WorldWideScience

Sample records for station unit

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

    Science.gov (United States)

    2010-12-06

    ...- 2010-0373] Dresden Nuclear Power Station, Units 2 and 3 and Quad Cities Nuclear Power Station, Unit Nos... and DPR-25 for Dresden Nuclear Power Station, Units 2 and 3, respectively, located in Grundy County, Illinois, and to Renewed Facility Operating License Nos. DPR-29 and DPR-30 for Quad Cities Nuclear Power...

  2. 76 FR 40754 - Duke Energy Carolinas, LLC Catawba Nuclear Station, Units 1 and 2; McGuire Nuclear Station, Units...

    Science.gov (United States)

    2011-07-11

    ..., 50-270, And 50-287] Duke Energy Carolinas, LLC Catawba Nuclear Station, Units 1 and 2; McGuire Nuclear Station, Units 1 and 2; Oconee Nuclear Station, Units 1, 2, and 3; Notice of Withdrawal of... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY...

  3. 78 FR 46616 - Virginia Electric and Power Company; North Anna Power Station, Units 1 and 2; Surry Power Station...

    Science.gov (United States)

    2013-08-01

    ...] Virginia Electric and Power Company; North Anna Power Station, Units 1 and 2; Surry Power Station, Units 1... the Emergency Plan, ``Conditions of licenses,'' for North Anna Power Station, Units 1 and 2 (NAPS), for Renewed Facility Operating License Nos. NPF-4 and NPF-7, and Surry Power Station, Units 1 and 2...

  4. 78 FR 35646 - Byron Nuclear Station, Units 1 and 2, and Braidwood Nuclear Station, Units 1 and 2

    Science.gov (United States)

    2013-06-13

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

  5. Space vehicle field unit and ground station system

    Science.gov (United States)

    Judd, Stephen; Dallmann, Nicholas; Delapp, Jerry; Proicou, Michael; Seitz, Daniel; Michel, John; Enemark, Donald

    2017-09-19

    A field unit and ground station may use commercial off-the-shelf (COTS) components and share a common architecture, where differences in functionality are governed by software. The field units and ground stations may be easy to deploy, relatively inexpensive, and be relatively easy to operate. A novel file system may be used where datagrams of a file may be stored across multiple drives and/or devices. The datagrams may be received out of order and reassembled at the receiving device.

  6. 75 FR 9956 - PSEG Nuclear LLC, Hope Creek Generating Station and Salem Nuclear Generating Station, Unit Nos. 1...

    Science.gov (United States)

    2010-03-04

    ... COMMISSION PSEG Nuclear LLC, Hope Creek Generating Station and Salem Nuclear Generating Station, Unit Nos. 1... Station, Unit Nos. 1 and 2 (Salem), and Hope Creek Generating Station (HCGS). The licenses provide, among... life or property or the common defense and security, and are otherwise in the public interest. NRC...

  7. Station black out of Fukushima Daiichi Nuclear Power Station Unit 1 was not caused by tsunamis

    International Nuclear Information System (INIS)

    Ito, Yoshinori

    2013-01-01

    Station black out (SBO) of Fukushima Daiichi Nuclear Power Station Unit 1 would be concluded to be caused before 15:37 on March 11, 2011 because losses of emergency ac power A system was in 15:36 and ac losses of B system in 15:37 according to the data published by Tokyo Electric Power Co. (TEPCO) in May 10, 2013. Tsunami attacked the site of Fukushima Daiichi Nuclear Power Station passed through the position of wave amplitude meter installed at 1.5 km off the coast after 15:35 and it was also recognized tsunami arrived at the coast of Unit 4 sea side area around in 15:37 judging from a series of photographs taken from the south side of the site and general knowledge of wave propagation. From a series of photographs and witness testimony, tsunami didn't attack Fukushima Daiichi Nuclear Power Station uniformly and tsunami's arrival time at the site of Unit 1 would be far later than arrival time at the coast of Unit 4 sea side area, which suggested it would be around in 15:39. TEPCO insisted tsunami passed through 1.5 km off the coast around in 15:33 and clock of wave amplitude meter was incorrect, which might be wrong. Thus SBO of Fukushima Daiichi Nuclear Power Station Unit 1 occurred before tsunami's arrival at the site of Unit 1 and was not caused by tsunami. (T. Tanaka)

  8. 76 FR 24538 - Duke Energy Carolinas, LLC; Catawba Nuclear Station, Units 1 and 2; McGuire Nuclear Station...

    Science.gov (United States)

    2011-05-02

    ..., 50-270, and 50-287] Duke Energy Carolinas, LLC; Catawba Nuclear Station, Units 1 and 2; McGuire Nuclear Station, Units 1 and 2; Oconee Nuclear Station, Units 1, 2, and 3; Notice of Withdrawal of... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY...

  9. Preoperation of Hamaoka Nuclear Power Station Unit No. 4

    International Nuclear Information System (INIS)

    Fukuyo, Tadashi; Kurata, Satoshi

    1994-01-01

    Chubu Electric Power Co. finished preoperation of Hamaoka Nuclear Power Station Unit No. 4 in September, 1993. Although unit 4 has the same reactor design as unit 3, its rated electrical output (1,137MW) is 37MW more than that of unit 3. This increase was achieved mainly by adopting a Moisture Separater Heater in the turbine system. We started preoperation of unit 4 in November 1992 and performed various tests at electrical outputs of 20%, 50%, 75%, and 100%. We finished preoperation without any scram or other major problems and obtained satisfactory results for the functions and performance of the plant. This paper describes the major results of unit 4 preoperation. (author)

  10. Evaluation of River Bend Station Unit 1 Technical Specifications

    International Nuclear Information System (INIS)

    Baxter, D.E.; Bruske, S.J.

    1985-08-01

    This document was prepared for the Nuclear Regulatory Commission (NRC) to assist them in determining whether the River Bend Station Unit 1 Technical Specifications (T/S), which govern plant systems configurations and operations, are in conformance with the requirements of the Final Safety Analysis Report (FSAR) as amended, and the requirements of the Safety Evaluation Report (SER) as supplemented. A comparative audit of the FSAR as amended, and the SER as supplemented was performed with the River Bend T/S. Several discrepancies were identified and subsequently resolved through discussions with the cognizant NRC reviewer, NRC staff reviewers and/or utility representatives. The River Bend Station Unit 1 T/S, to the extent reviewed, are in conformance with the FSAR and SER

  11. 77 FR 66484 - PSEG Nuclear LLC; Hope Creek Generating Station and Salem Generating Station, Units 1 and 2...

    Science.gov (United States)

    2012-11-05

    ... COMMISSION PSEG Nuclear LLC; Hope Creek Generating Station and Salem Generating Station, Units 1 and 2... Nos. NPF-57, DPR-70, and DPR-75, which authorize operation of the Hope Creek Generating Station (HCGS... will not endanger life or property or the common defense and security, and are otherwise in the public...

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

    International Nuclear Information System (INIS)

    1977-09-01

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

  13. 75 FR 36700 - Exelon Generation Company, LLC; Three Mile Island Nuclear Station, Unit 1; Environmental...

    Science.gov (United States)

    2010-06-28

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

  14. 78 FR 77726 - Exelon Generation Company, LLC Three Mile Island Nuclear Station, Unit 1

    Science.gov (United States)

    2013-12-24

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

  15. 75 FR 38845 - Exelon Generation Company, LLC; Three Mile Island Nuclear Station, Unit No. 1; Exemption

    Science.gov (United States)

    2010-07-06

    ...; Three Mile Island Nuclear Station, Unit No. 1; Exemption 1.0 Background Exelon Generation Company, LLC... of the Three Mile Island Nuclear Station, Unit 1 (TMI-1). The license provides, among other things... demonstrations, the licensee stated that three qualified operators are available to perform the manual action at...

  16. 77 FR 50533 - Dominion Nuclear Connecticut, Inc.; Millstone Power Station, Unit 3

    Science.gov (United States)

    2012-08-21

    ....; Millstone Power Station, Unit 3 AGENCY: Nuclear Regulatory Commission. ACTION: Environmental assessment and... search, select ``ADAMS Public Documents'' and then select ``Begin Web- based ADAMS Search.'' For problems... Optimized ZIRLO\\TM\\ fuel rod cladding in future core reload applications for Millstone Power Station, Unit 3...

  17. 77 FR 11596 - Central Vermont Public Service Corporation, Millstone Power Station, Unit 3; Notice of...

    Science.gov (United States)

    2012-02-27

    ... NUCLEAR REGULATORY COMMISSION [Docket No. 50-423; NRC-2012-0044] Central Vermont Public Service Corporation, Millstone Power Station, Unit 3; Notice of Consideration of Approval of Application Regarding... License (No. NPF- 49) for the Millstone Power Station, Unit 3 (MPS3) to the extent held by Central Vermont...

  18. Enhanced Hourly Wind Station Data for the Contiguous United States

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — U.S. Enhanced Hourly Wind Station Data is digital data set DSI-6421, archived at the National Centers for Environmental Information (NCEI; formerly National Climatic...

  19. 47 CFR 90.421 - Operation of mobile station units not under the control of the licensee.

    Science.gov (United States)

    2010-10-01

    ....421 Operation of mobile station units not under the control of the licensee. Mobile stations, as... unauthorized operation of such units not under its control. (a) Public Safety Pool. (1) Mobile units licensed... 47 Telecommunication 5 2010-10-01 2010-10-01 false Operation of mobile station units not under the...

  20. Method of sharing mobile unit state information between base station routers

    NARCIS (Netherlands)

    Bosch, H.G.P.; Mullender, Sape J.; Polakos, Paul Anthony; Rajkumar, Ajay; Sundaram, Ganapathy S.

    2007-01-01

    The present invention provides a method of operating a first base station router. The method may include transmitting state information associated with at least one inactive mobile unit to at least one second base station router. The state information is usable to initiate an active session with the

  1. Method of sharing mobile unit state information between base station routers

    NARCIS (Netherlands)

    Bosch, H.G.P.; Mullender, Sape J.; Polakos, Paul Anthony; Rajkumar, Ajay; Sundaram, Ganapathy S.

    2010-01-01

    The present invention provides a method of operating a first base station router. The method may include transmitting state information associated with at least one inactive mobile unit to at least one second base station router. The state information is usable to initiate an active session with the

  2. 32 CFR 884.9 - Requests for custody of members stationed outside the United States.

    Science.gov (United States)

    2010-07-01

    ...) DEPARTMENT OF THE AIR FORCE MILITARY PERSONNEL DELIVERY OF PERSONNEL TO UNITED STATES CIVILIAN AUTHORITIES... stationed outside the United States to the United States for delivery to civilian authorities if the offense... process sought to be enforced or otherwise to show legitimate cause for noncompliance. 4 4 See footnote in...

  3. Optimal selection of Orbital Replacement Unit on-orbit spares - A Space Station system availability model

    Science.gov (United States)

    Schwaab, Douglas G.

    1991-01-01

    A mathematical programing model is presented to optimize the selection of Orbital Replacement Unit on-orbit spares for the Space Station. The model maximizes system availability under the constraints of logistics resupply-cargo weight and volume allocations.

  4. Evaluation of High-Performance Rooftop HVAC Unit Naval Air Station Key West, Florida

    Energy Technology Data Exchange (ETDEWEB)

    Howett, Daniel H. [ORNL; Desjarlais, Andre Omer [ORNL; Cox, Daryl [ORNL

    2018-01-01

    This report documents performance of a high performance rooftop HVAC unit (RTU) at Naval Air Station Key West, FL. This report was sponsored by the Federal Energy Management Program as part of the "High Performance RTU Campaign".

  5. Acquisition of a Leica ScanStation II LIDAR unit

    Science.gov (United States)

    2008-04-01

    The funding will be used to purchase a LiDAR (Light Detection and Ranging) unit to generate external funding in many diverse areas. The investigators will initially seek funding from NSF, transportation agencies, and emergency management agencies for...

  6. Counter rotating type hydroelectric unit suitable for tidal power station

    International Nuclear Information System (INIS)

    Kanemoto, T; Suzuki, T

    2010-01-01

    The counter rotating type hydroelectric unit, which is composed of the axial flow type tandem runners and the peculiar generator with double rotational armatures,was proposed to utilize effectively the tidal power. In the unit, the front and the rear runners counter drive the inner and the outer armatures of the generator, respectively. Besides, the flow direction at the rear runner outlet must coincide with the flow direction at the front runner inlet, because the angular momentum through the rear runner must coincides with that through the front runner. That is, the flow runs in the axial direction at the rear runner outlet while the axial inflow at the front runner inlet. Such operations are suitable for working at the seashore with rising and falling tidal flows, and the unit may be able to take place of the traditional bulb type turbines. The tandem runners were operated at the on-cam conditions, in keeping the induced frequency constant. The output and the hydraulic efficiency are affected by the adjustment of the front and the blade setting angles. The both optimum angles giving the maximum output and/or efficiency were presented at the various discharges/heads. To promote more the tidal power generation by this type unit, the runners were also modified so as to be suitable for both rising and falling flows. The hydraulic performances are acceptable while the output is determined mainly by the trailing edge profiles of the runner blades.

  7. 76 FR 48184 - Exelon Nuclear, Peach Bottom Atomic Power Station, Unit 1; Exemption From Certain Security...

    Science.gov (United States)

    2011-08-08

    ... NUCLEAR REGULATORY COMMISSION [Docket No. 50-171; NRC-2011-0141] Exelon Nuclear, Peach Bottom Atomic Power Station, Unit 1; Exemption From Certain Security Requirements 1.0 Background Exelon Nuclear... nuclear reactor facility. PBAPS Unit 1 was a high-temperature, gas-cooled reactor that was operated from...

  8. Genesee generating station, unit 1: Construction and commissioning

    Energy Technology Data Exchange (ETDEWEB)

    Trowsdale, D.R.

    1995-12-31

    The Genesee Power Plant is located about 80 kilometers southwest of Edmonton, in an area with vast coal reserves. Completion of the plant`s 410-megawatt Unit 1 in 1994 concluded the last phase of a development originally approved for construction and commercial operation in 1980. This paper reviews the history of the plant, its site plan and general design features, and presents a case study of the construction and commissioning of Unit 1. The case study describes work schedule management, construction coordination, quality control and quality assurance procedures, site cost control, safety management, labor relations, commissioning management, scheduling and staffing, work planning and coordination, and problems encountered during construction and commissioning, as well as actions taken to solve those problems.

  9. Daily snow depth measurements from 195 stations in the United States

    Energy Technology Data Exchange (ETDEWEB)

    Allison, L.J. [ed.] [Oak Ridge National Lab., TN (United States). Carbon Dioxide Information Analysis Center; Easterling, D.R.; Jamason, P.; Bowman, D.P.; Hughes, P.Y.; Mason, E.H. [National Oceanic and Atmospheric Administration, Asheville, NC (United States). National Climatic Data Center

    1997-02-01

    This document describes a database containing daily measurements of snow depth at 195 National Weather Service (NWS) first-order climatological stations in the United States. The data have been assembled and made available by the National Climatic Data Center (NCDC) in Asheville, North Carolina. The 195 stations encompass 388 unique sampling locations in 48 of the 50 states; no observations from Delaware or Hawaii are included in the database. Station selection criteria emphasized the quality and length of station records while seeking to provide a network with good geographic coverage. Snow depth at the 388 locations was measured once per day on ground open to the sky. The daily snow depth is the total depth of the snow on the ground at measurement time. The time period covered by the database is 1893--1992; however, not all station records encompass the complete period. While a station record ideally should contain daily data for at least the seven winter months (January through April and October through December), not all stations have complete records. Each logical record in the snow depth database contains one station`s daily data values for a period of one month, including data source, measurement, and quality flags.

  10. Genesee generating station Unit 1. Construction and commissioning

    Energy Technology Data Exchange (ETDEWEB)

    Trowsdale, D.R.; Keller, A. [Edmonton Power, Edmonton, AB (Canada)

    1995-12-31

    The history of the Genesee Power Project was recapped, providing details of its site plan and design features and a case study of the construction and commissioning of Genesee Unit 1. General principles and specific steps taken to ensure the successful completion of the work were presented. General construction management information and more specific information on scheduling, coordination, quality control and quality assurance measures, site cost control, safety, and labour relations were described. Construction and management problems of all types were recounted, including some significant equipment failures during commissioning. In the end,the construction and commissioning of the Genesee Project was successful, being completed ahead of schedule and under budget. The success of the project was attributed to the best use of available skills and resources, and a capable managerial, engineering and technical staff.

  11. 75 FR 13606 - Arizona Public Service Company, Palo Verde Nuclear Generating Station, Units 1, 2, and 3...

    Science.gov (United States)

    2010-03-22

    ...] Arizona Public Service Company, Palo Verde Nuclear Generating Station, Units 1, 2, and 3; Environmental...-74, issued to Arizona Public Service Company (APS, the licensee), for operation of the Palo Verde Nuclear Generating Station, Units 1, 2, and 3 (PVNGS, Units 1, 2, and 3), located in Maricopa County...

  12. In core reload design for cycle 4 of Daya Bay nuclear power station both units

    International Nuclear Information System (INIS)

    Zhang Zongyao; Liu Xudong; Xian Chunyu; Li Dongsheng; Zhang Hong; Liu Changwen; Rui Min; Wang Yingming; Zhao Ke; Zhang Hong; Xiao Min

    1998-01-01

    The basic principles and the contents of the reload design for Daya Bay nuclear power station are briefly introduced. The in core reload design results, and the comparison between the calculated values and the measured values of both units the fourth cycle are also given. The reload design results of the two units satisfy all the economic requirements and safety criteria. The experimented results shown that the predicated values are tally good with all the measurement values

  13. Technical specifications: Seabrook Station, Unit 1 (Docket No. 50-443)

    International Nuclear Information System (INIS)

    1990-03-01

    The Seabrook Station, Unit 1 Technical Specifications were prepared by the US Nuclear Regulatory Commission to set forth the limits, operating conditions, and other requirements applicable to a nuclear reactor facility as set forth in Section 50.36 of 10 CFR Part 50 for the protection of the health and safety of the public

  14. 76 FR 30204 - Exelon Nuclear, Dresden Nuclear Power Station, Unit 1; Exemption From Certain Security Requirements

    Science.gov (United States)

    2011-05-24

    ... NUCLEAR REGULATORY COMMISSION [Docket No. 50-010; NRC-2011-0108] Exelon Nuclear, Dresden Nuclear Power Station, Unit 1; Exemption From Certain Security Requirements 1.0 Background Exelon Nuclear is the... nuclear material are not inimical to the common defense and security and do not constitute an unreasonable...

  15. 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)

  16. 77 FR 59679 - Central Vermont Public Service Corporation (Millstone Power Station, Unit 3); Order Approving...

    Science.gov (United States)

    2012-09-28

    ... NUCLEAR REGULATORY COMMISSION [NRC-2012-0044; Docket No. 50-423] Central Vermont Public Service Corporation (Millstone Power Station, Unit 3); Order Approving Application Regarding Corporate Restructuring and Conforming Amendment I Dominion Nuclear Connecticut, Inc. (DNC), Central Vermont Public Service...

  17. 75 FR 52045 - Arizona Public Service Company, Palo Verde Nuclear Generating Station, Unit 3; Environmental...

    Science.gov (United States)

    2010-08-24

    ... NUCLEAR REGULATORY COMMISSION [NRC-2010-0281; Docket No. STN 50-530] Arizona Public Service Company, Palo Verde Nuclear Generating Station, Unit 3; Environmental Assessment and Finding of No.... NPF-74, issued to Arizona Public Service Company (APS, the licensee), for operation of Palo Verde...

  18. 77 FR 42768 - Central Vermont Public Service Corporation, Millstone Power Station, Unit 3; Notice of...

    Science.gov (United States)

    2012-07-20

    ... NUCLEAR REGULATORY COMMISSION [Docket No. 50-423; NRC-2012-0044] Central Vermont Public Service Corporation, Millstone Power Station, Unit 3; Notice of Consideration of Approval of Transfer of Facility... Public Service Corporation (CVPS)' interest in the Renewed Facility Operating License (No. NPF-49) for...

  19. 76 FR 5408 - Entergy Operations, Inc., Waterford Steam Electric Station, Unit 3, Environmental Assessment and...

    Science.gov (United States)

    2011-01-31

    ... concluded that the proposed actions will have no significant impact. Environmental Assessment Identification... impacts associated with the proposed exemption. The details of the staff's safety evaluation will be... COMMISSION Entergy Operations, Inc., Waterford Steam Electric Station, Unit 3, Environmental Assessment and...

  20. Conformance to Regulatory Guide 1.97, Wolf Creek Station, Unit No. 1. Revision 1

    International Nuclear Information System (INIS)

    Udy, A.C.

    1985-01-01

    This EG and G Idaho, Inc., report provides a review of the submittals for the Wolf Creek Station, Unit No. 1, and identifies areas of full conformance to Regulatory Guide 1.97, Revision 2. Any exceptions to these guidelines are evaluated and those areas where sufficient basis for acceptability is not provided are identified

  1. 75 FR 9955 - Entergy Operations, Inc.; Grand Gulf Nuclear Station, Unit 1; Environmental Assessment and...

    Science.gov (United States)

    2010-03-04

    ... or water use, or result in changes to the quality or quantity of non- radiological effluents. No... human environment. Accordingly, the NRC has determined not to prepare an environmental impact statement... Gulf Nuclear Station, Unit 1; Environmental Assessment and Finding of No Significant Impact The U.S...

  2. 76 FR 72007 - ZionSolutions, LLC; Zion Nuclear Power Station, Units 1 and 2; Exemption From Certain Security...

    Science.gov (United States)

    2011-11-21

    ... NUCLEAR REGULATORY COMMISSION [Docket Nos. 50-295 and 50-304; NRC-2011-0244] ZionSolutions, LLC; Zion Nuclear Power Station, Units 1 and 2; Exemption From Certain Security Requirements 1.0 Background Zion Nuclear Power Station (ZNPS or Zion), Unit 1, is a Westinghouse 3250 MWt Pressurized Water Reactor...

  3. 78 FR 22347 - GPU Nuclear Inc., Three Mile Island Nuclear Power Station, Unit 2, Exemption From Certain...

    Science.gov (United States)

    2013-04-15

    ... Operating License No. DPR-73 issued for Three Mile Island Nuclear Power Station (TMI), Unit 2, located in... NUCLEAR REGULATORY COMMISSION [Docket No. 50-320; NRC-2013-0065] GPU Nuclear Inc., Three Mile Island Nuclear Power Station, Unit 2, Exemption From Certain Security Requirements AGENCY: Nuclear...

  4. 75 FR 9623 - Arizona Public Service Company, et al.; Palo Verde Nuclear Generating Station, Units 1, 2, and 3...

    Science.gov (United States)

    2010-03-03

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

  5. 76 FR 24064 - Arizona Public Service Company, Palo Verde Nuclear Generating Station, Units 1, 2, and 3, Notice...

    Science.gov (United States)

    2011-04-29

    ... Service Company, Palo Verde Nuclear Generating Station, Units 1, 2, and 3, Notice of Issuance of Renewed... issued Renewed Facility Operating License Nos. NPF-41, NPF-51, and NPF-74 to Arizona Public Service Company (licensee), the operator of the Palo Verde Nuclear Generating Station, Units 1, 2, and 3 (PVNGS...

  6. 75 FR 15745 - Arizona Public Service Company, et al. Palo Verde Nuclear Generating Station, Units 1, 2, and 3...

    Science.gov (United States)

    2010-03-30

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

  7. 75 FR 8149 - Arizona Public Service Company, et al. Palo Verde Nuclear Generating Station, Units 1, 2, and 3...

    Science.gov (United States)

    2010-02-23

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

  8. Photovoltaic power stations in Germany and the United States: A comparative study by data envelopment analysis

    International Nuclear Information System (INIS)

    Sueyoshi, Toshiyuki; Goto, Mika

    2014-01-01

    This study compares Photovoltaic (PV) power stations between Germany and the United States to examine which country more efficiently provides renewable energy in their usages. For the comparative analysis, this study utilizes Data Envelopment Analysis (DEA) as a methodology to evaluate the performance of PV power stations from the perspective of both solar and land usages. A total of one hundred sixty PV power stations (eighty in Germany and eighty in the United States) are used for this comparison. The demand for sustainable energy and energy security has been rapidly increasing over the past decade because of concerns about environment and limited resources. PV solutions are one of many renewable technologies that are being developed to satisfy a recent demand of electricity. Germany is the world's top installer and consumer of PV power and the United States is one of the top five nations. Germany leads the way in installed PV capacity even though the nation has less solar resources and land area. Due to limited solar resources, low insolation and sunshine, and land area, the United States should have a clear advantage over Germany. However, the empirical result of this study exhibits that PV power stations in Germany operate more efficiently than those of the United States even if the latter has many solar and land advantages. The surprising result indicates that the United States has room for improvement when it comes to utilizing solar and land resources and needs to reform the solar policy. For such a purpose, Feed-In Tariff (FIT) may be an effective energy policy at the state level in the United States because the FIT provides investors such as utility companies and other types of energy firms with financial incentives to develop large PV power stations and generation facilities for other renewable energy. It may be true that the FIT is a powerful policy tool to promote PV and other renewable installation and support a reduction of an amount of greenhouse

  9. Corrective action decision document, Second Gas Station, Tonopah test range, Nevada (Corrective Action Unit No. 403)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-11-01

    This Corrective Action Decision Document (CADD) for Second Gas Station (Corrective Action Unit [CAU] No. 403) has been developed for the U.S. Department of Energy`s (DOE) Nevada Environmental Restoration Project to meet the requirements of the Federal Facility Agreement and Consent Order (FFACO) of 1996 as stated in Appendix VI, {open_quotes}Corrective Action Strategy{close_quotes} (FFACO, 1996). The Second Gas Station Corrective Action Site (CAS) No. 03-02-004-0360 is the only CAS in CAU No. 403. The Second Gas Station CAS is located within Area 3 of the Tonopah Test Range (TTR), west of the Main Road at the location of former Underground Storage Tanks (USTs) and their associated fuel dispensary stations. The TTR is approximately 225 kilometers (km) (140 miles [mi]) northwest of Las Vegas, Nevada, by air and approximately 56 km (35 mi) southeast of Tonopah, Nevada, by road. The TTR is bordered on the south, east, and west by the Nellis Air Force Range and on the north by sparsely populated public land administered by the Bureau of Land Management and the U.S. Forest Service. The Second Gas Station CAS was formerly known as the Underground Diesel Tank Site, Sandia Environmental Restoration Site Number 118. The gas station was in use from approximately 1965 to 1980. The USTs were originally thought to be located 11 meters (m) (36 feet [ft]) east of the Old Light Duty Shop, Building 0360, and consisted of one gasoline UST (southern tank) and one diesel UST (northern tank) (DOE/NV, 1996a). The two associated fuel dispensary stations were located northeast (diesel) and southeast (gasoline) of Building 0360 (CAU 423). Presently the site is used as a parking lot, Building 0360 is used for mechanical repairs of vehicles.

  10. Corrective action decision document, Second Gas Station, Tonopah test range, Nevada (Corrective Action Unit No. 403)

    International Nuclear Information System (INIS)

    1997-11-01

    This Corrective Action Decision Document (CADD) for Second Gas Station (Corrective Action Unit [CAU] No. 403) has been developed for the U.S. Department of Energy's (DOE) Nevada Environmental Restoration Project to meet the requirements of the Federal Facility Agreement and Consent Order (FFACO) of 1996 as stated in Appendix VI, open-quotes Corrective Action Strategyclose quotes (FFACO, 1996). The Second Gas Station Corrective Action Site (CAS) No. 03-02-004-0360 is the only CAS in CAU No. 403. The Second Gas Station CAS is located within Area 3 of the Tonopah Test Range (TTR), west of the Main Road at the location of former Underground Storage Tanks (USTs) and their associated fuel dispensary stations. The TTR is approximately 225 kilometers (km) (140 miles [mi]) northwest of Las Vegas, Nevada, by air and approximately 56 km (35 mi) southeast of Tonopah, Nevada, by road. The TTR is bordered on the south, east, and west by the Nellis Air Force Range and on the north by sparsely populated public land administered by the Bureau of Land Management and the U.S. Forest Service. The Second Gas Station CAS was formerly known as the Underground Diesel Tank Site, Sandia Environmental Restoration Site Number 118. The gas station was in use from approximately 1965 to 1980. The USTs were originally thought to be located 11 meters (m) (36 feet [ft]) east of the Old Light Duty Shop, Building 0360, and consisted of one gasoline UST (southern tank) and one diesel UST (northern tank) (DOE/NV, 1996a). The two associated fuel dispensary stations were located northeast (diesel) and southeast (gasoline) of Building 0360 (CAU 423). Presently the site is used as a parking lot, Building 0360 is used for mechanical repairs of vehicles

  11. 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

  12. 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.)

  13. Centrifugal Compressor Unit-based Heat Energy Recovery at Compressor Stations

    Directory of Open Access Journals (Sweden)

    V. S. Shadrin

    2016-01-01

    Full Text Available About 95% of the electricity consumed by air compressor stations around the world, is transformed into thermal energy, which is making its considerable contribution to global warming. The present article dwells on the re-use (recovery of energy expended for air compression.The article presents the energy analysis of the process of compressing air from the point of view of compressor drive energy conversion into heat energy. The temperature level of excess heat energy has been estimated in terms of a potential to find the ways of recovery of generated heat. It is shown that the temperature level formed by thermal energy depends on the degree of air compression and the number of stages of the compressor.Analysis of technical characteristics of modern equipment from leading manufacturers, as well as projects of the latest air compressor stations have shown that there are two directions for the recovery of heat energy arising from the air compression: Resolving technological problems of compressor units. The use of the excess heat generation to meet the technology objectives of the enterprise. This article examines the schematic diagrams of compressor units to implement the idea of heat recovery compression to solve technological problems: Heating of the air in the suction line during operation of the compressor station in winter conditions. Using compression heat to regenerate the adsorbent in the dryer of compressed air.The article gives an equity assessment of considered solutions in the total amount of heat energy of compressor station. Presented in the present work, the analysis aims to outline the main vectors of technological solutions that reduce negative impacts of heat generation of compressor stations on the environment and creating the potential for reuse of energy, i.e. its recovery.

  14. The decommissioning of commercial magnox gas cooled reactor power stations in the United Kingdom

    International Nuclear Information System (INIS)

    Holt, G.

    1998-01-01

    There are nine commercial Magnox gas-cooled reactor power stations in the United Kingdom. Three of these stations have been shutdown and are being decommissioning, and plans have also been prepared for the eventual decommissioning of the remaining operational stations. The preferred strategy for the decommissioning of the Magnox power stations has been identified as 'Safestore' in which the decommissioning activities are carried out in a number of steps separated by quiescent periods of care and maintenance. The final clearance of the site could be deferred for up to 135 years following station shutdown so as to obtain maximum benefit from radioactive decay. The first step in the decommissioning strategy is to defuel the reactors and transport all spent and new fuel off the site. This work has been completed at all three shutdown stations. Decommissioning work is continuing on the three sites and has involved activities such as dismantling, decontamination, recycling and disposal of some plant and structures, and the preparation of others for retention on the site for a period of care and maintenance. Significant experience has been gained in the practical application of decommissioning, with successful technologies and processes being identified for a wide range of activities. For example, large and small metallic and concrete structures, some with complex geometries, have been successfully decontaminated. Also, the reactors have been prepared for a long period of care and maintenance, with instrumentation and sampling systems having been installed to monitor their continuing integrity. All of this work has been done under careful safety, technical, and financial control. (author)

  15. WIND SPEED AND ATMOSPHERIC STABILITY TRENDS FOR SELECTED UNITED STATES SURFACE STATIONS

    Energy Technology Data Exchange (ETDEWEB)

    Buckley, R; Allen H. Weber, A

    2006-11-01

    Recently it has been suggested that global warming and a decrease in mean wind speeds over most land masses are related. Decreases in near surface wind speeds have been reported by previous investigators looking at records with time spans of 15 to 30 years. This study focuses on United States (US) surface stations that have little or no location change since the late 1940s or the 1950s--a time range of up to 58 years. Data were selected from 62 stations (24 of which had not changed location) and separated into ten groups for analysis. The group's annual averages of temperature, wind speed, and percentage of Pasquill-Gifford (PG) stability categories were fitted with linear least squares regression lines. The results showed that the temperatures have increased for eight of the ten groups as expected. Wind speeds have decreased for nine of the ten groups. The mean slope of the wind speed trend lines for stations within the coterminous US was -0.77 m s{sup -1} per century. The percentage frequency of occurrence for the neutral (D) PG stability category decreased, while that for the unstable (B) and the stable (F) categories increased in almost all cases except for the group of stations located in Alaska.

  16. Start-up test of Fukushima Daini Nuclear Power Station Unit No.3

    International Nuclear Information System (INIS)

    Inomata, Toshio; Umezu, Akira; Kajikawa, Makoto; Koibuchi, Hiroshi; Netsu, Nobuhiko.

    1986-01-01

    In Unit 3 of the Fukushima Nuclear Power Station II (daini), a BWR power plant of output 1,100 MW, commercial operation was started in June 1985. Its start-up test was finished successfully in about nine months. That is, new equipments introduced were demonstration tested. Though the items of testing are increased, the start-up test took short time, resulting in construction period only 54.7 months of the Unit 3, the shortest in the world. During the test, there was no scramming other than the planned. Described are the following: an outline of the Unit 3, the items of its improvement and standardization, including the new equipments, preparations for the start-up test, the start-up test and its evaluation. (Mori, K.)

  17. 78 FR 41425 - In the Matter of Duke Energy Carolinas, LLC; (Oconee Nuclear Station, Units 1, 2, and 3...

    Science.gov (United States)

    2013-07-10

    ...; EA-13-010] In the Matter of Duke Energy Carolinas, LLC; (Oconee Nuclear Station, Units 1, 2, and 3... Energy Carolinas, LLC, Oconee Nuclear Station, 7800 Rochester Highway, Seneca, SC 29672. Filing is... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY...

  18. Integrated base stations and a method of transmitting data units in a communications system for mobile devices

    NARCIS (Netherlands)

    Bosch, H.G.P.; Mullender, Sape J.; Narlikar, G.J.; Samuel, L.G.; Yagati, L.N.

    2006-01-01

    Integrated base stations and a method of transmitting data units in a communications system for mobile devices. In one embodiment, an integrated base station includes a communications processor having a protocol stack configured with a media access control layer and a physical layer.

  19. North Anna Power Station - Unit 1: Overview of steam generator replacement project activities

    International Nuclear Information System (INIS)

    Gettler, M.W.; Bayer, R.K.; Lippard, D.W.

    1993-01-01

    The original steam generators at Virginia Electric and Power Company's (Virginia Power) North Anna Power Station (NAPS) Unit 1 have experienced corrosion-related degradation that require periodic inspection and plugging of steam generator tubes to ensure their continued safe and reliable operation. Despite improvements in secondary water chemistry, continued tube degradation in the steam generators necessitated the removal from service of approximately 20.3 percent of the tubes by plugging, (18.6, 17.3, and 25.1 for steam generators A, B, and C, respectively). Additionally, the unit power was limited to 95 % during, its last cycle of operation. Projections of industry and Virginia Power experience indicated the possibility of mid-cycle inspections and reductions in unit power. Therefore, economic considerations led to the decision to repair the steam generators (i.e., replace the steam generator lower assemblies). Three new Model 51F Steam Generator lower assembly units were ordered from Westinghouse. Virginia Power contracted Bechtel Power Corporation to provide the engineering and construction support to repair the Unit 1 steam generators. On January 4, 1993, after an extended coastdown period, North Anna Unit 1 was brought off-line and the 110 day (breaker-to-breaker) Steam Generator Replacement Project (SGRP) outage began. As of this paper, the outage is still in progress

  20. Technical Specifications, Seabrook Station, Unit 1 (Docket No. 50-443). Appendix ''A'' to License No. NPF-56

    International Nuclear Information System (INIS)

    1986-10-01

    This report provides specifications for the Seabrook Station Unit 1 reactor concerning: safety limits and limiting safety settings; limiting conditions for operation and surveillance requirements; design features; and administrative controls

  1. 78 FR 77508 - Duke Energy Carolinas, LLC; William States Lee III Nuclear Station, Units 1 and 2; Combined...

    Science.gov (United States)

    2013-12-23

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Duke Energy Carolinas, LLC; William States Lee III Nuclear Station, Units 1 and 2; Combined Licenses Application Review AGENCY: Nuclear Regulatory Commission. ACTION: Final environmental impact...

  2. International Space Station (ISS) Orbital Replaceable Unit (ORU) Wet Storage Risk Assessment

    Science.gov (United States)

    Squire, Michael D.; Rotter, Henry A.; Lee, Jason; Packham, Nigel; Brady, Timothy K.; Kelly, Robert; Ott, C. Mark

    2014-01-01

    The International Space Station (ISS) Program requested the NASA Engineering and Safety Center (NESC) to evaluate the risks posed by the practice of long-term wet storage of ISS Environmental Control and Life Support (ECLS) regeneration system orbital replacement units (ORUs). The ISS ECLS regeneration system removes water from urine and humidity condensate and converts it into potable water and oxygen. A total of 29 ORUs are in the ECLS system, each designed to be replaced by the ISS crew when necessary. The NESC assembled a team to review the ISS ECLS regeneration system and evaluate the potential for biofouling and corrosion. This document contains the outcome of the evaluation.

  3. Investigation on Main Radiation Source at Operation Floor of Fukushima Daiichi Nuclear Power Station Unit 4

    Science.gov (United States)

    Hirayama, Hideo; Kondo, Kenjiro; Suzuki, Seishiro; Hamamoto, Shimpei; Iwanaga, Kohei

    2017-09-01

    Pulse height distributions were measured using a LaBr3 detector set in a 1 cm lead collimator to investigate main radiation source at the operation floor of Fukushima Daiichi Nuclear Power Station Unit 4. It was confirmed that main radiation source above the reactor well was Co-60 from the activated steam dryer in the DS pool (Dryer-Separator pool) and that at the standby area was Cs-134 and Cs-137 from contaminated buildings and debris at the lower floor. Full energy peak count rate of Co-60 was reduced about 1/3 by 12mm lead sheet placed on the floor of the fuel handling machine.

  4. Final environmental statement for Shoreham Nuclear Power Station, Unit 1: (Docket No. 50-322)

    International Nuclear Information System (INIS)

    1977-10-01

    The proposed action is the issuance of an Operating License to the Long Island Lighting Company (LILCO) for the startup and operation of the Shoreham Nuclear Power Station, Unit 1 (the plant) located on the north shore of Long Island, the State of New York, County of Suffolk, in the town of Brookhaven. The Shoreham station will employ a boiling-water reactor (BWR), which will operate at a thermal output of 2436 MW leading to a gross output of 846 MWe and a net output of about 820 MWe. The unit will be cooled by once-through flow of water from the Long Island Sound. One nuclear unit with a net capacity of 820 MWe will be added to the generating resources of the Long Island Lighting Company. This will have a favorable effect on reserve margins and provide a cost savings of approximately $62.1 million (1980 dollars) in production costs in 1980 if the unit comes on line as scheduled; additional cost savings will be realized in subsequent years. Approximately 100 acres (40 hectares) of the 500-acre (202-hectare) site of rural (mostly wooded) land owned by the applicant have been cleared. Most of this will be unavailable for other uses during at least the 40-year life of the plant. No offsite acreage has been or will be cleared. Land in the vicinity of the site has undergone some residential development that is typical for all of this area of Long Island. The operation of Shoreham Unit 1 will have insignificant impacts on this and other types of land uses in the vicinity of the site. 33 figs., 56 tabs

  5. Efficient erection of a piping unit in a nuclear power station

    International Nuclear Information System (INIS)

    Halstrick, V.; Peters, G.

    1986-01-01

    In consideration of the negative experience gathered in the past extensive project logistics are required for the erection of piping units in a nuclear power station in order to be able to recognize and master the numerous influences and different marginal conditions with reasonable certainty and at an early stage. The utilization of requirements from the analysis of experience for the conception of project management begins with the erection planning and results in check lists for the execution of erection. During production planning these check lists are verified for realization. Because of the extensive data, EDP-aided systems are applied for checking and controlling the flow of information and material. A dialogue-aided system is presented for project planning and controlling which enables a transparent and farsighted execution of a project. By means of comparable piping units it is demonstrated that due to the created controlling system a great success becomes obvious in relation to the past. (orig.) [de

  6. Simplified conversions between specific conductance and salinity units for use with data from monitoring stations

    Science.gov (United States)

    Schemel, Laurence E.

    2001-01-01

    The U.S. Geological Survey, Bureau of Reclamation, and the California Department of Water Resources maintain a large number of monitoring stations that record specific conductance, often referred to as “electrical conductivity,” in San Francisco Bay Estuary and the Sacramento-San Joaquin Delta. Specific conductance units that have been normalized to a standard temperature are useful in fresh waters, but conversion to salinity units has some considerable advantages in brackish waters of the estuary and Delta. For example, salinity is linearly related to the mixing ratio of freshwater and seawater, which is not the case for specific conductance, even when values are normalized to a standard temperature. The Practical Salinity Scale 1978 is based on specific conductance, temperature, and pressure measurements of seawater and freshwater mixtures (Lewis 1980 and references therein). Equations and data that define the scale make possible conversions between specific conductance and salinity values.

  7. Start-up tests of Kashiwazakikariwa Nuclear Power Station Unit No.2 and No.5

    International Nuclear Information System (INIS)

    Fueki, Kensuke; Aoki, Shiro; Tanaka, Yasuhisa; Yahagi, Kimitoshi

    1991-01-01

    The Kashiwazakikariwa Nuclear Power Station Units No.5 and No.2 started commercial operation on April 10 and September 28 of 1990 respectively. As the result of the application of the First and Second LWR Improvement and Standardization Program, the plants were designed aiming at improvement of reliability, operation, and maintenance while maintaining safety. Construction of the plants took 6.5 to 7 years for completion, during which period the last 10 months were spent for the start up tests program. Start up tests were carried out under deliberate management to assure that the plants can operate safely and steadily at the prescribed operating points, and the schedules and tests item modifications adopted in Unit No.2 and No.5 were verified under the start up tests program. (author)

  8. Development of a Power Electronics Unit for the Space Station Plasma Contactor

    Science.gov (United States)

    Hamley, John A.; Hill, Gerald M.; Patterson, Michael J.; Saggio, Joseph, Jr.; Terdan, Fred; Mansell, Justin D.

    1994-01-01

    A hollow cathode plasma contactor has been baselined as a charge control device for the Space Station (SS) to prevent deleterious interactions of coated structural components with the ambient plasma. NASA LeRC Work Package 4 initiated the development of a plasma contactor system comprised of a Power Electronics Unit (PEU), an Expellant Management Unit (EMU), a command and data interface, and a Plasma Contactor Unit (PCU). A breadboard PEU was designed and fabricated. The breadboard PEU contains a cathode heater and discharge power supply, which were required to operate the PCU, a control and auxiliary power converter, an EMU interface, a command and telemetry interface, and a controller. The cathode heater and discharge supplies utilized a push-pull topology with a switching frequency of 20 kHz and pulse-width-modulated (PWM) control. A pulse ignition circuit derived from that used in arcjet power processors was incorporated in the discharge supply for discharge ignition. An 8088 based microcontroller was utilized in the breadboard model to provide a flexible platform for controller development with a simple command/data interface incorporating a direct connection to SS Mulitplexer/Demultiplexer (MDM) analog and digital I/O cards. Incorporating this in the flight model would eliminate the hardware and software overhead associated with a 1553 serial interface. The PEU autonomously operated the plasma contactor based on command inputs and was successfully integrated with a prototype plasma contactor unit demonstrating reliable ignition of the discharge and steady-state operation.

  9. Second periodic safety review of Angra Nuclear Power Station, unit 1

    Energy Technology Data Exchange (ETDEWEB)

    Martins, Carlos F.O.; Crepaldi, Roberto; Freire, Enio M., E-mail: ottoncf@tecnatom.com.br, E-mail: emfreire46@gmail.com, E-mail: robcrepaldi@hotmail.com [Tecnatom do Brasil Engenharia e Servicos Ltda, Rio de Janeiro, RJ (Brazil); Campello, Sergio A., E-mail: sacampe@eletronuclear.gov.br [Eletrobras Termonuclear S.A. (ELETRONUCLEAR), Rio de Janeiro, RJ (Brazil)

    2015-07-01

    This paper describes the second Periodic Safety Review (PSR2-A1) of Angra Nuclear Power Station, Unit 1, prepared by Eletrobras Eletronuclear S.A. and Tecnatom do Brasil Engenharia e Servicos Ltda., during Jul.2013-Aug.2014, covering the period of 2004-2013. The site, in Angra dos Reis-RJ, Brazil, comprises: Unit 1, (640 MWe, Westinghouse PWR, operating), Unit 2 (1300 MWe, KWU/Areva, operating) and Unit 3 (1405 MWe, KWU/Areva, construction). The PSR2-A1 attends the Standards 1.26-Safety in Operation of Nuclear Power Plants, Brazilian Nuclear Regulatory Commission (CNEN), and IAEA.SSG.25-Periodic Safety Review of Nuclear Power Plants. Within 18 months after each 10 years operation, the operating organization shall perform a plant safety review, to investigate the evolution consequences of safety code and standards, regarding: Plant design; structure, systems and components behavior; equipment qualification; plant ageing management; deterministic and probabilistic safety analysis; risk analysis; safety performance; operating experience; organization and administration; procedures; human factors; emergency planning; radiation protection and environmental radiological impacts. The Review included 6 Areas and 14 Safety Parameters, covered by 33 Evaluations.After document evaluations and discussions with plant staff, it was generated one General and 33 Specific Guide Procedures, 33 Specific and one Final Report, including: Description, Strengths, Deficiencies, Areas for Improvement and Conclusions. An Action Plan was prepared by Electronuclear for the recommendations. It was concluded that the Unit was operated within safety standards and will attend its designed operational lifetime, including possible life extensions. The Final Report was submitted to CNEN, as one requisite for renewal of the Unit Permanent Operation License. (author)

  10. Damodar Valley Corporation, Chandrapura Unit 2 Thermal Power Station Residual Life Assessment Summary report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-02-01

    The BHEL/NTPC/PFC/TVA teams assembled at the DVC`s Chadrapura station on July 19, 1994, to assess the remaining life of Unit 2. The workscope was expanded to include major plant systems that impact the unit`s ability to sustain generation at 140 MW (Units 1-3 have operated at average rating of about 90 MW). Assessment was completed Aug. 19, 1994. Boiler pressure parts are in excellent condition except for damage to primary superheater header/stub tubes and economizer inlet header stub tubes. The turbine steam path is in good condition except for damage to LP blading; the spar rotor steam path is in better condition and is recommended for Unit 2. Nozzle box struts are severely cracked from the flame outs; the cracks should not be repaired. HP/IP rotor has surface cracks at several places along the steam seal areas; these cracks are shallow and should be machined out. Detailed component damage assessments for above damaged components have been done. The turbine auxiliary systems have been evaluated; cooling tower fouling/blockage is the root cause for the high turbine back pressure. The fuel processing system is one of the primary root causes for limiting unit capacity. The main steam and hot reheat piping systems were conservatively designed and have at least 30 years left;deficiencies needing resolution include restoration of insulation, replacement of 6 deformed hanger clamp/bolts, and adjustment of a few hanger settings. The cold reheat piping system is generally in good condition; some areas should be re-insulated and the rigid support clamps/bolts should be examined. The turbine extraction piping system supports all appeared to be functioning normally.

  11. 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...

  12. Analysis of internal events for the Unit 1 of the Laguna Verde nuclear power station

    International Nuclear Information System (INIS)

    Huerta B, A.; Aguilar T, O.; Nunez C, A.; Lopez M, R.

    1993-01-01

    This volume presents the results of the starter event analysis and the event tree analysis for the Unit 1 of the Laguna Verde nuclear power station. The starter event analysis includes the identification of all those internal events which cause a disturbance to the normal operation of the power station and require mitigation. Those called external events stay beyond the reach of this study. For the analysis of the Laguna Verde power station eight transient categories were identified, three categories of loss of coolant accidents (LOCA) inside the container, a LOCA out of the primary container, as well as the vessel break. The event trees analysis involves the development of the possible accident sequences for each category of starter events. Events trees by systems for the different types of LOCA and for all the transients were constructed. It was constructed the event tree for the total loss of alternating current, which represents an extension of the event tree for the loss of external power transient. Also the event tree by systems for the anticipated transients without scram was developed (ATWS). The events trees for the accident sequences includes the sequences evaluation with vulnerable nucleus, that is to say those sequences in which it is had an adequate cooling of nucleus but the remoting systems of residual heat had failed. In order to model adequately the previous, headings were added to the event tree for developing the sequences until the point where be solved the nucleus state. This process includes: the determination of the failure pressure of the primary container, the evaluation of the environment generated in the reactor building as result of the container failure or cracked of itself, the determination of the localization of the components in the reactor building and the construction of boolean expressions to estimate the failure of the subordinated components to an severe environment. (Author)

  13. Socio-economic impacts of nuclear generating stations: Crystal River Unit 3 case study

    International Nuclear Information System (INIS)

    Bergmann, P.A.

    1982-07-01

    This report documents a case study of the socio-economic impacts of the construction and operation of the Crystal River Unit 3 nuclear power station. It is part of a major post-licensing study of the socio-economic impacts at twelve nuclear power stations. The case study covers the period beginning with the announcement of plans to construct the reactor and ending in the period 1980 to 1981. The case study deals with changes in the economy, population, settlement patterns and housing, local government and public services, social structure, and public response in the study area during the construction/operation of the reactor. A regional modeling approach is used to trace the impact of construction/operation on the local economy, labor market, and housing market. Emphasis in the study is on the attribution of socio-economic impacts to the reactor or other causal factors. As part of the study of local public response to the construction/operation of the reactor, the effects of the Three Mile Island accident are examined

  14. CNSS plant concept, capital cost, and multi-unit station economics

    International Nuclear Information System (INIS)

    1984-07-01

    United Engineers and Constructors (UE and C) and the Babcock and Wilcox Company (B and W) have performed several studies over the last eight years related to small integral pressurized water reactors. These reactors include the 365 MWt (100 MWe) Consolidated Nuclear Steam Generator (CNSG) and the 1200 MWt Consolidated Nuclear Steam System (CNSS). The studies, mostly performed under contract to the Oak Ridge National Laboratory, have led to a 1250 MWt (400 MWe) Consolidated Nuclear Steam System (CNSS) plant concept, with unique design and cost features. This report contains an update of earlier studies of the CNSS reactor and balance-of-plant concept design, capital costs, and multi-unit plant economics incorporating recent design developments, improvements, and post-TMI-2 upgrades. The economic evaluation compares the total system economic impact of a phased, three stage 400 MWe CNSS implementation program, i.e., a three-unit station, to the installation of a single 1200 MWe Pressurized Water Reactor (PWR) into a typical USA utility system

  15. Summary of plant life management evaluation for Onagawa Nuclear Power Station Unit-1

    International Nuclear Information System (INIS)

    Nodate, Kazumi

    2014-01-01

    The Onagawa Nuclear Power Station Unit-1 (Onagawa NPS-1) began commercial operation on June 1, 1984, and has reached 30-year from starting of operation on June of 2014. To that end, we implemented the Plant Life Management (PLM) evaluation for Onagawa NPS-1 as our first experience. We decided on a Long-term Maintenance Management Policy from result of the evaluation, and then applied the Safety-Regulations change approval application on November 6, 2013 and its correcting application on April 16, 2014. Our application was approved on May 21, 2014 through investigation by the Nuclear Regulatory Agency. Also at implementation of the PLM evaluation, we considered effects of the Great East Japan Earthquake that occurred on March 11, 2011 against ageing phenomena. In this paper, we introduce summary of PLM evaluation for Onagawa NPS-1 and the evaluation that considered effects of the Great East Japan Earthquake. (author)

  16. Results of the 8th regular inspection of Unit 1 in the Shimane Nuclear Power Station

    International Nuclear Information System (INIS)

    1983-01-01

    The 8th regular inspection of Unit 1 in the Shimane Nuclear Power Station was carried out from May 22 to October 21, 1982. Inspection was made on the reactor proper, reactor cooling system, instrumentation/control system, radiation control facility, etc. By the examinations of external appearance, leakage, performance, etc., no abnormality was observed. In the regular inspection, personnel exposure dose was all below the permissible level. The works done during the inspection were the following: the improvement in the hydraulic system for control rod drive, the installation of barriers, leakage detectors and alarms, the improvement in concentrated liquid waste storage tanks and piping, the installation of the gas treatment system for emergency use, and containment vessel monitors, the improvement in monitoring posts and the installation of α-β dust and iodine monitors, stress corrosion cracking countermeasures. (Mori, K.)

  17. Draft environmental impact statement. River Bend Nuclear Power Station, Unit 1

    International Nuclear Information System (INIS)

    Anon.

    1980-01-01

    Federal financing of an undivided ownership interest of River Bend Nuclear Power Station Unit 1 on a 3293-acre site near St. Francisville, Louisiana is proposed in a supplement to the final environmental impact statement of September 1974. The facility would consist of a boiling-water reactor that would produce a maximum of 2894 megawatts (MW) of electrical power. A design level of 3015 MW of electric power could be realized at some time in the future. Exhaust steam would be cooled by mechanical cooling towers using makeup water obtained from and discharged to the Mississippi River. Power generated by the unit would be transmitted via three lines totaling 140 circuit miles traversing portions of the parishes of West Feliciana, East Feliciana, East Baton Rouge, West Baton Rouge, Pointe Coupee, and Iberville. The unit would help the applicant meet the power needs of rural electric consumers in the region, and the applicant would contribute significanlty to area tax base and employment rolls during the life of the unit. Construction related activities would disturb 700 forested acres on the site and 1156 acres along the transmission routes. Of the 60 cubic feet per second (cfs) taken from the river, 48 cfs would evaporate during the cooling process and 12 cfs would return to the river with dissolved solids concentrations increased by 500%. The terrace aquifer would be dewatered for 16 months in order to lower the water table at the building site, and Grants Bayou would be transformed from a lentic to a lotic habitat during this period. Fogging and icing due to evaporation and drift from the cooling towers would increase slightly. During the construction period, farming, hunting, and fishing on the site would be suspended, and the social infractructure would be stressed due to the influx of a maximum of 2200 workers

  18. Ring thermal shield piping modification at Pickering Nuclear Generating Station 'A' Unit 1

    International Nuclear Information System (INIS)

    Brown, R.; Cobanoglu, M.M.

    1995-01-01

    Each of the four Pickering Nuclear Generating Station A (PNGSA) CANDU units was constructed with its reactor and dump tank surrounded by a concrete Calandria Vault (CV). The Ring Thermal Shield (RTS) system at PNGSA units is a water cooled structure with internal cooling channels with the purpose of attenuating excessive heat flux from the calandria shell to the end shield rings and adjoining concrete (Figure 1). In newer CANDU units the reactor calandria vessel is surrounded by a large water filled shield tank which eliminates the requirement for the RTS system. The RTS structures are situated in the space between the calandria and the vault walls. Each RTS is assembled from eight flat sided carbon steel segments, tilted towards the calandria and supported from the end shield rings. Cooling water to the RTS is supplied by carbon steel cooling pipes with a portion of the pipe run embedded in the vault walls. Flow through each RTS is divided into two independent circuits, having an inlet and an outlet cooling line. There are four locations of RTS inlet and outlet cooling lines. The inlet lines are located at the bottom and the outlet lines at the top of the RTS. The 'L' shaped section of RTS inlet and outlet cooling lines, from the RTS waterbox to the start of embedded portion at the concrete wall, had become defective due to corrosion induced by excessive Moisture levels in the calandria vaults. An on-line leak sealing capability was developed and placed in service in all four PNGSA units. However, a leak found during the 1994 Unit 1 outage was too large,to seal with the current capability, forcing Ontario Hydro (OH) to develop a method to replace the corroded pipes. The repair project was subject to some lofty performance targets. All tools had to be able to withstand dose rates of up to 3000 Rem/hour. These tools, along with procedures and personnel had to successfully repair the RTS system within 6 months otherwise a costly outage extension would result. This

  19. Site preparation and excavation works for the foundation of station main building among construction works for No. 1 unit in Kashiwazaki-Kariwa Nuclear Pwer Station

    International Nuclear Information System (INIS)

    Ueyama, Koreyasu

    1982-01-01

    Tokyo Electric Power Co., Inc., is planning the nuclear power station of final capacity 8,000 MW (7 units) in the region spread over Kashiwazaki City and Kariwa Village in Niigata Prefecture. For No. 1 unit (1100 MWe BWR), the reactor installation license was obtained in September, 1977, the site preparation and road construction started in April, 1978, and harbour construction works started in August, 1979. The construction works are now at the peak, and the overall progressing rate as of the end of June, 1982, is about 51 %. The site is a hilly region of dune along the coast of the Sea of Japan, and No. 1 unit is located in the southern part of the site. This paper reports on the outline of the project, site preparation and excavation works for the foundation of the station main building. For the site preparation and the excavation works for the foundation the main building, the shape of slope cutting, the design of landslide-preventing wall for the vertical excavation for the reactor complex building, and the construction plan and the result are reported. For underground water impermeable wall works, its outline, groundwater condition, groundwater simulation analysis, the investigation of wall installation, the wall structure and construction are described in detail. Also the outline of the control of slope face measurement, the control standards and the measured results are reported. (Wakatsuki, Y.)

  20. Use of Physio-Hydrological Units for SMOS Validation at the Valencia Anchor Station Study Area

    Science.gov (United States)

    Millán-Scheiding, C.; Antolín, C.; Marco, J.; Soriano, M. P.; Torre, E.; Requena, F.; Carbó, E.; Cano, A.; Lopez-Baeza, E.

    2009-04-01

    The SMOS space mission will soil moisture over the continents and ocean surface salinity with the sufficient resolution to be used in global climate change studies. With the aim of validating SMOS land data and products at the Valencia Anchor Station site (VAS) in a Mediterranean Ecosystem area of Spain, we have designed a sample methodology using a subdivision of the landscape in environmental units related to the spatial variability of soil moisture (Millán-Scheiding, 2006; Lopez-Baeza, et al. 2008). These physio-hydrological units are heterogeneously structured entities which present a certain degree of internal uniformity of hydrological parameters. The units are delimited by integrating areas with the same physio-morphology, soil type, vegetation, geology and topography (Flugel, et al 2003; Millán-Scheiding et al, 2007). Each of these units presented over the same pedological characteristics, vegetation cover, and landscape position should have a certain degree of internal uniformity in its hydrological parameters and therefore similar soil moisture (SM). The main assumption for each unit is that the dynamical variation of the hydrological parameters within one unit should be minimum compared to the dynamics of another unit. This methodology will hopefully provide an effective sampling design consisting of a reduced number of measuring points, sparsely distributed over the area, or alternatively, using SM validation networks where each sampling point is located where it is representative of the mean soil moisture of a complete unit area. The Experimental Plan for the SMOS Validation Rehearsal Campaign at the VAS area of April-May 2008 used this environmental subdivision in the selection and sampling of over 21.000 soil moisture points in a control area of 10 x 10 km2. The ground measurements were carried out during 4 nights corresponding to a drying out period of the soil. The sampling consisted of 700 plots with 4 volumetric SM cylinders and 7 Delta-T Theta

  1. 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

  2. 75 FR 53985 - Arizona Public Service Company, et al., Palo Verde Nuclear Generating Station, Unit 3; Temporary...

    Science.gov (United States)

    2010-09-02

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

  3. 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

  4. 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

  5. 76 FR 52357 - Exelon Generation Company, LLC; PSEG Nuclear, LLC; Peach Bottom Atomic Power Station, Unit 3...

    Science.gov (United States)

    2011-08-22

    ... NRC Library at http://www.nrc.gov/reading-rm/adams.html . From this page, the public can gain entry... operation of the Peach Bottom Atomic Power Station (PBAPS), Unit 3, located in York and Lancaster Counties... from the NRC Library on the NRC Web site at http://www.nrc.gov/reading-rm/doc-collections/cfr/ . III...

  6. 76 FR 79228 - Combined Licenses at William States Lee III Nuclear Station Site, Units 1 and 2; Duke Energy...

    Science.gov (United States)

    2011-12-21

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Combined Licenses at William States Lee III Nuclear Station Site, Units 1 and 2; Duke Energy Carolinas, LLC AGENCY: Nuclear Regulatory Commission. ACTION: Draft environmental impact statement; public...

  7. 78 FR 6839 - Duke Energy Carolinas, LLC, Oconee Nuclear Station, Units 1, 2, and 3 Denial of Amendment to...

    Science.gov (United States)

    2013-01-31

    ... From the Federal Register Online via the Government Publishing Office ] NUCLEAR REGULATORY COMMISSION Duke Energy Carolinas, LLC, Oconee Nuclear Station, Units 1, 2, and 3 Denial of Amendment to Facility Operating License AGENCY: Nuclear Regulatory Commission. ACTION: Denial; opportunity to request a...

  8. Conformance to Regulatory Guide 1.97, Beaver Valley Power Station, Unit No. 2 (Docket No. 50-412)

    International Nuclear Information System (INIS)

    Stoffel, J.W.; Udy, A.C.

    1985-11-01

    This EG and G Idaho, Inc., report reviews the submittals for Regulatory Guide 1.97 for Unit No. 2 of the Beaver Valley Power Station and identifies areas of nonconformance to the regulatory guide. Exceptions to Regulatory Guide 1.97 are evaluated and those areas where sufficient basis for acceptability is not provided are identified

  9. Technical Specifications, Seabrook Station, Unit 1 (Docket No. 50-443): Appendix ''A'' to License No. NPF-67

    International Nuclear Information System (INIS)

    1989-05-01

    The Seabrook Station, Unit 1 Technical Specifications were prepared by the US Nuclear Regulatory Commission to set forth the limits, operating conditions, and other requirements applicable to a nuclear reactor facility as set forth in Section 50.36 of 10 CFR Part 50 for the protection of the health and safety of the public

  10. 78 FR 79017 - Zion Solutions, LLC; Zion Nuclear Power Station, Units 1 and 2; Exemption From Certain Physical...

    Science.gov (United States)

    2013-12-27

    ... COMMISSION Zion Solutions, LLC; Zion Nuclear Power Station, Units 1 and 2; Exemption From Certain Physical... shut down facility and responsibility for its decommissioning was transferred to ZionSolutions (ZS), a subsidiary of EnergySolutions. ZS was established solely for the purpose of acquiring and decommissioning the...

  11. 77 FR 35079 - License Renewal Application for Seabrook Station, Unit 1 ; NextEra Energy Seabrook, LLC

    Science.gov (United States)

    2012-06-12

    ... NUCLEAR REGULATORY COMMISSION [Docket No. 50-443; NRC-2010-0206] License Renewal Application for Seabrook Station, Unit 1 ; NextEra Energy Seabrook, LLC AGENCY: Nuclear Regulatory Commission. ACTION: License renewal application; intent to prepare supplement to draft [[Page 35080

  12. 78 FR 29158 - In the Matter of Zion Solutions, LLC; Zion Nuclear Power Station, Units 1 and 2; Order Approving...

    Science.gov (United States)

    2013-05-17

    ... and DPR-48] In the Matter of Zion Solutions, LLC; Zion Nuclear Power Station, Units 1 and 2; Order... formed for the purpose of acquiring ES, Inc. and is held by certain investment fund entities organized by... Environmental Management Programs, in writing, of such receipt no later than one (1) business day prior to the...

  13. Results of the 4th regular inspection in Unit 1 of the Mihama Nuclear Power Station

    International Nuclear Information System (INIS)

    1981-01-01

    The 4th regular inspection of Unit 1 in the Mihama Nuclear Power Station was made from July, 1975, to December, 1980, on its reactor and associated facilities. The respective stages of inspection during the years are described. The inspection by external appearance examination, disassembling leakage inspection and performance tests indicated crackings in piping for fuel-replacement water tank, the container penetration of recirculation pipe for residual-heat removal, and main steam-relief valve, and leakage in one fuel assembly. Radiation exposure of the personnel during the inspection was less than the permissible dose. Radiation exposure data for the personnel are given in tables. The improvements and repairs done accordingly were as follows: reapir of the piping for a fuel-replacement tank and recirculation piping for residual-heat removal, replacement of the main steam-relief valve, plugging of heating tubes for the steam-generator, replacement of pins and covers for control-rod guide pipes, improvement of safety protection system and installation of rare gas monitor. (J.P.N.)

  14. Data book of examination of the ruptured pipe at the Hamaoka Nuclear Power Station Unit-1

    International Nuclear Information System (INIS)

    2002-03-01

    In order to investigate root cause of the pipe rupture, which took place at the Hamaoka Nuclear Power Station Unit-1 of Chubu Electric Power Company on November 7, 2001, a task force was established within the Nuclear and Industrial Safety Agency (NISA) and initiated a detailed investigation of the ruptured pipe. The Japan Atomic Energy Research Institute (JAERI) was asked from the Ministry of Education, Culture, Sports, Science and Technology (MEXT) in response to the request from NISA to cooperate as an independent neutral organization with NISA and perform an examination of the ruptured pipe independently from Chubu Electric Power Company. JAERI accepted the request by considering the fact that JAERI is an integrated research institution for nuclear research and development, a prime research institution for nuclear safety research, a research institution with experience of root-cause investigation of various nuclear incidents and accidents of domestic as well as overseas, and a research institution provided with advanced examination facilities necessary for examination of the ruptured pipe. The JAERI examination group was formed at the Tokai Research Establishment and conducted detailed and thorough examination of the pieces taken from the ruptured pipe primarily in the Reactor Fuel Examination Facility (RFEF) with the use of tools such as scanning electron microscopes and other equipments. Purpose of examination was to provide technical information in order to identify causes of the pipe rupture through examination of the pieces taken from the ruptured region of the pipe. The result of the present examination has already been reported to NISA and has also been published as the JAERI-Tech report No.2001-94. This report is a data book containing the detailed data obtained by the present examination. (author)

  15. Inversion of Multi-Station Schumann Resonance Background Records for Global Lightning Activity in Absolute Units

    Science.gov (United States)

    Williams, E. R.; Mushtak, V. C.; Guha, A.; Boldi, R. A.; Bor, J.; Nagy, T.; Satori, G.; Sinha, A. K.; Rawat, R.; Hobara, Y.; Sato, M.; Takahashi, Y.; Price, C. G.; Neska, M.; Alexander, K.; Yampolski, Y.; Moore, R. C.; Mitchell, M. F.; Fraser-Smith, A. C.

    2014-12-01

    Every lightning flash contributes energy to the TEM mode of the natural global waveguide that contains the Earth's Schumann resonances. The modest attenuation at ELF (0.1 dB/Mm) allows for the continuous monitoring of the global lightning with a small number of receiving stations worldwide. In this study, nine ELF receiving sites (in Antarctica (3 sites), Hungary, India, Japan, Poland, Spitsbergen and USA) are used to provide power spectra at 12-minute intervals in two absolutely calibrated magnetic fields and occasionally, one electric field, with up to five resonance modes each. The observables are the extracted modal parameters (peak intensity, peak frequency and Q-factor) for each spectrum. The unknown quantities are the geographical locations of three continental lightning 'chimneys' and their lightning source strengths in absolute units (C2 km2/sec). The unknowns are calculated from the observables by the iterative inversion of an evolving 'sensitivity matrix' whose elements are the partial derivatives of each observable for all receiving sites with respect to each unknown quantity. The propagation model includes the important day-night asymmetry of the natural waveguide. To overcome the problem of multiple minima (common in inversion problems of this kind), location information from the World Wide Lightning Location Network has been used to make initial guess solutions based on centroids of stroke locations in each chimney. Results for five consecutive days in 2009 (Jan 7-11) show UT variations with the African chimney dominating on four of five days, and America dominating on the fifth day. The amplitude variations in absolute source strength exceed that of the 'Carnegie curve' of the DC global circuit by roughly twofold. Day-to-day variations in chimney source strength are of the order of tens of percent. Examination of forward calculations performed with the global inversion solution often show good agreement with the observed diurnal variations at

  16. AECL's participation in the commissioning of Point Lepreau generating station unit 1

    International Nuclear Information System (INIS)

    Chawla, S.; Singh, K.; Yerramilli, S.

    1983-05-01

    Support from Atomic Energy of Canada Ltd. (AECL) to Point Lepreau during the commissioning program has been in the form of: seconded staff for commissioning program management, preparation of commissioning procedures, and hands-on commissioning of several systems; analysis of test results; engineering service for problem solving and modifications; design engineering for changes and additions; procurement of urgently-needed parts and materials; technological advice; review of operational limits; interpretation of design manuals and assistance with and preparation of submissions to regulatory authorities; and development of equipment and procedures for inspection and repairs. This, together with AECL's experience in the commissioning of other 600 MWe stations, Douglas Point and Ontario Hydro stations, provides AECL with a wide range of expertise for providing operating station support services for CANDU stations

  17. 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

  18. 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

  19. 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

  20. 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

  1. Dresden Nuclear Power Station, Unit No. 1: Primary cooling system chemical decontamination: Draft environmental statement (Docket No. 50-10)

    International Nuclear Information System (INIS)

    1980-05-01

    The staff has considered the environmental impact and economic costs of the proposed primary cooling system chemical decontamination at Dresden Nuclear Power Station, Unit 1. The staff has focused this statement on the occupational radiation exposure associated with the proposed Unit 1 decontamination program, on alternatives to chemical decontamination, and on the environmental impact of the disposal of the solid radioactive waste generated by this decontamination. The staff has concluded that the proposed decontamination will not significantly affect the quality of the human environment. Furthermore, any impacts from the decontamination program are outweighed by its benefits. 2 figs., 7 tabs

  2. International Space Station (ISS) Plasma Contactor Unit (PCU) Utilization Plan Assessment Update

    Science.gov (United States)

    Hernandez-Pellerano, Amri; Iannello, Christopher J.; Garrett, Henry B.; Ging, Andrew T.; Katz, Ira; Keith, R. Lloyd; Minow, Joseph I.; Willis, Emily M.; Schneider, Todd A.; Whittlesey, Edward J.; hide

    2014-01-01

    The International Space Station (ISS) vehicle undergoes spacecraft charging as it interacts with Earth's ionosphere and magnetic field. The interaction can result in a large potential difference developing between the ISS metal chassis and the local ionosphere plasma environment. If an astronaut conducting extravehicular activities (EVA) is exposed to the potential difference, then a possible electrical shock hazard arises. The control of this hazard was addressed by a number of documents within the ISS Program (ISSP) including Catastrophic Safety Hazard for Astronauts on EVA (ISS-EVA-312-4A_revE). The safety hazard identified the risk for an astronaut to experience an electrical shock in the event an arc was generated on an extravehicular mobility unit (EMU) surface. A catastrophic safety hazard, by the ISS requirements, necessitates mitigation by a two-fault tolerant system of hazard controls. Traditionally, the plasma contactor units (PCUs) on the ISS have been used to limit the charging and serve as a "ground strap" between the ISS structure and the surrounding ionospheric plasma. In 2009, a previous NASA Engineering and Safety Center (NESC) team evaluated the PCU utilization plan (NESC Request #07-054-E) with the objective to assess whether leaving PCUs off during non-EVA time periods presented risk to the ISS through assembly completion. For this study, in situ measurements of ISS charging, covering the installation of three of the four photovoltaic arrays, and laboratory testing results provided key data to underpin the assessment. The conclusion stated, "there appears to be no significant risk of damage to critical equipment nor excessive ISS thermal coating damage as a result of eliminating PCU operations during non- EVA times." In 2013, the ISSP was presented with recommendations from Boeing Space Environments for the "Conditional" Marginalization of Plasma Hazard. These recommendations include a plan that would keep the PCUs off during EVAs when the

  3. Research at United States Antarctic stations during the International Magnetosphere Study

    International Nuclear Information System (INIS)

    Rosenberg, T.J.

    1982-01-01

    During the International Magnetospheric Study (IMS) the U.S. operated programs at McMurdo, Siple, South Pole, and Palmer stations and at the Soviet Vostok station. Details concerning measurement locations are considered, and program summaries are provided. The programs are related to the study of geomagnetic variations, magnetic pulsations in the polar cap, cosmic noise absorption, VLF radio waves, auroral photometry, the morphology and dynamics of visible auroral forms, cosmic ray intensity variations, and auroral infrasonic waves. One program is based on the utilization of VHF Doppler auroral radar

  4. Considerations for increasing unit 1 spent fuel pool capacity at the Laguna Verde station

    International Nuclear Information System (INIS)

    Vera, A.

    1992-01-01

    To increase the spent fuel storage capacity at the Laguna Verde Station in a safe and economical manner and assure a continuous operation of the first Mexican Nuclear Plant, Comision Federal de Electricidad (CFE), the Nation's Utility, seeked alternatives considering the overall world situation, the safety and licensing aspects, as well as the economics and the extent of the nuclear program of Mexico. This paper describes the alternatives considered, their evaluation and how the decision taken by CFE in this field, provides the Laguna Verde Station with a maximum of 37 years storage capacity plus full core reserve

  5. System Definition Document: Reactor Data Necessary for Modeling Plutonium Disposition in Catawba Nuclear Station Units 1 and 2

    International Nuclear Information System (INIS)

    Ellis, R.J.

    2000-01-01

    The US Department of Energy (USDOE) has contracted with Duke Engineering and Services, Cogema, Inc., and Stone and Webster (DCS) to provide mixed-oxide (MOX) fuel fabrication and reactor irradiation services in support of USDOE's mission to dispose of surplus weapons-grade plutonium. The nuclear station units currently identified as mission reactors for this project are Catawba Units 1 and 2 and McGuire Units 1 and 2. This report is specific to Catawba Nuclear Station Units 1 and 2, but the details and materials for the McGuire reactors are very similar. The purpose of this document is to present a complete set of data about the reactor materials and components to be used in modeling the Catawba reactors to predict reactor physics parameters for the Catawba site. Except where noted, Duke Power Company or DCS documents are the sources of these data. These data are being used with the ORNL computer code models of the DCS Catawba (and McGuire) pressurized-water reactors

  6. Advanced control and instrumentation systems for Fukushima Dai-ni nuclear power station unit No.4

    International Nuclear Information System (INIS)

    Kimura, Masatoshi; Asami, Kazuo; Miyake, Masao; Murata, Fumio; Akita, Akira.

    1988-01-01

    Now 20 years have elapsed since BWR nuclear power stations were introduced in Japan, and by many research and development and technical innovation, Japanese nuclear power stations have been stably operated at the high rate of operation foremost in the world. In the latest measurement and control system, in order to realize the high reliability and controllability of operation required for nuclear power plants, the new products freely using digital technology and optical multiple transmission technology have been put in practical use, and by applying those to actual plants, the very good results have been obtained. In this paper, the newest and most excellent measurement and control system which was put in practical use for No.4 plant in Fukushima No.2 Nuclear Power Station, which was constructed by Hitachi Ltd. as the main contractor, is generally reported. In the measurement and control techniques for nuclear power stations, the further improvement of operational reliability, the rate of operation and maintainability based on the new man-machine system has been demanded, and in order to meet these needs, Hitachi Ltd. positively developed all the aspects of operational handling, control, watch and transmission by general technical innovation. The new NUCAMM-80, NURECS, HIPLEX and other system are described. (Kako, I.)

  7. Surry Power Station, Units 1 and 2. Semiannual operating report, January--June 1975

    International Nuclear Information System (INIS)

    1975-01-01

    Net electric power generated by Unit 1 was 2,315,124 MWH(e) and Unit 2 generated 2,062,954 MWH(e) with Unit 1 generator on line for 3,157.8 hrs and Unit 2 on line for 2,881.2 hrs. Information is presented concerning power generation, shutdowns, corrective maintenance, chemistry and radiochemistry, occupational radiation exposure, release of radioactive materials, abnormal occurrences, and environmental monitoring. (FS)

  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. 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

  10. The competitive economics of a middle aged multi unit nuclear generating station

    International Nuclear Information System (INIS)

    Talbot, K.H.

    1994-01-01

    In 1992 Ontario Hydro's 15 year old 4 x 850 MWe Candu, Bruce A Nuclear Generating Station was predicted to need considerable capital investment to replace pressure tubes, steam generators and other prematurely ageing equipment in order to restore the station to high performance. Over the subsequent two years the station has undergone 2 major economic assessment studies which have confirmed the economic viability of continued operation of the plant. Declining demand for electricity in Ontario combined with a excess of generating capacity and a need to stabilise electricity rates have however forced significant operational cost reductions and reduced capital availability for rehabilitation work, it's medium and long term future remains in question. This presentation offers a practical illustration of the need to maintain steady high performance from nuclear generating plant via the appropriate life management techniques. The avoidance of mid life infusion of capital is considered as essential if nuclear generation is to successfully survive major changes in economic conditions. 2 tabs., 7 figs

  11. 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

  12. Technical Specifications, Braidwood Station, Unit Nos. 1 and 2 (Docket Nos. STN 50-456 and STN 50-457). Appendix ''A'' to License No. NPF-59

    International Nuclear Information System (INIS)

    1986-10-01

    Information is presented for Braidwood Station Unit Nos. 1 and 2 in the areas of: safety limits and limiting safety system settings; limiting conditions for operation and surveillance requirements; design features; and administrative controls

  13. POLLUTION PREVENTION OPPORTUNITY ASSESSMENT UNITED STATES ARMY CORPS OF ENGINEERS PITTSBURGH ENGINEER WAREHOUSE AND REPAIR STATION AND EMSWORTH LOCKS AND DAMS PITTSBURGH, PENNSYLVANIA

    Science.gov (United States)

    This report summarizes work conducted at the United States Army Corps of Engineers (USACE) Pittsburgh Engineering Warehouse and Repair Station (PEWARS) and Emsworth Locks and Dams in Pittsburgh, Pennsylvania under the U.S. Environmental Protection Agency's (EPA's) Waste Reduction...

  14. Damage of the Unit 1 reactor building overhead bridge crane at Onagawa Nuclear Power Station caused by the Great East Japan Earthquake and its repair works

    International Nuclear Information System (INIS)

    Sugamata, Norihiko

    2014-01-01

    The driving shaft bearings of the Unit 1 overhead bridge crane were damaged by the Great East Japan Earthquake at Onagawa Nuclear Power Station. The situation, investigation and repair works of the bearing failure are introduced in this paper. (author)

  15. Conformance to Regulatory Guide 1.97, Comanche Peak Steam Electric Station, Unit Nos. 1 and 2 (Docket Nos. 50-445 and 50-446)

    International Nuclear Information System (INIS)

    Udy, A.C.

    1985-03-01

    This EG and G Idaho, Inc. report reviews the submittals for the Comanche Peak Steam Electric Station, Unit Nos. 1 and 2, and identifies areas of conformance to Regulatory Guide 1.97. Any exceptions to these guidelines are evaluated

  16. Management of main generator condition during long term plant shut down at Higashidori Nuclear Power Station Unit 1

    International Nuclear Information System (INIS)

    Kato, Seiji

    2014-01-01

    Higashidori Nuclear Power Station Unit 1 shut down on February 6, 2011 to start 4th refuel outage. On March 11, 2011, we keep going refuel outage on this moment a large earthquake occurred and tsunami was generated following it which called 'Great East Japan Earthquake'. Refuel outage takes 3 ∼ 5 months normally but Higashidori NPS still keeping shut down over 3 years due to some issues. In this paper, we introduce about management of Main generator condition during long term plant shut down situation in addition to normal plant shut down situation to keep well. (author)

  17. 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

  18. 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

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

    International Nuclear Information System (INIS)

    1987-08-01

    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

  20. 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

  1. 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

  2. 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

  3. Technical evaluation of RETS-required reports for Rancho Seco Nuclear Generating Station, Unit 1 for 1983

    International Nuclear Information System (INIS)

    Magleby, E.H.; Young, T.E.

    1985-01-01

    A review of the reports required by Federal regulations and the plant-specific Radiological Effluent Technical Specifications (RETS) for operations conducted during 1983 was performed. The periodic reports reviewed for the Rancho Seco Nuclear Generating Station, Unit 1 were the Semiannual Effluent Release Report, January 1, 1983 to June 30, 1983 and the Radiation Exposure, Environmental Protection, Effluent and Waste Disposal Report. The principal review guidelines were the plant's specific RETS which were based on NRC guidance given in NUREG-0133, ''Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants.'' The Licensee's submitted reports were found to be reasonably complete and consistent with the review guidelines

  4. Quad-Cities Station, Units 1 and 2. Annual operating report for 1976

    International Nuclear Information System (INIS)

    1976-01-01

    Net electrical power generated by Unit 1 was 3,393,062 MWH with the generator on line 5,703.0 hrs. Unit 2 generated 4,304,684 MWH with the generator on line 7,145.3 hrs. Information is presented concerning modifications, maintenance, power generation, shutdowns, occupational radiation exposures, and organization

  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. TMI-related retrofits for Maanshan Nuclear Power Station units 1 and 2

    International Nuclear Information System (INIS)

    Ketelsen, S.C.; Shinbrot, C.H.; Viger, J.R.

    1984-01-01

    This paper presents a review of several TMIrelated retrofit designs, under the purview of the Engineer, that were initiated for the Maanshan Nuclear Power Station in response to NUREG 0737. The NUREG 0737 items discussed herein include: post-Accident Sampling Capability, instrumentation for Detection of Inadequate Core Cooling, Reactor Coolant System Vents, Post-Accident Radiation and Shielding Design Review, Direct Indication of Relief and Safety Valve Position, Post-Accident Radiation Monitors, Containment Wide-Range Pressure Monitors, Containment Water Level Monitors, and Containment Hydrogen Monitor

  7. 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

  8. 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, terrestrial- and aquatic-ecological impacts, and air-quality impacts will be small. Steam fog from the station's cooling lake has the potential for reducing visibility over nearby roads and bridges. A fog-monitoring program for nearby roads and bridges 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 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. 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

  9. 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

  10. 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

  11. Browns Ferry Nuclear Power Station, Units 1, 2, and 3. Semiannual report, January--June 1975

    International Nuclear Information System (INIS)

    1975-01-01

    Browns Ferry units 1 and 2 operated at maximum power from January 1 to March 22 except as limited by thermal margins, fuel preconditioning, optimum power shape, maintenance, and Unit 2 start-up tests. On March 22 a cable tray fire started causing spurious starting of equipment due to faulted control cables. The reactors were manually scrammed and placed in cold shutdown for fire investigation, clean up, and fuel removal. Information is also presented concerning maintenance, radiochemistry, occupational radiation exposure, release of radioactive materials, and non-radiological environmental monitoring

  12. 77 FR 41814 - Entergy Operations, Inc.; Grand Gulf Nuclear Station, Unit 1

    Science.gov (United States)

    2012-07-16

    ... evaporation, the EPU is not introducing any new contaminants or pollutants and is not increasing the amount of those potential contaminants presently allowed for release by GGNS Unit 1. Chemical and biocide wastes... emergent marsh wetlands. As stated above, the groundwater in the alluvium in the floodplain is in close...

  13. Combined Solar Charging Stations and Energy Storage Units Allocation for Electric Vehicles by Considering Uncertainties

    DEFF Research Database (Denmark)

    Yousefi Khanghah, Babak; Anvari-Moghaddam, Amjad; Guerrero, Josep M.

    2017-01-01

    , maximizes the benefit of CSs owners and minimizes the power loss, load demand and voltage sags during peak times considering different technical constraints. The optimization variables are the location and capacity of solar units and energy storage systems. In this paper, charge-discharge process of EVs...

  14. Indian Point Station, Units 1 and 2. Annual operations report No. 25, 1975

    International Nuclear Information System (INIS)

    1976-01-01

    Indian Point-1 Reactor remained in the shutdown condition in compliance with NRC's IAC for ECCS. Unit 2 generated 4,889,038 MWH(e) and was on line 8,323.1 hrs. Information is presented concerning operation, maintenance, occupational personnel radiation protection, primary coolant chemistry, abnormal occurrences, changes, tests, and experiments

  15. Construction and start-up testing experience of Kashiwazakikariwa Nuclear Power Station Unit No.1

    International Nuclear Information System (INIS)

    Natsume, Nobuo; Murakami, Hideaki

    1986-01-01

    In order to overcome the new location condition in Japan Sea coast, new techniques were developed and adopted to ensure the safety in construction and to shorten the construction period as far as possible. The commercial operation was started on September 18, 1985. This plant is a BWR plant of 1100 MWe output. The results of the improvement and standardization of BWRs and the measures for reliability improvement and radiation dose reduction were fully adopted in this plant. The site of the power station and the layout of the main facilities are explained. As the features of the location condition, the severe weather condition in winter such as snow, wind and lightning and high waves in the sea were considered. The rockbed for installing the foundation of the reactor building was deep, and the aseismatic design condition was made stricter, accordingly, the quantity of materials increased. A tent dome was developed to cover above the reactor containment vessel being assembled, a lightning forecast system was installed, and synchro-lift method was adopted for caisson breakwaters. The countermeasures to the deep rockbed and the measures to shorten the construction period were taken. The results of the trial operation are reported. (Kako, I.)

  16. Analysis of core damage frequency: Surry Power Station, Unit 1 external events

    International Nuclear Information System (INIS)

    Bohn, M.P.; Lambright, J.A.; Daniel, S.L.; Johnson, J.J.; Ravindra, M.K.; Hashimoto, P.O.; Mraz, M.J.; Tong, W.H.

    1990-12-01

    This report presents the analysis of external events (earthquakes, fires, floods, etc.) performed for the Surry Power Station as part of the USNRC-sponsored NUREG-1150 program. Both the internal and external events analyses make full use of recent insights and developments in risk assessment methods. In addition, the external event analyses make use of newly-developed simplified methods. As a first step, a screening analysis was performed which showed that all external events were negligible except for fires and seismic events. Subsequent detailed analysis of fires resulted in a total (mean) core damage frequency of 1.13E-5 per year. The seismic analysis resulted in a total (mean) core damage frequency of 1.16E-4 per year using hazard curves developed by Lawrence Livermore National Laboratory and 2.50E-5 per year using hazard curves developed by the Electric Power Research Institute. Uncertainty analyses were performed, and dominant components and sources of uncertainty were identified. 71 refs., 61 figs., 59 tabs

  17. Analysis of internal events for the Unit 1 of the Laguna Verde Nuclear Power Station. Appendixes

    International Nuclear Information System (INIS)

    Huerta B, A.; Lopez M, R.

    1995-01-01

    This volume contains the appendices for the accident sequences analysis for those internally initiated events for Laguna Verde Unit 1, Nuclear Power Plant. The appendix A presents the comments raised by the Sandia National Laboratories technical staff as a result of the review of the Internal Event Analysis for Laguna Verde Unit 1 Nuclear Power Plant. This review was performed during a joint Sandia/CNSNS multi-day meeting by the end 1992. Also included is a brief evaluation on the applicability of these comments to the present study. The appendix B presents the fault tree models printed for each of the systems included and analyzed in the Internal Event Analysis for LVNPP. The appendice C presents the outputs of the TEMAC code, used for the cuantification of the dominant accident sequences as well as for the final core damage evaluation. (Author)

  18. Analysis of internal events for the Unit 1 of the Laguna Verde Nuclear Power Station. Appendixes

    International Nuclear Information System (INIS)

    Huerta B, A.; Lopez M, R.

    1995-01-01

    This volume contains the appendices for the accident sequences analysis for those internally initiated events for Laguna Verde Unit 1, Nuclear Power Plant. The appendix A presents the comments raised by the Sandia National Laboratories technical staff as a result of the review of the Internal Event Analysis for Laguna Verde Unit 1 Nuclear Power Plant. This review was performed during a joint Sandia/CNSNS multi-day meeting by the end 1992. Also included is a brief evaluation on the applicability of these comments to the present study. The appendix B presents the fault tree models printed for each of the systems included and.analyzed in the Internal Event Analysis for LVNPP. The appendice C presents the outputs of the TEMAC code, used for the cuantification of the dominant accident sequences as well as for the final core damage evaluation. (Author)

  19. Palo Verde Generating Station, Units 4 and 5. License application, general information

    International Nuclear Information System (INIS)

    1978-01-01

    A license application for two more Palo Verde reactors, Units 4 and 5, is presented. The two PWR reactors have a nominal net generating power each of 1,270 MW(e). Containments are steel-lined prestressed cylindrical structures with hemispherical domes. The reactors are replicas of Palo Verde 1, 2 and 3 (see DOCKETS 50528, 50529 and 50530) using the standard Combustion Engineering System 80 (see DOCKET-STN-50470)

  20. Marble Hill Nuclear Generating Station, Units 1 and 2. License application, PSAR, general information

    International Nuclear Information System (INIS)

    1975-01-01

    An application is presented for two PWR reactors to be constructed in Salud Township, Jefferson County, Indiana, about six miles northeast of New Washington on the Ohio River. Each unit will have a rated core power level of 3411 MW(t) with a corresponding electrical output of 1130 MW(e). Mechanical draft cooling towers will be provided. The facility, which will replicate the Byron facility will be employed for the generation of electricity for transmission, sale for resale, and distribution

  1. Fulton Generating Station Units 1 and 2 (Docket Nos. 50-463 and 50-464): Final environmental statement

    International Nuclear Information System (INIS)

    1975-04-01

    The proposed action is the issuance of construction permits to the Philadelphia Electric Company for the construction of the Fulton Generating Station, Units 1 and 2, located in Fulton and Drumore Townships, Lancaster County, Pennsylvania. Makeup water for cooling will be withdrawn form Conowingo Pond at a maximum rate of 43,000 gpm. The dissolved solids content of the blowdown water will be increased by a factor of about two. The remainder of the water will be evaporated to the atmosphere by cooling towers. About 10 acres offsite, some 7 acres of which is woodland, will be used for railroad-spur construction. About 0.25 mile of new transmission-line rights-of-way (9 acres) will be needed, although 49 miles of new transmission line, which will require about 3 miles of selective clearing, will be constructed on existing rights-of-way. An unestablished amount of land will be used for access-road construction, but the applicant will use existing roadway corridors where feasible. A small loss of consumer species will result from loss of habitat. Some loss of benthic and pelagic organisms in Conowingo Pond will be caused by intake and discharge construction. The Station's thermal and chemical discharges will meet the State water-quality standards. The duration of additional ground-level fog caused by Station operation is expected to be less than 3 hr/year. (Sect. 5.3.3). No observable effects are expected from salt deposition from cooling-tower drift. (Sect. 5.3.3). Decomposers, primary producers, and zooplankton will be entrained and killed in the cooling-tower system; they, as well as benthic organisms, will be affected by the heated-water discharge. This loss will have little effect on the pond food web. 30 figs., 76 tabs

  2. FOREST FIRES AROUND UNITS OF CONSERVATION – A CASE STUDY IN ÁGUAS EMENDADAS ECOLOGICAL STATION, DISTRITO FEDERAL

    Directory of Open Access Journals (Sweden)

    Eugênio P. Costa

    2009-09-01

    Full Text Available This study aimed to analyze aspects of fire use on urban areas around Águas Emendadas Ecological Station (ESECAE, in Distrito Federal, and to evaluate the foremost fire occurrences, equipment availability and tools for combatants and beyond decreasing forest fire incidences. The local population in town region around it (considering three kilometers as ray from the station, fire crew members units of conservation and the garrison body of firemen were interviewed in a representative form. Results had shown that most inclined areas to forest fire occurrence (33.4% highways edges and secondary roads had their localization related to urban environment, in which 34% of residents used fire as land cleanness. Machines availability, tools and equipment for execution of the activities on prevention and combat exist; however, there is not any equipment for individual protection for all fire crew members. As a solution, educative campaigns to emphasize the negative consequences of using fire (as a tool land and also to alert people for the risks caused by it should be done.

  3. Ensuring radiation safety during construction of the facility ''Ukrytie'' and restoration of unit 3 of the Chernobyl nuclear power station

    International Nuclear Information System (INIS)

    Belovodsky, L.F.; Panfilov, A.P.

    1997-01-01

    On April 26, 1986, an accident at the fourth power unit of the Chernobyl NPS (ChNPS) destroyed the reactor core and part of the power unit building, whereby sizeable amounts of radioactive materials, stored in reactor at operation, were released into the environment, and there were also highly active fragments of fuel elements and pieces of graphite from reactor spread on ChNPS site near to safety block. Information on the accident at ChNPS, including its cause and consequences, was considered at special meeting, conducted by IAEA on August 25-29, 1986, in Vienna. In final report of International Advisory Group for Nuclear Safety (IAGNS), prepared by results of meeting activities, the main stages of the accident effects elimination (AEE) immediately on the station site according to the data, received before August 1, 1986, were discussed. In 1987-1990 the published materials on the later period of AEE, completed by building ''Ukrytie'' installation at the fourth power unit of ChNPS

  4. 20 kHz main inverter unit. [for space station power supplies

    Science.gov (United States)

    Hussey, S.

    1989-01-01

    A proof-of-concept main inverter unit has demonstrated the operation of a pulse-width-modulated parallel resonant power stage topology as a 20-kHz ac power source driver, showing simple output regulation, parallel operation, power sharing and short-circuit operation. The use of a two-stage dc input filter controls the electromagnetic compatibility (EMC) characteristics of the dc power bus, and the use of an ac harmonic trap controls the EMC characteristics of the 20-kHz ac power bus.

  5. Improvement of the Industrial Estimates in the Managerial Unit Base Sugar Station "Paquito Rosales", of the County Santiago de Cuba

    Directory of Open Access Journals (Sweden)

    Adriana Cabrera–Milanés

    2015-12-01

    Full Text Available The Cuban sugar industry now has flexible management tools in the manufacturing process of sugar cane, due to the importance and necessity of continuous improvement of industrial operations. Consequently, manufacturing indicators careful planning is important, since it reflects the efficient productions and how the cost and expense are kept at a minimum level. Thus the overall objective of the research is to improve the planning of industrial indicators in the grinding phase at the Managerial Unit Base (MUB sugar station "Paquito Rosales" in Santiago de Cuba through an econometric model. The main result shows a notable improvement in the planning process, because the estimate cost of production changed notably, $36 684, 00 in wage expenses compared to planning cost in the sugar factory. 

  6. Seismic structural fragility investigation for the San Onofre Nuclear Generating Station, Unit 1 (Project I); SONGS-1 AFWS Project

    International Nuclear Information System (INIS)

    Wesley, D.A.; Hashimoto, P.S.

    1982-04-01

    An evaluation of the seismic capacities of several of the San Onofre Nuclear Generating Station, Unit 1 (SONGS-1) structures was conducted to determine input to the overall probabilistic methodology developed by Lawrence Livermore National Laboratory. Seismic structural fragilities to be used as input consist of median seismic capacities and their variabilities due to randomness and uncertainty. Potential failure modes were identified for each of the SONGS-1 structures included in this study by establishing the seismic load-paths and comparing expected load distributions to available capacities for the elements of each load-path. Particular attention was given to possible weak links and details. The more likely failure modes were screened for more detailed investigation

  7. Metallurgical investigation of cracking of the isolation valve downstream piping of regenerative heat exchanger at beaver valley unit 1 station

    International Nuclear Information System (INIS)

    Rao, G.V.

    1998-01-01

    A metallurgical investigation was conducted to establish the mechanism and cause of cracking in the regenerative heat exchanger piping at Beaver Valley Unit 1 PWR station in the USA. The investigation, which was centered on an eight inch long pipe section containing the cracking included surface examinations, metallographic and fractographic examinations, and chemistry evaluations. The results of the examinations showed that there were two types of pipe degradation mechanisms that affected the type 304 stainless schedule 40 piping. These consisted of localized corrosive attack on the OD surface due to the presence of chlorides, sulphates and phosphates, and transgranular stress corrosion cracking in the pipe wall due to the presence of chloride contaminants. The overall results of the investigation showed that the introduction of contaminants from external sources other than pipe insulation was the cause of heat exchanger pipe cracking. (author)

  8. Investigation of Main Radiation Source above Shield Plug of Unit 3 at Fukushima Daiichi Nuclear Power Station

    Science.gov (United States)

    Hiratama, Hideo; Kondo, Kenjiro; Suzuki, Seishiro; Tanimura, Yoshihiko; Iwanaga, Kohei; Nagata, Hiroshi

    2017-09-01

    Pulse height distributions were measured using a CdZnTe detector inside a lead collimator to investigate main source producing high dose rates above the shield plugs of Unit 3 at Fukushima Daiichi Nuclear Power Station. It was confirmed that low energy photons are dominant. Concentrations of Cs-137 under 60 cm concrete of the shield plug were estimated to be between 8.1E+9 and 5.7E+10 Bq/cm2 from the measured peak count rate of 0.662 MeV photons. If Cs-137 was distributed on the surfaces of the gaps with radius 6m and with the averaged concentration of 5 points, 2.6E+10 Bq/cm2, total amount of Cs-137 is estimated to be 30 PBq.

  9. International Space Station (ISS) Carbon Dioxide Removal Assembly (CDRA) Desiccant/Adsorbent Bed (DAB) Orbital Replacement Unit (ORU) Redesign

    Science.gov (United States)

    Reysa, Richard P.; Lumpkin, John P.; Sherif, Dian El; Kay, Robert; Williams, David E.

    2007-01-01

    The Carbon Dioxide Removal Assembly (CDRA) is a part of the International Space Station (ISS) Environmental Control and Life Support (ECLS) system. The CDRA provides carbon dioxide (CO2) removal from the ISS on-orbit modules. Currently, the CDRA is the secondary removal system on the ISS, with the primary system being the Russian Vozdukh. Within the CDRA are two desiccant/adsorbent beds (DAB), which perform the carbon dioxide removal function. The DAB adsorbent containment approach required improvements with respect to adsorbent containment. These improvements were implemented through a redesign program and have been implemented on units returning from orbit. This paper presents a DAB design modification implementation description, a hardware performance comparison between the unmodified and modified DAB configurations, and a description of the modified DAB hardware implementation into the on-orbit CDRA.

  10. Development of filtered containment venting system and application for Kashiwazaki-Kariwa Nuclear Power Station Unit 6, 7

    International Nuclear Information System (INIS)

    Murai, Soutarou; Hiranuma, Naoki; Kimura, Takeo; Omori, Shuichi; Watanabe, Fumitoshi; Sasa, Daisuke

    2014-01-01

    The Fukushima Dai-ichi Nuclear Power Station (1F) of Tokyo Electric Power Company (TEPCO) had experienced severe radio-active release to the environment in the Tohoku Region Pacific Coast Earthquake (alias: the Great East Japan Earthquake) in 2011. Under the Station Black-Out (SBO) conditions caused by tsunami with the earthquake, the 1F operators had tried to vent the gasses in the Primary Containment Vessels (PCVs) of the unit 1, 2 and 3 to the environment through the water pools in the suppression chambers of the PCVs. Its venting, however, was imperfect and, as a result, major direct radio-active release to the environment was caused. After this disaster, TEPCO launched a project to develop the Filtered Containment Venting System (FCVS), in which our very bitter experiences in the 1F accident as described above are reflected. One of the main purposes of the development of the FCVS is to enhance operability of venting under the severe plant conditions such as the SBO during progressing of severe core damage, and another is to enhance removal performance of radio-nuclides with the newly added filtering equipment, which is installed in the venting line from the PCV to the outer. The Kashiwazaki-Kariwa NPS unit 6 and 7 will be the first reactors applied the FCVSs. In this paper, we show the design concept of the TEPCO's FCVS, the brief overview of the system design and the summary of experiment which has been performed for getting the performance data of the FCVS such as decontamination factor in various conditions. (author)

  11. 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

  12. Technical evaluation report on the adequacy of station electric-distribution-system voltages for the Millstone Nuclear Power Station, Units 1 and 2. Docket Nos. 50-245, 50-336

    International Nuclear Information System (INIS)

    Selan, J.C.

    1983-01-01

    This report documents the technical evaluation of the adequacy of the station electric-distribution-system voltages for the Millstone Nuclear Power Station, Units 1 and 2. The evaluation is to determine if the onsite distribution system, in conjunction with the offsite power sources, has sufficient capacity to automatically start and operate all Class 1E loads within the equipment voltage ratings under certain conditions established by the Nuclear Regulatory Commission. The analyses submitted demonstrate that adequate voltages will be supplied to the Class 1E equipment under the worst-case conditions analyzed

  13. Control structures design for fossil power station units; Diseno de estructuras de control para unidades termoelectricas

    Energy Technology Data Exchange (ETDEWEB)

    Palomares Gonzalez, Daniel; Ricano Castillo, Juan Manuel [Instituto de Investigaciones Electricas, Cuernavaca (Mexico)

    1989-12-31

    In this paper are designed an analyzed the control ties of a 300MW fossil unit at different operation levels. The design and analysis were developed on an operation range of 50% to 100% load. The main control ties were studied among which are the feedwater flow, the superheating zone temperatures and the generated output. The technique used for the design is the decomposition in singular values (DSV) of the plant transference matrix. This is a recent technique that permits finding the most important interactions among output-input variables, over a significative frequencies range for the transference matrix of the plant. For this purpose utilizes the control properties of the transference matrix, such as: control effort, output-input interaction and ruggedness with respect to uncertainties. The control structures obtained were tested in a digital model of a fossil plant unit. A comparison study of both structures (original and modified) showed enhancement in the performance of the power plant with modified structure. [Espanol] En este trabajo se disenan y analizan los lazos de control de una unidad termoelectrica de 300 MW, a diferentes niveles de operacion. El diseno y analisis se desarrollo sobre un rango de operacion de 50 a 100 por ciento de carga. Se estudiaron los principales lazos de control entre los que se encuentran el flujo de agua de alimentacion, las temperaturas de la zona de sobrecalentamiento y la potencia generada. La tecnica utilizada para el diseno es la descomposicion en valores singulares (DVS) de la matriz de transferencia de la planta. Esta es una tecnica reciente que permite encontrar las interacciones mas importantes entre variables entrada-salida, sobre un rango de frecuencias significativas para la matriz de transferencia de la planta. Utiliza para ello las propiedades de control de la matriz de transferencia, como son: esfuerzo de control, interaccion entrada-salida y robustez con respecto a incertidumbres. Las estructuras de control

  14. MEASUREMENTS OF THE CONFINEMENT LEAKTIGHTNESS AT THE KOLA NUCLEAR POWER STATION (UNIT 2) IN RUSSIA

    International Nuclear Information System (INIS)

    GREENE, G.A.; GUPPY, J.G.

    1998-01-01

    This is the final report on the INSP project entitled, ''Kola Confinement Leaktightness'' conducted by BNL under the authorization of Project Work Plan WBS 1.2.2.1. This project was initiated in February 1993 to assist the Russians to reduce risks associated with the continued operation of older Soviet-designed nuclear power plants, specifically the Kola VVER-440/230 Units 1 and 2, through upgrades in the confinement performance to reduce the uncontrolled leakage rate. The major technical objective of this-project was to improve the leaktightness of the Kola NPP VVER confinement boundaries, through the application of a variety of sealants to penetrations, doors and hatches, seams and surfaces, to the extent that current technology permitted. A related objective was the transfer, through training of Russian staff, of the materials application procedures to the staff of the Kola NPP. This project was part of an overall approach to minimizing uncontrolled releases from the Kola NPP VVER440/230s in the event of a serious accident, and to thereby significantly mitigate the consequences of such an accident. The US provided materials, application technology, and applications equipment for application of sealant materials, surface coatings, potting materials and gaskets, to improve the confinement leaktightness of the Kola VVER-440/23Os. The US provided for training of Russian personnel in the applications technology

  15. MEASUREMENTS OF THE CONFINEMENT LEAKTIGHTNESS AT THE KOLA NUCLEAR POWER STATION (UNIT 2) IN RUSSIA

    Energy Technology Data Exchange (ETDEWEB)

    GREENE,G.A.; GUPPY,J.G.

    1998-08-01

    This is the final report on the INSP project entitled, ``Kola Confinement Leaktightness'' conducted by BNL under the authorization of Project Work Plan WBS 1.2.2.1. This project was initiated in February 1993 to assist the Russians to reduce risks associated with the continued operation of older Soviet-designed nuclear power plants, specifically the Kola VVER-440/230 Units 1 and 2, through upgrades in the confinement performance to reduce the uncontrolled leakage rate. The major technical objective of this-project was to improve the leaktightness of the Kola NPP VVER confinement boundaries, through the application of a variety of sealants to penetrations, doors and hatches, seams and surfaces, to the extent that current technology permitted. A related objective was the transfer, through training of Russian staff, of the materials application procedures to the staff of the Kola NPP. This project was part of an overall approach to minimizing uncontrolled releases from the Kola NPP VVER440/230s in the event of a serious accident, and to thereby significantly mitigate the consequences of such an accident. The US provided materials, application technology, and applications equipment for application of sealant materials, surface coatings, potting materials and gaskets, to improve the confinement leaktightness of the Kola VVER-440/23Os. The US provided for training of Russian personnel in the applications technology.

  16. 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

  17. Streamflow Gaging Stations

    Data.gov (United States)

    Department of Homeland Security — This map layer shows selected streamflow gaging stations of the United States, Puerto Rico, and the U.S. Virgin Islands, in 2013. Gaging stations, or gages, measure...

  18. Technical specifications: Susquehanna Steam Electric Station, Unit No. 2 (Docket No. 50-388). Appendix A to License No. NPF-22

    International Nuclear Information System (INIS)

    1984-03-01

    Susquehanna Steam Electric Station, Unit 2 Technical Specifications were prepared by the US Nuclear Regulatory Commission to set forth the limits, operating conditions, and other requirements applicable to a nuclear reactor facility as set forth in Section 50.36 of 10 CFR Part 50 for the protection of the health and safety of the public

  19. Technical specifications, Braidwood Station, Unit Nos. 1 and 2 (Docket Nos. STN 50-456 and STN 50-457): Appendix ''A'' to License No. NPF-70

    International Nuclear Information System (INIS)

    1987-05-01

    The Braidwood Station, Unit Nos. 1 and 2, Technical Specifications were prepared by the US Nuclear Regulatory Commission to set forth the limits, operating conditions, and other requirements applicable to a nuclear reactor facility as set forth in Section 50.36 of 10 CFR Part 50 for the protection of the health and safety of the public. 18 figs., 55 tabs

  20. Conformance to Regulatory Guide 1.97, North Anna Power Station, Unit Nos. 1 and 2 (Docket Nos. 50-338 and 50-339)

    International Nuclear Information System (INIS)

    Udy, A.C.

    1985-09-01

    This EG and G Idaho, Inc. report reviews the submittals for Regulatory Guide 1.97, Revision 3, for Unit Nos. 1 and 2 of the North Anna Power Station and identifies areas of nonconformance to the regulatory guide. Exceptions to Regulatory Guide 1.97 are evaluated and those areas where sufficient basis for acceptability is not provided are identified

  1. Montague Nuclear Power Station, Units 1 and 2: Final environmental statement (Docket Nos. 50-496 and 50-497)

    International Nuclear Information System (INIS)

    1977-02-01

    The proposed action is the issuance of construction permits to the Northeast Nuclear Energy Company for the construction of the Montague Nuclear Power Station, Units 1 and 2, located on the Connecticut River in the Town of Montague, Massachusetts. The plant will employ two identical boiling-water reactors to produce up to 3579 megawatts thermal (MWt) each. Two steam turbine-generators will use this heat to provide 1150 MWe (net) of electrical power capacity from each turbine-generator. A design power level of 3759 MWt (1220 Mwe net) for each unit is anticipated at a future date and is considered in the assessments contained in this statement. The waste heat will be rejected through natural-draft cooling towers using makeup water obtained from and discharged to the Connecticut River. The 1900-acre site is about 90% forest, with the remaining acreage in transmission-line corridor and old-field vegetation. The total loss of mixed-age forest will be 1273 acres. Nodesignated scenic areas will be crossed. Sixty acres of public lands, State forests, and parks will be lost to transmission facilities as well as losses associated with crossings of 2.0 miles of water bodies and 11.9 miles of wetlands. The maximum estimated potential loss of salable wood products will be $849,600. A maximum of 85.8 cfs of cooling water will be withdrawn from the Connecticut River. A maximum of 17.2 cfs will be returned to the river with the dissolved solids concentration increased by a factor of about 5. A maximum of 68.6 cfs will be evaporated to the atmosphere by the cooling towers. 143 refs., 58 figs., 69 tabs

  2. Microorganisms in confined habitats: Microbial monitoring and control of intensive care units, operating rooms, cleanrooms and the International Space Station

    Directory of Open Access Journals (Sweden)

    Maximilian Mora

    2016-10-01

    Full Text Available Indoor environments, where people spend most of their time, are characterized by a specific microbial community, the indoor microbiome. Most indoor environments are connected to the natural environment by high ventilation, but some habitats are more confined: intensive care units, operating rooms, cleanrooms and the international space station (ISS are extraordinary living and working areas for humans, with a limited exchange with the environment. The purposes for confinement are different: a patient has to be protected from infections (intensive care unit, operating room, product quality has to be assured (cleanrooms, or confinement is necessary due to extreme, health-threatening outer conditions, as on the ISS. The ISS represents the most secluded man-made habitat, constantly inhabited by humans since November 2000 – and, inevitably, also by microorganisms. All of these man-made confined habitats need to be microbiologically monitored and controlled, by e.g. microbial cleaning and disinfection. However, these measures apply constant selective pressures, which support microbes with resistance capacities against antibiotics or chemical and physical stresses and thus facilitate the rise of survival specialists and multi-resistant strains. In this article, we summarize the available data on the microbiome of aforementioned confined habitats. By comparing the different operating, maintenance and monitoring procedures as well as microbial communities therein, we emphasize the importance to properly understand the effects of confinement on the microbial diversity, the possible risks represented by some of these microorganisms and by the evolution of (antibiotic resistances in such environments - and the need to reassess the current hygiene standards.

  3. Process improvement studies for the Submerged Demineralizer System (SDS) at the Three Mile Island Nuclear Power Station, Unit 2

    International Nuclear Information System (INIS)

    Campbell, D.O.; Collins, E.D.; King, L.J.; Knauer, J.B.

    1982-05-01

    Tests were made to investigate flowsheet modifications which might improve the expected performance of the reference Submerged Demineralizer System (SDS) flowsheet for decontaminating the high-activity-level water at the Three Mile Island Nuclear Power Station, Unit 2. The tests included one series designed to show the effects of aging time, temperature, and pH on reduction of the concentrations of residual 137 Cs and 90 Sr, and a second series designed to evaluate the physical sorption of 125 Sb on silica gel or other inorganic sorbents. Results of the tests indicated that the most promising method for reducing 137 Cs and 90 Sr concentrations below 10 -4 μCi/mL is to age the effluent water from the zeolite columns for at least 2 h at 75 0 C prior to its passage through another zeolite column. Sorption of the 125 Sb on silica gel or other inorganic sorbents did not show sufficient promise to be considered for practical use. A previously identified method for removal of 125 Sb requires deionization of the water by removal of the sodium on a cation exchange resin prior to sorption of 125 Sb on anion exchange resin; however, this method would generate a relatively large amount of low-activity-level solid waste

  4. MRP-227 Reactor vessel internals inspection planning and initial results at the Oconee nuclear station unit 2

    International Nuclear Information System (INIS)

    Davidsaver, S.B.; Fyfitch, S.; Whitaker, D.E.; Doss, R.L.

    2015-01-01

    The U.S. PWR industry has pro-actively developed generic inspection requirements and standards for reactor vessel (RV) internals. The Electric Power Research Institute (EPRI) Pressurized Water Reactor (PWR) Materials Reliability Program (MRP) has issued MRP-227-A and MRP-228 with mandatory and needed requirements based on the Nuclear Energy Institute (NEI) document NEI 03-08. The inspection and evaluation guidelines contained in MRP-227-A consider eight age-related degradation mechanisms: stress corrosion cracking (SCC), irradiation-assisted stress corrosion cracking (IASCC), wear, fatigue, thermal aging embrittlement, irradiation embrittlement, void swelling and irradiation growth, and thermal and irradiation-enhanced stress relaxation or irradiation-enhanced creep. This paper will discuss the decision planning efforts required for implementing the MRP-227-A and MRP-228 requirements and the results of these initial inspections at the Oconee Nuclear power station (ONS) units. Duke Energy and AREVA overcame a significant technology and NDE challenge by successfully completing the first-of-a-kind MRP-227-A scope requirements at ONS-1 in one outage below the estimated dose and with zero safety issues or events. This performance was repeated at ONS-2 a year later. The remote NDE tooling and processes developed to examine the MRP-227-A scope for ONS-1 and ONS-2 are transferable to other PWRs

  5. THE STRUCTURE OF SUBTIDAL MACROALGAL ASSEMBLAGES AT THE TAMOIOS ECOLOGICAL STATION, A THREATENED CONSERVATION UNIT IN RIO DE JANEIRO, BRAZIL

    Directory of Open Access Journals (Sweden)

    Victor de Souza Koutsoukos

    2015-03-01

    Full Text Available The structure of subtidal rocky bottom communities at Tamoios Ecological Station (TES, situated in Ilha Grande Bay, Rio de Janeiro State, as well as in other Brazilian marine protected areas, is insufficiently characterized. The present study describes the macroalgal assemblages of shallow subtidal rocky bottoms on two islands of the TES-Imboassica (IM and Búzios Pequena (BPadopting species and genera as observational units. Two sites were surveyed on each island in summer 2011. Random 30x30 cm quadrats (n=3 were scraped to collect all macroalgae except crustose species. The subtidal assemblages, in which 58 macroalgal species occurred, were characterized by the high frequency and percent cover of Sargassum vulgare C. Agardh (56.8±8.4%. The sites differed significantly in total number of species and Shannon-Weiner diversity index (PERMANOVA, p5% were Sargassum, Laurencia, Wrangelia, Canistrocarpus, Asparagopsis, Hypnea, Ceratodictyon, Gayliella, Spyridia and Chondria.Dissimilarities within and between the islands, as shown by nMDS of the cover data, suggest that different spatial scales should be considered in monitoring the rocky bottom communities of Ilha Grande Bay.

  6. Radionuclide identification and dose rate projection for en-masse coolant channel replacement at Rajasthan Atomic Power Station, Unit-2

    International Nuclear Information System (INIS)

    Shuka, A.K.; Jain, S.K.; Nischal, Rajan; Agarwal, Sharad; Gandhimathinathan, S.; Sharma, R.M.

    1999-01-01

    The en-masse coolant channel replacement (EMCCR) in Rajasthan Atomic Power Station (RAPS) Unit-2 was carried out during 1996-97. This job which involved high intensity of nonuniformi radiation field, was done for the first time in India in any PHWR. Identification and estimation of gamma emitting radionuclides present in the highly active components played an important role in planning this job at various stages. Dose rates projected on the basis of samples collected from 0-11 coolant tube (RAPS-2) in 1992 were of great help in formulating the methodology and designing the facility at Solid Waste Management Plant for safe disposal of highly radioactive reactor components removed during the campaign. Based on dose rate projection, the initial dose rate was expected to reduce to a value somewhere between 2-15% after a cooling time of about 600 days. The projected values were later found in good agreement with the actual values obtained on analysis of chip samples collected from coolant tubes of channel K-8 and G-15. These data were of vital importance in job planning and exposure control during EMCCR campaign. (author)

  7. Destructive examination of a cracked alloy A-286 Vent Valve Jackscrew from the Oconee unit 1 nuclear station

    International Nuclear Information System (INIS)

    Fyfitch, S.; Davidsaver, S.B.; Redmond, K.; Whitaker, D.E.; Doss, R.L.

    2015-01-01

    During the Fall 2012 refueling outage at Oconee Nuclear Station Unit 1, a reactor vessel internals video inspection revealed an abnormal condition on a reactor vessel vent valve. One of the Alloy A-286 jackscrews on this vent valve was visibly extended more than the other and bent, the lower section of the jackscrew threads were galled, and the lower barrel nuts were recessed. Furthermore, a circumferential crack-like indication was identified on the lower portion of the other jackscrew. The vent valve assembly was replaced during the refueling outage and the cracked portion of the jackscrew was submitted to Duke Energy's metallurgy lab for a failure mode determination. The failure investigation included metallography, scanning electronic microscopy (SEM), energy dispersive x-ray spectroscopy (EDS), and ASTM grain size determination. This paper determines that the failure most likely occurred from the resultant bending stress on the cracked jackscrew as the result of an impact load to the other jackscrew, and initiated and propagated by an intergranular stress corrosion cracking (IGSCC) mechanism. (authors)

  8. Investigation of Contaminated Groundwater at Solid Waste Management Unit 12, Naval Weapons Station Charleston, North Charleston, South Carolina, 2008

    Science.gov (United States)

    Vroblesky, Don A.; Petkewich, Matthew D.

    2009-01-01

    The U.S. Geological Survey and the Naval Facilities Engineering Command Southeast investigated natural and engineered remediation of chlorinated volatile organic compound (VOC) groundwater contamination at Solid Waste Management Unit 12 at the Naval Weapons Station Charleston, North Charleston, South Carolina, beginning in 2000. The primary contaminants of interest in the study are tetrachloroethene, 1,1,1-trichloroethane, trichloroethene, cis-1,2-dichloroethene, vinyl chloride, 1,1-dichloroethane, and 1,1-dichloroethene. Engineered remediation aspects at the site consist of a zero-valent-iron permeable reactive barrier (PRB) installed in December 2002 intercepting the contamination plume and a phytoremediation test stand of loblolly pine trees planted in the source area in May 2003. The U.S. Geological Survey planted an additional phytoremediation test stand of loblolly pine trees on the upgradient side of the southern end of the PRB in February 2008. At least once during the summer, however, the trees were inadvertently mowed during lawn cutting activity. The PRB along the main axis of the contaminant plume appears to be actively removing contamination. In contrast to the central area of the PRB, the data from the southern end of the PRB indicate that contaminants are moving around the PRB. Concentrations in wells upgradient from the PRB showed a general decrease in VOC concentrations. VOC concentrations in some wells in the forest downgradient from the PRB showed a sharp increase in 2005, followed by a decrease in 2006. Farther downgradient in the forest, the VOC concentrations began to increase in 2007 and continued to increase into 2008. The VOC-concentration changes in groundwater beneath the forest appear to indicate movement of a groundwater-contaminant pulse through the forest. It also is possible that the data may represent lateral shifting of the plume in response to changes in groundwater-flow direction.

  9. Efforts to Reduce International Space Station Crew Maintenance for the Management of the Extravehicular Mobility Unit Transport Loop Water Quality

    Science.gov (United States)

    Steele, John W.; Etter, David; Rector, Tony; Boyle, Robert; Vandezande, Christopher

    2013-01-01

    The EMU (Extravehicular Mobility Unit) contains a semi-closed-loop re-circulating water circuit (Transport Loop) to absorb heat into a LCVG (Liquid Coolant and Ventilation Garment) worn by the astronaut. A second, single-pass water circuit (Feed-water Loop) provides water to a cooling device (Sublimator) containing porous plates, and that water sublimates through the porous plates to space vacuum. The cooling effect from the sublimation of this water translates to a cooling of the LCVG water that circulates through the Sublimator. The quality of the EMU Transport Loop water is maintained through the use of a water processing kit (ALCLR Airlock Cooling Loop Remediation) that is used to periodically clean and disinfect the water circuit. Opportunities to reduce crew time associated with on-orbit ALCLR operations include a detailed review of the historical water quality data for evidence to support an extension to the implementation cycle. Furthermore, an EMU returned after 2-years of use on the ISS (International Space Station) is being used as a test bed to evaluate the results of extended and repeated ALCLR implementation cycles. Finally, design, use and on-orbit location enhancements to the ALCLR kit components are being considered to allow the implementation cycle to occur in parallel with other EMU maintenance and check-out activities, and to extend the life of the ALCLR kit components. These efforts are undertaken to reduce the crew-time and logistics burdens for the EMU, while ensuring the long-term health of the EMU water circuits for a post-Shuttle 6-year service life.

  10. Palo Verde Nuclear Generating Station, Units 1, 2 and 3 (Docket Nos. STN 50-528, STN 50-529 and STN 50-530): Final environmental statement

    International Nuclear Information System (INIS)

    1975-09-01

    The proposed action is the issuance of construction permits to the Arizona public Service Company for the construction of the Palo Verde Nuclear Generating Station, Units 1, 2, and 3. Preparation of the 3800-acre site will involve the clearing of up to 2500 acres of land, 1500 of which will be prominently devoted to station facilities. An additional 1200- to 1300-acre evaporation pond will ultimately be developed during the lifetime of the station. About 2200 site acres, previously devoted to agriculture, will be excluded from this land use. Soil disturbance during construction of the station, transmission lines, and water conveyance pipeline will tend to promote erosion and increase siltation in local ephemeral water courses. Stringent measures will be taken to minimize these effects. The total radiation dose to construction workers is estimated to be 15 man-rem. This dose is a small fraction of the approximately 470 man-rem which will be received by the construction force over the same period from natural background radiation. Station, transmission line, and water pipeline construction will kill, remove, displace, or otherwise disturb involved flora and fauna, and will eliminate varying amounts of wildlife breeding, nesting, and forage habitat. These will not be important permanent impacts to the population stability and structure of the involved local ecosystems of the Sonoran desert; however, measures will be taken to minimize such effects as do result form the proposed action

  11. 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

  12. 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

  13. Sea Levels Online: Sea Level Variations of the United States Derived from National Water Level Observation Network Stations

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — Water level records are a combination of the fluctuations of the ocean and the vertical land motion at the location of the station. Monthly mean sea level (MSL)...

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

    International Nuclear Information System (INIS)

    1983-02-01

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

  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. 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

  17. 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

  18. 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

  19. 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

  20. 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

  1. 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

  2. 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

  3. Addendum to the Closure Report for Corrective Action Unit 403: Second Gas Station, Tonopah Test Range, Nevada, Revision 0

    Energy Technology Data Exchange (ETDEWEB)

    Grant Evenson

    2009-05-01

    This document constitutes an addendum to the Closure Report for Corrective Action Unit 403: Second Gas Station, Tonopah Test Range, Nevada, September 1998 as described in the document Supplemental Investigation Report for FFACO Use Restrictions, Nevada Test Site, Nevada (SIR) dated November 2008. The SIR document was approved by NDEP on December 5, 2008. The approval of the SIR document constituted approval of each of the recommended UR removals. In conformance with the SIR document, this addendum consists of: • This page that refers the reader to the SIR document for additional information • The cover, title, and signature pages of the SIR document • The NDEP approval letter • The corresponding section of the SIR document This addendum provides the documentation justifying the cancellation of the UR for CAS 03-02-004-0360, Underground Storage Tanks. This UR was established as part of a Federal Facility Agreement and Consent Order (FFACO) corrective action and is based on the presence of contaminants at concentrations greater than the action levels established at the time of the initial investigation (FFACO, 1996). Since this UR was established, practices and procedures relating to the implementation of risk-based corrective actions (RBCA) have changed. Therefore, this UR was reevaluated against the current RBCA criteria as defined in the Industrial Sites Project Establishment of Final Action Levels (NNSA/NSO, 2006). This re-evaluation consisted of comparing the original data (used to define the need for the UR) to risk-based final action levels (FALs) developed using the current Industrial Sites RBCA process. The re-evaluation resulted in a recommendation to remove the UR because contamination is not present at the site above the risk-based FALs. Requirements for inspecting and maintaining this UR will be canceled, and the postings and signage at this site will be removed. Fencing and posting may be present at this site that are unrelated to the FFACO UR

  4. 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

  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 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

  7. 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

  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. Investigation of Ground-Water Contamination at Solid Waste Management Unit 12, Naval Weapons Station Charleston, North Charleston, South Carolina

    Science.gov (United States)

    Vroblesky, Don A.; Casey, Clifton C.; Petkewich, Matthew D.; Lowery, Mark A.; Conlon, Kevin J.; Harrelson, Larry G.

    2007-01-01

    The U.S. Geological Survey and the Naval Facilities Engineering Command Southeast investigated natural and engineered remediation of chlorinated volatile organic compound ground-water contamination at Solid Waste Management Unit 12 at the Naval Weapons Station Charleston, North Charleston, South Carolina. The primary contaminants of interest are tetrachloroethene, 1,1,1-trichloroethane, trichloroethene, cis-1,2-dichloroethene, vinyl chloride, 1,1-dichloroethane, and 1,1-dichloroethene. In general, the hydrogeology of Solid Waste Management Unit 12 consists of a surficial aquifer, composed of sand to clayey sand, overlain by dense clay that extends from about land surface to a depth of about 8 to 10 feet and substantially limits local recharge. During some months in the summer, evapotranspiration and limited local recharge result in ground-water level depressions in the forested area near wells 12MW-12S and 12MW-17S, seasonally reflecting the effects of evapotranspiration. Changes in surface-water levels following Hurricane Gaston in 2004 resulted in a substantial change in the ground-water levels at the site that, in turn, may have caused lateral shifting of the contaminant plume. Hydraulic conductivity, determined by slug tests, is higher along the axis of the plume in the downgradient part of the forests than adjacent to the plume, implying that there is some degree of lithologic control on the plume location. Hydraulic conductivity, hydraulic gradient, sulfur-hexafluoride measurements, and historical data indicate that ground-water flow rates are substantially slower in the forested area relative to upgradient areas. The ground-water contamination, consisting of chlorinated volatile organic compounds, extends eastward in the surficial aquifer from the probable source area near a former underground storage tank. Engineered remediation approaches include a permeable reactive barrier and phytoremediation. The central part of the permeable reactive barrier along the

  10. 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.)

  11. 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

  12. Palo Verde Nuclear Generating Station Units 1, 2, and 3: Draft environmental statement (Docket Nos. STN 50-528, 529, and 530)

    International Nuclear Information System (INIS)

    1975-04-01

    The proposed action is the issuance of construction permits to the Arizona Public Service Corporation for the construction of the Palo Verde Nuclear Generating Station, Units 1, 2 and 3. Preparation of the 3880-acre site will involve the clearing of up to 2500 acres of land, 1500 of which will be permanently devoted to station facilities. An additional 1200- to 1300-acre evaporation pond will ultimately be developed during the lifetime of the station. About 2200 site acres, previously devoted to agriculture, will be excluded from this land use (Sec. 4. 1). Soil disturbance during construction of the station, transmission lines, and water conveyance pipeline will tend to promote erosion and increase siltation in local ephemeral water courses. Stringent measures will be taken to minimize these effects (Sec. 4.5). Station, transmission line, and water pipeline construction will kill, remove displace, or otherwise disturb involved flora and fauna, and will eliminate varying amounts of wildlife breeding, nesting, and forage habitat. These will not be important impacts to the population stability and structure of the involved local ecosystems of the Sonoran desert; however, measures will be taken to minimize such effects (Sec. 4.3 and 4.5). Approximately 60 acres of agricultural land will be temporarily affected by construction in transmission corridors. The great majority can be returned to that use upon completion of construction, thus the impact is considered minor. Similarly, most grazing lands affected along these corridors, as well as along the water pipeline corridor, can eventually be returned to that use. New archaeological resources could be discovered along the path of final transmission corridor alignments. The applicant will take measures to locate and protect such resources if they exist. 75 refs., 24 figs., 65 tabs

  13. Palo Verde Nuclear Generating Station, Units 1, 2, and 3 (Docket Nos. STN 50-528, STN 50-529, and STN 50-530): Final environmental statement

    International Nuclear Information System (INIS)

    1982-02-01

    The proposed action is the issuance of operating licenses to the Arizona Public Service Company (APS, applicant) for the startup and operation of PVNGS, Units 1, 2, and 3, located in Maricopa County, about 24 km (15 mi) west of Buckeye, Arizona. The information in this statement represents the second assessment of the environmental impact associated with PVNGS Units 1, 2, and 3 pursuant to the guidelines of the National Environmental Policy Act of 1969 (NEPA) and Title 10 of the Code of Federal Regulations (10 CFR) Part 51 of the Commissions's Regulations. After receiving an application in July 1974 to construct this station, the staff carried out a review of impacts that would occur during its construction and operation. That evaluation was issued as a Final Environmental Statement/emdash/Construction Phase (FES-CP). After this environmental review, a safety review, an evaluation by the Advisory Committee on Reactor Safeguards, and public hearings in Phoenix, Arizona, the US Nuclear Regulatory Commission issued Construction Permits Nos. CPPR-141, CPPR-142, and CPPR-143 for the construction of PVNGS Units 1, 2, and 3. As of September 1981, the construction of Unit 1 was about 92 percent complete, Unit 2 was 68 percent complete, and Unit 3 was 26 percent complete. 11 figs., 21 tabs

  14. 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

  15. 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

  16. 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

  17. 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

  18. 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

  19. 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

  20. 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

  1. NRC Fact-Finding Task Force report on the ATWS event at Salem Nuclear Generating Station, Unit 1, on February 25, 1983

    International Nuclear Information System (INIS)

    1983-03-01

    An NRC Region I Task Force was established on March 1, 1983 to conduct fact finding and data collection with regard to the circumstances which led to an anticipated transient without scram (ATWS) event at the Public Service Electric and Gas Company's Salem Generating Station, Unit 1 on February 25, 1983. The charter of the Task Force was to determine the factual information pertinent to management and administrative controls which should have ensured proper operation of the reactor trip breakers in the solid state protection system. This report documents the findings of the Task Force along with its conclusions

  2. 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

  3. 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

  4. 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

  5. Technical evaluation report on the proposed design modifications and technical specification changes on grid voltage degradation for the Millstone Nuclear Power Station, Unit 1

    International Nuclear Information System (INIS)

    Selan, J.C.

    1982-01-01

    This report documents the technical evaluation of the proposed design modifications and Technical Specification change for protection of Class 1E equipment from grid voltage degradation for the Millstone Nuclear Power Station, Unit 1. The review criteria are based on several IEEE standards and the Code of Federal Regulations. The evaluation finds that the licensee has not provided sufficient information on the undervoltage protection system to allow a complete evaluation into the adequacy of protecting the Class 1E equipment from sustained voltage degradation

  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)

    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

  7. 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

  8. 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

  9. 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

  10. 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

  11. 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

  12. 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

  13. Indian Point Station, Units 1, 2, and 3. Annual operations report No. 27: January--December 1977

    International Nuclear Information System (INIS)

    1978-01-01

    Unit 1 remained shutdown with the fuel removed to the Fuel Handling Building pending a decision by the Company on the installation of an ECCS. Information for Unit 2 and 3 is presented concerning procedure changes, tests, experiments, maintenance, equipment examinations, radioactivity releases, shutdowns and forced power reductions, and the number of personnel and Man/Rem exposure by work and job function

  14. Design and performance of the helically coiled boilers of two AGR power stations in the United Kingdom

    International Nuclear Information System (INIS)

    El-Nagdy, M.; Papa, A.D.

    1988-01-01

    The Hartlepool and Heysham-I AGR stations have been commissioned and operating since 1983. The main features, of the design of the helical once-through boilers raising the steam for power generation, are outlined. The modifications to the feed inlet flow ferrules, necessary to improve the boiler performance and optimize the power output, have been described. Comparisons between the thermal and hydrodynamic performance of the boilers before and following these alterations are given. The improvements in the computer code predictions of the plant performance have also been presented. (author)

  15. Nuclear power stations licensing

    International Nuclear Information System (INIS)

    Solito, J.

    1978-04-01

    The judicial aspects of nuclear stations licensing are presented. The licensing systems of the United States, Spain, France and Federal Republic of Germany are focused. The decree n 0 60.824 from July 7 sup(th), 1967 and the following legislation which define the systematic and area of competence in nuclear stations licensing are analysed [pt

  16. 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

  17. 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

  18. 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

  19. 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

  20. Verifying the prevalence, properties, and congruent hydraulics of at-many-stations hydraulic geometry (AMHG) for rivers in the continental United States

    Science.gov (United States)

    Barber, Caitline A.; Gleason, Colin J.

    2018-01-01

    Hydraulic geometry (HG) has long enabled daily discharge estimates, flood risk monitoring, and water resource and habitat assessments, among other applications. At-many-stations HG (AMHG) is a newly discovered form of HG with an evolving understanding. AMHG holds that there are temporally and spatially invariant ('congruent') depth, width, velocity, and discharge values that are shared by all stations of a river. Furthermore, these river-wide congruent hydraulics have been shown to link at-a-station HG (AHG) in space, contrary to previous expectation of AHG as spatially unpredictable. To date, AMHG has only been thoroughly examined on six rivers, and its congruent hydraulics are not well understood. To address the limited understanding of AMHG, we calculated AMHG for 191 rivers in the United States using USGS field-measured data from over 1900 gauging stations. These rivers represent nearly all geologic and climatic settings found in the continental U.S. and allow for a robust assessment of AMHG across scales. Over 60% of rivers were found to have AMHG with strong explanatory power to predict AHG across space (defined as r2 > 0.6, 118/191 rivers). We also found that derived congruent hydraulics bear little relation to their observed time-varying counterparts, and the strength of AMHG did not correlate with any available observed or congruent hydraulic parameters. We also found that AMHG is expressed at all fluvial scales in this study. Some statistically significant spatial clusters of rivers with strong and weak AMHG were identified, but further research is needed to identify why these clusters exist. Thus, this first widespread empirical investigation of AMHG leads us to conclude that AMHG is indeed a widely prevalent natural fluvial phenomenon, and we have identified linkages between known fluvial parameters and AMHG. Our work should give confidence to future researchers seeking to perform the necessary detailed hydraulic analysis of AMHG.

  1. 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

  2. Assessment of Infrasound Signals Recorded on Seismic Stations and Infrasound Arrays in the Western United States using Ground Truth Sources

    Science.gov (United States)

    Park, Junghyun; Hayward, Chris; Stump, Brian W.

    2018-02-01

    Ground truth sources in Utah during 2003-2013 are used to assess the contribution of temporal atmospheric conditions to infrasound detection and the predictive capabilities of atmospheric models. Ground truth sources consist of 28 long duration static rocket motor burn tests and 28 impulsive rocket body demolitions. Automated infrasound detections from a hybrid of regional seismometers and infrasound arrays use a combination of STA/LTA ratios and spectral analyses. These detections are grouped into station triads using a Delaunay triangulation network and then associated to estimate phase velocity and azimuth to filter signals associated with a particular source location. The resulting range and azimuth distribution from sources to detecting stations varies seasonally and is consistent with predictions based on seasonal atmospheric models. Impulsive signals from rocket body detonations are observed at greater distances ( > 700 km) than the extended duration signals generated by the rocket burn test (up to 600 km). Infrasound energy attenuation associated with the two source types is quantified as a function of range and azimuth from infrasound amplitude measurements. Ray tracing results using ground-to-space (G2S) atmospheric specifications are compared to these observations and illustrate the degree to which the time variations in characteristics of the observations can be predicted over a multiple year time period.

  3. 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

  4. NOAA Water Level Predictions Stations for the Coastal United States and Other Non-U.S. Sites

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — The National Ocean Service (NOS) maintains a long-term database containing water level measurements and derived tidal data for coastal waters of the United States...

  5. Integrated safety assessment report: Integrated Safety Assessment Program: Millstone Nuclear Power Station, Unit 1 (Docket No. 50-245): Draft report

    International Nuclear Information System (INIS)

    1987-04-01

    The Integrated Safety Assessment Program (ISAP) was initiated in November 1984, by the US Nuclear Regulatory Commission to conduct integrated assessments for operating nuclear power reactors. The integrated assessment is conducted in a plant-specific basis to evaluate all licensing actions, licensee initiated plant improvements and selected unresolved generic/safety issues to establish implementation schedules for each item. In addition, procedures will be established to allow for a periodic updating of the schedules to account for licensing issues that arise in the future. This report documents the review of Millstone Nuclear Power Station, Unit No. 1, operated by Northeast Nuclear Energy Company (located in Waterford, Connecticut). Millstone Nuclear Power Station, Unit No. 1, is one of two plants being reviewed under the pilot program for ISAP. This report indicates how 85 topics selected for review were addressed. This report presents the staff's recommendations regarding the corrective actions to resolve the 85 topics and other actions to enhance plant safety. The report is being issued in draft form to obtain comments from the licensee, nuclear safety experts, and the Advisory Committee for Reactor Safeguards (ACRS). Once those comments have been resolved, the staff will present its positions, along with a long-term implementation schedule from the licensee, in the final version of this report

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

    International Nuclear Information System (INIS)

    1982-11-01

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

  7. 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

  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. Routes and Stations

    Data.gov (United States)

    Department of Homeland Security — he Routes_Stations table is composed of fixed rail transit systems within the Continental United States, Alaska, Hawaii, the District of Columbia, and Puerto Rico....

  10. Public Transit Stations

    Data.gov (United States)

    Department of Homeland Security — fixed rail transit stations within the Continental United States, Alaska, Hawaii, the District of Columbia, and Puerto Rico. The modes of transit that are serviced...

  11. Revised draft environmental statement related to construction of Atlantic Generating Station Units 1 and 2 (Docket Nos. STN 50-477 and STN 50-478)

    International Nuclear Information System (INIS)

    1976-10-01

    The proposed action is the issuance of a construction permit to Public Service Electric and Gas Company (PDE and G) for the construction of the Atlantic Generating Station (AGS), Units 1 and 2. The AGS is the first nuclear power station in the United States proposed for construction in the offshore waters on the continental shelf. The AHS will be located in the Atlantic Ocean 2.8 miles offshore of Atlantic and Ocean countries. New Jersey, 11 miles northeast of Atlantic City, and will consist of two floating nuclear power plants enclosed in a protective rubble-mound breakwater. Both plants will be identical, of standardized design, and will employ pressurized water reactors to produce up to approximately 3425 megawatts thermal (MWt) each. Steam turbine generators will use this heat to produce up to approximately 1150 megawatts of electrical power (MWe) per unit. The main condensers will be cooled by the flow of seawater drawn from within the breakwater and discharged shoreward and external to the breakwater. This statement identifies various environmental aspects and potential adverse effects associated with the construction and operation of the AGS. Based upon an approximate two-year review period which included a multidisciplined assessment of extensive survey and modeling data, these effects are considered by the staff to be of a generally acceptable nature. Breakwater construction will result in the destruction of 100 acres of benthic infauna (burrowing animals) and the development of a reef-type community on the breakwater. The production of new biomass (standing crop) by the reef community is expected to compensate for the infaunal biomass destroyed by dredging and will contribute mainly to the local sport fishery. 93 figs., 110 tabs

  12. 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

  13. Analysis of fuel handling system for fuel bundle safety during station blackout in 500 MWe PHWR unit of India

    International Nuclear Information System (INIS)

    Madhuresh, R.; Nagarajan, R.; Jit, I.; Sanatkumar, A.

    1996-01-01

    Situations of Station Blackout (SBO) i.e. postulated concurrent unavailability of Class Ill and Class IV power, could arise for a long period, while on-power refuelling or other fuel handling operations are in progress with the hot irradiated fuel bundles being anywhere in the system from the Reactor Building to the Spent Fuel Storage Bay. The cooling provisions for these fuel bundles are diverse and specific to the various stages of fuel handling operations and are either on Class Ill or on Class II power with particular requirements of instrument air. Therefore, during SBO, due to the limited availability of Class II power and instrument air, it becomes difficult to maintain cooling to these fuel bundles. However, some minimal cooling is essential, to ensure the safety of the bundles. As discussed in the paper, safety of these fuel bundles in the system and/or for those lying in the liner tube region of the reactor end fitting is ensured, during SBO, by resorting to passive means like 'stay-put', 'gravity- fill', 'D 2 0- steaming' etc. for cooling the bundles. The paper also describes various consequences emanating from these cooling schemes. (author). 6 refs., 2 tabs., 8 figs

  14. Perkins Nuclear Station, Units 1, 2, and 3: Final environmental statement (Docket Nos. STN 50-488, STN 50-489, and STN 50-490

    International Nuclear Information System (INIS)

    1975-10-01

    The proposed action is the issuance of a construction permit to the Duke Power Company for the construction of the Perkins Nuclear Station (PNS) Units 1, 2, and 3 located in Davie County, North Carolina. A total of 2402 acres will be used for the PNS site; another 1401 acres will be used for the Carter Creek Impoundment. Construction-related activities on the primary site will disturb about 617 acres. Approximately 631 acres of land will be required for transmission line right-of-way, and a railroad spur will affect 77 acres. This constitutes a minor local impact. The heat dissipation system will require a maximum water makeup of 55,816 gpm, of which 50,514 gpm will be consumed due to drift and evaporative losses. This amount represents 4% of the mean monthly flow of the Yadkin River. The cooling tower blowdown and chemical effluents from the station will increase the dissolved solids concentration in the Yadkin River by a maximum of 18 ppm. The thermal alterations and increases in total dissolved solids concentration will not significantly affect the aquatic productivity of the Yadkin River. 26 figs., 51 tabs

  15. Socioeconomic impacts of nuclear generating stations: Crystal River Unit 3 case study. Technical report 1 Oct 78-4 Jan 82

    International Nuclear Information System (INIS)

    Bergmann, P.A.

    1982-07-01

    The report documents a case study of the socioeconomic impacts of the construction and operation of the Crystal River Unit 3 nuclear power station. It is part of a major post-licensing study of the socioeconomic impacts at twelve nuclear power stations. The case study covers the period beginning with the announcement of plans to construct the reactor and ending in the period, 1980-81. The case study deals with changes in the economy, population, settlement patterns and housing, local government and public services, social structure, and public response in the study area during the construction/operation of the reactor. A regional modeling approach is used to trace the impact of construction/operation on the local economy, labor market, and housing market. Emphasis in the study is on the attribution of socioeconomic impacts to the reactor or other causal factors. As part of the study of local public response to the construction/operation of the reactor, the effects of the Three Mile Island accident are examined

  16. 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

  17. 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

  18. 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

  19. Use of Aquaporins to Achieve Needed Water Purity on the International Space Station for the Extravehicular Mobility Unit Space Suit System

    Science.gov (United States)

    Hill, Terry R.; Taylor, Brandon W.

    2012-01-01

    With the retirement of the U.S. Space Shuttle fleet, the supply of extremely high quality water required for the Extravehicular Mobility Unit (EMU) space suit cooling on the International Space Station (ISS) will become a significant operational hardware challenge in the very near future. One proposed solution is the use of a filtration system consisting of a semipermeable membrane embedded with aquaporin proteins, a special class of transmembrane proteins that facilitate passive, selective transport of water in vivo. The specificity of aquaporins is such that only water is allowed through the protein structure, and it is this novel property that invites their adaptation for use in water filtration systems, specifically those onboard the ISS for the EMU space suit system. These proteins are also currently being developed for use in terrestrial filtration systems.

  20. Contamination movement around a permeable reactive barrier at Solid Waste Management Unit 12, Naval Weapons Station Charleston, North Charleston, South Carolina, 2009

    Science.gov (United States)

    Vroblesky, Don A.; Petkewich, Matthew D.; Conlon, Kevin J.

    2010-01-01

    The U.S. Geological Survey and the Naval Facilities Engineering Command Southeast investigated natural and engineered remediation of chlorinated volatile organic compound groundwater contamination at Solid Waste Management Unit 12 at the Naval Weapons Station Charleston, North Charleston, South Carolina, beginning in 2000. In early 2004, groundwater contaminants began moving around the southern end of a permeable reactive barrier (PRB) installed by a consultant in December 2002. The PRB is a 130-foot-long and 3-foot-wide barrier consisting of varying amounts of zero-valent iron with or without sand mixture. Contamination moving around the PRB probably has been transported at least 75 feet downgradient from the PRB at a rate of about 15 to 29 feet per year.

  1. 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

  2. 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

  3. 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

  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 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

  6. Evaluation of zeolite mixtures for decontaminating high-activity-level water at the Three Mile Island Unit 2 Nuclear Power Station

    International Nuclear Information System (INIS)

    Collins, E.D.; Campbell, D.O.; King, L.J.; Knauer, J.B.; Wallace, R.M.

    1984-05-01

    Mixtures of Linde Ionsiv IE-96 and Ionsiv A-51 were evaluated for use in the Submerged Demineralizer System (SDS) that was installed at the Three Mile Island Unit 2 Nuclear Power Station to decontaminate approx. 2780 m 3 of high-activity-level water. The original SDS flowsheet was conservatively designed for removal of cesium and strontium and would have required the use of approx. 60 SDS columns. Mixed zeolite tests were made on a 10 -5 scale and indicated that the appropriate ratio of IE-96/A-51 was 3/2. A mathematical model was used to predict the performance of the mixed zeolite columns in the SDS configuration and with the intended method of operation. Actual loading results were similar to those predicted for strontium and better than those predicted for cesium. The number of SDS columns needed to process the HALW was reduced to approx. 10. 6 references, 4 figures, 2 tables

  7. 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

  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 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

  10. 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

  11. 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

  12. 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

  13. 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

  14. 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

  15. 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

  16. Critical evaluation of the nonradiological environmental technical specifications. Volume 3. Peach Bottom Atomic Power Station Units 2 and 3

    Energy Technology Data Exchange (ETDEWEB)

    Adams, S.M.; Cunningham, P.A.; Gray, D.D.; Kumar, K.D.; Witten, A.J.

    1976-08-10

    A comprehensive study of the data collected as part of the environmental Technical Specifications program for Units 2 and 3 of the Peach Bottom Nuclear Power Plant was conducted for the Office of Regulatory Research of the U.S. Nuclear Regulatory Commission. The program included an analysis of both the hydrothermal and ecological monitoring data collected from 1967 through 1976. Specific recommendations are made for improving both the present hydrothermal and ecological monitoring programs. Hydrothermal monitoring would be improved by more complete reporting of in-plant operating parameters. In addition, the present boat surveys could be discontinued, and monitoring efforts could be directed toward expanding the present thermograph network. Ecological monitoring programs were judged to be of high quality because standardized collection techniques, consistent reporting formats, and statistical analyses were performed on all of the data and were presented in an annual report. Sampling for all trophic groups was adequate for the purposes of assessing power plant induced perturbations. Considering the extensive period of preoperational data (six years) and operational data (three years) available for analysis, consideration could be given to reducing monitoring effort after data have been collected for a period when both units are operating at full capacity. In this way, an assessment of the potential ecological impact of the Peach Bottom facility can be made under conditions of maximum plant induced perturbations.

  17. Critical evaluation of the nonradiological environmental technical specifications. Volume 3. Peach Bottom Atomic Power Station Units 2 and 3

    International Nuclear Information System (INIS)

    Adams, S.M.; Cunningham, P.A.; Gray, D.D.; Kumar, K.D.; Witten, A.J.

    1976-01-01

    A comprehensive study of the data collected as part of the environmental Technical Specifications program for Units 2 and 3 of the Peach Bottom Nuclear Power Plant was conducted for the Office of Regulatory Research of the U.S. Nuclear Regulatory Commission. The program included an analysis of both the hydrothermal and ecological monitoring data collected from 1967 through 1976. Specific recommendations are made for improving both the present hydrothermal and ecological monitoring programs. Hydrothermal monitoring would be improved by more complete reporting of in-plant operating parameters. In addition, the present boat surveys could be discontinued, and monitoring efforts could be directed toward expanding the present thermograph network. Ecological monitoring programs were judged to be of high quality because standardized collection techniques, consistent reporting formats, and statistical analyses were performed on all of the data and were presented in an annual report. Sampling for all trophic groups was adequate for the purposes of assessing power plant induced perturbations. Considering the extensive period of preoperational data (six years) and operational data (three years) available for analysis, consideration could be given to reducing monitoring effort after data have been collected for a period when both units are operating at full capacity. In this way, an assessment of the potential ecological impact of the Peach Bottom facility can be made under conditions of maximum plant induced perturbations

  18. Corrective Action Decision Document for Corrective Action Unit 490: Station 44 Burn Area, Tonopah Test Range, Nevada (Rev. No.: 0, February 2001)

    Energy Technology Data Exchange (ETDEWEB)

    DOE/NV

    2001-02-23

    This Corrective Action Decision Document identifies and rationalizes the U.S. Department of Energy, Nevada Operations Office's selection of a recommended Corrective Action Alternative (CAA) appropriate to facilitate the closure of Corrective Action Unit (CAU) 490, Station 44 Burn Area, Tonopah Test Range (TTR), Nevada, under the Federal Facility Agreement and Consent Order. Corrective Action Unit 490 is located on the Nellis Air Force Range and the Tonopah Test Range and is approximately 140 miles northwest of Las Vegas, Nevada. This CAU is comprised of four Corrective Action Sites (CASs): 03-56-001-03BA, Fire Training Area (located southwest of Area 3); RG-56-001-RGBA, Station 44 Burn Area (located west of Main Lake); 03-58-001-03FN, Sandia Service Yard (located north of the northwest corner of Area 3); and 09-54-001-09L2, Gun Propellant Burn Area (located south of the Area 9 Compound on the TTR). A Corrective Action Investigation was performed in July and August 2000, and analytes detected during the corrective action investigation were evaluated against preliminary action levels to determine contaminants of concern (COCs). There were no COCs identified in soil at the Gun Propellant Burn Area or the Station 44 Burn Area; therefore, there is no need for corrective actions at these two sites. Five soil samples at the Fire Training Area and seven at the Sandia Service Yard exceeded PALs for total petroleum hydrocarbons-diesel. Upon the identification of COCs specific to CAU 490, Corrective Action Objectives were developed based on a review of existing data, future use, and current operations at the TTR, with the following three CAAs under consideration: Alternative 1 - No Further Action, Alternative 2 - Closure In Place - No Further Action With Administrative Controls, and Alternative 3 - Clean Closure by Excavation and Disposal. These alternatives were evaluated based on four general corrective action standards and five remedy selection decision factors. Based

  19. Evaluation of severe accident risks and the potential for risk reduction: Surry Power Station, Unit 1: Draft report for comment

    International Nuclear Information System (INIS)

    Benjamin, A.S.; Boyd, G.J.; Kunsman, D.M.; Murfin, W.B.; Williams, D.C.

    1987-02-01

    The Severe Accident Risk Reduction Program (SARRP) has completed a rebaselining of the risks to the public from a particular pressurized water reactor with a subatmospheric containment (Surry, Unit 1). Emphasis was placed on determining the magnitude and character of the uncertainties, rather than focusing on a point estimate. The risk-reduction potential of a set of proposed safety option backfits was also studied, and their costs and benefits were also evaluated. It was found that the risks from internal events are generally lower than previously evaluated in the Reactor Safety Study (RSS). However, certain unresolved issues (such as direct containment heating) caused the top of the uncertainty band to appear at a level that is comparable with the RSS point estimate. None of the postulated safety options appears to be cost effective for the Surry power plant. This work supports the Nuclear Regulatory Commission's assessment of severe accidents in NUREG-1150

  20. Evaluation of severe accident risks and the potential for risk reduction: Surry Power Station, Unit 1: Draft report for comment

    Energy Technology Data Exchange (ETDEWEB)

    Benjamin, A.S.; Boyd, G.J.; Kunsman, D.M.; Murfin, W.B.; Williams, D.C.

    1987-02-01

    The Severe Accident Risk Reduction Program (SARRP) has completed a rebaselining of the risks to the public from a particular pressurized water reactor with a subatmospheric containment (Surry, Unit 1). Emphasis was placed on determining the magnitude and character of the uncertainties, rather than focusing on a point estimate. The risk-reduction potential of a set of proposed safety option backfits was also studied, and their costs and benefits were also evaluated. It was found that the risks from internal events are generally lower than previously evaluated in the Reactor Safety Study (RSS). However, certain unresolved issues (such as direct containment heating) caused the top of the uncertainty band to appear at a level that is comparable with the RSS point estimate. None of the postulated safety options appears to be cost effective for the Surry power plant. This work supports the Nuclear Regulatory Commission's assessment of severe accidents in NUREG-1150.

  1. Preparative engineering on the Tomari Nuclear Power Station Unit 3. In-site measurement on wave pressure working to new type bank protection

    International Nuclear Information System (INIS)

    Matsumoto, Yoriaki; Hoshi, Hideki; Amano, Hideki

    2003-01-01

    The Tomari Nuclear Power Station Unit 3 is planned to construct it at sea-side area adjacent to southern-east portion of Unit 1 and 2, and has been carried out its preparative engineerings such as bank protection with about 670 m in length, its development, and so on, corresponding to it. Among them, as type of landfill for protection of important construction at its background the Amahata covered-block type bank protection developed by a series of hydrologic tests was adopted. This engineering was begun on March, 2001, and most of establishment on the landfill bank protection was finished on June, 2003. Then, an in-situ measurement aiming to obtain actual testing data and so on of wave pressure at this type of bank protection, was planned, to carry out its measurement at winter (October, 2002 to February, 2003) showing the highest wave at this sea area. Here were reported on relationship between incident wave and wave pressure feature working at new type bank protection together with describing on outlines of the in-situ measurement. (G.K.)

  2. 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...

  3. Corrective Action Investigation Plan for Corrective Action Unit 490: Station 44 Burn Area, Tonopah Test Range, Nevada (with Record of Technical Change No.1)

    International Nuclear Information System (INIS)

    2000-01-01

    This Corrective Action Investigation Plan (CAIP) contains the U.S. Department of Energy, Nevada Operations Office's approach to collect the data necessary to evaluate corrective action alternatives appropriate for the closure of Corrective Action Unit (CAU) 490 under the Federal Facility Agreement and Consent Order. Corrective Active Unit 490 consists of four Corrective Action Sites (CASs): 03-56-001-03BA, Fire Training Area (FTA); RG-56-001-RGBA, Station 44 Burn Area; 03-58-001-03FN, Sandia Service Yard; and 09-54-001-09L2, Gun Propellant Burn Area. These CASs are located at the Tonopah Test Range near Areas 3 and 9. Historically, the FTA was used for training exercises where tires and wood were ignited with diesel fuel. Records indicate that water and carbon dioxide were the only extinguishing agents used during these training exercises. The Station 44 Burn Area was used for fire training exercises and consisted of two wooden structures. The two burn areas (ignition of tires, wood, and wooden structures with diesel fuel and water) were limited to the building footprints (10 ft by 10 ft each). The Sandia Service Yard was used for storage (i.e., wood, tires, metal, electronic and office equipment, construction debris, and drums of oil/grease) from approximately 1979 to 1993. The Gun Propellant Burn Area was used from the 1960s to 1980s to burn excess artillery gun propellant, solid-fuel rocket motors, black powder, and deteriorated explosives; additionally, the area was used for the disposal of experimental explosive items. Based on site history, the focus of the field investigation activities will be to: (1) determine the presence of contaminants of potential concern (COPCs) at each CAS, (2) determine if any COPCs exceed field-screening levels and/or preliminary action levels, and (3) determine the nature and extent of contamination with enough certainty to support selection of corrective action alternatives for each CAS. The scope of this CAIP is to resolve the

  4. Corrective Action Investigation Plan for Corrective Action Unit 490: Station 44 Burn Area, Tonopah Test Range, Nevada (with Record of Technical Change No.1)

    Energy Technology Data Exchange (ETDEWEB)

    U.S. Department of Energy, Nevada Operations Office

    2000-06-09

    This Corrective Action Investigation Plan (CAIP) contains the U.S. Department of Energy, Nevada Operations Office's approach to collect the data necessary to evaluate corrective action alternatives appropriate for the closure of Corrective Action Unit (CAU) 490 under the Federal Facility Agreement and Consent Order. Corrective Active Unit 490 consists of four Corrective Action Sites (CASs): 03-56-001-03BA, Fire Training Area (FTA); RG-56-001-RGBA, Station 44 Burn Area; 03-58-001-03FN, Sandia Service Yard; and 09-54-001-09L2, Gun Propellant Burn Area. These CASs are located at the Tonopah Test Range near Areas 3 and 9. Historically, the FTA was used for training exercises where tires and wood were ignited with diesel fuel. Records indicate that water and carbon dioxide were the only extinguishing agents used during these training exercises. The Station 44 Burn Area was used for fire training exercises and consisted of two wooden structures. The two burn areas (ignition of tires, wood, and wooden structures with diesel fuel and water) were limited to the building footprints (10 ft by 10 ft each). The Sandia Service Yard was used for storage (i.e., wood, tires, metal, electronic and office equipment, construction debris, and drums of oil/grease) from approximately 1979 to 1993. The Gun Propellant Burn Area was used from the 1960s to 1980s to burn excess artillery gun propellant, solid-fuel rocket motors, black powder, and deteriorated explosives; additionally, the area was used for the disposal of experimental explosive items. Based on site history, the focus of the field investigation activities will be to: (1) determine the presence of contaminants of potential concern (COPCs) at each CAS, (2) determine if any COPCs exceed field-screening levels and/or preliminary action levels, and (3) determine the nature and extent of contamination with enough certainty to support selection of corrective action alternatives for each CAS. The scope of this CAIP is to resolve

  5. Technical specifications, Braidwood Station Unit Nos. 1 and 2 (Docket Nos. STN 50-456 and STN 50-457): Appendix ''A'' to License No. NPF-72, [October 1986-July 1987

    International Nuclear Information System (INIS)

    1987-07-01

    The Braidwood Station, Units 1 and 2, technical specifications were prepared by the US Nuclear Regulatory Commission to set forth the limits, operating conditions, and other requirements applicable to a nuclear reactor facility as set forth in Section 50.36 of 10 CFR Part 50 for the protection of the health and safety of the public

  6. 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

  7. 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

  8. Release of radionuclides and chelating agents from cement-solidified decontamination low-level radioactive waste collected from the Peach Bottom Atomic Power Station Unit 3

    Energy Technology Data Exchange (ETDEWEB)

    Akers, D.W.; Kraft, N.C.; Mandler, J.W. [EG and G Idaho, Inc., Idaho Falls, ID (United States)

    1994-03-01

    As part of a study being performed for the Nuclear Regulatory Commission (NRC), small-scale waste-form specimens were collected during a low oxidation-state transition-metal ion (LOMI)-nitric permanganate (NP)-LOMI solidification performed in October 1989 at the Peach Bottom Atomic Power Station Unit 3. The purpose of this program was to evaluate the performance of cement-solidified decontamination waste to meet the low-level waste stability requirements defined in the NRC`s ``Technical Position on Waste Form,`` Revision 1. The samples were acquired and tested because little data have been obtained on the physical stability of actual cement-solidified decontamination ion-exchange resin waste forms and on the leachability of radionuclides and chelating agents from those waste forms. The Peach Bottom waste-form specimens were subjected to compressive strength, immersion, and leach testing in accordance with the NRC`s ``Technical Position on Waste Form,`` Revision 1. Results of this study indicate that the specimens withstood the compression tests (>500 psi) before and after immersion testing and leaching, and that the leachability indexes for all radionuclides, including {sup 14}C, {sup 99}{Tc}, and {sup 129}I, are well above the leachability index requirement of 6.0, required by the NRC`s ``Technical Position on Waste Form,`` Revision 1.

  9. 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 16 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 conduit supports. The scope and methodologies for the CAP workscopes as summarized in Revision 0 to the conduit support project status reports and as detailed in related documents referenced in this evaluation were developed to resolve various design issues raised by the Comanche Peak Response Team (CPRT); CYGNA Energy Services (CYGNA); and the NRC staff. The NRC staff concludes that the CAP workscopes for conduit supports provide a comprehensive program for resolving the associated technical concerns identified by the CPRT, CYGNA, and the NRC staff. The NRC staff further concludes that implementation of the CAP workscope for conduit supports ensures that the design of conduit supports at CPSES satisfies the applicable requirements of 10 CFR Part 50

  10. A pilot application of risk-based methods to establish in-service inspection priorities for nuclear components at Surry Unit 1 Nuclear Power Station

    International Nuclear Information System (INIS)

    Vo, T.; Gore, B.; Simonen, F.; Doctor, S.

    1994-08-01

    As part of the Nondestructive Evaluation Reliability Program sponsored by the US Nuclear Regulatory Commission, the Pacific Northwest Laboratory is developing a method that uses risk-based approaches to establish in-service inspection plans for nuclear power plant components. This method uses probabilistic risk assessment (PRA) results and Failure Modes and Effects Analysis (FEMA) techniques to identify and prioritize the most risk-important systems and components for inspection. The Surry Nuclear Power Station Unit 1 was selected for pilot applications of this method. The specific systems addressed in this report are the reactor pressure vessel, the reactor coolant, the low-pressure injection, and the auxiliary feedwater. The results provide a risk-based ranking of components within these systems and relate the target risk to target failure probability values for individual components. These results will be used to guide the development of improved inspection plans for nuclear power plants. To develop inspection plans, the acceptable level of risk from structural failure for important systems and components will be apportioned as a small fraction (i.e., 5%) of the total PRA-estimated risk for core damage. This process will determine target (acceptable) risk and target failure probability values for individual components. Inspection requirements will be set at levels to assure that acceptable failure probabilistics are maintained

  11. 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

  12. Investigation of Contaminated Ground Water at Solid Waste Management Unit 12, Naval Weapons Station Charleston, North Charleston, South Carolina, 2006-2007

    Science.gov (United States)

    Vroblesky, Don A.; Petkewich, Matthew D.; Lowery, Mark A.; Conlon, Kevin J.; Harrelson, Larry G.

    2008-01-01

    The U.S. Geological Survey investigated natural and engineered remediation of chlorinated volatile organic compound (VOC) ground-water contamination at Solid Waste Management Unit 12 at the Naval Weapons Station Charleston, North Charleston, South Carolina, beginning in 2000. The primary contaminants of interest in the study are tetrachloroethene, 1,1,1-trichloroethane, trichloroethene, cis-1,2-dichloroethene, vinyl chloride, 1,1-dichloroethane, and 1,1-dichloroethene. The permeable reactive barrier (PRB) along the main axis of the contaminant plume appears to be actively removing contamination. In contrast to the central area of the PRB, the data from the southern end of the PRB indicate that contaminants are moving around the PRB. Concentrations in wells 12MW-10S and 12MW-03S, upgradient from the PRB, showed a general decrease in VOC concentrations. VOC concentrations in some wells in the forest showed a sharp increase, followed by a decrease. In 2007, the VOC concentrations began to increase in well 12MW-12S, downgradient from the PRB and thought to be unaffected by the PRB. The VOC-concentration changes in the forest, such as at well 12MW-12S, may represent lateral shifting of the plume in response to changes in ground-water-flow direction or may represent movement of a contamination pulse through the forest.

  13. 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

  14. Marble Hill Nuclear Generating Station, Units 1 and 2: Final environmental statement (Docket Nos. STN 50-546 and STN 50-547)

    International Nuclear Information System (INIS)

    1976-09-01

    The proposed action is the issuance of construction permits to the Public Service Company of Indiana, Inc., Northern Indiana Public Service Company, Inc., East Kentucky Power Cooperative, Inc., and Wabash Valley Power Association for the construction of the Marble Hill Nuclear Generating Station, Units 1 and 2 (MH 1and2). The 987-acre site is predominately forest and cropland. Construction-related activities on the site would disturb about 250 acres. The portion of this land not be used for the plant facilities, parking lots, roads, etc., will be restored by seeding and landscaping. The temporary removal of vegetation will tend to promote erosion. Increased siltation and turbidity can be expected in local streams during construction, but measures will be taken to minimize these effects. A maximum of 69 cfs of cooling water will be withdrawn from the Ohio River of which cfs will be returned to the river via pipeline with the dissolved solids concentration increased by a factor of about 6. About cfs will be evaporated to the atmosphere by the cooling towers. The volume of discharge (9 cfs) is very small compared with the river flow (annual mean is about 110,000 cfs) and the thermal effect on the river ecosystem is not expected to be significant. Chemical discharges from the plant will be diluted to concentrations below those which might adversely affect aquatic biota. The risk associated with accidental radiation exposure will be very low. 43 figs., 115 tabs

  15. Draft environmental statement related to the proposed Jamesport Nuclear Power Station, Units 1 and 2: (Docket Nos. STN-50-516 and STN-50-517)

    International Nuclear Information System (INIS)

    1975-02-01

    The proposed action is the issuance of construction permits to the Long Island Lighting Company for the construction of the Jamesport Nuclear Power Station, Units 1 and 2, located on Long Island Sound in the Town of Riverhead, New York. Operation of the proposed once-through cooling system will result in the heating of 4180 cfs of water by 18/degree/F. Phytoplankton, zooplankton, and ichthyoplankton will be entrained by the cooling system. The organisms in approximately 40 /times/ 10 9 ft 3 of water per year will suffer direct mortality due to chlorination and heat shock. The risk associated with accidental radiation exposure will be very low. A bottom area of some 105.5 acres will be affected by dredging and jetty construction. Of this total, 4.35 acres will be permanently replaced by jetties, and 101.15 acres will be temporarily (a total of four years) disrupted by dredging. This impact will be temporary, since the dredged areas will be recolonized by the benthic community upon completion of work. There is a potential for substantial impingement loss of fishes on the intake screens which will require additional data to quantify. Approximately 39 miles of transmission lines will be constructed. Ninety-two percent of the total routings utilize existing rights-of-way, railroad rights-of-way, or new rights-of-way immediately adjacent to railroad rights-of-way. The rights-of-way will require approximately 621 acres. 65 refs., 64 tabs

  16. Technical evaluation report on the seven main transformer failures at the North Anna Power Station, Units 1 and 2 (Docket Nos. 50-338, 50-339)

    International Nuclear Information System (INIS)

    Dalton, K.J.; Kresser, J.V.; Savage, J.W.; Selan, J.C.

    1984-01-01

    This report documents technical evaluations on various aspects pertaining to the seven main transformer failures at the North Anna Power Station, Units 1 and 2. These reports cover the subjects of Probability Risk Assessment (PRA), Failure Modes and Effects Analysis (FMEA), Root Causes, Protection Systems, Modifications, Failure Statistics, and Generic Aspects. The PRA determined that the contribution from a main transformer failure affecting plant safety systems so as to increase the risk to the public health and safety is negligible. The FMEA determined that a main transformer failure can have primary and secondary effects on plant safety system operation. The evaluation of the Root Causes found that no single common cause contributed to the seven failures. Each failure was found to have specific circumstances for initiating the failure. Both the generator and transformer primary protection systems were found to perform correctly and were designed within industry standards and practices. The proposed modifications resulting from the analyses of the failures will improve system reliability and integrity, and will reduce potentially damaging effects. The failure statistic survey found very limited data bases from which a meaningful correlation could be ascertained. The statistical comparison found no appreciable anomalies with the NAPS failures. The evaluation of all the available information and the results of the separate reports on the main transformer failures found that several generic concerns exist

  17. Integrated plant safety assessment: Systematic Evaluation Program, San Onofre Nuclear Generating Station, Unit 1 (Docket No. 50-206): Final report

    International Nuclear Information System (INIS)

    1986-12-01

    The Systematic Evaluation Program was initiated in February 1977 by the US Nuclear Regulatory Commission to review the designs of older operating nuclear reactor plants to reconfirm and document their safety. The review provides: (1) an assessment of how these plants compare with current licensing safety requirements relating to selected issues; (2) a basis for deciding on how these differences should be resolved in an integrated plant review; and (3) a documented evaluation of plant safety. This report documents the review of San Onofre Nuclear Generating Station, Unit 1, operated by Southern California Edison Company. The San Onofre plant is one of ten plants reviewed under Phase II of this program. This report indicates how 137 topics selected for review under Phase I of the program were addressed. Equipment and procedural changes have been identified as a result of the review. This report will be one of the bases in considering the issuance of a full-term operating license in place of the existing provisional operating license. This report also addresses the comments and recommendations made by the Advisory Committee on Reactor Safeguards in connection with its review of the draft report issued in April 1985

  18. Technical evaluation report on the adequacy of station electric distribution system voltages for the Point Beach Nuclear Plant, Units 1 and 2. (Docket Nos. 50-266, 50-301)

    International Nuclear Information System (INIS)

    White, R.L.

    1983-01-01

    This report documents the technical evaluation of the adequacy of the station electric distribution system voltages for the Point Beach Nuclear Plant, Units 1 and 2. The evaluation is to determine if the onsite distribution system, in conjunction with the offsite power sources, has sufficient capacity to automatically start and operate all Class 1E loads within the equipment voltage ratings under certain conditions established by the Nuclear Regulatory Commission. For the worst case conditions study submitted by the licensee, it was shown that the station electric distribution system voltages would be adequate to start and operate 4160-volt and 480-volt Class 1E loads and their associated low voltage controls

  19. International Space Station Assembly

    Science.gov (United States)

    1999-01-01

    The International Space Station (ISS) is an unparalleled international scientific and technological cooperative venture that will usher in a new era of human space exploration and research and provide benefits to people on Earth. On-Orbit assembly began on November 20, 1998, with the launch of the first ISS component, Zarya, on a Russian Proton rocket. The Space Shuttle followed on December 4, 1998, carrying the U.S.-built Unity cornecting Module. Sixteen nations are participating in the ISS program: the United States, Canada, Japan, Russia, Brazil, Belgium, Denmark, France, Germany, Italy, the Netherlands, Norway, Spain, Sweden, Switzerland, and the United Kingdom. The ISS will include six laboratories and be four times larger and more capable than any previous space station. The United States provides two laboratories (United States Laboratory and Centrifuge Accommodation Module) and a habitation module. There will be two Russian research modules, one Japanese laboratory, referred to as the Japanese Experiment Module (JEM), and one European Space Agency (ESA) laboratory called the Columbus Orbital Facility (COF). The station's internal volume will be roughly equivalent to the passenger cabin volume of two 747 jets. Over five years, a total of more than 40 space flights by at least three different vehicles - the Space Shuttle, the Russian Proton Rocket, and the Russian Soyuz rocket - will bring together more than 100 different station components and the ISS crew. Astronauts will perform many spacewalks and use new robotics and other technologies to assemble ISS components in space.

  20. The analysis of the cases of circulatory and respiratory arrest in the work of the Regional Unit of Ambulance Service - Sródmieście Station.

    Science.gov (United States)

    Chemperek, Ewa; Mikuła, Agnieszka; Goniewicz, Mariusz; Krawczyk, Wojciech

    2004-01-01

    The major causes of deaths all over the world are circulatory system diseases, neoplasms and injuries. Each man can become a participant of the event which results in life-threatening emergencies and the most immediate possible actions are essential. The period of time for starting efficient life-restoration actions is very short, estimated at 4-5 minutes. Ambulance Service is a medical organization created to apply aid in life-threatening emergencies. The standards of the developed western countries determine the arrival time at 7-10 minutes from the call time. Both first-aid applied by the accident witnesses and efficient actions of ambulance service have significance for effective pre-hospital aid and increasing the chances of survival of people in need. The study analysed emergency records of the ambulance cars of the Regional Unit of Ambulance Service - Sródmieście Station in Lublin in the year 2000. 3,723 calls were recorded. In 142 cases complete resuscitation actions were carried out due to circulatory and respiratory arrest. The records selected this way went through a detailed analysis. In 3.8% of the interventions of emergency teams the necessity of applying advanced life support was observed. The time of arrival at the scene, transport of the patient to the admission room as well as efficiency of resuscitation comply with the European standards. The efficiency of resuscitation actions estimated at 51.4% depended on the age of the patient, the cause of circulatory and respiratory arrest and ambulance arrival time. Taking up basic life support by witnesses of the event was observed in 2.8% of cases, in 8.5% aid was applied by the medical staff members who happened to be at the scene.

  1. Efforts to Reduce International Space Station Crew Maintenance Time in the Management of the Extravehicular Mobility Unit Transport Loop Water Quality

    Science.gov (United States)

    Etter,David; Rector, Tony; Boyle, robert; Zande, Chris Vande

    2012-01-01

    The EMU (Extravehicular Mobility Unit) contains a semi-closed-loop re-circulating water circuit (Transport Loop) to absorb heat into a LCVG (Liquid Coolant and Ventilation Garment) worn by the astronaut. A second, single-pass water circuit (Feed-water Loop) provides water to a cooling device (Sublimator) containing porous plates, and that water sublimates through the porous plates to space vacuum. The cooling effect from the sublimation of this water translates to a cooling of the LCVG water that circulates through the Sublimator. The quality of the EMU Transport Loop water is maintained through the use of a water processing kit (ALCLR - Airlock Cooling Loop Remediation) that is used to periodically clean and disinfect the water circuit. Opportunities to reduce crew time associated with ALCLR operations include a detailed review of the historical water quality data for evidence to support an extension to the implementation cycle. Furthermore, an EMU returned after 2-years of use on the ISS (International Space Station) is being used as a test bed to evaluate the results of extended and repeated ALCLR implementation cycles. Finally, design, use and on-orbit location enhancements to the ALCLR kit components are being considered to allow the implementation cycle to occur in parallel with other EMU maintenance and check-out activities, and to extend the life of the ALCLR kit components. These efforts are undertaken to reduce the crew-time and logistics burdens for the EMU, while ensuring the long-term health of the EMU water circuits for a post- Shuttle 6-year service life.

  2. Effect of the californian red worm (Eisenia foetida during the composteo and vermicomposteo in properties of the Experimental Station of the Academic Rural Unit Carmen Pampa

    Directory of Open Access Journals (Sweden)

    Paco Gabriel

    2011-08-01

    Full Text Available The objective of the present work was to evaluate the biotransformación of the organic residuals, of kitchen (Rc remains, pulp of coffee (Pc and cardboard (C by means of compostaje methods and vermicompostaje. The investigation was taken I end up in the Experimental Station, module of lombricultura of the Career of Agronomic Engineering of Carmen Pampa Unit Academic Campesina, located in the community of Carmen Pampa of the Municipality of Coroico Department of La Paz, Bolivia. The used design was totally at random with 3 treatments and 3 repetitions, to compare among obtaining methods in quality it used the test of fixed effects and it stops quantity the test "t" of Student. The quantity of initial sustrato studied in compostaje was of 1m3 and 0,02m3 vermicompostaje ending up culminating the investigation in 120 days. The results in decomposition are obtained in smaller time by means of the method vermicompostaje in Pc in advance of three months of 98.33% continued by C and Rc; while in compostaje it was the treatment with Rc of 3 months with 3 weeks with 90.40% of decomposition, continued by Pc and C. In quantity, starting from 1m3 of initial sustrato bigger bioabono was obtained with Pc 271.62 kg, 465.83 kg, Rc 249.71 kg, 446.00 kg and C 212.48 kg, 404.00 kg, in compost and vermicompost respectively. The chemical composition of the bioabonos of Rc, Pc, C in N and P is tipificados like first floor, high K, Ca in low compost and half vermicompost, half Mg, MO under and lightly alkaline pH to neuter in the two obtaining methods.

  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)

    1990-04-01

    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

  4. Final environmental statement related to the proposed construction of Douglas Point Nuclear Generating Station, Units 1 and 2: (Docket Nos. 50-448 and 50-449)

    International Nuclear Information System (INIS)

    1976-03-01

    The proposed action is the issuance of construction permits to the Potomac Electric Power Company for the construction of the Douglas Point Nuclear Generating Station, Units 1 and 2, located in Charles County, Maryland. The exhaust steam will be cooled via a closed-cycle mode incorporating natural-draft wet cooling towers. The water used in the cooling system will be obtained from the Potomac River. Construction-related activities on the site will convert about 290 acres of the 1390 acres of forested land at the Douglas Point site to industrial use. In addition to acreage at the site, approximately 4.5 miles of transmission corridor will require about 211 acres of land for rights-of-way. This corridor will connect with 27 miles of existing rights-of-way over which a line connecting Possum Point to Burches Hill has already been approved. The installation of new transmission line, uniquely identified with Douglas Point, along the existing right-of-way will involve approximately 464 additional acres. As described in the application, the maximum river water intake will be about 97,200 gpm. Of this, a maximum of about 28,000 gpm will be lost in drift or evaporation from the cooling towers. About 700 gpm maximum of fresh well water will be consumed. It is conservatively assumed that all aquatic organisms entrained in the service water system will be killed due to thermal and mechanical shock. It is further estimated that at 97,200 gpm maximum total river water intake, the maximum impact on the striped bass fishery will be a reduction of <5%. The risk associated with accidental radiation exposure is very low. 32 figs., 59 tabs

  5. ARRA-funded VS30 measurements using multi-technique approach at strong-motion stations in California and central-eastern United States

    Science.gov (United States)

    Yong, Alan; Martin, Antony; Stokoe, Kenneth; Diehl, John

    2013-01-01

    Funded by the 2009 American Recovery and Reinvestment Act (ARRA), we conducted geophysical site characterizations at 191 strong-motion stations: 187 in California and 4 in the Central-Eastern United States (CEUS). The geophysical methods used at each site included passive and active surface-wave and body-wave techniques. Multiple techniques were used at most sites, with the goal of robustly determining VS (shear-wave velocity) profiles and VS30 (the time-averaged shear-wave velocity in the upper 30 meters depth). These techniques included: horizontal-to-vertical spectral ratio (HVSR), two-dimensional (2-D) array microtremor (AM), refraction microtremor (ReMi™), spectral analysis of surface wave (SASW), multi-channel analysis of surface waves (Rayleigh wave: MASRW; and Love wave: MASLW), and compressional- and shear-wave refraction. Of the selected sites, 47 percent have crystalline, volcanic, or sedimentary rock at the surface or at relatively shallow depth, and 53 percent are of Quaternary sediments located in either rural or urban environments. Calculated values of VS30 span almost the full range of the National Earthquake Hazards Reduction Program (NEHRP) Site Classes, from D (stiff soils) to B (rock). The NEHRP Site Classes based on VS30 range from being consistent with the Class expected from analysis of surficial geology, to being one or two Site Classes below expected. In a few cases where differences between the observed and expected Site Class occurred, it was the consequence of inaccurate or coarse geologic mapping, as well as considerable degradation of the near-surface rock. Additionally, several sites mapped as rock have Site Class D (stiff soil) velocities, which is due to the extensive weathering of the surficial rock.

  6. Palo Verde Nuclear Generating Station, Units 1, 2 and 3 (Docket Nos. STN 50-528, STN 50-529 and STN 50-530): Draft supplement to the Final environmental satement

    International Nuclear Information System (INIS)

    1975-11-01

    The proposed action is the issuance of construction permits to the Arizona Public Service Company for the construction of the Palo Verde Nuclear Generating Station, Units 1, 2, and 3. Preparation of the 3800-acre site will involve the clearing of up to 2500 acres of land, 1500 of which will be permanently devoted to station facilities. An additional 1200- to 1300-acre evaporation pond will ultimately be developed during the lifetime of the station. About 2200 site acres, previously devoted to agriculture, will be excluded from this land use. Soil disturbance during construction of the station, transmission lines, and water conveyance pipeline will tend to promote erosion and increase siltation in local ephemeral water courses. Stringent measures will be taken to minimize these effects. Station, transmission line, and water pipeline construction will kill, remove, displace, or otherwise disturb involved flora and fauna, and will eliminate varying amounts of wildlife breeding, nesting, and forage habitat. These will not be important permanent impacts to the population stability and structure of the involved local ecosystems of the Sonoran desert; however, measures will be taken to minimize such effects as do result from the proposed action. The pumping of groundwater will cause a local drawdown of about 1 ft/yr, less than that currently occurring; hence, the impact is considered acceptable. 1 fig., 20 tabs

  7. 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

  8. 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...

  9. Addendum to the Corrective Action Decision Document/Closure Report for Corrective Action Unit 321: Area 22 Weather Station Fuel Storage Nevada Test Site, Nevada, Revision 0

    Energy Technology Data Exchange (ETDEWEB)

    Lynn Kidman

    2008-10-01

    This document constitutes an addendum to the August 2001, Corrective Action Decision Document / Closure Report for Corrective Action Unit 321: Area 22 Weather Station Fuel Storage as described in the document Recommendations and Justifications for Modifications for Use Restrictions Established under the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office Federal Facility Agreement and Consent Order (UR Modification document) dated February 2008. The UR Modification document was approved by NDEP on February 26, 2008. The approval of the UR Modification document constituted approval of each of the recommended UR modifications. In conformance with the UR Modification document, this addendum consists of: • This cover page that refers the reader to the UR Modification document for additional information • The cover and signature pages of the UR Modification document • The NDEP approval letter • The corresponding section of the UR Modification document This addendum provides the documentation justifying the cancellation of the UR for CAS 22-99-05, Fuel Storage Area. This UR was established as part of a Federal Facility Agreement and Consent Order (FFACO) corrective action and is based on the presence of contaminants at concentrations greater than the action levels established at the time of the initial investigation (FFACO, 1996; as amended August 2006). Since this UR was established, practices and procedures relating to the implementation of risk-based corrective actions (RBCA) have changed. Therefore, this UR was re-evaluated against the current RBCA criteria as defined in the Industrial Sites Project Establishment of Final Action Levels (NNSA/NSO, 2006c). This re-evaluation consisted of comparing the original data (used to define the need for the UR) to risk-based final action levels (FALs) developed using the current Industrial Sites RBCA process. The re-evaluation resulted in a recommendation to remove the UR because

  10. Final supplement to the final environmental statement related to construction of Palo Verde Nuclear Generating Station Units 1, 2 and 3 (Docket Nos. STN 50-528, STN 50-529, and STN 50-530)

    International Nuclear Information System (INIS)

    1976-02-01

    The proposed action is the issuance of construction permits to the Arizona Public Service Company for the construction of the Palo Verde Nuclear Generating Station, Units 1, 2, and 3. Preparation of the 3800-acre site will involve the clearing of up to 2500 acres of land, 1500 of which will ultimately be developed during the lifetime of the station. About 2200 site acres, previously devoted to agriculture, will be excluded from this land use. Soil disturbance during construction of the station, transmission lines, and water conveyance pipeline will tend to promote erosion and increase siltation local ephemeral water courses. Stringent measures will be taken to minimize these effects (Sec. 4.5). Station, transmission line, and water pipeline construction will kill, remove, displace, or otherwise disturb involved flora and fauna, and will eliminate varying amounts of wildlife breeding, nesting, and forage habitat. These will not be important permanent impacts to the population stability and structure of the involved local ecosystems of the Sonoran desert; however, measures will be taken to minimize such effects as do results from the proposed action. 26 refs., 1 fig., 20 tabs

  11. Station Transfers

    Data.gov (United States)

    Department of Homeland Security — ixed rail transit external system transfers for systems within the Continental United States, Alaska, Hawaii, the District of Columbia, and Puerto Rico. The modes of...

  12. 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

  13. Technical-evaluation report on the proposed technical-specification changes for the inservice surveillance of safety-related hydraulic and mechanical snubbers at the Millstone Nuclear Power Station, Unit 2 (Docket No. 50-336)

    International Nuclear Information System (INIS)

    Selan, J.C.

    1983-01-01

    This report documents the technical evaluation of the proposed Technical Specification changes to Limiting Conditions for Operation, Surveillance Requirements and Bases for safety-related hydraulic and mechanical snubbers at the Millstone Nuclear Power Station, Unit 2. The evaluation is to determine whether the proposed Technical Specifications are in conformance with the model Standard Technical Specification set forth by the NRC. A check list, Appendix A of this report, compares the licensee's submittal with the NRC requirements and includes Proposed Resolution of the Deviations

  14. Safety Evaluation Report related to the operation of Palo Verde Nuclear Generating Station, Units 1, 2, and 3 (Docket Nos. STN 50-528, STN 50-529, and STN 50-530)

    International Nuclear Information System (INIS)

    1984-10-01

    Supplement No. 6 to the Safety Evaluation Report for the application filed by Arizona Public Service Company, et al., for licenses to operate the Palo Verde Nuclear Generating Station, Units 1, 2, and 3 (Docket Nos. STN 50-528/529/530), located in Maricopa County, Arizona, 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 an evaluation of (1) additional information submitted by the applicant since Supplement No. 5 was issued and (2) matters that the staff had under review when Supplement No. 5 was issued

  15. Safety Evaluation Report related to the operation of Palo Verde Nuclear Generating Station, Units 1, 2, and 3 (Docket Nos. STN 50-528, STN 50-529, and STN 50-530). Supplement No. 7

    International Nuclear Information System (INIS)

    1984-12-01

    Supplement No. 7 to the Safety Evaluation Report for the application filed by Arizona Public Service Company et al. for licenses to operate the Palo Verde Nuclear Generating Station, Units 1, 2, and 3 (Docket Nos. STN 50-528/529/530), located in Maricopa County, Arizona, 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 an evaluation of: (1) additional information submitted by the applicant since Supplement No. 6 was issued; and (2) matters that the staff had under review when Supplement No. 6 was issued

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

    International Nuclear Information System (INIS)

    1982-06-01

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

  17. Programmatic environmental impact statement related to decontamination and disposal of radioactive wastes resulting from March 28, 1979 accident, Three Mile Island Nuclear Station, Unit 2 (Docket No. 50-320): Draft

    International Nuclear Information System (INIS)

    1986-12-01

    In accordance with the National Environmental Policy Act and the Commission's implementing regulations and its April 27, 1981 Statement of Policy, the Programmatic Environmental Impact Statement related to decontamination and disposal of radioactive wastes resulting from March 28, 1979, accident Three Mile Island Nuclear Station, Unit 2 NUREG-0683 (PEIS) is being supplemented. This draft supplement updates the environmental evaluation of accident-generated water disposal alternatives published in the PEIS, utilizing more complete and current information. Also, the draft supplement includes a specific environmental evaluation of the licensee's recently submitted proposal for water disposition

  18. Safety Evaluation Report related to the operation of Palo Verde Nuclear Generating Station, Units 1, 2, and 3 (Docket Nos. STN 50-528, STN 50-529, and STN 50-530). Supplement No. 9

    International Nuclear Information System (INIS)

    1985-12-01

    Supplement No. 9 to the Safety Evaluation Report for the application filed by Arizona Public Service Company et al. for licenses to operate the Palo Verde Nuclear Generating Station, Units 1, 2 and 3 (Docket Nos. STN 50-528/529/530), located in Maricopa County, Arizona, 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 an evaluation of: (1) additional information submitted by the applicant since Supplement No. 8 was issued; and (2) matters that the staff had under review when Supplement No. 8 was issued, specifically those issues which required resolution prior to Unit 2 fuel loading and testing up to 5% of full power

  19. Safety Evaluation Report related to the operation of Palo Verde Nuclear Generating Station, Units 1, 2, and 3 (Dockets Nos. STN 50-528, STN 50-529, and STN 50-530)

    International Nuclear Information System (INIS)

    1987-03-01

    Supplement No. 11 to the Safety Evaluation Report for the application filed by Arizona Public Service Company et al. for licenses to operate the Palo Verde Nuclear Generating Station, Units 1, 2, and 3 (Docket Nos. STN 50-528/529/530), located in Maricopa County, Arizone, 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 an evaluation of (1) additional information submitted by the applicant since Supplement No. 10 was issued and (2) other matters requiring staff review since Supplenent No. 10 was issued, specifically those issues that required resolution before Unit 3 low-power licensing

  20. Formative feedback from the first-person perspective using Google Glass in a family medicine objective structured clinical examination station in the United States.

    Science.gov (United States)

    Youm, Julie; Wiechmann, Warren

    2018-01-01

    This case study explored the use of Google Glass in a clinical examination scenario to capture the first-person perspective of a standardized patient as a way to provide formative feedback on students' communication and empathy skills 'through the patient's eyes.' During a 3-year period between 2014 and 2017, third-year students enrolled in a family medicine clerkship participated in a Google Glass station during a summative clinical examination. At this station, standardized patients wore Google Glass to record an encounter focused on communication and empathy skills 'through the patient's eyes.' Students completed an online survey using a 4-point Likert scale about their perspectives on Google Glass as a feedback tool (N= 255). We found that the students' experiences with Google Glass 'through the patient's eyes' were largely positive and that students felt the feedback provided by the Google Glass recording to be helpful. Although a third of the students felt that Google Glass was a distraction, the majority believed that the first-person perspective recordings provided an opportunity for feedback that did not exist before. Continuing exploration of first-person perspective recordings using Google Glass to improve education on communication and empathy skills is warranted.

  1. Results of Steam-Water-Oxygen Treatment of the Inside of Heating Surfaces in Heat-Recovery Steam Generators of the PGU-800 Power Unit at the Perm' District Thermal Power Station

    Science.gov (United States)

    Ovechkina, O. V.; Zhuravlev, L. S.; Drozdov, A. A.; Solomeina, S. V.

    2018-05-01

    Prestarting, postinstallation steam-water-oxygen treatment (SWOT) of the natural circulation/steam reheat heat-recovery steam generators (HRSG) manufactured by OAO Krasny Kotelshchik was performed at the PGU-800 power unit of the Perm District Thermal Power Station (GRES). Prior to SWOT, steam-oxygen cleaning, passivation, and preservation of gas condensate heaters (GCH) of HRSGs were performed for 10 h using 1.3MPa/260°C/70 t/h external steam. After that, test specimens were cut out that demonstrated high strength of the passivating film. SWOT of the inside of the heating surfaces was carried out during no-load operation of the gas turbine unit with an exhaust temperature of 280-300°C at the HRSG inlet. The steam turbine was shutdown, and the generated steam was discharged into the atmosphere. Oxygen was metered into the discharge pipeline of the electricity-driven feed pumps and downcomers of the evaporators. The behavior of the concentration by weight of iron compounds and the results of investigation of cutout specimens by the drop or potentiometric method indicate that the steam-water-oxygen process makes it possible to remove corrosion products and reduce the time required to put a boiler into operation. Unlike other processes, SWOT does not require metal-intensive cleaning systems, temporary metering stations, and structures for collection of the waste solution.

  2. Hydrogen Filling Station

    Energy Technology Data Exchange (ETDEWEB)

    Boehm, Robert F; Sabacky, Bruce; Anderson II, Everett B; Haberman, David; Al-Hassin, Mowafak; He, Xiaoming; Morriseau, Brian

    2010-02-24

    Hydrogen is an environmentally attractive transportation fuel that has the potential to displace fossil fuels. The Freedom CAR and Freedom FUEL initiatives emphasize the importance of hydrogen as a future transportation fuel. Presently, Las Vegas has one hydrogen fueling station powered by natural gas. However, the use of traditional sources of energy to produce hydrogen does not maximize the benefit. The hydrogen fueling station developed under this grant used electrolysis units and solar energy to produce hydrogen fuel. Water and electricity are furnished to the unit and the output is hydrogen and oxygen. Three vehicles were converted to utilize the hydrogen produced at the station. The vehicles were all equipped with different types of technologies. The vehicles were used in the day-to-day operation of the Las Vegas Valley Water District and monitoring was performed on efficiency, reliability and maintenance requirements. The research and demonstration utilized for the reconfiguration of these vehicles could lead to new technologies in vehicle development that could make hydrogen-fueled vehicles more cost effective, economical, efficient and more widely used. In order to advance the development of a hydrogen future in Southern Nevada, project partners recognized a need to bring various entities involved in hydrogen development and deployment together as a means of sharing knowledge and eliminating duplication of efforts. A road-mapping session was held in Las Vegas in June 2006. The Nevada State Energy Office, representatives from DOE, DOE contractors and LANL, NETL, NREL were present. Leadership from the National hydrogen Association Board of Directors also attended. As a result of this session, a roadmap for hydrogen development was created. This roadmap has the ability to become a tool for use by other road-mapping efforts in the hydrogen community. It could also become a standard template for other states or even countries to approach planning for a hydrogen

  3. Advantages of active love wave techniques in geophysical characterizations of seismographic station - Case studies in California and the central and eastern United States

    Science.gov (United States)

    Martin, Antony; Yong, Alan K.; Salomone, Larry A.

    2014-01-01

    Active-source Love waves, recorded by the multi-channel analysis of surface wave (MASLW) technique, were recently analyzed in two site characterization projects. Between 2010 and 2012, the 2009 American Recovery and Reinvestment Act (ARRA) funded GEOVision to conduct geophysical investigations at 191 seismographic stations in California and the Central Eastern U.S. (CEUS). The original project plan was to utilize active and passive Rayleigh wave-based techniques to obtain shear-wave velocity (VS) profiles to a minimum depth of 30 m and the time-averaged VS of the upper 30 meters (VS30). Early in this investigation it became clear that Rayleigh wave techniques, such as multi-channel analysis of surface waves (MASRW), were not suited for characterizing all sites. Shear-wave seismic refraction and MASLW techniques were therefore applied. In 2012, the Electric Power Research Institute funded characterization of 33 CEUS station sites. Based on experience from the ARRA investigation, both MASRW and MASLW data were acquired by GEOVision at 24 CEUS sites. At shallow rock sites, sites with steep velocity gradients, and, sites with a thin, low velocity, surficial soil layer overlying stiffer sediments, Love wave techniques generally were found to be easier to interpret, i.e., Love wave data typically yielded unambiguous fundamental mode dispersion curves and thus, reduce uncertainty in the resultant VS model. These types of velocity structure often excite dominant higher modes in Rayleigh wave data, but not in the Love wave data. It is possible to model Rayleigh wave data using multi- or effective-mode techniques; however, extraction of Rayleigh wave dispersion data was found to be difficult in many cases. These results imply that field procedures should include careful scrutiny of Rayleigh wave-based dispersion data in order to also collect Love wave data when warranted.

  4. Technical specifications, Waterford Steam Electric Station, Unit No. 3 (Docket No. 50-382). Appendix A to License No. NPF-38

    International Nuclear Information System (INIS)

    1985-03-01

    The Waterford, Unit 3 Technical Specifications were prepared by the US Nuclear Regulatory Commission to set forth the limits, operating conditions, and other requirements applicable to a nuclear reactor facility as set forth in Section 50.36 of 10 CFR Part 50 for the protection of the health and safety of the public

  5. Technical specifications, Shoreham Nuclear Power Station, Unit No. 1 (Docket No. 50-322): Appendix ''A'' to License No. NPF-82

    International Nuclear Information System (INIS)

    1989-04-01

    The Shoreham, Unit 1, Technical Specifications were prepared by the US Nuclear Regulatory Commission to set forth the limits, operating conditions, and other requirements applicable to a nuclear facility as set forth in Section 50.36 of 10 CFR Part 50 for the protection of the health and safety of the public. 20 figs., 75 tabs

  6. H2USA: Siting Refueling Stations in the Northeast

    Energy Technology Data Exchange (ETDEWEB)

    Melaina, Marc W [National Renewable Energy Laboratory (NREL), Golden, CO (United States); Muratori, Matteo [National Renewable Energy Laboratory (NREL), Golden, CO (United States); Zuboy, Jarett [Consultant; Ellis, Steve [Honda

    2017-11-01

    To achieve cost-effective deployment of both fuel cell electric vehicles (FCEVs) and hydrogen stations, the number of vehicles and public stations must grow together in areas of highest demand. This fact sheet introduces two advanced modeling tools and presents preliminary analysis of the hydrogen refueling station locations needed to support early consumer demand for FCEVs in the Northeast United States. United States.

  7. Safety Evaluation Report related to the restart of Rancho Seco Nuclear Generating Station, Unit 1, following the event of December 26, 1985 (Docket No. 50-312)

    International Nuclear Information System (INIS)

    1987-10-01

    On December 26, 1985, the Rancho Seco Nuclear Generating Station, owned and operated by the Sacramento Municipal Utility District (SMUD), experienced a loss of dc power within the integrated control system (ICS) while the plant was at 76% power. The ensuing reactor trip was followed by a rapid overcooling transient and automatic initiation of the safety features actuation system (SFAS). The overcooling transient continued until ICS dc power was restored 26 minutes after its loss. Two letters from the NRC Region V Administrator (dated December 26, 1985) confirmed that the Rancho Seco plant would not be returned to power operation until SMUD (the licensee) had provided the NRC with an assessment of the root cause of the transient and a justification as to why the Rancho Seco facility is ready to resume power operation. In response, the licensee submitted the ''Rancho Seco Action Plan for Performance Improvement'' on July 3, 1986; revisions to that action plan were submitted on December 15, 1986 and February 28, 1987. The NRC staff has reviewed the action plan and numerous other supporting documents submitted by the licensee. The staff's evaluation of the information supporting restart of Rancho Seco is presented in this safety evaluation report

  8. Safety Evaluation Report related to the restart of Davis-Besse Nuclear Power Station, Unit 1, following the event of June 9, 1985 (Docket No. 50-346)

    International Nuclear Information System (INIS)

    1986-06-01

    On June 9, 1985, the Davis-Besse Nuclear Power Station, operated by the Toledo Edison Company, experienced a partial loss of main feedwater while the plant was at 90% power. The ensuing reactor trip was followed by spurious isolation of the steam geneators which initiated a chain of events involving a number of equipment malfunctions and several operator errors ultimately interrupting all feedwater for a short period of time. By the time operators were able to restore feedwater, both steam generators had dried out. A letter from the Director of the Office of Nuclear Reactor Regulation, pursuant to 10 CFR 50.54(f) of the Commission's regulations, confirmed that the Davis-Besse facility would not be restarted without NRC approval. The letter also requested that Toledo Edison submit its program for resolving numerous concerns identified by the staff. In response, the license submitted the Davis-Besse Course of Action report. The staff has reviewed that document and other supporting material submitted by the licensee; the staff's evaluation of that information is presented in this report

  9. INSTALLATION OF A POST-ACCIDENT CONFINEMENT HIGH-LEVEL RADIATION MONITORING SYSTEM IN THE KOLA NUCLEAR POWER STATION (UNIT 2) IN RUSSIA

    Energy Technology Data Exchange (ETDEWEB)

    GREENE,G.A.; GUPPY,J.G.

    1998-09-01

    This is the final report on the INSP project entitled, ``Post-Accident Confinement High-Level Radiation Monitoring System'' conducted by BNL under the authorization of Project Work Plan WBS 1.2.2.6 (Attachment 1). This project was initiated in February 1993 to assist the Russians in reducing risks associated with the continued operation of older Soviet-designed nuclear power plants, specifically the Kola VVER-440/230 Unit 2, through improved accident detection capability, specifically by the installation of a dual train high-level radiation detection system in the confinement of Unit 2 of the Kola NPP. The major technical objective of this project was to provide, install and make operational the necessary hardware inside the confinement of the Kola NPP Unit 2 to provide early and reliable warning of the release of radionuclides from the reactor into the confinement air space as an indication of the occurrence of a severe accident at the plant. In addition, it was intended to provide hands-on experience and training to the Russian plant workers in the installation, operation, calibration and maintenance of the equipment in order that they may use the equipment without continued US assistance as an effective measure to improve reactor safety at the plant.

  10. INSTALLATION OF A POST-ACCIDENT CONFINEMENT HIGH-LEVEL RADIATION MONITORING SYSTEM IN THE KOLA NUCLEAR POWER STATION (UNIT 2) IN RUSSIA

    International Nuclear Information System (INIS)

    GREENE, G.A.; GUPPY, J.G.

    1998-01-01

    This is the final report on the INSP project entitled, ''Post-Accident Confinement High-Level Radiation Monitoring System'' conducted by BNL under the authorization of Project Work Plan WBS 1.2.2.6 (Attachment 1). This project was initiated in February 1993 to assist the Russians in reducing risks associated with the continued operation of older Soviet-designed nuclear power plants, specifically the Kola VVER-440/230 Unit 2, through improved accident detection capability, specifically by the installation of a dual train high-level radiation detection system in the confinement of Unit 2 of the Kola NPP. The major technical objective of this project was to provide, install and make operational the necessary hardware inside the confinement of the Kola NPP Unit 2 to provide early and reliable warning of the release of radionuclides from the reactor into the confinement air space as an indication of the occurrence of a severe accident at the plant. In addition, it was intended to provide hands-on experience and training to the Russian plant workers in the installation, operation, calibration and maintenance of the equipment in order that they may use the equipment without continued US assistance as an effective measure to improve reactor safety at the plant

  11. Analysis of internal events for the Unit 1 of the Laguna Verde nuclear power station; Analisis de eventos internos para la Unidad 1 de la Central Nucleolelectrica de Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Huerta B, A.; Aguilar T, O.; Nunez C, A.; Lopez M, R. [Comision Nacional de Seguridad Nuclear y Salvaguardias, 03000 Mexico D.F. (Mexico)

    1993-07-01

    This volume presents the results of the starter event analysis and the event tree analysis for the Unit 1 of the Laguna Verde nuclear power station. The starter event analysis includes the identification of all those internal events which cause a disturbance to the normal operation of the power station and require mitigation. Those called external events stay beyond the reach of this study. For the analysis of the Laguna Verde power station eight transient categories were identified, three categories of loss of coolant accidents (LOCA) inside the container, a LOCA out of the primary container, as well as the vessel break. The event trees analysis involves the development of the possible accident sequences for each category of starter events. Events trees by systems for the different types of LOCA and for all the transients were constructed. It was constructed the event tree for the total loss of alternating current, which represents an extension of the event tree for the loss of external power transient. Also the event tree by systems for the anticipated transients without scram was developed (ATWS). The events trees for the accident sequences includes the sequences evaluation with vulnerable nucleus, that is to say those sequences in which it is had an adequate cooling of nucleus but the remoting systems of residual heat had failed. In order to model adequately the previous, headings were added to the event tree for developing the sequences until the point where be solved the nucleus state. This process includes: the determination of the failure pressure of the primary container, the evaluation of the environment generated in the reactor building as result of the container failure or cracked of itself, the determination of the localization of the components in the reactor building and the construction of boolean expressions to estimate the failure of the subordinated components to an severe environment. (Author)

  12. [The balance of harmful trace contaminants between the air humidity condensate and air in a simulator of the Mir orbit station moisture condensation unit].

    Science.gov (United States)

    Zlotopol'skiĭ, V M; Smolenskaia, T S

    2000-01-01

    Subject of the investigation was the balance of harmful trace contaminants (HTC) between the air moisture condensate and air in a simulator of the MIR moisture condensation unit. Experiments involved various classes of water-solvent compounds including alcohols (C1-C4), ketons (C1-C2), aldehydes (C1-C2), fatty acids (C2-C4), esters (acetates C4-C6), and ammonium. For most of the compounds, removal efficiency correlates with air humidity and virtually does not depend on the HTC concentration within the range of 0.25 to 59.1 mg/m3.

  13. Programmatic Environmental Impact Statement: related to decontamination and disposal of radioactive wastes resulting from March 28, 1979 accident Three Mile Island Nuclear Station, Unit 2 (Docket No. 50-320). Final supplement dealing with occupational radiation dose. Supplement No. 1

    International Nuclear Information System (INIS)

    1984-10-01

    In accordance with the National Environmental Policy Act, the Programmatic Environmental Impact Statement Related to Decontamination and Disposal of Radioactive Wastes Resulting from March 28, 1979 Accident Three Mile Island Nuclear Station, Unit 2 has been supplemented. The supplement was required because current information indicates that cleanup may entail substantially more occupational radiation dose to the cleanup work force than originally anticipated. Cleanup was originally estimated to result in from 2000 to 8000 person-rem of occupational radiation dose. Although nearly 2000 person-rem have resulted from cleanup operations performed up to now, current estimates now indicate that between 13,000 and 46,000 person-rem are expected to be required. Alternative cleanup methods considered in the supplement either did not result in appreciable dose savings or were not known to be technically feasible

  14. 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

  15. Programmatic environmental impact statement related to decontamination and disposal of radioactive wastes resulting from March 28, 1979 accident, Three Mile Island Nuclear Station, Unit 2 (Docket No. 50-320). Draft supplement dealing with occupational radiation dose. Supplement No. 1

    International Nuclear Information System (INIS)

    1983-12-01

    In accordance with the National Environmental Policy Act, the Programmatic Environmental Impact Statement Related to Decontamination and Disposal of Radioactive Waste for the 1979 Accident at Three Mile Island Nuclear Station Unit 2 has been supplemented. The supplement was required because current information indicates that cleanup will entail substantially more occupational radiation dose to the cleanup work force than originally anticipated. Cleanup was originally estimated to result in from 2000 to 8000 person-rem of occupational radiation dose. Although only 1700 person-rem have resulted from cleanup operations performed up to now, current estimates now indicate that between 13,000 and 46,000 person-rem are expected to be required. Alternate cleanup methods considered in the supplement either did not result in appreciable dose savings or were not known to be technically feasible

  16. Population dose estimation from a hypothetical release of 2.4 x 106 curies of noble gases and 1 x 104 curies of 131I at the Three Mile Island Nuclear Station, Unit 2

    International Nuclear Information System (INIS)

    Berger, C.D.; Lane, B.H.; Cotter, S.J.; Miller, C.W.; Glandon, S.R.

    1981-09-01

    Beginning on March 28, 1979, a sequence of events occurred at the Three Mile Island Nuclear Station Unit 2 (TMINS-2) nuclear power reactor which resulted in the accidental release of approximately 2.4 x 10 6 Ci of noble gases and 13 to 15 Ci 131 I. A comprehensive study of this incident has been reported by the President's Commission on the Accident at Three Mile Island. As part of this study, the Technical Assessment Task Group for the Commission addressed a series of alternative event scenarios, including the potential for a higher release of 131 I. As a continuation of this task, this report presents the estimated collective dose to the population within 50 miles of TMINS-2 from a hypothetical release of 2.4 x 10 6 Ci of noble gases and 1 x 10 4 Ci 131 I by the methodology of atmospheric dispersion modeling and population dose estimation through the inhalation, ingestion and immersion exposure pathways

  17. Programmatic Environmental Impact Statement related to decontamination and disposal of radioactive wastes resulting from March 28, 1979 accident at Three Mile Island Nuclear Station, Unit 2 (Docket No. 50-320): Final report

    International Nuclear Information System (INIS)

    1987-06-01

    In accordance with the National Environmental Policy Act, the Commission's implementing regulations, and the Commission's April 27, 1981 Statement of Policy, the Programmatic Environmental Impact Statement related to decontamination and disposal of radioactive wastes resulting from March 28, 1979, accident Three Mile Island Nuclear Station, Unit 2 NUREG-0683 (PEIS) is being supplemented. This supplement updates the environmental evaluation of accident-generated water disposal alternatives published in the PEIS, utilizing more complete and current information. Also, the supplement includes a specific environmental evaluation of the licensee's proposal for water disposition. Although no clearly preferable water disposal alternative was identified, the supplement concluded that a number of alternatives could be implemented without significant environmental impact. The NRC staff has concluded that the licensee's proposed disposal of the accident-generated water by evaporation will not significantly affect the quality of the human environment. Further, any impacts from the disposal program are outweighed by its benefits

  18. Safety Evaluation Report related to the operation of Comanche Peak Steam Electric Station, Units 1 and 2 (Docket Nos. 50-445 and 50-446). Supplement No. 7

    International Nuclear Information System (INIS)

    1985-01-01

    Supplement 7 to the Safety Evaluation Report for the Texas Utilities Electric Company application for a license to operate Comanche Peak Steam Electric Station, Units 1 and 2 (Docket Nos. 50-445, 50-446), located in Somervell County, Texas, has been jointly prepared by the Office of Nuclear Reactor Regulation and the Comanche Peak Technical Review of the US Nuclera Regulatory Commission. This supplement provides the results of the staff's evaluation and resolution of approximately 80 technical concerns and allegations in the areas of Electric/Instrumentation and Test Programs regarding construction and plant readiness testing practices at the Comanche Peak facility. Issues raised during Atomic Safety and Licensing Board hearings will be dealt with in future supplements to the Safety Evaluation Report

  19. Evaluation of zeolite mixtures for decontamination of high-activity-level water in the Submerged Demineralizer System (SDS) flowsheet at the Three Mile Island Nuclear Power Station, Unit 2

    International Nuclear Information System (INIS)

    King, L.J.; Campbell, D.O.; Collins, E.D.; Knauer, J.B.; Wallace, R.M.

    1983-01-01

    Mixtures of Linde Ionsiv IE-96 and Ionsiv A-51 zeolites were evaluated for use in the Submerged Demineralizer System (SDS) that was installed at the Three Mile Island Nuclear Power Station, Unit 2 (TMI-2) for decontaminating approx. 3000 m 3 (approx. 700,000 gal) of high-activity-level water in the containment building sump. Small-scale, tracer-level column tests were made using various mixtures of the zeolites to evaluate the capability for simultaneous removal of cesium and strontium. A column loading test was made in a hot cell using a mixture of equal parts of the zeolites to evaluate the performance of the mixture in removing cesium and strontium from a sample of TMI-2 sump water. A computerized mathematical model of the mixed-bed SDS system was used to evaluate the test data in order to select a zeolite mixture and predict system performance

  20. Treatment of opinions, etc. in the public hearing on the alteration of reactor installation (addition of Unit 2) in the Shimane Nuclear Power Station of The Chugoku Electric Power Company, Inc

    International Nuclear Information System (INIS)

    1983-01-01

    The Nuclear Safety Commission has acknowledged the governmental policy, and further decided on the treatment of the opinions expressed by the local people in the public hearing held in May, 1983, in Shimane Prefecture on the addition of Unit 2 to the Shimane Nuclear Power Station, Chugoku Electric Power Co., Inc. The NSC has directed the Committee on Examination of Reactor Safety to take into consideration the opinions in its later examination. The opinions expressed by the local people in the form of question are given as follows: siting conditions (earthquake, ground, weather, etc.), the safety design for reactor installation (general aspect, aseismatic design, core design, ECCS, the teaching of TMI accident, etc.), radioactive wastes, radiation exposure, site evaluation. (Mori, K.)

  1. Considerations of the opinions and others in the public hearing on the alteration in reactor installation (addition of Unit 3) in the Hamaoka Nuclear Power Station of the Chubu Electric Power Co., Inc

    International Nuclear Information System (INIS)

    1982-01-01

    A public hearing was held in Hamaoka Town, Shizuoka Prefecture, on the alteration in reactor installation, i.e., the addition of Unit 3 in the Hamaoka Nuclear Power Station, Chubu Electric Power Co., Inc., on March 19, 1981, by the Nuclear Safety Commission. The opinions and others stated by the local people were taken into consideration in the governmental examinations on the installation, etc. The considerations of such opinions principally in the examinations by NSC are explained in the form of questions (i.e. opinion, etc.) and answers (i.e. considerations) as follows: site conditions (earthquakes, ground, hydraulic features, etc.), the safety design of the reactor facilities (overall plant, aseismic design, the control of inflammable gas concentration, radioactive waste treatment, the reflection of accident experiences, etc.), radioactive waste management, radiation exposure relation, the technical capabilities of personnel (operation, etc.). (J.P.N.)

  2. Final programmatic environmental impact statement related to decontamination and disposal of radioactive wastes resulting from March 28, 1979 accident, Three Mile Island Nuclear Station, Unit 2, Docket No. 50-320

    International Nuclear Information System (INIS)

    1981-03-01

    A Final Programmatic Environmental Impact Statement (PEIS) related to the decontamination and disposal of radioactive wastes resulting from the March 28, 1979, accident at Three Mile Island Nuclear Station, Unit 2 (Docket No. 50-320) has been prepared by the Office of Nuclear Reactor Regulation of the Nuclear Regulatory Commission in response to a directive issued by the Commission on November 21, 1979. This statement is an overall study of the activities necessary for decontamination of the facility, defueling, and disposition of the radioactive wastes. The available alternatives considered ranged from implementation of full cleanup to no action other than continuing to maintain the reactor in a safe shutdown condition. Also included are comments of governmental agencies, other organizations, and the general public on the Draft PEIS on this project, and staff responses to these comments. (author)

  3. 47 CFR 90.425 - Station identification.

    Science.gov (United States)

    2010-10-01

    ... Telecommunication FEDERAL COMMUNICATIONS COMMISSION (CONTINUED) SAFETY AND SPECIAL RADIO SERVICES PRIVATE LAND MOBILE RADIO SERVICES Operating Requirements § 90.425 Station identification. Stations licensed under... mobile units. (ii) In the Industrial/Business Pool, licensees may request the Commission's local Engineer...

  4. Guidelines for Learning Stations.

    Science.gov (United States)

    Fehrle, Carl C.; Schulz, Jolene

    Guidelines for designing and planning learning stations for pupils at the elementary grade level include suggestions on how to develop a station that will be successful in meeting the learners' needs. Instructions for the use of tapes at a station and matching pupils with stations are given, as are guidelines on classroom arrangement and record…

  5. Environmental assessment, proposed generating station for Darlington

    International Nuclear Information System (INIS)

    1975-04-01

    This document indicates the intention of Ontario Hydro to seek approval from the Provincial Government for its plan to construct and operate a 3400 MWe nuclear generating station at the Darlington site, west of Bowmanville. This preliminary proposal also contains the environmental assessment. The environmental section of this proposal describes and assesses the existing environment and the environmental influences which would occur due to the construction and operation of a nuclear generating station, consisting of four 850 MW units, at the Darlington site. This proposed station is similar to the Bruce GS A station presently under construction. (author)

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

    International Nuclear Information System (INIS)

    1975-10-01

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

  7. The cooling facility of the Central Railway Station of Berne, Switzerland - A network operated by the city's public utilities including absorption cooling units; Kaelteverbund Bahnhof Bern, Energiecontracting mit Absorptionskaeltemaschinen

    Energy Technology Data Exchange (ETDEWEB)

    Bretscher, M.

    2004-07-01

    The energy policy of the municipality of Berne aims to create innovative technical solutions which contribute to the reduction of air pollution. This led to the idea to utilise part of the free waste heat of the city's waste incineration plant for the production of cold water. The subject of cold water production was already raised by Energie Wasser Bern in 1998. A pilot study examined the feasibility of a cold energy production unit, and consultations with land owners revealed interest in a joint solution. Project development was initiated by the Swiss Federal Railways (SBB), the Canton of Berne and the City of Berne. On the basis of the documentation produced by the engineering company KIWI AG in Duebendorf, the three constructors decided to implement central cold energy production using an absorption-type refrigerating installation in a contracting solution. The new cold energy production centre is ideally located in the basement of the SBB station main building where it was possible to integrate the existing refrigerating installation of the computer centre in the combined system. Initial operating experiences demonstrate that the incorporation of absorption-type refrigerating units in interconnected cold water systems is not quite so easy. Parallel operation of two units and precise adherence to the constant cold water temperature with a fluctuating return temperature places extreme demands on the control engineering of the installation. Approximately CHF 5.2 million have been invested in the combined cold energy installation up to autumn 2003. Energie Wasser Bern is responsible for financing, operating, maintenance and repair for a period of 20 years. The cold energy price calculated by the contractor is made up of the two components: base and operating rates. The base rate represents the fixed cost parts, i.e. the annual interest on capital and the fixed operating costs. The operating rate comprises the variable costs (mainly for primary energy

  8. Shippingport Station decommissioning project overview

    International Nuclear Information System (INIS)

    Schreiber, J.J.

    1985-01-01

    The U.S. Department of Energy is in the process of decommissioning the Shippingport Atomic Power Station located on the Ohio River, 30 miles northwest of Pittsburgh, Pennsylvania. The Shippingport Station is the first commercial size nuclear power plant to undergo decommissioning in the United Staes. The plant is located on approximately 7 acres of land owned by the Duquesne Light Company (DLC) and leased to the U.S. Government. DLC operates two nuclear power plants, Beaver Valley 1 and 2, located immediately adjacent to the site and the Bruce Mansfield coal-fired power plant is also within the immediate area. The Station was shutdown in October, 1982. Defueling operations began in 1983 and were completed by September, 1984. The Shippingport Station consists of a 275' x 60' fuel handling building containing the reactor containment chamber, the service building, the turbine building, the radioactive waste processing building, the administration building and other smaller support buildings. The Station has four coolant loops and most of the containment structures are located below grade. Structures owned by the U.S. Government including the fuel handling building, service building, contaminated equipment room, the boiler chambers, the radioactive waste processing building and the decontamination and laydown buildings will be dismantled and removed to 3 feet below grade. The area will then be filled with clean soil and graded. The turbine building, testing and training building and the administration building are owned by DLC and will remain

  9. Decommissioning of nuclear power stations

    International Nuclear Information System (INIS)

    Gregory, A.R.

    1988-01-01

    In the United Kingdom the Electricity Boards, the United Kingdom Atomic Energy Authority (UKAEA) and BNFL cooperate on all matters relating to the decommissioning of nuclear plant. The Central Electricity Generating Board's (CEGB) policy endorses the continuing need for nuclear power, the principle of reusing existing sites where possible and the building up of sufficient funds during the operating life of a nuclear power station to meet the cost of its complete clearance in the future. The safety of the plant is the responsibility of the licensee even in the decommissioning phase. The CEGB has carried out decommissioning studies on Magnox stations in general and Bradwell and Berkeley in particular. It has also been involved in the UKAEA Windscale AGR decommissioning programme. The options as to which stage to decommission to are considered. Methods, costs and waste management are also considered. (U.K.)

  10. Alkaline RFC Space Station prototype - 'Next step Space Station'. [Regenerative Fuel Cells

    Science.gov (United States)

    Hackler, I. M.

    1986-01-01

    The regenerative fuel cell, a candidate technology for the Space Station's energy storage system, is described. An advanced development program was initiated to design, manufacture, and integrate a regenerative fuel cell Space Station prototype (RFC SSP). The RFC SSP incorporates long-life fuel cell technology, increased cell area for the fuel cells, and high voltage cell stacks for both units. The RFC SSP's potential for integration with the Space Station's life support and propulsion systems is discussed.

  11. Water Level Station History

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — Images contain station history information for 175 stations in the National Water Level Observation Network (NWLON). The NWLON is a network of long-term,...

  12. Fire Stations - 2009

    Data.gov (United States)

    Kansas Data Access and Support Center — Fire Stations in Kansas Any location where fire fighters are stationed or based out of, or where equipment that such personnel use in carrying out their jobs is...

  13. Fire Stations - 2007

    Data.gov (United States)

    Kansas Data Access and Support Center — Fire Station Locations in Kansas Any location where fire fighters are stationed at or based out of, or where equipment that such personnel use in carrying out their...

  14. Weather Radar Stations

    Data.gov (United States)

    Department of Homeland Security — These data represent Next-Generation Radar (NEXRAD) and Terminal Doppler Weather Radar (TDWR) weather radar stations within the US. The NEXRAD radar stations are...

  15. Newport Research Station

    Data.gov (United States)

    Federal Laboratory Consortium — The Newport Research Station is the Center's only ocean-port research facility. This station is located at Oregon State University's Hatfield Marine Science Center,...

  16. Big Game Reporting Stations

    Data.gov (United States)

    Vermont Center for Geographic Information — Point locations of big game reporting stations. Big game reporting stations are places where hunters can legally report harvested deer, bear, or turkey. These are...

  17. Ocean Station Vessel

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — Ocean Station Vessels (OSV) or Weather Ships captured atmospheric conditions while being stationed continuously in a single location. While While most of the...

  18. Hammond Bay Biological Station

    Data.gov (United States)

    Federal Laboratory Consortium — Hammond Bay Biological Station (HBBS), located near Millersburg, Michigan, is a field station of the USGS Great Lakes Science Center (GLSC). HBBS was established by...

  19. Reference Climatological Stations

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — The Reference Climatological Stations (RCS) network represents the first effort by NOAA to create and maintain a nationwide network of stations located only in areas...

  20. Safety Evaluation Report related to the operation of Comanche Peak Steam Electric Station, Units 1 and 2 (Docket Nos. 50-445 and 50-446). Supplement No. 13

    International Nuclear Information System (INIS)

    1986-05-01

    Supplement 13 to the Safety Evaluation Report related to the operation of 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 presents 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 the Atomic Safety and Licensing Board, allegers, intervenor Citizens Association for Sound Energy (CASE), NRC inspections of various types, and Cygna Energy Services while conducting its independent design assessment. The NRC staff concludes that the CPRT Program Plan provides an overall structure for addressing all existing issues and any future issues which may be identified from further evaluations, and if properly implemented will provide important evidence of the design and construction quality of CPSES, and will identify any needed corrective action. The report identifies items to be addressed by the NRC staff during the implementation phase

  1. Safety Evaluation Report related to the operation of Comanche Peak Steam Electric Station, Units 1 and 2 (Docket Nos. 50-445 and 50-446). Supplement No. 11

    International Nuclear Information System (INIS)

    1985-05-01

    Supplement 11 to the Safety Evaluation Report for the Texas Utilities Electric Company application for a license to operate Comanche Peak Steam Electric Station, Units 1 and 2 (Docket Nos. 50-445, 50-446), located in Somervell County, Texas, has been jointly prepared by the Office of Nuclear Reactor Regulation and the Comanche Peak Technical Review Team (TRT) of the US Nuclear Regulatory Commission (NRC) and is in two parts. Part 1 (Appendix 0) of this supplement provides the results of the TRT's evaluation of approximately 124 concerns and allegations relating specifically to quality assurance and quality control (QA/QC) issues regarding construction proctices at the Comanche Peak facility. Part 2 (Appendix P) contains an overall summary and conclusion of the QA/QC aspects of the NRC Technical Review Team efforts as reported in supplemental Safety Evaluation Report SERs 7, 8, 9, and 10. Since QA/QC issues are also contained in each of the other supplements, the TRT considered that such a summary and conclusion from all supplements was necessary for a complete TRT description of QA/QC activities at Comanche Peak

  2. Decontamination and disposal of radioactive wastes resulting from the March 28, 1979 accident, Three-Mile Island Nuclear Station, Unit 2, Pennsylvania-Docket No. 50-320 (final supplement 2 to the final environmental impact statement of March 1981)

    International Nuclear Information System (INIS)

    1987-06-01

    Implementation of actions necessary for decontamination of the facility, defueling of the reactor, and disposition of the radioactive wastes that resulted from the accident on March 28, 1979 at Unit 2 of the Three-Mile Island Nuclear Station in Dauphin County, Pennsylvania are discussed. This second final supplement to the final environmental impact statement, filed in March 1981 on facility decontamination, reevaluates the environmental impacts of accident-generated water disposal alternatives, using more complete and current information. This supplement also includes a specific evaluation of the recently submitted proposal for water disposition. The project would alleviate a radiological hazard that threatens the well-being of the surrounding population and downstream communities. Risks to the general public have been estimated to be very small fractions of the estimated normal incidence of cancer fatalities and genetic disorders. The most significant potential impact is the risk of physical injury associated with transportation accidents. Social impacts during the operation could result in reduced property values, competition between the work force and tourists for temporary housing, and congestion of local traffic arteries. Some psychological stress would experienced by area residents. Economic effects could include increased electricity rates, reduced tourism, and possible resistance to consumption of area goods that consumers might mistakenly think are contaminated

  3. Space Station - Opportunity for international cooperation and utilization

    Science.gov (United States)

    Pedersen, K. S.

    1984-01-01

    In connection with his announcement regarding the development of a permanently manned Space Station, President Reagan invited the United States' friends and allies to join in the Space Station program. The President's invitation was preceded by more than two years of interaction between NASA and some of its potential partners in Space Station planning activities. Attention is given to international participation in Space Station planning, international cooperation on the Space Station, the guidelines for international cooperation, and the key challenges. Questions regarding quid pro quos are considered along with aspects of technology transfer, commercial use, problems of management, and the next steps concerning the Space Station program.

  4. Environmental Statement, Lake City Station, Unit One.

    Science.gov (United States)

    1973-09-17

    western fox squirrel, exists in the site vicinity. Sizeable populations of gray squirrel ( Sciurus carolinensis) and deer (Odocoileus virginianus...crowned kinglet Re gulus satrapa 11 Cedar waxwing Bombycilla decrorum 107 Northern shrike Lanius excubitor 1 Starling Sturnus vulgaris 76 Myrtle warbler...carolinensis Fox squirrel Sciurus nie Fed squirrel Tamiasciurus hudscriicus Eastern flying squirrel Glauctrys volans Deer mouse Peromyscus hniiiulatus White

  5. Environmental Statement, Oswego Steam Station, Unit Six.

    Science.gov (United States)

    1973-03-29

    woodcock (Philohela minor , cottontail rabbits (Sylvilagus floridanus), ruffed grouse (Bonasa umbellus) and gray squirrel ( Sciurus carolinensis). There are a...herring gull (Laurus argentatus) crow (Corvus brachyrhynchos rock dove (Columbo livia) wood thrush (Hylacichia inustelina) starling (Sturnus vulgaris

  6. INTERACT Station Catalogue - 2015

    DEFF Research Database (Denmark)

    and research groups. Therefore, INTERACT has produced a catalogue of research stations including descriptions of the physical setting, facilities and services offered at the stations. It is our hope that this catalogue will help researchers identify research stations that suit their specific needs. The 2015......INTERACT stations are located in all major environmental envelopes of the Arctic providing an ideal platform for studying climate change and its impact on the environment and local communities. Since alpine environments face similar changes and challenges as the Arctic, the INTERACT network also...... includes some alpine stations located outside the Arctic. The INTERACT research stations provide an ideal platform for circumarctic research and monitoring. Activities span from small short term research projects to larger long term monitoring programmes. The stations are thus visited by many researchers...

  7. IAEA International Peer Review Mission on Mid-and-Long-Term Roadmap Towards the Decommissioning of TEPCO's Fukushima Daiichi Nuclear Power Station Units 1-4, Tokyo and Fukushima Prefecture, Japan, 15-22 April 2013. Mission Report

    International Nuclear Information System (INIS)

    2013-01-01

    Following the accident at TEPCO's Fukushima Daiichi Nuclear Power Station (NPS) on 11 March 2011, the ''Mid-and-Long-Term Roadmap towards the Decommissioning of TEPCO's Fukushima Daiichi Nuclear Power Station Units 1-4'' was adopted by the Government of Japan and TEPCO Council on Mid-to-Long-Term Response for Decommissioning in December 2011 and revised in July 2012. The Roadmap, which is scheduled for an additional update in June 2013, describes the main steps and activities to be implemented for the decommissioning of the Fukushima Daiichi NPS through the combined efforts of the Government of Japan and TEPCO. Within the framework of the IAEA Action Plan on Nuclear Safety, the Government of Japan invited the IAEA to conduct an independent peer review of the Roadmap with two main objectives: - To improve the decommissioning planning and the implementation of pre-decommissioning activities at TEPCO's Fukushima Daiichi NPS; and - To share with the international community the good practices and lessons learned by the review. The review has been organized in two steps, and the IAEA conducted the first part in Japan from 15 to 22 April 2013. The objective of the first mission was to undertake an initial review of the Roadmap, including assessments of decommissioning strategy, planning and timing of decommissioning phases and a review of several specific short-term issues and recent challenges. Specifically, it covered the assessment of current reactor conditions, assessment of management of radioactive releases and associated doses, control of radioactive exposure of employees and decontamination within the site for improvement of working environment, structural integrity of reactor buildings and other constructions. The incidents recently experienced at the site, related with failures of the power supply and leakages of water from the underground reservoirs, were also included in the review of the specific short-term issues. The Government of Japan and TEPCO have

  8. Non-Coop Station History

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — Station history documentation for stations outside the US Cooperative Observer network. Primarily National Weather Service stations assigned WBAN station IDs. Other...

  9. Amtrak Rail Stations (National)

    Data.gov (United States)

    Department of Transportation — Updated database of the Federal Railroad Administration's (FRA) Amtrak Station database. This database is a geographic data set containing Amtrak intercity railroad...

  10. Cooperative Station History Forms

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — Various forms, photographs and correspondence documenting the history of Cooperative station instrumentation, location changes, inspections, and...

  11. Characterizing toxic emissions from a coal-fired power plant demonstrating the AFGD ICCT Project and a plant utilizing a dry scrubber/baghouse system: Bailly Station Units 7 and 8 and AFGD ICCT Project. Final report. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Dismukes, E.B.

    1994-10-20

    This report describes results of assessment of the risk of emissions of hazardous air pollutants at one of the electric power stations, Bailly Station, which is also the site of a Clean Coal Technology project demonstrating the Pure Air Advanced Flue Gas Desulfurization process (wet limestone). This station represents the configuration of no NO{sub x} reduction, particulate control with electrostatic precipitators, and SO{sub 2} control with a wet scrubber. The test was conducted September 3--6, 1993. Sixteen trace metals were determined along with 5 major metals. Other inorganic substances and organic compounds were also determined.

  12. Naval Station Guantanamo Bay: History and Legal Issues Regarding Its Lease Agreements

    Science.gov (United States)

    2016-11-17

    service unit under Marine command, arrived at the naval station in early January 2002 to begin construction of facilities for up to 2,000 detainees. 20... parcels of land to the United States for use as naval or coaling stations. Naval Station Guantanamo Bay, Cuba, was the sole installation established...22 U.S.C. §2573. Naval Station Guantanamo Bay Congressional Research Service 9 accomplish this objective. 36 If enacted, the United States

  13. TEPCO plans to construct Higashidori Nuclear Power Station

    International Nuclear Information System (INIS)

    Tsuruta, Atsushi

    2008-01-01

    In 2006, TEPCO submitted to the government plans for the construction of Higashidori Nuclear Power Station. The application was filed 41 years after the project approved by the Higashidori Village Assembly. This nuclear power station will be the first new nuclear power plant constructed by TEPCO since the construction of Units No.6 and 7 at the Kashiwazaki Kariwa Nuclear Power Station 18 years ago. Higashidori Nuclear Power Station is to be constructed at a completely new site, which will become the fourth TEPCO nuclear power station. Higashidori Nuclear Power Station Unit No.1 will be TEPCO's 18th nuclear reactor. Unit No.1 will be an advanced boiling water reactor (ABWR), a reactor-type with a proven track record. It will be TEPCO's third ABWR. Alongside incorporating the latest technology, in Higashidori Nuclear Power Station Unit No.1, the most important requirement is for TEPCO to reflect in the new unit information and experience acquired from the operation of other reactors (information and experience acquired through the experience of operating TEPCO's 17 units at Fukushima Daiichi Nuclear Power Station, Fukushima Daini Nuclear Power Station and Kashiwazaki Kashiwa Nuclear Power Station in addition to information on non-conformities at nuclear power stations in Japan and around the world). Higashidori Nuclear Power Station is located in Higashidori-Village (Aomori Prefecture) and the selected site includes a rich natural environment. From an environmental perspective, we will implement the construction with due consideration for the land and sea environment, aiming to ensure that the plant can co-exist with its natural surroundings. The construction plans are currently being reviewed by the Nuclear and Industrial Safety Agency. We are committed to making progress in the project for the start of construction and subsequent commercial operation. (author)

  14. Secure base stations

    NARCIS (Netherlands)

    Bosch, Peter; Brusilovsky, Alec; McLellan, Rae; Mullender, Sape J.; Polakos, Paul

    2009-01-01

    With the introduction of the third generation (3G) Universal Mobile Telecommunications System (UMTS) base station router (BSR) and fourth generation (4G) base stations, such as the 3rd Generation Partnership Project (3GPP) Long Term Evolution (LTE) Evolved Node B (eNB), it has become important to

  15. Ondergronds Station Blijdorp, Rotterdam

    NARCIS (Netherlands)

    Hijma, M.P.|info:eu-repo/dai/nl/266562426; Cohen, K.M.|info:eu-repo/dai/nl/185633374

    2014-01-01

    Het is in de herfst van 2005. Een lief meisje, Marieke, rijdt op haar vouwfiets door Rotterdam. Bij het Centraal Station is het al tijden een grote bouwplaats. Onder de nieuwe hal komt een veel groter metrostation en ook onder de Statenweg in Blijdorp is een grote bouwput voor een nieuw station.

  16. SPS rectifier stations

    CERN Multimedia

    CERN PhotoLab

    1974-01-01

    The first of the twelves SPS rectifier stations for the bending magnets arrived at CERN at the end of the year. The photograph shows a station with the rectifiers on the left and in the other three cubicles the chokes, capacitors and resistor of the passive filter.

  17. Meyrin Petrol Station

    CERN Multimedia

    2006-01-01

    Please note that the Meyrin petrol station will be closed for maintenance work on Tuesday 19 and Wednesday 20 December 2006. If you require petrol during this period we invite you to use the Prévessin petrol station, which will remain open. TS-IC-LO Section Tel.: 77039 - 73793

  18. Final site environmental statement: Blue Hills Station, Unit Nos. 1 and 2. Related to the determination of the suitability of Site G for eventual construction. Docket Nos. 50-510 and 50-511

    International Nuclear Information System (INIS)

    1978-07-01

    The site suitability analysis is based on the assumption that the Blue Hills Station will employ two pressurized water reactors to produce outputs of approximately 2814 MWt each. Two steam turbine generators will use the heat produced to provide approximately 957 MWe (gross) each. The exhaust steam will be cooled by four low-profile round mechanical-draft cooling towers. Assuming construction of a nuclear station at site G, a summary of environmental impacts and adverse effects is presented

  19. The Roman stational liturgy

    Directory of Open Access Journals (Sweden)

    Janusz Mieczkowski

    2012-03-01

    Full Text Available The papal stational liturgy in Rome was a particular kind of worship service from the Christian Antiquity to the XIV century. Its essential elements are four. Its always took place under the leadership of the pope or his representative. This form of liturgy was mobile: it was celebrated in different basilicas or churches of Rome. Third, the choice of church depended on the feast, liturgical seasons or commemoration being celebrated. Fourth, the stational liturgy was the urban liturgical celebration of the day. The highpoint of this system was Lent. Throughout the entire system Church of Rome manifested its own unity. The station was usually the Pope’s solemn mass in the stational church for the whole city. But on certain days in the year the Pope went in another church (collecta, from which a solemn procession was made to the stational church.

  20. [STEM on Station Education

    Science.gov (United States)

    Lundebjerg, Kristen

    2016-01-01

    The STEM on Station team is part of Education which is part of the External Relations organization (ERO). ERO has traditional goals based around BHAG (Big Hairy Audacious Goal). The BHAG model is simplified to a saying: Everything we do stimulates actions by others to advance human space exploration. The STEM on Station education initiate is a project focused on bringing off the earth research and learning into classrooms. Educational resources such as lesson plans, activities to connect with the space station and STEM related contests are available and hosted by the STEM on Station team along with their partners such as Texas Instruments. These educational activities engage teachers and students in the current happenings aboard the international space station, inspiring the next generation of space explorers.

  1. Pumps for nuclear power stations

    International Nuclear Information System (INIS)

    Ogura, Shiro

    1979-01-01

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

  2. Space agriculture in micro- and hypo-gravity: A comparative study of soil hydraulics and biogeochemistry in a cropping unit on Earth, Mars, the Moon and the space station

    Science.gov (United States)

    Maggi, Federico; Pallud, Céline

    2010-12-01

    Increasing interest is developing towards soil-based agriculture as a long-term bioregenerative life support during space and planetary explorations. Contrary to hydroponics and aeroponics, soil-based cropping would offer an effective approach to sustain food and oxygen production, decompose organic wastes, sequester carbon dioxide, and filter water. However, the hydraulics and biogeochemical functioning of soil systems exposed to gravities lower than the Earth's are still unknown. Since gravity is crucial in driving water flow, hypogravity will affect nutrient and oxygen transport in the liquid and gaseous phases, and could lead to suffocation of microorganisms and roots, and emissions of toxic gases. A highly mechanistic model coupling soil hydraulics and nutrient biogeochemistry previously tested on soils on Earth ( g=9.806 m s -2) is used to highlight the effects of gravity on the functioning of cropping units on Mars (0.38 g), the Moon (0.16 g), and in the international space station (ISS, nearly 0 g). For each scenario, we have compared the net leaching of water, the leaching of NH 3, NH 4+, NO 2- and NO 3- solutes, the emissions of NH 3, CO 2, N 2O, NO and N 2 gases, the concentrations profiles of O 2, CO 2 and dissolved organic carbon (DOC) in soil, the pH, and the dynamics of various microbial functional groups within the root zone against the same control variables in the soil under terrestrial gravity. The response of the soil ecodynamics was relatively linear; gravitational accelerations lower than the Earth's resulted in 90-100% lower water leaching rates, 95-100% lower nutrient leaching rates, and lower emissions of NH 3 and NO gases (80-95% and 30-40%, respectively). Lower N loss through leaching resulted in 60-100% higher concentration of the microbial biomass, but did not alter the vertical stratification of the microbial functional groups with respect to the stratification on Earth. However, the higher biomass concentration produced higher

  3. Report of evaluation to confirm the validity of 'the Concept of securing the mid-term safety' for units 1 to 4 at Fukushima Dai-ichi Nuclear Power Station, Tokyo Electric Power Co., Inc

    International Nuclear Information System (INIS)

    Ono, Hiroshi; Hoshi, Harutaka; Funayama, Kyoko

    2012-03-01

    The Nuclear and Industrial Safety Agency (NISA) requested Tokyo Electric Power Co., Inc. (TEPCO) to submit the report to confirm that the emergency measures performed to pacify the Fukushima Dai-ichi NPP accident complied with 'the basic target and requirements for securing safety' which were defined in order to secure the safety of the public and workers until the operation for reactor decommissioning starts following the completion of Step 2. After receipt of the report from TEPCO, NISA requested the Japan Nuclear Energy Safety Organization (JNES) to cooperate to evaluate technical adequacy on safety assessment of loss of coolant injection into reactor pressure vessel in 'Report on the Facility Operation Plan based on the 'Concept of Securing the Mid-Term Safety' for Units 1 to 4 at Fukushima Dai-ichi Nuclear Power Station (NPS), TEPCO (part 1)'. JNES implemented the evaluation for temperature of the in-vessel structural materials, amount of cesium released to the environment and effective dose at loss of coolant injection applying different analytical method from TEPCO and confirmed analytical conditions, calculation process and validity of the calculated results in response to the cooperation request of NISA. (1) In base analysis, JNES evaluated temperature of the in-vessel structure, amount of cesium released to the environment and effective dose using appropriate analytical models and analytical conditions with suitable conservativeness and confirmed that the calculated result of a final dose was less than the dose limit as a guide. (2) In reference analysis, JNES evaluated temperature of the in-vessel structure, amount of cesium released to the environment and effective dose using the conservative analytical model equivalent to TEPCO analytical method under same analytical conditions and confirmed no erroneous calculation process by TEPCO. (3) In sensitivity analysis, JNES evaluated the following cases for 12 hours loss of

  4. 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.

  5. Guangdong Daya Bay nuclear power station project

    International Nuclear Information System (INIS)

    Zeng Wen Xing

    1994-01-01

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

  6. Anemometer performance at fire-weather stations.

    Science.gov (United States)

    Donald A. Haines; John S. Frost

    1984-01-01

    A survey of 142 fire-weather stations in the Northeastern United States showed that, although maintenance was generally satisfactory, calibration or testing of anemometers was virtually nonexistent. We tested these anemometers using portable equipment that we designed and found the deviations from true wind speed.

  7. Materials Test Station

    Data.gov (United States)

    Federal Laboratory Consortium — When completed, the Materials Test Station at the Los Alamos Neutron Science Center will meet mission need. MTS will provide the only fast-reactor-like irradiation...

  8. MCFRS Incidents by Station

    Data.gov (United States)

    Montgomery County of Maryland — This dataset contains the monthly summary data indicating incident occurred in each fire station response area. The summary data is the incident count broken down by...

  9. FEMA DFIRM Station Start

    Data.gov (United States)

    Minnesota Department of Natural Resources — This table contains information about station starting locations. These locations indicate the reference point that was used as the origin for distance measurements...

  10. "Central Station" Londonis

    Index Scriptorium Estoniae

    2000-01-01

    Londoni galeriis Milch seitsme läti, leedu ja eesti kunstniku projekt "Central Station". Kuraatorid Lisa Panting, Sally Tallant. Eestist osalevad Hanno Soans (Catarina Campinoga koostöös valminud video), Kiwa, Kai Kaljo

  11. Mukilteo Research Station

    Data.gov (United States)

    Federal Laboratory Consortium — Research at the Mukilteo Research Station focuses on understanding the life cycle of marine species and the impacts of ecosystem stressors on anadromous and marine...

  12. Electrostatic pickup station

    CERN Multimedia

    CERN PhotoLab

    1982-01-01

    Electrostatic pickup station, with 4 interleaved electrodes, to measure beam position in the horizontal and vertical plane. This type is used in the transfer lines leaving the PS (TT2, TT70, TTL2). See also 7904075.

  13. Capacity at Railway Stations

    DEFF Research Database (Denmark)

    Landex, Alex

    2011-01-01

    zone(s) the possible conflicts with other trains (also in the opposite direction) are taken into account leading to more trustworthy results. Although the UIC 406 methodology proposes that the railway network should be divided into line sections when trains turn around and when the train order...... is changed, this paper recommends that the railway lines are not always be divided. In case trains turn around on open (single track) line, the capacity consumption may be too low if a railway line is divided. The same can be the case if only few trains are overtaken at an overtaking station. For dead end......Stations do have other challenges regarding capacity than open lines as it is here the traffic is dispatched. The UIC 406 capacity method that can be used to analyse the capacity consumption can be exposed in different ways at stations which may lead to different results. Therefore, stations need...

  14. Master Station History Report

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — The Standard/Legacy MSHR, formally identified as the DSI-9767 dataset, is the legacy dataset/report sorted by NCDC Station ID and period of record. This...

  15. ASOS Station Photos

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — The images contained in this library are of stations in the Automated Surface Observing System (ASOS) network. These images were taken between 1998-2001 for the ASOS...

  16. Natural Weathering Exposure Station

    Data.gov (United States)

    Federal Laboratory Consortium — The Corps of Engineers' Treat Island Natural Weathering Exposure Station is a long-term natural weathering facility used to study concrete durability. Located on the...

  17. Multiple Craft Stations.

    Science.gov (United States)

    Johns, Mary Sue

    1980-01-01

    Described are three craft stations (claywork, papermaking, and stamp designing) for intermediate grade students, to correlate with their classroom study which focused on Ohio: its history, geography, cities, industries, products and famous natives. (KC)

  18. Signal Station Inspection Reports

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — Handwritten reports resulting from detailed inspections of US Army Signal Service Stations, 1871-1889. Features reported included instrument exposure and condition,...

  19. Maine Field Station

    Data.gov (United States)

    Federal Laboratory Consortium — In 2000 NOAA's National Marine Fisheries Service established the Maine Field Station in Orono, ME to have more direct involvement in the conservation of the living...

  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. 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.

  2. 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

  3. Gas Stations, US, 2010, NAVTEQ

    Data.gov (United States)

    U.S. Environmental Protection Agency — The Gas_Stations dataset is derived from the Navteq 'AUTOSVC' SDC layer (FAC_TYPE=5540) and contains gas stations and petrol stations. This NAVTEQ dataset is...

  4. Enhanced Master Station History Report

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — The Enhanced Master Station History Report (EMSHR) is a compiled list of basic, historical information for every station in the station history database, beginning...

  5. Performance assessment of Point Lepreau Generating Station

    International Nuclear Information System (INIS)

    Alikhan, S.

    1991-01-01

    The Point Lepreau Generating Station, a 680 MWe CANDU unit, is located about 40 km southwest of the city of Saint John, New Brunswick, Canada. It was declared in-service on 1 February, 1983 and, since then, has demonstrated an average cross capacity factor of over 93% up to the end of 1990. This paper compared the performance of the station with other sister CANDU units and the Light Water Reactors world-wide using the following ten performance indicators, as applicable: - gross capacity factor; - fuel burn-up; - heavy water upkeep; - unplanned reactor trips while critical; - forced outage rate; - fuel handling performance; - derived emission of radioactive effluents to environment; - personnel radiation dose; - industrial safety; - low-level solid radioactive wastes. The paper examines various areas of station activities including management and organization, operations and maintenance, technical support, fuel handling and health physics in order to highlight some of the 'good practices' which are believed to have made a significant contribution towards achieving the demonstrated performance of Point Lepreau G.S. In addition, several areas of potential improvement are discussed in order to maintain and enhance, where practicable, the safety, reliability and economic performance of the station. In this context, a careful review of the operating experiences, both in-house and at other stations, and a judicious application of lessons learned plays a significant role. (author)

  6. Groundwater Hydrology and Chemistry in and near an Emulsified Vegetable-Oil Injection Zone, Solid Waste Management Unit 17, Naval Weapons Station Charleston, North Charleston, South Carolina, 2004-2009

    Science.gov (United States)

    Vroblesky, Don A.; Petkewich, Matthew D.; Lowery, Mark A.; Conlon, Kevin J.; Casey, Clifton C.

    2010-01-01

    The U.S. Geological Survey and the Naval Facilities Engineering Command Southeast investigated the hydrology and groundwater chemistry in the vicinity of an emulsified vegetable-oil injection zone at Solid Waste Management Unit (SWMU) 17, Naval Weapons Station Charleston, North Charleston, South Carolina. In May 2004, Solutions-IES initiated a Phase-I pilot-scale treatability study at SWMU17 involving the injection of an edible oil emulsion into the aquifer near wells 17PS-01, 17PS-02, and 17PS-03 to treat chlorinated solvents. The Phase-I injection of emulsified vegetable oil resulted in dechlorination of trichloroethene (TCE) to cis-1,2-dichloroethene (cDCE), but the dechlorination activity appeared to stall at cDCE, with little further dechlorination of cDCE to vinyl chloride (VC) or to ethene. The purpose of the present investigation was to examine the groundwater hydrology and chemistry in and near the injection zone to gain a better understanding of the apparent remediation stall. It is unlikely that the remediation stall was due to the lack of an appropriate microbial community because groundwater samples showed the presence of Dehalococcoides species (sp.) and suitable enyzmes. The probable causes of the stall were heterogeneous distribution of the injectate and development of low-pH conditions in the injection area. Because groundwater pH values in the injection area were below the range considered optimum for dechlorination activity, a series of tests was done to examine the effect on dechlorination of increasing the pH within well 17PS-02. During and following the in-well pH-adjustment tests, VC concentrations gradually increased in some wells in the injection zone that were not part of the in-well pH-adjustment tests. These data possibly reflect a gradual microbial acclimation to the low-pH conditions produced by the injection. In contrast, a distinct increase in VC concentration was observed in well 17PS-02 following the in-well pH increase. Adjustment

  7. Public Radio Stations' Educational Services, 1982-83.

    Science.gov (United States)

    Katz, Joan H.; Wood, Denise E.

    Highlights are presented from a third survey of educational services provided by public radio stations to elementary, secondary, and postsecondary educational institutions throughout the United States for the 2-year period from September 1, 1981 to August 30, 1983. Findings presented are based on the responses of 49 stations out of the 132…

  8. Utilities respond to nuclear station blackout rule

    International Nuclear Information System (INIS)

    Rubin, A.M.; Beasley, B.; Tenera, L.P.

    1990-01-01

    The authors discuss how nuclear plants in the United States have taken actions to respond to the NRC Station Blackout Rule, 10CFR50.63. The rule requires that each light water cooled nuclear power plant licensed to operate must be able to withstand for a specified duration and recover from a station blackout. Station blackout is defined as the complete loss of a-c power to the essential and non-essential switch-gear buses in a nuclear power plant. A station blackout results from the loss of all off-site power as well as the on-site emergency a-c power system. There are two basic approaches to meeting the station blackout rule. One is to cope with a station blackout independent of a-c power. Coping, as it is called, means the ability of a plant to achieve and maintain a safe shutdown condition. The second approach is to provide an alternate a-c power source (AAC)

  9. ILRS Station Reporting

    Science.gov (United States)

    Noll, Carey E.; Pearlman, Michael Reisman; Torrence, Mark H.

    2013-01-01

    Network stations provided system configuration documentation upon joining the ILRS. This information, found in the various site and system log files available on the ILRS website, is essential to the ILRS analysis centers, combination centers, and general user community. Therefore, it is imperative that the station personnel inform the ILRS community in a timely fashion when changes to the system occur. This poster provides some information about the various documentation that must be maintained. The ILRS network consists of over fifty global sites actively ranging to over sixty satellites as well as five lunar reflectors. Information about these stations are available on the ILRS website (http://ilrs.gsfc.nasa.gov/network/stations/index.html). The ILRS Analysis Centers must have current information about the stations and their system configuration in order to use their data in generation of derived products. However, not all information available on the ILRS website is as up-to-date as necessary for correct analysis of their data.

  10. International Space Station Future Correlation Analysis Improvements

    Science.gov (United States)

    Laible, Michael R.; Pinnamaneni, Murthy; Sugavanam, Sujatha; Grygier, Michael

    2018-01-01

    Ongoing modal analyses and model correlation are performed on different configurations of the International Space Station (ISS). These analyses utilize on-orbit dynamic measurements collected using four main ISS instrumentation systems: External Wireless Instrumentation System (EWIS), Internal Wireless Instrumentation System (IWIS), Space Acceleration Measurement System (SAMS), and Structural Dynamic Measurement System (SDMS). Remote Sensor Units (RSUs) are network relay stations that acquire flight data from sensors. Measured data is stored in the Remote Sensor Unit (RSU) until it receives a command to download data via RF to the Network Control Unit (NCU). Since each RSU has its own clock, it is necessary to synchronize measurements before analysis. Imprecise synchronization impacts analysis results. A study was performed to evaluate three different synchronization techniques: (i) measurements visually aligned to analytical time-response data using model comparison, (ii) Frequency Domain Decomposition (FDD), and (iii) lag from cross-correlation to align measurements. This paper presents the results of this study.

  11. International Space Station Carbon Dioxide Removal Assembly Testing

    Science.gov (United States)

    Knox, James C.

    2000-01-01

    Performance testing of the International Space Station Carbon Dioxide Removal Assembly flight hardware in the United States Laboratory during 1999 is described. The CDRA exceeded carbon dioxide performance specifications and operated flawlessly. Data from this test is presented.

  12. Toluene stability Space Station Rankine power system

    Science.gov (United States)

    Havens, V. N.; Ragaller, D. R.; Sibert, L.; Miller, D.

    1987-01-01

    A dynamic test loop is designed to evaluate the thermal stability of an organic Rankine cycle working fluid, toluene, for potential application to the Space Station power conversion unit. Samples of the noncondensible gases and the liquid toluene were taken periodically during the 3410 hour test at 750 F peak temperature. The results obtained from the toluene stability loop verify that toluene degradation will not lead to a loss of performance over the 30-year Space Station mission life requirement. The identity of the degradation products and the low rates of formation were as expected from toluene capsule test data.

  13. Telephony Earth Station

    Science.gov (United States)

    Morris, Adrian J.; Kay, Stan

    The Telephony Earth Station (TES), a digital full-mesh SCPC (single channel per carrier) system designed for satellite voice and data transmission is described. As compared to companded FM, the advanced speech compression and forward error correction techniques used by TES better achieve the quality, power, and bandwidth ideal for each application. In addition, the TES offers a fully demand-assigned voice call setup, handles point-to-point data channels, supports a variety of signaling schemes, and does not require any separate pilot receivers at the station, while keeping costs low through innovative technology and packaging. The TES can be used for both C-band and Ku-band (domestic or international) applications, and is configurable either as an VSAT (very small aperture terminal) using an SSPA, or as a larger station depending on the capacity requirements. A centralized DAMA processor and network manager is implemented using a workstation.

  14. Waste Transfer Stations

    DEFF Research Database (Denmark)

    Christensen, Thomas Højlund

    2011-01-01

    tion and transport is usually the most costly part of any waste management system; and when waste is transported over a considerable distance or for a long time, transferring the waste from the collection vehicles to more efficient transportation may be economically beneficial. This involves...... a transfer station where the transfer takes place. These stations may also be accessible by private people, offering flexibility to the waste system, including facilities for bulky waste, household hazardous waste and recyclables. Waste transfer may also take place on the collection route from small...... satellite collection vehicles to large compacting vehicles that cannot effectively travel small streets and alleys within the inner city or in residential communities with narrow roads. However, mobile transfer is not dealt with in this chapter, which focuses on stationary transfer stations. This chapter...

  15. Hydrogen vehicle fueling station

    Energy Technology Data Exchange (ETDEWEB)

    Daney, D.E.; Edeskuty, F.J.; Daugherty, M.A. [Los Alamos National Lab., NM (United States)] [and others

    1995-09-01

    Hydrogen fueling stations are an essential element in the practical application of hydrogen as a vehicle fuel, and a number of issues such as safety, efficiency, design, and operating procedures can only be accurately addressed by a practical demonstration. Regardless of whether the vehicle is powered by an internal combustion engine or fuel cell, or whether the vehicle has a liquid or gaseous fuel tank, the fueling station is a critical technology which is the link between the local storage facility and the vehicle. Because most merchant hydrogen delivered in the US today (and in the near future) is in liquid form due to the overall economics of production and delivery, we believe a practical refueling station should be designed to receive liquid. Systems studies confirm this assumption for stations fueling up to about 300 vehicles. Our fueling station, aimed at refueling fleet vehicles, will receive hydrogen as a liquid and dispense it as either liquid, high pressure gas, or low pressure gas. Thus, it can refuel any of the three types of tanks proposed for hydrogen-powered vehicles -- liquid, gaseous, or hydride. The paper discusses the fueling station design. Results of a numerical model of liquid hydrogen vehicle tank filling, with emphasis on no vent filling, are presented to illustrate the usefulness of the model as a design tool. Results of our vehicle performance model illustrate our thesis that it is too early to judge what the preferred method of on-board vehicle fuel storage will be in practice -- thus our decision to accommodate all three methods.

  16. Space Station cupola definition

    Science.gov (United States)

    Weaver, Laurie A.

    1988-01-01

    The concept of a Space Station cupola has evolved from a small bubble-type viewport into the primary location for proximity operations requiring direct unobstructed viewing. Derived from a viewing analysis conducted by the Man-Systems Division at the Johnson Space Center, the cupola represents a solution for out-of-plane viewing which cannot be provided by windows placed in the shell of the habitation and/or laboratory modules. An extended Man-Systems design study resulted in several cupola configurations, each illustrating an alternate solution to the required balance between viewing, projected Space Station operations, and human/machine interface issues.

  17. Testing EDM of Total Stations

    Directory of Open Access Journals (Sweden)

    Cirbus Ján

    2001-03-01

    Full Text Available The paper is devoted to testing electrooptical distance measuring devices (EDM built in total stations, than can be used for various tasks in the contemporary geodetic works. A rich market offer and availability of these universal measuring systems with satisfying distance range, excellent accuracy and other parameters, make total stations as dominant terrestrial geodetic instruments.For succesfully applying these instruments, above all for relliable distance measurements, the stability of the modulation frequency is the most important pre-condition. In the article, therefore, there are given some methods to verify the modulation frequency stability. In addition, some ways for determining the EDM distance constant and periodical corrections of the phase measuring unit are introduced for 4 types of EDM : LEICA 1700L, TOPCON GTS6A, TOPCON GTS2, C.ZEISS ELTA50. It were also investigated their possibilities for precise distance survey. Values of the determined constants and periodical corrections are presented in Tab. 2.Based on the investigation results of the 4 EDM types and using the values m obtained for different distances S, equations of the a posteriori standard deviations in form : m = (a+b.S were derived too.

  18. Shippingport Station Decommissioning Project

    International Nuclear Information System (INIS)

    1989-01-01

    This Topical Report is a synopsis of the decontamination of plant components and structures at the Shippingport Station Decommissioning Project (SSDP). The information is provided as a part of the Technology Transfer Program to document the preparation activities in support of the shipment of radioactive wastes and the unconditional release of the site and structural materials. 1 ref., 16 figs., 4 tabs

  19. Designing a Weather Station

    Science.gov (United States)

    Roman, Harry T.

    2012-01-01

    The collection and analysis of weather data is crucial to the location of alternate energy systems like solar and wind. This article presents a design challenge that gives students a chance to design a weather station to collect data in advance of a large wind turbine installation. Data analysis is a crucial part of any science or engineering…

  20. Hydrogen Fuelling Stations

    DEFF Research Database (Denmark)

    Rothuizen, Erasmus Damgaard

    station has been developed in Dymola. The models include the fuelling protocol (J2601) for hydrogen vehicles made by Society of Automotive Engineers (SAE) and the thermodynamic property library CoolProp is used for retrieving state point. The components in the hydrogen fuelling library are building up...

  1. Point Lepreau generating station

    International Nuclear Information System (INIS)

    Ganong, G.H.D.; Strang, A.E.; Gunter, G.E.; Thompson, T.S.

    Point Lepreau-1 reactor is a 600 MWe generating station expected to be in service by October 1979. New Brunswick is suffering a 'catch up' phenomenon in load growth and needs to decrease dependence on foreign oil. The site is on salt water and extensive study has gone into corrosion control. Project management, financing and scheduling have unique aspects. (E.C.B.)

  2. Avoiding Service Station Fraud.

    Science.gov (United States)

    Burton, Grace M.; Burton, John R.

    1982-01-01

    High school students are warned against service station fraud. A problem-solving section is designed to help students calculate consumer costs for various fraudulent transactions. Several ways of reducing fraud or of lessening the chances of problems are noted. (MP)

  3. The Service Station.

    Science.gov (United States)

    Ohio State Univ., Columbus. Center for Vocational and Technical Education.

    The purpose of the teacher's guide is to encourage the primary student to expand his or her awareness of jobs within the community. The role of the service station worker is examined, with emphasis on the goods and services provided. Subject areas for which the materials in this guide have potential are social studies, art, and language. Each set…

  4. Electrostatic pickup station

    CERN Multimedia

    CERN PhotoLab

    1979-01-01

    Electrostatic pickup station, with 4 electrodes, to measure beam position in the horizontal and vertical plane. This type is used in the transfer lines leaving the PS (TT2, TTL2, TT70). See also 8206063, where the electrode shapes are clearly visible.

  5. Space Station Water Quality

    Science.gov (United States)

    Willis, Charles E. (Editor)

    1987-01-01

    The manned Space Station will exist as an isolated system for periods of up to 90 days. During this period, safe drinking water and breathable air must be provided for an eight member crew. Because of the large mass involved, it is not practical to consider supplying the Space Station with water from Earth. Therefore, it is necessary to depend upon recycled water to meet both the human and nonhuman water needs on the station. Sources of water that will be recycled include hygiene water, urine, and cabin humidity condensate. A certain amount of fresh water can be produced by CO2 reduction process. Additional fresh water will be introduced into the total pool by way of food, because of the free water contained in food and the water liberated by metabolic oxidation of the food. A panel of scientists and engineers with extensive experience in the various aspects of wastewater reuse was assembled for a 2 day workshop at NASA-Johnson. The panel included individuals with expertise in toxicology, chemistry, microbiology, and sanitary engineering. A review of Space Station water reclamation systems was provided.

  6. Space Station Energy Sizing

    Science.gov (United States)

    Rice, R. R.

    1983-01-01

    A general schematic for a space station power system is described. The major items of interest in the power system are the solar array, transfer devices, energy storage, and conversion equipment. Each item will have losses associated with it and must be utilized in any sizing study, and can be used as a checklist for itemizing the various system components.

  7. 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)

  8. Robotic dissolution station

    Energy Technology Data Exchange (ETDEWEB)

    Beugelsdijk, T.J.; Hollen, R.M.; Temer, D.J.; Haggart, R.J.; Erkkila, T.H.

    1991-12-31

    This invention is comprised of a robotic station for dissolving active metals in acid in an automated fashion. A vessel with cap, containing the active metal is placed onto a shuttle which retracts to a point at which it is directly beneath a cap removing and retaining mechanism. After the cap is removed, a tube carrying an appropriate acid is inserted into the vessel, and the acid is introduced. The structure of the station forms an open hood which is swept of gases generated by the dissolution and the air removed to a remote location for scrubbing. After the reaction is complete, the shuttle extends and the vessel may be removed by a robot arm.

  9. Shippingport station communications program

    International Nuclear Information System (INIS)

    Stote, J.J.

    1988-01-01

    The author discusses how the communications program for the Shippingport Atomic Power Station has a long history. It can be traced as far back as 1953, when the U.S. Atomic Energy Commission (AEC) awarded a contract to Westinghouse Electric to design the nuclear portion of a power plant for electric utility use. During May of the next year, President Eisenhower initiated groundbreaking ceremonies for the construction of the commercial atomic power plant at Shippingport, Pennsylvania

  10. The nuclear power station

    International Nuclear Information System (INIS)

    Plettner, B.

    1987-04-01

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

  11. Summit Station Skiway Review

    Science.gov (United States)

    2013-03-01

    determine its usefulness for enhancing runway performance. We docu- mented the snow strength with a Rammsonde Cone Penetrometer and de- termined the... Penetrometer and delivered it to Summit during the Phase III turnover in February 2011 so that it would be available for testing during spring skiway...discussed current maintenance practices with the Station Manager, trained staff on proper use of the Rammsonde Cone Penetrometer , inspected current

  12. Dose management programmes at Kaiga Generating Station

    International Nuclear Information System (INIS)

    Vijayan, P.; Prabhakaran, V.; Managavi, Sadashiv B.; Danannavar, Veerendra; Biju, P.; Manoj Kumar, M.; Shrikrishna, U.V.

    2001-01-01

    Kaiga Generating Station (KGS) has two units of pressurized heavy water reactors of 220 MWe each capacity. KGS-2 started power generation since 1999 and KGS-1 since 2000. Several programmes such as assessment of radioactive condition, training on radiological safety aspects, job planning in radioactive areas, etc. are conducted periodically to implement an effective dose control programmes in KGS. These efforts are briefly discussed in this report. Facilities and techniques to implement ALARA programs are also highlighted in this report. (author)

  13. 33 CFR 334.930 - Anaheim Bay Harbor, Calif.; Naval Weapons Station, Seal Beach.

    Science.gov (United States)

    2010-07-01

    ... Weapons Station, Seal Beach. 334.930 Section 334.930 Navigation and Navigable Waters CORPS OF ENGINEERS... Bay Harbor, Calif.; Naval Weapons Station, Seal Beach. (a) The restricted area. The water of Anaheim Bay Harbor between the east and west jetties at the United States Naval Weapons Station, Seal Beach...

  14. 75 FR 38147 - FirstEnergy Nuclear Operating Company; Davis-Besse Nuclear Power Station; Exemption

    Science.gov (United States)

    2010-07-01

    ... Company; Davis-Besse Nuclear Power Station; Exemption 1.0 Background FirstEnergy Nuclear Operating Company... of the Davis-Besse Nuclear Power Station, Unit 1 (DBNPS). The license provides, among other things...-Besse Nuclear Power Station Exemption Request The licensee provided detailed information in the...

  15. Automatic Traffic Recorder (ATR) Stations

    Data.gov (United States)

    Department of Homeland Security — The data included in the GIS Traffic Stations Version database have been assimilated from station description files provided by FHWA for Weigh-in-Motion (WIM), and...

  16. Weigh-in-Motion Stations

    Data.gov (United States)

    Department of Homeland Security — The data included in the GIS Traffic Stations Version database have been assimilated from station description files provided by FHWA for Weigh-in-Motion (WIM), and...

  17. Emergency Medical Service (EMS) Stations

    Data.gov (United States)

    Kansas Data Access and Support Center — EMS Locations in Kansas The EMS stations dataset consists of any location where emergency medical services (EMS) personnel are stationed or based out of, or where...

  18. Small power stations in the limelight

    International Nuclear Information System (INIS)

    Stricker, C.

    2001-01-01

    This short article discusses what the author describes as the small, 'decentrally situated' power stations of the future. The situation, where important players in the energy market are turning away from large-scale technology and propagating the use of small-scale decentralised power generation, is discussed. Technologies examined include micro-turbines, fuel cells, wind power, small combined heat and power units, Stirling-motor powered co-generation units and solar electricity generation. Also, the developments in the increasingly liberalised electricity market, in which electricity is already becoming a set of products from which the customer can freely choose, is discussed

  19. Environmental radiation measurement around Kaiga Generating Station

    International Nuclear Information System (INIS)

    Shelly, P.G.; Takale, R.A.; Swarnkar, M.; Sahu, S.K.; Pandit, G.G.

    2018-01-01

    Kaiga Generating Station (KGS) is the sixth nuclear power station of DAE situated at Kaiga, near river Kali in Uttar Kannada district of Karnataka. The plant has been in operation since March 2000 and has four units. The fourth unit went critical on 27 November 2010. The two oldest units comprise the west half of the site and the two newer units are adjoining the east side of the site. All of the four units are small-sized CANDU plants of 220 MWe. The gamma radiation monitoring in the region is carried out using Thermoluminescence Dosimeters (TLDs). It was started in late 1989 to generate the data on prevalent external gamma radiation levels in the environs of KGS. During preoperational period twenty-seven locations had been surveyed and the furthest monitoring location was approximately 15 Km from stack. After the power plant started operating, twenty-six monitoring locations were selected for the regular TLD monitoring covering 32 kin. Over the period according to the requirement of the site monitoring locations has been increased to forty. The results of environmental gamma monitoring programme carried out at the KGS sites in terms of annual average dose to public is given in this paper

  20. Air and radiation monitoring stations

    CERN Multimedia

    AUTHOR|(SzGeCERN)582709

    2015-01-01

    CERN has around 100 monitoring stations on and around its sites. New radiation measuring stations, capable of detecting even lower levels of radiation, were installed in 2014. Two members of HE-SEE group (Safety Engineering and Environment group) in front of one of the new monitoring stations.

  1. International Space Station: Expedition 2000

    Science.gov (United States)

    2000-01-01

    Live footage of the International Space Station (ISS) presents an inside look at the groundwork and assembly of the ISS. Footage includes both animation and live shots of a Space Shuttle liftoff. Phil West, Engineer; Dr. Catherine Clark, Chief Scientist ISS; and Joe Edwards, Astronaut, narrate the video. The first topic of discussion is People and Communications. Good communication is a key component in our ISS endeavor. Dr. Catherine Clark uses two soup cans attached by a string to demonstrate communication. Bill Nye the Science Guy talks briefly about science aboard the ISS. Charlie Spencer, Manager of Space Station Simulators, talks about communication aboard the ISS. The second topic of discussion is Engineering. Bonnie Dunbar, Astronaut at Johnson Space Flight Center, gives a tour of the Japanese Experiment Module (JEM). She takes us inside Node 2 and the U.S. Lab Destiny. She also shows where protein crystal growth experiments are performed. Audio terminal units are used for communication in the JEM. A demonstration of solar arrays and how they are tested is shown. Alan Bell, Project Manager MRMDF (Mobile Remote Manipulator Development Facility), describes the robot arm that is used on the ISS and how it maneuvers the Space Station. The third topic of discussion is Science and Technology. Dr. Catherine Clark, using a balloon attached to a weight, drops the apparatus to the ground to demonstrate Microgravity. The bursting of the balloon is observed. Sherri Dunnette, Imaging Technologist, describes the various cameras that are used in space. The types of still cameras used are: 1) 35 mm, 2) medium format cameras, 3) large format cameras, 4) video cameras, and 5) the DV camera. Kumar Krishen, Chief Technologist ISS, explains inframetrics, infrared vision cameras and how they perform. The Short Arm Centrifuge is shown by Dr. Millard Reske, Senior Life Scientist, to subject astronauts to forces greater than 1-g. Reske is interested in the physiological effects of

  2. Automation scope at Roxboro generating station

    International Nuclear Information System (INIS)

    Ipakchi, A.; Chrisler, G.; Damesek, S.; Fields, E.W.; Cook, B.C.; Divakaruni, M.

    1991-01-01

    Many fossil fired power plant have replaced their aging unit control hardware with modern DCS technology. This paper describes a jointly sponsored project by EPRI, Carolina Power and Light Co. (CP and L) and ABB, to implement plant automation functions which would complement DCS technology, and result in improvements in plant operations in terms of heat rate, availability, and operations cost. These will be demonstrated at CP and L's Roxboro Station, a 4 unit coal fired plant with total capacity of nearly 2,477 MW. The scope of this four year project includes installation of a plant-wide information management system, automation of unit testing, implementation of advanced controls, intelligent alarms, operator advisory functions, and a plant-wide simulator, as well as support for plant unit economic dispatch

  3. Lunar Base Thermoelectric Power Station Study

    International Nuclear Information System (INIS)

    Determan, William; Frye, Patrick; Mondt, Jack; Fleurial, Jean-Pierre; Johnson, Ken; Stapfer, Gerhard; Brooks, Michael; Heshmatpour, Ben

    2006-01-01

    Under NASA's Project Prometheus, the Nuclear Space Power Systems Program, the Jet Propulsion Laboratory, Pratt and Whitney Rocketdyne, and Teledyne Energy Systems have teamed with a number of universities, under the Segmented Thermoelectric Multicouple Converter (STMC) Task, to develop the next generation of advanced thermoelectric converters for space reactor power systems. Work on the STMC converter assembly has progressed to the point where the lower temperature stage of the segmented multicouple converter assembly is ready for laboratory testing, and promising candidates for the upper stage materials have been identified and their properties are being characterized. One aspect of the program involves mission application studies to help define the potential benefits from the use of these STMC technologies for designated NASA missions such as a lunar base power station where kilowatts of power would be required to maintain a permanent manned presence on the surface of the moon. A modular 50 kWe thermoelectric power station concept was developed to address a specific set of requirements developed for this particular mission concept. Previous lunar lander concepts had proposed the use of lunar regolith as in-situ radiation shielding material for a reactor power station with a one kilometer exclusion zone radius to minimize astronaut radiation dose rate levels. In the present concept, we will examine the benefits and requirements for a hermetically-sealed reactor thermoelectric power station module suspended within a man-made lunar surface cavity. The concept appears to maximize the shielding capabilities of the lunar regolith while minimizing its handling requirements. Both thermal and nuclear radiation levels from operation of the station, at its 100-m exclusion zone radius, were evaluated and found to be acceptable. Site preparation activities are reviewed as well as transport issues for this concept. The goal of the study was to review the entire life cycle of

  4. Space Station Radiator Test Hosted by NASA Lewis at Plum Brook Station

    Science.gov (United States)

    Speth, Randall C.

    1998-01-01

    In April of 1997, the NASA Lewis Research Center hosted the testing of the photovoltaic thermal radiator that is to be launched in 1999 as part of flight 4A of the International Space Station. The tests were conducted by Lockheed Martin Vought Systems of Dallas, who built the radiator. This radiator, and three more like it, will be used to cool the electronic system and power storage batteries for the space station's solar power system. Three of the four units will also be used early on to cool the service module.

  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). Supplement No. 9

    International Nuclear Information System (INIS)

    1985-03-01

    This supplement addresses TUEC's analyses in support of its request to amend the Comanche Peak Final Safety Analysis Report to eliminate the commitment that coatings inside the reactor Containment Building be qualified for Units 1 and 2. In addition, this supplement provides the results of the staff's evaluation and resolution of 62 technical concerns and allegations in the coatings area for Unit 1. Because of the favorable resolution of the items discussed in this report, the staff concludes for the issues considered herein, that there is reasonable assurance that the facility can be operated by TUEC without endangering the health and safety of the public

  6. Darlington Station outage - a maintenance perspective

    Energy Technology Data Exchange (ETDEWEB)

    Plourde, J.; Marczak, J.; Stone, M.; Myers, R.; Sutton, K. [Ontario Hydro, Darlington Nuclear Generating Station, Bowmanville, ON (Canada)

    1997-07-01

    Ontario Hydro's Darlington Nuclear Generating Station (4x881MW(e)net) has carried out its first station outage since full commercial operation. The outage presented challenges to the organization in terms of outage planning, support, management, and safe execution within the constraints of schedule, budget and resources. This paper will focus on the success of the outage maintenance program, identifying the major work programs - a vacuum structure and containment outage, an emergency service water system outage, an emergency coolant injection system outage, intake channel inspections, low pressure service water inspections, and significant outage maintenance work on each of the four reactor units. Planning for the outage was initiated early in anticipation of this important milestone in the station's life. Detailed safety reviews - nuclear, radiation, and conventional - were conducted in support of the planned maintenance program. System lineup and work protection were provided by the Station Operator work group. Work protection permitry was initiated well in advance of the outage. Station maintenance staff resources were bolstered in support of the outage to ensure program execution could be maintained within the schedule. Training programs were in place to ensure that expectations were clear and that high standards would be maintained. Materials management issues in support of maintenance activities were given high priority to ensure no delays to the planned work. Station management review and monitoring in preparation for and during the outage ensured that staff priorities remained focused. Lessons learned from the outage execution are being formalized in maintenance procedures and outage management procedures, and shared with the nuclear community. (author)

  7. Darlington Station outage - a maintenance perspective

    International Nuclear Information System (INIS)

    Plourde, J.; Marczak, J.; Stone, M.; Myers, R.; Sutton, K.

    1997-01-01

    Ontario Hydro's Darlington Nuclear Generating Station (4x881MW(e)net) has carried out its first station outage since full commercial operation. The outage presented challenges to the organization in terms of outage planning, support, management, and safe execution within the constraints of schedule, budget and resources. This paper will focus on the success of the outage maintenance program, identifying the major work programs - a vacuum structure and containment outage, an emergency service water system outage, an emergency coolant injection system outage, intake channel inspections, low pressure service water inspections, and significant outage maintenance work on each of the four reactor units. Planning for the outage was initiated early in anticipation of this important milestone in the station's life. Detailed safety reviews - nuclear, radiation, and conventional - were conducted in support of the planned maintenance program. System lineup and work protection were provided by the Station Operator work group. Work protection permitry was initiated well in advance of the outage. Station maintenance staff resources were bolstered in support of the outage to ensure program execution could be maintained within the schedule. Training programs were in place to ensure that expectations were clear and that high standards would be maintained. Materials management issues in support of maintenance activities were given high priority to ensure no delays to the planned work. Station management review and monitoring in preparation for and during the outage ensured that staff priorities remained focused. Lessons learned from the outage execution are being formalized in maintenance procedures and outage management procedures, and shared with the nuclear community. (author)

  8. Southeast Regional Experiment Station

    Science.gov (United States)

    1994-08-01

    This is the final report of the Southeast Regional Experiment Station project. The Florida Solar Energy Center (FSEC), a research institute of the University of Central Florida (UCF), has operated the Southeast Regional Experiment Station (SE RES) for the US Department of Energy (DOE) since September 1982. Sandia National Laboratories, Albuquerque (SNLA) provides technical program direction for both the SE RES and the Southwest Regional Experiment Station (SW RES) located at the Southwest Technology Development Institute at Las Cruces, New Mexico. This cooperative effort serves a critical role in the national photovoltaic program by conducting system evaluations, design assistance and technology transfer to enhance the cost-effective utilization and development of photovoltaic technology. Initially, the research focus of the SE RES program centered on utility-connected PV systems and associated issues. In 1987, the SE RES began evaluating amorphous silicon (a-Si) thin-film PV modules for application in utility-interactive systems. Stand-alone PV systems began receiving increased emphasis at the SE RES in 1986. Research projects were initiated that involved evaluation of vaccine refrigeration, water pumping and other stand-alone power systems. The results of this work have led to design optimization techniques and procedures for the sizing and modeling of PV water pumping systems. Later recent research at the SE RES included test and evaluation of batteries and charge controllers for stand-alone PV system applications. The SE RES project provided the foundation on which FSEC achieved national recognition for its expertise in PV systems research and related technology transfer programs. These synergistic products of the SE RES illustrate the high visibility and contributions the FSEC PV program offers to the DOE.

  9. Designing Space Station

    Science.gov (United States)

    1986-01-01

    An overview of preparations for the construction of Space Station Freedom (SSF) is presented. The video includes footage of astronauts testing materials for erectable structures in space both in the Shuttle bay while in orbit and in a neutral buoyancy tank at McDonald Douglas' Underwater Test Facility. Also shown are footage of robot systems that will assist the astronauts in building SSF, a computer simulation of an Orbiting Maneuvering Vehicle, solar dynamic mirrors that will power SSF, and mockups of the living quarters of the SSF.

  10. Report on Darlington nuclear generating station

    International Nuclear Information System (INIS)

    1985-12-01

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

  11. Nuclear hydrogen power stations

    International Nuclear Information System (INIS)

    Eroshov, M.E.

    1976-01-01

    Short information about investigations on hydrogen energetics being carried out in the USSR as well as a review of the world literature on this subject are given. Combined cycles of thermochemical and electrochemical reactions applied for hydrogen and oxigen production from water are shown to be of interest, as a number of reactions in a cycle may be reduced to two, and the temperature of processes may be decreased to the temperature range specific to modern reactors. Construction features of nuclear-hydrogen power stations producing hydrogen through the use of thermo-electro-chemical cycles are considered. It is shown that at this stage it is possible to reduce time and expenses needed for realization of hydrogen production on a wide scale as compared to other reaction cycles requiring high temperatures and consequently, construction of high-temperature reactors. The conditions of energy and water transport at great distances by using hydrogen lines and the possibilities of development of desert and arid lands by using this mode of operation are considered. Possible ecological effect of hydrogen energetics development on the environment is pointed out, in particular, when power complexes are concentrated on a limited area. It is shown that it is reasonable to locate nuclear-hydrogen stations on shores

  12. Nuclear hydrogen power stations

    International Nuclear Information System (INIS)

    Eroshov, M.E.

    1976-01-01

    Short information about investigations on hydrogen energetics being carried out in the USSR as well as a review of the world literature on this subject are given. Combined cycles of thermochemical and electrochemical reactions applied for hydrogen and oxygen production from water are shown to be of interest, as a number of reactions in a cycle may be reduced to two, and the temperature of processes may be decreased to the temperature range specific to modern reactors. Construction features of nuclear-hydrogen power stations producing hydrogen through the use of thermo-electrochemical cycles are considered. It is shown that at this stage it is possible to reduce time and expenses needed for realization of hydrogen production on a wide scale as compared to other reaction cycles requiring high temperatures and consequently, construction of high-temperature reactors. The conditions of energy and water transport at great distances by using hydrogen lines and the possibilities of development of desert and arid lands by using this mode of operation are considered. Possible ecological effect of hydrogen energetics development on the environment is pointed out, in particular, when power complexes are concentrated on a limited area. It is shown that it is reasonable to locate nuclear-hydrogen stations on shores

  13. Simple Solutions for Space Station Audio Problems

    Science.gov (United States)

    Wood, Eric

    2016-01-01

    Throughout this summer, a number of different projects were supported relating to various NASA programs, including the International Space Station (ISS) and Orion. The primary project that was worked on was designing and testing an acoustic diverter which could be used on the ISS to increase sound pressure levels in Node 1, a module that does not have any Audio Terminal Units (ATUs) inside it. This acoustic diverter is not intended to be a permanent solution to providing audio to Node 1; it is simply intended to improve conditions while more permanent solutions are under development. One of the most exciting aspects of this project is that the acoustic diverter is designed to be 3D printed on the ISS, using the 3D printer that was set up earlier this year. Because of this, no new hardware needs to be sent up to the station, and no extensive hardware testing needs to be performed on the ground before sending it to the station. Instead, the 3D part file can simply be uploaded to the station's 3D printer, where the diverter will be made.

  14. The work of the Animal Research Station, Cambridge.

    Science.gov (United States)

    Polge, Chris

    2007-06-01

    This paper traces the history of the Animal Research Station, Cambridge from its establishment in 1932 to its closure in 1986. The author worked there for forty years and was Director from 1979. Originally set up as a field station for Cambridge University's School of Agriculture, the Station was expanded after World War II as the Agricultural Research Council's Unit of Animal Reproduction. Beginning with semen and artificial insemination, research at the Station soon embraced superovulation and embryo transfer in farm animals. Many other technologies were also developed here, including IVF in pigs, cloning by nuclear transplantation of early embryonic cells, and the first genetically modified farm animals in Britain. This account recalls the Directors of the Station and their research teams together with details of their pioneering contribution to reproductive biology.

  15. Analysis of internal events for the Unit 1 of the Laguna Verde Nuclear Power Station. Appendixes; Analisis de eventos internos para la Unidad 1 de la Central Nucleoelectrica de Laguna Verde. Apendices

    Energy Technology Data Exchange (ETDEWEB)

    Huerta B, A.; Lopez M, R. [Comision Nacional de Seguridad Nuclear y Salvaguardias, 03000 Mexico D.F. (Mexico)

    1995-07-01

    This volume contains the appendices for the accident sequences analysis for those internally initiated events for Laguna Verde Unit 1, Nuclear Power Plant. The appendix A presents the comments raised by the Sandia National Laboratories technical staff as a result of the review of the Internal Event Analysis for Laguna Verde Unit 1 Nuclear Power Plant. This review was performed during a joint Sandia/CNSNS multi-day meeting by the end 1992. Also included is a brief evaluation on the applicability of these comments to the present study. The appendix B presents the fault tree models printed for each of the systems included and analyzed in the Internal Event Analysis for LVNPP. The appendice C presents the outputs of the TEMAC code, used for the cuantification of the dominant accident sequences as well as for the final core damage evaluation. (Author)

  16. Analysis of internal events for the Unit 1 of the Laguna Verde Nuclear Power Station. Appendixes; Analisis de eventos internos para la Unidad 1 de la Central Nucleoelectrica de Laguna Verde. Apendices

    Energy Technology Data Exchange (ETDEWEB)

    Huerta B, A.; Lopez M, R. [Comision Nacional de Seguridad Nuclear y Salvaguardias, 03000 Mexico D.F. (Mexico)

    1995-07-01

    This volume contains the appendices for the accident sequences analysis for those internally initiated events for Laguna Verde Unit 1, Nuclear Power Plant. The appendix A presents the comments raised by the Sandia National Laboratories technical staff as a result of the review of the Internal Event Analysis for Laguna Verde Unit 1 Nuclear Power Plant. This review was performed during a joint Sandia/CNSNS multi-day meeting by the end 1992. Also included is a brief evaluation on the applicability of these comments to the present study. The appendix B presents the fault tree models printed for each of the systems included and.analyzed in the Internal Event Analysis for LVNPP. The appendice C presents the outputs of the TEMAC code, used for the cuantification of the dominant accident sequences as well as for the final core damage evaluation. (Author)

  17. Modular integrated video system (MIVS) review station

    International Nuclear Information System (INIS)

    Garcia, M.L.

    1988-01-01

    An unattended video surveillance unit, the Modular Integrated Video System (MIVS), has been developed by Sandia National Laboratories for International Safeguards use. An important support element of this system is a semi-automatic Review Station. Four component modules, including an 8 mm video tape recorder, a 4-inch video monitor, a power supply and control electronics utilizing a liquid crystal display (LCD) are mounted in a suitcase for probability. The unit communicates through the interactive, menu-driven LCD and may be operated on facility power through the world. During surveillance, the MIVS records video information at specified time intervals, while also inserting consecutive scene numbers and tamper event information. Using either of two available modes of operation, the Review Station reads the inserted information and counts the number of missed scenes and/or tamper events encountered on the tapes, and reports this to the user on the LCD. At the end of a review session, the system will summarize the results of the review, stop the recorder, and advise the user of the completion of the review. In addition, the Review Station will check for any video loss on the tape

  18. Simulators of nuclear power stations

    International Nuclear Information System (INIS)

    Zanobetti, D.

    1984-01-01

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

  19. Local control stations

    International Nuclear Information System (INIS)

    Brown, W.S.; Higgins, J.C.; Wachtel, J.A.

    1993-01-01

    This paper describes research concerning the effects of human engineering design at local control stations (i.e., operator interfaces located outside the control room) on human performance and plant safety. The research considered both multifunction panels (e.g. remote shutdown panels) as well as single-function interfaces (e.g., valves, breakers, gauges, etc.). Changes in performance shaping factors associated with variations in human engineering at LCSs were estimated based on expert opinion. By means of a scaling procedure, these estimates were used to modify the human error probabilities in a PRA model, which was then employed to generate estimates of plant risk and scoping-level value/impact ratios for various human engineering upgrades. Recent documentation of human engineering deficiencies at single-function LCSs was also reviewed, and an assessment of the current status of LCSs with respect to human engineering was conducted

  20. Innovative Railway Stations

    Science.gov (United States)

    Rzepnicka, Sylwia; Załuski, Daniel

    2017-10-01

    In relation to modern demographic trends, evolving technologies and environment-friendly solutions increases the potential of rail considered as sustainable form of public transport. Contemporary tendencies of designing railway stations in Europe are focused on lowering energy consumption and reducing carbon emission. The main goal of the designers is to create a friendly and intuitive space for its users and at the same time a building that uses renewable energy sources and minimizes negative impact on the environment by the increase of biologically active areas, reuse of rainwater and greywater, innovative heating and cooling solutions and reduction of energy losses. The optimisation of a life circle in railway architecture introduces new approach to passenger service. Examples mentioned in the content of this article help to synthesize changes in approach to the design within the context of sustainability.

  1. Central Station Design Options

    DEFF Research Database (Denmark)

    2011-01-01

    The purpose of EDISON Work Package 4.1 is the evaluation of possible Central (charging) Stations design options for making possible the public charging of Electric Vehicles (EVs). A number of scenarios for EVs are assessed, with special emphasis on the options of Fast Charging and Battery Swapping....... With the 3-phase AC quick charging options of 11, 22 kW and 43 kW, (IEC 62196, EN60038, EN 61851) both the Danish and Bornholm environments offer a good chance for EV integration [1]. Dealing with Fast Charging, the study determined that 300kW Fast Charging, which corresponds to 10 minutes charging for a 50...... charging, rated at 50 kW, fast charging would be easier in both Denmark and Bornholm scenarios. For each scenario and charging power level, the possible number of EVs is estimated and finally architectural design options are proposed. Technical assessment is performed for evaluating the benefits...

  2. Heating of water by nuclear power stations

    International Nuclear Information System (INIS)

    Many studies have been carried out both in France and abroad to determine the magnitude of the thermal effects due to cooling of conventional or nuclear open-circuit electricity-generating stations. After an account of the main effects observed and the information derived from these results the discussion centres on the conclusions drawn from American research by the two bodies responsible for checking the impact of nuclear stations on the environment in the United States. The possible effects on aquatic organisms exposed to hot water discharges are of two kinds: the direct thermal effects (changes in the metabolism, growth rate and period of sexual maturity increase in mortality, etc..) and the indirect thermal effects (asphyxia due to a drop in the dissolved oxygen concentration, changes in the sensitivity to certain toxic substances, in resistance to infection, in the food chain) [fr

  3. Final programmatic environmental impact statement related to decontamination and disposal of radioactive wastes resulting from March 28, 1979 accident, Three Mile Island Nuclear Station, Unit 2, Docket No. 50-320

    International Nuclear Information System (INIS)

    1981-03-01

    The appendices included in this report include the following: Comments on the Draft Programmatic Environmental Impact Statement (A-1); Commission's Statement of Policy and Notice of Intent to Prepare a Programmatic Environmental Impact Statement (B-1); 'Final Environmental Assessment for Decontamination of the Three Mile Island Unit 2 Reactor Building Atmosphere, Final NRC Staff Report,' US Nuclear Regulatory Commission, NUREG-0662, May 1980 (C-1); 'Environmental Assessment for Use of EPICOR-Il at Three Mile Island Unit 2,' US Nuclear Regulatory Commission, NUREG-0591, October 3, 1979 (D-1); Fish and Fisheries of York Haven Pond and Conowingo Pond of the Susquehanna River and Upper Chesapeake Bay (E1); Reuse of Accident Water (F-1); Engineering Considerations for Treatment of TMI-2 Accident-Generated Liquid Waste G-1); Engineering Considerations Related to Immobilization of Radioactive Wastes (H-1); Justification for Radiation Fields Used in Section 6 I-1); Economic Cost Basis (K-1); Average Individual Quarterly Dose Limits Used in Determinations of Work Force Estimates (L-1); 'Long-Term Environmental Radiation Surveillance Plan for Three Mile Island,' US Environmental Protection Agency, 1981 (M-1); Occupational Radiation Exposure during Onsite Waste Handling (N-1); Decontamination Status of Auxiliary and Fuel Handling Buildings (0-1); Chemical Systems for Decontamination of Primary System Components (P-1); Onsite Storage Facility (Q-1); Proposed Additions to Technical Specifications for TMI-2 Cleanup Program (R-1); Calculations of Discharge of Processed Accident Water to the Atmosphere (S-1); The Behavior of Sorbable Radionuclides in the Susquehanna River and Chesapeake Bay (T-1); Decommissioning of TMI-2 (U-1); Assessment of Groundwater Liquid Pathway from Leakage of Containment Water at Three Mile Island, Unit 2 (V-1); Calculation Models and Parameters Used in Estimating Doses, and Interpretation of Model Results (W-1); Contributors to the PEIS X-1); Scheduled

  4. Programmatic environmental impact statement related to decontamination and disposal of radioactive wastes resulting from March 28, 1979 accident, Three Mile Island Nuclear Station, Unit 2 (Docket No. 50-320): Draft supplement dealing with post-defueling monitored storage and subsequent cleanup

    International Nuclear Information System (INIS)

    1988-04-01

    In accordance with the National Environmental Policy Act, the Commission's implementing regulations, and its April 27, 1981,Statement of Policy, the Programmatic environmental impact statement related to decontamination and disposal of radioactive wastes resulting from March 28, 1979 accident Three Mile Island Nuclear Station, Unit 2, NUREG-0683 (PEIS) is being supplemented. This draft supplement updates the enviromental evaluation of cleanup alternatives published in the PEIS, utilizing more complete and current information. Also, the draft supplement includes a specific environmental evaluation of the licensee's recently submitted proposal for post-defueling monitored storage. The NRC staff has concluded that the licensee's proposal to place the facility in a monitored storage configuration will not significantly affect the quality of the human environment. Further, any impacts from the long-term storage of the facility are outweighed by its benefits. 63 refs., 23 figs., 65 tabs

  5. Discharges from nuclear power stations

    International Nuclear Information System (INIS)

    1991-02-01

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

  6. Acceleration Environment of the International Space Station

    Science.gov (United States)

    McPherson, Kevin; Kelly, Eric; Keller, Jennifer

    2009-01-01

    Measurement of the microgravity acceleration environment on the International Space Station has been accomplished by two accelerometer systems since 2001. The Microgravity Acceleration Measurement System records the quasi-steady microgravity environment, including the influences of aerodynamic drag, vehicle rotation, and venting effects. Measurement of the vibratory/transient regime, comprised of vehicle, crew, and equipment disturbances, has been accomplished by the Space Acceleration Measurement System-II. Until the arrival of the Columbus Orbital Facility and the Japanese Experiment Module, the location of these sensors, and therefore, the measurement of the microgravity acceleration environment, has been limited to within the United States Laboratory. Japanese Aerospace Exploration Agency has developed a vibratory acceleration measurement system called the Microgravity Measurement Apparatus which will be deployed within the Japanese Experiment Module to make distributed measurements of the Japanese Experiment Module's vibratory acceleration environment. Two Space Acceleration Measurement System sensors from the United States Laboratory will be re-deployed to support vibratory acceleration data measurement within the Columbus Orbital Facility. The additional measurement opportunities resulting from the arrival of these new laboratories allows Principal Investigators with facilities located in these International Space Station research laboratories to obtain microgravity acceleration data in support of their sensitive experiments. The Principal Investigator Microgravity Services project, at NASA Glenn Research Center, in Cleveland, Ohio, has supported acceleration measurement systems and the microgravity scientific community through the processing, characterization, distribution, and archival of the microgravity acceleration data obtained from the International Space Station acceleration measurement systems. This paper summarizes the PIMS capabilities available

  7. Photochemical Assessment Monitoring Stations (PAMS)

    Data.gov (United States)

    U.S. Environmental Protection Agency — Photochemical Assessment Monitoring Stations (PAMS). This file provides information on the numbers and distribution (latitude/longitude) of air monitoring sites...

  8. Station History Of The Seismic Station In Ahmadu Bello University ...

    African Journals Online (AJOL)

    The station history of the Ahmadu Bello University, Zaria seismic station has been carried out. A total of two hundred and thirty (230) events at epicentral distances between 24o and 180o were selected from recordings covering the period January 1985 to December 1992. Dominants in the selected events are events from ...

  9. Stanwell power station project

    Energy Technology Data Exchange (ETDEWEB)

    Mills, David R; J Dey, Christopher [University of Sidney, Sidney (Australia); Morrison, Graham L [University of New South Wales, Sidney (Australia)

    2000-07-01

    This paper describes the Compact Linear Fresnel Reflector (CLFR) being developed for installation at the Stanwell power station in Queensland Australia. Stanwell Corporation Limited (SCL). Solahart International, Solsearch Pty. Ltd. And the universities of Sidney and New South Wales are cooperating in the project, and this first plant being partly funded by the Australian Greenhouse Office. The solar plant will be attached to a 1440 MW(e) coal fired plant. The 17000 m{sup 2} array will be the largest array in Australia, producing a peak of 13 MW of thermal energy which will offset the use of coal in the generation of electricity. It will use direct steam generation and will feed either steam or hot water at 265 Celsius degrees directly into the power station preheating cycle. The CLFR system, first developed by the University of Sidney and Solsearch Pty. Ltd., is simple and offers small reflector size, low structural cost, fixed receiver geometry. Initial installed plant costs are approximately US$1000 per kWe, but this includes the effect of high up-front design costs and the cost should drop substantially in the second and subsequent plants. [Spanish] Proyecto de la Planta Electrica Stanwell este articulo describe el Reflector Lineal Compacto Fresnel (CLFR, siglas en ingles) que se esta desarrollando para la instalacion de la planta electrica Stanwell en Queensland, Australia. La Corporacion Stanwell Limited (SCL), Solahart International, Solsearch Pty. Ltd., las universidades de Sidney y de New South Wales estan cooperando en este proyecto, y esta primera planta esta parcialmente auspiciada por la Australian Greenhouse Office. La planta solar sera anexa a una planta de carbon de 1440 MW(e). Este arreglo de 17000 m{sup 2} sera el mayor en Australia y producira un maximo de 13 MW en energia termica la cual contrarrestara el uso del carbon en la generacion de electricidad. Utilizara generacion con vapor directo y alimentara ya sea vapor o agua caliente a 265 grados

  10. Some novel on-power refuelling features of CANDU stations

    International Nuclear Information System (INIS)

    Erwin, D.; Pendlebury, B.; Watson, J.F.; Welch, A.C.

    1976-01-01

    Part A of the paper describes the reasons for, and advantages resulting from, the use of flow assisted refuelling in the CANDU type nuclear reactors at the Pickering Generating Station. A separate fuel handling system is used for each reactor unit, as distinct from the system employed at the Bruce Generating station, where the fuel handling system is shared among several units. Part B of the paper describes some of the advantages of the shared concept with particular emphasis on the availability of the fuel handling system. (author)

  11. Controversial power station

    International Nuclear Information System (INIS)

    Marcan, P.

    2008-01-01

    When information on plans to build a power station in Trebisov first appeared reactions differed. A 40-billion investment in a town with more than 20% unemployment seemed attractive. But some people did not like the idea of having a power plant located in the town. Around one year after the investment was officially announced TREND returned to Trebisov. In the meantime the investor has managed to overcome one of the biggest obstacles on its way to building a new power plant. The ministry responsible gave the environmental study a positive rating. But objectors are still not sure that everything is fine. They claim that the study misinterprets data and that the ministry did not show expertise when evaluating it. 'Is it possible that a coal power plant located in a town would have twice as many positive effects on peoples' health than negative ones? Why don't we build them everywhere?'asked the chairman of the civic society, Trebisov nahlas, Gejza Gore. The developer of the project, Ceskoslovenska energeticka spolocnost (CES), Kosice is fighting back and claims that their counterpart lacks professional arguments. In the meantime it is preparing for area management proceedings. Trebisov is also involved in the discussion and claims that the town planning scheme does not include such a project. The Ministry of Construction has a different opinion. In the opinion of the Ministry the town planning scheme allows a 885-megawatt power plant to be built only a few hundred meters away from housing estates. (author)

  12. Swedish encapsulation station review

    International Nuclear Information System (INIS)

    Andersson, Sven Olof; Brunzell, P.; Heibel, R.; McCarthy, J.; Pennington, C.; Rusch, C.; Varley, G.

    1998-06-01

    In the Encapsulation Station (ES) Review performed by NAC International, a number of different areas have been studied. The main objectives with the review have been to: Perform an independent review of the cost estimates for the ES presented in SKB's document 'Plan 1996'. This has been made through comparisons between the ES and BNFL's Waste Encapsulation Plant (WEP) at Sellafield as well as with the CLAB facility. Review the location of the ES (at the CLAB site or at the final repository) and its interaction with other parts of the Swedish system for spent fuel management. Review the logistics and plant capacity of the ES. Identify important safety aspects of the ES as a basis for future licensing activities. Based on NAC International's experience of casks for transport and storage of spent fuel, review the basic design of the copper/steel canister and the transport cask. This review insides design, manufacturing, handling and licensing aspects. Perform an overall comparison between the ES project and the CLAB project with the objective to identify major project risks and discuss their mitigation

  13. Swedish encapsulation station review

    Energy Technology Data Exchange (ETDEWEB)

    Andersson, Sven Olof; Brunzell, P.; Heibel, R.; McCarthy, J.; Pennington, C.; Rusch, C.; Varley, G. [NAC International, Zuerich (Switzerland)

    1998-06-01

    In the Encapsulation Station (ES) Review performed by NAC International, a number of different areas have been studied. The main objectives with the review have been to: Perform an independent review of the cost estimates for the ES presented in SKB`s document `Plan 1996`. This has been made through comparisons between the ES and BNFL`s Waste Encapsulation Plant (WEP) at Sellafield as well as with the CLAB facility. Review the location of the ES (at the CLAB site or at the final repository) and its interaction with other parts of the Swedish system for spent fuel management. Review the logistics and plant capacity of the ES. Identify important safety aspects of the ES as a basis for future licensing activities. Based on NAC International`s experience of casks for transport and storage of spent fuel, review the basic design of the copper/steel canister and the transport cask. This review insides design, manufacturing, handling and licensing aspects. Perform an overall comparison between the ES project and the CLAB project with the objective to identify major project risks and discuss their mitigation 19 refs, 9 figs, 35 tabs

  14. Dan jiang kou hydropower station turbine refurbishment

    Science.gov (United States)

    Zhang, R. Y.; Nie, S. Q.; Bazin, D.; Cheng, J. H.

    2012-11-01

    Dan jiangkou hydropower station refurbished project, isan important project of Chinese refurbishment market. Tianjin Alstom Hydro Co., ltd won this contract by right of good performance and design technology,Its design took into account all the constraints linked to the existing frame. It results in a specific and highly advanced shape.The objective of this paper is to introduce the successful turbine hydraulic design, model test and mechanical design of Dan jiangkou project; and also analyze the cavitation phenomena occurred on runner band surface of Unit 4 after putting into commercial operation. These technology and feedback shall be a good reference and experience for other similar projects

  15. AUSTA - a self-sufficient environmental analysis station for the analysis of nitrogen, sulfur and carbon compounds. Sub-project: development and construction of the central processing unit for the self-sufficient environmental analysis station. Final report; AUSTA - Autarke Umweltmessstation zur Analyse von Stickstoff-, Schwefel- und Kohlenstoffverbindungen. Teilvorhaben: Entwicklung und Konstruktion der Zentraleinheit fuer die autarke Umweltmessstation. Abschlussbericht

    Energy Technology Data Exchange (ETDEWEB)

    Lenk, N.; Ehrling, C.

    2002-07-01

    The aim of the common research project was the development of basics as well as the construction and the testing of a functional model for an environmental analysis system. This system should be able not only to analyze independently environmental toxicologically interesting Carbon, Nitrogen and Sulfur species from watery samples, but also to evaluate and document the results of the analysis. A functional model for the determination of TC/TN and the species TIC, Nitrate, Nitrite, Ammonium, Sulfite and Sulfide from an aqueous matrix, was built and tested successfully in the laboratory. The functional model was realized in a modular construction. Micro system technical components were integrated into the system. The dosage of samples and standards as well as the sample preparation for the determination of Nitrate is carried out via a special own-developed control module. The construction of the combustion unit with reactors and the appendant technique for joining parts was carried out in a miniaturization, not realized up to now. (orig.)

  16. Programmatic Environmental Impact Statement related to decontamination and disposal of radioactive wastes resulting from March 28, 1979 accident, Three Mile Island Nuclear Station, Unit 2 (Docket No. 50-320)

    International Nuclear Information System (INIS)

    1989-08-01

    This supplement updates the environmental evaluation of cleanup alternatives published in the PEIS utilizing more complete and current information. This supplement evaluates the licensee's proposal to complete the current cleanup effort and place the facility into monitored storage for an unspecified period of time. The licensee has indicated that the likely disposition of the facility following the storage period would by decommissioning at the time Unit 1 is decommissioned. Specifically, the supplement provides an environmental evaluation of the licensee's proposal and a number of alternative courses of action from the end of the current defueling effort to the beginning of decommissioning. However, it does not provide an evaluation of the environmental impacts associated with decommissioning. The Nuclear Regulatory Commission staff has concluded that the licensee's proposal to place the facility in monitored storage will not significantly affect the quality of the human environment. Further, any impacts associated with this action are outweighed by its benefits. The benefit of this action is the ultimate elimination of the small but continuing risk associated with the conditions of the facility resulting from the March 28, 1979, incident. 56 refs., 19 figs., 115 tabs

  17. Seismometer array station processors

    International Nuclear Information System (INIS)

    Key, F.A.; Lea, T.G.; Douglas, A.

    1977-01-01

    A description is given of the design, construction and initial testing of two types of Seismometer Array Station Processor (SASP), one to work with data stored on magnetic tape in analogue form, the other with data in digital form. The purpose of a SASP is to detect the short period P waves recorded by a UK-type array of 20 seismometers and to edit these on to a a digital library tape or disc. The edited data are then processed to obtain a rough location for the source and to produce seismograms (after optimum processing) for analysis by a seismologist. SASPs are an important component in the scheme for monitoring underground explosions advocated by the UK in the Conference of the Committee on Disarmament. With digital input a SASP can operate at 30 times real time using a linear detection process and at 20 times real time using the log detector of Weichert. Although the log detector is slower, it has the advantage over the linear detector that signals with lower signal-to-noise ratio can be detected and spurious large amplitudes are less likely to produce a detection. It is recommended, therefore, that where possible array data should be recorded in digital form for input to a SASP and that the log detector of Weichert be used. Trial runs show that a SASP is capable of detecting signals down to signal-to-noise ratios of about two with very few false detections, and at mid-continental array sites it should be capable of detecting most, if not all, the signals with magnitude above msub(b) 4.5; the UK argues that, given a suitable network, it is realistic to hope that sources of this magnitude and above can be detected and identified by seismological means alone. (author)

  18. Future international cooperation on space stations

    Science.gov (United States)

    Bartoe, John-David

    In the course of the next thirty years, extensive international cooperation in space may become the norm rather than the exception. The benefits from the mutual application and exchange of assets and knowledge may enable the development of projects that no nation could afford alone. Cooperation on technical projects may also yield political benefits such as alliance building, although potentially at a cost of making the program hostage to the vagaries of international politics. Successful past cooperative projects include the Apollo-Soyuz Test Project, Spacelab and Soviet Salyut and Mir space stations. The ongoing Space Station Freedom program is offering the first sustained long term opportunity for international cooperation in space. In addition to enabling potential advances in science and technology development, the station may serve as the stepping stone for future international efforts in areas such as planetary exploration. Any significant future increase in international cooperation would likely need to include both the United States and the Soviet Union. Such cooperation could offer many unique possibilities, including interactions between the Freedom and Mir. Indeed the success of future manned exploration missions may well depend on how well space-faring nations learn to cooperate with each other. International involvement in technical programs always creates an additional element of complexity regarding the technical requirements and resource management of a project. However, the experience of international cooperation to date tells us that there can be significant gains, both tangible and symbolic, from international participation.

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

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    1998-07-01

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

  20. Hinkley Point 'C' power station public inquiry: statement of case

    International Nuclear Information System (INIS)

    1988-08-01

    This Statement of Case contains full particulars of the case which the Central Electricity Generating Board (CEGB) proposes to put forward at the Hinkley Point ''C'' Inquiry. It relates to the planning application made by the CEGB for the construction of a 1200 MW Pressurized Water Reactor (PWR) power station at Hinkley Point in the United Kingdom, adjacent to an existing nuclear power station. The inquiry will consider economic, safety, environmental and planning matters relevant to the application and the implications for agriculture and local amenities of re-aligning two power transmission lines. The Statement contains submissions on the following matters: Topic 1 The Requirement for the Station; Topic 2 Safety and Design, including Radioactive Discharges; Topic 3 The On-Site Management of Radioactive Waste and Decommissioning of the Station; Topic 4 Emergency Arrangements; Topic 5 Local and Environmental Issues. (author)

  1. Physical degradation assessment of generator station cables

    International Nuclear Information System (INIS)

    Stonkus, D.J.

    1988-01-01

    Preliminary studies of fossil-fired and nuclear generator station cables indicate that the low voltage PVC insulated cables are in relatively good condition. The insulation is flexible and in the case of nuclear cables can withstand a design basis event after nearly 15 years of service. Cables insulated with styrene butadiene rubber have been found embrittled and cables insulated with SBR should be closely inspected in any plant assurance program. Thermal analysis using oxidative induction technique shows promise to indicate cable insulation degradation. Long term reliability assurance and plant life extension studies are being actively pursued at Ontario Hydro. A major study is currently underway to extend the life of the oldest operating fossil-fuel station, the 8-unit, 2400 MW Lakeview TGS in operation since the 1960s. Plant life assurance programs have been initiated at the 2000 MW Lambton TGS in operation since 1969, and for the oldest operating nuclear plant, Pickering NGS A in operation since the early 1970s. As cables are considered one of the critical components in a generator station due to the extreme difficulty and cost of cable replacement, test programs have been initiated to evaluate the physical degradation of the cables and relate the results to electrical diagnostic tests and to chemical changes. The decommissioning of two small nuclear stations, the 20 MW Nuclear Power Demonstration (NPD) and the 200 MW Douglas Point NGS, which were placed in service in 1962 and 1967 respectively, will provide an opportunity to perform destructive electrical and physical evaluation on field aged cables

  2. Opportunities for the operation of the Comision Federal de Electricidad`s fossil fuel power plant stations eventually to be retired as cogeneration units; Oportunidades de operar las centrales termoelectricas de la Comision Federal de Electricidad, eventualmente retirables como unidades de cogeneracion

    Energy Technology Data Exchange (ETDEWEB)

    Buendia Dominguez, E. H. [Instituto de Investigaciones Electricas, Cuernavaca (Mexico); Merlos Rueda, R. M. [Programa de Ahorro de Energia para el Sector Electrico, Mexico, D. F. (Mexico)

    1995-12-31

    The Programa de Ahorro de Energia para el Sector Electrico (PAESE) (Program for Energy Conservation for the Electric Sector) in collaboration with the Instituto de Investigaciones Electricas (IIE), decided to evaluate technically and economically the possibilities of operating the Comision Federal de Electricidad`s Thermoelectric Power Stations (TPS), eventually to be retired as cogeneration units in supplying thermal energy to industry. The study was focussed to the Monterrey and San Jeronimo Power Stations, determining in a first stage, the optimum radius for handling and transporting steam and/or hot water and so to define the industries that potentially could obtain heat energy from the TPS, in this stage the thermal needs of the evaluated industries were determined (pressure, temperature and flow). In a second stage, the different arrangements to be made to operate the selected TPS, so as to be in position of satisfying such thermal energy demands were evaluated. This paper presents the results of this study. [Espanol] El Programa de Ahorro de Energia para el Sector Electrico (PAESE), en colaboracion con el Instituto de Investigaciones Electricas, decidieron evaluar tecnica y economicamente las posibilidades de operar las centrales termoelectricas (CT`s) de la Comision Federal de Electricidad, eventualmente retirables, como unidades de cogeneracion al ofrecer calor a la industria. El estudio se enfoco en las centrales de Monterrey y San Jeronimo, determinado en una primera etapa el radio optimo para el manejo y transporte de vapor y/o agua caliente y asi definir a las industrias que potencialmente podrian recibir calor de las CT`s, en esta etapa se determinaron las necesidades termicas de las industrias evaluadas (presion, temperatura y flujo). En una segunda etapa se evaluo los diferentes arreglos para operar las CT`s seleccionadas para que pudieran satisfacer dichas demandas termicas. En este trabajo se presentaron los resultados de dicho estudio.

  3. 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...

  4. Torness: proposed nuclear power station

    International Nuclear Information System (INIS)

    Anon.

    1979-01-01

    The need for and desirability of nuclear power, and in particular the proposed nuclear power station at Torness in Scotland, are questioned. Questions are asked, and answered, on the following topics: position, appearance and cost of the proposed Torness plant, and whether necessary; present availability of electricity, and forecast of future needs, in Scotland; energy conservation and alternative energy sources; radiation hazards from nuclear power stations (outside, inside, and in case of an accident); transport of spent fuel from Torness to Windscale; radioactive waste management; possibility of terrorists making a bomb with radioactive fuel from a nuclear power station; cost of electricity from nuclear power; how to stop Torness. (U.K.)

  5. Space station neutral external environment

    Science.gov (United States)

    Ehlers, H.; Leger, L.

    1988-01-01

    Molecular contamination levels arising from the external induced neutral environment of the Space Station (Phase 1 configuration) were calculated using the MOLFLUX model. Predicted molecular column densities and deposition rates generally meet the Space Station contamination requirements. In the doubtful cases of deposition due to materials outgassing, proper material selection, generally excluding organic products exposed to the external environment, must be considered to meet contamination requirements. It is important that the Space Station configuration, once defined, is not significantly modified to avoid introducing new unacceptable contamination sources.

  6. Portable power stations

    Science.gov (United States)

    Butler, D.

    1994-02-01

    A description is given of a novel portable power system that is suitable for isolated users of electricity. The unit comprises: (1) a bi-directional, self-paralleling, microprocessor-controlled inverter; (2) a set of gelled-electrolyte, valve-regulated lead/acid batteries; (3) a fuel tank and diesel-generator set; (4) a weatherproof enclosure; (5) renewable energy component(s). The key component is the `smart' inverter that starts and stops the generator automatically and performs float- and boost-charging functions. The system strategy is to store the energy in fuel or in a renewable resource. With this approach, the battery is used only as a source of short-term peaking power and for the low-energy demands of the load curve. This allows maximum utilization of the battery component.

  7. Southern Research Station Global Change Research Strategy 2011-2019

    Science.gov (United States)

    Kier Klepzig; Zoe Hoyle; Stevin Westcott; Emrys Treasure

    2012-01-01

    In keeping with the goals of the Research and Development agenda of the Forest Service, U.S. Department of Agriculture (USDA), the Southern Research Station (SRS) provides the information and technology needed to develop best management practices for the forest lands of the Southern United States, where science-guided actions are needed to sustain ecosystem health,...

  8. Modeling of Space Station electric power system with EMTP

    Science.gov (United States)

    Tam, Kwa-Sur; Yang, Lifeng; Dravid, Narayan V.

    1990-01-01

    The authors provide an introduction to using the electromagnetic transients (EMTP) program to model aerospace power system components. A brief general overview of EMTP is presented. The modeling of the dc/dc converter unit in the space station electric power system is described as an illustration.

  9. 49 CFR 192.171 - Compressor stations: Additional safety equipment.

    Science.gov (United States)

    2010-10-01

    ..., other than an electrical induction or synchronous motor, must have an automatic device to shut down the... event of inadequate cooling or lubrication of the unit. (d) Each compressor station gas engine that operates with pressure gas injection must be equipped so that stoppage of the engine automatically shuts...

  10. WVU Hydrogen Fuel Dispensing Station

    Energy Technology Data Exchange (ETDEWEB)

    Davis, William [West Virginia University Research Corporation, Morgantown, WV (United States)

    2015-09-01

    The scope of this project was changed during the course of the project. Phase I of the project was to construct a site similar to the site at Central West Virginia Regional Airport in Charleston, WV to show that duplication of the site was a feasible method of conducting hydrogen stations. Phase II of the project was necessitated due to a lack of funding that was planned for the development of the station in Morgantown. The US Department of Energy determined that the station in Charleston would be dismantled and moved to Morgantown and reassembled at the Morgantown site. This necessitated storage of the components of the station for almost a year at the NAFTC Headquarters which caused a number of issues with the equipment that will be discussed in later portions of this report. This report will consist of PHASE I and PHASE II with discussions on each of the tasks scheduled for each phase of the project.

  11. VT Data - Electric Charging Stations

    Data.gov (United States)

    Vermont Center for Geographic Information — Locations of Electric Charging Stations provided by the NREL national laboratory of the U.S. Department of Energy, Office of Energy Efficiency and Renewable Energy....

  12. Services for nuclear power stations

    International Nuclear Information System (INIS)

    Fremann, M.; Ryckelynck

    1987-01-01

    This article gives an information as complete as possible about the activities of the french nuclear industry on the export-market. It describes the equipment and services available in the field of services for nuclear power stations [fr

  13. Gravity Station Data for Portugal

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — The gravity station data total 3064 records. This data base was received in April 1997. Principal gravity parameters include Free-air Anomalies which have been...

  14. Gravity Station Data for Spain

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — The gravity station data total 28493 records. This data base was received in April 1997. Principal gravity parameters include Free-air Anomalies which have been...

  15. Space Station Human Factors Research Review. Volume 3: Space Station Habitability and Function: Architectural Research

    Science.gov (United States)

    Cohen, Marc M. (Editor); Eichold, Alice (Editor); Heers, Susan (Editor)

    1987-01-01

    Articles are presented on a space station architectural elements model study, space station group activities habitability module study, full-scale architectural simulation techniques for space stations, and social factors in space station interiors.

  16. Space Station Freedom power - A reliability, availability, and maintainability assessment of the proposed Space Station Freedom electric power system

    Science.gov (United States)

    Turnquist, S. R.; Twombly, M.; Hoffman, D.

    1989-01-01

    A preliminary reliability, availability, and maintainability (RAM) analysis of the proposed Space Station Freedom electric power system (EPS) was performed using the unit reliability, availability, and maintainability (UNIRAM) analysis methodology. Orbital replacement units (ORUs) having the most significant impact on EPS availability measures were identified. Also, the sensitivity of the EPS to variations in ORU RAM data was evaluated for each ORU. Estimates were made of average EPS power output levels and availability of power to the core area of the space station. The results of assessments of the availability of EPS power and power to load distribution points in the space stations are given. Some highlights of continuing studies being performed to understand EPS availability considerations are presented.

  17. Space stations systems and utilization

    CERN Document Server

    Messerschmid, Ernst

    1999-01-01

    The design of space stations like the recently launched ISS is a highly complex and interdisciplinary task. This book describes component technologies, system integration, and the potential usage of space stations in general and of the ISS in particular. It so adresses students and engineers in space technology. Ernst Messerschmid holds the chair of space systems at the University of Stuttgart and was one of the first German astronauts.

  18. Internationalization of the Space Station

    Science.gov (United States)

    Lottmann, R. V.

    1985-01-01

    Attention is given to the NASA Space Station system elements whose production is under consideration by potential foreign partners. The ESA's Columbus Program declaration encompasses studies of pressurized modules, unmanned payload carriers, and ground support facilities. Canada has expressed interest in construction and servicing facilities, solar arrays, and remote sensing facilities. Japanese studies concern a multipurpose experimental module concept. Each of these foreign investments would expand Space Station capabilities and lay the groundwork for long term partnerships.

  19. 46 CFR 28.395 - Embarkation stations.

    Science.gov (United States)

    2010-10-01

    ... COAST GUARD, DEPARTMENT OF HOMELAND SECURITY UNINSPECTED VESSELS REQUIREMENTS FOR COMMERCIAL FISHING... least one designated survival craft embarkation station and any additional embarkation stations.... Each embarkation station must be arranged to allow the safe boarding of survival craft. ...

  20. Non-Coop Station History (Unindexed)

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — Station history documentation for stations outside the US Cooperative Observer network. Documents should be compared with those in the Non-Coop Station History...

  1. Advances in power station construction

    International Nuclear Information System (INIS)

    Anon.

    1986-01-01

    This book is about power stations - specifically about the construction of modern power stations by the Central Electricity Generating Board in England and Wales over the past decade. It describes the work of the CEGB's Generation Development and Construction Division, perhaps better known throughout the world as simply 'Barnwood' where it has its Headquarters in Gloucester, UK. Barnwood was formed in the early 1970s to concentrate the CEGB's then dispersed engineering construction resources to cope with the smaller number but greatly increased size and complexity of modern power station projects. Perhaps uniquely over the ten years since its formation Barnwood has managed the construction of all types of station; coal-fired, oil-fired, nuclear, pumped storage and hydro. This book tells the story of these various projects and gives detailed descriptions of the respective stations. However, it is not intended as a comprehensive description of power station technology. Rather it is intended to convey the scale of such projects and the many decisions and compromises which have to be made in the course of managing their construction

  2. 47 CFR 73.6016 - Digital Class A TV station protection of TV broadcast 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 TV... Class A TV station protection of TV broadcast stations. Digital Class A TV stations must protect authorized TV broadcast stations, applications for minor changes in authorized TV broadcast stations filed on...

  3. Refurbishment of Point Lepreau Generating Station

    International Nuclear Information System (INIS)

    Thompson, P.D.; Jaitly, R.; Ichiyen, N.; Petrilli, M.A.

    2004-01-01

    NB Power is planning to conduct an 18-month maintenance outage of the Point Lepreau Generating Station (PLGS) beginning in April 2008. The major activity would be the replacement of all 380 Fuel Channel and Calandria Tube Assemblies and the connecting feeder pipes. This activity is referred to as Retube. NB Power would also take advantage of this outage to conduct a number of repairs, replacements, inspections and upgrades (such as rewinding or replacing the generator, replacement of shutdown system trip computers, replacement of certain valves and expansion joints, inspection of systems not normally accessible, etc). These collective activities are referred to as Refurbishment. This would allow the station to operate for an additional 25 to 30 years. The scope of the project was determined from the outcome of a two-year study involving a detailed condition assessment of the station that examined issues relating to ageing and obsolescence. The majority of the plant components were found to be capable of supporting extended operation without needing replacement or changes. In addition to the condition assessment, a detailed review of Safety and Licensing issues associated with extended operation was performed. This included a review of known regulatory and safety issues, comparison of the station against current codes and standards, and comparison of the station against safety related modifications made to more recent CANDU 6 units. Benefit cost analyses (BCA) were performed to assist the utility in determining which changes were appropriate to include in the project scope. As a Probabilistic Safety Assessment (PSA) for PLGS did not exist at the time, a risk baseline for the station had to be determined for use in the BCA. Extensive dialogue with the Canadian Nuclear Safety Commission staff was also undertaken during this phase. A comprehensive Licensing Framework was produced upon which the CNSC provided feedback to NB Power. This feedback was important in terms of

  4. The international space station: A pathway to the future

    Science.gov (United States)

    Kitmacher, Gary H.; Gerstenmaier, William H.; Bartoe, John-David F.; Mustachio, Nicholas

    2005-07-01

    Nearly six years after the launch of the first International Space Station element, and four years after its initial occupation, the United States and our 6 international partners have made great strides in operating this impressive Earth orbiting research facility. This past year we have done so in the face of the adversity of operating without the benefit of the Space Shuttle. In his January 14, 2004, speech announcing a new vision for America's space program, President Bush affirmed the United States' commitment to completing construction of the International Space Station by 2010. The President also stated that we would focus our future research aboard the Station on the long-term effects of space travel on human biology. This research will help enable human crews to venture through the vast voids of space for months at a time. In addition, ISS affords a unique opportunity to serve as an engineering test bed for hardware and operations critical to the exploration tasks. NASA looks forward to working with our partners on International Space Station research that will help open up new pathways for future exploration and discovery beyond low Earth orbit. This paper provides an overview of the International Space Station Program focusing on a review of the events of the past year, as well as plans for next year and the future.

  5. Pumped energy transfer stations (STEP)

    International Nuclear Information System (INIS)

    Tournery, Jean-Francois

    2015-12-01

    As objectives of development are high for renewable energies (they are supposed to cover 50 per cent of new energy needs by 2035), pumped energy transfer stations are to play an important role in this respect. The author first discusses the consequences of the development of renewable energies on the exploitation of electric grids: issue of intermittency for some of them, envisaged solutions. Then, he addresses one of the solutions: the storage of electric power. He notices that increasing the potential energy of a volume of water is presently the most mature solution to face massive needs of the power system. Dams and pumped energy transfer stations represent now almost the whole installed storage power in the world. The author then presents these pumped energy transfer stations: principle, brief history (the first appeared in Italy and Switzerland at the end of the 1890's). He indicates the various parameters of assessment of such stations: maximum stored energy, installed power in pumping mode and turbine mode, time constant, efficiency, level of flexibility. He discusses economic issues. He describes and comments the operation of turbine-pump groups: ternary groups, reversible binary groups. He discusses barriers to be overcome and technical advances to be made for varying speed groups and for marine stations. He finally gives an overview (table with number of stations belonging to different power ranges, remarkable installations) of existing stations in China, USA, Japan, Germany, Austria, Spain, Portugal, Italy, Switzerland, France and UK, and indicate predictions regarding storage needs at the world level. Some data are finally indicated for the six existing French installations

  6. 75 FR 76498 - Firstenergy Nuclear Operating Company, Davis-Besse Nuclear Power Station; Environmental...

    Science.gov (United States)

    2010-12-08

    ... Company, Davis-Besse Nuclear Power Station; Environmental Assessment And Finding of No Significant Impact... operation of the Davis-Besse Nuclear Power Station, Unit 1 (DBNPS), located in Ottawa County, Ohio. In... the reactor coolant pressure boundary of light-water nuclear power reactors provide adequate margins...

  7. 75 FR 16523 - FirstEnergy Nuclear Operating Company; Davis-Besse Nuclear Power Station; Exemption

    Science.gov (United States)

    2010-04-01

    ... Company; Davis-Besse Nuclear Power Station; Exemption 1.0 Background FirstEnergy Nuclear Operating Company... of the Davis-Besse Nuclear Power Station, Unit 1 (DBNPS). The license provides, among other things... physical protection of licensed activities in nuclear power reactors against radiological sabotage...

  8. 75 FR 80549 - FirstEnergy Nuclear Operating Company, Davis-Besse Nuclear Power Station; Exemption

    Science.gov (United States)

    2010-12-22

    ... Company, Davis-Besse Nuclear Power Station; Exemption 1.0 Background FirstEnergy Nuclear Operating Company... of the Davis-Besse Nuclear Power Station, Unit 1 (DBNPS). The license provides, among other things... pressure-retaining components of the reactor coolant pressure boundary of light-water nuclear power...

  9. Optimization of the overall energy consumption in cascade fueling stations for hydrogen vehicles

    DEFF Research Database (Denmark)

    Rothuizen, Erasmus Damgaard; Rokni, Masoud

    2014-01-01

    Hydrogen fueling stations are emerging around and in larger cities in Europe and United States together with a number of hydrogen vehicles. The most stations comply with the refueling protocol made by society of automotive engineers and they use a cascade fueling system on-site for filling...

  10. System for a displaying at a remote station data generated at a central station and for powering the remote station from the central station

    Science.gov (United States)

    Perry, J. C. (Inventor)

    1980-01-01

    A system for displaying at a remote station data generated at a central station and for powering the remote station from the central station is presented. A power signal is generated at the central station and time multiplexed with the data and then transmitted to the remote station. An energy storage device at the remote station is responsive to the transmitted power signal to provide energizing power for the circuits at the remote station during the time interval data is being transmitted to the remote station. Energizing power for the circuits at the remote station is provided by the power signal itself during the time this signal is transmitted. Preferably the energy storage device is a capacitor which is charged by the power signal during the time the power is transmitted and is slightly discharged during the time the data is transmitted to energize the circuits at the remote station.

  11. Destination Station: Bringing The International Space Station to Communities Across the United States

    Science.gov (United States)

    Edgington, Susan

    2014-01-01

    Today, space is no longer just a field of advanced technological development and of scientific research of excellence, but has become an essential asset for everyday life. Space has spurred countless scientific and technological achievements which are commonly used in aeronautics, medicine, material science and production, in information and communications technology. In parallel, more and more services are carried out through the use of space applications, ranging from detection of natural disasters and environmental monitoring to global navigation and telecommunication. Using space missions to build a better understanding of the universe fulfills our centuries-old curiosity and leads humanity into the future, opening up new frontiers of knowledge. The International Astronautical Congresses have always represented an arena in which issues have been discussed with friendship and among experts: scientists, technicians and managers from universities, agencies, research centres and industry. At the same time it introduces students and young professionals to the field.

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

    International Nuclear Information System (INIS)

    1987-01-01

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

  13. 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

  14. 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

  15. Fort Calhoun Station, Unit 2. License application, PSAR, general information

    International Nuclear Information System (INIS)

    1975-09-01

    Application for construction and operating licenses for Calhoun-2 Reactor is presented. Financial data concerning the Omaha Public Power District and the Nebraska Public Power District are included. (DCC)

  16. 77 FR 76542 - Millstone Power Station, Unit 2; Exemption

    Science.gov (United States)

    2012-12-28

    ... Notice (IN) 92-18, ``Potential for Loss of Remote Shutdown Capability During a Control Room Fire... could be fire affected, however, it is an (air operated valve (AOV) that fails closed on loss of IA or... there is a minimal amount of Class A combustibles in this area, there is little chance of a fire...

  17. Millstone Nuclear Power Station, Unit 2. 1976 annual operating report

    International Nuclear Information System (INIS)

    1977-01-01

    Power ascension testing continued from the first of the year to May 8, 1976, with 100 percent power achieved for the first time on March 18. Information is presented concerning safety related maintenance, outages, procedure and design changes, tests other than start-up tests, and radiation exposures

  18. 77 FR 43382 - Millstone Power Station, Unit 2; Exemption

    Science.gov (United States)

    2012-07-24

    ... Proprietary Protective Signaling Systems for Watchman, Fire Alarm and Supervisory Service,'' and the 1978 and... system, which alarms at the main fire alarm panel in the CR. The licensee further stated that a fire in... (FHA Fire Zone A-1 B). The licensee also stated that actuation of this system results in an alarm...

  19. US central station nuclear electric generating units: significant milestones

    International Nuclear Information System (INIS)

    1979-09-01

    Listings of US nuclear power plants include significant dates, reactor type, owners, and net generating capacity. Listings are made by state, region, and utility. Tabulations of status, schedules, and orders are also presented

  20. Design of photovoltaic central power station concentrator array

    Energy Technology Data Exchange (ETDEWEB)

    1984-02-01

    A design for a photovoltaic central power station using tracking concentrators has been developed. The 100 MW plant is assumed to be located adjacent to the Saguaro Power Station of Arizona Public Service. The design assumes an advanced Martin Marietta two-axis tracking fresnel lens concentrator. The concentrators are arrayed in 5 MW subfields, each with its own power conditioning unit. The photovoltaic plant output is connected to the existing 115 kV switchyard. The site specific design allows detailed cost estimates for engineering, site preparation, and installation. Collector and power conditioning costs have been treated parametrically.