientific experiments or high risk visiting vehicles docking manoeuvres, would not be possible without Operations Data Files (ODF). ODFs are the User Manuals of the Space Station and have multiple faces, going from traditional step-by-step procedures, scripts, cue cards, over displays, to software which guides the crew through the execution of certain tasks. Those key operational documents are standardized as they are used on-board the Space Station by an international crew constantly changing every 3 months. Furthermore this harmonization effort is paramount for consistency as the crew moves from one element to another in a matter of seconds, and from one activity to another. On ground, a significant large group of experts from all International Partners drafts, prepares reviews and approves on a daily basis all Operations Data Files, ensuring their timely availability on-board the ISS for all activities. Unavailability of these operational documents will halt the conduct of experiments or cancel milestone events. This paper will give an insight in the ground preparation work for the ODFs (with a focus on ESA ODF processes) and will present an overview on ODF formats and their usage within the ISS environment today and show how vital they are. Furthermore the focus will be on the recently implemented ODF features, which significantly ease the use of this documentation and improve the efficiency of the astronauts performing the tasks. Examples are short video demonstrations, interactive 3D animations, Execute Tailored Procedures (XTP-versions), tablet products, etc.

  15. Space Station Initial Operational Concept (IOC) operations and safety view - Automation and robotics for Space Station

    Science.gov (United States)

    Bates, William V., Jr.

    1989-01-01

    The automation and robotics requirements for the Space Station Initial Operational Concept (IOC) are discussed. The amount of tasks to be performed by an eight-person crew, the need for an automated or directed fault analysis capability, and ground support requirements are considered. Issues important in determining the role of automation for the IOC are listed.

  16. Organization of the operating quality in EDF nuclear power stations

    International Nuclear Information System (INIS)

    Stolz, J.

    1976-01-01

    The organization of operating quality in EDF nuclear stations cover a number of planned and systematic actions of technical and management order carried on at station level and Nuclear Safety Department level. Priority is given to safety quality which has to remain the same during the whole life of the stations; the safety of a station depending from its designing, realization and starting up quality on one hand and from its operating methods on the other [fr

  17. 47 CFR 25.277 - Temporary fixed earth station operations.

    Science.gov (United States)

    2010-10-01

    ... 47 Telecommunication 2 2010-10-01 2010-10-01 false Temporary fixed earth station operations. 25.277 Section 25.277 Telecommunication FEDERAL COMMUNICATIONS COMMISSION (CONTINUED) COMMON CARRIER SERVICES SATELLITE COMMUNICATIONS Technical Operations § 25.277 Temporary fixed earth station operations...

  18. Modular space station, phase B extension. Program operations plan

    Science.gov (United States)

    1971-01-01

    An organized approach is defined for establishing the most significant requirements pertaining to mission operations, information management, and computer program design and development for the modular space station program. The operations plan pertains to the space station and experiment module program elements and to the ground elements required for mission management and mission support operations.

  19. A distributed planning concept for Space Station payload operations

    Science.gov (United States)

    Hagopian, Jeff; Maxwell, Theresa; Reed, Tracey

    1994-01-01

    The complex and diverse nature of the payload operations to be performed on the Space Station requires a robust and flexible planning approach. The planning approach for Space Station payload operations must support the phased development of the Space Station, as well as the geographically distributed users of the Space Station. To date, the planning approach for manned operations in space has been one of centralized planning to the n-th degree of detail. This approach, while valid for short duration flights, incurs high operations costs and is not conducive to long duration Space Station operations. The Space Station payload operations planning concept must reduce operations costs, accommodate phased station development, support distributed users, and provide flexibility. One way to meet these objectives is to distribute the planning functions across a hierarchy of payload planning organizations based on their particular needs and expertise. This paper presents a planning concept which satisfies all phases of the development of the Space Station (manned Shuttle flights, unmanned Station operations, and permanent manned operations), and the migration from centralized to distributed planning functions. Identified in this paper are the payload planning functions which can be distributed and the process by which these functions are performed.

  20. Space Station - An integrated approach to operational logistics support

    Science.gov (United States)

    Hosmer, G. J.

    1986-01-01

    Development of an efficient and cost effective operational logistics system for the Space Station will require logistics planning early in the program's design and development phase. This paper will focus on Integrated Logistics Support (ILS) Program techniques and their application to the Space Station program design, production and deployment phases to assure the development of an effective and cost efficient operational logistics system. The paper will provide the methodology and time-phased programmatic steps required to establish a Space Station ILS Program that will provide an operational logistics system based on planned Space Station program logistics support.

  1. Improvements in operational safety performance of the Magnox power stations

    Energy Technology Data Exchange (ETDEWEB)

    Marchese, C.J. [BNFL Magnox Generation, Berkeley (United Kingdom)

    2000-10-01

    In the 43 years since commencement of operation of Calder Hall, the first Magnox power station, there remain eight Magnox stations and 20 reactors still in operation, owned by BNFL Magnox Generation. This paper describes how the operational safety performance of these stations has significantly improved over the last ten years. This has been achieved against a background of commercial competition introduced by privatization and despite the fact that the Magnox base design belongs to the past. Finally, the company's future plans for continued improvements in operational safety performance are discussed. (author)

  2. Dealing with operational power station wastes

    Energy Technology Data Exchange (ETDEWEB)

    Pepper, R B [Central Electricity Generating Board, London (UK). Nuclear Health and Safety Dept.

    1981-08-01

    The disposal of wastes from nuclear power stations is discussed. Liquid and gaseous wastes, from magnox stations, which are of low level activity, are dispersed to the sea or estuaries on coastal sites or for the case of Trawfynyeld, to the nearby lake. Low activity solid wastes are either disposed of on local authority tips or in shallow land burial sites. Intermediate level wastes, consisting mainly of wet materials such as filter sludges and resins from cooling ponds, are at present stored in shielded storage tanks either dry or under water. Only one disposal route for intermediate waste is used by Britain, namely, sea-dumping. Materials for sea dumping have to be encapsulated in a durable material for example, concrete.

  3. Space station operations task force. Panel 4 report: Management integration

    Science.gov (United States)

    1987-01-01

    The Management Integration Panel of the Space Station Operations Task Force was chartered to provide a structure and ground rules for integrating the efforts of the other three panels and to address a number of cross cutting issues that affect all areas of space station operations. Issues addressed include operations concept implementation, alternatives development and integration process, strategic policy issues and options, and program management emphasis areas.

  4. An Operations Management System for the Space Station

    Science.gov (United States)

    Rosenthal, H. G.

    1986-09-01

    This paper presents an overview of the conceptual design of an integrated onboard Operations Management System (OMS). Both hardware and software concepts are presented and the integrated space station network is discussed. It is shown that using currently available software technology, an integrated software solution for Space Station management and control, implemented with OMS software, is feasible.

  5. Training of engineers for nuclear power station operation

    International Nuclear Information System (INIS)

    Myerscough, P.B.

    1980-01-01

    The requirements for staffing and training of a nuclear electric utility are described. Current training facilities at the Central Electricity Generating Board are applicable to gas-cooled technology with the possibility of the introduction of a thermal water system and fast reactors in the future. The CEGB training centres provide for the initial training of operational staff, revision training of experienced operational staff, and training of non-operational staff from the stations and supporting departments. Details are given of the content of the training courses which also provide simulation facilities of the basic dynamics of the CEGB stations. Further developments in simulation will include dynamics of the boiler and turbine plants in Magnox stations. The flexibility of the AGR simulations will enable the training exercises to be adjusted to meet changing operating patterns for each AGR station. (U.K.)

  6. National Geospatial Data Asset (NGDA) Continuously Operating Reference Stations (CORS)

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — The National Geodetic Survey (NGS), an office of NOAA's National Ocean Service, manages a network of Continuously Operating Reference Stations (CORS) that provide...

  7. Elements of an advanced integrated operator control station

    International Nuclear Information System (INIS)

    Clarke, M.M.; Kreifeldt, J.G.

    1984-01-01

    One of the critical determinants of performance for any remotely operated maintenance system is the compatibility achieved between elements of the man/machine interface (e.g., master manipulator controller, controls, displays) and the human operator. In the remote control engineering task of the Consolidated Fuel Reprocessing Program, considerable attention has been devoted to optimizing the man/machine interface of the operator control station. This system must be considered an integral element of the overall maintenance work system which includes transporters, manipulators, remote viewing, and other parts. The control station must reflect the integration of the operator team, control/display panels, manipulator master controllers, and remote viewing monitors. Human factors principles and experimentation have been used in the development of an advanced integrated operator control station designed for the advance servomanipulator. Key features of this next-generation design are summarized in this presentation. 7 references, 4 figures

  8. Elements of an advanced integrated operator control station

    International Nuclear Information System (INIS)

    Clarke, M.M.; Kreifeldt, J.G.

    1984-01-01

    One of the critical determinants of peformance for any remotely operated maintenance system is the compatibility achieved between elements of the man/machine interface (e.g., master manipulator controller, controls, displays, etc.) and the human operator. In the Remote Control Engineering task of the Consolidated Fuel Reprocessing Program, considerable attention has been devoted to optimizing the man/machine interface of the operator control station. This system must be considered an integral element of the overall maintenance work system which includes transporters, manipulators, remote viewing, and other parts. The control station must reflect the integration of the operator team, control/display panels, manipulator master controllers, and remote viewing monitors. Human factors principles and experimentation have been used in the development of an advanced integrated operator control station designed for the advance servomanipulator. Key features of this next-generation design are summarized in this presentation. 7 references, 4 figures

  9. (Shippingport Atomic Power Station). Quarterly operating report, third quarter 1980

    Energy Technology Data Exchange (ETDEWEB)

    Zagorski, J. F.

    1980-01-01

    At the beginning of the third quarter of 1980, the Shippingport Atomic Power Station was operating with the 1A, 1B, 1C, and 1D reactor coolant loops and the 1AC and 1BD purification loops in service. During the quarter, the Station was operated for Duquesne Light Company System grid including base load and swing load operation. Twelve (12) planned swing load operations were performed on the LWBR Core this quarter to complete the LWBR operating plan of fifty (50) during this operating phase. The Station was shutdown on September 12 for the Fall 1980 Shutdown and remained in this mode through the end of the quarter. The LWBR Core has generated 18,297.98 EFPH from start-up through the end of the quarter. There were no radioactive liquid discharges from the Radioactive Waste Processing System to the river this quarter. The radioactive liquid waste effluent line to the river remained blanked off to prevent inadvertent radioactive liquid waste discharges. During the quarter, approximately 0.001 curies of Xe 133 activity were released from the station. The radioactivity released from Shippingport Station is far too small to have any measurable effect on the general background environmental radioactivity outside the plant.

  10. Operation of nuclear power stations during 1975

    International Nuclear Information System (INIS)

    1976-08-01

    In 1975, the production of nuclear energy in the Community of the Nine was 77 thousand million net kWh, an increase of 26.5% over 1974. A short commentry explains this large increase and the situation in each country is briefly reviewed. Then data on the evolution of net production (partitioned according to reactor family), on the availability of reactor types according to their age, and on the structure of nuclear plants (situation at the end of 1975) are presented. The statistical data of annual operation are given for each reactor

  11. Development of a Space Station Operations Management System

    Science.gov (United States)

    Brandli, A. E.; McCandless, W. T.

    To enhance the productivity of operations aboard the Space Station, a means must be provided to augment, and frequently to supplant, human effort in support of mission operations and management, both on the ground and onboard. The Operations Management System (OMS), under development at the Johnson Space Center, is one such means. OMS comprises the tools and procedures to facilitate automation of station monitoring, control, and mission planning tasks. OMS mechanizes, and hence rationalizes, execution of tasks traditionally performed by mission planners, the mission control center team, onboard System Management software, and the flight crew.

  12. Development of a Space Station Operations Management System

    Science.gov (United States)

    Brandli, A. E.; Mccandless, W. T.

    1988-01-01

    To enhance the productivity of operations aboard the Space Station, a means must be provided to augment, and frequently to supplant, human effort in support of mission operations and management, both on the ground and onboard. The Operations Management System (OMS), under development at the Johnson Space Center, is one such means. OMS comprises the tools and procedures to facilitate automation of station monitoring, control, and mission planning tasks. OMS mechanizes, and hence rationalizes, execution of tasks traditionally performed by mission planners, the mission control center team, onboard System Management software, and the flight crew.

  13. Analytical modeling of nuclear power station operator reliability

    International Nuclear Information System (INIS)

    Sabri, Z.A.; Husseiny, A.A.

    1979-01-01

    The operator-plant interface is a critical component of power stations which requires the formulation of mathematical models to be applied in plant reliability analysis. The human model introduced here is based on cybernetic interactions and allows for use of available data from psychological experiments, hot and cold training and normal operation. The operator model is identified and integrated in the control and protection systems. The availability and reliability are given for different segments of the operator task and for specific periods of the operator life: namely, training, operation and vigilance or near retirement periods. The results can be easily and directly incorporated in system reliability analysis. (author)

  14. Operation of the UK Magnox Stations in a competitive market

    International Nuclear Information System (INIS)

    Corrigan, A.

    2000-01-01

    In 1955 the UK Government announced the first major civil nuclear power plant construction programme based on the Magnox design of reactor. This was followed in 1956 with the commencement of operation of Calder Hall, the world's first nuclear power station. The initial programme was for the construction of 1 500-2 000 MW of plant but, with the success of the early stations, this was increased to 5 000 MW by 1960. In total 11 Magnox nuclear power stations were commissioned in the UK over the period 1956 to 1971, comprising a total of 26 reactors (see Table 1). At present 20 of the reactors remain in operation, with an average life of 37 years. Output from the stations has been steady for many years and they have been regarded as the workhorses of the electricity generation industry in the UK. In 1990 the electricity supply and distribution system was deregulated and a market system introduced which has led to a reduction in the sale price of electricity. In addition to this it has been necessary to invest in the plants to maintain safety levels and operational reliability. The plant's can only continue in operation provided they remain safe and economic. This paper will review recent experience with the life management of the Magnox stations. (author)

  15. 47 CFR 25.137 - Application requirements for earth stations operating with non-U.S. licensed space stations.

    Science.gov (United States)

    2010-10-01

    ... space stations. (a) Earth station applicants or entities filing a “letter of intent” or “Petition for... Union. (d) Earth station applicants requesting authority to operate with a non-U.S.-licensed space... 47 Telecommunication 2 2010-10-01 2010-10-01 false Application requirements for earth stations...

  16. Role of check operators in achieving operational excellence at Virginia Power's nuclear stations

    International Nuclear Information System (INIS)

    Shriver, B.L.; Williams, T.M.; Stewart, W.L.

    1987-01-01

    Virginia Power has implemented a Check Operator Program as a part of its commitment to excellence in the operation of the North Anna and Surry nuclear power stations. The Check Operator Program utilizes highly qualified licensed personnel to independently evaluate the performance of licensed operators and senior operators during normal, abnormal and simulated emergency conditions. Emphasis is placed upon individual and team performance as well as the procedures and training which support the operators. The check operators report to line management to ensure that their recommendations are implemented into the overall operations philosophy of the power station

  17. Experiences of operation for Ikata Nuclear Power Station

    International Nuclear Information System (INIS)

    Kashimoto, Shigeyuki

    1979-01-01

    No. 1 plant in the Ikata Nuclear Power Station, Shikoku Electric Power Co., Inc., is a two-loop PWR unit with electric output of 566 MW, and it began the commercial operation on September 30, 1977, as the first nuclear power station in Shikoku. It is the 13th LWR and 7th PWR in Japan. The period of construction was 52 months since it had been started in June, 1973. During the period, it became the object of the first administrative litigation to seek the cancellation of permission to install the reactor, and it was subjected to the influence of the violent economical variation due to the oil shock, but it was completed as scheduled. After the start of operation, it continued the satisfactory operation, and generated about 2.35 billion KWh for 4300 operation hours. It achieved the rate of utilization of 96.7%. Since March 28, 1978, the first periodical inspection was carried out, and abnormality was not found in the reactor, the steam generator and the fuel at all. The period of inspection was 79 days and shorter than expected. The commercial operation was started again on June 14. The outline of the Ikata Nuclear Power Station, its state of operation, and the periodical inspection are reported. Very good results were able to be reported on the operation for one year, thanks to the valuable experiences offered by other electric power companies. (Kako, I.)

  18. Operational characteristics of pediatric radiology: Image display stations

    International Nuclear Information System (INIS)

    Taira, R.K.

    1987-01-01

    The display of diagnostic images is accomplished in the UCLA Pediatric Radiology Clinical Radiology Imaging System (CRIS) using 3 different types of digital viewing stations. These include a low resolution station with six 512 x 512 monitors, a high resolution station with three 1024 x 1024 monitors, and a very high resolution workstation with two 2048 x 2048 monitors. The display stations provide very basic image processing manipulations including zoom and scroll, contrast enhancement, and contrast reversal. The display stations are driven by a computer system which is dedicated for clinical use. During times when the clinical computer is unavailable (maintenance or system malfunction), the 512 x 512 workstation can be switched to operate from a research PACS system in the UCLA Image Processing Laboratory via a broadband communication network. Our initial clinical implementation involves digital viewing for pediatric radiology conferences. Presentation of inpatient cases use the six monitor 512 x 512 multiple viewing station. Later stages of the clinical implementation involve the use of higher resolution displays for the purpose of primary diagnosis from video displays

  19. Training of technical staff for nuclear power station operation

    International Nuclear Information System (INIS)

    Haire, T.P.; Myerscough, P.B.

    1981-01-01

    The statutory training requirements covering the technical staff in the CEGB (Central Electricity Generating Board) are discussed. Details of the training programmes emphasize the importance of the staff having a thorough understanding of the nuclear processes involved in the station operation and not relying solely upon a mechanistic approach to operating procedures. The impact of this philosophy on the design of training simulators is examined and a brief comparison is made with the training philosophies in other countries. (U.K.)

  20. Operator Station Design System - A computer aided design approach to work station layout

    Science.gov (United States)

    Lewis, J. L.

    1979-01-01

    The Operator Station Design System is resident in NASA's Johnson Space Center Spacecraft Design Division Performance Laboratory. It includes stand-alone minicomputer hardware and Panel Layout Automated Interactive Design and Crew Station Assessment of Reach software. The data base consists of the Shuttle Transportation System Orbiter Crew Compartment (in part), the Orbiter payload bay and remote manipulator (in part), and various anthropometric populations. The system is utilized to provide panel layouts, assess reach and vision, determine interference and fit problems early in the design phase, study design applications as a function of anthropometric and mission requirements, and to accomplish conceptual design to support advanced study efforts.

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

    International Nuclear Information System (INIS)

    Wieman, J.L.

    1995-01-01

    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.) [de

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

    International Nuclear Information System (INIS)

    1976-01-01

    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

  3. Operations planning for Space Station Freedom - And beyond

    Science.gov (United States)

    Gibson, Stephen S.; Martin, Thomas E.; Durham, H. J.

    1992-01-01

    The potential of automated planning and electronic execution systems for enhancing operations on board Space Station Freedom (SSF) are discussed. To exploit this potential the Operations Planning and Scheduling Subsystem is being developed at the NASA Johnson Space Center. Such systems may also make valuable contributions to the operation of resource-constrained, long-duration space habitats of the future. Points that should be considered during the design of future long-duration manned space missions are discussed. Early development of a detailed operations concept as an end-to-end mission description offers a basis for iterative design evaluation, refinement, and option comparison, particularly when used with an advanced operations planning system capable of modeling the operations and resource constraints of the proposed designs.

  4. Operating experience and performance at Narora Atomic Power Station

    International Nuclear Information System (INIS)

    Mittal, Subhash; Gupta, J.P.

    1998-01-01

    Narora Atomic Power Station consists of two units of 220 MWe capacity each. These are Pressurized Heavy Water Reactors, fuelled by natural uranium, moderated and cooled by heavy water. The Station is owned by Nuclear Power Corporation of India Ltd., which is responsible for design, construction, commissioning, and operation of all nuclear power stations in the country. NAPS was the first opportunity to apply operating experiences in design, keeping in view the evolving safety and seismicity requirements, ease of maintenance, inservice inspection needs, improved construction ability and standardization. Both the units of NAPS are having improved safety standards of current international levels. All the equipment are indigenous with improved quality and reliability. The first unit of the station went critical in March 1989 and synchronized to the grid in July 1989. The second units followed with its criticality in October 1991 and synchronization in January 1992. Considering the initial stabilizing period, the performance of both units of NAPS has progressively improved over the years. The annual capacity factor for NAPS - 1 was 90.01% and for NAPS - 2 was 89.01% for the financial year 1997-1998. This paper presents an analysis of the performance during the last three years and measures taken to improve it. The stated enhanced performance could be achieved by improvement in human performance by training/re-training, scrupulous monitoring and review of equipment/systems, institution of adequate procedure and ensuring their adherence. (authors)

  5. Space station automation and robotics study. Operator-systems interface

    Science.gov (United States)

    1984-01-01

    This is the final report of a Space Station Automation and Robotics Planning Study, which was a joint project of the Boeing Aerospace Company, Boeing Commercial Airplane Company, and Boeing Computer Services Company. The study is in support of the Advanced Technology Advisory Committee established by NASA in accordance with a mandate by the U.S. Congress. Boeing support complements that provided to the NASA Contractor study team by four aerospace contractors, the Stanford Research Institute (SRI), and the California Space Institute. This study identifies automation and robotics (A&R) technologies that can be advanced by requirements levied by the Space Station Program. The methodology used in the study is to establish functional requirements for the operator system interface (OSI), establish the technologies needed to meet these requirements, and to forecast the availability of these technologies. The OSI would perform path planning, tracking and control, object recognition, fault detection and correction, and plan modifications in connection with extravehicular (EV) robot operations.

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

    International Nuclear Information System (INIS)

    Fang Chunfa

    2000-01-01

    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

  7. The Chooz power station: ten years of operation

    International Nuclear Information System (INIS)

    Teste du Bailler, Andre

    1977-01-01

    The switching into actual service of the Chooz plant, the first pressurized water reactor ever built in France, occurred on 3rd april 1967. Ten years later, one can establish a highly positive balance schedule of plant's operation whose availability is satisfactory, except the mechanical failure which occurred during the startup. The behavior of the equipment, in particular of the components of the primary loop, was satisfactory in its whole since it allowed the gradual increase in capacity by 15% with respect to the initial design. It allowed also the achievment of noticeable progress in the design of equipment intended for the new power stations. Interesting results have also been obtained in radioprotection, working conditions of the staff and environment protection fields. Finally, the training of the operating teams has been closely followed, whether it concerned the operators directly affected by plant operation or the trainees gathered in a school specially organized for this purpose and transferred since to a training Center [fr

  8. Operational results in the Onagawa Nuclear Power Station

    International Nuclear Information System (INIS)

    Hasegawa, Kanichi; Kato, Katsuya; Terada, Hideo; Kamata, Takakage; Kaimura, Yoshiharu

    1986-01-01

    In the Onagawa Nuclear Power Station, Unit 1 (BWR type, with electric output 524 MW) started operation in June 1, 1984. The power plant has then continued non-stop operation up to April 2, 1985, thus exhibiting its base load plant. In fiscal 1984, the continuous operation is for 342 days; the capacity factor is about 96.1 %, which is the world's top. During the period, the radioactivity releases to the environment in both liquid and gaseous wastes are below the detection limits. The collective exposure dose for plant personnel is merely 6 man-rem. Subsequently, its 1st periodical inspection was started on April 3, 1985, and finished in July the same year. So, the power plant is now again in operation. (Mori, K.)

  9. (Shippingport Atomic Power Station). Quarterly operating report, fourth quarter 1980

    Energy Technology Data Exchange (ETDEWEB)

    1980-01-01

    At the beginning of the fourth quarter of 1980, the Shippingport Atomic Power Station remained shutdown for the normally planned semiannual maintenance and testing program, initiated September 12, 1980. Operational testing began on November 7. Maximum power was achieved November 28 and was maintained throughout the remainder of the quarter except as noted. The LWBR Core has generated 19,046.07 EFPH from start-up through the end of the quarter. During this quarter, approximately 0.000025 curies of Xe 133 activity were released from the station. During the fourth quarter of 1980, 1081 cubic feet of radioactive solid waste was shipped out of state for burial. These shipments contained 0.037 curies of radioactivity.

  10. Commissioning and operation of the CEBAF end station refrigeration system

    International Nuclear Information System (INIS)

    Arenius, D.; Bevins, B.; Chronis, W.C.; Ganni, V.

    1996-01-01

    The CEBAF End Station Helium Refrigerator (ESR) System provides refrigeration at 80 K, 20 K and 4.5 K to three End Station experimental halls. The facility consists of a two stage helium screw compressor system, 4.5 K refrigerator, cryogen distribution valve box, and transfer lines to the individual experimental halls. The 4.5 K cold box and compressors were originally part of the ESCAR 1500 W, 4 K refrigeration system at Lawrence Berkeley Laboratory which was first commissioned in 1977. The compressors, 4.5 K cold box, and control system design were modified to adapt the plant for the requirements of the CEBAF experimental halls. Additional subsystems of cryogen distribution, transfer lines, warm gas management, and computer control interface were added. This paper describes the major plant subsystems, modifications, operational experiences and performance

  11. International Cooperation of Payload Operations on the International Space Station

    Science.gov (United States)

    Melton, Tina; Onken, Jay

    2003-01-01

    One of the primary goals of the International Space Station (ISS) is to provide an orbiting laboratory to be used to conduct scientific research and commercial products utilizing the unique environment of space. The ISS Program has united multiple nations into a coalition with the objective of developing and outfitting this orbiting laboratory and sharing in the utilization of the resources available. The primary objectives of the real- time integration of ISS payload operations are to ensure safe operations of payloads, to avoid mutual interference between payloads and onboard systems, to monitor the use of integrated station resources and to increase the total effectiveness of ISS. The ISS organizational architecture has provided for the distribution of operations planning and execution functions to the organizations with expertise to perform each function. Each IPP is responsible for the integration and operations of their payloads within their resource allocations and the safety requirements defined by the joint program. Another area of international cooperation is the sharing in the development and on- orbit utilization of unique payload facilities. An example of this cooperation is the Microgravity Science Glovebox. The hardware was developed by ESA and provided to NASA as part of a barter arrangement.

  12. French experience in operating pressurized water reactor power stations. Ten years' operation of the Ardennes power station

    International Nuclear Information System (INIS)

    Teste du Bailler, A.; Vedrinne, J.F.

    1978-01-01

    In the paper the experience gained over ten years' operation of the Ardennes (Chooz) nuclear power station is summarized from the point of view of monitoring and control equipment. The reactor was the first pressurized water reactor to be installed in France; it is operated jointly by France and Belgium. The equipment, which in many cases consists of prototypes, was developed for industrial use and with the experience that has now been gained it is possible to evaluate its qualities and defects, the constraints which it imposes and the action that has to be taken in the future. (author)

  13. How the Station will operate. [operation, management, and maintenance in space

    Science.gov (United States)

    Cox, John T.

    1988-01-01

    Aspects of the upcoming operational phase of the Space Station (SS) are examined. What the crew members will do with their time in their specialized roles is addressed. SS maintenance and servicing and the interaction of the SS Control Center with Johnson Space Center is discussed. The planning of payload operations and strategic planning for the SS are examined.

  14. CO2 on the International Space Station: An Operations Update

    Science.gov (United States)

    Law, Jennifer; Alexander, David

    2016-01-01

    PROBLEM STATEMENT: We describe CO2 symptoms that have been reported recently by crewmembers on the International Space Station and our continuing efforts to control CO2 to lower levels than historically accepted. BACKGROUND: Throughout the International Space Station (ISS) program, anecdotal reports have suggested that crewmembers develop CO2-related symptoms at lower CO2 levels than would be expected terrestrially. Since 2010, operational limits have controlled the 24-hour average CO2 to 4.0 mm Hg, or below as driven by crew symptomatology. In recent years, largely due to increasing awareness by crew and ground team, there have been increased reports of crew symptoms. The aim of this presentation is to discuss recent observations and operational impacts to lower CO2 levels on the ISS. CASE PRESENTATION: Crewmembers are routinely asked about CO2 symptoms in their weekly private medical conferences with their crew surgeons. In recent ISS expeditions, crewmembers have noted symptoms attributable to CO2 starting at 2.3 mmHg. Between 2.3 - 2.7 mm Hg, fatigue and full-headedness have been reported. Between 2.7 - 3.0 mm Hg, there have been self-reports of procedure missed steps or procedures going long. Above 3.0 - 3.4 mm Hg, headaches have been reported. A wide range of inter- and intra-individual variability in sensitivity to CO2 have been noted. OPERATIONAL / CLINICAL RELEVANCE: These preliminary data provide semi-quantitative ranges that have been used to inform a new operational limit of 3.0 mmHg as a compromise between systems capabilities and the recognition that there are human health and performance impacts at recent ISS CO2 levels. Current evidence would suggest that an operational limit between 0.5 and 2.0 mm Hg may maintain health and performance. Future work is needed to establish long-term ISS and future vehicle operational limits.

  15. Operational considerations for the Space Station Life Science Glovebox

    Science.gov (United States)

    Rasmussen, Daryl N.; Bosley, John J.; Vogelsong, Kristofer; Schnepp, Tery A.; Phillips, Robert W.

    1988-01-01

    The U.S. Laboratory (USL) module on Space Station will house a biological research facility for multidisciplinary research using living plant and animal specimens. Environmentally closed chambers isolate the specimen habitats, but specimens must be removed from these chambers during research procedures as well as while the chambers are being cleaned. An enclosed, sealed Life Science Glovebox (LSG) is the only locale in the USL where specimens can be accessed by crew members. This paper discusses the key science, engineering and operational considerations and constraints involving the LSG, such as bioisolation, accessibility, and functional versatility.

  16. On Chinese National Continuous Operating Reference Station System of GNSS

    Directory of Open Access Journals (Sweden)

    CHEN Junyong

    2007-11-01

    Full Text Available Objective: Global navigation satellite system (GNSS Continuous Operating Reference Station (CORS System can maintain a accurate, 3D, geocentric and dynamic reference coordinate frame in the corresponding area, can provide positioning and navigation service. It can also serve for the meteorology, geodynamics, earthquake monitoring and Location Based services (LBS etc in the same area. Until now, our country can’t provide a facing National CORS System serving for every profession and trade, and the national sharing platform of CORS System resources has not been established. So this paper discusses some valuable insight how to construct the National CORS System in China. Method: Constructing goal、Service object、CORS distribution、CORS geographic、geology and communication environment and other factors, are major considerations for the Constructing the National CORS System. Moreover, constructing GNSS CORS is more specific, mainly from four aspects, namely site-selection、civil construction、security measures and equipment-selection for consideration. Outcome: The project of the Constructing Global navigation satellite system (GNSS Continuous Operating Reference Station (CORS System in china is put forward, and is discussed from goal、principle、project and other for construction. Some meaning thought how to construct the National CORS System is submitted Conclusion: The Global navigation satellite system (GNSS Continuous Operating Reference Station (CORS System in china is the lack of a unified planning and design in the national level. So far, the national CORS system serving all walks of life has not been provided, and the national sharing platform of CORS System resources has not been established The primary mission of the Global navigation satellite system (GNSS Continuous Operating Reference Station (CORS System in china is as follows: using data set of GNSS and receiving, transport, process, integration, transmit information and

  17. Operating Experience at the Aagesta Nuclear Power Station

    International Nuclear Information System (INIS)

    Sandstroem, S.

    1966-09-01

    Sweden's first nuclear power reactor Agesta, achieved criticality on July 17, 1963. Full power (65 MW t ) 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

  18. Operating Experience at the Aagesta Nuclear Power Station

    Energy Technology Data Exchange (ETDEWEB)

    Sandstroem, S [ed.

    1966-09-15

    Sweden's first nuclear power reactor Agesta, achieved criticality on July 17, 1963. Full power (65 MW{sub t}) 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.

  19. Operating Experience at the Aagesta Nuclear Power Station

    Energy Technology Data Exchange (ETDEWEB)

    Sandstroem, S. (ed.)

    1966-09-15

    Sweden's first nuclear power reactor Agesta, achieved criticality on July 17, 1963. Full power (65 MW{sub t}) 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.

  20. 47 CFR 90.1331 - Restrictions on the operation of base and fixed stations.

    Science.gov (United States)

    2010-10-01

    ...-3700 MHz Band § 90.1331 Restrictions on the operation of base and fixed stations. (a)(1) Except as provided in paragraph (a)(2) of this section, base and fixed stations may not be located within 150 km of... these stations are available at http://www.fcc.gov/ib/sd/3650/. (2) Base and fixed stations may be...

  1. Space station operations task force. Panel 3 report: User development and integration

    Science.gov (United States)

    1987-01-01

    The User Development and Integration Panel of the Space Station Operations Task Force was chartered to develop concepts relating to the operations of the Space Station manned base and the platforms, user accommodation and integration activities. The needs of the user community are addressed in the context with the mature operations phase of the Space Station. Issues addressed include space station pricing options, marketing strategies, payload selection and resource allocation options, and manifesting techniques.

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

    International Nuclear Information System (INIS)

    Xu Pingsheng

    2007-01-01

    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)

  3. Shippingport Atomic Power Station Operating Experience, Developments and Future Plans

    International Nuclear Information System (INIS)

    Feinroth, H.; Oldham, G.M.; Stiefel, J.T.

    1963-01-01

    This paper describes and evaluates five years of operation and test of the Shippingport Atomic Power Station and discusses the current technical developments and future plans of the Shippingport programme. This programme is directed towards development of the basic technology of light-water reactors to provide the basis for potential reduction in the costs of nuclear power. The Shippingport reactor plant has operated for over five years and has been found to integrate readily into a utility system either as a base load or peak load unit. Plant component performance has been reliable. There have been no problems in contamination or waste disposal. Access to primary coolant components for maintenance has been good, demonstrating the integrity of fuel elements. Each of the three refuelling operations performed since start-up of Shippingport has required successively less time to accomplish. Recently, the third seed was refuelled in 32 working days, about one quarter the time required for the first refuelling. The formal requirements of personnel training, written administrative procedures, power plant manuals, etc., which have been a vital factor in the successful implementation of the Shippingport programme, are described. The results obtained from the comprehensive test programme carried out at Shippingport are compared with calculations, and good agreement has been obtained. Reactor core performance, plant stability, and response to load changes, fuel element and control rod performance, long-term effects such as corrosion and radiation level build-up, component performance, etc., are discussed in this paper. The principal objective of the current and future programmes of the Shippingport Project in advancing the basic technology of water-cooled reactors is discussed. This programme includes the continued operation of the Shippingport plant, and the development, design, manufacture and test operation of a long-life, highpower density second core - Core 2. At its

  4. Establishment and evaluation of operation function model for cascade hydropower station

    OpenAIRE

    Chang-ming Ji; Ting Zhou; Hai-tao Huang

    2010-01-01

    Toward solving the actual operation problems of cascade hydropower stations under hydrologic uncertainty, this paper presents the process of extraction of statistical characteristics from long-term optimal cascade operation, and proposes a monthly operation function algorithm for the actual operation of cascade hydropower stations through the identification, processing, and screening of available information during long-term optimal operation. Applying the operation function to the cascade hy...

  5. BR3/Vulcain Nuclear Power Station. Construction and Operational Experience

    Energy Technology Data Exchange (ETDEWEB)

    Storrer, J. [Belgonucleaire, S.A., Brussels (Belgium)

    1968-04-15

    power density of 41 MW(th)t U. The expected average fuel burnup and core life are 25 000 MWd/t U and 620 equivalent full-power days, respectively. These characteristics have been achieved without taking advantage of various improvements - such as the possibility of flattening the power distribution in the core by the use of two or more fuel enrichments - which are planned for more advanced Vulcain cores. The successful construction and operation of BR3/Vulcain will have demonstrated that components and techniques are available to build and operate simple, compact reactors in the small to medium power range, using long-life, high-power density cores and variable moderation. From the analyses carried out so far this concept competes well with other reactor concepts, while market surveys have indicated that there is a world market for small to medium power stations at prices within reach of those currently mentioned for the Vulcain design. (author)

  6. Shippingport Atomic Power Station. Quarterly operating report, third quarter 1978

    Energy Technology Data Exchange (ETDEWEB)

    Jones, T. D.

    1978-01-01

    A loss of ac power to the station occurred on July 28, 1978 caused by an interaction between Beaver Valley Power Station and Shippingport Atomic Power Station when the main transformer of Unit No. 1 of the Beaver Valley Power Station developed an internal failure and tripped the BVPS. Two environmental studies were continued this quarter. The first involves reduction of main unit condenser chlorination and the second, river intake screen fish impingement sampling. There were no radioactive liquid discharges from the Radioactive Waste Processing System to the river this quarter. During the third quarter of 1978, 874 cubic feet of radioactive solid waste was shipped out of state for burial. At the end of the quarter, the Fall shutdown continued with the plant heated up, the main turbine on turning gear and plant testing in progress prior to Station startup.

  7. Leadership and Cultural Challenges in Operating the International Space Station

    Science.gov (United States)

    Clement, J. L.; Ritsher, J. B.; Saylor, S. A.; Kanas, N.

    2006-01-01

    Operating the International Space Station (ISS) involves an indefinite, continuous series of long-duration international missions, and this requires an unprecedented degree of cooperation across multiple sites, organizations, and nations. ISS flight controllers have had to find ways to maintain effective team performance in this challenging new context. The goal of this study was to systematically identify and evaluate the major leadership and cultural challenges faces by ISS flight controllers, and to highlight the approaches that they have found most effective to surmount these challenges. We conducted a qualitative survey using a semi-structured interview. Subjects included 14 senior NASA flight controllers who were chosen on the basis of having had substantial experience working with international partners. Data were content analyzed using an iterative process with multiple coders and consensus meetings to resolve discrepancies. To further explore the meaning of the interview findings, we also conducted some new analyses of data from a previous questionnaire study of Russian and American ISS mission control personnel. The interview data showed that respondents had substantial consensus on several leadership and cultural challenges and on key strategies for dealing with them, and they offered a wide range of specific tactics for implementing these strategies. Surprisingly few respondents offered strategies for addressing the challenge of working with team members whose native language is not American English. The questionnaire data showed that Americans think it is more important than Russians that mission control personnel speak the same dialect of one shared common language. Although specific to the ISS program, our results are consistent with recent management, cultural, and aerospace research. We aim to use our results to improve training for current and future ISS flight controllers.

  8. A 31-day battery-operated recording weather station.

    Science.gov (United States)

    Richard J. Barney

    1972-01-01

    The battery-powered recording weather station measures and records wet bulb temperature, dry bulb temperature, wind travel, and rainfall for 31 days. Assembly procedures and cost of supplies and components are discussed.

  9. The training and assessment of operations engineers at Hinkley Point 'B' nuclear power station

    International Nuclear Information System (INIS)

    Walsey, B.A.; Howard, J.D.

    1986-01-01

    The Nuclear Power Training Centre at Oldbury-on-Severn was established to provide a common training of staff at all nuclear power stations operated by the Central Electricity Generating Board, following the ''Standard Specification for the Nuclear Training of Staff at CEGB Nuclear Power Stations''. The paper deals with the following aspects of AGR Stations: The Legislation applicable to these stations. The current training requirements for Operations Staff. The development of training for operations staff at Hinkley Point 'B' including training for career progression within the Operations Department. A detailed explanation of the training package developed for Reactor Desk Drivers at Hinkley 'B'. Revision training of Operations staff to ensure that they continue to run the plant in a safe and commercially viable manner. The training of Shift Operations Engineers for their duties under the Station Emergency Plan. (author)

  10. 29 CFR 4.122 - Contracts for operation of postal contract stations.

    Science.gov (United States)

    2010-07-01

    ... Application of the McNamara-O'Hara Service Contract Act Specific Exclusions § 4.122 Contracts for operation of postal contract stations. The Act, in paragraph (7) of section 7, exempts from its provisions “any... 29 Labor 1 2010-07-01 2010-07-01 true Contracts for operation of postal contract stations. 4.122...

  11. 78 FR 40519 - Cooper Nuclear Station; Application and Amendment to Facility Operating License Involving...

    Science.gov (United States)

    2013-07-05

    ... NUCLEAR REGULATORY COMMISSION [Docket No. 50-298; NRC-2013-0139] Cooper Nuclear Station; Application and Amendment to Facility Operating License Involving Proposed No Significant Hazards..., issued to Nebraska Public Power District (the licensee), for operation of the Cooper Nuclear Station (CNS...

  12. Monitoring of the operation of a nuclear power station with design problems in an importing country: The Almaraz power station

    International Nuclear Information System (INIS)

    Reig, J.

    1984-01-01

    The purpose of this paper is to describe the regulatory activities carried out in Spain as a result of the design problem occurring in the steam generators during operation of Unit I of the Almaraz nuclear power station. First, a brief introduction is given to the operating history and characteristics of Unit I of Almaraz. Particular attention is paid to the specific licences issued subsequent to commercial operation which place limitations on the operation of the station and to the operational incidents of which the Nuclear Safety Council (CSN) has been notified. Next, a description is provided of the safety evaluation carried out by the CSN. Three aspects merit particular attention: methodology, evaluation and conclusions. The methodology applied by an importing country is normally based on that of the country of origin of the design, so that the overall evaluation by the NRC has been considered sufficiently representative of aspects specific to the Almaraz power station. In this regard the importance of international collaboration is clearly seen as a principal instrument for performing the evaluation. In the evaluation a distinction is made between general and specific aspects and between inspection programmes and quality assurance requirements. In addition, the conclusions leading to the requirement of the imposition of additional limitations on the operating licence are stated. Apart from the safety evaluation carried out by the CSN, other regulatory activities have been performed over this two-year period. These activities, which include site inspections, audits of the principal supplier company, other independent calculations and so on, are described. Lastly, the paper refers to the lessons learned from the operation of the above-mentioned unit, which are immediately applicable to other Spanish nuclear power stations. (author)

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

    International Nuclear Information System (INIS)

    Kueffer, K. von.

    1976-01-01

    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.)

  14. Enhanced methods for operating refueling station tube-trailers to reduce refueling cost

    Science.gov (United States)

    Elgowainy, Amgad; Reddi, Krishna

    2017-08-22

    A method and apparatus are provided for operating a refueling station including source tube-trailers and at least one compressor to reduce refueling cost. The refueling station includes a gaseous fuel supply source including a plurality of tanks on a tube trailer coupled to a first control unit, and high pressure buffer storage having predefined capacity coupled to a second control unit and the first tanks by a pressure control valve and the first control unit, and at least one compressor. The refueling station is operated at different modes depending on a state of the refueling station at the beginning of each operational mode. The refueling system is assessed at the end of each operational mode to identify the state of the system and select a next mode of operation. The operational modes include consolidating hydrogen, or any gaseous fuel, within the tubes mounted on the trailer.

  15. Study of Naval Air Station Operations to Reduce Fuel Consumption

    Science.gov (United States)

    2014-06-01

    reasons and loyalty of frequent business customers , schedules rarely change significantly from week to week. Following the schedule generation, aircraft...Air Station ppm pounds per minute xiv rft ready for tasking SHARP Sierra Hotel Aviation Readiness Program Simio Simulation Modeling Framework...America, the U.S. airline industry experienced a total of $7.18 billion in delay costs in 2013 at an average cost per minute of $78.17 (Airlines

  16. Cause trending analysis for licensing operational events in Daya Bay Nuclear Power Station

    International Nuclear Information System (INIS)

    Wang Dewei

    2005-01-01

    The human causal factors for all human error licensing operational events on Daya Bay nuclear power station since 1993 to 2003 are categorized, the trend of these causal factors is analyzed. The emphasis is placed on analyzing the deficiencies on complying with and executing regulations and procedures. The results provide directional reference for nuclear power station to improve human performance. (author)

  17. (Shippingport Atomic Power Station). Quarterly operating report, third quarter 1979

    Energy Technology Data Exchange (ETDEWEB)

    Jones, T. D.

    1979-01-01

    At the beginning of the third quarter of 1979, the Shippingport Atomic Power Station remained shutdown to complete repairs of the turbine generator hydrogen circulation fan following discovery of a rubbing noise on May 24, 1979. The Station was in a cooldown condition at approximately 180/sup 0/F and 300 psig with a steam bubble in the pressurizer and the reactor coolant pumps in slow speed. The reactor plant cooldown heat exchanger was in service to maintain coolant temperature. The 1A, 1B, 1C, and 1D reactor coolant loops and the 1AC and 1BD purification loops remained in service. All expended PWR Core 2 fuel elements have previously been shipped off-site. The remaining irradiated PWR Core 2 core barrel and miscellaneous refueling tools were in storage under shielding water in the deep pit of the Fuel Handling Building. The LWBR Core has generated 12,111.00 EFPH from startup through the end of the quarter.

  18. Easy-to-Use UAV Ground Station Software for Low-Altitude Civil Operations, Phase I

    Data.gov (United States)

    National Aeronautics and Space Administration — We propose to design and develop easy-to-use Ground Control Station (GCS) software for low-altitude civil Unmanned Aerial Vehicle (UAV) operations. The GCS software...

  19. Draft Title V Operating Permit: Andeavor Field Services, LLC - Walker Hollow Compressor Station

    Science.gov (United States)

    Draft Operating Permit (Permit Number: V-UO-000979-2017.00), statement of basis, public notice bulletin, and the administrative permit docket (application and other supporting documents) for the Andeavor Walker Hollow Compressor Station.

  20. Title V Operating Permit: QEP Field Services Company - Wonsits Valley Compressor Station

    Science.gov (United States)

    Response to public comments and the Title V Operating Permit for the QEP Field Services Company, Wonsits Valley Compressor Station, located on the Uintah and Ouray Indian Reservation in Uintah County, Utah.

  1. Title V Operating Permit: QEP Field Services Company - Coyote Wash Compressor Station

    Science.gov (United States)

    Response to public comments and the Title V Operating Permit for the QEP Field Services Company, Coyote Wash Compressor Station, located on the Uintah and Ouray Indian Reservation in Uintah County, Utah.

  2. SUMMARY AND EVALUATION OF STARTUP AND OPERATING EXPERIENCE AT INDIAN POINT STATION

    Energy Technology Data Exchange (ETDEWEB)

    Freyberg, R. H.; Prestele, J. A.

    1963-09-15

    A description of the Indian Point Power Station is given aiong with a summary and evaluation of startup and operating experience. Equipment failures and problems and various corrective measures are also outlined. (C.E.S.)

  3. Automating Stowage Operations for the International Space Station

    Science.gov (United States)

    Knight, Russell; Rabideau, Gregg; Mishkin, Andrew; Lee, Young

    2013-01-01

    A challenge for any proposed mission is to demonstrate convincingly that the proposed systems will in fact deliver the science promised. Funding agencies and mission design personnel are becoming ever more skeptical of the abstractions that form the basis of the current state of the practice with respect to approximating science return. To address this, we have been using automated planning and scheduling technology to provide actual coverage campaigns that provide better predictive performance with respect to science return for a given mission design and set of mission objectives given implementation uncertainties. Specifically, we have applied an adaptation of ASPEN and SPICE to the Eagle-Eye domain that demonstrates the performance of the mission design with respect to coverage of science imaging targets that address climate change and disaster response. Eagle-Eye is an Earth-imaging telescope that has been proposed to fly aboard the International Space Station (ISS).

  4. The appliction of project management in operations preparation of nuclear power station

    International Nuclear Information System (INIS)

    Tang Zhengrong; Zhang Zhixiong

    2001-01-01

    Concept, history, characteristics of the project management is introduced. Analysis is performed on the suitability of application of project management approach in nuclear power station operations preparation. Then the application of project management is detailed in order to present the readers our study and practice. Theory and practice indicate that the project management is a useful management tool for operations preparation of nuclear power station to achieve a good performance

  5. The application of project management in operations preparation of nuclear power station

    International Nuclear Information System (INIS)

    Zhang Zhixiong; Tang Zhengrong

    2000-01-01

    The author first presents a brief introduction of the concept, history, characteristics of project management. Analysis is performed on the suitability of application of project management approach in nuclear power station operations preparation. Then the application of project management is detailed in order to present the readers authors' study and practice. Theory and practice indicate that the project management is a useful management tool for operations preparation of nuclear power station to achieve a good performance

  6. Control Centre operations as the focus for building station teamwork - issues and resource impacts

    International Nuclear Information System (INIS)

    Mathews, G.; Lane, L.; Davey, E.

    2006-01-01

    Effective teamwork among station work groups is essential for plant production and safety in all phases of plant operation. To achieve effective teamwork, all contributing work groups must have ongoing access to and share a common perspective on station work priorities, and recognize how their individual contributions fit with and support the contributions of other groups in support of the larger station goals. Achieving and maintaining this alignment in perspective across all workgroups can be a challenge in large organizations. This paper discusses the experience at Darlington in building and maintaining station teamwork among the station workgroups in support of day-to-day plant operations. The issues encountered and the resource impacts of specific teamwork supporting practices adopted are outlined. (author)

  7. Cooper Nuclear Station. Annual operating report: January--December 1976

    International Nuclear Information System (INIS)

    1977-01-01

    Plant operations including a chronological summary and a summary of plant outages and power reductions are described. Information is also presented concerning fuel performance, vessel transient condition events, facility changes, maintenance, and personnel radiation exposure

  8. Operating Nuclear Power Stations in a Regulated Cyber Security Environment

    Energy Technology Data Exchange (ETDEWEB)

    Dorman, E.

    2014-07-01

    The United States Nuclear Regulatory Commission (NRC) issued 10CFR73.54 to implement a regulated Cyber Security Program at each operating nuclear reactor facility. Milestones were implemented December 31, 2012 to mitigate the attack vectors for the most critical digital assets acknowledged by the industry and the NR C. The NRC inspections have begun. The nuclear Cyber Security Plan, implemented by the site Cyber Security Program (Program), is an element of the operating license at each facility. (Author)

  9. Operating Nuclear Power Stations in a Regulated Cyber Security Environment

    International Nuclear Information System (INIS)

    Dorman, E.

    2014-01-01

    The United States Nuclear Regulatory Commission (NRC) issued 10CFR73.54 to implement a regulated Cyber Security Program at each operating nuclear reactor facility. Milestones were implemented December 31, 2012 to mitigate the attack vectors for the most critical digital assets acknowledged by the industry and the NR C. The NRC inspections have begun. The nuclear Cyber Security Plan, implemented by the site Cyber Security Program (Program), is an element of the operating license at each facility. (Author)

  10. Annual report on operational management of nuclear power stations, 1979-1980

    International Nuclear Information System (INIS)

    1981-04-01

    This report was compiled by the Agency of Natural Resoures and Energy. The commercial nuclear power stations in Japan started the operation in 1966 for the first time, and as of the end of March, 1981, 22 plants with more than 15.5 million kW capacity were in operation. Nuclear power generation is regarded as the top-rated substitute energy for petroleum, and the target of its development in 1990 is about 52 million kW. The government and the people are exerting utmost efforts to attain the target. The result of the rate of operation of nuclear power stations reached 60.8% in 1980, but it is important to maintain the good, stable state of operation by perfecting the operational management hereafter in order to establish the position of LWRs. At present, the operational management officers of the government stay in nationwide power stations, and supervise the state of operations, thus the system of operational management was strengthened after the Three Mile Island accident in the U.S., and the improvement in the rate of operation is expected. A table shows the nuclear power stations in operation and under construction. The state of operations of individual nuclear power plants in 1979 and 1980, the accidents and failures occurred in nuclear power plants from 1966 to 1980, the minor troubles, the conditions in the regular inspections of individual nuclear power plants, radioactive waste management and the radiation exposure of workers are reported. (Kako, I.)

  11. Plant Operation Station for HTR-PM Low Power and Shutdown operation Probabilistic safety analysis

    International Nuclear Information System (INIS)

    Liu Tao; Tong Jiejuan

    2014-01-01

    Full range Probabilistic safety analysis (PSA) is one of key conditions for nuclear power plant (NPP) licensing according to the requirement of nuclear safety regulatory authority. High Temperature Gas Cooled Reactor Pebble-bed Module (HTR-PM) has developed construction design and prepared for the charging license application. So after the normal power operation PSA submitted for review, the Low power and Shutdown operation Probabilistic safety analysis (LSPSA) also begin. The results of LSPSA will together with prior normal power PSA results to demonstrate the safety level of HTR-PM NPP Plant Operation Station (POS) is one of important terms in LSPSA. The definition of POS lays the foundation for LSPSA modeling. POS provides initial and boundary conditions for the following event tree and fault tree model development. The aim of this paper is to describe the state-of-the-art of POS definition for HTR-PM LSPSA. As for the first attempt to the high temperature gas cooled reactor module plant, the methodology and procedure of POS definition refers to the LWR LSPSA guidance, and adds to plant initial status analysis due to the HTR-PM characteristics. A specific set of POS grouping vectors is investigate and suggested for HTR-PM NPP, which reflects the characteristics of plant modularization and on-line refueling. As a result, seven POSs are given according to the grouping vectors at the end of the paper. They will be used to the LSPSA modelling and adjusted if necessary. The papers ’work may provide reference to the analogous NPP LSPSA. (author)

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

    International Nuclear Information System (INIS)

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

    2000-01-01

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

  13. Annual report on nuclear power station operational management, 1984

    International Nuclear Information System (INIS)

    1985-09-01

    As of the end of fiscal year 1984, 28 nuclear power plants were in operation in Japan, the total power output of which was 20.56 million kW, equivalent to 22.9 % of the total generated electric power in Japan. Now nuclear power generation bears a very important role in the stable supply and cost stabilization of electric power. The result of the capacity factor in fiscal year 1984 was 73.9 %, which showed that the nuclear power generation and safety management technologies in Japan are at the top level in the world. However, in order that nuclear power generation accomplishes the role as main power source sufficiently hereafter by increasing the number of plants, the reliability and economical efficiency must be further improved, and especially the safety management and operational management become important. For the purpose, the operational experience accumulated so far must be effectively utilized. In this book, the outline of the administration on the safety regulation of nuclear power generation, the state of operation of nuclear power plants, the state of accidents and failures, the state of regular inspections and so on are summarized. Also the state of radioactive waste management and the radiation control for workers are reported. (Kako, I.)

  14. Pilgrim Nuclear Power Station, Unit 1. Annual operating report, 1975

    International Nuclear Information System (INIS)

    1976-01-01

    Net electric power generated in 1975 was 1,074,401 MW(e) with the generator on line 4,680.7 hrs. Information is presented concerning operations, maintenance, radioactive effluents and waste shipments, health physics, shutdowns, and personnel exposures

  15. Vermont Yankee Nuclear Power Station. Annual operating report, 1975

    International Nuclear Information System (INIS)

    1976-01-01

    Net electrical power generated was 3,560,206 MWh(e) with the reactor on line 7,689 hrs. Information is presented concerning operations power generation, shutdowns, corrective maintenance, primary coolant chemistry, occupational radiation exposure, reportable occurrences, core spray welds inspection, loss of start-up transformer, and union strike

  16. Pilgrim Nuclear Power Station, Unit 1. Annual operating report, 1975

    International Nuclear Information System (INIS)

    1976-01-01

    Net electrical power generated was 2,587,248 MWH(e) with the reactor on line 6,242.4 hr. Information is presented concerning operations, power generation, shutdowns, corrective maintenance, chemistry and radiochemistry, occupational radiation exposure, release of radioactive materials, and reportable occurrences

  17. Indicators for monitoring of safety operation and condition of nuclear power stations

    International Nuclear Information System (INIS)

    Manova, D.

    2001-01-01

    A common goal of all employees in the nuclear power field is safety operation of nuclear power stations. The evaluation and control of NPP safety operation are a part of the elements of safety management. The present report is related only to a part of the total assessment and control of the plant safety operation, namely - the indicator system for monitoring of Kozloduy NPP operation and condition. (author)

  18. The Spanish Nuclear Safety Council and nuclear power stations in operation in Spain

    International Nuclear Information System (INIS)

    Perello, M.

    1984-01-01

    On 20 April 1980 the Spanish Congress of Deputies passed an Act setting up the Nuclear Safety Council (CSN) as the sole organization responsible for nuclear safety and radiation protection. In this paper it is stated that that date marked the beginning of a new nuclear safety policy in Spain. As one of its objectives, this policy is aimed at the monitoring and testing of operating nuclear installations. A detailed description is given of the Operating Nuclear Installation Service (SINE), including its basic structure, its functions and the technical and manpower resources available to it. The maintenance of close relations with other organs of the CSN is considered of paramount importance in order for the tasks allotted to SINE to be fulfilled. International co-operation and outside contracting greatly assist importing countries which have limited manpower resources. A description is then given of the present state of the nuclear power stations in operation in Spain together with an account of the most important initiatives which have been taken so far. The year 1968 saw the beginning of commercial operation of the Jose Cabrera nuclear power station, which has the only single-loop PWR reactor in the world. At present, it is being subjected to the Systematic Evaluation Programme (SEP). The Santa Maria de Garona nuclear power station has been operating for over twelve years and is also being subjected to the SEP although design modifications derived from operating experience have already been introduced. The Vandellos I station was the last of the first generation and has also benefited from the operating experience of similar French plants. Unit 1 of the Almaraz power station opens the door to the second generation and the generic problem which has occurred with the steam generators is in process of being solved. Lastly, some general conclusions are presented about the organization of and experience acquired with operating nuclear power stations. (author)

  19. Operating Experience of MACSTOR Modules at CANDU 6 Stations

    International Nuclear Information System (INIS)

    Beaudoin, Robert R.

    2005-01-01

    Over the last three decades, Atomic Energy of Canada Limited (AECL) has contributed to the technology development and implementation of dry spent fuel management facilities in Canada, Korea and Romania During that period, AECL has developed a number of concrete canister models and the MACSTOR200 module, a medium size air-cooled vault with a 228 MgU (Mega grams of Uranium) capacity. AECL's dry storage technologies were used for the construction of eight large-scale above ground dry storage facilities for CANDU spent fuel. As of 2005, those facilities have an installed capacity in excess of 5,000 MgU. Since 1995, the two newest dry storage installations built for CANDU 6 reactors at Gentilly 2 (Canada) and Cernavoda (Romania) used the MACSTOR 200 module. Seven such modules have been built at Gentilly 2 during the 1995 to 2004 period and one at Cernavoda in 2003. The construction and operating experience of those modules is reviewed in this paper. The MACSTOR 200 modules were initially designed for a 50-year service life, with recent units at Gentilly 2 licensed for a 100-year service life in a rural (non-maritime) climate. During the 1995-2005 period, six of the eight modules were loaded with fuel. Their operation has brought a significant amount of experience on loading operations, performance of fuel handling equipment, radiation shielding, heat transfer, monitoring of the two confinement boundaries and radiation dose to personnel. Heat dissipation performance of the MACSTOR 200 was initially licensed using values derived from full scale tests made at AECL's Whiteshell Research Laboratories, that were backed-up by temperature measurements made on the first two modules. Results and computer models developed for the MACSTOR 200 module are described. Korea Hydro and Nuclear Power (KHNP) and its subsidiary Nuclear Environment Technology Institute (NETEC), in collaboration with Hyundai Engineering Company Ltd. (HEC) and AECL, are developing a new dry storage module to

  20. Automatic sequencing and control of Space Station airlock operations

    Science.gov (United States)

    Himel, Victor; Abeles, Fred J.; Auman, James; Tqi, Terry O.

    1989-01-01

    Procedures that have been developed as part of the NASA JSC-sponsored pre-prototype Checkout, Servicing and Maintenance (COSM) program for pre- and post-EVA airlock operations are described. This paper addresses the accompanying pressure changes in the airlock and in the Advanced Extravehicular Mobility Unit (EMU). Additionally, the paper focuses on the components that are checked out, and includes the step-by-step sequences to be followed by the crew, the required screen displays and prompts that accompany each step, and a description of the automated processes that occur.

  1. Quality surveillance at Duke Power operating nuclear stations

    International Nuclear Information System (INIS)

    Bradley, W.H.

    1985-01-01

    The Duke Power quality assurance (QA) program originally had three levels of QA audits that reported results to different levels of management and in different time frames. It soon became obvious that although problems were being identified, considerable confusion was being created by reporting them to different levels. Additionally, it was recognized that all audits were dealing in history: events that had already occurred and therefore could not be averted. What was needed was a problem identification system focused on current activities. The Duke quality surveillance program was created by dropping the first level of audits and replacing it with an on-the-scene review system to identify current problems. The quality surveillance program is a success and will be even more so after surveillance personnel acquire additional technical expertise. To that end, a training program has been initiated that will stop just short of operator licensing in the operations area and will also include other areas such as health physics and chemistry

  2. Education and training of operators and maintenance staff at commercial nuclear power stations in Japan

    International Nuclear Information System (INIS)

    Takahashi, M.; Kataoka, H.

    1998-01-01

    Safe and stable operation of a nuclear power station requires personnel fostering. In Japan, with the objectives of systematically securing qualified people for a long period of time, and maintaining and improving their skills and knowledge, the utilities have created strict personnel training plans, for continuous education and training. Concrete examples of education and training for operators and maintenance personnel at commercial nuclear power stations in Japan, such as education systems training, facility and contents of curriculum, are detailed including some related matters. Recent activities to catch up with environment changes surrounding education and training of operators and maintenance staff are also mentioned. (author)

  3. Comprehensive Test Ban Treaty (CTBT) monitoring station operating regime influence on radionuclide detection sensitivity

    International Nuclear Information System (INIS)

    Williams, D.L.

    1999-01-01

    International Monitoring System (IMS) stations are being deployed worldwide in support of the Comprehensive [Nuclear] Test Ban Treaty (CTBT). The highly sensitive radionuclide monitoring stations regularly sample airborne radionuclide particulates to determine whether fission products are present in the atmosphere that may be indicative of a nuclear weapons test. Standards have been set for these stations regarding their operation regime and the minimum detectable concentrations (MDCs) for specific radionuclides likely to be present after a nuclear weapons test. This study uses actual CTBT monitoring data to relate a subset of the specified operational standards with the listed MDC limits. It is determined that a relationship exists between the specified operational regime and the MDC values. Since the background radioactivity is largely a function of the radon and thoron progeny, longer decay operational regimes allow for a reduction in the background. For longer lived radionuclides, this corresponds to a reduction in MDC. (author)

  4. Oconee Nuclear Station, Units 1, 2, and 3. Semiannual operating report, January--June 1975

    International Nuclear Information System (INIS)

    1975-01-01

    Information is presented concerning operations, performance characteristics, changes, tests, inspections, containment leak tests, maintenance, primary coolant chemistry, station staff changes, reservoir investigations, plume mapping, and operational environmental radioactivity monitoring data for oconee Units 1, 2, and 3. The non-radiological environmental surveillance program is also described. (FS)

  5. PI Microgravity Services Role for International Space Station Operations

    Science.gov (United States)

    DeLombard, Richard

    1998-01-01

    During the ISS era, the NASA Lewis Research Center's Principal Investigator Microgravity Services (PIMS) project will provide to principal investigators (PIs) microgravity environment information and characterization of the accelerations to which their experiments were exposed during on orbit operations. PIMS supports PIs by providing them with microgravity environment information for experiment vehicles, carriers, and locations within the vehicle. This is done to assist the PI with their effort to evaluate the effect of acceleration on their experiments. Furthermore, PIMS responsibilities are to support the investigators in the area of acceleration data analysis and interpretation, and provide the Microgravity science community with a microgravity environment characterization of selected experiment carriers and vehicles. Also, PIMS provides expertise in the areas of microgravity experiment requirements, vibration isolation, and the implementation of requirements for different spacecraft to the microgravity community and other NASA programs.

  6. Operational radio interferometry observation network (ORION) mobile VLBI station. [for NASA Crustal Dynamics Project

    Science.gov (United States)

    Renzetti, N. A.; Vegos, C. J.; Parks, G. S.; Sniffin, R. W.; Gannon, D. L.; Nishimura, H. G.; Clements, P. A.; Mckinney, R. P.; Menninger, F. J.; Vandenberg, N. R.

    1983-01-01

    The design and current status of the ORION mobile VLBI station is described. The station consists of a five-meter antenna, a receiving and recording system installed in a mobile antenna transporter, and an electronics transporter. The station is designed for field operation by a two-person crew at the rate of two sites per week. The various subsystems are described in detail, including the antenna, housing facilities for electronics and crew, microwave equipment, receiver, data acquisition subsystem, frequency and timing subsystem, phase calibration, monitoring and control, water vapor radiometer, and communications.

  7. A joint program for seismographic station operations in the Republic of Kazakstan

    International Nuclear Information System (INIS)

    Kim, W.Y.; Belyashova, N.N.; Richards, P.G.

    1998-01-01

    In this paper there are examples of seismic signals recorded at the stations operated jointly by the Kazakhstan National Nuclear Centre and Lamont-Doherty Earth Observatory of Columbia University. Also the way the stations can be used to interpret the natural (earthquake) and and anthropogenic (explosion) sources from which the signals originated is shown. Examples include nuclear explosions carried out by China, India and Pakistan in recent years and months

  8. Annual report of operation management in nuclear power stations, fiscal year 1985

    International Nuclear Information System (INIS)

    1986-09-01

    Twenty years have elapsed since the first practical nuclear reactor in Japan started the operation. In the generated power in fiscal year 1985, that of nuclear power stations for the first time overtook that of thermal power stations, and now the age of nuclear power as the main and oil power as the subordinate has begun. As of the end of fiscal year 1985, there were 32 nuclear power plants in operation, having total output capacity of 24.521 million kW. In fiscal year 1985, nuclear power plants generated about 159 billion kWh, which is about 26 % of electric power supply. As to the capacity factor, 76 % was attained in fiscal year 1985, and this is ranked in the top group of LWR-operating countries in the world. It showed that the Japanese technology of nuclear power generation is at the top level in the world. However, in order to increase nuclear power generation and to accomplish the role of main electric power source hereafter, it is necessary to further increase the reliability and economical efficiency. The list of nuclear power stations in Japan, the state of operation of nuclear power stations, the state of accidents and troubles, the state of regular inspection, the management of radioactive wastes and the radiation exposure of workers in nuclear power stations, the operational management and others are reported. (Kako, I.)

  9. An examination of automation and robotics in the context of Space Station operations

    Science.gov (United States)

    Criswell, David R.; Lee, Douglas S.; Ragusa, James; Starks, Scott A.; Woodruff, John; Paules, Granville

    1988-01-01

    A NASA-sponsored review of Space Station automation and robotics (A&R) applications from an operations and utilization perspective is presented. The goals of the A&R panel and this report are to identify major suggestions for advanced A&R operations application in Space Station as well as key technologies that have emerged or gained prominence since the completion of previous reports; to review and incorporate the range of possible Space Station A&R applications into a framework for evaluation of A&R opportunities; and to propose incentives for the government, work packages, and subcontractors to more aggressively identify, evaluate, and incorporate advanced A&R in Space Station Operations. The suggestions for A&R focused on narrow objectives using a conservative approach tuned to Space Station at IOC and limiting the Station's growth capabilities. A more aggressive stance is to identify functional needs over the Program's life, exploit and leverage available technology, and develop the key advanced technologies permitting effective use of A&R. The challenge is to systematically identify candidate functions to be automated, provide ways to create solutions resulting in savings or increased capabilities, and offer incentives that will promote the automation.

  10. INTELLECTUAL MODEL FORMATION OF RAILWAY STATION WORK DURING THE TRAIN OPERATION EXECUTION

    Directory of Open Access Journals (Sweden)

    O. V. Lavrukhin

    2014-11-01

    Full Text Available Purpose. The aim of this research work is to develop an intelligent technology for determination of the optimal route of freight trains administration on the basis of the technical and technological parameters. This will allow receiving the operational informed decisions by the station duty officer regarding to the train operation execution within the railway station. Metodology. The main elements of the research are the technical and technological parameters of the train station during the train operation. The methods of neural networks in order to form the self-teaching automated system were put in the basis of the generated model of train operation execution. Findings. The presented model of train operation execution at the railway station is realized on the basis of artificial neural networks using learning algorithm with a «teacher» in Matlab environment. The Matlab is also used for the immediate implementation of the intelligent automated control system of the train operation designed for the integration into the automated workplace of the duty station officer. The developed system is also useful to integrate on workplace of the traffic controller. This proposal is viable in case of the availability of centralized traffic control on the separate section of railway track. Originality. The model of train station operation during the train operation execution with elements of artificial intelligence was formed. It allows providing informed decisions to the station duty officer concerning a choice of rational and a safe option of reception and non-stop run of the trains with the ability of self-learning and adaptation to changing conditions. This condition is achieved by the principles of the neural network functioning. Practical value. The model of the intelligent system management of the process control for determining the optimal route receptionfor different categories of trains was formed.In the operational mode it offers the possibility

  11. Education and training of operators and maintenance staff at Hamaoka Nuclear Power Stations

    International Nuclear Information System (INIS)

    Makido, Hideki; Hayashi, Haruhisa

    1999-01-01

    At Hamaoka Nuclear Power Station, in order to ensure higher safety and reliability of plant operation, education and training is provided consistently, on a comprehensive basis, for all operating, maintenance and other technical staff, aimed at developing more capable human resources in the nuclear power division. To this end, Hamaoka Nuclear Power Station has the 'Nuclear Training Center' on its site. The training center provides the technical personnel including operators and maintenance personnel with practical training, utilizing simulators for operation training and the identical facilities with those at the real plant. Thus, it plays a central role in promoting comprehensive education and training concerning nuclear power generation. Our education system covers knowledge and skills necessary for the safe and stable operation of nuclear power plant, targeting new employees to managerial personnel. It is also organized systematically in accordance with experience and job level. We will report the present education and training of operators and maintenance personnel at Hamaoka Nuclear Training Center. (author)

  12. Statement on safety requirements concerning the long-term operation of the Muehleberg nuclear power station

    International Nuclear Information System (INIS)

    2012-12-01

    This report published by the Swiss Federal Nuclear Safety Inspectorate ENSI investigates the safety requirements with respect to the long-term operation of the Muehleberg nuclear power station in Switzerland. Relevant international requirements and Swiss legal stipulations concerning the long-term operation of the power station are stated. The management of aging processes is looked at. The regular verification of the integrity of various plant components such as containments, piping, steam generation system, etc. is looked at in detail. The state-of-the-art concerning deterministic accident analyses and refitting technology are discussed, as are automated safety systems. The applicable laws, decrees and guidelines are listed in appendices

  13. Neumayer III and Kohnen Station in Antarctica operated by the Alfred Wegener Institute

    Directory of Open Access Journals (Sweden)

    Christine Wesche

    2016-08-01

    Full Text Available The Alfred Wegener Institute operates two stations in Dronning Maud Land, Antarctica. The German overwintering station Neumayer III is located on the Ekström Ice Shelf at 70°40’S and 08°16’W and is the logistics base for three long-term observatories (meteorology, air chemistry and geophysics and nearby research activities. Due to the vicinity to the coast (ca. 20 km from the ice shelf edge, the Neumayer III Station is the junction for many German Antarctic expeditions, especially as the starting point for the supply traverse for the second German station Kohnen. The summer station Kohnen is located about 600 km from the coast and 750 km from Neumayer III Station on the Antarctic plateau at 75°S and 00°04’E. It was erected as the base for the deep-drilling ice core project, which took place between 2001 and 2006. Since then Kohnen Station is used as a logistics base for different research projects.

  14. Experience from the construction and operation of Tarapur and Rajasthan Nuclear Power Stations

    International Nuclear Information System (INIS)

    Shah, J.C.; Pardiwala, T.F.; Kothare, V.V.; Rao, M.H.P.; Nanjundeswaran, K.

    1977-01-01

    India's experience in construction and operation of nuclear power stations so far covers two BWR and four PHWR Units in three power stations. Two more PHWR units are at an early stage of construction. The twin unit Tarapur Station (2x210 MWe BWR) was built as a turnkey project which restricted participation of Indian engineers in design and construction considerably. The contrasting approach adopted for Rajasthan Station (2x220 MWe PHWR) involved Indian personnel and contractors fully in construction and commissioning, with Canadians providing supervisory assistance in Rajasthan I and essentially consultative help for Rajasthan II. Subsequent stations are wholly Indian efforts. Tarapur went into commercial operation in 1969, 60 months after breaking of ground. Construction was essentially uneventful, major problems faced being stress corrosion induced cracks in the reactor lining and complete change of steam generator tubes. In its seven years of operations, Tarapur has faced several problems mainly arising from rather early designs, indifferent fuel performance, constraints of twin-unit approach and operations in an inadequately developed grid system apart from those generally stemming from assimilation of an advanced technology in a developing country. The Station has undergone six refuellings during this period. Most of the problems have been overcome by design changes, system augmentations and experience and the Station operation since mid 1974 have generally been steady at around 90% of the rated capacity. Construction of Rajasthan I at a remote and isolated site proceeded relatively slowly. Local availability of skilled and semi-skilled manpower was poor, affecting construction. Inadequate roads impeded movements of overdimensioned components. Observing strict Quality Assurance standards required several major rectifications at site. Rajasthan I went on line in 1973 after overcoming major turbine bearing problems during commissioning. Since then, while

  15. A shared-world conceptual model for integrating space station life sciences telescience operations

    Science.gov (United States)

    Johnson, Vicki; Bosley, John

    1988-01-01

    Mental models of the Space Station and its ancillary facilities will be employed by users of the Space Station as they draw upon past experiences, perform tasks, and collectively plan for future activities. The operational environment of the Space Station will incorporate telescience, a new set of operational modes. To investigate properties of the operational environment, distributed users, and the mental models they employ to manipulate resources while conducting telescience, an integrating shared-world conceptual model of Space Station telescience is proposed. The model comprises distributed users and resources (active elements); agents who mediate interactions among these elements on the basis of intelligent processing of shared information; and telescience protocols which structure the interactions of agents as they engage in cooperative, responsive interactions on behalf of users and resources distributed in space and time. Examples from the life sciences are used to instantiate and refine the model's principles. Implications for transaction management and autonomy are discussed. Experiments employing the model are described which the authors intend to conduct using the Space Station Life Sciences Telescience Testbed currently under development at Ames Research Center.

  16. 47 CFR 25.220 - Non-conforming transmit/receive earth station operations.

    Science.gov (United States)

    2010-10-01

    ... 47 Telecommunication 2 2010-10-01 2010-10-01 false Non-conforming transmit/receive earth station operations. 25.220 Section 25.220 Telecommunication FEDERAL COMMUNICATIONS COMMISSION (CONTINUED) COMMON CARRIER SERVICES SATELLITE COMMUNICATIONS Technical Standards § 25.220 Non-conforming transmit/receive...

  17. 47 CFR 25.218 - Off-axis EIRP envelopes for FSS earth station operations.

    Science.gov (United States)

    2010-10-01

    ... 47 Telecommunication 2 2010-10-01 2010-10-01 false Off-axis EIRP envelopes for FSS earth station operations. 25.218 Section 25.218 Telecommunication FEDERAL COMMUNICATIONS COMMISSION (CONTINUED) COMMON CARRIER SERVICES SATELLITE COMMUNICATIONS Technical Standards § 25.218 Off-axis EIRP envelopes for FSS...

  18. Preparations for the 1994 OSART [operational safety review] at Hunterston Power Station

    International Nuclear Information System (INIS)

    Moir, I.A.

    1993-01-01

    The International Atomic Energy Agency have accepted an invitation from the Scottish Office to carry out an Operational Safety Review at Hunterston Power Station in April 1994. This paper outlines the preparations being undertaken by Scottish Nuclear Limited to ensure the standards set by the International Atomic Energy Agency are met. (author)

  19. Scheduled Operation of PV Power Station Considering Solar Radiation Forecast Error

    Science.gov (United States)

    Takayama, Satoshi; Hara, Ryoichi; Kita, Hiroyuki; Ito, Takamitsu; Ueda, Yoshinobu; Saito, Yutaka; Takitani, Katsuyuki; Yamaguchi, Koji

    Massive penetration of photovoltaic generation (PV) power stations may cause some serious impacts on a power system operation due to their volatile and unpredictable output. Growth of uncertainty may require larger operating reserve capacity and regulating capacity. Therefore, in order to utilize a PV power station as an alternative for an existing power plant, improvement in controllability and adjustability of station output become very important factor. Purpose of this paper is to develop the scheduled operation technique using a battery system (NAS battery) and the meteorological forecast. The performance of scheduled operation strongly depends on the accuracy of solar radiation forecast. However, the solar radiation forecast contains error. This paper proposes scheduling method and rescheduling method considering the trend of forecast error. More specifically, the forecast error scenario is modeled by means of the clustering analysis of the past actual forecast error. Validity and effectiveness of the proposed method is ascertained through computational simulations using the actual PV generation data monitored at the Wakkanai PV power station and solar radiation forecast data provided by the Japan Weather Association.

  20. Economic benefits of the Space Station to commercial communication satellite operators

    Science.gov (United States)

    Price, Kent M.; Dixson, John E.; Weyandt, Charles J.

    1987-01-01

    The economic and financial aspects of newly defined space-based activities, procedures, and operations (APOs) and associated satellite system designs are presented that have the potential to improve economic performance of future geostationary communications satellites. Launch insurance, launch costs, and the economics of APOs are examined. Retrieval missions and various Space Station scenarios are addressed. The potential benefits of the new APOs to the commercial communications satellite system operator are quantified.

  1. Definition of technology development missions for early space stations orbit transfer vehicle serving. Phase 2, task 1: Space station support of operational OTV servicing

    Science.gov (United States)

    1983-01-01

    Representative space based orbital transfer vehicles (OTV), ground based vehicle turnaround assessment, functional operational requirements and facilities, mission turnaround operations, a comparison of ground based versus space based tasks, activation of servicing facilities prior to IOC, fleet operations requirements, maintenance facilities, OTV servicing facilities, space station support requirements, and packaging for delivery are discussed.

  2. Boiler recirculation pumps for nuclear power stations - present state of development. Directions for planning, operational experience

    International Nuclear Information System (INIS)

    Mattias, H.B.

    1976-01-01

    Boiler recirculation pumps are important components of modern power stations. The development of large recirculation pumps up to a driving power of 1,500 kW was faced with some problems in meeting the plant requirements. In this paper, the present state of development is dealt with. The development problems in the fields of hydrodynamics, cavitation, corrosion and erosion are dealt with as well as the problems of the design of the casing with regard to thermodynamics and strength. Finally, operational experience with the boiler recirculation pump for 600 MW power stations will be reported on. (orig./AK) [de

  3. Retrofitting and operation solid radwaste system Dresden Station, Units 2 and 3

    International Nuclear Information System (INIS)

    Testa, J.; Homer, J.C.

    1982-01-01

    Units 2 and 3 at Dresden Station are twin 794 MW (net) BWR units that became operational in 1970 and 1971. The waste streams are typical of BWR stations, namely, bead resin and filter sludge (powdered resins and diatomaceous earth), evaporator concentrate containing approximately 25% dissolved solids and dry active waste. The original solid radwaste system utilized cement for solidification in open top 55 gallon drums. Remote handling was provided by means of a monorail with moving platforms supporting the drums. A relatively light-weight compactor was used to compact DAW into 55 gallon drums. Difficulties were experienced with this system

  4. Ten year report on the operation of the Latina nuclear power station 1964-1973

    International Nuclear Information System (INIS)

    1976-07-01

    The final report on the operation of the Latina nuclear power station, required under the terms of the contract of participation between ENEL and EURATOM is presented. It covers the first ten years of commercial operation (1 January 1964-31 December 1973) of this power station. Latina uses a British Magnox-type gas-graphite natural uranium reactor with a design thermal capacity of 724 MW. The rated electrical output of the three main turbogenerators was originally 210 MW (3x70), but was reduced to 160 MW in 1971. Construction began in November 1958 and was completed when the reactor first reached criticality in December 1962, the station being connected to the Italian electricity network for the first time in May 1963. The gross rated output of 210 MWe was reached in December 1963 and commercial operation began on 1 January 1964, by which date, however, the power station had already fed 295.5 million kWh into the network

  5. Large eddy simulation of cooling flows in underground subway station according to different PSD operating conditions

    Energy Technology Data Exchange (ETDEWEB)

    Jang, Yong Jun; Kim, Jin Ho; Park, Sung Huk; Koo, Dong Hoe [Korea Railroad Research Institute, Uiwang (Korea, Republic of)

    2015-11-15

    Large eddy simulation (LES) method is applied to systematically investigate the cooling fluid flow and the temperature distribution under the operating of air conditioning in the deeply underground subway station. The Shin-Gum-Ho subway station in Seoul which is the 8{sup th} floor and 43.6 m deep is selected for this analysis. The entire station is covered for simulation. The ventilation mode for air conditioning is kept as ordinary state. Different operating conditions for Platform screen door (PSD) are applied. First one is PSD is completely close and second one is PSD is regularly open and close which imitate the actual circumstances in the platform. The ventilation diffusers are modeled as 95 square shapes in the lobby and 222 squares in the platform. The temperature variations and flow behaviors are numerically simulated after operating of air conditioning for the whole station and the calculated results are compared with experimental data. LES method solves the momentum and thermal equations. Werner-Wengle wall law is applied to viscous sub layers for near wall resolution. The total grid numbers are 7.5 million and the whole domain is divided to 22 blocks. Multi blocks are computed in parallel using MPI. The results show the temperature difference in the platform between PSD-close and PSD-regularly open and close cases is 3-4 .deg. C.

  6. Large eddy simulation of cooling flows in underground subway station according to different PSD operating conditions

    International Nuclear Information System (INIS)

    Jang, Yong Jun; Kim, Jin Ho; Park, Sung Huk; Koo, Dong Hoe

    2015-01-01

    Large eddy simulation (LES) method is applied to systematically investigate the cooling fluid flow and the temperature distribution under the operating of air conditioning in the deeply underground subway station. The Shin-Gum-Ho subway station in Seoul which is the 8"t"h floor and 43.6 m deep is selected for this analysis. The entire station is covered for simulation. The ventilation mode for air conditioning is kept as ordinary state. Different operating conditions for Platform screen door (PSD) are applied. First one is PSD is completely close and second one is PSD is regularly open and close which imitate the actual circumstances in the platform. The ventilation diffusers are modeled as 95 square shapes in the lobby and 222 squares in the platform. The temperature variations and flow behaviors are numerically simulated after operating of air conditioning for the whole station and the calculated results are compared with experimental data. LES method solves the momentum and thermal equations. Werner-Wengle wall law is applied to viscous sub layers for near wall resolution. The total grid numbers are 7.5 million and the whole domain is divided to 22 blocks. Multi blocks are computed in parallel using MPI. The results show the temperature difference in the platform between PSD-close and PSD-regularly open and close cases is 3-4 .deg. C

  7. Rate of generation of tritium during the operation of Tsuruga Power Station Unit No. 2

    International Nuclear Information System (INIS)

    Funamoto, Hisao; Yoshinari, Masaharu; Fukuda, Masayuki; Makino, Shinichi; Watari, Tuneo

    1994-01-01

    Total amount of 3 H activity in primary coolant due to the operation of Tsuruga Power Station Unit No. 2 was estimated. The 3 H inventory was measured for samples from the spent fuel pool, primary coolant and miscellaneous tanks. From the result of the measurement and the data of environmental release of 3 H, the rate of generation of 3 H in the reactor was found to be 25 TBq/GWa. Since Tsuruga Power Station Unit No. 2 is a PWR type reactor, we presume that most of the 3 H in primary coolant is formed by 10 B(n, 2α) 3 H reaction. It is necessary to release about 23 TBq/GWa of 3 H to maintain the station inventory at the present level. (author)

  8. Development of Abnormal Operating Strategies for Station Blackout in Shutdown Operating Mode in Pressurized Water Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Yoon, Duk-Joo; Lee, Seung-Chan; Sung, Je-Joong; Ha, Sang-Jun [KHNP CRI, Daejeon (Korea, Republic of); Hwang, Su-Hyun [FNC Tech. Co., Yongin (Korea, Republic of)

    2016-10-15

    Loss of all AC power is classified as one of multiple failure accident by regulatory guide of Korean accident management program. Therefore we need develop strategies for the abnormal operating procedure both of power operating and shutdown mode. This paper developed abnormal operating guideline for loss of all AC power by analysis of accident scenario in pressurized water reactor. This paper analyzed the loss of ultimate heat sink (LOUHS) in shutdown operating mode and developed the operating strategy of the abnormal procedure. Also we performed the analysis of limiting scenarios that operator actions are not taken in shutdown LOUHS. Therefore, we verified the plant behavior and decided operator action to taken in time in order to protect the fuel of core with safety. From the analysis results of LOUHS, the fuel of core maintained without core uncovery for 73 minutes respectively for opened RCS states after the SBO occurred. Therefore, operator action for the emergency are required to take in 73 minutes for opened RCS state. Strategy is to cooldown by using spent fuel pool cooling system. This method required to change the plant design in some plant. In RCS boundary closed state, first abnormal operating strategy in shutdown LOUHS is first abnormal operating strategy in shutdown LOUHS is to remove the residual heat of core by steam dump flow and auxiliary feedwater of SG.

  9. Optimizing the use of operating experience at Ontario Hydro's Bruce Nuclear Generating Station 'A'

    International Nuclear Information System (INIS)

    Williams, E.L.

    1991-01-01

    One of the most significant lessons learned from the Three Mile Island event (March 1979), and again with the Chernobyl disaster - (April 1986) was the ongoing requirement to learn from our mistakes and near misses, and those of our fellow utilities around the world: so that as an industry we do not repeat the same mistakes. The very future of our industry will depend on how well each one of us accomplishes this important ask. This paper describes in detail the challenges encountered by one station when incorporating a comprehensive 'Operating Program'. It begins with the Corporate Office's directives to its stations for such a program; and follows up with the details of the actual station implementation of the program, and day to day operating experiences. The paper describes in detail the following Operating Experience programs: - Root Cause Determination process. The Institute of Nuclear Power Operations, Human Performance Enhancement System (HPES) as an integral component of the Root Cause process. Finding solutions for our station for problems identified elsewhere is covered herein; - Significant Event Recommendation Tracking System: - Commitment Tracking System; - Operating Experience (Sharing Lessons Learned) System. The paper will show all the above processes tie closely together and complement each other. The paper discusses the staff required for such processes and their training requirements. It recommends process time lines, reporting mechanisms, and sign off requirements. It will describe the equipment utilized to carry out this work effectively, and with a minimum of staff. One unique feature of the Bruce 'A' system is an 'Effectiveness Follow-Up', usually three to six months after the event recommendations have been completed. By rechecking the finished actions and reviewing them with the personnel involved with the originating event we ensure that the real root causes have been identified and resolved. (author)

  10. Optimizing the use of operating experience at Ontario Hydro's Bruce Nuclear Generating Station 'A'

    Energy Technology Data Exchange (ETDEWEB)

    Williams, E L [Operating Experience Reactor Safety, Bruce Nuclear Generating Station ' A' , Ontario Hydro, Tiverton, Ontario (Canada)

    1991-04-01

    One of the most significant lessons learned from the Three Mile Island event (March 1979), and again with the Chernobyl disaster - (April 1986) was the ongoing requirement to learn from our mistakes and near misses, and those of our fellow utilities around the world: so that as an industry we do not repeat the same mistakes. The very future of our industry will depend on how well each one of us accomplishes this important ask. This paper describes in detail the challenges encountered by one station when incorporating a comprehensive 'Operating Program'. It begins with the Corporate Office's directives to its stations for such a program; and follows up with the details of the actual station implementation of the program, and day to day operating experiences. The paper describes in detail the following Operating Experience programs: - Root Cause Determination process. The Institute of Nuclear Power Operations, Human Performance Enhancement System (HPES) as an integral component of the Root Cause process. Finding solutions for our station for problems identified elsewhere is covered herein; - Significant Event Recommendation Tracking System: - Commitment Tracking System; - Operating Experience (Sharing Lessons Learned) System. The paper will show all the above processes tie closely together and complement each other. The paper discusses the staff required for such processes and their training requirements. It recommends process time lines, reporting mechanisms, and sign off requirements. It will describe the equipment utilized to carry out this work effectively, and with a minimum of staff. One unique feature of the Bruce 'A' system is an 'Effectiveness Follow-Up', usually three to six months after the event recommendations have been completed. By rechecking the finished actions and reviewing them with the personnel involved with the originating event we ensure that the real root causes have been identified and resolved. (author)

  11. Computer software design description for the Treated Effluent Disposal Facility (TEDF), Project L-045H, Operator Training Station (OTS)

    International Nuclear Information System (INIS)

    Carter, R.L. Jr.

    1994-01-01

    The Treated Effluent Disposal Facility (TEDF) Operator Training Station (OTS) is a computer-based training tool designed to aid plant operations and engineering staff in familiarizing themselves with the TEDF Central Control System (CCS)

  12. 76 FR 45301 - PSEG Nuclear LLC, Hope Creek Generating Station; Notice of Issuance of Renewed Facility Operating...

    Science.gov (United States)

    2011-07-28

    ... NUCLEAR REGULATORY COMMISSION Docket No. 50-354 [NRC-2009-0391] PSEG Nuclear LLC, Hope Creek... operator of the Hope Creek Generating Station (HCGS). Renewed Facility Operating License No. NPF- 57... Renewal of Nuclear Power Plants, Supplement 45, Regarding Hope Creek Generating Station and Salem Nuclear...

  13. Investigation the Effects of Operation Methods on Energy Consumption in Agricultural Water Pumping Stations

    Directory of Open Access Journals (Sweden)

    M. DelfanAzari

    2017-01-01

    Full Text Available Introduction: The energy crisis has led the world toward the reduction of energy consumption. More than 70 percent of the energy in agriculture sector is used by pumps. In our country, there is no clear standard and guideline and also no adequate supervision for the design, selection, installation and operation of pumping systems appropriate to the circumstances and needs. Consequently, these systems operate with low efficiency and high losses of energy. While more than 20 percent of the world's electricity is consumed by pumps, average pumping efficiency is less than 40%. So evaluation of pumping stations and providing some solutions to increase efficiency and pumping system’s life time and to reduce energy consumption can be an effective in optimization of energy consumption in the country. The main reasons for the low efficiency of pumping systems comparing to potential efficiency are using unsuitable techniques for flow control, hydraulic and physical changes of pumping system during the time, using pumps or motors with low efficiency and poor maintenance. Normally the amount of flow is not constant over the time in a pumping system and needed flow rate is changed at different times. Designing of pumping system should be responsible for peak requirements as well as it must suggest the suitable flow control method to achieve least energy losses for minimum flow requirements. Also one of the main capabilities to reduce energy consumption in pumping stations is improving the flow control method. Using the flow control valves and bypass line with high energy losses is very common. While the use of variable speed pumps (VSPs that supply water requirement with sufficient pressure and minimum amount of energy, is limited due to lack of awareness of designers and (or high initial costs. Materials and Methods: In this study, the operation of the pumping stations under four scenarios (for discharge control in a drip irrigation system was analyzed

  14. Daya Bay Nuclear Power Station five-year business plan and operating results

    International Nuclear Information System (INIS)

    Zhang Shanming

    2000-01-01

    Guangdong Nuclear Power Joint Venture Company, Ltd. first 5-Year Business Plan (hereinafter referred to as 5-Year Business Plan) serves as guidance of both the operations and management of the company. Continuous performance improvement of the nuclear power station has been achieved through the fulfillment of goals and improvement plan defined by the 5-Year Business Plan, and through standard and systematic management. Daya Bay Nuclear Power Station (GNPS) has made great contributions to sustainable economic developments of both Guangdong and Hong Kong since its commercial operation in 1994. As of the end of 1999, the cumulative off-take electricity generated by GNPS had reached 69.9 billion kWh. Of the WANO indicators universally applied by nuclear power industry throughout the world, 6 indicators of Daya Bay performance entered the world top quartile while 9 the medium level

  15. Operational and biological effects zones from base stations of cellular telephony

    Energy Technology Data Exchange (ETDEWEB)

    Geronikolou, St. A., E-mail: sgeronik@bioacademy.gr [Biomedical Research Foundation Academy of Athens, Athens (Greece); Zimeras, S., E-mail: zimste@aegean.gr [University of the Aegean, Karlovassi, Samos (Greece); Tsitomeneas, S. Th., E-mail: stsit@teipir.gr [Piraeus University of Applied Sciences, Aigaleo (Greece)

    2016-03-25

    The possible environmental impacts of cellular base stations are operational and biological. The operational effects comprise Εlectro-Μagnetic Interference (EMI), lightning alterations and aesthetic degradation. Both thermal and non-thermal biological effects depend on the absorption of UHF radiofrequencies used. We measured, calculated and estimated the impact zones. The results are: (a) The lightning lethal zone equal to the antenna height, (b) the EMI impact in a zone up to 40m and (c) the ICNIRP’s limits exceed to a zone of 8∼20m into the antenna’s radiation pattern (for 2G GSM and 3G UMTS station). Finally we conclude the adverse effects must not expected in a zone of more than 150m from the radiated antenna, whereas, there is possibility of stochastic effects in intermediate distances (20/40-150m).

  16. Safety Evaluation Report related to the operation of River Bend Station (Docket No. 50-458)

    International Nuclear Information System (INIS)

    1984-10-01

    Supplement No. 1 to the Safety Evaluation Report on the application filed by Gulf States Utilities Company as applicant and for itself and Cajun Electric Power Cooperative, as owners, for a license to operate River Bend Station has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement reports the status of certain items that had not been resolved at the time of publication of the Safety Evaluation Report

  17. Black Fox Station, Units 1 and 2. Application for construction permits and operating licenses

    International Nuclear Information System (INIS)

    1975-01-01

    An application to construct and operate Black Fox Station, Units 1 and 2, is presented. The two BWR type reactors will have a rated core thermal power of 3579 MW(t) and a net electrical power of approximately 1150 MW(e). The facility will be located in Inola Township, 23 miles east of Tulsa on the east side of the Verdigris River in Rogers County, Oklahoma

  18. Final environmental statement related to the operation of River Bend Station (Docket No. 50-458)

    International Nuclear Information System (INIS)

    1985-01-01

    This Final Environmental Statement contains the second assessment of the environmental impact associated with the operation of River Bend Station, pursuant to the National Environment Policy Act of 1969 (NEPA) and Title 10 of the Code of Federal Regulations, Part 51, as amended, of the Nuclear Regulatory Commission regulations. This statement examines the environment, environmental consequences and mitigating actions, and environmental and economic benefits and costs

  19. Draft environmental statement related to the operation of River Bend Station (Docket No. 50-458)

    International Nuclear Information System (INIS)

    1984-07-01

    This draft environmental statement contains the second assessment of the environmental impact associated with the operation of River Bend Station, pursuant to the National Environmental Policy Act of 1969 (NEPA) and Title 10 of the Code of Federal Regulations, Part 51, as amended, of the Nuclear Regulatory Commission regulations. This statement examines the environment, environmental consequences and mitigating actions, and environmental and economic benefits and costs

  20. Operation of the Hoenoe wind power test station. Final report; Drift av Hoenoe provstation. Slutrapport

    Energy Technology Data Exchange (ETDEWEB)

    Ellsen, Magnus; Carlson, Ola [Chalmers Univ. of Tech., Goeteborg (Sweden). Dept. of Electric Power Engineering

    2002-04-01

    This project has made it possible to have autonomous operation of the Chalmers experimental wind turbine. By development of the optimal speed and stall control the energy production is good. The test station has been put in good order and is well prepared to been shown to visitors. The proposed research will focus on series capacitors for increasing the power output and better control of the damping valves to reduce vibrations.

  1. Planning in the Continuous Operations Environment of the International Space Station

    Science.gov (United States)

    Maxwell, Theresa; Hagopian, Jeff

    1996-01-01

    The continuous operation planning approach developed for the operations planning of the International Space Station (ISS) is reported on. The approach was designed to be a robust and cost-effective method. It separates ISS planning into two planning functions: long-range planning for a fixed length planning horizon which continually moves forward as ISS operations progress, and short-range planning which takes a small segment of the long-range plan and develops a detailed operations schedule. The continuous approach is compared with the incremental approach, the short and long-range planning functions are described, and the benefits and challenges of implementing a continuous operations planning approach for the ISS are summarized.

  2. Operation and maintenance of thermal power stations best practices and health monitoring

    CERN Document Server

    Chanda, Pradip

    2016-01-01

    This book illustrates operation and maintenance practices/guidelines for economic generation and managing health of a thermal power generator beyond its regulatory life. The book provides knowledge for professionals managing power station operations, through its unique approach to chemical analysis of water, steam, oil etc. to identify malfunctioning/defects in equipment/systems much before the physical manifestation of the problem. The book also contains a detailed procedure for conducting performance evaluation tests on different equipment, and for analyzing test results for predicting maintenance requirements, which has lent a new dimension to power systems operation and maintenance practices. A number of real life case studies also enrich the book. This book will prove particularly useful to power systems operations professionals in the developing economies, and also to researchers and students involved in studying power systems operations and control. .

  3. Obtaining college credit for licensed operator courses at the Wolf Creek Generating Station

    International Nuclear Information System (INIS)

    Russo, C.W.; Coulthard, R.C.

    1985-01-01

    The presentation examined alternatives to formal college courses as a means to obtain college credit toward a baccalaureate degree for station operations personnel. The focus is on the American Council on Education (ACE-PONSI) program which evaluates and makes credit recommendations for courses sponsored by organizations, like utilities, whose primary function is not education. Significant elements of the licensed operator program were prepared for an ACE-PONSI review and determined to be equivalent to college level nuclear engineering technology course work. The ACE-PONSI evaluation provides a good foundation and a significant amount of the training program evaluation required prior to the INPO accreditation effort

  4. Design and field operation of 1175 MW steam turbine for Ohi Nuclear Power Station

    International Nuclear Information System (INIS)

    Hirota, Yoshio; Nakagami, Yasuo; Fujii, Hisashi; Shibanai, Hirooki.

    1980-01-01

    Two 1175 MW steam turbine and generator units have been successfully in commercial operation since March 1979 and December 1979 respectively at Ohi Nuclear Power Station of the Kansai Electric Power Company. Those units, the largest in their respective outputs in Japan, have also such remarkable design features as two-stage reheat, nozzle governing turbine, water cooled generator stator and turbine-driven feedwater pumps. This paper covers design features and some topics of various pre-operational tests of the above-mentioned units. (author)

  5. Design and field operation of 1175 MW steam turbine for Ohi Nuclear Power Station

    International Nuclear Information System (INIS)

    Hirota, Y.; Nakagami, Y.; Fujii, H.; Shibanai, H.

    1980-01-01

    Two 1,175 MW steam turbine and generator units have been successfully in commercial operation since March 1979 and December 1979 respectively at Ohi Nuclear Power Station of the Kansai Electric Power Company. Those units, the largest in their respective outputs in Japan, have also such remarkable design features as two-stage reheat, nozzle governing turbine, water cooled generator stator and turbine-driven feedwater pumps. This paper covers design features and some topics of various pre-operational tests of the above-mentioned units. (author)

  6. Safety evaluation report related to the operation of River Bend Station (Docket No. 50-458)

    International Nuclear Information System (INIS)

    1984-05-01

    The Safety Evaluation Report for the application filed by the Gulf States Utilities Company, as applicant and owner, for a license to operate the River Bend Station (Docket No. 50-458) has been prepared by the Office of Nuclear Reactor Regulation of US Nuclear Regulatory Commission. The facility is located near St. Francisville, Louisiana. Subject to favorable resolution of the items discussed in this report, the NRC staff concludes that the facility can be operated by the applicant without endangering the health and safety of the public

  7. An independent spent-fuel storage installation at Surry Station: Design and operation

    International Nuclear Information System (INIS)

    McKay, H.S.; Wakeman, B.H.; Pickworth, J.M.; Routh, S.D.; Hopkins, W.C.

    1989-07-01

    Design and licensing of the Surry Power Station Independent Spent Fuel Storage Installation (ISFSI) was initiated in 1982 by Virginia Power as part of a comprehensive strategy to increase spent fuel storage capacity at the Station. Designed to use large, metal dry storage casks, the Surry ISFSI will accommodate 84 such casks with a total storage capacity of 811 MTU of spent PWR fuel assemblies. The ISFSI is located at the Surry Station in a wooded area approximately 1000 meters (3300 feet) east of the reactor facilities. Construction of the first of three reinforced concrete storage pads and its associated support systems was completed in March 1986. The operating license and Technical Specifications were issued by the US NRC on July 2, 1986. Initial loading operations of a General Nuclear Systems, Inc., CASTOR V/21 storage cask began in September 1986. The first two CASTOR V/21 casks were placed in storage at the ISFSI in December 1986. 16 refs., 33 figs., 16 tabs

  8. Ten-yearly report on operations at the Garigliano nuclear power station

    International Nuclear Information System (INIS)

    1977-01-01

    This document is the final report on operation of the Garigliano Nuclear Power Station as required under the participation contract between Enel and Euratom and refers to the first ten years of commercial operation (1 May 1964-31 December 1973) of the power station. In the decade in question the Garigliano Power Station has assumed an important position in the world spectrum of nuclear energy since it was the first thermal-power reactor in the world to have irradiated considerable quantities of plutonium as a fuel in its own core for the production of energy. An experimental programme on this was started in 1966 with theoretical study of plutonium recycling and was followed by the charging of the Garigliano reactor with some mixed oxide elements (PuO 2 -UO 2 ) in 1968 and 1970. The excellent performance of these prototype elements, which among other things were examined in detail at the end of each radiation cycle, prompted Enel to decide in favour of the use of entire batches of recycled fuel elements of the PuO 2 -UO 2 type in the reactor from 1975 onwards

  9. Accidents in the operation of nuclear power stations. Action for damages against foreign operators

    International Nuclear Information System (INIS)

    Willner, K.

    1986-01-01

    On the occasion of a lecture evening of the Leo Goodman Library in Munich questions of civil liability of foreign reactor operators in cases of nuclear accidents were discussed by participants of various universities. Special subjects were i.a. problems of civil procedural and insurance law, absolute liability according to sec. 25 Atomic Energy Act as well as questions of applicable law. (WG) [de

  10. Space Station Freedom assembly and operation at a 51.6 degree inclination orbit

    Science.gov (United States)

    Troutman, Patrick A.; Brewer, Laura M.; Heck, Michael L.; Kumar, Renjith R.

    1993-01-01

    This study examines the implications of assembling and operating Space Station Freedom at a 51.6 degree inclination orbit utilizing an enhanced lift Space Shuttle. Freedom assembly is currently baselined at a 220 nautical mile high, 28.5 degree inclination orbit. Some of the reasons for increasing the orbital inclination are (1) increased ground coverage for Earth observations, (2) greater accessibility from Russian and other international launch sites, and (3) increased number of Assured Crew Return Vehicle (ACRV) landing sites. Previous studies have looked at assembling Freedom at a higher inclination using both medium and heavy lift expendable launch vehicles (such as Shuttle-C and Energia). The study assumes that the shuttle is used exclusively for delivering the station to orbit and that it can gain additional payload capability from design changes such as a lighter external tank that somewhat offsets the performance decrease that occurs when the shuttle is launched to a 51.6 degree inclination orbit.

  11. Amateur Radio on the International Space Station - the First Operational Payload on the ISS

    Science.gov (United States)

    Bauer, F. H.; McFadin, L.; Steiner, M.; Conley, C. L.

    2002-01-01

    As astronauts and cosmonauts have adapted to life on the International Space Station (ISS), they have found Amateur Radio and its connection to life on Earth to be a constant companion and a substantial psychological boost. Since its first use in November 2000, the first five expedition crews have utilized the amateur radio station in the FGB to talk to thousands of students in schools, to their families on Earth, and to amateur radio operators around the world. Early in the development of ISS, an international organization called ARISS (Amateur Radio on the International Space Station) was formed to coordinate the construction and operation of amateur radio (ham radio) equipment on ISS. ARISS represents a melding of the volunteer teams that have pioneered the development and use of amateur radio equipment on human spaceflight vehicles. The Shuttle/Space Amateur Radio Experiment (SAREX) team enabled Owen Garriott to become the first astronaut ham to use amateur radio from space in 1983. Since then, amateur radio teams in the U.S. (SAREX), Germany, (SAFEX), and Russia (Mirex) have led the development and operation of amateur radio equipment on board NASA's Space Shuttle, Russia's Mir space station, and the International Space Station. The primary goals of the ARISS program are fourfold: 1) educational outreach through crew contacts with schools, 2) random contacts with the Amateur Radio public, 3) scheduled contacts with the astronauts' friends and families and 4) ISS-based communications experimentation. To date, over 65 schools have been selected from around the world for scheduled contacts with the orbiting ISS crew. Ten or more students at each school ask the astronauts questions, and the nature of these contacts embodies the primary goal of the ARISS program, -- to excite student's interest in science, technology and amateur radio. The ARISS team has developed various hardware elements for the ISS amateur radio station. These hardware elements have flown to ISS

  12. 75 FR 3622 - Revisions to Rules Authorizing the Operation of Low Power Auxiliary Stations in the 698-806 MHz...

    Science.gov (United States)

    2010-01-22

    ... translators, and Class A stations are continuing to operate in the 700 MHz Band after the transition. The..., marketing, and packaging materials, including online materials, related to such devices. The labeling must... display (including online display) any low power auxiliary stations, including wireless microphones, that...

  13. 75 FR 3639 - Revisions to Rules Authorizing the Operation of Low Power Auxiliary Stations in the 698-806 MHz...

    Science.gov (United States)

    2010-01-22

    .... 10-24; DA 10-92] Revisions to Rules Authorizing the Operation of Low Power Auxiliary Stations in the... Auxiliary Stations, Including Wireless Microphones, and the Digital Television Transition AGENCY: Federal... language that must be used in the consumer disclosure that is required by Section 15.216 of Appendix B in...

  14. Emergency operating instruction improvements at San Onofre Nuclear Generating Station Units 2 and 3

    International Nuclear Information System (INIS)

    Trillo, M.W.; Smith, B.H.

    1989-01-01

    In late 1987, San Onofre nuclear generating station (SONGS) began an extensive upgrade of the units 2 and 3 emergency operating instructions (EOIs). The original intent of this program was to incorporate revised generic guidance and to correct problems that were identified by operators. While this program was in progress, the US Nuclear Regulatory Commission (NRC) conducted a series of audits of emergency operating procedure (EOP) development and maintenance programs as 16 commercial nuclear facilities in the United States. These audits included four stations with Combustion Engineering-designed nuclear steam supply systems. (One of these audits included a review of preupgrade SONGS units 2 and 3 EOIs.) Significant industrywide comments resulted from these audits. The NRC has stated its intent to continue the review and audit of EOIs and the associated maintenance programs at all US commercial nuclear facilities. The units 2 and 3 EOI upgrade program developed procedural improvements and procedural program maintenance improvements that address many of the existing audit comments that have been received by the industry. Other resulting improvements may be useful in minimizing NRC comments in future such audits. Specific improvements are discussed. The upgrade program resulted in benefits that were not originally anticipated. The results of this program can be of significant use by other utilities in addressing the industrywide concerns that have been raised in recent NRC audits of EOP development and maintenance programs

  15. Surry Power Station, Units 1 and 2. Semiannual operating report, July--December 1974

    International Nuclear Information System (INIS)

    1974-01-01

    Net electric power generated by Surry Unit 1 was 6,930,353 MWH with the generator on line for 10,417.7 hours. Net electric power generated by Unit 2 was 5,699,299 MWH with the generator on line for 8,384.2 hours. Information is presented concerning operation, radioactive effluent releases, solid radioactive wastes, fuel shipments, occurrences in which temperature limitations on the condenser cooling water discharge were exceeded, changes in station organization, occupational personnel radiation exposure, nonradiological monitoring including thermal, physical, and biological programs, and the radiological environmental monitoring program. (U.S.)

  16. Safety evaluation report related to the operation of River Bend Station (Docket No. 50-458)

    International Nuclear Information System (INIS)

    1985-08-01

    Supplement No. 3 to the Safety Evaluation Report on the application filed by Gulf States Utilities Company as applicant and for itself and Cajun Electric Power cooperative, as owners, for a license to operate River Bend Station has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located in West Feliciana Parish, near St. Francisville, Louisiana. This supplement reports the status of certain items that had not been resolved at the time of publication of the Safety Evaluation Report, Supplement No. 1, and Supplement No. 2

  17. Commissioning and operation of distillation column at Madras Atomic Power Station (Paper No. 1.10)

    International Nuclear Information System (INIS)

    Neelakrishnan, G.; Subramanian, N.

    1992-01-01

    In Madras Atomic Power Station (MAPS), an upgrading plant based on vacuum distillation was constructed to upgrade the downgraded heavy water collected in vapor recovery dryers. There are two distillation columns and each having a capacity of 77.5 tonne per annum of reactor grade heavy water with average feed concentration of 30% IP. The performance of the distillation columns has been very good. The column I and column II have achieved an operating factor of 92% and 90% respectively. The commissioning activities, and subsequent improvements carried out in the distillation columns are described. (author)

  18. Design and development of a Space Station proximity operations research and development mockup

    Science.gov (United States)

    Haines, Richard F.

    1986-01-01

    Proximity operations (Prox-Ops) on-orbit refers to all activities taking place within one km of the Space Station. Designing a Prox-Ops control station calls for a comprehensive systems approach which takes into account structural constraints, orbital dynamics including approach/departure flight paths, myriad human factors and other topics. This paper describes a reconfigurable full-scale mock-up of a Prox-Ops station constructed at Ames incorporating an array of windows (with dynamic star field, target vehicle(s), and head-up symbology), head-down perspective display of manned and unmanned vehicles, voice- actuated 'electronic checklist', computer-generated voice system, expert system (to help diagnose subsystem malfunctions), and other displays and controls. The facility is used for demonstrations of selected Prox-Ops approach scenarios, human factors research (work-load assessment, determining external vision envelope requirements, head-down and head-up symbology design, voice synthesis and recognition research, etc.) and development of engineering design guidelines for future module interiors.

  19. Managing operations of plug-in hybrid electric vehicle (PHEV) exchange stations for use with a smart grid

    International Nuclear Information System (INIS)

    Nurre, Sarah G.; Bent, Russell; Pan, Feng; Sharkey, Thomas C.

    2014-01-01

    We consider a deterministic integer programming model for determining the optimal operations of multiple plug-in hybrid electric vehicle (PHEV) battery exchange stations over time. The operations include the number of batteries to charge, discharge, and exchange at each point in time over a set time horizon. We allow discharging of batteries back to the power grid, through vehicle-to-grid technology. We incorporate the exchange station's dependence on the power network, transportation network, and other exchange stations. The charging and discharging at these exchange stations lead to a greater amount of variability which creates a less predictable and flat power generation curve. We introduce and test three policies to smooth the power generation curve by balancing its load. Further, tests are conducted evaluating these policies while factoring wind energy into the power generation curve. These computational tests use realistic data and analysis of the results suggest general operating procedures for exchange stations and evaluate the effectiveness of these power flattening policies. - Highlights: • Model the operations of plug-in hybrid electric vehicle battery exchange stations. • Determine the optimal and general charging, discharging, and exchange operations. • Conclude that forced customer service levels are unnecessary with proper pricing. • Examine policies to reduce variability in power generation from PHEVs and wind. • Observe that strict constraints on exchange stations best reduce variability

  20. Operating Experience with Nuclear Power Stations in Member States in 2012. 2013 Edition (CD-ROM)

    International Nuclear Information System (INIS)

    2013-07-01

    This report is the forty-fourth in the IAEA’s series of annual reports on operating experience with nuclear power stations in Member States. This report provides annual performance data and outage information for individual nuclear power plants from around the world. Summaries of historical performance and outages during the lifetimes of those plants are also included. Additionally, in order to provide a broad picture of nuclear power usage, this report contains six figures that illustrate global operational statistics through 2012. The report is a direct output from the IAEA’s Power Reactor Information System (PRIS), whose databank contains all operating experience data published in the IAEA’s operating experience annual reports since 1970 and basic information on power reactors, including design data. It presents operating experience data for all worldwide nuclear power plants after starting commercial operation. The PRIS databank is available free of charge to IAEA Member States through its public website and on-line application PRIS-Statistics. The web-site www.iaea.org/pris contains publicly available information about reactor units and nuclear industry results. The PRIS-Statistics (http://pris.iaea.org) allows direct access to the database through the Internet. This application allows registered users report generation through pre-designed reports and filters

  1. Using Distributed Operations to Enable Science Research on the International Space Station

    Science.gov (United States)

    Bathew, Ann S.; Dudley, Stephanie R. B.; Lochmaier, Geoff D.; Rodriquez, Rick C.; Simpson, Donna

    2011-01-01

    In the early days of the International Space Station (ISS) program, and as the organization structure was being internationally agreed upon and documented, one of the principal tenets of the science program was to allow customer-friendly operations. One important aspect of this was to allow payload developers and principle investigators the flexibility to operate their experiments from either their home sites or distributed telescience centers. This telescience concept was developed such that investigators had several options for ISS utilization support. They could operate from their home site, the closest telescience center, or use the payload operations facilities at the Marshall Space Flight Center in Huntsville, Alabama. The Payload Operations Integration Center (POIC) processes and structures were put into place to allow these different options to its customers, while at the same time maintain its centralized authority over NASA payload operations and integration. For a long duration space program with many scientists, researchers, and universities expected to participate, it was imperative that the program structure be in place to successfully facilitate this concept of telescience support. From a payload control center perspective, payload science operations require two major elements in order to make telescience successful within the scope of the ISS program. The first element is decentralized control which allows the remote participants the freedom and flexibility to operate their payloads within their scope of authority. The second element is a strong ground infrastructure, which includes voice communications, video, telemetry, and commanding between the POIC and the payload remote site. Both of these elements are important to telescience success, and both must be balanced by the ISS program s documented requirements for POIC to maintain its authority as an integration and control center. This paper describes both elements of distributed payload

  2. Measurement uncertainty recapture (MUR) power uprates operation at Kuosheng Nuclear Power Station

    International Nuclear Information System (INIS)

    Chang Chinjang; Wang Tunglu; Lin Chihpao

    2009-01-01

    Measurement Uncertainty Recapture PowerUprates (MUR PU) are achieved through the use of state-of-the-art feedwater flow measurement devices, i.e., ultrasonic flow meters (UFMs), that reduce the degree of uncertainty associated with feedwater flow measurement and in turn provide for a more accurate calculation of thermal power. The Institute of Nuclear Energy Research (INER) teamed with Sargent and Lundy, LLC (S and L), Pacific Engineers and Constructors, Ltd (PECL), and AREVA to develop a program and plan for the Kuosheng Nuclear Power Station (KNPS) MUR PU Engineering Service Project and for the assistance to Kuosheng MUR PU operation. After regulator's approval of the licensing requests, KSNPS conducted the power ascension test and switchover to the new rated thermal power for Unit 2 and Unit 1 on 7/7/2007 and 11/30/2007, respectively. From then on, KNPS became the first nuclear power plant implementing MUR PU operation in Taiwan and in Asia. (author)

  3. The International Space Station: Operations and Assembly - Learning From Experiences - Past, Present, and Future

    Science.gov (United States)

    Fuller, Sean; Dillon, William F.

    2006-01-01

    As the Space Shuttle continues flight, construction and assembly of the International Space Station (ISS) carries on as the United States and our International Partners resume the building, and continue to carry on the daily operations, of this impressive and historical Earth-orbiting research facility. In his January 14, 2004, speech announcing a new vision for America s space program, President Bush ratified the United States commitment to completing construction of the ISS by 2010. Since the launch and joining of the first two elements in 1998, the ISS and the partnership have experienced and overcome many challenges to assembly and operations, along with accomplishing many impressive achievements and historical firsts. These experiences and achievements over time have shaped our strategy, planning, and expectations. The continual operation and assembly of ISS leads to new knowledge about the design, development and operation of systems and hardware that will be utilized in the development of new deep-space vehicles needed to fulfill the Vision for Exploration and to generate the data and information that will enable our programs to return to the Moon and continue on to Mars. This paper will provide an overview of the complexity of the ISS Program, including a historical review of the major assembly events and operational milestones of the program, along with the upcoming assembly plans and scheduled missions of the space shuttle flights and ISS Assembly sequence.

  4. Human Error and the International Space Station: Challenges and Triumphs in Science Operations

    Science.gov (United States)

    Harris, Samantha S.; Simpson, Beau C.

    2016-01-01

    Any system with a human component is inherently risky. Studies in human factors and psychology have repeatedly shown that human operators will inevitably make errors, regardless of how well they are trained. Onboard the International Space Station (ISS) where crew time is arguably the most valuable resource, errors by the crew or ground operators can be costly to critical science objectives. Operations experts at the ISS Payload Operations Integration Center (POIC), located at NASA's Marshall Space Flight Center in Huntsville, Alabama, have learned that from payload concept development through execution, there are countless opportunities to introduce errors that can potentially result in costly losses of crew time and science. To effectively address this challenge, we must approach the design, testing, and operation processes with two specific goals in mind. First, a systematic approach to error and human centered design methodology should be implemented to minimize opportunities for user error. Second, we must assume that human errors will be made and enable rapid identification and recoverability when they occur. While a systematic approach and human centered development process can go a long way toward eliminating error, the complete exclusion of operator error is not a reasonable expectation. The ISS environment in particular poses challenging conditions, especially for flight controllers and astronauts. Operating a scientific laboratory 250 miles above the Earth is a complicated and dangerous task with high stakes and a steep learning curve. While human error is a reality that may never be fully eliminated, smart implementation of carefully chosen tools and techniques can go a long way toward minimizing risk and increasing the efficiency of NASA's space science operations.

  5. The Impact of Climatological Conditions on Low Enriched Uranium Loading Station Operations for the HEU Blend Down Project

    International Nuclear Information System (INIS)

    Chang, R.C.

    2002-01-01

    A computer model was developed using COREsim to perform a time motion study for the Low Enriched Uranium (LEU) Loading Station operations. The project is to blend Highly Enriched Uranium (HEU) with Natural Uranium (NU) to produce LEU to be shipped to Tennessee Valley Authority (TVA) for further processing. To cope with a project cost reduction, the LEU Loading Station concept has changed from an enclosed building with air-conditioning to a partially enclosed building without air conditioning. The LEU Loading Station is within a radiological contaminated area; two pairs of coveralls and negative pressure respirator are required. As a result, inclement weather conditions, especially heat stress, will affect and impact the LEU loading operations. The purposes of the study are to determine the climatological impacts on LEU Loading operations, resources required for committed throughputs, and to find out the optimum process pathways for multi crews working simultaneously in the space-lim ited LEU Loading Station

  6. The approach associated with the continued operation of the Calder Hall and Chapelcross nuclear power stations to 50 years

    International Nuclear Information System (INIS)

    Ayres, G.

    1996-01-01

    Calder Hall was the world's first commercial nuclear power station, commencing operation in 1956, and with its sister station at Chapelcross has operated successfully, with consistently high load factors, for approximately 40 years. The first part of this paper reviews the operating history of the stations. Secondly, the paper will briefly describe both the work carried out under the Long Term Safety Review which has supported operation to 40 years and the work being carried out as part of a Periodic Safety Review to support continued operation of both stations to 50 years. The commercial improvements, some of which, of course, do have some nuclear safety significance, will be briefly described in the context of operating within what is increasingly becoming a demanding privatized electricity market in the United Kingdom. Finally, potential life limiting features will be identified and the monitoring programmes described leading to the conclusion that there is no reason why the stations should not continue to operate to at least 50 years. (author). 4 refs

  7. Experience of remote under water handling operations at Tarapur Atomic Power Station

    International Nuclear Information System (INIS)

    Agarwal, S.K.

    1990-01-01

    Each Refuelling outage of Tarapur Atomic Power Station Reactors involves a great deal of remote underwater handling operations using special remote handling tools, working deep down in the reactor vessel under about sixty feet of water and in the narrow confines of highly radioactive core. The remote underwater handling operations include incore and out of core sipping operations, fuel reloading or shuffling, uncoupling of control rod drives, replacement and shuffling of control blades, replacement of local power range monitors, spent fuel shipment in casks, retrieval of fallen or displaced fuel top guide spacers, orifices and their installation, underwater CCTV inspection of reactor internals, core verification, channelling and dechannelling of fuel bundles, inspection of fuel bundles and channels, unbolting and removal of old racks, installation of high density racks, removal and reinstallation of fuel support plugs and guide tubes, underwater cutting of irradiated hardware material and their disposal, fuel reconstitution, removal and reinstallation of system dryer separator etc.. The paper describes in brief the salient experience of remote underwater handling operations at TAPS especially the unusual problems faced and solved, by using special tools, employing specific techniques and by repeated efforts, patience, ingenuity and skills. (author). 10 figs

  8. Operating experience with nuclear power stations in Member States in 1997

    International Nuclear Information System (INIS)

    1998-12-01

    This report is twenty-ninth in the IAEA series of annual reports on operating experience with nuclear power stations in Member States. The report is a direct output from the Agency's Power Reactor Information System (PRIS), whose database contains all operating experience data published in Agency's operating experience annual reports published since 1971 and basic information on power reactors, including design data. According to the information available to the Agency at the end of 1997, there were 437 nuclear power reactors having a total capacity of 351795 MW(e). During 1997 three new reactors having total capacity of 3555 MW(e) were connected to the grid in France and the Republic of Korea. There were 36 nuclear power plants under construction in the world. Load, operation and availability factors are used as the basic performance factors. In addition to annual performance data and outage information, the report contains a historical summary of performance and outages during the lifetime of individual plants and five figures illustrating worldwide performance and statistical data

  9. Addressing Challenges to the Design & Test of Operational Lighting Environments for the International Space Station

    Science.gov (United States)

    Clark, Toni A.

    2014-01-01

    In our day to day lives, the availability of light, with which to see our environment, is often taken for granted. The designers of land based lighting systems use sunlight and artificial light as their toolset. The availability of power, quantity of light sources, and variety of design options are often unlimited. The accessibility of most land based lighting systems makes it easy for the architect and engineer to verify and validate their design ideas. Failures with an implementation, while sometimes costly, can easily be addressed by renovation. Consider now, an architectural facility orbiting in space, 260 miles above the surface of the earth. This human rated architectural facility, the International Space Station (ISS) must maintain operations every day, including life support and appropriate human comforts without fail. The facility must also handle logistics of regular shipments of cargo, including new passengers. The ISS requires accommodations necessary for human control of machine systems. Additionally, the ISS is a research facility and supports investigations performed inside and outside its livable volume. Finally, the facility must support remote operations and observations by ground controllers. All of these architectural needs require a functional, safe, and even an aesthetic lighting environment. At Johnson Space Center, our Habitability and Human Factors team assists our diverse customers with their lighting environment challenges, via physical test and computer based analysis. Because of the complexity of ISS operational environment, our team has learned and developed processes that help ISS operate safely. Because of the dynamic exterior lighting environment, uses computational modeling to predict the lighting environment. The ISS' orbit exposes it to a sunrise every 90 minutes, causing work surfaces to quickly change from direct sunlight to earthshine to total darkness. Proper planning of vehicle approaches, robotics operations, and crewed

  10. Preparedness of fire safety in underground train station: Comparison between train operators in Malaysia with other operators from the developed countries

    Science.gov (United States)

    Tajedi, Noor Aqilah A.; Sukor, Nur Sabahiah A.; Ismail, Mohd Ashraf M.; Shamsudin, Shahrul A.

    2017-10-01

    The purpose of this paper is to compare the fire evacuation plan and preparation at the underground train stations in the different countries. The methodology for this study was using the extended questionnaire survey to investigate the Rapid Rail Sdn Bhd, Malaysia's fire safety plan and preparation at the underground train stations. There were four sections in the questionnaire which included (i) background of the respondents, (ii) the details on the train stations, safety instruction and fire evacuation exercises (iii) technical systems, installation and equipment at the underground stations and (iv) procedures and technical changes related to fire safety that had been applied by the operators. Previously, the respondents from the different train operator services in the developed countries had completed the questionnaires. This paper extends the response from the Rapid Rail Sdn Bhd to compare the emergency procedures and preparation for fire event with the developed countries. As a result, this study found that the equipment and facilities that provided at the underground train stations that operated by Rapid Rail are relevant for fire safety procedures and needs. The main advantage for Rapid Rail is the underground stations were designed with two or more entrances/exits that may perform better evacuation compare to one main entrance/exit train stations in the other developed countries.

  11. Metrological and operational performance of measuring systems used in vehicle compressed natural gas filling stations

    Energy Technology Data Exchange (ETDEWEB)

    Velosa, Jhonn F.; Abril, Henry; Garcia, Luis E. [CDT de GAS (Venezuela). Gas Technological Development Center Corporation

    2008-07-01

    Corporation CDT GAS financially supported by the Colombian government through COLCIENCIAS, carried out a study aimed at designing, developing and implementing in Colombia a calibration and metrological verification 'specialized service' for gas meters installed at dispensers of filling stations using compressed natural gas. The results permitted the identification of improving opportunities (in measuring systems, equipment and devices used to deliver natural gas) which are focused on achieving the highest security and reliability of trading processes of CNG for vehicles. In the development of the first stage of the project, metrological type variables were initially considered, but given the importance of the measuring system and its interaction with the various elements involving gas supply to the filling station, the scope of the work done included aspects related to the operational performance, that is, those influencing the security of the users and the metrological performance of the measuring system. The development of the second stage counted on the collaboration of national companies from the sector of CNG for vehicles, which permitted the carrying out of multiple calibrations to the measuring systems installed in the CNG dispensers, thus achieving, in a concrete way, valid and reliable technological information of the implemented procedures. (author)

  12. Influence of Trash-Barriering on Operation of Pumping Station with Wet-Pits

    Directory of Open Access Journals (Sweden)

    Baoyun Qiu

    2014-04-01

    Full Text Available Trash racks are set before inlet sumps of a pumping station with wet-pits in order to block trash. The flow fields before and behind the trash rack were numerically simulated and flow fields in the inlet sump were calculated using the simulated velocity distribution of the section behind the trash rack as the inlet boundary condition. Local head loss of trash-barriering increases with the increase of blockage ratio of the trash rack. When waterweeds block upper part of the trash rack, flow pattern behind the trash rack will be extremely turbulent, flow velocity of lower part of inlet section of inlet sump will increase, flow velocity of the upper part will decrease, and even backflow appears, which will deteriorate the flow pattern and increase head loss in the inlet sump. Trash-barriering has little effect on velocity distribution of impeller inlet section. Trash-barriering will not only increase head and power of the pump but also decrease the flow. For the example of the pumping station: when blockage ratios of the trash racks are 0.3, 0.5, and 0.7, operating cost will increase by 13%~43% than that of without trash racks. Therefore, the trash rack should be cleaned up timely.

  13. Short-term optimal operation of Three-gorge and Gezhouba cascade hydropower stations in non-flood season with operation rules from data mining

    International Nuclear Information System (INIS)

    Ma Chao; Lian Jijian; Wang Junna

    2013-01-01

    Highlights: ► Short-term optimal operation of Three-gorge and Gezhouba hydropower stations was studied. ► Key state variable and exact constraints were proposed to improve numerical model. ► Operation rules proposed were applied in population initiation step for faster optimization. ► Culture algorithm with difference evolution was selected as optimization method. ► Model and method proposed were verified by case study with feasible operation solutions. - Abstract: Information hidden in the characteristics and relationship data of a cascade hydropower stations can be extracted by data-mining approaches to be operation rules and optimization support information. In this paper, with Three-gorge and Gezhouba cascade hydropower stations as an example, two operation rules are proposed due to different operation efficiency of water turbines and tight water volume and hydraulic relationship between two hydropower stations. The rules are applied to improve optimization model with more exact decision and state variables and constraints. They are also used in the population initiation step to develop better individuals with culture algorithm with differential evolution as an optimization method. In the case study, total feasible population and the best solution based on an initial population with an operation rule can be obtained with a shorter computation time than that of a pure random initiated population. Amount of electricity generation in a dispatch period with an operation rule also increases with an average increase rate of 0.025%. For a fixed water discharge process of Three-gorge hydropower station, there is a better rule to decide an operation plan of Gezhouba hydropower station in which total hydraulic head for electricity generation is optimized and distributed with inner-plant economic operation considered.

  14. Organization, Management and Function of International Space Station (ISS) Multilateral Medical Operations

    Science.gov (United States)

    Duncan, James M.; Bogomolov, V. V.; Castrucci, F.; Koike, Y.; Comtois, J. M.; Sargsyan, A. E.

    2007-01-01

    Long duration crews have inhabited the ISS since November of 2000. The favorable medical outcomes of its missions can be largely attributed to sustained collective efforts of all ISS Partners medical organizations. In-flight medical monitoring and support, although crucial, is just a component of the ISS system of Joint Medical Operations. The goal of this work is to review the principles, design, and function of the multilateral medical support of the ISS Program. The governing documents, which describe the relationships among all ISS partner medical organizations, were evaluated, followed by analysis of the roles, responsibilities, and decision-making processes of the ISS medical boards, panels, and working groups. The degree of integration of the medical support system was evaluated by reviewing the multiple levels of the status reviews and mission assurance activities carried out throughout the last six years. The Integrated Medical Group, consisting of physicians and other essential personnel in the mission control centers represents the front-line medical support of the ISS. Data from their day-to-day activities are presented weekly at the Space Medicine Operations Team (SMOT), where known or potential concerns are addressed by an international group of physicians. A broader status review is conducted monthly to project the state of crew health and medical support for the following month, and to determine measures to return to nominal state. Finally, a comprehensive readiness review is conducted during preparations for each ISS mission. The Multilateral Medical Policy Board (MMPB) issues medical policy decisions and oversees all health and medical matters. The Multilateral Space Medicine Board (MSMB) certifies crewmembers and visitors for training and space flight to the Station, and physicians to practice space medicine for the ISS. The Multilateral Medical Operations Panel (MMOP) develops medical requirements, defines and supervises implementation of

  15. Design of the system of maintenance operations occupational safety and health database application of nuclear power station

    International Nuclear Information System (INIS)

    Wang Xuehong; Li Xiangyang; Ye Yongjun

    2011-01-01

    Based on the KKS code of building equipment in nuclear power station, this paper introduces the method of establishing the system of maintenance operation occupational safety and health database application. Through the application system of maintenance occupational safety and health database, it can summarize systematically all kinds of maintenance operation dangerous factor of nuclear power station, and make a convenience for staff to learn the maintenance operation dangerous factors and the prevention measures, so that it can achieve the management concept of 'precaution crucial, continuous improvement' that advocated by OSHMS. (authors)

  16. 78 FR 32278 - Vogtle Electric Generating Station, Units 3 and 4; Southern Nuclear Operating Company; Change to...

    Science.gov (United States)

    2013-05-29

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

  17. Application of wire electrodes in electric discharge machining of metal samples of reactor blocks of the operative atomic power station

    International Nuclear Information System (INIS)

    Gozhenko, S.V.

    2007-01-01

    Features of application of electroerosive methods are considered during the process of direct definition of properties of metal of the equipment of power units of the atomic power station. Results of development of a complex of the equipment for wire electric discharge machining of metal templet and its use are presented at the control of the basic metal of the main circulating pipelines over blocks of the atomic power station of Ukraine over long terms of operation

  18. Annual report of operation management in nuclear power stations, fiscal year 1985. Showa 60 nendo genshiryoku hatsudensho unten kanri nenpo

    Energy Technology Data Exchange (ETDEWEB)

    1986-01-01

    Twenty years have elapsed since the first practical nuclear reactor in Japan started the operation. In the generated power in fiscal year 1985, that of nuclear power stations for the first time overtook that of thermal power stations, and now the age of nuclear power as the main and oil power as the subordinate has begun. As of the end of fiscal year 1985, there were 32 nuclear power plants in operation, having total output capacity of 24.521 million kW. In fiscal year 1985, nuclear power plants generated about 159 billion kWh, which is about 2 % of electric power supply. As to the capacity factor, 76% was attained in fiscal year 1985, and this is ranked in the top group of LWR-operating countries in the world. It showed that the Japanese technology of nuclear power generation is at the top level in the world. However, in order to increase nuclear power generation and to accomplish the role of main electric power source hereafter, it is necessary to further increase the reliability and economical efficiency. The list of nuclear power stations in Japan, the state of operation of nuclear power stations, the state of accidents and troubles, the state of regular inspection, the management of radioactive wastes and the radiation exposure of workers in nuclear power stations, the operational management and others are reported.

  19. Operating experience with nuclear power stations in Member States in 2002

    International Nuclear Information System (INIS)

    2003-11-01

    This report is the thirty-fourth in the Agency's series of annual reports on operating experience with nuclear power stations in Member States. The report is a direct output from the Agency's Power Reactor Information System (PRIS), whose database contains all operating experience data published in the Agency's operating experience annual reports since 1971 and basic information on power reactors, including design data. It presents operating experience data for all worldwide nuclear power plants after starting commercial operation. The PRIS databank is available free of charge to IAEA Member States through its two services: PRIS-PC and MicroPRIS. The PRIS-PC allows direct access to the database via telephone lines or through the Internet. The MicroPRIS contains a subset of the PRIS database and is a personal computer version of PRIS data available on diskette in a form readily accessible by standard, commercially available personal computer packages. PRIS is also available in the Internet at http://www.iaea.org/programmes/a2. Load, operation and availability factors are used as the basic performance factors. Energy unavailability factors, separate for planned and unplanned unavailability, due either to causes in the plant or causes external to the plant, are used as a measure of energy lost through a unit not being available. However, some ambiguity remains in the operator reports of the unavailability data, resulting in inconsistencies in these factors. It is recognized that there is an inherent difficulty in reporting unavailability in energy with relation to a maximum capacity which may change several times during the year. In addition, there are different practices in reporting planned and unplanned unavailability among Member States. The unavailability factors in this report should therefore be used with caution. It should be noted that, for load, operation and unavailability factors, there might be differences between the data of this report and those

  20. A study of operation of station fire brigade with comparison for Japan and the U.S

    International Nuclear Information System (INIS)

    Ichiki, Kuniyasu

    2011-01-01

    With the occurrence of a fire at Kashiwazaki Kariwa No. 3 unit on a site transformer when Niigata Chuetsu Offshore Earthquake occurred in 2007, the movement of establishing station fire brigade broke out all over Japan. Fire brigade of U.S. power stations is an organization structured with the standards of clear requirements. Some of station fire event reports include examples of activation of station fire brigade. Preparing station fire brigade with good expertise is quite meaningful on the viewpoint of ruling out significant threats of fire against nuclear safety, such as Browns Ferry station fire occurred in 1975. The purpose of this study is to extract useful knowledge through making research on examples of operations of station fire brigade of both Japan and the U.S. As for fire occurrence, relatively frequent fires are seen at Japanese stations with miscellaneous components or some material for works. In the U.S., on the other hand, we can identify relatively frequent fires occurred with important equipment. This might make fire brigades of the U.S. well-prepared for fire fighting by establishing fire-coping strategies for every location in the station. Also, in some stations, fire brigade is continuously trained to enhance its firefighting and rescuing abilities. With the aspect of training of brigades, they are often assembled with devoted staff, which enable them acquiring frequent training and educations to improve their skills further. Fire fighting and rescuing are inevitably dangerous task. This is why frequent training is essential in order to prevent injuries and to keep up their motivation. Unfortunately, the circumstance for brigades in Japan is not helpful enough in experiencing special training needed for them. We have to figure out some way to get over such disadvantages. (author)

  1. Post-IOC space station: Models of operation and their implications for organizational behavior, performance and effectiveness

    Science.gov (United States)

    Danford, S.; Meindl, J.; Hunt, R.

    1985-01-01

    Issues of crew productivity during design work on space station are discussed. The crew productivity is defined almost exclusively in terms of human factors engineering and habitability design concerns. While such spatial environmental conditions are necessary to support crew performance and productivity, they are not sufficient to ensure high levels of crew performance and productivity on the post-Initial Operational Configurations (IOC) space station. The role of the organizational environment as a complement to the spatial environment for influencing crew performance in such isolated and confined work settings is examined. Three possible models of operation for post-IOC space station's organizational environment are identified and it is explained how they and space station's spatial environment will combine and interact to occasion patterns of crew behavior is suggested. A three phase program of research design: (1) identify patterns of crew behavior likely to be occasioned on post-IOC space station for each of the three models of operation; and (2) to determine proactive/preventative management strategies which could be adopted to maximize the emergence of preferred outcomes in crew behavior under each of the several spatial and organizational environment combinations.

  2. Operation and management of United Central Piping LPG supply stations in Shenzhen

    Energy Technology Data Exchange (ETDEWEB)

    Lai Yankai

    1997-11-01

    Shenzhen has based its city gas development project on the eventual conversion to natural gas supply by way of central piping LPG supply stations. To fully exploit the potential gas supply capability of every central piping station and cut down the total running cost, we have been connecting the existing supply stations and their piping system into a network, which not only provided a more reliable gas supply performance, but can greatly simplify the evacuation of gas stations from the ever-expanding downtown areas to suburbs. Through this way, the periodic gas stock held by individual stations can be transferred to storage terminal or stations of enough holding capability; the supplying distance has been much lengthened and the gas volume held in the piping system increased; gas supply covered by small stations has been shifted to new and large stations. By linking these stations, we are able to provide pipeline LP gas supply for a large area, and in the same time lay down the pipeline infrastructure for the upcoming LNG supply so that an easy conversion to LNG supply can be secured as soon as the projected LNG terminal is put to service. (au)

  3. Ecological effects of nuclear steam electric station operations on estuarine systems. Final report

    International Nuclear Information System (INIS)

    Mihursky, J.A.

    1983-01-01

    This report summarizes the findings of studies of the impact of the Calvert Cliffs Nuclear Power Plant on the aquatic biota of Chesapeake Bay. Physical findings show that the typical radial extent of influence of the discharge on the physical and chemical environment of the Bay is rather limited (< 2 km). This suggestion is bolstered by findings of phytoplankton and zooplankton studies: when effects were noted at all, they only appeared at sampling stations nearest (within 2 km of) the discharge. Also, direct entrainment effects on these groups were either small (in the case of phytoplankton) or species-specific (in the case of zooplankton). Benthos showed mixed responses to plant operations - the populations of some species were enhanced, one species was adversely affected, and others were unaffected. The major plant effect on the benthos was due to habitat resource enrichment, and the consequence was higher standing stocks (e.g., more food for fish) in the affected area. Direct plant effects on finfish are dominated by impingement. Mortality as a result of impingement, for many species, tends to be moderate to slight. Effects as a result of entrainment of eggs and larvae are limited because the Calvert Cliffs area is not a major spawning location for any species. In sum, the Calvert Cliffs plant appears to have a limited effect on the Chesapeake Bay ecosystem. 180 references, 6 figures, 18 tables

  4. Operation of a soil vapor extraction and air sparging system at a former gasoline service station

    International Nuclear Information System (INIS)

    Gromicko, G.J.; Klingensmith, R.C.; Simpson, D.K.

    1995-01-01

    Closure activities for three underground storage tanks (USTs) were conducted at Quaker State Corporation's (QSC) former service station in Conneaut, Pennsylvania as part of a property transfer during July, 1991. The facility, formerly owned by QSC, was operated from construction (early 1960's) through the sale of the property (early 1980's). Subsequent to sale of the facility, the property has been resold and the building reconfigured several times. The facility is located on a comer lot located along state highway Route 322 in the business district of Conneaut Lake as shown in Figure 1. Across the highway to the north, is Conneaut lake. The site is bordered by a residential property to the south and commercial properties on the east and west. A Pennsylvania State Game Commission Game Lands, is located approximately 150 feet southeast of the property Quaker State again became involved with the property in 1991 when the cur-rent owner attempted to sell the property and the lender for the prospective purchaser identified the presence of USTs. Subsequent to the confirmation of the USTS, UST closure activities were initiated. Subsurface investigations were conducted to delineate the extent of potential petroleum impacts and corrective actions were initiated which are on-going today

  5. Monitoring equipment environment during nuclear plant operation at Salem and Hope Creek generating stations

    International Nuclear Information System (INIS)

    Blum, A.; Smith, R.J.

    1991-01-01

    Monitoring of environmental parameters has become a significant issue for operating nuclear power plants. While the long-term benefits of plant life extension programs are being pursued with comprehensive environmental monitoring programs, the potential effect of local hot spots at various plant locations needs to be evaluated for its effect on equipment degradation and shortening of equipment qualified life. A significant benefit can be experienced from temperature monitoring when a margin exists between the design versus actual operating temperature. This margin can be translated into longer equipment qualified life and significant reduction in maintenance activities. At PSE and G, the immediate need for monitoring environmental parameters is being accomplished via the use of a Logic Beach Bitlogger. The Bitlogger is a portable data loggings system consisting of a system base, input modules and a communication software package. Thermocouples are installed on selected electrical equipment and cables are run from the thermocouples to the input module of the Bitlogger. Temperature readings are taken at selected intervals, stored in memory, and downloaded periodically to a PC software program, i.e., Lotus. The data is formatted into tabular or graphical documents. Because of their versatility, Bitloggers are being used differently at the authors Nuclear facility. At the Salem Station (2 Units-4 loop Westinghouse PWR), a battery powered, fully portable, calibrated Bitlogger is located in an accessible area inside Containment where it monitors the temperature of various electrical equipment within the Pressurizer Enclosure. It is planned that close monitoring of the local hot spot temperatures in this area will allow them to adjust and reconcile the environmental qualification of the equipment

  6. 75 FR 10833 - In the Matter of Entergy Nuclear Operations; Vermont Yankee Nuclear Power Station; Demand for...

    Science.gov (United States)

    2010-03-09

    ... NUCLEAR REGULATORY COMMISSION [Docket No. 05000271; License No. DPR-28; EA-10-034; NRC-2010-0089] In the Matter of Entergy Nuclear Operations; Vermont Yankee Nuclear Power Station; Demand for... this Demand for Information, the following information, in writing, and under oath or affirmation: 1...

  7. Autonomous rendezvous and docking operations of unmanned expendable cargo transfer vehicles (e.g. Centaur) with Space Station Freedom

    Science.gov (United States)

    Emmet, Brian R.

    1991-01-01

    This paper describes the results of the feasibility study using Centaur or other CTV's to deliver payloads to the Space Station Freedom (SSF). During this study was examined the requirements upon unmanned cargo transfer stages (including Centaur) for phasing, rendezvous, proximity operations and docking/berthing (capture).

  8. Safety evaluation report related to the operation of Shoreham Nuclear Power Station, Unit No. 1. Docket No. 50-322

    International Nuclear Information System (INIS)

    1983-02-01

    Supplement No. 3 to the Safety Evaluation Report of Long Island Lighting Company's application for a license to operate the Shoreham Nuclear Power Station, Unit 1, located in Suffolk County, New York, has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement addresses several items that have come to light since the previous supplement was issued

  9. Addressing Obsolescence in Operating Power Stations by Implementation of Safety Related Digital Upgrades Paper for Spanish Nuclear Society

    Energy Technology Data Exchange (ETDEWEB)

    Legrand, R.

    2014-07-01

    Obsolescence of Instrumentation and Controls is a major problem facing operating Nuclear Power Stations globally. AREVA is the only supplier that has supported the successful licensing, engineering, procurement, installation and commissioning of a full-scope digital Instrumentation and Control (I and C) Protection System in the United States. (Author)

  10. Operating experience with nuclear power stations in Member States in 2005

    International Nuclear Information System (INIS)

    2006-10-01

    This report is the thirty-seventh in the Agency's series of annual reports on operating experience with nuclear power stations in Member States. For the first time it is issued purely in an electronic version. The report is a direct output from the Agency's Power Reactor Information System (PRIS), whose databank contains all operating experience data published in the Agency's operating experience annual reports since 1970 and basic information on power reactors, including design data. It presents operating experience data for all worldwide nuclear power plants after starting commercial operation. The PRIS databank is available free of charge to IAEA Member States through its two services: PRIS-PC, and PRIS CD-ROM. The PRIS-PC allows direct access to the database through the Internet. The PRIS-PC on CD-ROM only includes data for reactors in operation, under construction and shutdown. It keeps the same feature as in the current front-end-tool PRIS-PC interface. This front-end-tool interface allows to search and query through pre-designed statistics. The PRIS-PC on CD-ROM contains mapping interface including a view of the world map with zooming features to country, region and site map and links to PRIS database to retrieve related (nuclear power plant) information. PRIS data and related indicators are also available on the PRIS Website: www.iaea.org/programmes/a2. It contains publicly available information about reactor units and nuclear industry results. Load, operation and availability factors are used as the basic performance indicators. Energy unavailability factors, separate for planned and unplanned unavailability, due either to causes under plant management control or external causes out of plant management control, are used as a measure of energy lost through a unit not being available. However, some ambiguity remains in the operators' reports of the unavailability data, resulting in inconsistencies in these factors. It is recognized that there is an inherent

  11. Operating experience with nuclear power stations in Member States in 2006

    International Nuclear Information System (INIS)

    2007-08-01

    This report is the thirty-eighth in the Agency's series of annual reports on operating experience with nuclear power stations in Member States. For the second time it is issued purely in an electronic version. The report is a direct output from the Agency's Power Reactor Information System (PRIS), whose databank contains all operating experience data published in the Agency's operating experience annual reports since 1970 and basic information on power reactors, including design data. It presents operating experience data for all worldwide nuclear power plants after starting commercial operation. The PRIS databank is available free of charge to IAEA Member States through its services: web-based PRIS-Statistics (http://prisweb.iaea.org/statistics/), PRIS-PC, PRIS CD-ROM and PRIS Website. The PRIS-Statistics and PRIS-PC allow direct access to the database through the Internet. The PRIS-PC on CD-ROM only includes data for reactors in operation, under construction and shutdown. It keeps the same feature as in the current front-end-tool PRIS-PC interface. This front-endtool interface allows to search and query through pre-designed statistics. PRIS data and related indicators are also available on the PRIS Website: www.iaea.org/programmes/a2. It contains publicly available information about reactor units and nuclear industry results. Load, operation and availability factors are used as the basic performance indicators. Energy unavailability factors, separate for planned and unplanned unavailability, due either to causes under plant management control or external causes out of plant management control, are used as a measure of energy lost through a unit not being available. However, some ambiguity remains in the operators' reports of the unavailability data, resulting in inconsistencies in these factors. It is recognized that there is an inherent difficulty in reporting unavailability in energy due to external causes with relation to energy losses due to load following

  12. Draft environmental statement related to the operation of Hope Creek Generating Station (Docket No. 50-354)

    International Nuclear Information System (INIS)

    Wagner, D.H.

    1984-06-01

    This report contains an assessment of the environmental impact associated with the operation of the Hope Creek Generating Station pursuant to the National Environment Policy Act of 1969 (NEPA) and Title 10 of the Code of Federal Regulations, Part 51, as amended, of the Nuclear Regulatory Commission regulations. This statement examines the environmental impacts, environmental consequences and mitigating actions, and environmental and economic benefits and costs associated with station operation. Land use and terrestrial and aquatic ecological impacts will be small. No operational impacts to historic and archeological sites are anticipated. The effects of routine operations, energy transmission, and periodic maintenance of rights-of-way and transmission facilities should not jeopardize any populations of endangered or threatened species. No significant impacts are anticipated from normal operational releases of radioactivity. The risk of radiation exposure associated with accidental release of radioactivity is very low. Socioeconomic impacts of the project are anticipated to be minimal. The action called for is the issuance of an operating license for Hope Creek Generating Station, Unit 1

  13. IAEA Leads Operational Safety Mission to Rajasthan Atomic Power Station 3 and 4

    International Nuclear Information System (INIS)

    2012-01-01

    Full text: An international team of nuclear safety experts led by the International Atomic Energy Agency (IAEA) today completed a review of safety practices at Units 3 and 4 of the Rajasthan Atomic Power Station in Rawatbhata. The team noted a series of good practices and made recommendations and suggestions to reinforce safety practices. The IAEA assembled the Operational Safety Review Team (OSART) at the request of the Government of India. Led by the IAEA's Division of Nuclear Installation Safety, the team performed an in-depth operational safety review from 29 October to 14 November 2012. The team was comprised of experts from Canada, Belgium, Finland, Germany, Romania, Slovakia, Slovenia, Sweden and the IAEA. The team conducted an in-depth review of the aspects essential to the safe operation of the Power Plant. The conclusions of the review are based on the IAEA's Safety Standards and good international practices. The review covered the areas of Management, Organization and Administration; Training; Operations; Maintenance; Technical Support; Operating Experience; Radiation Protection; Chemistry; Emergency Planning and Preparedness; and Severe Accident Management. The OSART team identified a number of good practices of the plant. These will be shared in due course by the IAEA with the global nuclear industry for consideration. Examples include the following: - The Power Plant's safety culture cultivates a constructive work environment and a sense of accountability among the Power Plant personnel, and gives its staff the opportunity to expand skills and training; - The Power Plant's Public Awareness Programme provides educational opportunities to the local community about nuclear and radiation safety; - The Power Plant has a Management of Training and Authorization system for effective management of training activities; and - The Power Plant uses testing facilities and mockups to improve the quality of maintenance work and to reduce radiation doses. The OSART

  14. Private financing and operation of a space station: Investment requirements, risk, government support and other primary business management considerations

    Science.gov (United States)

    Simon, M.

    1982-01-01

    Private investment in a manned space station is considered as an alternative to complete government sponsorship of such a program. The implications of manned space operations are discussed from a business perspective. The most significant problems and risks which would be faced by a private company involved in a space station enterprise are outlined and possible government roles in helping to overcome these difficulties suggested. Economic factors such as inflation and the rate of interest are of primary concern, but less obvious conditions such as antitrust and appropriate regulatory laws, government appropriations for space activities, and national security are also considered.

  15. Potential human factors deficiencies in the design of local control stations and operator interfaces in nuclear power plants

    International Nuclear Information System (INIS)

    Hartley, C.S.; Levy, I.S.; Fecht, B.A.

    1984-04-01

    The Pacific Northwest Laboratory has completed a project to identify human factors deficiencies in safety-significant control stations outside the control room of a nuclear power plant and to determine whether NUREG-0700, Guidelines for Control Room Design Reviews, would be sufficient for reviewing those local control stations (LCSs). The project accomplished this task by first, reviewing existing data pertaining to human factors deficiencies in LCSs involved in significant safety actions; second, surveying LCSs environments and design features at several operating nuclear power plants; and third, assessing the results of that survey relative to the contents of NUREG-0700

  16. Description of the operation and radiological impact of a spanish coastal coal-fired power station

    International Nuclear Information System (INIS)

    Corbacho, Jose A.; Baeza, Antonio; Robles, Beatriz; Mora, Juan C.; Cancio, David

    2008-01-01

    The 'Litoral' Coal-Fired Power Plant (LCFPP) is situated in the town of Carboneras (Almeria) in southern Spain. Its nominal output power is 1589 M We. The fuel used is imported sub-bituminous coal supplied by collier vessels, and unloaded in a port annexed to the plant. The climate of the area is semi-arid mediterranean, with particularly low rainfall. The plant's radiological impact was studied considering various exposure pathways for the workers and the general public. In particular, inhalation and external exposure contributions to the effective dose due to the different materials involved in the operation (coals, fly ash, and bottom ash) were evaluated. Alpha spectrometry was used to characterize radiologically the airborne particulates collected in aerosol filters at points within the installation, and to determine 210 Po levels in aerosols collected in filters placed around the power station. High resolution gamma spectrometry was used to characterize coal and ash samples from the plant, and soil samples collected outside the installation within a radius of 5 km. A dose rate monitor was used to measure the ambient dose equivalent at different points inside and outside the plant. Samples of the seawater used in the plant and of products for human consumption produced nearby were also collected and characterized radiologically. The effective dose was evaluated following a realistic approach based principally on experimental measurements and in situ observations, complemented with mathematical models when necessary. The resulting estimated effective doses for selected representative groups of workers and general public were all below the reference levels used in this work. (author)

  17. Leibstadt nuclear power station (KKL): The Future after twenty years of operation

    International Nuclear Information System (INIS)

    Schoenenberger, M.

    2005-01-01

    Switzerland's largest power plant, KKL (1 165 MW BWR), is situated on the Swiss side of the Rhine River, not far from the entry of the Aare River. In 2003, the plant generated some 17% of the electricity consumed in the country. In line with the importance of the plant, it shareholders are all major Swiss power utilities. KKL was connected to the power grid in December 1984. Its construction cost amounted to approx. euro 3 200 million. After some backfitting measures at an expense of approx. euro 200 million, the plant is now in excellent technical shape. Generating costs, which were very high in the beginning, have been greatly reduced in the meantime. This was helped by a decrease of borrowed capital, the favorable development of interest rates and, above all, the rise in annual production. This, in turn, was achieved in various programs increasing plant power, and by shortening the annual revision outages. From the coming year onward, costs could be below Eurocent 3.3/kWh. Also the organization and the staff of te plant are prepared for the future. They have demonstrated their fitness in various national and international reviews. Also the political environment is favorable, by and large. In 2003, the Swiss voting population so clearly rejected the two opt-out initiatives that there has been a lasting positive change in the policy of continuing the operation of existing plants. Also for KKL, the waste management problem is still unsolved. This is due primarily to political reasons. The envisaged repository for low-level waste was rejected in a referendum in 2003. Technically and in its organization, the Leibstadt Nuclear Power Station is ready for the future. The electricity generated at Leibstadt is desired and accepted politically. (orig.)

  18. 47 CFR 74.765 - Posting of station and operator licenses.

    Science.gov (United States)

    2010-10-01

    ... SERVICES EXPERIMENTAL RADIO, AUXILIARY, SPECIAL BROADCAST AND OTHER PROGRAM DISTRIBUTIONAL SERVICES Low... the licensee, if the licensee does not reside in the community served by the station, and the name and...

  19. Airline Operational Control (AOC)/UAS Ground Control Station (GCS) Collaboration, Phase I

    Data.gov (United States)

    National Aeronautics and Space Administration — We propose to form a network and a set of tools that will create a shared situation awareness with Unmanned Aircraft Systems (UAS) Ground Control Stations (GCSs) and...

  20. Mathematical model for estimating of technical and technological indicators of railway stations operation

    Directory of Open Access Journals (Sweden)

    D.M. Kozachenko

    2013-06-01

    Full Text Available Purpose. The article aims to create a mathematical model of the railway station functioning for the solving of problems of station technology development on the plan-schedule basis. Methodology. The methods of graph theory and object-oriented analysis are used as research methods. The model of the station activity plan-schedule includes a model of technical equipment of the station (plan-schedule net and a model of the station functioning , which are formalized on the basis of parametric graphs. Findings. The presented model is implemented as an application to the graphics package AutoCAD. The software is developed in Visual LISP and Visual Basic. Taking into account that the construction of the plan-schedule is mostly a traditional process of adding, deleting, and modifying of icons, the developed interface is intuitively understandable for a technologist and practically does not require additional training. Originality. A mathematical model was created on the basis of the theory of graphs and object-oriented analysis in order to evaluate the technical and process of railway stations indicators; it is focused on solving problems of technology development of their work. Practical value. The proposed mathematical model is implemented as an application to the graphics package of AutoCAD. The presence of a mathematical model allows carrying out an automatic analysis of the plan-schedule and, thereby, reducing the period of its creation more than twice.

  1. [The social hygiene problems in the operator work of hydroelectric power station workers and the means for enhancing work capacity].

    Science.gov (United States)

    Karakashian, A N; Lepeshkina, T R; Ratushnaia, A N; Glushchenko, S S; Zakharenko, M I; Lastovchenko, V B; Diordichuk, T I

    1993-01-01

    Weight, tension and harmfulness of professional activity, peculiarities of labour conditions and characteristics of work, shift dynamics of operative personnel's working capacity were studied in the course of 8-hour working day currently accepted at hydroelectric power stations (HEPS) and experimental 12-hour schedule. Working conditions classified as "admissible", positive dynamics of operators' state, their social and material contentment were a basis for 12-hour two-shift schedule to be recommended as more appropriate. At the same time, problem of optimal shift schedules for operative personnel of HEPS remains unsolved and needs to be further explored.

  2. An advanced automation system for operation of Sao Paulo pumping stations from TRANSPETRO Master Control Center - CNCO

    Energy Technology Data Exchange (ETDEWEB)

    Corcioli, Mario Sergio; Barreto, Camila Maria Benevenuto [TRANSPETRO, Rio de Janeiro, RJ (Brazil)

    2009-07-01

    Since 2000 the operations of the TRANSPETRO pumping stations in the state of Sao Paulo region began to be transferred from local control centers located at the transfer and storage terminals to the National Operational Control Center (CNCO) of TRANSPETRO, located at the headquarters of the company, in Rio de Janeiro. The proposed paper aims to presenting an overview of the automation system that was developed to enable such pumping stations to be operated from CNCO in a reliable and secure manner, focusing on tools that offer an embedded system alarms completely free of false alarms with automatic determining of the root cause, and also automatic and advanced diagnoses of problems caused by failures of hardware, human error and abnormal conditions of the process, providing the CNCO SCADA system of accurate and quality information that help operators to make decisions. The referred automation system was integrated for the first time to CNCO SCADA system in 2000, for pipeline pumps of Osvat (Sao Sebastiao - Vale do Paraiba pipeline) station at the Sao Sebastiao Terminal - northern coast of Sao Paulo region. (author)

  3. Materials Science Research Rack Onboard the International Space Station Hardware and Operations

    Science.gov (United States)

    Lehman, John R.; Frazier, Natalie C.; Johnson, Jimmie

    2012-01-01

    The Materials Science Research Rack (MSRR) is a research facility developed under a cooperative research agreement between NASA and ESA for materials science investigations on the International Space Station (ISS). MSRR was launched on STS-128 in August 2009, and is currently installed in the U.S. Destiny Laboratory Module. Since that time, MSRR has performed virtually flawlessly, logging more than 620 hours of operating time. The MSRR accommodates advanced investigations in the microgravity environment on the ISS for basic materials science research in areas such as solidification of metals and alloys. The purpose is to advance the scientific understanding of materials processing as affected by microgravity and to gain insight into the physical behavior of materials processing. MSRR allows for the study of a variety of materials including metals, ceramics, semiconductor crystals, and glasses. Materials science research benefits from the microgravity environment of space, where the researcher can better isolate chemical and thermal properties of materials from the effects of gravity. With this knowledge, reliable predictions can be made about the conditions required on Earth to achieve improved materials. MSRR is a highly automated facility with a modular design capable of supporting multiple types of investigations. Currently the NASA-provided Rack Support Subsystem provides services (power, thermal control, vacuum access, and command and data handling) to the ESA developed Materials Science Laboratory (MSL) which accommodates interchangeable Furnace Inserts (FI). Two ESA-developed FIs are presently available on the ISS: the Low Gradient Furnace (LGF) and the Solidification and Quenching Furnace (SQF). Sample-Cartridge Assemblies (SCAs), each containing one or more material samples, are installed in the FI by the crew and can be processed at temperatures up to 1400 C. Once an SCA is installed, the experiment can be run by automatic command or science conducted via

  4. Safety Evaluation Report related to the operation of Hope Creek Generation Station (Docket No. 50-354). Supplement No. 6

    International Nuclear Information System (INIS)

    1986-07-01

    Supplement No. 6 to the Safety Evaluation Report on the application filed by Public Service Electric and Gas Company on its own behalf as co-owner and as agent for the other co-owner, the Atlantic City Electric Company, for a license to operate Hope Creek Generating Station has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located in Lower Alloways Creek Township in Salem County, New Jersey. This supplement reports the status of certain items that has not been resolved at the time of the publication of the Safety Evaluation Report. This supplement supports the issuance of a full-power license to operate Hope Creek Generating Station

  5. Final Environmental Statement related to the operation of Beaver Valley Power Station, Unit 2 (Docket No. 50-412)

    International Nuclear Information System (INIS)

    1985-09-01

    This Final Environmental Statement contains the second assessment of the environmental impact associated with Beaver Valley Power Station Unit 2 pursuant to the National Environmental Policy Act of 1969 (NEPA) and Title 10 of the Code of Federal Regulations, Part 51, as amended, of the Nuclear Regulatory Commission regulations. This statement examines the environment, environmental consequences and mitigating actions, and environmental benefits and costs, and concludes that the action called for is the issuance of an operating license for Beaver Valley Unit 2

  6. Safety evaluation report related to the operation of Beaver Valley Power Station, Unit 2 (Docket No. 50-412)

    International Nuclear Information System (INIS)

    1987-03-01

    This report, Supplement No. 4 to the Safety Evaluation Report for the application filed by the Duquesne Light Company et al. (the applicant) for a license to operate the Beaver Valley Power Station, Unit 2 (Docket No. 50-412), has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement reports the status of certain items that had not been resolved when the Safety Evaluation Report and its Supplements 1, 2, and 3 were published

  7. Safety evaluation report related to the operation of Beaver Valley Power Station, Unit 2 (Docket No. 50-412)

    International Nuclear Information System (INIS)

    1986-05-01

    This report, Supplement No. 1 to the Safety Evaluation Report for the application filed by the Duquesne Light Company et al. (the applicant) for a license to operate the Beaver valley Power Station, Unit 2 (Docket No. 50-412), has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement reports the status of certain items that had not been resolved at the time the Safety Evaluation Report was published

  8. Draft environmental statement related to the operation of Millstone Nuclear Power Station, Unit No. 3 (Docket No. 50-423)

    International Nuclear Information System (INIS)

    1984-07-01

    This Draft Environmental Statement contains the second assessment of the environmental impact associated with the operation of Millstone Nuclear Power Station, Unit 3, pursuant to the National Environmental Policy Act of 1969 (NEPA) and Title 10 of the Code of Federal Regulations, Part 51, as amended, of the Nuclear Regulatory Commission regulations. This statement examines the environment, environmental consequences and mitigating actions, and environmental and economic benefits and costs

  9. Safety Evaluation Report related to the operation of Shoreham Nuclear Power Station, Unit No. 1 (Docket No. 50-322)

    International Nuclear Information System (INIS)

    1989-04-01

    Supplement 10 (SSER 10) to the Safety Evaluation Report on Long Island Lighting Company's application for a license to operate the Shoreham Nuclear Power Station, Unit 1, located in Suffolk County, New York, has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement addresses several items that have been reviewed by the staff since the previous supplement was issued

  10. Final environmental statement related to the operation of Clinton Power Station, Unit No. 1. Docket No. 50-461

    International Nuclear Information System (INIS)

    1982-05-01

    This final environmental statement contains the second assessment of the environmental impact associated with operation of Clinton Power Station Unit 1 pursuant to the National Environmental Policy Act of 1969 (NEPA) and 10 CFR Part 51, as amended, of the NRC's regulations. This statement examines: the affected environment, environmental consequences and mitigating actions, and environmental and economic benefits and costs. Land-use and terrestrial- and aquatic-ecological impacts will be small. Air-quality impacts will also be small. However, steam fog from the station's cooling lake has the potential for reducing visibility over nearby roads and bridges. A fog-monitoring program for roads and ridges near the lake has been recommended. Impacts to historic and prehistoric sites will be negligible. Chemical discharges to Lake Clinton and Salt Creek are expected to have no appreciable impacts on water quality under normal conditions and will be required to meet conditions of the station's NPDES permit. The hydrothermal analyses indicate that under certain meteorological conditions (1-in-50-year drought), the plant would have to be operated at reduced power levels in order to meet the thermal standards established by the Illinois Pollution Control Board Order PCB 81-82. The effects of routine operations, energy transmission, and periodic maintenance of rights-of-way and transmission line facilties should not jeopardize any populations of endangered or threatened species. No significant impacts are anticipated from normal operational releases of radioactivity. Contentions associated with environmental issues accepted during the operating-license hearing are related to assessment of effects of low-level radiation. The net socioeconomic effects of the project will be beneficial. The action called for is the issuance of an operating license for Unit 1 of Clinton

  11. Startup and first operation evaluation of the nuclear station at Fessenheim

    International Nuclear Information System (INIS)

    Leblond, Andre; Ferriole, Guy.

    1978-01-01

    Having first recalled the main characteristics of the Fessenheim power station and its different construction and startup stages, the starting tests and the difficulties encountered are described. The main results recorded and the conclusions which can be drawn are analyzed [fr

  12. 47 CFR 80.1073 - Radio operator requirements for ship stations.

    Science.gov (United States)

    2010-10-01

    .... 80.1073 Section 80.1073 Telecommunication FEDERAL COMMUNICATIONS COMMISSION (CONTINUED) SAFETY AND SPECIAL RADIO SERVICES STATIONS IN THE MARITIME SERVICES Global Maritime Distress and Safety System (GMDSS... selecting HF DSC guard channels and receiving scheduled maritime safety information broadcasts; (4...

  13. Tethered balloon operation for wintering aerosol measurements in the lower troposphere at Syowa Station, Antarctica

    OpenAIRE

    Keiichiro Hara; Kazuo Osada; Takashi Yamanouchi

    2007-01-01

    The 46th Japanese Antarctic Research Expedition (JARE-46) carried out twenty seven tethered-balloon-borne aerosol measurements at Syowa Station for better understanding of aerosol chemical and physical properties in the lower troposphere from 6th January 2005 until 11 December 2005. This report summarizes the plan, preparation, field activities and some troubles/problems in the tethered-balloon observations.

  14. Nuclear power station: validation of a method for designing operation mimic diagrams

    International Nuclear Information System (INIS)

    Colard, M.I.; De Vlaminck, M.; Javaux, D.

    1995-01-01

    This is the first time in a Belgium nuclear power station that the design of mimic diagrams has involved biotechnologists. The methodology is based upon task analysis, the formalism of which has been evaluated. It is now integrated in the Dimos assisted supervision system to produce the final design of mimic diagram images. (authors). 3 figs., 3 refs

  15. Safety evaluation report related to the operation of Millstone Nuclear Power Station, Unit No. 3 (Docket No. 50-423)

    International Nuclear Information System (INIS)

    1984-07-01

    The Safety Evaluation Report for the application filed by Northeast Nuclear Energy Company, as applicant and agent for the owners, for a license to operate the Millstone Nuclear Power Station Unit 3 (Docket No. 50-423), has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located in the town of Waterford, New London County, Connecticut, on the north shore of Long Island Sound. Subject to favorable resolution of the items discussed in this report, the NRC staff concludes that the facility can be operated by the applicant without endangering the health and safety of the public

  16. Safety Evaluation Report related to the operation of Hope Creek Generating Station (Docket No. 50-354)

    International Nuclear Information System (INIS)

    1984-10-01

    The Safety Evaluation Report for the application filed by Public Service Electric and Gas Company, as applicant, for a license to operate the Hope Creek Generating Station (Docket No. 50-354), has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located in Salem County, New Jersey. Subject to favorable resolution of the items discussed in this report, the NRC staff concludes that the facility can be operated by the applicant without endangering the health and safety of the public

  17. Safety Evaluation Report related to the operation of Beaver Valley Power Station, Unit 2 (Docket No. 50-412)

    International Nuclear Information System (INIS)

    1985-10-01

    This Safety Evaluation Report on the application filed by Duquesne Light Company, as applicant and agent for the owners, for a license to operate the Beaver Valley Power Station Unit 2 (Docket No. 50-412) has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located in Shippingport Borough, Beaver County, Pennsylvania, on the south bank of the Ohio River. Subject to the favorable resolution of the items discussed in this report, the staff concludes that the facility can be operated by the applicant without endangering the health and safety of the public

  18. HVAC modifications and computerized energy analysis for the Operations Support Building at the Mars Deep Space Station at Goldstone

    Science.gov (United States)

    Halperin, A.; Stelzmuller, P.

    1986-01-01

    The key heating, ventilation, and air-conditioning (HVAC) modifications implemented at the Mars Deep Space Station's Operation Support Building at Jet Propulsion Laboratories (JPL) in order to reduce energy consumption and decrease operating costs are described. An energy analysis comparison between the computer simulated model for the building and the actual meter data was presented. The measurement performance data showed that the cumulative energy savings was about 21% for the period 1979 to 1981. The deviation from simulated data to measurement performance data was only about 3%.

  19. RISK DECREASE PROBLEM WITH MAKING ERRORS IN ACTIVITY OF OPERATORS DEALING WITH AUTOMATIC CONTROL SYSTEMS OF GAS-DISTRIBUTION STATIONS

    Directory of Open Access Journals (Sweden)

    V. V. Egorov

    2011-01-01

    Full Text Available The paper contains an analysis of specific features pertaining to the activity of operators dealing with automatic control systems of gas-distribution stations. The professional operator’s activity is presented in the form of the developed data model. Possible conceptual approaches to the research are analyzed in the paper. The paper describes an author’s approach to studying a risk decrease problem in the activity of operators on the basis of the analytical research results. Technology for obtaining  research results is cited in the paper. 

  20. Application of modern tools and techniques to maximize engineering productivity in the development of orbital operations plans for the space station progrm

    Science.gov (United States)

    Manford, J. S.; Bennett, G. R.

    1985-01-01

    The Space Station Program will incorporate analysis of operations constraints and considerations in the early design phases to avoid the need for later modifications to the Space Station for operations. The application of modern tools and administrative techniques to minimize the cost of performing effective orbital operations planning and design analysis in the preliminary design phase of the Space Station Program is discussed. Tools and techniques discussed include: approach for rigorous analysis of operations functions, use of the resources of a large computer network, and providing for efficient research and access to information.

  1. The Hyperspectral Imager for the Coastal Ocean (HICO): Four Years Operating on the International Space Station (Invited)

    Science.gov (United States)

    Davis, C. O.; Nahorniak, J.; Tufillaro, N.; Kappus, M.

    2013-12-01

    The Hyperspectral Imager for the Coastal Ocean (HICO) is the first spaceborne imaging spectrometer designed to sample the coastal ocean. HICO images selected coastal regions at 92 m spatial resolution with full spectral coverage (88 channels covering 400 to 900 nm) and a high signal-to-noise ratio to resolve the complexity of the coastal ocean. Under sponsorship of the Office of Naval Research, HICO was built by the Naval Research Laboratory, which continues to operate the sensor. HICO has been operating on the International Space Station since October 2009 and has collected over 8000 scenes for more than 50 users. As Project Scientist I have been the link to the international ocean optics community primarily through our OSU HICO website (http://hico.oregonstate.edu). HICO operations are now under NASA support and HICO data is now also be available through the NASA Ocean Color Website (http://oceancolor.gsfc.nasa.gov ). Here we give a brief overview of HICO data and operations and discuss the unique challenges and opportunities that come from operating on the International Space Station.

  2. Final environmental statement related to the operation of Millstone Nuclear Power Station, Unit No. 3 (Docket No. 50-423)

    International Nuclear Information System (INIS)

    1984-12-01

    This Final Environmental Statement contains the second assessment of the environmental impact associated with the operation of Millstone Nuclear Power Station, Unit 3, pursuant to the National Environmental Policy Act of 1969 (NEPA) and Title 10 of the Code of Federal Regulations, Part 51, as amended, of the Nuclear Regulatory Commission regulations. This statement examines the environment, environmental consequences and mitigating actions, and environmental and economic benefits and costs. Land use and terrestrial and aquatic ecological impacts will be small. Operational impacts to historic and archeologic sites will be small. The effects of routine operations, energy transmission, and periodic maintenance of rights-of-way and transmission facilities should not jeopardize any populations of endangered or threatened species. No significant impacts are anticipated from normal operational releases of radioactivity. The risk of radiation exposure associated with accidental release of radioactivity is very low. The net socioeconomic effects of the project will be beneficial. On the basis of the analysis and evaluation set forth in this environmental statement, it is concluded that the action called for under NEPA and 10 CFR 51 is the issuance of an operating license for Millstone Nuclear Power Station, Unit 3. 101 references, 33 figures, 30 tables

  3. Experience in industrial operation of the plant for immobilizing radioactive wastes in thermosetting resins at the Ardennes Nuclear Power Station

    International Nuclear Information System (INIS)

    Haller, P.; Romestain, P.; Bruant, J.P.

    1983-01-01

    The French Atomic Energy Commission (CEA) has developed, at the Grenoble Centre for Nuclear Studies, a procedure for immobilizing low- and intermediate-level wastes in thermosetting resins of the polyester or epoxy types. To demonstrate feasibility on an industrial scale, a pilot plant has been set up at the effluent treatment station of the Ardennes Franco-Belgium Nuclear Power Station (SENA), which is a 305 MW(e) PWR type. Assembly work began in January 1979. After a period devoted to final adjustments and operation with inactive products, conditioning of active products began in January 1981. In the paper, the methods of conditioning the three types of waste (evaporation concentrates, ion exchange resins and filter cartridges) are described, experience of the start-up and operation of the plant is reported and the principal results of coating characterization tests are given. The results of tests on active and inactive products show that the characteristics of the materials obtained on an industrial scale match those of laboratory products and confirm their high quality with regard to mechanical behaviour, fire resistance, homogeneity and low-leachability. Industrial experience and economic comparisons show that the process of immobilizing waste from nuclear power stations in thermosetting resins offers an extremely interesting alternative to classical methods of conditioning. (author)

  4. Tethered balloon operation for wintering aerosol measurements in the lower troposphere at Syowa Station, Antarctica

    Directory of Open Access Journals (Sweden)

    Keiichiro Hara

    2007-03-01

    Full Text Available The 46th Japanese Antarctic Research Expedition (JARE-46 carried out twenty seven tethered-balloon-borne aerosol measurements at Syowa Station for better understanding of aerosol chemical and physical properties in the lower troposphere from 6th January 2005 until 11 December 2005. This report summarizes the plan, preparation, field activities and some troubles/problems in the tethered-balloon observations.

  5. Application of a hazard and operability study method to hazard evaluation of a chemical unit of the power station.

    Science.gov (United States)

    Habibi, E; Zare, M; Barkhordari, A; Mirmohammadi, Sj; Halvani, Ghh

    2008-12-28

    The aim of this study was to identify the hazards, evaluate their risk factors and determine the measure for promotion of the process and reduction of accidents in the chemical unit of the power station. In this case and qualitative study, HAZOP technique was used to recognize the hazards and problems of operations on the chemical section at power station. Totally, 126 deviations were documented with various causes and consequences. Ranking and evaluation of identified risks indicate that the majority of deviations were categorized as "acceptable" and less than half of that were "unacceptable". The highest calculated risk level (1B) related to both the interruption of acid entry to the discharge pumps and an increased density of the acid. About 27% of the deviations had the lowest risk level (4B). The identification of hazards by HAZOP indicates that it could, systemically, assess and criticize the process of consumption or production of acid and alkali in the chemical unit of power plant.

  6. Wisconsin Public Service, Weston Generating Station; Petition to Object to Issuance of Title V Operating Permit

    Science.gov (United States)

    This document may be of assistance in applying the Title V air operating permit regulations. This document is part of the Title V Petition Database available at www2.epa.gov/title-v-operating-permits/title-v-petition-database.

  7. Dresden Nuclear Power Station, Units 1, 2, and 3. Annual operating report: January--December 1977

    International Nuclear Information System (INIS)

    1978-01-01

    After a summary of reactor operating experiences, data are presented concerning amendments to the operating licenses and technical specifications, changes, modifications, tests, experiments, and maintenance of safety-related equipment

  8. Selective analysis of power plant operation on the Hudson River with emphasis on the Bowline Point Generating Station. Volume 1

    International Nuclear Information System (INIS)

    Barnthouse, L.W.; Cannon, J.B.; Christensen, S.G.

    1977-07-01

    A comprehensive study of the effects of power plant operation on the Hudson River was conducted. The study included thermal, biological, and air quality effects of existing and planned electrical generating stations. This section on thermal impacts presents a comprehensive mathematical modeling and computer simulation study of the effects of heat rejection from the plants. The overall study consisted of three major parts: near-field analysis; far-field analysis; and zone-matched near-field/far-field analysis. Near-field analyses were completed for Roseton, Danskammer, and Bowline Point Generating Stations, and near-field dilution ratios range from a low of about 2 for Bowline Point and 3 for Roseton to a maximum of 6 for both plants. The far-field analysis included a critical review of existing studies and a parametric review of operating plants. The maximum thermal load case, based on hypothetical 1974 river conditions, gives the daily maximum cross-section-averaged and 2-mile-segment-averaged water temperatures as 83.80 0 F in the vicinity of the Indian Point Station and 83.25 0 F in the vicinity of the Bowline Station. This maximum case will be significantly modified if cooling towers are used at certain units. A full analysis and discussion of these cases is presented. A study of the Hudson River striped bass population is divided into the following eight subsections: distribution of striped bass eggs, larvae, and juveniles in the Hudson River; entrainment mortality factor; intake factor; impingement; effects of discharges; compensation; model estimates of percent reduction; and Hudson River striped bass stock

  9. Application of a water quality model for determining instream aeration station location and operational rules: A case study

    Directory of Open Access Journals (Sweden)

    Charles S. Melching

    2018-01-01

    Full Text Available Instream aeration has been used as a supplement to secondary treatment or a substitute for tertiary treatment for meeting dissolved oxygen (DO standards in rivers. Many studies have used water quality models to determine the number, location, and capacity of instream aeration stations (IASs needed to meet DO standards in combination with other pollution control measures. DO concentrations have been improved in the North Shore Channel and North Branch Chicago River by the Devon Avenue IAS for more than 35 years. A study was initiated to determine whether it was better to rehabilitate or relocate this station and to determine appropriate operational guidance for the IAS at the selected location. A water quality model capable of simulating DO concentrations during unsteady flow was used to evaluate the proper location for an IAS and operational guidance for this IAS. Three test years, a dry year, a wet year, and an extreme year, were considered in the evaluation. The study found that the Devon Avenue IAS should be rehabilitated as this location performed as well as or better than any of 10 alternative locations. According to the new operational guidance for this IAS, the amount of time with blowers operating could be substantially reduced compared to traditional operations while at the same time the attainment of the DO standards could be increased. This study shows that a carefully designed modeling study is key to effective selection, location, and operation of IASs such that attainment of DO standards can be maximized while operation hours of blowers can be minimized. Keywords: Instream aeration, Dissolved oxygen, Water quality modeling, Water quality management, Computer simulation

  10. 78 FR 61400 - Entergy Nuclear Operations, Inc., Pilgrim Nuclear Power Station, Issuance of Director's Decision

    Science.gov (United States)

    2013-10-03

    ... 40 years since their initial construction. The wires, and possibly the connections and splices inside conduits, are designed to operate properly only in a dry environment and are not designed to operate in a... construction. There are no existing methods to ensure operability, short of visual inspection or replacing...

  11. COMBINED CYCLE GAS TURBINE FOR THERMAL POWER STATIONS: EXPERIENCE IN DESIGNING AND OPERATION, PROSPECTS IN APPLICATION

    Directory of Open Access Journals (Sweden)

    N. V. Karnitsky

    2014-01-01

    Full Text Available The paper has reviewed main world tendencies in power consumption and power system structure. Main schemes of combined cycle gas turbines have been considered in the paper. The paper contains an operational analysis of CCGT blocks that are operating within the Belarusian energy system. The analysis results have been given in tables showing main operational indices of power blocks

  12. Analysis of gross error rates in operation of commercial nuclear power stations

    International Nuclear Information System (INIS)

    Joos, D.W.; Sabri, Z.A.; Husseiny, A.A.

    1979-01-01

    Experience in operation of US commercial nuclear power plants is reviewed over a 25-month period. The reports accumulated in that period on events of human error and component failure are examined to evaluate gross operator error rates. The impact of such errors on plant operation and safety is examined through the use of proper taxonomies of error, tasks and failures. Four categories of human errors are considered; namely, operator, maintenance, installation and administrative. The computed error rates are used to examine appropriate operator models for evaluation of operator reliability. Human error rates are found to be significant to a varying degree in both BWR and PWR. This emphasizes the import of considering human factors in safety and reliability analysis of nuclear systems. The results also indicate that human errors, and especially operator errors, do indeed follow the exponential reliability model. (Auth.)

  13. Possible efficiency improvement by application of various operating regimes for the cooling water pump station at thermal power plant - Bitola

    Directory of Open Access Journals (Sweden)

    Mijakovski Vladimir

    2012-01-01

    Full Text Available Thermal power plant (TPP - Bitola is the largest electricity producer in the Republic of Macedonia with installed capacity of 691 MW. It is a lignite fired power plant, in operation since 1982. Most of the installed equipment is of Russian origin. Power plant's cold end comprised of a condenser, pump station and cooling tower is depicted in the article. Possible way to raise the efficiency of the cold end by changing the operating characteristics of the pumps is presented in the article. Diagramic and tabular presentation of the working characteristics of the pumps (two pumps working in paralel for one block with the pipeline, as well as engaged power for their operation are also presented in this article.

  14. Sandia National Laboratories land use permit for operations at Oliktok Alaska Long Range Radar Station.

    Energy Technology Data Exchange (ETDEWEB)

    Catechis, Christopher Spyros

    2013-02-01

    The property subject to this Environmental Baseline Survey (EBS) is located at the Oliktok Long Range Radar Station (LRRS). The Oliktok LRRS is located at 70À 30 W latitude, 149À 53 W longitude. It is situated at Oliktok Point on the shore of the Beaufort Sea, east of the Colville River. The purpose of this EBS is to document the nature, magnitude, and extent of any environmental contamination of the property; identify potential environmental contamination liabilities associated with the property; develop sufficient information to assess the health and safety risks; and ensure adequate protection for human health and the environment related to a specific property.

  15. Empirical Requirements Analysis for Mars Surface Operations Using the Flashline Mars Arctic Research Station

    Science.gov (United States)

    Clancey, William J.; Lee, Pascal; Sierhuis, Maarten; Norvig, Peter (Technical Monitor)

    2001-01-01

    Living and working on Mars will require model-based computer systems for maintaining and controlling complex life support, communication, transportation, and power systems. This technology must work properly on the first three-year mission, augmenting human autonomy, without adding-yet more complexity to be diagnosed and repaired. One design method is to work with scientists in analog (mars-like) setting to understand how they prefer to work, what constrains will be imposed by the Mars environment, and how to ameliorate difficulties. We describe how we are using empirical requirements analysis to prototype model-based tools at a research station in the High Canadian Arctic.

  16. High-Rate Communications Outage Recorder Operations for Optimal Payload and Science Telemetry Management Onboard the International Space Station

    Science.gov (United States)

    Shell, Michael T.; McElyea, Richard M. (Technical Monitor)

    2002-01-01

    All International Space Station (ISS) Ku-band telemetry transmits through the High-Rate Communications Outage Recorder (HCOR). The HCOR provides the recording and playback capability for all payload, science, and International Partner data streams transmitting through NASA's Ku-band antenna system. The HCOR is a solid-state memory recorder that provides recording capability to record all eight ISS high-rate data during ISS Loss-of-Signal periods. NASA payloads in the Destiny module are prime users of the HCOR; however, NASDA and ESA will also utilize the HCOR for data capture and playback of their high data rate links from the Kibo and Columbus modules. Marshall Space Flight Center's Payload Operations Integration Center manages the HCOR for nominal functions, including system configurations and playback operations. The purpose of this paper is to present the nominal operations plan for the HCOR and the plans for handling contingency operations affecting payload operations. In addition, the paper will address HCOR operation limitations and the expected effects on payload operations. The HCOR is manifested for ISS delivery on flight 9A with the HCOR backup manifested on flight 11A. The HCOR replaces the Medium-Rate Communications Outage Recorder (MCOR), which has supported payloads since flight 5A.1.

  17. Wet steam turbines for nuclear generating stations -design and operating experience

    International Nuclear Information System (INIS)

    Usher, J.

    1977-01-01

    Lecture to the Institution of Nuclear Engineers, 11 Jan. 1977. The object of this lecture was to give an account of some design features of large wet steam turbines and to show by describing some recent operational experience how their design concepts were fulfilled. Headings are as follows: effects of wet steam cycle on turbine layout and operation (H.P. turbine, L.P. turbine); turbine control and operation; water separators; and steam reheaters. (U.K.)

  18. Packaging's Contribution for the Effectiveness of the Space Station's Food Service Operation

    Science.gov (United States)

    Rausch, B. A.

    1985-01-01

    Storage limitations will have a major effect on space station food service. For example: foods with low bulk density such as ice cream, bread, cake, standard type potato chips and other low density snacks, flaked cereals, etc., will exacerbate the problem of space limitations; package containers are inherently volume consuming and refuse creating; and the useful observation that the optimum package is no package at all leads to the tentative conclusion that the least amount of packaging per unit of food, consistent with storage, aesthetics, preservation, cleanliness, cost and disposal criteria, is the most practical food package for the space station. A series of trade offs may have to be made to arrive at the most appropriate package design for a particular type of food taking all the criteria into account. Some of these trade offs are: single serve vs. bulk; conventional oven vs. microwave oven; nonmetallic aseptically vs. non-aseptically packaged foods; and comparison of aseptic vs. nonaseptic food packages. The advantages and disadvantages are discussed.

  19. Safety Evaluation Report related to the operation of Beaver Valley Power Station, Unit 2 (Docket No. 50-412)

    International Nuclear Information System (INIS)

    1987-05-01

    This report, Supplement No. 5 to the Safety Evaluation Report for the application filed by the Duquesne Light Company et al. (the applicant) for a license to operate the Beaver Valley Power Station, Unit 2 (Docket No. 50-412), has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement reports the status of certain items that had not been resolved when the Safety Evaluation Report and its Supplements 1, 2, 3, and 4 were published

  20. Safety Evaluation Report related to the operation of Clinton Power Station, Unit No. 1, Docket No. 50-461

    International Nuclear Information System (INIS)

    1983-05-01

    Supplement No. 2 to the Safety Evaluation Report on the application filed by Illinois Power Company, Soyland Power Cooperative, Inc., and Western Illinois Power Cooperative, Inc., as applicants and owners, for a license to operate the Clinton Power Station, Unit No. 1, has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located in Harp Township, DeWitt County, Illinois. This supplement reports the status of certain items that had not been resolved at the time of publication of the Safety Evaluation Report and Supplement No. 1

  1. Safety evaluation report related to the operation of Clinton Power Station, Unit No. 1 (Docket No. 50-461)

    International Nuclear Information System (INIS)

    1987-03-01

    Supplement No. 8 to the Safety Evaluation Report on the application filed by Illinois Power Company, Soyland Power Cooperative, Inc., and Western Illinois Power Cooperative, Inc., as applicants and owners, for a license to operate the Clinton Power Station, Unit No. 1, has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located in Harp Township, DeWitt County, Illinois. This supplement reports the status of items that have been resolved by the staff since Supplement No. 7 was issued

  2. Safety evaluation report related to the operation of River Bend Station (Docket No. 50-458). Supplement No. 2

    International Nuclear Information System (INIS)

    1985-08-01

    Supplement No. 2 to the Safety Evaluation Report on the application filed by Gulf States Utilities Company as applicant and for itself and Cajun Electric Power Cooperative, as owners, for a license to operate River Bend Station has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located in West Feliciana Parish, near St. Francisville, Louisiana. This supplement reports the status of certain items that had not been resolved at the time the Safety Evaluation Report was published

  3. Safety Evaluation Report related to the operation of Hope Creek Generating Station (Docket No. 50-354). Supplement No. 1

    International Nuclear Information System (INIS)

    1985-03-01

    Supplement No. 1 to the Safety Evaluation Report on the application filed by Public Service Electric and Gas Company as applicant for itself and Atlantic City Electric Company, as owners, for a license to operate Hope Creek Generating Station has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located in Lower Alloways Creek Township in Salem County, New Jersey. This supplement reports the status of certain items that had not been resolved at the time of publication of the Safety Evaluation Report

  4. Safety Evaluation Report related to the operation of Hope Creek Generating Station (Docket No. 50-354). Supplement No. 4

    International Nuclear Information System (INIS)

    1985-12-01

    Supplement No. 4 to the Safety Evaluation Report on the application filed by Public Service Electric and Gas Company on its own behalf as co-owner and as agent for the other co-owner, the Atlantic City Electric Company, for a license to operate Hope Creek Generating Station has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located in Lower Alloways Creek Township in Salem County, New Jersey. This supplement reports the status of certain items that had not been resolved at the time of publication of the Safety Evaluation Report

  5. Safety Evaluation Report related to the operation of Hope Creek Generating Station (Docket No. 50-354)

    International Nuclear Information System (INIS)

    1985-10-01

    Supplement No. 3 to the Safety Evaluation Report on the application filed by Public Service Electric and Gas Company on its own behalf as co-owner and as agent for the other co-owner, the Atlantic City Electric Company, for a license to operate Hope Creek Generating Station has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located in Lower Alloways Creek Township in Salem County, New Jersey. This supplement reports the status of certain items that had not been resolved at the time of publication of the Safety Evaluation Report. 6 tabs

  6. Safety Evaluation Report related to the operation of Waterford Steam Electric Station, Unit No. 3 (Docket No. 50-382)

    International Nuclear Information System (INIS)

    1985-03-01

    Supplement 10 to the Safety Evaluation Report for the application filed by Louisiana Power and Light Company for a license to operate the Waterford Steam Electric Station, Unit 3 (Docket No. 50-382), located in St. Charles Parish, Louisiana, has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The purpose of this supplement is to update the Safety Evaluation Report by providing the staff's evaluation of information submitted by the licensee since the Safety Evaluation Report and its nine previous supplements were issued

  7. Safety evaluation report related to the operation of Millstone Nuclear Power Station, Unit No. 3 (Docket No. 50-423)

    International Nuclear Information System (INIS)

    1985-09-01

    The Safety Evaluation Report issued in August 1984 provided the results of the NRC staff review of Northeast Nuclear Energy Company's application for a license to operate the Millstone Nuclear Power Station, Unit No. 3. Supplement No. 1 to that report, issued in March 1985 updated the information contained in the Safety Evaluation Report and addressed the ACRS Report issued on September 10, 1984. The Report, Supplement No. 2 updates the information contained in the Safety Evaluation Report and Supplement No. 1 and addresses prior unresolved items. The facility is located in Waterford Township, New London, Connecticut. 11 refs., 9 tabs

  8. Safety evaluation report related to the operation of Hope Creek Generation Station (Docket No. 50-354). Supplement No. 5

    International Nuclear Information System (INIS)

    1986-04-01

    Supplement No. 5 to the Safety Evaluation Report on the application filed by Public Service Electric and Gas Company on its own behalf as co-owner and as agent for the other co-owner, the Atlantic City Electric Company, for a license to operate Hope Creek Generating Station has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located in Lower Alloways Creek Township in Salem County, New Jersey. This supplement reports the status of certain items that had not been resolved at the time of the publication of the Safety Evaluation Report

  9. Safety evaluation report related to the operation of Hope Creek Generating Station (Docket No. 50-354). Supplement 2

    International Nuclear Information System (INIS)

    1985-08-01

    Supplement No. 2 to the Safety Evaluation Report on the application filed by Public Service Electric and Gas Company as applicant for itself and Atlantic City Electric Company, as owners, for a license to operate Hope Creek Generating Station has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located in Lower Alloways Creek Township in Salem County, New Jersey. This supplement reports the status of certain items that had not been resolved at the time of publication of the Safety Evaluation Report

  10. Safety evaluation report related to the operation of Beaver Valley Power Station, Unit 2 (Docket No. 50-412)

    International Nuclear Information System (INIS)

    1987-08-01

    This report, Supplement No. 6 to the Safety Evaluation Report for the application filed by the Duquesne Light Company et al. (the licensee) for a license to operate the Beaver Valley Power Station, Unit 2 (Docket No. 50-412), has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement reports the status of certain items that had not been resolved when the Safety Evaluation Report and its Supplements 1, 2, 3, 4, and 5 were published

  11. Tianwan Nuclear Power Station. An Example for Chinese - Russian - German Co-operation

    International Nuclear Information System (INIS)

    Heidowitzsch, B.

    2004-01-01

    The Tianwan NPS is the first NPP worldwide, equipped completely with digital control systems. The DCS platforms TELEPERM XS and TELEPERM XP fulfill all automation tasks from reactor protection to water treatment system. The screen-based OM690 system offers a modern HMI for NPP operation. The Tianwan NPS Main IC project is an example of successful multi-cultural co-operation

  12. Heuristic Storage System Sizing for Optimal Operation of Electric Vehicles Powered by Photovoltaic Charging Station

    Directory of Open Access Journals (Sweden)

    Erik Blasius

    2016-01-01

    Full Text Available This paper discusses the utilisation of PV systems for electric vehicles charging for transportation requirements of smart cities. The gap between PV power output and vehicles charging demand is highly variable. Therefore, there is a need for additional support from a public distribution grid or a storage device in order to handle the residual power. Long term measurement data retrieved from a charging station for 15 vehicles equipped with a PV system were used in the research. Low and high irradiation seasons influenced the PV output. The charging demand of electric vehicles varied over the course of a year and was correlated to weather conditions. Therefore, the sizing and performance of a supportive storage device should be evaluated in a statistical manner using long period observations.

  13. Development and prospects of guidance system for operators in nuclear power station

    International Nuclear Information System (INIS)

    Aeba, Youichi

    1988-01-01

    In nuclear power plants, the information on plant process and the status of machinery and equipment is collected in a central control room, and operators watch the information and carry out the necessary operation according to circumstances, in this way, the stable safe operation is carried out. Recently, process parameters and the status of machinery and equipment are displayed, being classified by the objectives of monitoring, and when operators evaluate the condition of a plant, the burden of collecting required information is reduced, and the identification of the cause of abnormality and the forecast of the range of spread and the development of abnormality are eased. However, the burden of operators in the case of coping with the abnormal event in a plant is still heavy. In this report, the prospect of the operation-supporting system to which knowledge engineering is applied and the status of its development are described. The concept, system constitution, knowledge expression and inference control mechanism of the operation-supporting system, the test of the system and the results, and the perspective of the system hereafter are reported. (Kako, I.)

  14. Operating Experience with Nuclear Power Stations in Member States in 2011. 2012 Edition (CD-ROM)

    International Nuclear Information System (INIS)

    2012-08-01

    This CD contains the 43rd edition of the IAEA's series of annual reports on operating experience with nuclear power plants in Member States. It is a direct output from the IAEA's Power Reactor Information System (PRIS) and contains information on electricity production and overall performance of individual operational plants during 2011. In addition to annual information, the report contains a historical summary of performance during the lifetime of individual plants and figures illustrating worldwide performance of the nuclear industry. The CD contains also an overview of design characteristics and dashboards of all operating nuclear power plants worldwide.

  15. 78 FR 784 - Entergy Nuclear Operations, Inc.; Pilgrim Nuclear Power Station; Exemption

    Science.gov (United States)

    2013-01-04

    ... Decontamination August 7, 2012. Center. Quincy Medical Center Medical October 5, 2011. Service Drill. KIDS Site..., Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation. [FR Doc. 2012-31709 Filed 1...

  16. Draft Title V Operating Permit: Andeavor Field Services, LLC - Walker Hollow Compressor Station

    Science.gov (United States)

    Draft Title V Operating Permit, statement of basis, public notice bulletin, and the administrative permit docket (application and other supporting documents) for the Draft Part 71 Permit for Andeavor Field Services, LLC - Walker Hollow CS.

  17. Locating Portable Stations to Support the Operation of Bike Sharing Systems

    Science.gov (United States)

    2017-12-26

    Redistributing bikes has been a major challenge for the daily operation of bike sharing system around the world. Existing literature explore solution strategies that rely on pick-up-and-delivery routing as well as user incentivization approaches. The...

  18. Pilgrim Nuclear Power Station, Unit 1. Annual operating report for 1976

    International Nuclear Information System (INIS)

    Net electrical power generated was 2,415,511 MWH with the generator on line 5,333.6 hrs. Information is presented concerning operations, procedure changes, tests, experiments, maintenance, unit shutdowns and power reductions, and radiation doses to personnel

  19. Three Mile Island Nuclear Station, Unit 1. Semiannual operating report No. 4, July--December 1975

    International Nuclear Information System (INIS)

    1976-01-01

    Information is presented concerning operations, shutdowns, maintenance, changes, tests, experiments, radioactive effluent releases, solid radioactive waste, primary coolant chemistry, personel radiation, and refueling. Histograms of thermal power vs. time are included

  20. 78 FR 53482 - Entergy Operations, Inc., River Bend Station, Unit 1; Exemption

    Science.gov (United States)

    2013-08-29

    ... effect on the quality of the human environment (78 FR 50454; August 19, 2013). This exemption is... Regulatory Commission. Michele G. Evans, Director, Division of Operating Reactor Licensing, Office of Nuclear...

  1. Salem Nuclear Generating Station, Unit 1. Annual operating report for 1976

    International Nuclear Information System (INIS)

    1977-01-01

    Initial reactor criticality was achieved 12/11/76 and power generation began 12/25/76. Information is presented concerning operation, maintenance, procedure and specification changes, power generation, unit shutdowns and forced power reductions, testing, and personnel radiation exposures

  2. Influence of the cost development in power station construction and operation on power station planning with special regard to the effects on electricity supply

    International Nuclear Information System (INIS)

    Krieb, K.H.; Frenzel, P.; Vogel, J.

    1974-01-01

    A survey on the present structure of thermal power facilities in the FRG is followed by a discussion of the development of power plant costs in the last few years. Also mentioned are the findings of studies of costs as a function of the power station size and the effects of the overall cost increase on the power generation costs of the last few years. Finally, a model conception for the development of power stations is presented which makes predictions about the future size of power stations and their constructional parts. (UA/AK) [de

  3. Putting ROSE to Work: A Proposed Application of a Request-Oriented Scheduling Engine for Space Station Operations

    Science.gov (United States)

    Jaap, John; Muery, Kim

    2000-01-01

    Scheduling engines are found at the core of software systems that plan and schedule activities and resources. A Request-Oriented Scheduling Engine (ROSE) is one that processes a single request (adding a task to a timeline) and then waits for another request. For the International Space Station, a robust ROSE-based system would support multiple, simultaneous users, each formulating requests (defining scheduling requirements), submitting these requests via the internet to a single scheduling engine operating on a single timeline, and immediately viewing the resulting timeline. ROSE is significantly different from the engine currently used to schedule Space Station operations. The current engine supports essentially one person at a time, with a pre-defined set of requirements from many payloads, working in either a "batch" scheduling mode or an interactive/manual scheduling mode. A planning and scheduling process that takes advantage of the features of ROSE could produce greater customer satisfaction at reduced cost and reduced flow time. This paper describes a possible ROSE-based scheduling process and identifies the additional software component required to support it. Resulting changes to the management and control of the process are also discussed.

  4. Optimization of the operating conditions of gas-turbine power stations considering the effect of equipment deterioration

    Science.gov (United States)

    Aminov, R. Z.; Kozhevnikov, A. I.

    2017-10-01

    In recent years in most power systems all over the world, a trend towards the growing nonuniformity of energy consumption and generation schedules has been observed. The increase in the portion of renewable energy sources is one of the important challenges for many countries. The ill-predictable character of such energy sources necessitates a search for practical solutions. Presently, the most efficient method for compensating for nonuniform generation of the electric power by the renewable energy sources—predominantly by the wind and solar energy—is generation of power at conventional fossil-fuel-fired power stations. In Russia, this problem is caused by the increasing portion in the generating capacity structure of the nuclear power stations, which are most efficient when operating under basic conditions. Introduction of hydropower and pumped storage hydroelectric power plants and other energy-storage technologies does not cover the demand for load-following power capacities. Owing to a simple design, low construction costs, and a sufficiently high economic efficiency, gas turbine plants (GTPs) prove to be the most suitable for covering the nonuniform electric-demand schedules. However, when the gas turbines are operated under varying duty conditions, the lifetime of the primary thermostressed components is considerably reduced and, consequently, the repair costs increase. A method is proposed for determination of the total operating costs considering the deterioration of the gas turbine equipment under varying duty and start-stop conditions. A methodology for optimization of the loading modes for the gas turbine equipment is developed. The consideration of the lifetime component allows varying the optimal operating conditions and, in some cases, rejecting short-time stops of the gas turbine plants. The calculations performed in a wide range of varying fuel prices and capital investments per gas turbine equipment unit show that the economic effectiveness can

  5. Pre and post-operational radioecological studies around Kaiga Nuclear Power Station

    International Nuclear Information System (INIS)

    Karunakara, N.

    2018-01-01

    Four PHWR rectors of 220 MWe each are operating at Kaiga. The Centre for Advanced Research in Environmental Radioactivity (CARER), Mangalore University is engaged in frontline research studies on different aspects of environmental radioactivity and radioecology studies around Kaiga and West Coast of India for the last 30 years. Extensive studies were carried out on radiation levels, radionuclides distribution, and transfer of radionuclides through terrestrial, aquatic and atmospheric pathways in the environment of West Coast of India including the Kaiga nuclear power plant. The baseline studies on radioactivity levels around Kaiga region was carried out well before the nuclear power plant became operational and the data generated under these studies are considered to be highly valuable for impact assessments. The nuclear power plant became operational in the year 1999 and since then extensive studies were carried out on radiological impact assessments, through collaboration with Bhabha Atomic Research Centre (BARC) and Nuclear Power Corporation of India (NPCIL)

  6. Operation of Beaver Valley Power Station, Unit 2, Docket No. 50-412, Beaver County, Pennsylvania

    International Nuclear Information System (INIS)

    1985-09-01

    The final environmental impact statement (EPA No. 850438F) assesses the effects of operating a pressurized water reactor in Pennsylvania on the south bank of the Ohio River, which would serve as the final heat sink for the cooling system. Operation of Unit 2 would add 836 MW of capacity and increase system reliability. The plant would employ 465 at an $18 million payroll. Facilities for the plant would take up 56 acres of agricultural land. The operation result in both water and noise pollution. There is only a small probability of impacts due to potential radiation exposure. The Federal Water Pollution Control Act of 1972 and Nuclear Regulatory Commission Regulations require the impact statement

  7. Management, administrative and operational causes of the accident: Chernobyl nuclear power station

    International Nuclear Information System (INIS)

    Anastas, G.

    1996-01-01

    Full text: The Chernobyl accident, which occurred in April 1986, was the result of management, administrative, operational, technical and design flaws. The accident released millions of curies of mixed fission products (including 70-100 P Bq of 137 Cs). The results of this study strongly suggest that the cultural, political, managerial and operational attributes of the Soviet 'system' performed in a synergistic manner to significantly contribute to the initiation of the accident. At the time of the accident, science, engineering and safety in the former Soviet Union were dominated by an atmosphere of politics, group think and 'dingoes tending the sheep'

  8. Operating Experience with Nuclear Power Stations in Member States in 2014. 2015 Edition (CD-ROM)

    International Nuclear Information System (INIS)

    2015-01-01

    This CD-ROM contains the 46th edition of the IAEA’s series of annual reports on operating experience with nuclear power plants in Member States. It is a direct output from the IAEA’s Power Reactor Information System (PRIS) and contains information on electricity production and overall performance of individual plants during 2014. In addition to annual information, the report contains a historical summary of performance during the lifetime of individual plants and figures illustrating worldwide performance of the nuclear industry. The CD-ROM contains also an overview of design characteristics and dashboards of all operating nuclear power plants worldwide

  9. Operating Experience with Nuclear Power Stations in Member States in 2013. 2014 Edition (CD-ROM)

    International Nuclear Information System (INIS)

    2014-07-01

    This CD-ROM contains the 45th edition of the IAEA's series of annual reports on operating experience with nuclear power plants in Member States. It is a direct output from the IAEA's Power Reactor Information System (PRIS) and contains information on electricity production and overall performance of individual plants during 2013. In addition to annual information, the report contains a historical summary of performance during the lifetime of individual plants and figures illustrating worldwide performance of the nuclear industry. The CD-ROM contains also an overview of design characteristics and dashboards (not included into the web version) of all operating nuclear power plants worldwide

  10. Operating Experience with Nuclear Power Stations in Member States. 2016 Edition (CD-ROM)

    International Nuclear Information System (INIS)

    2016-06-01

    This CD-ROM contains the 47th edition of the IAEA’s series of annual reports on operating experience with nuclear power plants in Member States. It is a direct output from the IAEA’s Power Reactor Information System (PRIS) and contains information on electricity production and overall performance of individual plants during 2015. In addition to annual information, the report contains a historical summary of performance during the lifetime of individual plants and figures illustrating worldwide performance of the nuclear industry. The CD-ROM contains also an overview of design characteristics and dashboards of all operating nuclear power plants worldwide

  11. Public Service Company, Fort St. Vrain Station, Petition For Objection to Issuance of Operating Permit

    Science.gov (United States)

    This document may be of assistance in applying the Title V air operating permit regulations. This document is part of the Title V Petition Database available at www2.epa.gov/title-v-operating-permits/title-v-petition-database. Some documents in the database are a scanned or retyped version of a paper photocopy of the original. Although we have taken considerable effort to quality assure the documents, some may contain typographical errors. Contact the office that issued the document if you need a copy of the original.

  12. Salt River Project San Tan Generating Station, Petition to Object to Title V Operating Permit

    Science.gov (United States)

    This document may be of assistance in applying the Title V air operating permit regulations. This document is part of the Title V Petition Database available at www2.epa.gov/title-v-operating-permits/title-v-petition-database. Some documents in the database are a scanned or retyped version of a paper photocopy of the original. Although we have taken considerable effort to quality assure the documents, some may contain typographical errors. Contact the office that issued the document if you need a copy of the original.

  13. NSSS operating characteristics: experience obtained from Fessenheim nuclear power station start-up

    International Nuclear Information System (INIS)

    Gouffon, A.; Wilmart, Y.

    1978-01-01

    The two 900 MWe units of the Fessenheim Nuclear Power Plant are the first of a series of 26 installations equipped with Framatome 3-loop PWR-type NSSS systems which are scheduled to enter into service in France by 1982. The tests carried out at Fessenheim represented the first of the series, and thus it was important to provide the most complete tests possible. We shall examine here only the part of the operating tests which made it possible to demonstrate the correct behavior of these reactors under transient conditions and the adaptation of regulation systems required to meet the needs of a modern operation

  14. Petition to Object to the Xcel Energy, Hayden Station, Hayden Colorado, Title V Operating Permit

    Science.gov (United States)

    This document may be of assistance in applying the Title V air operating permit regulations. This document is part of the Title V Petition Database available at www2.epa.gov/title-v-operating-permits/title-v-petition-database. Some documents in the database are a scanned or retyped version of a paper photocopy of the original. Although we have taken considerable effort to quality assure the documents, some may contain typographical errors. Contact the office that issued the document if you need a copy of the original.

  15. Management, administrative and operational causes of the accident: Chernobyl nuclear power station

    International Nuclear Information System (INIS)

    Anastas, G.

    1996-01-01

    The Chernobyl accident, which occurred in April 1986, was the result of management, administrative, operational, technical and design flaws. The accident released millions of curies of mixed fission products including 70-100 PBq of 137 Cs. At the time of the accident, science, engineering and safety in the former Soviet Union were dominated by an atmosphere of politics, group think and 'dingoes tending the sheep'. This corrupted safety culture exacerbated the poor design of the reactor. The results of this study strongly suggest that the cultural, political, managerial and operational attributes of the Soviet 'system' performed in a synergistic manner to significantly contribute to the initiation of the accident. (authors)

  16. Yankee Nuclear Power Station. Annual operating report: January--December 1976

    International Nuclear Information System (INIS)

    1977-01-01

    Net electrical power generated was 1,251,255 MWH with the reactor on line 7887 hrs. Information is presented concerning operations, power generation, shutdowns, corrective maintenance, chemistry and radiochemistry, occupational radiation exposure, release of radioactive materials, reportable occurrences, containment penetration tests, and fuel performance

  17. San Onofre Nuclear Generating Station, Unit 1. Annual operating report for 1976

    International Nuclear Information System (INIS)

    1977-01-01

    Gross electrical energy generated was 2,610,000 MWH with the generator on line 6,162.9 hrs. Information is presented concerning operations, power generation, shutdowns, corrective maintenance, chemistry and radiochemistry, occupational radiation exposure, release of radioactive materials, reportable occurrences, steam generator tube inspections, primary coolant chemistry, containment penetration leak tests, and radiological environmental monitoring

  18. Beaver Valley Power Station, Unit 1. Annual operating report for 1976

    International Nuclear Information System (INIS)

    Net electrical energy generated was 441,530 MWH with the generator on line 1714.9 hours. Information is presented concerning operations, maintenance, changes, licensee event reports, power generation, shutdowns and forced power reductions, personnel radiation exposures, and unique reporting requirements

  19. Millstone Nuclear Power Station, Unit 1. Annual operating report: 1 January--31 December 1976

    International Nuclear Information System (INIS)

    1977-01-01

    Net electrical power generated was 3,752,445 MWh with the generator on line 6,682 hrs. Information is presented concerning operations; shutdowns and power reductions; refueling; maintenance; failed fuel elements; power generation; occupational personnel radiation exposure; and changes in technical specifications, plant design, and key supervisory personnel

  20. SEP operating history of the Dresden Nuclear Power Station Unit 2

    International Nuclear Information System (INIS)

    Mays, G.T.; Harrington, K.H.

    1983-01-01

    206 forced shutdowns and power reductions were reviewed, along with 631 reportable events and other miscellaneous documentation concerning the operation of Dresden-2, in order to indicate those areas of plant operation that compromised plant safety. The most serious plant challenge to plant safety occurred on June 5, 1970; while undergoing power testing at 75% power, a spurious signal in the reactor pressure control system caused a turbine trip followed by a reactor scram. Subsequent erratic water level and pressure control in the reactor vessel, compounded by a stuck indicator pen on a water level monitor-recorder and inability of the isolation condenser to function, led to discharge of steam and water through safety valves into the reactor drywell. No significant contamination was discharged. There was no pressure damage or the reactor vessel of the drywell containment walls. Six areas of operation that should be of continued concern are diesel generator failures, control rod and rod drive malfunctions, radioactive waste management/health physics program problems, operator errors, turbine control valve and EHC problems, and HPCI failures. All six event types have continued to recur

  1. Nine Mile Point Nuclear Station, Unit 1. Annual report of operation: January--December 1976

    International Nuclear Information System (INIS)

    1977-01-01

    Net electrical power generated was 4,112,827 MWH with the reactor on line 7,727.67 hrs. Information is presented concerning operations, power generation, shutdowns, corrective maintenance, chemistry and radiochemistry, occupational radiation exposure, release of radioactive materials, reportable occurrences, and fuel performance

  2. Yankee Nuclear Power Station. Semiannual operating report, January--June 1975

    International Nuclear Information System (INIS)

    1975-01-01

    The plant operated at power with brief shutdowns and load reductions during this period. Net electrical power generated was 741,551,035 MWh with the generator on line 4,271.30 hrs. Data is presented concerning power generation, shutdowns, corrective maintenance, chemistry and radiochemistry, occupational personnel radiation exposures, release of radioactive materials, and abnormal occurrences. (FS)

  3. Yankee Nuclear Power Station. Semiannual operating report, July--December 1975

    International Nuclear Information System (INIS)

    1976-01-01

    Net electrical power generated was 1,193,419,764 MWh(e) with the reactor on line 7,214.13 hrs. Information is presented concerning operation, power generation, shutdowns, corrective maintenance, primary coolant chemistry, occupational radiation exposure, release of radioactive materials, and reportable occurrences

  4. A modern thermal power station operating on high-moisture lignite

    Energy Technology Data Exchange (ETDEWEB)

    V.R. Kotler; D.V. Sosin [All-Russia Thermal Engineering Institute (VTI), Moscow (Russian Federation)

    2009-07-01

    The boilers developed by the power machinery construction company Alstom for two power-generating units, the Maritsa East-II and Maritsa East-II, operating on high-moisture lignite from the Maritsa East field in Bulgaria are described.

  5. Quad-Cities Station, Units 1 and 2. Semiannual operating report, January--June 1975

    International Nuclear Information System (INIS)

    1975-01-01

    Unit 1 generated 2,024,125 net electrical MWH and the generator was on line 3162.6 hours. Unit 2 generated 746,184 net electrical MWH and was on line 1475.3 hrs. Data is included concerning operations, power generation, shutdowns, maintenance, changes, and tests. (FS)

  6. Three Mile Island Nuclear Station, Unit 1. 1976 annual operating report

    International Nuclear Information System (INIS)

    1977-01-01

    Net electrical power generated was 4,335,625 MWh with the reactor on line 5,747.5 hrs. Information is presented concerning operations; specification, procedures, and FSAR changes; corrective maintenance; irradiated fuel examinations; radioactive effluent releases; personnel radiation exposures; shutdowns; and forced power reductions

  7. Fort St. Vrain Nuclear Generating Station. Semiannual operations report, January--June 1975

    International Nuclear Information System (INIS)

    1975-01-01

    The reactor was in start-up testing during this period. Information is presented concerning fuel and equipment performance; changes in facility design; procedures; testing; staff; licensed operator training; surveillance; power generation; maintenance; shutdowns, primary coolant chemistry; radiation exposure; fission product release; solid wastes; and radioactive effluents

  8. Pilgrim Nuclear Power Station, Unit 1. Fifth semiannual operating and maintenance report, July--December 1974

    International Nuclear Information System (INIS)

    1974-01-01

    During this period the reactor was critical for 3,550.3 hrs and the net electrical power generated was 1,973,033 MWH. Information is presented concerning operations, maintenance, radioactive effluents, environmental monitoring, and radioactive materials released to unrestricted areas. (U.S.)

  9. Hydrogen and Hydrogen/Natural Gas Station and Vehicle Operations - 2006 Summary Report

    Energy Technology Data Exchange (ETDEWEB)

    Francfort; Donald Karner; Roberta Brayer

    2006-09-01

    This report is a summary of the operations and testing of internal combustion engine vehicles that were fueled with 100% hydrogen and various blends of hydrogen and compressed natural gas (HCNG). It summarizes the operations of the Arizona Public Service Alternative Fuel Pilot Plant, which produces, compresses, and dispenses hydrogen fuel. Other testing activities, such as the destructive testing of a CNG storage cylinder that was used for HCNG storage, are also discussed. This report highlights some of the latest technology developments in the use of 100% hydrogen fuels in internal combustion engine vehicles. Reports are referenced and WWW locations noted as a guide for the reader that desires more detailed information. These activities are conducted by Arizona Public Service, Electric Transportation Applications, the Idaho National Laboratory, and the U.S. Department of Energy’s Advanced Vehicle Testing Activity.

  10. Aging of nuclear station diesel generators: Evaluation of operating and expert experience: Phase 1, Study

    International Nuclear Information System (INIS)

    Hoopingarner, K.R.; Vause, J.W.; Dingee, D.A.; Nesbitt, J.F.

    1987-08-01

    Pacific Northwest Laboratory evaluated operational and expert experience pertaining to the aging degradation of diesel generators in nuclear service. The research, sponsored by the US Nuclear Regulatory Commission (NRC), identified and characterized the contribution of aging to emergency diesel generator failures. This report, Volume I, reviews diesel-generator experience to identify the systems and components most subject to aging degradation and isolates the major causes of failure that may affect future operational readiness. Evaluations show that as plants age, the percent of aging-related failures increases and failure modes change. A compilation is presented of recommended corrective actions for the failures identified. This study also includes a review of current, relevant industry programs, research, and standards. Volume II reports the results of an industry-wide workshop held on May 28 and 29, 1986 to discuss the technical issues associated with aging of nuclear service emergency diesel generators

  11. Operational improvement of immersion-type evaporators in the Oyster Creek nuclear generating station radwaste system

    International Nuclear Information System (INIS)

    Ross, M.

    1986-01-01

    From 1977 to 1979 Oyster Creek concentrated condensate demineralizer regeneration solutions in two 30 gpm immersion tube evaporators. Then evaporator performance declined to where they could not process water at a rate and quality sufficient to support the regenerations. An extensive test program determined the proper operating setpoints to improve evaporator performance. The changes produced distillate conductivity of 15-30 μmho vs a previously normal conductivity of 200-400 μmho. Despite abandoning demineralizer regeneration in 1984 the operability of one evaporator deteriorated to where it was taken out of service for cleaning and inspection. Tube scaling and failed gaskets were found and remidied. The evaporator is now performing satisfactorily

  12. Dresden Nuclear Power Station, Units 1, 2, and 3. Annual operating report: January thru December 1976

    International Nuclear Information System (INIS)

    1977-01-01

    Net electrical energy generated by Unit 1 was 953,015.5 MWH with the generator on line 7,399.37 hrs. Unit 2 generated 4,371,553.689 MWH with the generator on line 6,664.58 hrs while Unit 3 generated 4,034,251 MWH with the generator on line 7,234.86 hrs. Information is presented concerning operations, maintenance, and shutdowns

  13. Fort Calhoun Station, Unit 1. Annual operation report: January-December 1977 (including environmental report)

    International Nuclear Information System (INIS)

    1978-02-01

    Net electrical energy generated in 1977 was 2,922,683.7 MWH with the generator on line 6,959.8 hours. Information is presented concerning operations, power generation, shutdowns, maintenance, changes, tests, experiments, occupational personnel radiation exposures, and primary coolant chemistry. Data on radioactive effluent releases, meteorology, environmental monitoring, and potential radiation doses to individuals for July 7, 1977 to December 31, 1977 are also included

  14. Vermont Yankee Nuclear Power Station. Annual operating report: January--December 1976

    International Nuclear Information System (INIS)

    1977-01-01

    Net electrical energy generated was 3,260,016 MWH with the facility on line for 6,776 hrs. Information is presented concerning operation, procedure changes, tests, experiments, plant changes, corrective maintenance, license event reports, forced power reductions, shutdowns, personnel radiation exposures, use of chemicals, plant discharges, cooling tower blowdown, traveling screens, fish impingement, reactor start-up, scram reports, and primary coolant chemistry

  15. Operating nuclear power stations in a regulated cyber security environment: a roadmap for success

    Energy Technology Data Exchange (ETDEWEB)

    Dorman, E., E-mail: Erik.Dorman@areva.com [AREVA Inc., Cyber Security Solutions, Charlotte, NC (United States)

    2015-07-01

    The United States Nuclear Regulatory Commission (NRC) issued 10CFR73.54 to implement a regulated Cyber Security Program at each operating nuclear reactor facility. Milestones were implemented December 31, 2012 to mitigate the attack vectors for the most critical digital assets acknowledged by the industry and the NRC. The NRC inspections have begun. The nuclear Cyber Security Plan, implemented by the site Cyber Security Program (Program), is an element of the operating license at each facility. The Program is designed to protect critical digital assets (CDAs) by applying and maintaining defense-in depth protective strategies to ensure the capability to detect, respond to, and recover from cyber-attacks. The Program references NEI 08-09 R. 6, the Nuclear Energy Institute Template that provides guidance for applying Cyber Security controls derived from NIST 800-53/82 and slightly modified to fit the nuclear environment. Many mature processes are in place at nuclear facilities in response to numerous regulations implemented over the past 30 years. Many of these processes such as the Physical Security Program offer protections that are leveraged to protect the functions of critical digital assets from unauthorized physical access. Other processes and technology such as engineering design control, work management and pre-job briefs, control of portable media and mobile devices, and deterministically segregated networks protect critical digital assets. By leveraging the regulated nuclear environment, integrating NIST type Cyber Security controls, and prudently deploying technology the Cyber Security posture of operating nuclear facilities supports on-demand base load electricity 24/7 with capacity factors exceeding 85%. This paper is designed to provide a glimpse into Cyber Security Programs that support safe operation and reliability in the regulated nuclear environment while supporting the on-demand base load electricity production 24/7. (author)

  16. Operating nuclear power stations in a regulated cyber security environment: a roadmap for success

    International Nuclear Information System (INIS)

    Dorman, E.

    2015-01-01

    The United States Nuclear Regulatory Commission (NRC) issued 10CFR73.54 to implement a regulated Cyber Security Program at each operating nuclear reactor facility. Milestones were implemented December 31, 2012 to mitigate the attack vectors for the most critical digital assets acknowledged by the industry and the NRC. The NRC inspections have begun. The nuclear Cyber Security Plan, implemented by the site Cyber Security Program (Program), is an element of the operating license at each facility. The Program is designed to protect critical digital assets (CDAs) by applying and maintaining defense-in depth protective strategies to ensure the capability to detect, respond to, and recover from cyber-attacks. The Program references NEI 08-09 R. 6, the Nuclear Energy Institute Template that provides guidance for applying Cyber Security controls derived from NIST 800-53/82 and slightly modified to fit the nuclear environment. Many mature processes are in place at nuclear facilities in response to numerous regulations implemented over the past 30 years. Many of these processes such as the Physical Security Program offer protections that are leveraged to protect the functions of critical digital assets from unauthorized physical access. Other processes and technology such as engineering design control, work management and pre-job briefs, control of portable media and mobile devices, and deterministically segregated networks protect critical digital assets. By leveraging the regulated nuclear environment, integrating NIST type Cyber Security controls, and prudently deploying technology the Cyber Security posture of operating nuclear facilities supports on-demand base load electricity 24/7 with capacity factors exceeding 85%. This paper is designed to provide a glimpse into Cyber Security Programs that support safe operation and reliability in the regulated nuclear environment while supporting the on-demand base load electricity production 24/7. (author)

  17. The quality control program for an Ontario Hydro operated thermoluminescence dosimetry service at nuclear generating stations

    International Nuclear Information System (INIS)

    Orr, B.H.; Walsh, M.L.

    1975-11-01

    An essential aspect of the Ontario Hydro TLD service is the operation of an acceptable quality control (QC) program. The QC program which has been generally accepted by the A.E.C.B. is presented in this document. The aims of the program are as follows: (1) to ensure that Ontario Hydro maintains an acceptable standard of dosimetry; (2) to be able to demonstrate to any interested party that the dose measurements for individual workers have a high degree of credibility. (author)

  18. Use of environmental TLD data at a nuclear power station to estimate detection limits for radiation exposure due to station operation

    International Nuclear Information System (INIS)

    Lang, E.; Hardeman, J.; Kahn, B.

    1987-01-01

    The environmental radiation monitoring network maintained by the Georgia Department of Natural Resources at the Hatch Nuclear Plant, Baxley, GA, was used to determine the variability in measured background exposures in order to estimate the detection limits for radiation due to station operation. Data were obtained from LiF thermoluminescent dosimeters (TLDs) exposed in sets of four at 46 locations for 16 consecutive quarters from 1982 to 1985. The average exposure for 695 values was 11.8 microC kg-1 y-1 (mR/quarter). At individual locations, the averages of quarterly exposures ranged from 9.3 to 14.3 microC kg-1 y-1 and had standard deviations from 0.8 to 2.2 microC kg-1 y-1 with a typical standard deviation of 1.5 microC kg-1 y-1. The standard deviation due to reading the TLDs and subtracting the transit plus storage exposure, estimated as 0.4 microC kg-1 y-1, contributed only a small fraction of the uncertainty of the mean background; the greater contribution is from temporal fluctuations. There is a spatial pattern of higher background along the Altamaha River but no distinct seasonal pattern. The observation that exposure values at most locations rose and fell in unison suggested a calculational model that adjusts the average exposure level at a location by an increment determined each quarter at control locations. This model reduced the standard deviation for a predicted quarterly background exposure to 0.9 microC kg-1 y-1, with a range of 0.5 to 1.3 microC kg-1 y-1. If the standard deviation of the net value is multiplied by an error probability constant of 3.3 (type I and II errors not greater than 5%), the detection limits range from 2 to 5 microC kg-1 y-1 at the individual locations, with an average of 3 microC kg-1 y-1. This approach or two similar ones described earlier are recommended for improving the detection limit where needed

  19. Operating experience with nuclear power stations in Member States in 2008. 2009 edition

    International Nuclear Information System (INIS)

    2009-08-01

    This edition is the fortieth in the IAEA's series of annual reports on operating experience with nuclear power plants in Member States. It is a direct output from the IAEA's Power Reactor Information System (PRIS) and contains information on electricity production and overall performance of individual plants during 2008. In addition to annual information, the report contains a historical summary of performance during the lifetime of individual plants and figures illustrating worldwide performance of the nuclear industry. The CD-ROM provides enhanced features for data search and analysis

  20. Indian Point Station, Units 1, 2, and 3. Annual operating report for 1976

    International Nuclear Information System (INIS)

    1977-01-01

    Unit 1 remained in a shutdown condition pending a decision by the Company on the installation of an ECCS as required by NRC. Net electrical power generated by Unit 2 was 2,267,654 MWH with the unit on line 3,056.45 hrs. Unit 3 generated 1,872,947 MWH and was on line 2,286.01 hrs. Information is presented concerning operations, reportable events, corrective maintenance, fuel performance, radioactivity releases, shutdowns, primary coolant chemistry, and occupational radiation exposures

  1. Aging of nuclear station diesel generators: Evaluation of operating and expert experience: Workshop

    International Nuclear Information System (INIS)

    Hoopingarner, K.R.; Vause, J.W.

    1987-08-01

    Pacific Northwest Laboratory (PNL) evaluated operational and expert experience pertaining to the aging degradation of diesel generators in nuclear service. The research, sponsored by the US Nuclear Regulatory Commission (NRC), identified and characterized the contribution of aging to emergency diesel generator failures. This report, Volume II, reports the results of an industry-wide workshop held on May 28 and 29, 1986, to discuss the technical issues associated with aging of nuclear service emergency diesel generators. The technical issues discussed most extensively were: man/machine interfaces, component interfaces, thermal gradients of startup and cooldown and the need for an accurate industry database for trend analysis of the diesel generator system

  2. Peach Bottom Atomic Power Station, Units 2 and 3. Annual operating report: January--December 1976

    International Nuclear Information System (INIS)

    1977-01-01

    Unit 2 experienced 11 forced outages, 5 power reductions, and one major refueling outage which lasted about 3 months during which time the feedwater spargers were replaced. Net electrical power generated was 5,569,633 MWH with the generator on line 5,998 hrs. Unit 3 experienced 17 forced outages, 11 power reductions and 2 major outages. The first refueling outage began 12/24/77. Net electrical power generated was 6,049,644 MWH with the unit on line 6,829 hrs. Information is presented concerning operations, personnel exposures, radioactive releases, maintenance, and irradiated fuel examination

  3. Indian Point Station, Unit 1 and 2. Semiannual operating report No. 24, July--December 1974

    International Nuclear Information System (INIS)

    1975-01-01

    Net electrical power generated by Unit 1 was 519,130 MWH with the reactor critical for 2,400.39 hours and the generator on line for 2,316.14 hours. Unit 2 generated 2,427,828 MWH electrical power, was critical for 3,590.31 hours and the generator was on line for 3,485.41 hours. Operations and maintenance are summarized. Information is presented concerning radioactive effluent releases, occupational personnel radiation protection, primary coolant chemistry, changes, tests, and experiments. Environmental radioactivity is discussed. (U.S.)

  4. Robot-operated quality control station based on the UTT method

    Science.gov (United States)

    Burghardt, Andrzej; Kurc, Krzysztof; Szybicki, Dariusz; Muszyńska, Magdalena; Nawrocki, Jacek

    2017-03-01

    This paper presents a robotic test stand for the ultrasonic transmission tomography (UTT) inspection of stator vane thickness. The article presents the method of the test stand design in Autodesk Robot Structural Analysis Professional 2013 software suite. The performance of the designed test stand solution was simulated in the RobotStudio software suite. The operating principle of the test stand measurement system is presented with a specific focus on the measurement strategy. The results of actual wall thickness measurements performed on stator vanes are presented.

  5. Organization and Management of the International Space Station (ISS) Multilateral Medical Operations

    Science.gov (United States)

    Duncan, J. M.; Bogomolov, V. V.; Castrucci, F.; Koike, Y.; Comtois, J. M.; Sargsyan, A. E.

    2007-01-01

    The goal of this work is to review the principles, design, and function of the ISS multilateral medical authority and the medical support system of the ISS Program. Multilateral boards and panels provide operational framework, direct, and supervise the ISS joint medical operational activities. The Integrated Medical Group (IMG) provides front-line medical support of the crews. Results of ongoing activities are reviewed weekly by physician managers. A broader status review is conducted monthly to project the state of crew health and medical support for the following month. All boards, panels, and groups function effectively and without interruptions. Consensus prevails as the primary nature of decisions made by all ISS medical groups, including the ISS medical certification board. The sustained efforts of all partners have resulted in favorable medical outcomes of the initial fourteen long-duration expeditions. The medical support system appears to be mature and ready for further expansion of the roles of all Partners, and for the anticipated increase in the size of ISS crews.

  6. Experience in the chemistry field from the operating cycle of Grohnde and Philippsburg II nuclear power stations

    International Nuclear Information System (INIS)

    Jacobi, G.; Ruehle, W.

    1987-01-01

    Experience from the primary section of the plants in relation to the activity pattern of corrosion products, indicates primarily that cobalt-free materials have been used throughout in Philippsburg II nuclear power station, which was no longer economically possible at Grohnde because of the advanced stages of manufacture and installation. Consequently, the activity concentration for Co-60 in Philippsburg was lower from the outset than at a comparable time at Grohnde. The second part of the paper discusses experience from the secondary section of the plants, based on the AVT (all volatile treatment) method of operation and its effect on the deposits in the steam generators. The chemical control is described and a comparison is made between the sampling points at Grohnde and Philippsburg II. (orig.) [de

  7. Safety Evaluation Report related to the operation of Comanche Peak Steam Electric Station, Unit 2 (Docket No. 50-446)

    International Nuclear Information System (INIS)

    1992-09-01

    This document supplement 25 to the Safety Evaluation Report related to the operation of the Comanche Peak Steam Electric Station (CPSES), Unit 2 (NUREG-0797), has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission (NRC). The facility is located in Somervell County, Texas, approximately 40 miles southwest of Fort Worth, Texas. This supplement reports the status of certain issues that had not been resolved when the Safety Evaluation Report and Supplements 1, 2, 3, 4, 6, 12, 21, 22, 23, and 24 to that report were published. This supplement deals primarily with Unit 2 issues; however, it also references evaluations for several Unit 1 licensing items resolved since Supplement 24 was issued

  8. Safety Evaluation Report related to the operation of Comanche Peak Steam Electric Station, Unit 2 (Docket No. 50-446)

    International Nuclear Information System (INIS)

    1993-02-01

    Supplement 26 to the Safety Evaluation Report related to the operation of the Comanche Peak Steam Electric Station (CPSES), Unit 2, has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission (NRC). The facility is located in Somervell County, Texas, approximately 40 miles southwest of Fort Worth, Texas. This supplement reports the status of certain issues that had not been resolved when the Safety Evaluation Report and Supplements 1, 2, 3, 4, 6, 12, 21, 22, 23, 24, and 25 to that report were published. This supplement deals primarily with Unit 2 issues; however, it also references evaluations for several licensing issues that relate to Unit 1, which have been resolved since Supplement 25 was issued

  9. IEEE guide for planning of pre-operational testing programs for class 1E power systems for nuclear-power generating stations

    International Nuclear Information System (INIS)

    Anon.

    1976-01-01

    The Institute of Electrical and Electronics Engineers (IEEE) guide for pre-operational testing of Class 1E power systems for nuclear-power generating stations is presented. The guidelines apply to power systems both ac and dc supplies but not to the equipment which utilizes the ac and dc power. The pre-operational tests are performed after appropriate construction tests

  10. A study on the capture of carbon dioxide from a large refinery power station boiler by conversion to oxyfuel operation

    Energy Technology Data Exchange (ETDEWEB)

    Wilkinson, M.B.; Boden, J.C.; Panesar, R.S.; Allam, R.J. [BP Amoco, Sunbury-on-Thames (United Kingdom)

    2001-07-01

    A detailed feasibility study has been carried out on the conversion of an existing refinery power station boiler, fired with refinery off-gas, to oxyfuel operation with carbon dioxide capture. The conversion was shown to be technically feasible using proven technologies. Boiler output could be maintained without significant pressure-part modifications and there would be no loss of boiler efficiency. It would be possible to retain a capability to operate in conventional air firing mode for start-up and emergency situations. The concept has been developed to a stage where a demonstration plant could be designed. The major elements of the capital costs of conversion are associated with the air separation unit and the carbon dioxide treatment and compression train and the additional operating costs are associated principally with the power consumption of these units. Further optimisation of the oxyfuel combustion system is possible and it is anticipated that the ongoing developments in air separation technology will help to make significant reductions in these costs in the future. 5 refs., 6 figs.

  11. Operations of the thermal control system for Alpha Magnetic Spectrometer electronics following the beta angle of the International Space Station

    Energy Technology Data Exchange (ETDEWEB)

    Wang, Kun; Li, Jinbo; Cui, Zheng; Wang, Naihua; Sun, Qie; Cheng, Lin, E-mail: cheng@sdu.edu.cn

    2014-12-11

    The Alpha Magnetic Spectrometer (AMS) has been running and measuring cosmic rays on the International Space Station (ISS) since May 19, 2011. The thermal control system (TCS) plays an important role in keeping all components and equipment working in an operational temperature range. Since the AMS started working on the ISS, AMS thermal engineers have been monitoring the on-orbit status of the TCS. During normal operation, the local temperature of AMS components regularly varies along with the β angle of the ISS. Based on the collected temperature data, the general characteristics of local temperature variations of TCS for AMS Electronics following the β of the ISS are discussed with the statistics of the orbit-averaged temperature and the orbit standard deviation of temperature. Furthermore some temperature anomalies at specific β are also studied. - Highlights: • The variation of the main radiators temperature is statistically analyzed. • The hot case and cold case for the main radiators are found in normal operations. • The solar illumination falling on the inner sheet of RAM radiator leads to temperature jump. • The temperature anomalies on the WAKE radiator show a uniform trend except WR3 sensor. • The regularity of the temperature variation is described with fitted equations.

  12. Action Stations! 100 years of trauma care on maritime and amphibious operations in the Royal Navy.

    Science.gov (United States)

    Osborne, M; Smith, J E

    2015-01-01

    Over the past century trauma care within the Royal Navy (RN) has evolved; wartime experiences and military medical research have combined to allow significant improvement in the care of casualties. This article describes the key maritime and amphibious operations that have seen the Royal Navy Medical Service (RNMS) deliver high levels of support to wherever the Naval Service has deployed in the last 100 years. Key advancements in which progress has led to improved outcomes for injured personnel are highlighted--the control and treatment of blood loss, wound care, and the prevention and management of organ failure with optimal resuscitation. Historians often point out how slowly military medicine progressed for the first few thousand years of its recorded history, and how quickly it has progressed in the last century. This reflective article will show how the RNMS has been an integral part of that story, and how the lessons learnt by our predecessors have shaped our modern day doctrine surrounding trauma care.

  13. Lighting Quality Affects Eyestrain of Operators at Sorting Station in Beverage Industry

    Science.gov (United States)

    Anizar; Erwin

    2017-03-01

    This study observes sorters’ performance in two beverage industries whose job is to separate defect products found. Sorters observe bottles quality and beverage quality continuously, therefore requiring more focused eyes which makes eyes’ load heavier. Sorters’ eyestrain causes more defect products pass the selection. In this study, measurement is conducted toward ilumintation, operators’ time response, and defect products that pass the selection. Measurement is hold in 2 beverage industries for four days with four measurements per day, twice in the morning and twice in the afternoon. Ilumination is measured with 4 in 1 environmental meter in grid 1m x 1m, while operators’ time response is measured with Flicker Fusion. Illuminance is generally higher in the morning than in the evening, but still under the standard of Indonesia. Overall, sorters’ time response is higher in the morning than in the afternoon. Higher time response shows that operators experiencing lower fatigue than lower time response. The sorting duration also affects operators’ time response and defect products which pass the selection.

  14. VAS operational procedures and results at the Kansas City Satellite Field Services Station

    Science.gov (United States)

    Heckman, B.; Carle, W.; Anthony, R.

    1983-01-01

    An operational assessment of VAS data by using a Man-computer Interactive Data Access System (McIDAS) terminal linked by a 9600 band telephone line is discussed. Seven hours of VAS data were processed and edited daily. Data was scheduled 16 hours a day, 7 days a week; however, during this time period there were very few days with 16 hours of data to evalute. The McIDAS terminal, which has 10 display frames and 5 graphics, provide access to the sounding data processed. These data are processed using two procedures. The dwell sounding data are generated by using all 12 spectral channels with a spin budget of 39. To provide coverage for most of the United States, soundings are made starting at 18 minutes after the hour from approximately 49 deg N to 36 deg N and at 48 minutes after the hour from 36 deg N to 26 deg N. The dwell imaging mode uses 11 channels but the spin budge is 17. With the reduced spin budget, retrievals can be made at 18 or 48 minutes after the hour for approximately 44 deg N to 27 deg N. With these constraints a schedule, of data sets was proposed to use the schedule and how the data set could be used are shown.

  15. Plant operation and its behavior during the accident at Fukushima Nuclear Power Station

    International Nuclear Information System (INIS)

    Miyata, Koichi

    2012-01-01

    At the Fukushima Daiichi NPS, all external power supply sources were lost at 14:46 on March 11, 2011 because of the earthquake off-the Pacific coast in the Tohoku district. Units 1 to 3 that were under operation automatically shut down. This caused the emergency diesel power generators to start up. However, seawater pumps, emergency diesel generators and distribution boards were submerged because of the huge tsunami strike, and almost all safety functions of 'cooling' and 'closing' were lost and resulted in core damages of units 1 to 3 and hydrogen explosions of units 1, 3 and 4 leading to the discharge of a large amount of radioactive materials to the environment. Alternative injections of freshwater or sea water using fire engine and concrete pumpers were attempted and continued to reactors and spent fuel storage pools whose cooling functions were lost. Depressurization of pressurized containment vessels of units 1 and 3 was done in success by suppression chamber (S/C) venting which could restrain release of fission products, but S/C venting of unit 2 was not successful. (T. Tanaka)

  16. Design, construction and operating experience of boilers at Wylfa power station

    Energy Technology Data Exchange (ETDEWEB)

    Razzell, R N [Wylfa Power Station, Central Electricity Generating Board, Gwynedd (United Kingdom)

    1988-07-01

    The report will describe the boilers, but will emphasise the problems encountered and the solutions. The boilers are 'once through' with start up drums. Some redundancy was provided but this advantage was lost due to downrating of gas temperature. The boilers are carbon steel suspended plattens (992 per reactor) tightly packed in the annular space between the core shielding and the spherical wall of the pressure vessel. This construction denies access to repair tube leaks. when a leak occurs the faulty platten has to be plugged off. This is done with the reactor at 60% power. The process will be described. Reactor 1 commenced operation in 1971, Reactor 2 in June 1971. Between 1972 and May 1984 21 leaks occurred which resulted in a major shutdown for investigation. This revealed the leaks were caused by gas flow induced vibration resulting in fretting of tubes in clips. Restraints and additional clamps were fitted. This has been successful but the modifications were extensive and in very difficult working conditions, the Reactor being shut down until May 1976. A family of leaks adjacent to personnel access ways commenced in Reactor 1 in 1975 which was later identified as erosion/corrosion on the water/steam side caused by the feed flow instability. This problem is common to both Reactors. Various modifications have been applied. Redistribution of feed flow using orifice plates and ferrules was only temporarily successful. Following extensive rig testing the feed water has been dosed with amino methyl proponal (AMP) since September 1983 with an immediate and sustained reduction in the leak rate. The amine provides protection through the steam/water phase. Rig testing continues to attain a better understanding of the erosion/corrosion. (author)

  17. Design, construction and operating experience of boilers at Wylfa power station

    International Nuclear Information System (INIS)

    Razzell, R.N.

    1988-01-01

    The report will describe the boilers, but will emphasise the problems encountered and the solutions. The boilers are 'once through' with start up drums. Some redundancy was provided but this advantage was lost due to downrating of gas temperature. The boilers are carbon steel suspended plattens (992 per reactor) tightly packed in the annular space between the core shielding and the spherical wall of the pressure vessel. This construction denies access to repair tube leaks. when a leak occurs the faulty platten has to be plugged off. This is done with the reactor at 60% power. The process will be described. Reactor 1 commenced operation in 1971, Reactor 2 in June 1971. Between 1972 and May 1984 21 leaks occurred which resulted in a major shutdown for investigation. This revealed the leaks were caused by gas flow induced vibration resulting in fretting of tubes in clips. Restraints and additional clamps were fitted. This has been successful but the modifications were extensive and in very difficult working conditions, the Reactor being shut down until May 1976. A family of leaks adjacent to personnel access ways commenced in Reactor 1 in 1975 which was later identified as erosion/corrosion on the water/steam side caused by the feed flow instability. This problem is common to both Reactors. Various modifications have been applied. Redistribution of feed flow using orifice plates and ferrules was only temporarily successful. Following extensive rig testing the feed water has been dosed with amino methyl proponal (AMP) since September 1983 with an immediate and sustained reduction in the leak rate. The amine provides protection through the steam/water phase. Rig testing continues to attain a better understanding of the erosion/corrosion. (author)

  18. Insights of PSA studies made for operating nuclear power stations in Finland

    International Nuclear Information System (INIS)

    Laaksonen, J.; Virolainen, R.

    1991-01-01

    In 1984 the Finnish regulatory authority (STUK) required the utilities to make plant specific probabilistic safety assessment (PSA) studies for each plant. It was also strongly recommended that most of the work be made by plant personnel. This advice was well observed by both utilities. Results of level 1 PSA studies were submitted for regulatory review in June 1989. Only internal initiating events, including loss-of-offsite power and human errors, were considered at this stage. Each study took an effort of 12 to 20 man years. A thorough regulatory review, about two man years per plant, is currently underway, and will cause some changes in the initial results of the studies. The utilities are continuing their PSA work with the fire and flood analysis, and then with the analysis of risks during start-up and shutdown conditions. As soon as a level 1 PSA study has been reviewed, and a common understanding of the models and data has been reached between the utility and the STUK, this basic PSA version will be the first element of a living PSA. The second element is a user friendly PSA code that can rapidly run through the quantitative part of the study and thus easily indicate the influence of any deviation from the basic version. The third element is plant specific data collection and processing system. The living PSA for the first plant is expected to be fully operational sometime next year. The first use of the living PSA will be the safety assessment of proposed plant modifications and a systematic re-evaluation of technical specifications

  19. Final environmental statement related to the operation of the Barnwell Fuel Receiving and Storage Station (Docket No. 70-1729)

    International Nuclear Information System (INIS)

    1976-01-01

    The proposed action is to issue a materials license, pursuant to 10 CFR Parts 30, 40 and 70 of the Commission's regulations, authorizing Allied-General Nuclear Services to receive and handle fuel casks containing spent reactor fuel elements and to store spent reactor fuel at the Barnwell Nuclear Fuel Plant (BNFP), in the Barnwell Fuel Receiving and Storage Station (BFRSS). The BFRSS is a part of, and contiguous to, the BNFP-Separations Facility which is being constructed on a small portion of a 1700 acre site about six miles west of the city of Barnwell in Barnwell County, South Carolina. Construction of the BFRSS facility has been completed and the BNFP Separations Facility is more than 90% complete. A uranium Hexafluoride Facility is being constructed on the same site, and a Plutonium Product Facility is proposed to be constructed adjacent to the Separations Facility. The license that is the subject of this action will, if issued, allow lthe use of the BFRSS separate4 from the operation of the Separations Facility. Impacts resulting from the construction of the BFRSS have already occurred and mitigating measures have been and are being implemented to offset any adverse impacts. Operation of the BFRSS will not interfere with water sources, and should cause no noticeable damage to the terrestrial or aquatic environments. Operating experience at other fuel receiving and storage facilities has shown that radioactive concentrations discharged to the environs (the more significant process effluents) have been well below applicabhle state and federal limits. The small quantities to be released during operation of the BFRSS will result in negligible environmental impact. 20 figs

  20. Coastal meteorological and water temperature data from National Water Level Observation Network (NWLON) and Physical Oceanographic Real-Time System (PORTS) stations of the NOAA Center for Operational Oceanographic Products and Services (CO-OPS)

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — The National Water Level Observation Network (NWLON) is a network of long-term water level stations operated and maintained by CO-OPS. NWLON stations are located on...

  1. Safety-evaluation report related to operation of McGuire Nuclear Station, Units 1 and 2. Docket Nos. 50-369 and 50-370

    International Nuclear Information System (INIS)

    1983-05-01

    This report supplements the Safety Evaluation Report Related to the Operation of McGuire Nuclear Station, Units 1 and 2 (SER (NUREG-0422)) issued in March 1978 by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission with respect to the application filed by Duke Power Company, as applicant and owner, for licenses to operate the McGuire Nuclear Station, Units 1 and 2 (Docket Nos. 50-369 and 50-370). The facility is located in Mecklenburg County, North Carolina, about 17 mi north-northwest of Charlotte, North Carolina. This supplement provides information related to issuance of a full-power authorization for Unit 2. The staff concludes that the McGuire Nuclear Station can be operated by the licensee without endangering the health and safety of the public

  2. Optimization of Cognitive Radio Secondary Information Gathering Station Positioning and Operating Channel Selection for IoT Sensor Networks

    Directory of Open Access Journals (Sweden)

    Jinyi Wen

    2018-01-01

    Full Text Available The Internet of Things (IoT is the interconnection of different objects through the internet using different communication technologies. The objects are equipped with sensors and communications modules. The cognitive radio network is a key technique for the IoT and can effectively address spectrum-related issues for IoT applications. In our paper, a novel method for IoT sensor networks is proposed to obtain the optimal positions of secondary information gathering stations (SIGSs and to select the optimal operating channel. Our objective is to maximize secondary system capacity while protecting the primary system. In addition, we propose an appearance probability matrix for secondary IoT devices (SIDs to maximize the supportable number of SIDs that can be installed in a car, in wearable devices, or for other monitoring devices, based on optimal deployment and probability. We derive fitness functions based on the above objectives and also consider signal to interference-plus-noise ratio (SINR and position constraints. The particle swarm optimization (PSO technique is used to find the best position and operating channel for the SIGSs. In a simulation study, the performance of the proposed method is evaluated and compared with a random resources allocation algorithm (parts of this paper were presented at the ICTC2017 conference (Wen et al., 2017.

  3. Operation of TUT Solar PV Power Station Research Plant under Partial Shading Caused by Snow and Buildings

    Directory of Open Access Journals (Sweden)

    Diego Torres Lobera

    2013-01-01

    Full Text Available A grid connected solar photovoltaic (PV research facility equipped with comprehensive climatic and electric measuring systems has been designed and built in the Department of Electrical Engineering of the Tampere University of Technology (TUT. The climatic measuring system is composed of an accurate weather station, solar radiation measurements, and a mesh of irradiance and PV module temperature measurements located throughout the solar PV facility. Furthermore, electrical measurements can be taken from single PV modules and strings of modules synchronized with the climatic data. All measured parameters are sampled continuously at 10 Hz with a data-acquisition system based on swappable I/O card technology and stored in a database for later analysis. The used sampling frequency was defined by thorough analyses of the PV system time dependence. Climatic and electrical measurements of the first operation year of the research facility are analyzed in this paper. Moreover, operation of PV systems under partial shading conditions caused by snow and building structures is studied by means of the measured current and power characteristics of PV modules and strings.

  4. Safety evaluation report related to the operation of Byron Station, Units 1 and 2 (Docket Nos. STN 50-454 and STN 50-455)

    International Nuclear Information System (INIS)

    1987-03-01

    Supplement No. 8 to the Safety Evaluation Report related to Commonwealth Edison Company's application for licenses to operate the Byron Station, Units 1 and 2, located in Rockvale Township, Ogle County, Illinois, has been prepared by th Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement provides recent information regarding resolution of the license conditions identified in the SER. Because of the favorable resolution of the items discussed in this report, the staff concludes that the Byron Station, Unit 2 can be operated by the licensee at power levels greater than 5% without endangering the health and safety of the public

  5. Effect of low air velocities on thermal homeostasis and comfort during exercise at space station operational temperature and humidity

    Science.gov (United States)

    Beumer, Ronald J.

    1989-01-01

    The effectiveness of different low air velocities in maintaining thermal comfort and homeostasis during exercise at space station operational temperature and humidity was investigated. Five male subjects exercised on a treadmill for successive ten minute periods at 60, 71, and 83 percent of maximum oxygen consumption at each of four air velocities, 30, 50, 80, and 120 ft/min, at 22 C and 62 percent relative humidity. No consistent trends or statistically significant differences between air velocities were found in body weight loss, sweat accumulation, or changes in rectal, skin, and body temperatures. Occurrence of the smallest body weight loss at 120 ft/min, the largest sweat accumulation at 30 ft/min, and the smallest rise in rectal temperature and the greatest drop in skin temperature at 120 ft/min all suggested more efficient evaporative cooling at the highest velocity. Heat storage at all velocities was evidenced by increased rectal and body temperatures; skin temperatures declined or increased only slightly. Body and rectal temperature increases corresponded with increased perception of warmth and slight thermal discomfort as exercise progressed. At all air velocities, mean thermal perception never exceeded warm and mean discomfort, greatest at 30 ft/min, was categorized at worst as uncomfortable; sensation of thermal neutrality and comfort returned rapidly after cessation of exercise. Suggestions for further elucidation of the effects of low air velocities on thermal comfort and homeostasis include larger numbers of subjects, more extensive skin temperature measurements and more rigorous analysis of the data from this study.

  6. Leach studies on cement-solidified ion exchange resins from decontamination processes at operating nuclear power stations

    International Nuclear Information System (INIS)

    McIsaac, C.V.; Akers, D.W.; McConnell, J.W.; Morcos, N.

    1992-01-01

    The effects of varying pH and leachant compositions on the physical stability and leachability of radionuclides and chelating agents were determined for cement-solidified decontamination ion-exchange resin wastes collected from two operating commercial light water reactors. Small scale waste-form specimens were collected during waste solidifications performed at the Brunswick Steam Electric Plant Unit 1 and at the James A. FitzPatrick Nuclear Power Station. The collected specimens were leach tested, and their compressive strength was measured in accordance with the Nuclear Regulatory Commission's ''Technical Position on Waste Form'' (Revision 1), from the Low-Level Waste Management Branch. Leachates from these studies were analyzed for radionuclides, selected transition metals, and chelating agents to assess the leachability of these waste form constituents. Leachants used for the study were deionized water, simulated seawater, and groundwater compositions similar to those found at Barnwell, South Carolina and Hanford, Washington. Results of this study indicate that initial leachant pH does not affect leachate pH or releases from cement-solidified decontamination ion-exchange resin waste forms. However, differences in leachant composition and the presence of chelating agents may affect the releases of radionuclides and chelating agents. In addition, results from this study indicate that the cumulative releases of radionuclides and chelating agents observed for forms that disintegrated were similar to those for forms that maintained their general physical integrity

  7. ENEL's experience in the management of irradiated fuel. Old and new problems encountered by nuclear station operators

    International Nuclear Information System (INIS)

    Ariemma, A.; Cuzzaniti, M.; Zaffiro, B.; Bertini, A.

    1983-01-01

    The experience acquired in recent years in the management of spent fuel discharged from ENEL's reactors has revealed a substantial change in the attitude of nuclear station operators in connection with the end of the fuel cycle downstream from the reactor (back-end). While in the past, after President Carter's outline of US policy in April 1977, the utilities had to face great difficulty in reprocessing their fuel owing to inadequate capacity, today the same problem is regarded as a matter of cost-benefit analysis from an industrial standpoint and of appropriate planning for the utilization of the recovered fissile materials. Since the present technology allows spent fuel storage (dry or underwater) to be planned for rather long periods and plutonium utilization requires a very stringent schedule, the present trend is to ensure medium-term storage of spent fuel and to seek a greater flexibility in the final reprocessing stages so as to render plutonium availability consistent with the programmes for its utilization. As a consequence, the solution to the problems posed by high-activity waste disposal is being delayed, thus allowing an exhaustive and detailed analysis of all the possible solutions to be made. The paper describes a number of solutions to the problems ENEL has encountered in the fuel cycle back-end. (author)

  8. International Space Station Common Cabin Air Assembly Condensing Heat Exchanger Hydrophilic Coating Operation, Recovery, and Lessons Learned

    Science.gov (United States)

    Balistreri, Steven F.; Steele, John W.; Caron, Mark E.; Laliberte, Yvon J.; Shaw, Laura A.

    2013-01-01

    The ability to control the temperature and humidity of an environment or habitat is critical for human survival. These factors are important to maintaining human health and comfort, as well as maintaining mechanical and electrical equipment in good working order to support the human and to accomplish mission objectives. The temperature and humidity of the International Space Station (ISS) United States On-orbit Segment (USOS) cabin air is controlled by the Common Cabin Air Assembly (CCAA). The CCAA consists of a fan, a condensing heat exchanger (CHX), an air/water separator, temperature and liquid sensors, and electrical controlling hardware and software. The CHX is the primary component responsible for control of temperature and humidity. The CCAA CHX contains a chemical coating that was developed to be hydrophilic and thus attract water from the humid influent air. This attraction forms the basis for water removal and therefore cabin humidity control. However, there have been several instances of CHX coatings becoming hydrophobic and repelling water. When this behavior is observed in an operational CHX in the ISS segments, the unit s ability to remove moisture from the air is compromised and the result is liquid water carryover into downstream ducting and systems. This water carryover can have detrimental effects on the ISS cabin atmosphere quality and on the health of downstream hardware. If the water carryover is severe and widespread, this behavior can result in an inability to maintain humidity levels in the USOS. This paper will describe the operation of the five CCAAs within the USOS, the potential causes of the hydrophobic condition, and the impacts of the resulting water carryover to downstream systems. It will describe the history of this behavior and the actual observed impacts to the ISS USOS. Information on mitigation steps to protect the health of future CHX hydrophilic coatings as well as remediation and recovery of the full heat exchanger will be

  9. Power stations

    International Nuclear Information System (INIS)

    Cawte, H.; Philpott, E.F.

    1980-01-01

    The object is to provide a method of operating a dual purpose power station so that the steam supply system is operated at a high load factor. The available steam not required for electricity generation is used to provide process heat and the new feature is that the process plant capacity is determined to make the most economic use of the steam supply system, and not to match the passout capacity of the turbine of the turbogenerator. The product of the process plant should, therefore, be capable of being stored. A dual-purpose power station with a nuclear-powered steam source, turbogenerating means connected to the steam source and steam-powered process plant susceptible to wide variation in its rate of operation is described. (U.K.)

  10. Final Environmental Statement related to the operation of Wolf Creek Generating Station, Unit No. 1. Docket No. STN 50-482, Kansas Gas and Electric Company, et al

    International Nuclear Information System (INIS)

    1982-06-01

    This final environmental statement contains the second assessment of the environmental impact associated with operation of Wolf Creek Generating Station Unit 1 pursuant to the National Environmental Policy Act of 1969 (NEPA) and 10 CFR Part 51, as amended, of the NRC's regulations. This statement examines: the affected environment, environmental consequences and mitigating actions, and environmental and economic benefits and costs. Land use and terrestrial- and aquatic-ecological impacts will be small. Air-quality impacts will also be small. However, steam fog from the station's cooling lake has the potential for reducing visibility over nearby roads and bridges. A fog-monitoring program for roads and bridges near the lake has been recommended. Impacts to historic and prehistoric sites will be negligible. Chemical discharges to the Neosho River are expected to have no appreciable impacts on water quality under normal conditions and will be required to meet conditions of the station's NPDES permit. The effects of routine operations, energy transmission, and periodic maintenance of rights-of-way and transmission line facilities should not jeopardize any populations of endangered or threatened species. No significant impacts are anticipated from normal operational releases of radioactivity. The risk associated with accidental radiation exposure is very low. The net socioeconomic effects of the project will be beneficial. The action called for is the issuance of an operating license for the Wolf Creek Generating Station Unit 1

  11. Safety Evaluation Report related to the operation of Limerick Generating Station, Units 1 and 2 (Docket Nos. 50-352 and 50-353). Supplement 2

    International Nuclear Information System (INIS)

    1984-10-01

    In August 1983 the staff of the Nuclear Regulatory Commission issued its Safety Evaluation Report (NUREG-0991) regarding the application of the Philadelphia Electric Company (the applicant) for licenses to operate the Limerick Generating Station, Units 1 and 2, located on a site in Montgomery and Chester Counties, Pennsylvania. This supplement addresses further issues that require resolution and closes them out

  12. Safety Evaluation Report related to the operation of Byron Station, Units 1 and 2 (Docket Nos. STN 50-454 and STN 50-455). Supplement No. 7

    International Nuclear Information System (INIS)

    1986-11-01

    Supplement No. 7 to the Safety Evaluation Report related to Commonwealth Edison Company's application for licenses to operate the Byron Station, Units 1 and 2, located in Rockvale Township, Ogle County, Illinois, has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement provides additional information supporting the license for initial criticality and power ascension to full-power operation for Unit 2

  13. Safety evaluation report related to the operation of Nine Mile Point Nuclear Station, Unit No. 2 (Docket No. 50-410). Supplement No. 1

    International Nuclear Information System (INIS)

    1985-06-01

    This report supplements the Safety Evaluation Report for the application filed by Niagara Mohawk Power Corporation, as applicant and co-owner, for a license to operate the Nine Mile Point Nuclear Station Unit 2. The facility is located near Oswego, New York. Subject to favorable resolution of the issues discussed in this report, the NRC staff concludes that the facility can be operated by the applicant without endangering the health and safety of the public. 1 fig., 3 tabs

  14. Safety Evaluation Report related to the full-term operating license for Dresden Nuclear Power Station, Unit 2 ( Docket No. 50-237)

    International Nuclear Information System (INIS)

    1990-10-01

    The Safety Evaluation Report for the full-term operating license application filed by Commonwealth Edison Company for the Dresden Nuclear Power Station, Unit 2, has been prepared by the Office of Nuclear Regulation of the US Nuclear Regulatory Commission. The facility is located in Grundy County, Illinois. Subject to favorable resolution of the items discussed in this report, the staff concludes that the facility can continue to be operated without endangering the health and safety of the public. 72 refs

  15. Safety Evaluation Report related to the operation of LaSalle County Station, Units 1 and 2. Docket Nos. 50-373 and 50-374

    International Nuclear Information System (INIS)

    1984-03-01

    This supplement to the Safety Evaluation Report of Commonwealth Edison Company's application for a license to operate its La Salle County Station, Unit 2, located in Brookfield Township, La Salle County, Illinois, has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement is to update evaluations on Unit 2 issues identified in the previous Safety Evaluation Report and Supplements that need resolution prior to issuance of the full power operating license for Unit 2

  16. Analysis of the quality of wastewater from the service stations located in the operative area of Helsinki Region Environmental Services Authority

    OpenAIRE

    Dahal, Karna

    2012-01-01

    The objective of this thesis was to analyse the data of pollutant parameters for waste water from the service stations situated in the operative area of the Viikinmäki and Suomenoja WWTPs in the Helsinki Region Environmental Services Authority (HSY). The main reason for this analysis was that HSY wanted to know about the quality of waste water discharged from the service stations into the influent of its WWTPs. The number of cars used in Finland is increasing day by day; hence, au...

  17. Safety Evaluation Report related to the operation of Nine Mile Point Nuclear Station, Unit No. 2 (Docket No. 50-410)

    International Nuclear Information System (INIS)

    1987-07-01

    This report supplements the Safety Evaluation Report (NUREG-1047, February 1985) for the application filed by Niagara Mohawk Power Corporation, as applicant and co-owner, for the license to operate Nine Mile Point Nuclear Station, Unit 2 (Docket No. 50-410). It has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located near Oswego, New York. This report supports the issuance of the full-power license for Nine Mile Point Nuclear Station, Unit No. 2

  18. Final environmental statement related to the operation of Comanche Peak Steam Electric Station, Units 1 and 2: (Docket Nos. 50-445 and 50-446)

    International Nuclear Information System (INIS)

    1981-09-01

    The proposed action is the issuance of operating licenses to the Texas Utilities Generating Company for the startup and operation of Units 1 and 2 of the Comanche Peak Steam Electric Station located on Squaw Creek Reservoir in Somervell County, Texas, about 7 km north-northeast of Glen Rose, Texas, and about 65 km southwest of Fort Worth in north-central Texas. The information in this environmental statement represents the second assessment of the environmental impact associated with the Comanche Peak Steam Electric Station pursuant to the guidelines of the National Environmental Policy Act of 1969 (NEPA) and 10 CFR Part 51 of the Commission's Regulations. After receiving an application to construct this station, the staff carried out a review of impact that would occur during its construction and operation. This evaluation was issued as a Final Environmental Statement -- Construction Phase. After this environmental review, a safety review, an evaluation by the Advisory Committee on Reactor Safeguards, and public hearings in Glen Rose, Texas, the US Atomic Energy Commission (now US Nuclear Regulatory Commission) issued construction permits for the construction of Units 1 and 2 of the Comanche Peak Steam Electric Station. 16 figs., 34 tabs

  19. Simulations of the neutron energy-spectra at the Olympus Gate Environmental Monitoring Station due to historical Bevatron operations

    International Nuclear Information System (INIS)

    Donahue, R.J.; Thomas, R.H.; Zeman, G.H.

    2001-01-01

    Offsite neutron fluences resulting from Bevatron operations reached a maximum in 1959, prior to the addition of a permanent concrete roof shield, which was constructed in 1962. From the first operation of the Bevatron measurements of neutron fluence were made at locations around the perimeter of the Lawrence Berkeley National Laboratory (LBNL) campus. Since the late 1950's measurements made at several locations, and particularly at the site of what is now called the Olympus Gate Environmental Monitoring Station, have been routinely reported and published. Early measurements were used to establish the shape of the neutron-energy spectrum from which an energy-averaged fluence-to-dose equivalent conversion coefficient could be derived. This conversion coefficient was then applied to a measured total neutron fluence to obtain the appropriate dose equivalent quantity required by regulation. Recent work by Thomas et al. (2000) have compared the early conversion coefficients used in the sixties with those accepted today and suggest suggested that ''the dose equivalents reported in the late fifties and early sixties were conservative by factors between two and four. In any current review of the historical data, therefore it would be prudent to reduce the reported dose equivalents by at least a factor of two.'' However, that analysis was based on the ''state of the art'' neutron energy-spectra of the '60s. This paper provides a detailed knowledge of the neutron energy spectrum at the site boundary paper thus removing any uncertainty in the analysis of Thomas et al., which might be caused by the use of the early neutron energy-spectra. Detailed Monte Carlo analyses of the interactions of 6.2 GeV protons in thick, medium-A targets are described. In the computer simulations, neutrons produced were allowed to scatter in the atmosphere. Detailed neutron energy spectra were calculated at a distance and elevation corresponding to the location of the Olympus Gate EMS. Both older

  20. Estimating cancer risk in relation to tritium exposure from routine operation of a nuclear-generating station in Pickering, Ontario.

    Science.gov (United States)

    Wanigaratne, S; Holowaty, E; Jiang, H; Norwood, T A; Pietrusiak, M A; Brown, P

    2013-09-01

    Evidence suggests that current levels of tritium emissions from CANDU reactors in Canada are not related to adverse health effects. However, these studies lack tritium-specific dose data and have small numbers of cases. The purpose of our study was to determine whether tritium emitted from a nuclear-generating station during routine operation is associated with risk of cancer in Pickering, Ontario. A retrospective cohort was formed through linkage of Pickering and north Oshawa residents (1985) to incident cancer cases (1985-2005). We examined all sites combined, leukemia, lung, thyroid and childhood cancers (6-19 years) for males and females as well as female breast cancer. Tritium estimates were based on an atmospheric dispersion model, incorporating characteristics of annual tritium emissions and meteorology. Tritium concentration estimates were assigned to each cohort member based on exact location of residence. Person-years analysis was used to determine whether observed cancer cases were higher than expected. Cox proportional hazards regression was used to determine whether tritium was associated with radiation-sensitive cancers in Pickering. Person-years analysis showed female childhood cancer cases to be significantly higher than expected (standardized incidence ratio [SIR] = 1.99, 95% confidence interval [CI]: 1.08-3.38). The issue of multiple comparisons is the most likely explanation for this finding. Cox models revealed that female lung cancer was significantly higher in Pickering versus north Oshawa (HR = 2.34, 95% CI: 1.23-4.46) and that tritium was not associated with increased risk. The improved methodology used in this study adds to our understanding of cancer risks associated with low-dose tritium exposure. Tritium estimates were not associated with increased risk of radiationsensitive cancers in Pickering.

  1. Safety-Evaluation Report related to the operation of Grand Gulf Nuclear Station, Units 1 and 2. Docket Nos. 50-416 and 50-417

    International Nuclear Information System (INIS)

    1983-05-01

    Supplement 4 to the Safety Evaluation Report for Mississippi Power and Light Company, et. al., joint application for licenses to operate the Grand Gulf Nuclear Station, Units 1 and 2, located on the east bank of the Mississippi River near Port Gibson in Claiborne County, Mississippi, has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement reports the status on the resolution of those issues that required further evaluation before authorizing operation of Unit 1 above 5% rated power and other issues that were to be evaluated during the first cycle of power operation

  2. Safety evaluation report related to the operation of Millstone Nuclear Power Station, Unit No. 3 (Docket No. 50-423). Supplement No. 5

    International Nuclear Information System (INIS)

    1986-01-01

    This report supplements the Safety Evaluation Report (NUREG-1031) issued in July 1984, Supplement 1 issued in March 1985, Supplement 2 issued in September 1985, Supplement 3 issued in November 1985, and Supplement 4 issued in November 1985 by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission with respect to the application filed by Northeast Nuclear Energy Company (licensee and agent for the owners) for a license to operate Millstone Nuclear Power Station, Unit No. 3 (Docket 50-423). The supplement provides more recent information regarding resolution of license conditions identified in the SER. Because of the favorable resolution of the items discussed in this report, the staff concludes that Millstone Nuclear Power Station, Unit No. 3, can be operated by the licensee at power levels greater than 5% without endangering the health and safety of the public. 13 refs

  3. Final environmental statement related to the operation of Limerick Generating Station, Units 1 and 2, Docket Nos. 50-352 and 50-353, Philadelphia Electric Company

    International Nuclear Information System (INIS)

    1989-08-01

    In April 1984 the staff of the Nuclear Regulatory Commission issued its Final Environmental Statement (NUREG-0974) related to the operation of Limerick Generating Station, Units 1 and 2, (Docket Nos. 50-352 and 50-353), located on the Schuylkill River, near Pottstown, in Limerick Township, Montgomery and Chester Counties, Pennsylvania. The NRC has prepared this supplement to NUREG-0974 to present its evaluation of the alternative of facility operation with the installation of further severe accident mitigation design features. The NRC staff has discovered no substantial changes in the proposed action as previously evaluated in the Final Environmental Statement that are relevant to environmental concerns nor significant new circumstances or information relevant to environmental concerns and bearing on the licensing of Limerick Generating Station, Units 1 and 2. 15 refs., 10 tabs

  4. Final Environmental Statement related to the operation of Comanche Peak Steam Electric Station, Units 1 and 2 (Docket Nos. 50-445 and 50-446)

    International Nuclear Information System (INIS)

    1989-10-01

    In September 1981, the staff of the Nuclear Regulatory Commission (NRC) issued its Final Environmental Statement (NUREG-0775) related to the operation of Comanche Peak Steam Electric Station, Units 1 and 2 (Docket Nos. 50-445 and 50-446), located in Somervell County, Texas, approximately 40 miles southwest of Fort Worth, Texas. The NRC has prepared this supplement to NUREG-0775 to present its evaluation of the alternative of operating Comanche Peak with the installation of further severe-accident-mitigation design features. The NRC has discovered no substantial changes in the proposed action as previously evaluated in the Final Environmental Statement that are relevant to environmental concerns and bearing on the licensing of Comanche Peak Steam Electric Station, Units 1 and 2. 6 refs., 3 tabs

  5. IEEE standard requirements for reliability analysis in the design and operation of safety systems for nuclear power generating stations

    International Nuclear Information System (INIS)

    Anon.

    1976-01-01

    The purpose of this standard is to provide uniform, minimum acceptable requirements for the performance of reliability analyses for safety-related systems found in nuclear-power generating stations, but not to define the need for an analysis. The need for reliability analysis has been identified in other standards which expand the requirements of regulations (e.g., IEEE Std 379-1972 (ANSI N41.2-1972), ''Guide for the Application of the Single-Failure Criterion to Nuclear Power Generating Station Protection System,'' which describes the application of the single-failure criterion). IEEE Std 352-1975, ''Guide for General Principles of Reliability Analysis of Nuclear Power Generating Station Protection Systems,'' provides guidance in the application and use of reliability techniques referred to in this standard

  6. Safety evaluation report related to the operation of Waterford Steam Electric Station, Unit No. 3 (Docket No. 50-382). Supplement No. 7

    International Nuclear Information System (INIS)

    1984-09-01

    Supplement 7 to the Safety Evaluation Report for Louisiana Power and Light's application for a license to operate Waterford Steam Electric Station, Unit 3 (Docket No. 50-382), located in St. Charles Parish, Louisiana, has been jointly prepared by the Office of Nuclear Reactor Regulation and the Region IV Office of the US Nuclear Regulatory Commission. This supplement provides the results to date of the staff's evaluation of approximately 350 allegations and concerns of poor construction practices at the Waterford 3 facility

  7. Safety-evaluation report related to the operation of Shoreham Nuclear Power Station, Unit No. 1 (Docket No. 50-322)

    International Nuclear Information System (INIS)

    1983-09-01

    Supplement 4 (SSER 4) to the Safety Evaluation Report on Long Island Lighting Company's application for a license to operate the Shoreham Nuclear Power Station, Unit 1, located in Suffolk County, New York, has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement addresses several items that have been reviewed by the staff since the previous supplement was issued

  8. Safety evaluation report related to the operation of Shoreham Nuclear Power Station, Unit No. 1 (Docket No. 50-322). Supplement No. 7

    International Nuclear Information System (INIS)

    1984-09-01

    Supplement 7 (SSER 7) to the Safety Evaluation Report on Long Island Lighting Company's application for a license to operate the Shoreham Nuclear Power Station, Unit 1, located in Suffolk County, New York, has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement addresses several items that have been reviewed by the staff since the previous supplement was issued

  9. Safety Evaluation Report related to the operation of Shoreham Nuclear Power Station, Unit No. 1 (Docket No. 50-322). Supplement No. 8

    International Nuclear Information System (INIS)

    1984-12-01

    Supplement 8 (SSER 8) to the Safety Evaluation Report on Long Island Lighting Company's application for a license to operate the Shoreham Nuclear Power Station, Unit 1, located in Suffolk County, New York, has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement addresses several items that have been reviewed by the staff since the previous supplement was issued

  10. Safety evaluation report related to the operation of Shoreham Nuclear Power Station, Unit No. 1 (Docket No. 50-322). Supplement No. 6

    International Nuclear Information System (INIS)

    1984-07-01

    Supplement 6 (SSER 6) to the Safety Evaluation Report on Long Island Lighting Company's application for a license to operate the Shoreham Nuclear Power Station, Unit 1, located in Suffolk County, New York, has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement addresses several items that have been reviewed by the staff since the previous supplement was issued

  11. Safety Evaluation Report, related to the operation of Byron Station, Units 1 and 2 (Docket Nos. STN 50-454 and STN 50-455)

    International Nuclear Information System (INIS)

    1983-11-01

    Supplement No. 3 to the Safety Evaluation Report related to Commonwealth Edison Company's application for licenses to operate the Byron Station, Units 1 and 2, located in Rockvale Township, Ogle County, Illinois, has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement reports the status of certain items that had not been resolved at the time of publication of the Safety Evaluation Report

  12. Final Environmental Statement related to the operation of Nine Mile Point Nuclear Station, Unit No. 2 (Docket No. 50-410)

    International Nuclear Information System (INIS)

    1985-05-01

    This Final Environmental Statement contains the assessment of the environmental impact associated with the operation of the Nine Mile Point Nuclear Station, Unit 2, pursuant to the National Environmental Policy Act of 1969 (NEPA) and Title 10 of the Code of Federal Regulations, Part 51, as amended, of the Nuclear Regulatory Commission regulations. This statement examines the environment, environmental consequences and mitigating actions, and environmental and economic benefits and costs

  13. Safety evaluation report related to the operation of Byron Station, Units 1 and 2. Docket Nos. STN 50-454 and STN 50-455

    International Nuclear Information System (INIS)

    1983-01-01

    Supplement No. 2 to the Safety Evaluation Report related to Commonwealth Edison Company's application for licenses to operate the Byron Station, Units 1 and 2, located in Rockvale Township, Ogle County, Illinois, has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement reports the status of certain items that had not been resolved at the time of publication of the Safety Evaluation Report

  14. Safety Evaluation Report related to the operation of Byron Station, Units 1 and 2 (Docket Nos. STN 50-454 and STN 50-455)

    International Nuclear Information System (INIS)

    1984-05-01

    Supplement No. 4 to the Safety Evaluation Report related to Commonwealth Edison Company's application for licenses to operate the Byron Station, Units 1 and 2, located in Rockvale Township, Ogle County, Illinois, has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement reports the status of certain items that had not been resolved at the time of publication of the Safety Evaluation Report

  15. Safety Evaluation Report related to the operation of Shoreham Nuclear Power Station, Unit No. 1 (Docket No. 50-322). Supplement No. 9

    International Nuclear Information System (INIS)

    1985-12-01

    Supplement 9 (SSER 9) to the Safety Evaluation Report on Long Island Lighting Company's application for a license to operate the Shoreham Nuclear Power Station, Unit 1, located in Suffolk County, New York, has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement addresses several items that have been reviewed by the staff since the previous supplement was issued

  16. Safety Evaluation Report related to the operation of Beaver Valley Power Station, Unit 2 (Docket No. 50-412). Supplement No. 2

    International Nuclear Information System (INIS)

    1986-08-01

    This report, Supplement No. 2 to the the Safety Evaluation Report for the application filed by the Duquesne Light Company, et al. (the applicant) for a license to operate the Beaver Valley Power Station Unit 2 (Docket No. 50-412), has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement reports the status of certain items that had not been resolved at the time the Safety Evaluation Report was published

  17. Draft Environmental Statement related to the operation of Beaver Valley Power Station, Unit 2 (Docket No. 50-412)

    International Nuclear Information System (INIS)

    1984-12-01

    This Draft Environmental Statement contains the second assessment of the environmental impact associated with Beaver Valley Power Station Unit 2 pursuant to the National Environmental Policy Act of 1969 (NEPA) and Title 10 of the Code of Federal Regulations, Part 51, as amended, of the Nuclear Regulatory Commission regulations. This statement examines the environment, environmental consequences and mitigating actions, and environmental benefits and costs

  18. Final environmental statement related to the operation of North Anna Power Station, Units 1 and 2: (Docket Nos. 50-338 and 50-339)

    International Nuclear Information System (INIS)

    1980-08-01

    The proposed action is the issuance of Operating Licenses to the Virginia Electric and Power Company for the startup and operation of the North Anna Power Station, Units No. 1 and 2, located on Lake Anna in Louisa County, 40 miles east of Charlottesville, Virginia. The information in this second addendum responds to the Commission's directive that the staff address in narrative form the environmental dose commitments and health effects from fuel cycle releases, fuel cycle socioeconomic impacts, and possible cumulative impacts pending further treatment by rulemaking

  19. Safety evaluation report related to the operation of Limerick Generating Station, Units 1 and 2 (Docket Nos. 50-352-50-353). Supplement 1

    International Nuclear Information System (INIS)

    1983-12-01

    This report supplements the Safety Evaluation Report (NUREG-0991, August 1983) for the application filed by the Philadelphia Electric Company, as applicant and owner, for licenses to operate the Limerick Generating Station Units 1 and 2 (Docket Nos. 50-352 and 50-353). The facility is located near Pottstown, Pennsylvania. Subject to favorable resolution of the items discussed in this report, the NRC staff concludes that the facility can be operated by the applicant without endangering the health and safety of the public

  20. Safety Evaluation Report related to the operation of Grand Gulf Nuclear Station, Units 1 and 2 (Docket Nos. 50-416 and 50-417). Supplement 6

    International Nuclear Information System (INIS)

    1984-08-01

    Supplement 6 to the Safety Evaluation Report for Mississippi Power and Light Company et al. joint application for licenses to operate the Grand Gulf Nuclear Station, Units 1 and 2, located on the east bank of the Mississippi River near Port Gibson in Claiborne County, Mississippi, has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement reports the NRC staff's evaluation of open items from previous supplements and Technical Specification changes required before authorizing operation of Unit 1 above 5% of rated power

  1. Safety Evaluation Report related to the operation of Byron Station, Units 1 and 2 (Dockets Nos. STN 50-454 and STN 50-455)

    International Nuclear Information System (INIS)

    1984-10-01

    Supplement No. 5 to the Safety Evaluation Report related to Commonwealth Edison Company's application for licenses to operate the Byron Station, Units 1 and 2, located in Rockvale Township, Ogle County, Illinois, has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement reports the status of certain items that had not been resolved at the time of publication of the Safety Evaluation Report. Because of the favorable resolution of the items discussed in this report, the staff concludes that there is reasonable assurance that the facility can be operated by the applicant without endangering the health and safety of the public

  2. Safety Evaluation Report related to the operation of Grand Gulf Nuclear Station, Units 1 and 2 (Docket Nos. 50-416 and 50-417). Supplement No. 5

    International Nuclear Information System (INIS)

    1984-08-01

    Supplement 5 to the Safety Evaluation Report for Mississippi Power and Light Company, et al., joint application for licenses to operate the Grand Gulf Nuclear Station, Units 1 and 2, located on the east bank of the Mississippi River near Port Gibson in Claiborne County, Mississippi, has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement reports the status on the resolution of those issues that require further evaluation before authorizing operation of Unit 1 above 5% of rated power

  3. Safety evaluation report related to the operation of Braidwood Station, Units 1 and 2 (Docket Nos. 50-456 and 50-457)

    International Nuclear Information System (INIS)

    1983-11-01

    The Safety Evaluation Report for the application filed by the Commonwealth Edison Company, as applicant and owner, for a license to operate Braidwood Station, Units 1 and 2 (Docket Nos. STN 50-456 and STN 50-457), has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located in Reed Township, Will County, Illinois. Subject to favorable resolution of the items discussed in this report, the staff concludes that the facility can be operated by the applicant without endangering the health and safety of the public

  4. Safety Evaluation Report related to the operation of Nine Mile Point Nuclear Station, Unit No. 2 (Docket No. 50-410)

    International Nuclear Information System (INIS)

    1985-02-01

    The Safety Evaluation Report for the application filed by the Niagara Mohawk Power Corporation, as applicant and co-owner, for a license to operate the Nine Mile Point Nuclear Station, Unit 2 (Docket No. 50-410), has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located near Oswego, New York. Subject to favorable resolution of the items discussed in this report, the NRC staff concludes that the facility can be operated by the applicant without endangering the health and safety of the public

  5. Safety evaluation report related to the operation of Susquehanna Steam Electric Station, Units 1 and 2 (Docket Nos. 50-387 and 50-388). Suppl.6

    International Nuclear Information System (INIS)

    1984-03-01

    In April 1981, the staff of the Nuclear Regulatory Commission issued its Safety Evaluation Report (NUREG-0776) regarding the application of the Pennsylvania Power and Light Company (the applicant and/or licensee) and the Allegheny Electric Cooperative, Inc. (co-applicant) for licenses to operate the Susquehanna Steam Electric Station, Units 1 and 2, located on a site in Luzerne County, Pennsylvania. This supplement to NUREG-0776 addresses the remaining issues that required resolution before licensing operation of Unit 2 and closes them out

  6. Safety-evaluation report related to the operation of Limerick Generating Station, Units 1 and 2 (Docket Nos. 50-352 and 50-353)

    International Nuclear Information System (INIS)

    1983-08-01

    The Safety Evaluation Report for the application filed by the Philadelphia Electric Company, as applicant and owner, for licenses to operate the Limerick Generating Station Units 1 and 2 (Docket Nos. 50-352 and 50-353), has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located near Pottstown, Pennsylvania. Subject to favorable resolution of the items discussed in this report, the NRC staff concludes that the facility can be operated by the applicant without endangering the health and safety of the public

  7. Safety Evaluation Report related to the operation of Wolf Creek Generating Station, Unit No. 1 (Docket No. STN 50-482). Supplement No. 6

    International Nuclear Information System (INIS)

    1985-06-01

    This report supplements the Safety Evaluation Report (SER) for the application filed by the Kansas Gas and Electric Company, as applicant and agent for the owners, for a license to operate the Wolf Creek Generating Station, Unit 1 (Docket No. STN 50-482). The facility is located in Coffey County, Kansas. This supplement provides recent information regarding resolution of the license conditions identified in the SER. Because of the favorable resolution of the items discussed in this report, the staff concludes that the facility can be operated by the licensee at power levels greater than 5% without endangering the health and safety of the public

  8. Draft environmental statement related to the operation of Braidwood Station, Units 1 and 2 (Docket Nos. STN 50-456 and STN 50-457)

    International Nuclear Information System (INIS)

    1983-12-01

    The Draft Environment Statement contains the second assessment of the environmental impact associated with the operation of Braidwood Station, Units 1 and 2, pursuant to the National Environmental Policy Act of 1969 (NEPA) and Title 10 of the Code of Federal Regulations, Part 51, as amended, of the Nuclear Regulatory Commission regulations. This statement examines the environment, environmental consequences and mitigating actions, and environmental and economic benefits and costs. Land use and terrestrial and aquatic ecological impacts will be small. Operational impacts to historic and archeologic sites will be negligible. The effects of routine operations, energy transmission, and periodic maintenance of rights of way and transmission facilities should not jeopardize any populations of endangered or threatened species. No significant impacts are anticipated from normal operational releases of radioactivity. The risk of radiation exposure associated with accidental release of radioactivity is very low. The net socioeconomi effects of the project will be beneficial. On the basis of the analysis and evaluation set forth in this environmental statement, it is concluded that the action called for under NEPA and 10 CFR 51 is the issuance of operating licenses for Braidwood Station, Units 1 and 2

  9. Replacement of five main block valves without interruption of normal operation in a remote NGL station placed at 13400 FT AMSL, challenge and strategies

    Energy Technology Data Exchange (ETDEWEB)

    Quinto, Yamil; Morales, Raul; Elorreaga, Gerson [Compania Operadora del Gas del Amazonas, Lima (Peru)

    2012-07-01

    The present paper is aimed to share experience of the replacement of five block valves carried on in a pressure reduction station remotely operated and located in a remote area in The Andes of Peru at 13400 ft AMSL. To accomplish the job, it was necessary the construction of a temporary bypass made of carbon steel pipeline with its own regulating, instrumentation and automation facilities, hence capable of reduce the NGL pressure, controlled and remotely operated by a SCADA system. The temporary bypass connection and disconnection to put on service was carried out using Hot Tap and Line Stop equipment. The replacement of the five block valves was met without interruption of the hydrocarbons flow, and resetting the pressure reduction station to steady operating conditions. Besides the operating works these activities involve safety considerations for personal working in high altitudes. The outputs were the successful replacements of the block valves, and most important was that the NGL continuous flow was met, so both the production and processing plants were supplied with the daily transportation rates in standard conditions, and in accordance with the requirements of the plant operation. (author)

  10. Final environmental statement related to the operation of Braidwood Station, Units 1 and 2 (Docket Nos. STN 50-456 and STN 50-457)

    International Nuclear Information System (INIS)

    1984-06-01

    This Final Environmental Statement contains the second assessment of the environmental impact associated with the operation of Braidwood Station, Units 1 and 2, pursuant to the National Environmental Policy Act of 1969 (NEPA) and Title 10 of the Code of Federal Regulations, Part 51, as amended, of the Nuclear Regulatory Commission regulations. This statement examines the environment, environmental consequences and mitigating actions, and environmental and economic benefits and costs. Land use and terrestrial and aquatic ecological impacts will be small. Operational impacts to historic and archeologic sites will be moderate. The effects of routine operations, energy transmission, and periodic maintenance of rights of way and transmission facilities should not jeopardize any populations of endangered or threatened species. No significant impacts are anticipated from normal operational releases of radioactivity. The risk of radiation exposure associated with accidental release of radioactivity is very low. The net socioeconomic effects of the project will be beneficial. On the basis of the analysis and evaluation set forth in this environmental statement, it is concluded that the action called for under NEPA and 10 CFR 51 is the issuance of operating licenses for Braidwood Station, Units 1 and 2. 27 figures, 23 tables

  11. Draft environmental statement related to the operation of Limerick Generating Station, Units 1 and 2. Docket Nos. 50-352 and 50-353

    International Nuclear Information System (INIS)

    1983-06-01

    This Draft Environmental Statement contains the second assessment of the environmental impact associated with the operation of the Limerick Generating Station, Units 1 and 2, pursuant to the National Environment Policy Act of 1969 (NEPA) and Title 10 of the Code of Federal Regulations, Part 51, as amended, of the Nuclear Regulatory Commission regulations. This statement examines the environment, environmental consequences and mitigating actions, and environmental and economic benefits and costs. Land use and terrestrial and aquatic ecological impacts will be small. Operational impacts to historic and archeological sites will be negligible. The effects of routine operations, energy transmission, and periodic maintenance of rights of way and transmission facilities should not jeopardize any populations of endangered or threatened species. No significant impacts are anticipated from normal operational releases of radioactivity

  12. Particulate matter over a seven year period in urban and rural areas within, proximal and far from mining and power station operations in Greece.

    Science.gov (United States)

    Triantafyllou, A G; Zoras, S; Evagelopoulos, V

    2006-11-01

    Lignite mining operations and lignite-fired power stations result in major particulate pollution (fly ash and fugitive dust) problems in the areas surrounding these activities. The problem is more complicated, especially, for urban areas located not far from these activities, due to additional contribution from the urban pollution sources. Knowledge of the distribution of airborne particulate matter into size fraction has become an increasing area of focus when examining the effects of particulate pollution. On the other hand, airborne particle concentration measurements are useful in order to assess the air pollution levels based on national and international air quality standards. These measurements are also necessary for developing air pollutants control strategies or for evaluating the effectiveness of these strategies, especially, for long periods. In this study an attempt is made in order to investigate the particle size distribution of fly ash and fugitive dust in a heavy industrialized (mining and power stations operations) area with complex terrain in the northwestern part of Greece. Parallel total suspended particulates (TSP) and particulate matter with an aerodynamic diameter less than 10 microm (PM10) concentrations are analyzed. These measurements gathered from thirteen monitoring stations located in the greater area of interest. Spatial, temporal variation and trend are analyzed over the last seven years. Furthermore, the geographical variation of PM10 - TSP correlation and PM10/TSP ratio are investigated and compared to those in the literature. The analysis has indicated that a complex system of sources and meteorological conditions modulate the particulate pollution of the examined area.

  13. Improved grid operation through power smoothing control strategies utilizing dedicated energy storage at an electric vehicle charging station

    DEFF Research Database (Denmark)

    Martinsen, Thomas; Holjevac, Ninoslav; Bremdal, Bernt A.

    2016-01-01

    project (Flex-ChEV) supported by the ERA-Net Smart Grid FP7 program. The principal asset of the proposed charging station (CS) is a dedicated Energy Storage System (ESS) to compensate for adverse effects on the grid caused by peak charging demand and which could impose severe trials for the local DSO....... Furthermore, CS of this kind could serve multiple business purposes in a smart grid. It can serve as a hub for seamless integration of local renewable and distributed energy resources, it can provide added flexibility for the local grid through different ancillary services and it can act as an efficient......This paper addresses the principal service aspects for electric vehicles (EV), as well as issues related to energy storage design, charging station integration into power system and load management issues. It builds on the research conducted in the Flexible Electric Vehicle Charging Infrastructure...

  14. Final environmental statement: Related to the operation of Davis-Besse Nuclear Power Station, Unit 1 (Docket No. 50-346)

    International Nuclear Information System (INIS)

    1975-10-01

    The proposed action is the issuance of an operating license to the Toledo Edison Company and the Cleveland Electric Illuminating Company for the startup and operation of the Davis-Besse Nuclear Power Station Unit 1 (the station) located near Port Clinton in Ottawa County, Ohio. The total site area is 954 acres of which 160 acres have been removed from production of grain crops and converted to industrial use. Approximately 600 acres of the area is marshland which will be maintained as a wildlife refuge. The disturbance of the lake shore and lake bottom during construction of the station water intake and discharge pipes resulted in temporary turbidity, silting, and destruction of bottom organisms. Since completion of these activities, evidence of improvement in turbidity and transparency measurements, and the reestablishment of the bottom organism has been obtained. The cooling tower blowdown and service water which the station discharges to Lake Erie, via a submerged jet, will be heated no more than 20/degrees/F above the ambient lake water temperature. Although some small fish and plankton in the discharge water plume will be disabled as a result of thermal shock, exposure to chlorine and buffeting, few adult fish will be affected. The thermal plume resulting from the maximum thermal discharge is calculated to have an area of less than one acre within the 3/degrees/F isotherm (above lake ambient). Approximately 101 miles of transmission lines have been constructed, primarily over existing farmland, requiring about 1800 acres of land for the rights-of-way. Land use will essentially be unchanged since only the land required for the base of the towers is removed from production. Herbicides will not be used to maintain the rights-of-way. 14 figs., 34 refs

  15. 47 CFR 97.109 - Station control.

    Science.gov (United States)

    2010-10-01

    ... 47 Telecommunication 5 2010-10-01 2010-10-01 false Station control. 97.109 Section 97.109... SERVICE Station Operation Standards § 97.109 Station control. (a) Each amateur station must have at least one control point. (b) When a station is being locally controlled, the control operator must be at the...

  16. Safety Evaluation Report related to the operation of Limerick Generating Station, Units 1 and 2 (Docket Nos. 50-352 and 50-353). Supplement No. 6

    International Nuclear Information System (INIS)

    1985-08-01

    In August 1983 the staff of the Nuclear Regulatory Commission issued its Safety Evaluation Report (NUREG-0991) regarding the application of the Philadelphia Electric Company (the licensee) for licenses to operate the Limerick Generating Station, Units 1 and 2, located on a site in Montgomery and Chester Counties, Pennsylvania. A license for the operation of Limerick Unit 1 was issued on October 26, 1984. The license, which was restricted to a five percent power level, contained conditions which required resolution prior to proceeding beyond the five percent power level. Supplement 4, issued in May 1985, addressed some of these issues. Supplement 4 also contained the comments made by the Advisory Committee on Reactor Safeguards in its report dated November 6, 1984, regarding full power operation of Limerick Unit 1. Supplement 5, issued in July 1985, and this Supplement 6 address further issues, principally the status of offsite emergency planning, that require resolution prior to proceeding beyond the five percent power level

  17. Safety Evaluation Report related to the operation of Catawba Nuclear Station, Units 1 and 2 (Docket Nos. 50-413 and 50-414). Supplement No. 6

    International Nuclear Information System (INIS)

    1986-05-01

    This report supplements the Safety Evaluation Report (NUREG-0954) issued in February 1983 by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission with respect to the application filed by Duke Power Company, North Carolina Municipal Power Agency Number 1, North Carolina Membership Corporation, Saluda River Electric Cooperative, Inc., and Piedmont Municipal Power Agency, as applicants and owners, for licenses to operate the Catawba Nuclear Station, Units 1 and 2 (Docket Nos. 50-413 and 50-414, respectively). The facility is located in York County, South Carolina, approximately 9.6 km (6 miles) north of Rock Hill and adjacent to Lake Wylie. This supplement provides additional information supporting the license for operation above 5% power and power ascension to full-power operation for Unit 2

  18. Safety Evaluation Report related to the full-term operating license for Millstone Nuclear Power Station, Unit No. 1 (Docket No. 50-245)

    International Nuclear Information System (INIS)

    1985-10-01

    The Safety Evaluation Report for the full-term operating license application filed by the Connecticut Light and Power Company, the Hartford Electric Light Company, Western Massachusetts Electric Company and the Millstone Point Company [(now known as Connecticut Light and Power Company (CL and P) and Western Massachusetts Electric Company (WMECO) having authority to possess Millstone-1, 2, and 3, and the Northeast Nuclear Energy Company (NNECO) as the responsible entity for operation of the facilities)] for Millstone Nuclear Power Station Unit 1 has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located in the town of Waterford, Connecticut. Subject to favorable resolution of the items discussed in this report, the staff concludes that the facility can continue to be operated without endangering the health and safety of the public

  19. Proof of safer operation of power station plant during a fire by linking in fire simulation and system technical analysis

    International Nuclear Information System (INIS)

    Hensel, W.; Beyer, H.; Samman, A.

    1997-01-01

    In order to attain the basic aims of protection in power station plant, a series of systems, which must be available also in the event of a fire, are provided. The thermal loads for the systems and components which are necessary to attain the aims of protection are ascertained by means of a simulation of the cause of the fire for the specific scenario. Statements on the availability of the systems and components in the specific scenario are derived from the design values used as the basis. (orig.) [de

  20. On the operation of the Structural Materials Science end-station of the Kurchatov synchrotron radiation source in 2006

    International Nuclear Information System (INIS)

    Veligzhanin, A.A.; Guseva, E.V.; Zubavichus, Ya.V.; Trigub, A.L.; Chernyshev, A.A.

    2007-01-01

    The findings of investigation conducted at the end-station STM (Structural Materials Science) installed at the Kurchatov Centre for Synchrotron Radiation and Nanotechnology in 2006 are reported. During the reporting period, a variety of experiments aimed at the solution of diverse fundamental and applied problems have been performed in a cooperation with users from several laboratories located in Moscow, Saint-Petersburg and Rostov-on-Don, specialized in physics, chemistry and materials science. The emphasis in the research activity was placed on combined investigations into the atomic and electronic structures of functional materials with nanosized structural elements, including membrane catalysts, chemical gas sensors, materials with special magnetic, ferroelectric, and thermal properties, etc. In all the cases involved, the approach based on the utilization of the whole assortment of X-ray synchrotron experimental techniques implemented at the end-station STM (viz., small-angle X-ray scattering, X-ray diffraction, and X-ray absorption spectroscopy) provided detailed information on different aspects of the structural organization in the materials under study, which made it possible to suggest the most probable models for their structures [ru

  1. Safety Evaluation Report related to the operation of Waterford Steam Electric Station, Unit No. 3 (Docket No. 50-382). Supplement No. 8

    International Nuclear Information System (INIS)

    1984-12-01

    Supplement 8 to the Safety Evaluation Report for the application filed by Louisiana Power and Light Company for a license to operate the Waterford Steam Electric Station, Unit 3 (Docket No. 50-382), located in St. Charles Parish, Louisiana, has been prepared by the Office of Nuclear Reactor Regulation of the Nuclear Regulatory Commission. The purpose of this supplement is to update the Safety Evaluation Report by providing the staff's evaluation of information submitted by the applicant since the Safety Evaluation Report and its seven previous supplements were issued

  2. Safety Evaluation Report related to the operation of Braidwood Station, Units 1 and 2 (Docket Nos. 50-456 and 50-457)

    International Nuclear Information System (INIS)

    1987-05-01

    In November 1983, the staff of the Nuclear Regulatory Commission issued its Safety Evaluation Report (NUREG-1002) regarding the application filed by the Commonwealth Edison Company, as applicant and owner, for a license to operate Braidwood Station, Units 1 and 2 (Docket Nos. 50-456 and 50-457). The first supplement to NUREG-1002 was issued in September 1986; the second supplement to NUREG-1002 was issued in October 1986. This third supplement to NUREG-1002 reports the status of certain items that remained unresolved at the time Supplement 2 was published. The facility is located in Reed Township, Will County, Illinois

  3. Safety-evaluation report related to the operation of Waterford Steam Electric Station, Unit No. 3. Docket No. 50-382

    International Nuclear Information System (INIS)

    1983-06-01

    Supplement 5 to the Safety Evaluation Report for the application filed by Louisiana Power and Light Company for a license to operate the Waterford Steam Electric Station, Unit 3 (Docket No. 50-382), located in St. Charles Parish, Louisiana has been prepared by the Office of Nuclear Reactor Regulation of the Nuclear Regulatory Commission. The purpose of this supplement is to update the Safety Evaluation Report by providing the staff's evaluation of information submitted by the applicant since the Safety Evaluation Report and its four previous Supplements were issued

  4. Safety evaluation report related to the operation of Clinton Power Station, Unit No. 1 (Docket No. 50-461). Suppl. 3

    International Nuclear Information System (INIS)

    1984-05-01

    Supplement No. 3 to the Safety Evaluation Report on the application filed by Illinois Power Company, Soyland Power Cooperative, Inc., and Western Illinois Power Cooperative, Inc., as applicants and owners, for a license to operate the Clinton Power Station, Unit No. 1, has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located in Harp Township, DeWitt County, Illinois. This supplement reports the status of certain items that had not been resolved at the time of publication of the Safety Evaluation Report and Supplements No. 1 and 2

  5. Safety evaluation report related to the operation of Waterford Steam Electric Station, Unit No. 3 (Docket No. 50-382). Suppl.6

    International Nuclear Information System (INIS)

    1984-06-01

    Supplement 6 to the Safety Evaluation Report for the application filed by Louisiana Power and Light Company for a license to operate the Waterford Steam Electric Station, Unit 3 (Docket No. 50-382), located in St. Charles Parish, Louisiana, has been prepared by the Office of Nuclear Reactor Regulation of the Nuclear Regulatory Commission. The purpose of this supplement is to update the Safety Evaluation Report by providing the staff's evaluation of information submitted by the applicant since the Safety Evaluation Report and its five previous supplements were issued

  6. Safety Evaluation Report related to the operation of Clinton Power Station, Unit No. 1 (Docket No. 50-461). Supplement No. 6

    International Nuclear Information System (INIS)

    1986-07-01

    Supplement No. 6 to the Safety Evaluation Report on the application filed by Illinois Power Company, Soyland Power Cooperative, Inc., and Western Illinois Power Cooperative, Inc., as applicants and owners, for a license to operate the Clinton Power Station, Unit No. 1, has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located in Harp Township, DeWitt County, Illinois. This supplement reports the status of items that have been resolved by the staff since Supplement No. 5 was issued

  7. Safety evaluation report related to the operation of Clinton Power Station, Unit No. 1 (Docket No. 50-461). Supplement No. 5

    International Nuclear Information System (INIS)

    1986-01-01

    Supplement No. 5 to the Safety Evaluation Report on the application filed by Illinois Power Company, Soyland Power Cooperative, Inc., and Western Illinois Power Cooperative, Inc. as applicants and owners, for a license to operate the Clinton Power Station, Unit No. 1, has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located in Harp Township, DeWitt County, Illinois. This supplement reports the status of items that have been resolved by the staff since supplement No. 4 was issued

  8. Safety Evaluation Report related to the operation of Clinton Power Station, Unit No. 1 (Docket No. 50-461). Supplement No. 7

    International Nuclear Information System (INIS)

    1986-09-01

    Supplement No. 7 to the Safety Evaluation Report on the application filed by Illinois Power Company, Soyland Power Cooperative, Inc., and Western Illinois Power Cooperative, Inc., as applicants and owners, for a license to operate the Clinton Power Station, Unit No. 1, has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located in Harp Township, DeWitt County, Illinois. This supplement reports the status of items that have been resolved by the staff since Supplement No. 6 was issued

  9. Safety Evaluation Report related to the operation of Braidwood Station, Units 1 and 2 (Docket Nos. 50-456 and 50-457). Supplement No. 2

    International Nuclear Information System (INIS)

    1986-10-01

    In November 1983, the staff of the Nuclear Regulatory Commission issued its Safety Evaluation Report (NUREG-1002) regarding the application filed by the Commonwealth Edison Company, as applicant and owner, for a license to operate Braidwood Station, Units 1 and 2 (Docket Nos. 50-456 and 50-457). The first supplement to NUREG-1002 was issued in September 1986. This second supplement to NUREG-1002 reports the status of certain items that remained unresolved at the time Supplement 1 was published. The facility is located in Reed Township, Will County, Illinois

  10. Safety Evaluation Report related to the operation of Waterford Steam Electric Station, Unit No. 3 (Docket No. 50-382). Supplement 9

    International Nuclear Information System (INIS)

    1984-12-01

    Supplement 9 to the Safety Evaluation Report for Louisiana Power and Light's application for a license to operate Waterford Steam Electric Station, Unit 3 (Docket No. 50-382), located in St. Charles Parish, Louisiana, has been jointly prepared by the Office of Nuclear Reactor Regulation and the Region IV Office of the US Nuclear Regulatory Commission. This supplement provides the results of the staff's completion of its evaluation of approximately 350 allegations and concerns of poor construction practices at the Waterford 3 facility

  11. Safety Evaluation Report related to the operation of Clinton Power Station, Unit No. 1 (Docket No. 50-461). Supplement No. 4

    International Nuclear Information System (INIS)

    1985-02-01

    Supplement No. 4 to the Safety Evaluation Report on the application filed by Illinois Power Company, Soyland Power Cooperative, Inc., and Western Illinois Power Cooperative, Inc., as applicants and owners, for a license to operate the Clinton Power Station, Unit No. 1, has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located in Harp Township, DeWitt County, Illinois. This supplement reports the status of items that have been resolved by the staff since Supplement No. 3 was issued

  12. Demonstration of containment purge and vent valve operability for the Hope Creek Generating Station, Unit 1 (Docket No. 50-354)

    International Nuclear Information System (INIS)

    Kido, C.

    1985-05-01

    The containment purge and vent valve qualification program for the Hope Creek Generating Station has been reviewed by the NRC Licensing Support Section. The review indicates that the licensee has demonstrated the dependability of containment isolation against the buildup of containment pressure due to a LOCA/DBA with the restrictions that during operating conditions 1, 2, and 3 all purge and vent valves will be sealed closed and under administrative control, and during power ascension and descension conditions the 26 in. inboard valve (1-GS-HV-4952) will be used in series with the 2 in. bypass valve (1-GS-HV-4951) to control the release of containment pressure

  13. Safety Evaluation Report related to the operation of Braidwood Station, Units 1 and 2 (Docket Nos. 50-456 and 50-457). Supplement No. 1

    International Nuclear Information System (INIS)

    1986-09-01

    In November 1983 the staff of the Nuclear Regulatory Commission issued its Safety Evaluation Report (NUREG-1002) regarding the application filed by the Commonwealth Edison Company, as applicant and owner, for a license to operate Braidwood Station, Units 1 and 2 (Docket Nos. STN 50-456 and STN 50-457). The facility is located in Reed Township, Will County, Illinois. This first supplement to NUREG-1002 reports the status of certain items that remained unresolved at the time the Safety Evaluation Report was published

  14. Safety Evaluation Report related to the operation of Millstone Nuclear Power Station Unit No. 3 (Docket No. 50-4423). Supplement No. 1

    International Nuclear Information System (INIS)

    1985-03-01

    In July 1984 staff of the Nuclear Regulatory Commission issued its Safety Evaluation Report regarding the application of Northeast Nuclear Energy Company (applicant and agent for the owners) for a license to operate Millstone Nuclear Power Station, Unit No. 3 (Docket 50-423). The facility is located in the town of Waterford, New London County, Connecticut, on the north shore of Long Island Sound. This first supplement to NUREG-1031 reports the status of certain items that remained unresolved at the time the Safety Evaluation Report was published

  15. Browns Ferry Nuclear Power Station, Units 1, 2, and 3. Annual operating report: 1 January--31 December 1977

    International Nuclear Information System (INIS)

    1978-01-01

    The three reactors operated at near full power generating 17,622,500 MWH gross electrical power. There were 153 major power reductions including 50 scrams mostly caused by equipment failures. Data are presented concerning operations, modifications, occupational exposures, effluent activity, and waste disposal

  16. Flow and pressure profiles for the primary heat transport system of Rajasthan Atomic Power Station for the operation with few isolated reactor channels near the end shield cracks

    Energy Technology Data Exchange (ETDEWEB)

    Gaikwad, A J; Chaki, S K; Sehgal, R L; Venkat Raj, V [Reactor Safety Division, Bhabha Atomic Research Centre, Mumbai (India)

    1994-06-01

    The RAPS (Rajasthan Atomic Power Station) unit-1 is now operating at reduced power due to the removal of fifteen fuel channels for repair of south end shield cracks. The power level is restricted to 50% of the full power capacity as a precautionary measure. The relative difference that operation at 50% power and higher power would make to the end shield structure is being currently analysed with a view to operate this reactor at higher power levels. As a prerequisite, a detailed thermal hydraulic analysis is essential to assess the effect of reactor operation with isolated channels on the primary heat transport (PHT) system pressure, flow, temperature. The adequacy of the existing trip set points for the plant operation under this mode is also required to be assessed. In the present study, analysis of the PHT system has been carried out to determine the flow and pressure profiles for the RAPS heat transport system for operation of the reactor with isolated channels. (author). 5 refs., 1 fig., 1 tab.

  17. Safety evaluation report related to the operation of Limerick Generating Station, Units 1 and 2 (Docket Nos. 50-352 and 50-353)

    International Nuclear Information System (INIS)

    1989-06-01

    In August 1983 the staff of the Nuclear Regulatory Commission issued its Safety Evaluation Report (NUREG-0991) regarding the application of the Philadelphia Electric Company (the licensee) for licenses to operate the Limerick Generating Station, Units 1 and 2, located on site in Montgomery and Chester Counties, Pennsylvania. Supplement 1 to NUREG-0991 was issued in December 1983. Supplements 2 and 3 were issued in October 1984. License NPF-27 for the low-power operation of Limerick Unit 1 was issued on October 26, 1984. Supplement 4 was issued in May, 1985, Supplement 5 was issued in July 1985, and Supplement 6 was issued in August 1985. These supplements addressed further issues that required resolution before Unit 1 proceeded beyond the 5-percent power level. The full-power operating license for Limerick Unit 1 (NPF-39) was issued August 8, 1985, and the unit has completed two cycles of operation. Supplement 7 was issued April 1989 to address some of the few significant design differences between Units 1 and 2, the resolution of issues that remained open when the Unit 1 full-power license was issued and an assessment of some of the issues that required resolution before issuance of an operating license for Unit 2. This supplement addresses the remaining issues that required resolution before issuance of and operating license for Unit 2

  18. A process for superheating steam in a nuclear power station circuit and device for putting in operation this process

    International Nuclear Information System (INIS)

    Monteil, Marcel; Forestier, Jean; Leblanc, Bernard; Monteil, Pierre

    1975-01-01

    A process is described for superheating steam in a nuclear power station circuit, comprising a turbine with a high pressure chamber and a low pressure chamber. It consists in superheating the steam between the high and low pressure chambers of the turbine by using as heating fluid water under pressure at vaporisation temperature, directly taken from the recirculation or circulation flow water of the reactor or of the steam generators. The process is adapted to a pressurised water reactor using a once-through steam generator comprising in succession an economiser, a vaporiser and a superheater, the superheating water being taken at the vaporiser intake. It is also adapted for a boiling water reactor, in that the water is taken directly from the reactor vessel and at a suitable level in the recirculation water [fr

  19. Environmental Radiation Surveillance Results from over the Last Decade of Operational Experience at the Regional Radiation Monitoring Stations(RRMS)

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Hae Young [Daegu Regional Radiation Monitoring Station, Daegu (Korea, Republic of); Yoo, Dong Han [Ulsan Regional Radiation Monitoring Station, Ulsan (Korea, Republic of); Lee, Sang Hoon [Kyungpook National University, Daegu (Korea, Republic of)

    2015-10-15

    The objectives of the current program are to monitor environmental radiation/radioactivity level in Korea and to provide the base-line data on environmental radiation/radioactivity which will be useful in the case of radiological emergency situations. This program plays an important role in the view of protecting the public health against the potential hazards of radiation and maintaining a clean environment. This paper describes an introduction to the Regional Radiation Monitoring Stations (RRMS), and also presents some results of recent years (2001-2014). The environmental radiation surveillance results of years 2001-2014 have been described. It indicates normal levels of radiation in the past years. These kinds of studies are very important in providing references in understanding the environmental radioactivity level in a particular region.

  20. Preliminary results of a pilot study on the behaviour of nuclear power station operating staff in simulated faults

    International Nuclear Information System (INIS)

    Reinartz, S.J.

    1984-01-01

    The necessity of distinguishing the effect of a fault and the stabilizing effects of the automatic control devices leads to operating staff being supported by suitable configuration of the control room and work aids. The aim of the study consists of having a better understanding of how control room operating staff control a fault and how they carry out the problem solving tasks of fault recognition, diagnosis and compensation. These tasks differ from the normal daily tasks and operators only have to do them rarely. The study is intended to examine what is necessary so that operators can do their job: what information they have to have about plant conditions and how this should be shown: trend information of digital display, conventional indication or VDU screens. (orig./DG) [de

  1. Safety evaluation report related to the operation of Nine Mile Point Nuclear Station, Unit No. 2 (Docket No. 50-410)

    International Nuclear Information System (INIS)

    1986-07-01

    This report supplements the Safety Evaluation Report (NUREG-1047, February 1985) for the application filed by Niagara Mohawk Power Corporation, as applicant and co-owner, for a license to operate the Nine Mile Point Nuclear Station, Unit No. 2 (Docket No. 50-410). It has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located near Oswego, New York. Supplement 1 to the Safety Evaluation Report was published in June 1985 and contained the report from the Advisory Committee on Reactor Safeguards as well as the resolution to a number of outstanding issues from the Safety Evaluation Report. Supplement 2 was published in November 1985 and contained the resolution to a number of outstanding and confirmatory issues. Subject to favorable resolution of the issues discussed in this report, the NRC staff concludes that the facility can be operated by the applicant without endangering the health and safety of the public

  2. Safety evaluation report related to the operation of Seabrook Station, Units 1 and 2. Docket Nos. 50-443 and 50-444. Suppl. 1

    International Nuclear Information System (INIS)

    1983-04-01

    This report supplements the Safety Evaluation Report (NUREG-0896, March 1983) for the application filed by the Public Service Company of New Hampshire, et. al., for licenses to operate Seabrook Station, Units 1 and 2 (Docket Nos. STN 50-443 and STN 50-444). It has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission and provides recent information on open items identified in the SER. The facility is located in Seabrook, New Hampshire. Subject to favorable resolution of the items discussed in this report, the staff concludes that the facility can be operated by the applicant without endangering the health and safety of the public

  3. Safety Evaluation Report related to the operation of Seabrook Station, Units 1 and 2 (Docket Nos. 50-443 and 50-444)

    International Nuclear Information System (INIS)

    1989-05-01

    This report is Supplement No. 8 to the Safety Evaluation Report (SER) (NUREG-0896, March 1983) for the application filed by the Public Service Company of New Hampshire, et al., for licenses to operate Seabrook Station, Units 1 and 2 (Docket Nos. STN 50-443 and STN 50-444). It has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission and provides recent information on open items identified in the SER. The facility is located in Seabrook, New Hampshire. Subject to favorable resolution of the items discussed in this report, the staff concludes that the facility can be operated by the applicant without endangering the health and safety of the public. 2 figs., 1 tab

  4. Safety Evaluation Report related to the operation of Seabrook Station, Units 1 and 2 (Docket Nos. 50-443 and 50-444). Supplement No. 5

    International Nuclear Information System (INIS)

    1986-07-01

    This report is Supplement No. 5 to the Safety Evaluation Report (NUREG-0896, March 1983) for the application filed by the Public Service Company of New Hampshire, et al., for licenses to operate Seabrook Station, Units 1 and 2 Docket Nos. STN 50-443 and STN 50-444). It has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission and provides recent information on open items identified in the SER. The facility is located in Seabrook, New Hampshire. Subject to favorable resolution of the items discussed in this report, the staff concludes that the facility can be operated by the applicant without endangering the health and safety of the public

  5. Safety Evaluation Report related to the operation of Seabrook Station, Units 1 and 2 (Docket Nos. 50-443 and 50-444)

    International Nuclear Information System (INIS)

    1990-03-01

    This report is Supplement No. 9 to the Safety Evaluation Report (SER) (NUREG-0896, March 1983) for the application filed by the Public Service Company of New Hampshire, et al., for licenses to operate Seabrook Station, Units 1 and 2. It has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission and provides recent information on open items identified in the SER. The facility is located in Seabrook, New Hampshire. Subject to favorable resolution of the items discussed in this report, the staff concludes that the facility can be operated by the applicant without endangering the health and safety of the public. 70 refs., 1 fig., 1 tab

  6. Safety Evaluation Report related to the operation of Cartawba Nuclear Station, Units 1 and 2 (Docket Nos. 50-413 and 50-414). Supplement No. 5

    International Nuclear Information System (INIS)

    1986-02-01

    This report supplements the Safety Evaluation Report (NUREG-0954) issued in February 1983 by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission with respect to the application filed by Duke Power Company, North Carolina Municipal Power Agency Number 1, North Carolina Membership Corporation, Saluda River Electric Cooperative, Inc., and Piedmont Municipal Power Agency, as applicants and owners, for licenses to operate the Catawba Nuclear Station, Units 1 and 2 (Docket Nos. 50-413 and 50-414, respectively). The facility is located in York County, South Carolina, approximately 9.6 km (6 mi) north of Rock Hill and adjacent to Lake Wylie. This supplement provides additional information supporting the license for initial criticality and power ascension to full-power operation for Unit 2

  7. Safety Evaluation Report related to the operation of Limerick Generating Station, Units 1 and 2 (Docket Nos. 50-352 and 50-353). Supplement 3

    International Nuclear Information System (INIS)

    1984-10-01

    In August 1983 the staff of the Nuclear Regulatory Commission issued its Safety Evaluation Report (NUREG-0991) regarding the application of the Philadelphia Electric Company (the applicant) for licenses to operate the Limerick Generating Station, Units 1 and 2. Supplement 1 was issued in December 1983 and addressed several outstanding issues. Supplement 1 also contains the comments made by the Advisory Committee on Reactor Safeguards in its report dated October 18, 1983. Supplement 2 was issued in October 1984 and addressed fourteen outstanding and fifty-three confirmatory issues and closed them put. This Supplement 3 addresses the remaining issues that require resolution before issuance of the operating license for Unit 1 and closes them out

  8. Safety Evaluation Report related to the operation of Wolf Creek Generating Station, Unit No. 1 (Docket No. STN 50-482). Supplement No. 5

    International Nuclear Information System (INIS)

    1985-03-01

    This report supplements the Safety Evaluation Report (SER) for the application filed by the Kansas Gas and Electric Company, as applicant and agent for the owners, for a license to operate the Wolf Creek Generating Station, Unit 1 (Docket No. STN 50-482). The facility is located in Coffey County, Kansas. This supplement has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission and provides recent information regarding resolution of the open items identified in the SER. Because of the favorable resolution of the items discussed in this report, the staff concludes that the facility can be operated by the applicant without endangering the health and safety of the public

  9. Safety Evaluation Report related to the operation of Millstone Nuclear Power Station, Unit No. 3 (Docket No. 50-423). Supplement No. 4

    International Nuclear Information System (INIS)

    1985-11-01

    This report supplements the Safety Evaluation Report (NUREG-1031) issued in July 1984, Supplement 1 issued in March 1985, Supplement 2 issued in September 1985, and Supplement 3 issued in November 1985, by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission with respect to the application filed by Northeast Nuclear Energy Company (applicant and agent for the owners) for a license to operate Millstone Nuclear Power Station, Unit No. 3 (Docket 50-423). The facility is located in the Town of Waterford, New London County, Connecticut, on the north shore of Long Island Sound. This supplement provides more recent information supporting the license for initial criticality and power ascension to 5% power operation for Millstone 3. 37 refs., 10 tabs

  10. Final environmental statement related to the operation of Byron Station, Units 1 and 2 (Docket Nos. STN 50-454 and STN 50-455)

    International Nuclear Information System (INIS)

    1982-04-01

    The proposed action is the issuance of an operating license to Commonwealth Edison Company (CECo) of Chicago, Illinois, for startup and operation of the Byron Station, Units 1 and 2 on a 710-ha (1754-acre) site in Ogle County 6 km (4 miles) south-southwest of Byron, Illinois, and 3 km (2 miles) east of the Rock River. Each of the two generating units consists of a pressurized-water reactor, four steam generators, one steam turbine generator, a heat-dissipation system, and associated auxiliary and engineered safeguards. Information is presented under the following topics: purpose and need for the action; alternatives to the proposed action; project description and affected environment; environmental consequences and mitigating actions; evaluation of the proposed action; list of contributors; list of agencies and organizations requested to comment on the draft environmental statement; and responses to comments on the Draft Environmental Statement

  11. Safety evaluation report related to the operation of Seabrook Station, Units 1 and 2 (Docket Nos. 50-443 and 50-444)

    International Nuclear Information System (INIS)

    1986-05-01

    This report is Supplement 4 to the Safety Evaluation Report (SER, NUREG-0896, March 1983) for the application filed by the Public Service Company of New Hampshire, et al., for licenses to operate Seabrook Station, Units 1 and 2 (Docket Nos. STN 50-443 and STN 50-444). It has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission and provides recent information on open items identified in the SER. The facility is located in Seabrook, New Hamphsire. Subject to favorable resolution of the items discussed in this report, the staff concludes that the facility can be operated by the applicant without endangering the health and safety of the public

  12. Safety evaluation report related to the operation of Seabrook Station, Units 1 and 2 (Docket Nos. 50-443 and 50-444)

    International Nuclear Information System (INIS)

    1987-10-01

    This report is Supplement No. 7 to the Safety Evaluation Report (NUREG-0896, March 1983) for the application filed by the Public Service Company of New Hampshire, et al. for licenses to operate Seabrook Station, Units 1 and 2 (Docket Nos. STN 50-443 and STN 50-444). It has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission and provides recent information on open items identified in the SER. The facility is located in Seabrook, New Hampshire. Subject to favorable resolution of the items discussed in this report, the staff concludes that the facility can be operated by the applicant without endangering the health and safety of the public

  13. Safety Evaluation Report related to the operation of Comanche Peak Steam Electric Station, Units 1 and 2. Docket Nos. 50-445 and 50-446

    International Nuclear Information System (INIS)

    1983-03-01

    Supplement No. 3 to the Safety Evaluation Report (SER) related to the operation of the Comanche Peak Steam electric Station, Units 1 and 2, has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. the facility is located in Somervell County, Texas. Subject to favorable resolution of the items identified in this supplement, the staff concludes that the facility can be operated by the applicatn without endangering the health and safety of the public. This document provides the NRC staff's evaluation of the outstanding and confirmatory issues that have been resolved since Supplement No. 2 was issued in January 1982, and addresses changes to the SER and its earlier supplements which have resulted from the receipt of additonal information from the applicant during the period of January throught October 1982

  14. Safety-evaluation report related to the operation of Seabrook Station, Units 1 and 2. Docket Nos. 50-443 and 50-444

    International Nuclear Information System (INIS)

    1983-06-01

    This report is Supplement 2 to the Safety Evaluation Report (NUREG-0896, March 1983) for the application filed by the Public Service Company of New Hampshire, et al., for licenses to operate Seabrook Station, Units 1 and 2 (Docket Nos. STN 50-443 and STN 50-444). It has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission and provides recent information on open items identified in the SER. The facility is located in Seabrook, New Hampshire. Subject to favorable resolution of the items discussed in this report, the staff concludes that the facility can be operated by the applicant without endangering the health and safety of the public

  15. Space Station fluid management logistics

    Science.gov (United States)

    Dominick, Sam M.

    1990-01-01

    Viewgraphs and discussion on space station fluid management logistics are presented. Topics covered include: fluid management logistics - issues for Space Station Freedom evolution; current fluid logistics approach; evolution of Space Station Freedom fluid resupply; launch vehicle evolution; ELV logistics system approach; logistics carrier configuration; expendable fluid/propellant carrier description; fluid carrier design concept; logistics carrier orbital operations; carrier operations at space station; summary/status of orbital fluid transfer techniques; Soviet progress tanker system; and Soviet propellant resupply system observations.

  16. Result of 'clean plant operation tactics' in Onagawa Nuclear Power Station No.1 unit during the first fuel cycle and the first maintenance outage

    International Nuclear Information System (INIS)

    Nukazuka, Hideo; Terada, Hideo; Morikawa, Yoshitake; Tomura, Susumu.

    1986-01-01

    On June 1, 1984, No.1 plant in Onagawa Nuclear Power Station started the commercial operation, and recorded the nonstop operation for 344 days. The parallel off was made on April 3, 1985, and the first regular inspection was carried out. On July 12, 1985, the regular inspection was completed, and thereafter, the second cycle operation has been smoothly continued. Special attention was paid to the measures for reducing radiation exposure, and the attainment of the clean plant was aimed at. As the measures for reducing radiation level, the strengtheining of purifying facilities, the suppression of crud generation, the adoption of low cobalt material and the strengthening of shielding were carried out. For shortening exposure time, the machinery and equipment were improved, paying attention to automation, remote operation and labor saving, and the improvement of reliability, maintainability and inspection. In addition to these design measures, in the construction, operation and regular inspection, the clean plant measures were taken. Very good results were obtained. (Kako, I.)

  17. Fuzzy logics acquisition and simulation modules for expert systems to assist operator's decision for nuclear power stations

    International Nuclear Information System (INIS)

    Averkin, A.A.

    1994-01-01

    A new type of fuzzy expert system for assisting the operator's decisions in nuclear power plant system in non-standard situations is proposed. This expert system is based on new approaches to fuzzy logics acquisition and to fuzzy logics testing. Fuzzy logics can be generated by a T-norms axiomatic system to choose the most suitable to operator's way of thinking. Then the chosen fuzzy logic is tested by simulation of inference process in expert system. The designed logic is the input of inference module of expert system

  18. Order Granting and Denying in Part the Petition for Objection to the Xcel Energy, Hayden Station Operating Permit, Hayden Colorado

    Science.gov (United States)

    This document may be of assistance in applying the Title V air operating permit regulations. This document is part of the Title V Petition Database available at www2.epa.gov/title-v-operating-permits/title-v-petition-database. Some documents in the database are a scanned or retyped version of a paper photocopy of the original. Although we have taken considerable effort to quality assure the documents, some may contain typographical errors. Contact the office that issued the document if you need a copy of the original.

  19. Petition to Object to the Eastern Kentucky Power Coop. William C. Dale Power Station, Ford, Kentucky, Title V Operating Permit

    Science.gov (United States)

    This document may be of assistance in applying the Title V air operating permit regulations. This document is part of the Title V Petition Database available at www2.epa.gov/title-v-operating-permits/title-v-petition-database. Some documents in the database are a scanned or retyped version of a paper photocopy of the original. Although we have taken considerable effort to quality assure the documents, some may contain typographical errors. Contact the office that issued the document if you need a copy of the original.

  20. Shippingport Station Decommissioning Project

    International Nuclear Information System (INIS)

    McKernan, M.L.

    1989-01-01

    The Shippingport Atomic Power Station was located on the Ohio River in Shippingport Borough (Beaver County), Pennsylvania, USA. The US Atomic Energy Commission (AEC) constructed the plant in the mid-1950s on a seven and half acre parcel of land leased from Duquesne Light Company (DLC). The purposes were to demonstrate and to develop Pressurized Water Recovery technology and to generate electricity. DLC operated the Shippingport plant under supervision of (the successor to AEC) the Department of Energy (DOE)-Naval Reactors (NR) until operations were terminated on October 1, 1982. NR concluded end-of-life testing and defueling in 1984 and transferred the Station's responsibility to DOE Richland Operations Office (RL), Surplus Facility Management Program Office (SFMPO5) on September 5, 1984. SFMPO subsequently established the Shippingport Station Decommissioning Project and selected General Electric (GE) as the Decommissioning Operations Contractor. This report is intended to provide an overview of the Shippingport Station Decommissioning Project

  1. 78 FR 50455 - Vogtle Electric Generating Station, Units 3 and 4; Southern Nuclear Operating Company; Changes to...

    Science.gov (United States)

    2013-08-19

    ... Purification Return Line in order to maintain overpressure protection, replaces an isolation check valve in the CVS with an air operated globe valve, and separates the zinc and hydrogen injection lines. Part of the... modification which provides a spring-assisted check valve to the Reactor Coolant System Purification Return...

  2. 75 FR 3682 - Revisions to Rules Authorizing the Operation of Low Power Auxiliary Stations in the 698-806 MHz...

    Science.gov (United States)

    2010-01-22

    ... seeks comment on the adoption in its rules marketing and labeling requirements, including possible... microphones operating simultaneously, and only one or two vacant TV channels may be required for such users... ``white spaces'' proceeding are designed to ensure that there will be one or more TV channels available...

  3. Process for limiting the effects of operating faults in atomic power stations and plant to carry out the process

    International Nuclear Information System (INIS)

    Kudryavzev, B.K.; Svez, A.J.; Bulynin, V.D.; Butareev, B.A.; Kamsky, N.S.; Kosenko, V.P.; Kapitanov, A.M.; Basilov, V.A.

    1985-01-01

    The reactor plant operated with high temperature water surrounded with an airtight containment and with a multi-loop design includes a condensation device for the steam generated during faults. The condensation device contains an injector, cooling container and condensate collecting container. The injector has a supersonic nozzle, through which the steam/air mixture produced is introduced. (DG) [de

  4. The use of service limits for efficient operation of multi-station single-medium communication systems

    NARCIS (Netherlands)

    Borst, S.C.; Boxma, O.J.; Levy, H.

    1995-01-01

    Time limits are the major mechanisms used for controlling a large variety of multistation single-medium computer-communication systems like the FDDI network and the IEEE 802.4 Token Bus. The proper use of these mechanisms is still not understood and rules for efficient system operation are not

  5. 47 CFR 80.107 - Service of private coast stations and marine-utility stations.

    Science.gov (United States)

    2010-10-01

    ... 47 Telecommunication 5 2010-10-01 2010-10-01 false Service of private coast stations and marine...) SAFETY AND SPECIAL RADIO SERVICES STATIONS IN THE MARITIME SERVICES Operating Requirements and Procedures Operating Procedures-Land Stations § 80.107 Service of private coast stations and marine-utility stations. A...

  6. Final supplement to the final environmental statement related to operation of Three Mile Island Nuclear Station, Unit 2: (Docket No. 50-320)

    International Nuclear Information System (INIS)

    1976-12-01

    The proposed action is the continuation of construction permit CPPR-66 and the issuance of operating license to Metropolitan Edison Company, Jersey Central Power and Light Company, and the Pennsylvania Electric Company (the Applicants) for the operation of the Three Mile Island Nuclear Station, Unit 2, Docket No. 50-320, near Harrisburg in Dauphin County, Pennsylvania. The Three Mile Island Nuclear Station Unit Number 2 has a designed thermal rating of 2772 megawatts with a maximum electrical output of 959 megawatts. Two natural draft cooling towers are utilized for dissipating the waste heat from the closed cycle cooling system. Extension of TMINS-Bechtelsville 500 kV transmission line an additional 7.36 miles from Bechtelsville to Hosensack required acquisition of additional 175 foot wide right-of-way along an existing 150 foot wide 230 kV corridor. Construction of this line segment resulted in clearing of 21 acres of woodland, spanning over 134.5 acres of agricultural land and diverting of 0.4 acres from agriculture to use under tower bases. About 550 curies of radionuclides in liquid effluents (0.24 Ci/yr excluding tritium and 550 Ci/yr of tritium) will be released to the environment annually. Gaseous releases will be approximately 6700 Ci/yr of noble gases, 0.01 Ci/yr of iodine-131, 560 Ci/yr of tritium, 25 Ci/yr of argon-41, and 0.06 Ci/yr of particulates. No significant environmental impacts are anticipated from normal operational releases of radioactive materials. The calculated dose to the estimated year 1990 US population is less than 540 manrem/yr. This value is less than the natural fluctuation in the approximately 28,000,000 manrem/yr dose this population would receive from background radiation

  7. Operations of electric taxis to serve advance reservations by trip chaining: Sensitivity analysis on network size, customer demand and number of charging stations

    Directory of Open Access Journals (Sweden)

    Hao Wang

    2016-10-01

    Full Text Available This research investigated the performance of an Electric Taxi (ET fleet that catered solely for customers with advance reservations. In a previously related research, a customized Paired Pickup and Delivery Problem with Time Window and Charging Station (PPDPTWCS had been formulated to solve for the minimum number of taxis that would serve a fixed set of customer demand. The concept behind this fleet optimization was to chain multiple customer trips and trips to Charging Stations (CSs to form a route and assigned to a taxi driver. In this paper the sensitivity of the ET fleet’s operations with respect to network sizes, customer demand densities and number of CSs have been investigated. It also analyzed the market shares of the CSs and the occupancy of a CS over time. The results showed that, (1 the expansion of network size or the increase in customer demand density led to increase in fleet size, number of trips to the CSs and maximum occupancies at the CSs but these performance measures grew at different rates; (2 when the network size and number of CSs were fixed, an increase in customer demand density led to a better utilization of taxis in terms of more customers served per taxi and higher average revenue per taxi; (3 given the same network size and demand density, the ET fleet’s performance was relatively insensitive to the number of CSs; and (4 the usage of individual CS was affected by the number of CS and their locations; and (5 when all the ETs were fully charged at the beginning of the same shift hour, they visited the CSs in bunches when their batteries were about to run out. These findings contribute to a better understanding of the operations of the ET fleet and the CSs. They could be used for making better decisions in the planning of ET operations.

  8. Safety evaluation report related to the operation of Limerick Generating Station, Units 1 and 2, Docket nos. 50-352 and 50-353

    International Nuclear Information System (INIS)

    1989-08-01

    In August 1983 the staff of the Nuclear Regulatory commission issued its Safety Evaluation Report (NUREG-0991) regarding the application of the Philadelphia Electric Company (the licensee) for the licenses to operate the Limerick Generating Station, Units 1 and 2, located on a site in Montgomery and Chester Counties, Pennsylvania. Supplement 1 was issued in December 1983. Supplement 2 was issued in October 1984. Supplement 3 was issued in October 1984. Supplement 4 was issued in May 1985. Supplement 5 was issued in July 1985. Supplement 6 was issued in August 1985 and Supplement 7 was issued in April 1989. Supplement 7 addresses the major design differences between Units 1 and 2, the resolution of all issues that remained open when the Unit 1 full-power license was issued, the staff's assessment regarding the application by the licensee to operate Unit 2 and issues that require resolution before issuance of an operating license for Unit 2. Supplements 8 and 9 address further issues that require resolution prior to issuance of an operating license. 1 tab

  9. Fire Stations

    Data.gov (United States)

    Department of Homeland Security — Fire Stations in the United States Any location where fire fighters are stationed or based out of, or where equipment that such personnel use in carrying out their...

  10. Oconee Nuclear Station, Units 1, 2, and 3. Annual operating report for 1976, volume 1: nonradiological environmental surveillance report; II: summary of operations

    International Nuclear Information System (INIS)

    1977-01-01

    The non-radiological environmental surveillance program including thermal and chemical effluents, water quality, fish populations, benthos, fish impingement, gas-bubble disease, and plankton, fish larvae and fish egg entrainment is described. Information is also presented concerning operations, personnel radiation exposures, and fuel examinations

  11. Browns Ferry Nuclear Power Station, Units 1, 2, and 3. Annual operating report: January--December 1976

    International Nuclear Information System (INIS)

    1977-01-01

    Units 1 and 2 were down for the first half of the year caused by the fire of March 1975. Net electrical power generated by Unit 1 this year was 1,301,183 MWH with the generator on line 2,175.25 hrs. Unit 2 generated 1,567,170 MWH with the generator on line 2,548.73 hrs. Unit 3 began full power operation on November 20th and generated 1,416,891 MWH with the generator on line 2,058.20 hrs. Information is presented concerning operations, fuel performance, surveillance testing, containment leak testing, changes, power generation, shutdown and forced reductions, coolant chemistry, occupational radiation exposures, and maintenance

  12. H2moves.eu Scandinavia. ''Experience from operating a 70 MPa hydrogen refuelling station in Oslo''. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Sloth, M.

    2013-02-15

    As part of the H2MOVES Scandinavia project H2 Logic were to construct a large scale hydrogen refuelling station (HRS) in Oslo providing hydrogen for FCEV's from Daimler and Hyundai in the project. The effort has provided extensive results and lessons learned across the entire process from site selection, HRS design and manufacturing to the final installation and operation. An extensive site screening of more than 30 sites in Oslo was firstly conducted to identify the most optimal location for the HRS. A suitable site was identified at the research organisation SINTEF in Gaustad in the western part of Oslo. The location was strategically well located with regards to the other HRS's in the city ensuring good refuelling coverage in Oslo. The HRS was manufactured, installed and operated by H2 Logic based on the company's H2Station technology. The HRS provides 70MPa refuelling in accordance with the SAE J2601, and operation results have confirmed refuelling times consistently below four minutes for a full tank. The HRS includes onsite electrolysis production providing a 20kg/day base load supply, with potentially additional trucking-in of hydrogen up to a total capacity of 200kg/day. The installation of the HRS took in total 10 days, from arrival at site, until first refuelling was conducted. This included local inspection by third parties and authorities as well as several days of hydrogen production and compression to reach the necessary refuelling pressure. Before opening a refuelling recommendation process was successfully conducted by Daimler. The HRS opened on 21st November 2011 and has been operated for 13,5 months during the remainder project period (ending December 2012). The HRS is expected to continue operation beyond the project. Below are shown the major operation results from the HRS during the project: 1) 701 kg dispensed; 2) 313 refueling's conducted; 3) Average availability of 97% during first half of 2012; 4) 53% of all down

  13. Dresden Nuclear Power Station, Units 1, 2, and 3. Semiannual report on operating and maintenance, July--December 1974

    International Nuclear Information System (INIS)

    1975-01-01

    Unit 1 generated 388,882 MWH(e) and was on line 3111.2 hours, Unit 2 generated 1,204,106 MWH(e) and was on line 2013.4 hours, and Unit 3 generated 2,250,810 MWH(e) and was on line 3836 hours. Information is presented concerning operations, shutdowns, maintenance, changes, tests, and experiments for the three units. (U.S.)

  14. Safety Evaluation Report related to the operation of Nine Mile Point Nuclear Station, Unit No. 2 (Docket No. 50-410). Supplement No. 5

    International Nuclear Information System (INIS)

    1986-10-01

    This report supplements the Safety Evaluation Report (NUREG-1047, February 1985) for the application filed by Niagara Mohawk Power Corporation, as applicant and co-owner, for a license to operate Nine Mile Point Nuclear Station, Unit 2 (Docket No. 50-410). It has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located near Oswego, New York. Supplement 1 to the Safety Evaluation Report was published in June 1985 and contained the report from the Advisory Committee on Reactor Safeguards as well as the resolution of a number of outstanding issues from the Safety Evaluation Report. Supplement 2 was published in November 1985 and contained the resolution of a number of outstanding and confirmatory issues. Supplement 3 was published in July 1986 and contained the resolution of a number of outstanding and confirmatory items, one new confirmatory item, the evaluation of the Engineering Assurance Program, and the evaluation of a number of exemption requests. Supplement 4 was published in September 1986 and contained the resolution of a number of outstanding and confirmatory issues and the evaluation of a number of exemption requests. This report contains the resolution of a number of issues that have been resolved since Supplement 4 was issued. It also contains the evaluation of a number of requests for exemption from the applicant. This report also supports the issuance of the low-power license for Nine Mile Point Nuclear Station, Unit 2

  15. Tether applications for space station

    Science.gov (United States)

    Nobles, W.

    1986-01-01

    A wide variety of space station applications for tethers were reviewed. Many will affect the operation of the station itself while others are in the category of research or scientific platforms. One of the most expensive aspects of operating the space station will be the continuing shuttle traffic to transport logistic supplies and payloads to the space station. If a means can be found to use tethers to improve the efficiency of that transportation operation, it will increase the operating efficiency of the system and reduce the overall cost of the space station. The concept studied consists of using a tether to lower the shuttle from the space station. This results in a transfer of angular momentum and energy from the orbiter to the space station. The consequences of this transfer is studied and how beneficial use can be made of it.

  16. Design and development of improved ballscrew and control circuit for reactivity mechanisms of 220 MWe PHWR operating stations

    International Nuclear Information System (INIS)

    Jain, A.K.; Rama Mohan, N.; Mathew, Jimmy; Mathur, M.K.; Roy, S.; Ingle, V.J.; Ghoshal, B.; Ashok Kumar, B.; Patil, D.C.; Dwivedi, K.P.; Bhambra, H.S.

    2006-01-01

    There has been persistent failure of Ballscrews used for Reactivity Mechanism in standardised 220 MWe PHWR units. The detailed review of failures indicated that on one hand the number of demands for operation of Absorber Rod and Regulating Rod had increased due to use of digital circuit in the drive control system as compared analog circuits used earlier. On the other hand, the existing design of ballscrew had some inherent weaknesses to withstand the loads generated during starting and stopping of the regulating rods. To solve these problems two-pronged approach was adopted. The control problem was traced to overshooting of the servomotor of Absorber Rod and Regulating Rod to the full speed at the time of starting and thereafter, settling to the required speed. This sudden overshooting produces a jerk in the drive mechanism. A modified circuit has been evolved to solve this problem. Also, Changing the dead band and gain of control circuits have reduced the number of rod movements. A 'new design' of Ballscrew assembly was finalised by NPCIL with a view to withstand the severe loads generated during starting and stopping of the regulating rods and to achieve enhanced service life under water-lubrication condition. Based on this design, prototype assemblies were successfully manufactured by two Indian manufacturers. The design was cleared for manufacturing of the bulk production of Ballscrew assemblies after evaluation of its performance during rigorous 'Acceptance Testing'. Two ballscrews of new design were installed in the KGS-1 reactor and are operating since July 2005. This paper covers operational feedback including ballscrew failures in various units, Design/Development of Modified Reactivity Mechanism Ballscrews and Control Circuit based on analysis of underlying causes of failures and feedback on performance of new design. (author)

  17. Review and evaluation of Transamerica Delaval, Inc., diesel engine reliability and operability: Grand Gulf Nuclear Station Unit 1

    International Nuclear Information System (INIS)

    1984-07-01

    PNL and its consultants conclude that the TDI diesel engines at the GGNS have the needed operability and reliability to fulfill their intended (auxiliary) emergency power function for the first refueling cycle. This conclusion is reached with a number of understandings regarding limits to the engine requirements, NRC concurrence with MP and L findings/conclusions regarding items to be supplied to NRC, limitations on the engine Brake Mean Effective Pressure (BMEP), and MP and L's implementation of the modifications to their proposed surveillance and maintenance program

  18. Selective analysis of power plant operation on the Hudson River with emphasis on the Bowline Point Generating Station. Volume 2

    International Nuclear Information System (INIS)

    Barnthouse, L.W.; Cannon, J.B.; Christensen, S.G.

    1977-07-01

    Because of the location of the Bowline, Roseton, and Indian Point power generating facilities in the low-salinity zone of the Hudson estuary, operation of these plants with the present once-through cooling systems will adversely influence the fish populations that use the area for spawning and initial periods of growth and development. Recruitment rates and standing crops of several fish species may be lowered in response to the increased mortality caused by entrainment of nonscreenable eggs and larvae and by impingement of screenable young of the year. Entrainment and impingement data are particularly relevant for assessing which fish species have the greatest potential for being adversely affected by operation of Bowline, Roseton, and Indian Point with once-through cooling. These data from each of these three plants suggest that the six species that merit the greatest consideration are striped bass, white perch, tomcod, alewife, blueback herring, and bay anchovy. Two points of view are available for assessing the relative importance of the fish species in the Hudson River. From the fisheries point of view, the only two species of major importance are striped bass and shad. From the fish-community and ecosystem point of view, the dominant species, as determined by seasonal and regional standing crops (in numbers and biomass per hectare), are the six species most commonly entrained and impinged, namely, striped bass, white perch, tomcod, alewife, blueback herring, and anchovy

  19. Safety evaluation report related to the operation of Catawba Nuclear Station, Units 1 and 2. Docket Nos. 50-413 and 50-414. Suppl. 1

    International Nuclear Information System (INIS)

    1983-04-01

    This reort supplements the Safety Evaluation Report (NUREG-0954) issued in February 1983 by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission with respect to the application filed by Duke Power Company, North Carolina Municipal Power Agency Number 1, North Carolina Membership Corporation, and Saluda River Electric Cooperative, Inc. as applicants and owners, for licenses to operate the Catawba Nuclear Station, Units 1 and 2 (Docket Nos. 50-413 and 50-414, respectively). The facility is located in York County, South Carolina, approximately 9.6 km (6 mi) north of Rock Hill and adjacent to Lake Wylie. This supplement provides more recent information regarding resolution or updating of some of the open and confirmatory items and license conditions identified in the Safety Evaluation Report, and discusses the recommendations of the Advisory Committee on Reactor Safeguards in its report dated March 15, 1983

  20. Safety Evaluation Report related to the operation of Millstone Nuclear Power Station, Unit No. 3 (Docket No. 50-423). Supplement No. 3

    International Nuclear Information System (INIS)

    1985-11-01

    This report supplements the Safety Evaluation Report (NUREG-1031) issued in July 1984, Supplement 1 issued in March 1985, and Supplement 2 issued in September 1985 by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission with respect to the application filed by Northeast Nuclear Energy Company (applicant and agent for the owners) for a license to operate Millstone Nuclear Power Station, Unit No. 3 (Docket 50-423). The facility is located in the Town of Waterford, New London County, Connecticut, on the north shore of Long Island Sound. This supplement provides more recent information regarding resolution or updating of some of the open and confirmatory items and license conditions identified in the Safety Evaluation Report

  1. Safety evaluation report related to the operation of Catawba Nuclear Station, Units 1 and 2 (Docket Nos. 50-413 and 50-414)

    International Nuclear Information System (INIS)

    1984-07-01

    The report supplements the Safety Evaluation Report (NUREG-0954) issued in February 1983 by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission with respect to the application filed by Duke Power Company, North Carolina Municipal Power Agency Number 1, North Carolina Membership Corporation, and Saluda River Electric Cooperative, Inc. as applicants and owners, for licenses to operate the Catawba Nuclear Station, Units 1 and 2 (Docket Nos. 50-413 and 50-414, respectively). The facility is located in York County, South Carolina, approximately 9.6 km (6 mi) north of Rock Hill and adjacent to Lake Wylie. This supplement provides additional information supporting the license for fuel loading and precriticality testing for Unit 1

  2. Variation of radioactivity in the environmental media and dose evaluation in Suzhou city after normal operation of Qinshan Nuclear Power Station condition

    International Nuclear Information System (INIS)

    Fu Rongchu; Liu Li

    2002-01-01

    Objective: To study the radioactive monitoring in environmental media of Suzhou City when Qinshan Nuclear Power Station was in normal operational condition (from 1992-2001). Methods: The radiochemical method was used for monitoring the radioactivity level in air, soil and food. Results: The total radioactivity, concentrations of 134 I and 134,137 Cs in environmental media was far lower than the limit values specified by the national standard GB. Conclusion: The radioactivity level in Suzhou City is at the natural background level. The individual annual average effective dose for adults in that period caused by ingestion 134,137 Cs in food is 4.41 x 10 -4 mSv/a

  3. Automatic Weather Station (AWS Program operated by the University of Wisconsin-Madison during the 2012-2013 field season: Challenges and Successes

    Directory of Open Access Journals (Sweden)

    Matthew A. Lazzara

    2015-03-01

    Full Text Available This report reviews 2012-2013 field season activities of the University of Wisconsin-Madison's Antarctic Automatic Weather Station (AWS program, summarizes the science that these sites are supporting, and outlines the factors that impact the number of AWS sites serviced in any given field season. The 2012-2013 austral summer season was unusual in the AWS network history. Challenges encountered include, but are not limited to, warmer than normal conditions in the Ross Island area impacting airfield operations, changes to logistical procedures, and competition for shared resources. A flexible work plan provides the best means for taking on these challenges while maximizing AWS servicing efforts under restricted conditions and meeting the need for routine servicing that maintaining an autonomous observing network demands.

  4. Safety evaluation report related to the operation of Catawba Nuclear Station, Units 1 and 2 (Docket Nos. 50-413 and 50-414)

    International Nuclear Information System (INIS)

    1984-12-01

    This report supplements the Safety Evaluation Report (NUREG-0954) issued in February 1983 by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission with respect to the application filed by Duke Power Company, North Carolina Municipal Power Agency Number 1, North Carolina Membership Corporation, and Saluda River Electric Cooperative, Inc., as applicants and owners, for licenses to operate the Catawba Nuclear Station, Units 1 and 2 (Docket Nos. 50-413 and 50-414, respectively). The facility is located in York County, South Carolina, approximately 9.6 km (6 mi) north of Rock Hill and adjacent to Lake Wylie. This supplement provides additional information supporting the license for initial criticality and power ascension to full-power opertion for Unit 1

  5. Safety Evaluation Report related to the operation of Grand Gulf Nuclear Station, Units 1 and 2 (Docket Nos. 50-416 and 50-417)

    International Nuclear Information System (INIS)

    1984-10-01

    This report supplements the Safety Evaluation Report (NUREG-0831) issued in September 1981 by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission with respect to the application filed by Mississippi Power and Light (MP and L) Company, Middle South Energy, Inc., and South Mississippi Electric Power Association as applicants and owners, for licenses to operate the Grand Gulf Nuclear Station, Units 1 and 2 (Docket Nos. 50-416 and 50-417, respectively). The facility is located on the east bank of the Mississippi River near Port Gibson in Claiborne County, Mississippi. This supplement provides information on the NRC staff's evaluation of requests for exemptions to NRC regulations pursuant to the Commission's direction in CLI-84-19, dated October 25, 1984

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

    International Nuclear Information System (INIS)

    1984-07-01

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

  7. Safety evaluation report related to the operation of Catawba Nuclear Station, Units 1 and 2 (Docket Nos. 50-413 and 50-414). Supplement 2

    International Nuclear Information System (INIS)

    1984-06-01

    This report supplements the Safety Evaluation Report (NUREG-0954) and Supplement 1 with respect to the application filed by Duke Power Company, North Carolina Municipal Power Agency Number 1, North Carolina Membership Corporation, and Saluda River Electric Cooperative, Inc., as applicants and owners, for licenses to operate the Catawba Nuclear Station, Units 1 and 2 (Docket Nos., 50-413 and 50-414, respectively). The facility is located in York County, South Carolina, approximately 9.6 km (6 mi) north of Rock Hill and adjacent to Lake Wylie. This supplement provides more recent information regarding resolution or updating of some of the open and confirmatory issues and license conditions identified in the Safety Evaluation Report

  8. Safety Evaluation Report related to the operation of Braidwood Station, Units 1 and 2 (Docket Nos. STN 50-456 and STN 50-457)

    International Nuclear Information System (INIS)

    1988-06-01

    In November 1983, the staff of the Nuclear Regulatory Commission issued its Safety Evaluation Report (NUREG-1002) regarding the application filed by the Commonwealth Edison Company, as applicant and owner, for a license to operate Braidwood Station, Units 1 and 2 (Docket Nos. 50-456 and 50-457). The first supplement to NUREG-1002 was issued in September 1986; the second supplement was issued in October 1986; the third supplement was issued in May 1987; the fourth supplement was issued in July 1987 in support of the full power license for Unit 1; the fifth supplement was issued in December 1987 in support of the low power license for Unit 2. This sixth supplement to NUREG-1002 is in support of the full-power license for Unit 2 and provides the status of items that remained unresolved at the time Supplement 5 was published. The facility is located in Reed Township, Will County, Illinois

  9. Safety Evaluation report related to the operation of Braidwood Station, Units 1 and 2 (Docket Nos. STN 50-456 and STN 50-457)

    International Nuclear Information System (INIS)

    1987-07-01

    In November 1983, the staff of the Nuclear Regulatory Commission issued its Safety Evaluation Report (NUREG-1002) regarding the application filed by the Commonwealth Edison Company, as applicant and owner, for a license to operate Braidwood Station, Units 1 and 2 (Docket Nos. 50-456 and 50-457). The first supplement to NUREG-1002 was issued in September 1986; the second supplement to NUREG-1002 was issued in October 1986; the third supplement to NUREG-1002 was issued in May 1987. This fourth supplement to NUREG-1002 reports the status of certain items that remained unresolved at the time Supplement 3 was published. The facility is located in Reed Township, Will County, Illinois

  10. Safety Evaluation Report related to the operation of Limerick Generating Station, Units 1 and 2 (Docket Nos. 50-352 and 50-353). Supplement No. 4

    International Nuclear Information System (INIS)

    1985-05-01

    In August 1983 the staff of the Nuclear Regulatory Commission issued its Safety Evaluation Report (NUREG-0991) regarding the application of the Philadelphia Electric Company (the applicant) for licenses to operate the Limerick Generating Station, Units 1 and 2 located on a site in Montgomery and Chester Counties, Pennsylvania. A license (NPF-27) for the operation of Limerick Unit 1 was issued on October 26, 1984. The license, which was restricted to a five percent power level, contained conditions which required resolution prior to proceeding beyond the five percent power level. This Supplement 4 to the SER addresses some of those technical issues and their associated license conditions which require resolution prior to proceeding beyond the five percent power level. The remaining issues to be addressed prior to proceeding beyond the five percent power level will be addressed in a later supplement to this report. This Supplement 4 to the SER also contains the comments made by the Advisory Committee on Reactor Safeguards in its report dated November 6, 1984, regarding full power operation of Limerick Unit 1

  11. An examination of qualitative plant modelling as a basis for knowledge-based operator aids in nuclear power stations

    International Nuclear Information System (INIS)

    Herbert, M.; Williams, G.

    1986-01-01

    New qualitative techniques for representing the behaviour of physical systems have recently been developed. These allow a qualitative representation to be formally derived from a quantitative plant model. One such technique, Incremental Qualitative Analysis, is based on manipulating qualitative differential equations, called confluences, using sign algebra. This is described and its potential for reducing the amount of information presented to the reactor operator is discussed. In order to illustrate the technique, a specific example relating to the influence of failures associated with a pressurized water reactor pressuriser is presented. It is shown that, although failures cannot necessarily be diagnosed unambiguously, the number of possible failures inferred is low. Techniques for discriminating between these possible failures are discussed. (author)

  12. Hybrid radiation background monitoring in operational control and forecasting of environmental contamination by nuclear power station discharges

    International Nuclear Information System (INIS)

    Ermeev, I.S.; Eremenko, V.A.; Makarov, Y.A.; Matueev, V.V.; Zhernov, V.S.

    1986-01-01

    Rapid developments in nuclear power have stimulated research on monitoring and forecasting environmental radiation pollution (ERP), and in particular the amounts, compositions, and distributions of radionuclides in the environment. A conceptual model is presented for hybrid environmental radiation pollution monitoring. When there is an emergency, the model operates in a fashion most closely corresponding to the actual meteorological conditions, and the ERP data given by the model enable one to distinguish changes due to the man-made component from random fluctuations in the natural background. The measurement system in general includes mobile and stationary data-acquisition facilities linked by wire or radio to the central point. The system also accumulates and stores data on the radiation environment, which are edited on the basis of radioactive, chemical, and other transformations. The purpose of hybrid monitoring is ultimately to analyze trends in order to detect elevated discharges and thus to output data to the regional monitoring system

  13. Space Station Engineering Design Issues

    Science.gov (United States)

    Mcruer, Duane T.; Boehm, Barry W.; Debra, Daniel B.; Green, C. Cordell; Henry, Richard C.; Maycock, Paul D.; Mcelroy, John H.; Pierce, Chester M.; Stafford, Thomas P.; Young, Laurence R.

    1989-01-01

    Space Station Freedom topics addressed include: general design issues; issues related to utilization and operations; issues related to systems requirements and design; and management issues relevant to design.

  14. Web Design for Space Operations: An Overview of the Challenges and New Technologies Used in Developing and Operating Web-Based Applications in Real-Time Operational Support Onboard the International Space Station, in Astronaut Mission Planning and Mission Control Operations

    Science.gov (United States)

    Khan, Ahmed

    2010-01-01

    The International Space Station (ISS) Operations Planning Team, Mission Control Centre and Mission Automation Support Network (MAS) have all evolved over the years to use commercial web-based technologies to create a configurable electronic infrastructure to manage the complex network of real-time planning, crew scheduling, resource and activity management as well as onboard document and procedure management required to co-ordinate ISS assembly, daily operations and mission support. While these Web technologies are classified as non-critical in nature, their use is part of an essential backbone of daily operations on the ISS and allows the crew to operate the ISS as a functioning science laboratory. The rapid evolution of the internet from 1998 (when ISS assembly began) to today, along with the nature of continuous manned operations in space, have presented a unique challenge in terms of software engineering and system development. In addition, the use of a wide array of competing internet technologies (including commercial technologies such as .NET and JAVA ) and the special requirements of having to support this network, both nationally among various control centres for International Partners (IPs), as well as onboard the station itself, have created special challenges for the MCC Web Tools Development Team, software engineers and flight controllers, who implement and maintain this system. This paper presents an overview of some of these operational challenges, and the evolving nature of the solutions and the future use of COTS based rich internet technologies in manned space flight operations. In particular this paper will focus on the use of Microsoft.s .NET API to develop Web-Based Operational tools, the use of XML based service oriented architectures (SOA) that needed to be customized to support Mission operations, the maintenance of a Microsoft IIS web server onboard the ISS, The OpsLan, functional-oriented Web Design with AJAX

  15. Aerosol absorption coefficient and Equivalent Black Carbon by parallel operation of AE31 and AE33 aethalometers at the Zeppelin station, Ny Ålesund, Svalbard

    Science.gov (United States)

    Eleftheriadis, Konstantinos; Kalogridis, Athina-Cerise; Vratolis, Sterios; Fiebig, Markus

    2016-04-01

    Light absorbing carbon in atmospheric aerosol plays a critical role in radiative forcing and climate change. Despite the long term measurements across the Arctic, comparing data obtained by a variety of methods across stations requires caution. A method for extracting the aerosol absorption coefficient from data obtained over the decades by filter based instrument is still under development. An IASOA Aerosol working group has been initiated to address this and other cross-site aerosol comparison opportunities. Continuous ambient measurements of EBC/light attenuation by means of a Magee Sci. AE-31 aethalometer operating at the Zeppelinfjellet station (474 m asl; 78°54'N, 11°53'E), Ny Ålesund, Svalbard, have been available since 2001 (Eleftheriadis et al, 2009), while a new aethalometer model (AE33, Drinovec et al, 2014) has been installed to operate in parallel from the same inlet since June 2015. Measurements are recorded by a Labview routine collecting all available parameters reported by the two instrument via RS232 protocol. Data are reported at 1 and 10 minute intervals as averages for EBC (μg m-3) and aerosol absorption coefficients (Mm-1) by means of routine designed to report Near Real Time NRT data at the EBAS WDCA database (ebas.nilu.no) Results for the first 6 month period are reported here in an attempt to evaluate comparative performance of the two instruments in terms of their response with respect to the variable aerosol load of light absorbing carbon during the warm and cold seasons found in the high arctic. The application of available conversion schemes for obtaining the absorption coefficient by the two instruments is found to demonstrate a marked difference in their output. During clean periods of low aerosol load (EBC origin was also conducted. Drinovec, L., Močnik, G., Zotter, P., Prévôt, A. S. H., Ruckstuhl, C., Coz, E., Rupakheti, M., Sciare, J., Müller, T., Wiedensohler, A., and Hansen, A. D. A. The "dual-spot" Aethalometer: an

  16. Mobile environmental radiation monitoring station

    International Nuclear Information System (INIS)

    Assido, H.; Shemesh, Y.; Mazor, T.; Tal, N.; Barak, D.

    1997-01-01

    A mobile environmental radiation monitoring station has been developed and established for the Israeli Ministry of Environment. The radiation monitoring station is ready for immediate placing in any required location, or can be operated from a vehicle. The station collects data Tom the detector and transfers it via cellular communication network to a Computerized Control Center for data storage, processing, and display . The mobile station is fully controlled from the. Routinely, the mobile station responses to the data request accumulated since the last communication session. In case of fault or alarm condition in the mobile station, a local claim is activated and immediately initiates communication with the via cellular communication network. (authors)

  17. Validation of a Numerical Model for the Prediction of the Annoyance Condition at the Operator Station of Construction Machines

    Directory of Open Access Journals (Sweden)

    Eleonora Carletti

    2016-11-01

    Full Text Available It is well-known that the reduction of noise levels is not strictly linked to the reduction of noise annoyance. Even earthmoving machine manufacturers are facing the problem of customer complaints concerning the noise quality of their machines with increasing frequency. Unfortunately, all the studies geared to the understanding of the relationship between multidimensional characteristics of noise signals and the auditory perception of annoyance require repeated sessions of jury listening tests, which are time-consuming. In this respect, an annoyance prediction model was developed for compact loaders to assess the annoyance sensation perceived by operators at their workplaces without repeating the full sound quality assessment but using objective parameters only. This paper aims at verifying the feasibility of the developed annoyance prediction model when applied to other kinds of earthmoving machines. For this purpose, an experimental investigation was performed on five earthmoving machines, different in type, dimension, and engine mechanical power, and the annoyance predicted by the numerical model was compared to the annoyance given by subjective listening tests. The results were evaluated by means of the squared value of the correlation coefficient, R2, and they confirm the possible applicability of the model to other kinds of machines.

  18. Amtrak Stations

    Data.gov (United States)

    Department of Homeland Security — Updated database of the Federal Railroad Administration's (FRA) Amtrak Station database. This database is a geographic data set containing Amtrak intercity railroad...

  19. Safety Evaluation Report related to the operation of Limerick Generating Station, Units 1 and 2 (Docket Nos. 50-352 and 50-353). Supplement No. 5

    International Nuclear Information System (INIS)

    1985-07-01

    In August 1983 the NRC issues its Safety Evaluation Report regarding the application for licenses to operate the Limerick Generating Station, Units 1 and 2 located on a site in Montgomery and Chester Counties, Pennsylvania. Supplement 1 was issued in December 1983 and addressed several outstanding issues. SSER 1 also contains the comments made by the Advisory Committee on Reactor Safeguards in its interim report dated October 18, 1983. Supplement 2 was issued in October 1984. Supplement 3 was issued in October 1984 and addressed the remaining issues that required resolution before issuance of the operating licence for Unit 1. On October 26, 1984 a license (NPF-27) for Unit 1 was issued which was restricted to a five percent power level and contained conditions which required resolution prior to proceeding beyond the five percent power level. Supplement 4 issued in May 1985 addressed some of the technical issues and their associated license conditions, which required resolution prior to proceeding beyond the five percent power level. SSER 4 also contained the comments made by the Advisory Committee on Reactor Safeguards in its report dated November 6, 1984. This Supplement 5 to the SER addresses further issues that require resolution prior to proceeding beyond the five percent power level

  20. Operation planning for a pondage power station chain by means of linear programming and genetic optimisation; Einsatzplanung fuer eine Flusskraftwerkskette im Schwellbetrieb mittels LP und genetischer Optimierung

    Energy Technology Data Exchange (ETDEWEB)

    Mueller, H.; Huelsemann, M.

    1997-12-31

    This paper presents a system package which serves as a simulation and optimisation tool for daily operation planning for a hydroelectric cascade. The purpose of the planning is to maximise (the differentially weighted) production of electrical energy given a certain set of specifications and secondary conditions. Optimal operation management is achieved using a two-stage approach: first pre-optimisation by means of linear programming, followed by detail optimisation using a Genetic Algorithm based on a non-linear, dynamic model of the power station and reservoir chain. [Deutsch] Im Beitrag wird ein Systempaket als Simulations- und Optimierungswerkzeug zur taeglichen Betriebsplanung einer Wasserkraftwerkskaskade vorgestellt. Ziel der Wasserbewirtschaftung ist es, unter den gegebenen Vorgaben und Randbedingungen die (bewertete) Erzeugung elektrischer Energie zu maximieren. Das optimale Fahrplanmanagement wird durch einen zweistufigen Loesungsansatz realisiert: Mit einer Vor-Optimierung mittels Linearer Programmierung (LP), gefolgt von einer detaillierten Optimierung mit einem Genetischen Algorithmus, der auf ein nichtlineares, dynamisches Simulationsmodell fuer die Kette aus Kraftwerken und Stauraeumen zugreift. (orig./RHM)

  1. A Sounding-based Severe Weather Tool to Support Daily Operations at Kennedy Space Center and Cape Canaveral Air Force Station

    Science.gov (United States)

    Bauman, William H.; Roeder, William P.

    2014-01-01

    People and property at Kennedy Space Center (KSC) and Cape Canaveral Air Force Station (CCAFS) are at risk when severe weather occurs. Strong winds, hail and tornadoes can injure individuals and cause costly damage to structures if not properly protected. NASA's Launch Services Program and Ground Systems Development and Operations Program and other KSC programs use the daily and weekly severe weather forecasts issued by the 45th Weather Squadron (45 WS) to determine if they need to limit an activity such as working on gantries, or protect property such as a vehicle on a pad. The 45 WS requested the Applied Meteorology Unit (AMU) develop a warm season (May-September) severe weather tool for use in the Meteorological Interactive Data Display System (MIDDS) based on the late morning, 1500 UTC (1100 local time), CCAFS (XMR) sounding. The 45 WS frequently makes decisions to issue a severe weather watch and other severe weather warning support products to NASA and the 45th Space Wing in the late morning, after the 1500 UTC sounding. The results of this work indicate that certain stability indices based on the late morning XMR soundings can depict differences between days with reported severe weather and days with no reported severe weather. The AMU determined a frequency of reported severe weather for the stability indices and implemented an operational tool in MIDDS.

  2. Tobruk power station

    Energy Technology Data Exchange (ETDEWEB)

    Boergardts, B

    1978-01-01

    In February of 1975, the Electricity Corporation Benghazi (ECB) awarded a contract for the construction of a turnkey power station and seawater desalination plant in Tobruk, Libya to a consortium under the leadership of BBC Mannheim. This power station has an output of 129 MW and supplies about 24,000 m/sup 3/ of drinking water daily. It went into operation in 1977, two and a half years after the contract was awarded.

  3. Space Station galley design

    Science.gov (United States)

    Trabanino, Rudy; Murphy, George L.; Yakut, M. M.

    1986-01-01

    An Advanced Food Hardware System galley for the initial operating capability (IOC) Space Station is discussed. Space Station will employ food hardware items that have never been flown in space, such as a dishwasher, microwave oven, blender/mixer, bulk food and beverage dispensers, automated food inventory management, a trash compactor, and an advanced technology refrigerator/freezer. These new technologies and designs are described and the trades, design, development, and testing associated with each are summarized.

  4. National Seismic Station

    International Nuclear Information System (INIS)

    Stokes, P.A.

    1982-06-01

    The National Seismic Station was developed to meet the needs of regional or worldwide seismic monitoring of underground nuclear explosions to verify compliance with a nuclear test ban treaty. The Station acquires broadband seismic data and transmits it via satellite to a data center. It is capable of unattended operation for periods of at least a year, and will detect any tampering that could result in the transmission of unauthentic seismic data

  5. Draft Environmental Statement related to the operation of Seabrook Station, Units 1 and 2. Docket Nos. 50-443 and 50-444, Public Service Company of New Hampshire, et al

    International Nuclear Information System (INIS)

    1982-05-01

    This Draft Environmental Statement contains the second assessment of the environmental impact associated with the operation of the Seabrook Station, Units 1 and 2 pursuant to the National Environmental Policy Act of 1969 (NEPA) and 10 CFR 51, as amended, of the NRC regulations. This statement examines: the effected environment, environmental consequences and mitigating actions, and environmental and economic benefits and costs. Land use and terrestrial and aquatic-ecological impacts will be small. Operational impacts to historic and archeological sites will be negligible. The effects of routine operations, energy transmission, and periodic maintenance of rights-of-way and transmission facilities should not jeopardize any populations of endangered or threatened species. No significant impacts are anticipated from normal operational releases of radioactivity. The risk associated with accidental radiation exposure is very low. The net socioeconomic effects of the project will be beneficial. The action called for is the issuance of an operating license for Seabrook Station, Units 1 and 2

  6. 47 CFR 73.6018 - Digital Class A TV station protection of DTV stations.

    Science.gov (United States)

    2010-10-01

    ... 47 Telecommunication 4 2010-10-01 2010-10-01 false Digital Class A TV station protection of DTV... TV station protection of DTV stations. Digital Class A TV stations must protect the DTV service that... application for digital operation of an existing Class A TV station or to change the facilities of a digital...

  7. Operation of Grand Gulf Nuclear Station, Units 1 and 2, Dockets Nos. 50-416 and 50-417: Mississippi Power and Light Company, Middle South Energy, Inc., South Mississippi Electric Power Association. Final environmental statement

    International Nuclear Information System (INIS)

    1981-09-01

    The information in this Final Environmental Statement is the second assessment of the environmental impacts associated with the construction and operation of the Grand Gulf Nuclear Station, Units 1 and 2, located on the Mississippi River in Claiborne County, Mississippi. The Draft Environmental Statement was issued in May 1981. The first assessment was the Final Environmental Statement related to construction, which was issued in August 1973 prior to issuance of the Grand Gulf Nuclear Station construction permits. In September 1981 Grand Gulf Unit 1 was 92% complete and Unit 2 was 22% complete. Fuel loading for Unit 1 is scheduled for December 1981. The present assessment is the result of the NRC staff review of the activities associated with the proposed operation of the Station, and includes the staff responses to comments on the Draft Environmental Statement

  8. Safety evaluation report related to the operation of Comanche Peak Steam Electric Station, Units 1 and 2: Docket Nos. 50-445 and 50-446

    International Nuclear Information System (INIS)

    1988-07-01

    Supplement 15 to the Safety Evaluation Report related to the operation of the Comanche Peak Steam Electric Station (CPSES), Units 1 and 2 (NUREG-0797), has been prepared by the Office of Special Projects of the US Nuclear Regulatory Commission (NRC). The facility is located in Somervell County, Texas, approximately 40 miles southwest of Fort Worth, Texas. This supplement presents the staff's evaluation of the applicant's Corrective Action Program (CAP) related to the design of cable trays and cable tray hangers. The scope and methodologies for the CAP workscope as summarized in Revision O to the cable tray and cable tray hanger project status report and as detailed in related documents referenced in this evaluation were developed to resolve various design issues raised by the Atomic Safety and Licensing Board (ASLB) the intervenor, Citizens Association for Sound Energy (CASE); the Comanche Peak Response Team (CPRT); CYGNA Energy Services (CYGNA); and the NRC staff. The NRC staff concludes that the CAP workscope for cable trays and cable tray hangers provides a comprehensive program for resolving the associated technical concerns identified by the ASLB, CASE, CPRT, CYGNA, and the NRC staff and its implementation ensures that the design of cable trays and cable tray hangers at CPSES satisfies the applicable requirements of 10 CFR Part 50

  9. First retrieval of hourly atmospheric radionuclides just after the Fukushima accident by analyzing filter-tapes of operational air pollution monitoring stations.

    Science.gov (United States)

    Tsuruta, Haruo; Oura, Yasuji; Ebihara, Mitsuru; Ohara, Toshimasa; Nakajima, Teruyuki

    2014-10-22

    No observed data have been found in the Fukushima Prefecture (FP) for the time-series of atmospheric radionuclides concentrations just after the Fukushima Daiichi Nuclear Power Plant (FD1NPP) accident. Accordingly, current estimates of internal radiation doses from inhalation, and atmospheric radionuclide concentrations by atmospheric transport models are highly uncertain. Here, we present a new method for retrieving the hourly atmospheric (137)Cs concentrations by measuring the radioactivity of suspended particulate matter (SPM) collected on filter tapes in SPM monitors which were operated even after the accident. This new dataset focused on the period of March 12-23, 2011 just after the accident, when massive radioactive materials were released from the FD1NPP to the atmosphere. Overall, 40 sites of the more than 400 sites in the air quality monitoring stations in eastern Japan were studied. For the first time, we show the spatio-temporal variation of atmospheric (137)Cs concentrations in the FP and the Tokyo Metropolitan Area (TMA) located more than 170 km southwest of the FD1NPP. The comprehensive dataset revealed how the polluted air masses were transported to the FP and TMA, and can be used to re-evaluate internal exposure, time-series radionuclides release rates, and atmospheric transport models.

  10. Safety evaluation report related to the operation of Comanche Peak Steam Electric Station, Units 1 and 2 (Docket Nos. 50-445 and 50-446)

    International Nuclear Information System (INIS)

    1988-11-01

    Supplement 18 to the Safety Evaluation Report related to the operation of the Comanche Peak Steam Electric Station (CPSES), Units 1 and 2 (NUREG-0797), has been prepared by the Office of Special Projects of the US Nuclear Regulatory Commission (NRC). The facility is located in Somervell County, Texas, approximately 40 miles southwest of Fort Worth, Texas. This supplement presents the staff's evaluation of the applicant's Corrective Action Program (CAP) related to the structural design of the heating, ventilation, and air conditioning (HVAC) systems. The scope and methodologies for the CAP workscope as summarized in Revision 0 to the HVAC project status report and as detailed in related documents referenced in this evaluation were developed to resolve the technical concerns identified in the HVAC area. The NRC staff concludes that the CAP workscope for the HVAC structural design provides a comprehensive program for resolving the associated technical concerns and its implementation ensures that the structural design of the HVAC systems at CPSES satisfies the applicable requirements of 10 CFR Part 50. 32 refs

  11. A program of hydrological studies of the Zarnowieckie lake and the prognosis of the changes resulting from the operation of atomic and pump-storage power stations

    International Nuclear Information System (INIS)

    Zawisza, J.; Kajak, Z.; Pieczynska, E.

    1975-01-01

    Against the background of long-term program of the effect of heat release to the Zarnowieckie Lake and changes in its hydrodynamics the scope of preliminary hydrobiological studies began in 1974 is presented in the paper. The studies included: physical-and-chemical conditions forming the background to the biological processes, the production and destruction processes in pelagial, ground fauna group, and characteristics of some littoral organism groups. The fish group has been given special consideration by making an attempt to evaluate the parameters of the dynamics of the dominant populations as well as spatial distribution (echo depth finder). The status quo description is to be used as a frame of reference to estimate the results of changes in the environment caused by the operation of the atomic and pump-storage power stations. Preliminary hypotheses have been formulated in this connection. Attention has been drawn to the possible solution to ameliorate the negative effects by one-directional and intensive fish planning of the lake. (author)

  12. Safety Evaluation Report related to the operation of Comanche Peak Steam Electric Station, Units 1 and 2 (Docket Nos. 50-445 and 50-446)

    International Nuclear Information System (INIS)

    1990-01-01

    Supplement 22 to the Safety Evaluation Report related to the operation of the Comanche Peak Steam Electric Station, Units 1 and 2 (NUREG-0797), has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located in Somervell County, Texas, approximately 40 miles southwest of Fort Worth, Texas. This supplement reports the status of certain issues that had not been resolved at the time of publication of the Safety Evaluation Report and Supplements 1, 2, 3, 4, 6, 12, and 21 to that report. This supplement also includes the evaluations for licensing items resolved since Supplement 21 was issued. Supplement 5 has been cancelled. Supplements 7 through 11 were limited to the staff evaluation of allegations investigated by the NRC Technical Review Team. Supplement 13 presented the staff's evaluation of the Comanche Peak Response Team (CPRT) Program Plan, which was formulated by the applicant to resolve various construction and design issues raised by sources external to the applicant. Supplements 14 through 20 presented the staff's evaluation of the applicant's Corrective Action Program and CPRT activities. Items identified in Supplements 7, 8, 9, 10, 11, 13, 14, and 15 through 20 are not included in this supplement, except to the extent that they affect the applicant's Final Safety Analysis Report. 154 refs., 24 figs., 8 tabs

  13. Hydrologic investigations on construction and operation of small-scale hydropower stations in the southern Black Forest; Gewaesseroekologische Untersuchungen zum Bau und Betrieb einer Kleinwasserkraftanlage im Suedschwarzwald

    Energy Technology Data Exchange (ETDEWEB)

    Kerle, F.; Giesecke, J. [Stuttgart Univ. (Germany). Inst. fuer Wasserbau

    2003-07-01

    How far do ecologically optimized small hydropower systems (diversion type) still alter a river ecosystem? How can negative impacts be mitigated and compensated? To get more insight into these strategic important questions, a long-term case study (10 years) at the river Elz, Black Forest, has been implemented in 1999. The pre- and post-project analysis of the new 320-kW hydropower station (Wasserkraft Volk AG) uses methods of hydromorphological and biological monitoring in combination with ecological modeling (CASIMIR). After two years of hydropower operation, preliminary results show that the ecological sustainability of the directly affected river stretch (2 km) is still in good order. It can be shown that especially small fish species and earlier fish life stages profit from the water withdrawal while the habitat of adult brown trout is reduced even so an extraordinary environmental flow is released in the river bed. Restoration of riparian cover structures and foru new fishpasses help to compensate this unavoidable loss. Even if it is yet to early to audit all negative and positive aspects, the hydropower plant under investigation is an excellent example how a fair compromise between nature conservation, renewable energy supply and economics can be achieved. (orig.)

  14. First retrieval of hourly atmospheric radionuclides just after the Fukushima accident by analyzing filter-tapes of operational air pollution monitoring stations

    Science.gov (United States)

    Tsuruta, Haruo; Oura, Yasuji; Ebihara, Mitsuru; Ohara, Toshimasa; Nakajima, Teruyuki

    2014-01-01

    No observed data have been found in the Fukushima Prefecture (FP) for the time-series of atmospheric radionuclides concentrations just after the Fukushima Daiichi Nuclear Power Plant (FD1NPP) accident. Accordingly, current estimates of internal radiation doses from inhalation, and atmospheric radionuclide concentrations by atmospheric transport models are highly uncertain. Here, we present a new method for retrieving the hourly atmospheric 137Cs concentrations by measuring the radioactivity of suspended particulate matter (SPM) collected on filter tapes in SPM monitors which were operated even after the accident. This new dataset focused on the period of March 12–23, 2011 just after the accident, when massive radioactive materials were released from the FD1NPP to the atmosphere. Overall, 40 sites of the more than 400 sites in the air quality monitoring stations in eastern Japan were studied. For the first time, we show the spatio-temporal variation of atmospheric 137Cs concentrations in the FP and the Tokyo Metropolitan Area (TMA) located more than 170 km southwest of the FD1NPP. The comprehensive dataset revealed how the polluted air masses were transported to the FP and TMA, and can be used to re-evaluate internal exposure, time-series radionuclides release rates, and atmospheric transport models. PMID:25335435

  15. Safety Evaluation Report related to the operation of Nine Mile Point Nuclear Station, Unit No. 2 (Docket No. 50-410). Supplement No. 4

    International Nuclear Information System (INIS)

    1986-09-01

    This report supplements the Safety Evaluation Report (NUREG-1047, February 1985) for the application filed by Niagara Mohawk Power Corporation, as applicant and co-owner, for a license to operate Nine Mile Point Nuclear Station, Unit 2 (Docket No. 50-410). It has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located near Oswego, New York. Supplement 1 to the Safety Evaluation Report was published in June 1985, and contained the report from the Advisory Committee on Reactor Safeguards as well as the resolution of a number of outstanding issues from the Safety Evaluation Report. Supplement 2 was published in November 1985, and contained the resolution of a number of outstanding and confirmatory issues. Supplement 3 was published in July 1986, and contained the resolution of a number of outstanding and confirmatory items, one new confirmatory item, the evaluation of the Engineering Assurance Program, and evaluation of a number of exemption requests

  16. Effect of pH on the release of radionuclides and chelating agents from cement-solidified decontamination ion-exchange resins collected from operating nuclear power stations

    International Nuclear Information System (INIS)

    McIsaac, C.V.; Akers, D.W.; McConnell, J.W.

    1991-06-01

    Data are presented on the physical stability and leachability of radionuclides and chelating agents from cement-solidified decontamination ion-exchange resin wastes collected from two operating commercial light water reactors. Small-scale waste--form specimens collected during solidifications performed at the Brunswick Steam Electric Plant Unit 1 and at the James A. FitzPatrick Nuclear Power Station were leach-tested and subjected to compressive strength testing in accordance with the Nuclear Regulatory Commission's ''Technical Position on Waste Form'' (Revision 1). Samples of untreated resin waste collected from each solidification vessel before the solidification process were analyzed for concentrations of radionuclides, selected transition metals, and chelating agents to determine the quantities of these chemicals in the waste-form specimens. The chelating agents included oxalic, citric, and picolinic acids. In order to determine the effect of leachant chemical composition and pH on the stability and leachability of the waste forms, waste-form specimens were leached in various leachants. Results of this study indicate that differences in pH do not affect releases from cement-solidified decontamination ion-exchange resin waste forms, but that differences in leachant chemistry and the presence of chelating agents may affect the releases of radionuclides and chelating agents. Also, this study indicates that the cumulative releases of radionuclides and chelating agents are similar for waste- form specimens that decomposed and those that retained their general physical form. 36 refs., 60 figs., 28 tabs

  17. Safety evaluation report related to the operation of Comanche Peak Steam Electric Station, Units 1 and 2 (Docket Nos. 50-445 and 50-446)

    International Nuclear Information System (INIS)

    1988-03-01

    Supplement 14 to the Safety Evaluation Report related to the operation of the Comanche Peak Stam Electric Station (CPSES), Units 1 and 2 (NUREG-0797), has been prepared by the Office of Special Projects of the US Nuclear Regulatory Commission (NRC). The facility is located in Somerville County, Texas, approximately 40 miles southwest of Fort Worth, Texas. This supplement presents the staff's evaluation of the applicants' Corrective Action Program (CAP0 related to large ans small bore piping and pipe supports. The scope and methodologies for CAP workshop as summarized in revision O to the large and small bore piping project status reports and as detailed in related documents referenced in this evaluation were developed to resolve various design issues raised by the Atomic Safety and Licensing Board (ASLB);the intervenor, Citizens Association for Sound Energy (CASE);the Camanche Peak Response Team (CPRT);SYGNA Energy Services (CYGNA);and the NRC staff. The NRC staff concludes that the CAP workscopes for large and small bore piping provide a comprehensive program for resolving the associated technical concerns identified by the ASLB, CASE, CPRT, CYGNA, and the NRC staff and their implementation ensures that the design of large and small bore piping and pipe supports at CPSES satisfies the applicable requirements of 10 CFR 50

  18. Safety evaluation report related to the operation of Comanche Peak Steam Electric Station, Units 1 and 2: Docket No. 50-445 and 50-446

    International Nuclear Information System (INIS)

    1988-11-01

    Supplement 20 to the Safety Evaluation Report related to the operation of the Comanche Peak Steam Electric Station (CPSES), Units 1 and 2 (NUREG-0797), has been prepared by the Office of Special Projects of the US Nuclear Regulatory Commission (NRC). The facility is located in Somervell County, Texas, approximately 40 miles southwest of Fort Worth, Texas. This supplement presents the staff's evaluation of CPRT implementation of the Comanche Peak Response Team (CPRT) Program Plan and the issue-specific action plans (ISAPs), as well as the CPRT's investigations to determine the adequacy of various types of programs and hardware at CPSES. The results and conclusions of the CPRT activities are documented in a results report for each ISAP, a Collective Evaluation Report (CER), and a Collective Significance Report (CSR). This supplement also presents the staff's safety evaluation of TU Electric's root cause assessment of past CPSES design deficiencies and weaknesses. The NRC staff concludes that the CPRT has adequately implemented its investigative activities related to the design, construction, construction quality assurance/quality control, and testing at CPSES. The NRC staff further concludes that the CPRT evaluation of the results of its investigation is thorough and complete and its recommendations for corrective actions are sufficient to resolve identified deficiencies

  19. Humans on the International Space Station-How Research, Operations, and International Collaboration are Leading to New Understanding of Human Physiology and Performance in Microgravity

    Science.gov (United States)

    Ronbinson, Julie A.; Harm, Deborah L.

    2009-01-01

    As the International Space Station (ISS) nears completion, and full international utilization is achieved, we are at a scientific crossroads. ISS is the premier location for research aimed at understanding the effects of microgravity on the human body. For applications to future human exploration, it is key for validation, quantification, and mitigation of a wide variety of spaceflight risks to health and human performance. Understanding and mitigating these risks is the focus of NASA s Human Research Program. However, NASA s approach to defining human research objectives is only one of many approaches within the ISS international partnership (including Roscosmos, the European Space Agency, the Canadian Space Agency, and the Japan Aerospace Exploration Agency). Each of these agencies selects and implements their own ISS research, with independent but related objectives for human and life sciences research. Because the science itself is also international and collaborative, investigations that are led by one ISS partner also often include cooperative scientists from around the world. The operation of the ISS generates significant additional data that is not directly linked to specific investigations. Such data comes from medical monitoring of crew members, life support and radiation monitoring, and from the systems that have been implemented to protect the health of the crew (such as exercise hardware). We provide examples of these international synergies in human research on ISS and highlight key early accomplishments that derive from these broad interfaces. Taken as a whole, the combination of diverse research objectives, operational data, international sharing of research resources on ISS, and scientific collaboration provide a robust research approach and capability that no one partner could achieve alone.

  20. Construction on a new deep ice coring site at Dome Fuji Station -Operations carried out by the JARE-44 Dome Fuji overwintering team-

    Directory of Open Access Journals (Sweden)

    Takao Kameda

    2005-07-01

    Full Text Available Eight members of the 44th Japanese Antarctic Research Expedition (JARE-44 stayed at Dome Fuji Station (77°19′01″S, 39°42′11″E; 3810 m a.s.l.; ice thickness 3028±15 m; mean air temperature -54.4°C; lowest air temperature -79.7°C from January 19, 2003 to January 25, 2004 for glaciological, meteorological, and upper atmospheric observations, and for construction at a new ice coring site for deep ice coring. The construction was a continuation of the activities of JARE-43; JARE-44 primarily carried out interior work at the ice coring site. The following works were carried out during the overwintering period and are described in this paper: retrieval of casing pipes from the borehole, enlargement of the borehole, insertion of casing pipes into the borehole, movement of the winch system from the old to the new ice coring sites (44.5 m apart, floor construction, construction and preparation of a 10 m depth pit for the rotating mast, construction of stairs between the old and the new ice coring sites, construction of working tables, assembling the mast and the small goliath crane, setting up a lifter, testing the winch system, setting the winch for the chip collector, cable replacement for deep ice coring, assembling of a deep ice core drill, adjustment of a rotating mast, enlargement of caves for ice core storage, and general electrical work in the new ice coring site. The total working time for the above operations was 593.5 person-days. Since the average working time was 6 h/day, the total working time was 3561 person-hours. Preparations for borehole temperature measurements in a 2503 m borehole and the ice coring operation that was mainly conducted by the JARE-45 team are briefly described.

  1. Safety evaluation report related to the operation of LaSalle County Station, Units 1 and 2, (Docket Nos. 50-373 and 50-374). Supplement No. 7

    International Nuclear Information System (INIS)

    1983-12-01

    Supplement No. 7 to the Safety Evaluation Report of Commonwealth Edison Company's application for a license to operate its La Salle County Station, Unit 2, located on Brookfield Township, La Salle County, Illinois, has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement is to update our evaluations on Unit 2 issues identified in the previous Safety Evaluation Report and Supplements that need resolution prior to issuance of the operating license for Unit 2

  2. Ground-water hydrology and simulation of ground-water flow at Operable Unit 3 and surrounding region, U.S. Naval Air Station, Jacksonville, Florida

    Science.gov (United States)

    Davis, J.H.

    1998-01-01

    The Naval Air Station, Jacksonville (herein referred to as the Station), occupies 3,800 acres adjacent to the St. Johns River in Duval County, Florida. Operable Unit 3 (OU3) occupies 134 acres on the eastern side of the Station and has been used for industrial and commercial purposes since World War II. Ground water contaminated by chlorinated organic compounds has been detected in the surficial aquifer at OU3. The U.S. Navy and U.S. Geological Survey (USGS) conducted a cooperative hydrologic study to evaluate the potential for ground water discharge to the neighboring St. Johns River. A ground-water flow model, previously developed for the area, was recalibrated for use in this study. At the Station, the surficial aquifer is exposed at land surface and forms the uppermost permeable unit. The aquifer ranges in thickness from 30 to 100 feet and consists of unconsolidated silty sands interbedded with local beds of clay. The low-permeability clays of the Hawthorn Group form the base of the aquifer. The USGS previously conducted a ground-water investigation at the Station that included the development and calibration of a 1-layer regional ground-water flow model. For this investigation, the regional model was recalibrated using additional data collected after the original calibration. The recalibrated model was then used to establish the boundaries for a smaller subregional model roughly centered on OU3. Within the subregional model, the surficial aquifer is composed of distinct upper and intermediate layers. The upper layer extends from land surface to a depth of approximately 15 feet below sea level; the intermediate layer extends from the upper layer down to the top of the Hawthorn Group. In the northern and central parts of OU3, the upper and intermediate layers are separated by a low-permeability clay layer. Horizontal hydraulic conductivities in the upper layer, determined from aquifer tests, range from 0.19 to 3.8 feet per day. The horizontal hydraulic

  3. Safety Evaluation Report related to the operation of Comanche Peak Steam Electric Station, Units 1 and 2 (Docket Nos. 50-445 and 50-446)

    International Nuclear Information System (INIS)

    1990-02-01

    Supplement 23 to the Safety Evaluation Report related to the operation of the Comanche Peak Steam Electric Station (CPSES), Units 1 and 2 (NUREG-0797), has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission (NRC). The facility is located in Somervell County, Texas, approximately 40 miles southwest of Fort Worth, Texas. This supplement reports the status of certain issues that had not been resolved when the Safety Evaluation Report and supplements 1, 2, 3, 4, 6, 12, 21, and 22 to that report were published. This supplement also includes the evaluations for licensing items resolved since Supplement 22 was issued. Supplement 5 has not been issued. Supplements 7, 8, 9, 10, and 11 were limited to the staff evaluation of allegations investigated by the NRC Technical Review Team. Supplement 13 presented the staff's evaluation of the Comanche Peak Response Team (CPRT) Program Plan, which was formulated by the applicant to resolve various construction and design issues raised by sources external to TU Electric. Supplements 14 through 19 presented the staff's evaluation of the CPSES Corrective Action Program: large- and small-bore piping and pipe supports (Supplement 14); cable trays and cable tray hangers (Supplement 15); conduit supports (Supplement 16); mechanical, civil/structural, electrical, instrumentation and controls, and systems portions of the heating, ventilation, and air conditioning (HVAC) system workscopes (Supplement 17); HVAC structural design (Supplement 18); and equipment qualification (Supplement 19). Supplement 20 presented the staff's evaluation of the Comanche Peak Response Team implementation of the CPRT Program

  4. Safety evaluation report related to the operation of Comanche Peak Steam Electric Station, Units 1 and 2 (Docket Nos. 50-445 and 50-446)

    International Nuclear Information System (INIS)

    1990-04-01

    Supplement 24 to the Safety Evaluation Report related to the operation of the Comanche Peak Steam Electric Station (CPSES), Units 1 and 2 (NUREG-0797), has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission (NRC). The facility is located in Somervell County, Texas, approximately 40 miles southwest of Fort Worth, Texas. This supplement reports the status of certain issues that had not been resolved when the Safety Evaluation Report and Supplements 1, 2, 3, 4, 6, 12, 21, 22, and 23 to that report were published. This supplement also includes the evaluations for licensing items resolved since Supplement 23 was issued. Supplement 5 has not been issued. Supplements 7, 8, 9, 10, and 11 were limited to the staff evaluation of allegations investigated by the NRC Technical Review Team. Supplement 13 represented the staff's evaluation of the Comanche Peak Response Team (CPRT) Program Plan, which was formulated by the applicant to resolve various construction and design issues raised by sources external to TU Electric. Supplements 14 through 19 presented the staff's evaluation of the CPSES Corrective Action Program: large- and small-bore piping and pipe supports (Supplement 14); cable trays and cable tray hangers (Supplement 15); conduit supports (Supplement 16); mechanical, civil/structural, electrical, instrumentation and controls, and systems portions of the heating, ventilation, and air conditioning (HVAC) system workscopes (Supplement 17); HVAC structural design (Supplement 18); and equipment qualification (Supplement 19). Supplement 20 presented the staff's evaluation of the CPRT implementation of its Program Plan and the issue-specific action plans, as well as the CPRT's investigations to determine the adequacy of various types of programs and hardware at CPSES

  5. Safety evaluation report related to the operation of Comanche Peak Steam Electric Station, Units 1 and 2 (Docket Nos. 50-445 and 50-446)

    International Nuclear Information System (INIS)

    1988-11-01

    Supplement 19 to the Safety Evaluation Report related to the operation of the Comanche Peak Steam Electric Station (CPSES), Units 1 and 2 (NUREG-0797), has been prepared by the Office of Special Projects of the US Nuclear Regulatory Commission (NRC). The facility is located in Somervell County, Texas, approximately 40 miles southwest of Fort Worth, Texas. This supplement presents the staff's evaluation of the Texas Utilities Electric Company's (lead applicant's) corrective action program (CAP) related to equipment qualification. The scope and methodology for the CAP workscope, as summarized in Revision 0 to the Equipment Qualification Project Status Report and as detailed in related documents, were developed to resolve various issues raised by the Comanche Peak Response Team (CPRT) and the NRC staff to ensure that plant equipment is appropriately environmentally and/or seismically and dynamically qualified and documented in accordance with the validated plant design resulting from other CAP scopes of work for Unit 1 and areas common to Units 1 and 2. The staff concludes that the CAP workscope for equipment qualification provides a comprehensive program for resolving the concerns identified by the CPRT and the NRC staff, including issues raised in the Comanche Peak Safety Evaluation Report and its supplements, and its implementation will ensure that the environmental and/or seismic and dynamic qualification of equipment at CPSES satisfies the validated plant design and the applicable requirements of 10 CFR Part 50. As is routine staff practice, the NRC staff will verify the adequacy of implementation of the environmental and seismic and dynamic equipment qualification program at CPSES during inspections that will take place before fuel loading. 97 refs

  6. 47 CFR 97.203 - Beacon station.

    Science.gov (United States)

    2010-10-01

    ... 47 Telecommunication 5 2010-10-01 2010-10-01 false Beacon station. 97.203 Section 97.203... SERVICE Special Operations § 97.203 Beacon station. (a) Any amateur station licensed to a holder of a Technician, Technician Plus, General, Advanced or Amateur Extra Class operator license may be a beacon. A...

  7. Station Capacity

    DEFF Research Database (Denmark)

    Landex, Alex

    2011-01-01

    the probability of conflicts and the minimum headway times into account. The last method analyzes how optimal platform tracks are used by examining the arrival and departure pattern of the trains. The developed methods can either be used separately to analyze specific characteristics of the capacity of a station......Stations are often limiting the capacity of railway networks. This is due to extra need of tracks when trains stand still, trains turning around, and conflicting train routes. Although stations are often the capacity bottlenecks, most capacity analysis methods focus on open line capacity. Therefore...... for platform tracks and the probability that arriving trains will not get a platform track immediately at arrival. The third method is a scalable method that analyzes the conflicts in the switch zone(s). In its simplest stage, the method just analyzes the track layout while the more advanced stages also take...

  8. The Princess Elisabeth Station

    Science.gov (United States)

    Berte, Johan

    2012-01-01

    Aware of the increasing impact of human activities on the Earth system, Belgian Science Policy Office (Belspo) launched in 1997 a research programme in support of a sustainable development policy. This umbrella programme included the Belgian Scientific Programme on Antarctic Research. The International Polar Foundation, an organization led by the civil engineer and explorer Alain Hubert, was commissioned by the Belgian Federal government in 2004 to design, construct and operate a new Belgian Antarctic Research Station as an element under this umbrella programme. The station was to be designed as a central location for investigating the characteristic sequence of Antarctic geographical regions (polynia, coast, ice shelf, ice sheet, marginal mountain area and dry valleys, inland plateau) within a radius of 200 kilometers (approx.124 miles) of a selected site. The station was also to be designed as "state of the art" with respect to sustainable development, energy consumption, and waste disposal, with a minimum lifetime of 25 years. The goal of the project was to build a station and enable science. So first we needed some basic requirements, which I have listed here; plus we had to finance the station ourselves. Our most important requirement was that we decided to make it a zero emissions station. This was both a philosophical choice as we thought it more consistent with Antarctic Treaty obligations and it was also a logistical advantage. If you are using renewable energy sources, you do not have to bring in all the fuel.

  9. Station History Of The Seismic Station In Ahmadu Bello University ...

    African Journals Online (AJOL)

    Dominants in the selected events are events from Meditterranian, East Kazakhstan, India/Burma/China, South and Central America and North Ascension island regions. The limited number of events reporting at the station was due to low operational gain at the station which permitted only events whose magnitudes are ...

  10. Statistical Analysis of Model Data for Operational Space Launch Weather Support at Kennedy Space Center and Cape Canaveral Air Force Station

    Science.gov (United States)

    Bauman, William H., III

    2010-01-01

    The 12-km resolution North American Mesoscale (NAM) model (MesoNAM) is used by the 45th Weather Squadron (45 WS) Launch Weather Officers at Kennedy Space Center (KSC) and Cape Canaveral Air Force Station (CCAFS) to support space launch weather operations. The 45 WS tasked the Applied Meteorology Unit to conduct an objective statistics-based analysis of MesoNAM output compared to wind tower mesonet observations and then develop a an operational tool to display the results. The National Centers for Environmental Prediction began running the current version of the MesoNAM in mid-August 2006. The period of record for the dataset was 1 September 2006 - 31 January 2010. The AMU evaluated MesoNAM hourly forecasts from 0 to 84 hours based on model initialization times of 00, 06, 12 and 18 UTC. The MesoNAM forecast winds, temperature and dew point were compared to the observed values of these parameters from the sensors in the KSC/CCAFS wind tower network. The data sets were stratified by model initialization time, month and onshore/offshore flow for each wind tower. Statistics computed included bias (mean difference), standard deviation of the bias, root mean square error (RMSE) and a hypothesis test for bias = O. Twelve wind towers located in close proximity to key launch complexes were used for the statistical analysis with the sensors on the towers positioned at varying heights to include 6 ft, 30 ft, 54 ft, 60 ft, 90 ft, 162 ft, 204 ft and 230 ft depending on the launch vehicle and associated weather launch commit criteria being evaluated. These twelve wind towers support activities for the Space Shuttle (launch and landing), Delta IV, Atlas V and Falcon 9 launch vehicles. For all twelve towers, the results indicate a diurnal signal in the bias of temperature (T) and weaker but discernable diurnal signal in the bias of dewpoint temperature (T(sub d)) in the MesoNAM forecasts. Also, the standard deviation of the bias and RMSE of T, T(sub d), wind speed and wind

  11. 47 CFR 74.882 - Station identification.

    Science.gov (United States)

    2010-10-01

    ...'s call sign or designator, its location, and the call sign of the broadcasting station or name of... operation. Identification may be made by transmitting the station call sign by visual or aural means or by...

  12. Space Station Habitability Research

    Science.gov (United States)

    Clearwater, Yvonne A.

    1988-01-01

    The purpose and scope of the Habitability Research Group within the Space Human Factors Office at the NASA/Ames Research Center is described. Both near-term and long-term research objectives in the space human factors program pertaining to the U.S. manned Space Station are introduced. The concept of habitability and its relevancy to the U.S. space program is defined within a historical context. The relationship of habitability research to the optimization of environmental and operational determinants of productivity is discussed. Ongoing habitability research efforts pertaining to living and working on the Space Station are described.

  13. Power station instrumentation

    International Nuclear Information System (INIS)

    Jervis, M.W.

    1993-01-01

    Power stations are characterized by a wide variety of mechanical and electrical plant operating with structures, liquids and gases working at high pressures and temperatures and with large mass flows. The voltages and currents are also the highest that occur in most industries. In order to achieve maximum economy, the plant is operated with relatively small margins from conditions that can cause rapid plant damage, safety implications, and very high financial penalties. In common with other process industries, power stations depend heavily on control and instrumentation. These systems have become particularly significant, in the cost-conscious privatized environment, for providing the means to implement the automation implicit in maintaining safety standards, improving generation efficiency and reducing operating manpower costs. This book is for professional instrumentation engineers who need to known about their use in power stations and power station engineers requiring information about the principles and choice of instrumentation available. There are 8 chapters; chapter 4 on instrumentation for nuclear steam supply systems is indexed separately. (Author)

  14. Sexual function and postpartum depression 6 months after attempted operative vaginal delivery according to fetal head station: A prospective population-based cohort study.

    Directory of Open Access Journals (Sweden)

    Guillaume Ducarme

    Full Text Available To evaluate the effect of the fetal head station at attempted operative vaginal delivery (aOVD, and specifically midpelvic or low aOVD, on female and male sexual function and symptoms of postpartum depression (PPD at 6 months.Prospective population-based cohort study.1,941 women with singleton term fetuses in vertex presentation with midpelvic or low aOVD between 2008 and 2013 in a tertiary care university hospital.Symptoms of female sexual dysfunction using the Pelvic Organ Prolapse/Urinary Incontinence/Sexual Function Short Form Questionnaire (PISQ-12, symptoms of PPD using the Edinburgh Postnatal Depression Scale (EPDS score, symptoms of male sexual dysfunction using the International Index of Erectile Function (IIEF-15 and perineal pain were assessed 6 months after aOVD. We measured the association between midpelvic or low aOVD and symptoms of female and male sexual function and symptoms of PPD at 6 months using multiple regression and adjusting for demographics, and risk factors of sexual dysfunction, symptoms of PPD and perineal pain with adjusted odds ratios (aORs and 95% confidence intervals (95% CI.The study included 907 women (46.7% who responded to the questionnaire; 18.4% (167/907 had midpelvic aOVD, and 81.6% (740/907 low. Most women (873/907 [96.3%] of those with partners reported sexual activity at 6 months. No significant difference was observed for PISQ-12, EPDS, IIEF-15 scores and perineal pain between mid and low pelvic groups. Compared with low pelvic aOVD, midpelvic aOVD was not significantly associated with either female or male sexual dysfunction (p = 0.89 and p = 0.76, respectively, or maternal symptoms of PPD (p = 0.83. Perineal pain significantly increased the risk of male and female sexual dysfunction and maternal symptoms of PPD at 6 months (p = 0.02, p = 0.006, and p = 0.02, respectively.Midpelvic compared with low pelvic aOVD was not associated with an increase in sexual dysfunction, nor with symptoms of PPD at 6

  15. Safety evaluation report: related to the operation of Seabrook Station, Units 1 and 2, Docket Nos. 50-443 and 50-444, Public Service Company of New Hampshire, et al

    International Nuclear Information System (INIS)

    1983-03-01

    The Safety Evaluation Report for the application filed by the Public Service Company of New Hampshire, et al., for licenses to operate Seabrook Station, Units 1 and 2 (Docket Nos. STN 50-443 and STN 50-444), has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located in Seabrook, New Hampshire. Subject to favorable resolution of the items discussed in this report, the staff concludes that the facility can be operated by the applicant without endangering the health and safety of the public

  16. 47 CFR 80.123 - Service to stations on land.

    Science.gov (United States)

    2010-10-01

    ... 47 Telecommunication 5 2010-10-01 2010-10-01 false Service to stations on land. 80.123 Section 80... STATIONS IN THE MARITIME SERVICES Operating Requirements and Procedures Special Procedures-Public Coast Stations § 80.123 Service to stations on land. Marine VHF public coast stations, including AMTS coast...

  17. UMTS Network Stations

    Science.gov (United States)

    Hernandez, C.

    2010-09-01

    The weakness of small island electrical grids implies a handicap for the electrical generation with renewable energy sources. With the intention of maximizing the installation of photovoltaic generators in the Canary Islands, arises the need to develop a solar forecasting system that allows knowing in advance the amount of PV generated electricity that will be going into the grid, from the installed PV power plants installed in the island. The forecasting tools need to get feedback from real weather data in "real time" from remote weather stations. Nevertheless, the transference of this data to the calculation computer servers is very complicated with the old point to point telecommunication systems that, neither allow the transfer of data from several remote weather stations simultaneously nor high frequency of sampling of weather parameters due to slowness of the connection. This one project has developed a telecommunications infrastructure that allows sensorizadas remote stations, to send data of its sensors, once every minute and simultaneously, to the calculation server running the solar forecasting numerical models. For it, the Canary Islands Institute of Technology has added a sophisticated communications network to its 30 weather stations measuring irradiation at strategic sites, areas with high penetration of photovoltaic generation or that have potential to host in the future photovoltaic power plants connected to the grid. In each one of the stations, irradiance and temperature measurement instruments have been installed, over inclined silicon cell, global radiation on horizontal surface and room temperature. Mobile telephone devices have been installed and programmed in each one of the weather stations, which allow the transfer of their data taking advantage of the UMTS service offered by the local telephone operator. Every minute the computer server running the numerical weather forecasting models receives data inputs from 120 instruments distributed

  18. Final environmental statement related to the operation of Catawba Nuclear Station, Units 1 and 2. Docket Nos. 50-413 and 50-414, Duke Power Company, et al

    International Nuclear Information System (INIS)

    1983-01-01

    This Final Environmental Statement contains the second assessment of the environmental impact associated with the operation of the Catawba Nuclear Station, Units 1 and 2, pursuant to the National Environmental Policy Act of 1969 (NEPA) and 10 CFR 51, as amended, of the NRC regulations. This statement examines: the affected environment, environmental consequences and mitigating actions, and environmental and economic benefits and costs. Land use and terrestrial and aquatic-ecological impacts will be small. Operational impacts to historic and archeological sites will be negligible. The effects of routine operations, energy transmission, and periodic maintenance of rights-of-way and transmission facilities should not jeopardize any populations of endangered or threatened species. No significant impacts are anticipated from normal operational releases of radioactivity. The risk associated with accidental radiation exposure is very low. The net socioeconomic effects of the project will be beneficial

  19. 47 CFR 22.313 - Station identification.

    Science.gov (United States)

    2010-10-01

    ... Telephone Radio Systems in the Rural Radiotelephone Service; (5) [Reserved] (6) Stations operating pursuant... Telecommunication FEDERAL COMMUNICATIONS COMMISSION (CONTINUED) COMMON CARRIER SERVICES PUBLIC MOBILE SERVICES... of each station in the Public Mobile Services must ensure that the transmissions of that station are...

  20. The Ongoing Addition of Infrasound Sensors and the Flexette Wind-Noise Reducing System to Global Seismic Network Stations Operated by Project IDA

    Science.gov (United States)

    Ebeling, C. W.; Coon, C.

    2017-12-01

    Infrasound sensors are now being installed at Global Seismic Network (GSN) stations meeting certain infrastructure criteria. Manufactured by Hyperion Technology Group, Inc., these instruments (model IFS-3312) have a nominal sensitivity of 140 mV/Pa (at 1 Hz), a full-scale range of ±100 Pa, and a dynamic range of 120 dB. Low power consumption (750 mW at 12 VDC) and small size (153 mm x 178 mm) ease incorporation into the mix of existing GSN instrumentation. The accompanying flexible rosette ("Flexette") acoustic wind-noise reducing system, designed by Project IDA (International Deployment of Accelerometers-IDA), optimally includes 24 inlets, 4 secondary manifolds, and a single primary manifold. Each secondary manifold is connected to 6 inlets and to the primary manifold by 10-ft air hoses, thus eliminating stresses and the greater potential for leaks associated with the use of pipe. While the main design goal was to maximize the reduction of acoustic wind-noise over the widest range of wind speeds possible, consideration of additional criteria resulted in a Flexette base design easily tailored to meet individual station constraints and restrictions, made up of inexpensive (total cost Marshall Islands), in August 2017. During the next 6 months infrasound capability will be extended to IDA GSN stations BORG (Borganes, Iceland), EFI (Mount Kent, East Falkland Islands), and SACV (Santiago Island, Cape Verde).As with other data from GSN stations, real-time infrasound data are freely available from the Incorporated Research Institutions for Seismology-Data Management Center (IRIS-DMC).