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Sample records for mile point unit

  1. Transformer failure and common-mode loss of instrument power at Nine Mile Point Unit 2 on August 13, 1991

    Energy Technology Data Exchange (ETDEWEB)

    1991-10-01

    On August 13, 1991, at Nine Mile Point Unit 2 nuclear power plant, located near Scriba, New York, on Lake Ontario, the main transformer experienced an internal failure that resulted in degraded voltage which caused the simultaneous loss of five uninterruptible power supplies, which in turn caused the loss of several nonsafety systems, including reactor control rod position indication, some reactor power and water indication, control room annunciators, the plant communications system, the plant process computer, and lighting at some locations. The reactor was subsequently brought to a safe shutdown. Following this event, the US Nuclear Regulatory Commission dispatched an Incident Investigation Team to the site to determine what happened, to identify the probable causes, and to make appropriate findings and conclusions. This report describes the incident, the methodology used by the team in its investigation, and presents and the team's findings and conclusions. 59 figs., 14 tabs.

  2. Transformer failure and common-mode loss of instrument power at Nine Mile Point Unit 2 on August 13, 1991

    International Nuclear Information System (INIS)

    1991-10-01

    On August 13, 1991, at Nine Mile Point Unit 2 nuclear power plant, located near Scriba, New York, on Lake Ontario, the main transformer experienced an internal failure that resulted in degraded voltage which caused the simultaneous loss of five uninterruptible power supplies, which in turn caused the loss of several nonsafety systems, including reactor control rod position indication, some reactor power and water indication, control room annunciators, the plant communications system, the plant process computer, and lighting at some locations. The reactor was subsequently brought to a safe shutdown. Following this event, the US Nuclear Regulatory Commission dispatched an Incident Investigation Team to the site to determine what happened, to identify the probable causes, and to make appropriate findings and conclusions. This report describes the incident, the methodology used by the team in its investigation, and presents and the team's findings and conclusions. 59 figs., 14 tabs

  3. VT Mile Points - 1/10-Mile Intervals

    Data.gov (United States)

    Vermont Center for Geographic Information — The mile points data layer is comprised of discrete locations based on specific measured intervals along a route. These intervals are represented along a...

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

    International Nuclear Information System (INIS)

    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

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

    International Nuclear Information System (INIS)

    1985-06-01

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

  6. 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

  7. Technical evaluation report on the monitoring of electric power to the reactor protection system for the Nine Mile Point Nuclear Station, Unit 1 (Docket No. 50-220)

    International Nuclear Information System (INIS)

    Selan, J.C.

    1984-01-01

    This report documents the technical evaluation of the monitoring of electric power to the reactor protection system (RPS) at the Nine Mile Point Nuclear Station, Unit 1. The evaluation is to determine if the proposed design modification will protect the RPS from abnormal voltage and frequency conditions which could be supplied from the power supplies and will meet certain requirements set forth by the Nuclear Regulatory Commission. The proposed design modifications will protect the RPS from sustained abnormal voltage and frequency conditions from the supplying sources

  8. 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

  9. Safety Evaluation Report related to the operation of Nine Mile Point Nuclear Station, Unit No. 2 (Docket No. 50-410). Supplement No. 5

    International Nuclear Information System (INIS)

    1986-10-01

    This report supplements the Safety Evaluation Report (NUREG-1047, February 1985) for the application filed by Niagara Mohawk Power Corporation, as applicant and co-owner, for a license to operate Nine Mile Point Nuclear Station, Unit 2 (Docket No. 50-410). It has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located near Oswego, New York. Supplement 1 to the Safety Evaluation Report was published in June 1985 and contained the report from the Advisory Committee on Reactor Safeguards as well as the resolution of a number of outstanding issues from the Safety Evaluation Report. Supplement 2 was published in November 1985 and contained the resolution of a number of outstanding and confirmatory issues. Supplement 3 was published in July 1986 and contained the resolution of a number of outstanding and confirmatory items, one new confirmatory item, the evaluation of the Engineering Assurance Program, and the evaluation of a number of exemption requests. Supplement 4 was published in September 1986 and contained the resolution of a number of outstanding and confirmatory issues and the evaluation of a number of exemption requests. This report contains the resolution of a number of issues that have been resolved since Supplement 4 was issued. It also contains the evaluation of a number of requests for exemption from the applicant. This report also supports the issuance of the low-power license for Nine Mile Point Nuclear Station, Unit 2

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

    International Nuclear Information System (INIS)

    1986-07-01

    This report supplements the Safety Evaluation Report (NUREG-1047, February 1985) for the application filed by Niagara Mohawk Power Corporation, as applicant and co-owner, for a license to operate the Nine Mile Point Nuclear Station, Unit No. 2 (Docket No. 50-410). It has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located near Oswego, New York. Supplement 1 to the Safety Evaluation Report was published in June 1985 and contained the report from the Advisory Committee on Reactor Safeguards as well as the resolution to a number of outstanding issues from the Safety Evaluation Report. Supplement 2 was published in November 1985 and contained the resolution to a number of outstanding and confirmatory issues. Subject to favorable resolution of the issues discussed in this report, the NRC staff concludes that the facility can be operated by the applicant without endangering the health and safety of the public

  11. Operation of Nine Mile Point Nuclear Station, Unit No. 2, Docket No. 50-410, Town of Scriba, County of Oswego, New York

    International Nuclear Information System (INIS)

    1984-07-01

    The draft version of an environmental impact statement (EPA No. 840360D) on the proposed licensing of Unit 2 of the Nine Mile Point Nuclear Station in New York describe the plant site, the reactor and support facilities, the cooling system, and procedures for disposing of cooling tower sludge. Construction includes a substation and a new 345kV transmission line that would use an existing right-of-way. Positive impacts include the annual generation of 5.2 billion kWh of baseload capacity and improvements in the state power pool's bulk supply system. The $18 million payroll of 635 workers would benefit the local economy. Negative impacts would be the loss of forest brush land, slight degradation of ambient water quality, and a minor depression of ground water. There would likely be some loss of fish population. The Federal Water Pollution Control Act of 1972 and Nuclear Regulatory Commission Licensing require the impact statement

  12. 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

  13. Nuclear accidents. Three mile Island (United States)

    International Nuclear Information System (INIS)

    Duco, J.

    2004-01-01

    This paper describes the accident of Three Miles Island power plant which occurred the 28 march 1979 in the United States. The accident scenario, the consequences and the reactor core and vessel, after the accident, are analyzed. (A.L.B.)

  14. Experience of the Surveyor Mobile robot at Nine Mile Point

    International Nuclear Information System (INIS)

    Kniazewycz, B.G.; Irving, T.L.

    1987-01-01

    A successful test and evaluation program was recently conducted on a commercial-ready, wireless, remotely operated surveillance system for use in nuclear power plants. This evaluation of the Surveyor Mobile Surveillance System took place at Niagara Mohawk Power Corporation's (NMPC) Nine Mile Point (NMP) Nuclear Power Station. The remotely operated vehicles measures radiation, temperature and relative humidity and provides optical inspection capability. The vehicle is readily maneuvered through 36 inch wide passageways and labyrinth entries and can climb stairs, negotiating 180 degree turns on stair landings. The Surveyor systems consists of a Supervisory Control Station and a rugged, remotely operated, battery-powered vehicle. The Surveyor system is specifically designed to decrease personnel radiation exposure by supplementing the functions of an auxiliary operator or Health Physics Technician to perform periodic component inspections inside particular areas within a nuclear power plant. The purpose of this presentation is to describe the recent efforts, achievements and experiences of the personnel at NMP Unit 1. In particular, this will address the test and evaluation program for the Surveyor Mobile Surveillance Robot

  15. Three Mile Island Unit-2 events of 28 March 1979

    Energy Technology Data Exchange (ETDEWEB)

    Syed Hussin Shabuddin, Syed Nahar [PUSPATI, Selangor (Malaysia)

    1984-12-01

    Three Mile Island was the most severe accident at a commercial nuclear power plant in the United States. This paper attempts to give in detail and chronological order the technical events that happened on the day of the accident. Operator response to plant conditions and its consequences are explained.

  16. 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...

  17. 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...

  18. 78 FR 49553 - Three Mile Island, Unit 2; Post Shutdown Decommissioning Activities Report

    Science.gov (United States)

    2013-08-14

    ... NUCLEAR REGULATORY COMMISSION [Docket No. 50-320; NRC-2013-0183] Three Mile Island, Unit 2; Post Shutdown Decommissioning Activities Report AGENCY: Nuclear Regulatory Commission. ACTION: Notice of receipt... Shutdown Decommissioning Activity Report (PSDAR) for Three Mile Island, Unit 2 (TMI-2). The PSDAR provides...

  19. Analysis of Three Mile Island-Unit 2 accident

    International Nuclear Information System (INIS)

    1980-03-01

    The Nuclear Safety Analysis Center (NSAC) of the Electric Power Research Institute has analyzed the Three Mile Island-2 accident. Early results of this analysis were a brief narrative summary, issued in mid-May 1979 and an initial version of this report issued later in 1979 as noted in the Foreword. The present report is a revised version of the 1979 report, containing summaries, a highly detailed sequence of events, a comparison of that sequence of events with those from other sources, 25 appendices, references and a list of abbreviations and acronyms. A matrix of equipment and system actions is included as a folded insert

  20. TMI-2 [Three Mile Island Unit 2] licensing history

    International Nuclear Information System (INIS)

    Byrne, J.J.

    1988-01-01

    Three Mile Island (TMI), which is located in central Pennsylvania near Harrisburg, is the site of the TMI-2 accident, the most significant nuclear accident in US commercial nuclear power. Since the accident on March 28, 1979, TMI-2 has been undergoing cleanup activities designed to place the plant in a safe, stable, and secure postaccident configuration. At the completion of the cleanup program, TMI-2 will be placed in such a configuration, termed postdefueling monitored storage (PDMS), by the licensee, GPU Nuclear Corporation. The purpose of this paper is to provide a brief overview of the TMI-2 licensing history and to describe its impact on the regulatory process

  1. Analysis of Three Mile Island - Unit 2 accident

    International Nuclear Information System (INIS)

    1979-07-01

    The Nuclear Safety Analysis Center (NSAC) of the Electric Power Research Institute is analyzing the Three Mile Island-2 accident. An early result of this analysis was a brief narrative summary, issued in mid May 1979. The present report contains a revised version of that narrative summary, a highly detailed sequence of events, a standard reference list, a list of abbreviations and acronyms, and several appendices. The appendices serve either to describe plant features which are pertinent to the understanding of the sequence of events, or indicate how certain inferences and conclusions in the report were reached. Supplementing the appendices contained herein, additional appendices are in preparation; these will be issued when available (e.g., the appendices Hydrogen Phenomena and Operator Actions during Initial Transient will follow later). Also in preparation is a matrix of equipment and systems actions during the accident. This report together with future supplements and a separate Core Damage Assessment report, will embody the principal results of that phase of NSAC work which is devoted to learning and understanding what happened during the accident. Subsequent phases will concentrate on causes, lessons learned and generic remedial or preventive measures which may be appropriate

  2. Analysis of Three Mile Island-Unit 2 accident

    International Nuclear Information System (INIS)

    1979-07-01

    The Nuclear Safety Analysis Center (NSAC) of the Electic Power Research Institute is analyzing the Three Mile Island-2 accident. An early result of this analysis was a brief narrative summary, issued in mid-May 1979. The present report contains a revised version of that narrative summary, a highly detailed sequence of events, a standard reference list, a list of abbreviations and acronyms, and several appendices. The appendices serve either to describe plant features which are pertinent to the understanding of the sequence of events, or indicate how certain inferences and conclusions in the report were reached. Supplementing the appendices contained herein, additional appendices are in preparation; these will be issued when available (e.g., the appendices Hydrogen Phenomena and Operator Actions duing Initial Transient will follow later). Also in preparation is a matrix of equipment and systems actions during the accident. This report together with future supplements and a separate Core Damage Assessment report, will embody the principal results of that phase of NSAC's work which is devoted to learning and understanding what happened during the accident. Subsequent phases will concentrate on causes, lessons learned and generic remedial or preventive measures which may be appropriate

  3. Post-accident TMI-2 (Three Mile Island-Unit 2) decontamination and defueling

    International Nuclear Information System (INIS)

    Hofstetter, K.J.; Baston, V.F.

    1986-01-01

    Following the accident at Three Mile Island-Unit 2 (TMI-2), a substantial quantity of fission products was distributed throughout various plant systems and areas. The control of further migration of these radionuclides was accomplished by various physical and chemical means. The decontamination and defueling activities have proceeded within specific regulatory, administrative, and hardware restrictions. A summary of the post-accident status of the plant systems, the decontamination methods used, and the end-point criteria will be discussed. The hardware installed or utilized to perform the cleanup operations will be described. The methods and progress of defueling will also be presented. The development of detailed water chemistry requirements and their effects on systems and decontamination efforts are discussed. The planning, scheduling, and performance of specific recovery tasks are presented along with a general overview of water and chemical management at TMI-2

  4. Socio-economic impacts of nuclear generating stations: Nine Mile Point and Fitzpatrick case study

    International Nuclear Information System (INIS)

    Branch, K.; Cochran, R.; Meale, R.

    1982-07-01

    This report documents a case study of the socio-economic impacts of the construction and operation of the Nine Mile Point and Fitzpatrick nuclear power stations. 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 the 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

  5. Answers to frequently asked questions about cleanup activities at Three Mile Island, Unit 2. Public information report

    International Nuclear Information System (INIS)

    1980-09-01

    The document presents answers to frequently asked questions about plans for cleanup and decontamination activities at Three Mile Island, Unit 2. Answers to the questions asked are based on information in the NRC 'Draft 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

  6. Summary Report of Commercial reactor Criticality Data for Three Mile Island Unit 1

    International Nuclear Information System (INIS)

    Larry B. Wimmer

    2001-01-01

    The objective of the ''Summary Report of Commercial Reactor Criticality Data for Three Mile Island Unit I'' is to present the CRC data for the TMI-1 reactor. Results from the CRC evaluations will support the development and validation of the neutronics models used for criticality analyses involving commercial spent nuclear fuel. These models and their validation are discussed in the ''Disposal Criticality Analysis Methodology Topical Report'' (YMP 2000)

  7. Nondestructive techniques for assaying fuel debris in piping at Three Mile Island Unit 2

    International Nuclear Information System (INIS)

    Vinjamuri, K.; McIsaac, C.V.; Beller, L.S.; Isaacson, L.; Mandler, J.W.; Hobbins, R.R. Jr.

    1981-11-01

    Four major categories of nondestructive techniques - ultrasonic, passive gamma ray, infrared detection, and remote video examination - have been determined to be feasible for assaying fuel debris in the primary coolant system of the Three Mile Island Unit 2 (TMI-2) Reactor. Passive gamma ray detection is the most suitable technique for the TMI-2 piping; however, further development of this technique is needed for specific application to TMI-2

  8. Answers to questions about updated estimates of occupational radiation doses at Three Mile Island, Unit 2

    International Nuclear Information System (INIS)

    1983-12-01

    The purpose of this question and answer report is to provide a clear, easy-to-understand explanation of revised radiation dose estimates which workers are likely to receive over the course of the cleanup at Three Mile Island, Unit 2, and of the possible health consequences to workers of these new estimates. We will focus primarily on occupational dose, although pertinent questions about public health and safety will also be answered

  9. Examinations of fuel debris samples from Three Mile Island Unit 2

    International Nuclear Information System (INIS)

    Nagase, Fumihisa

    2012-01-01

    In the accident at the Fukushima-Daiichi nuclear power plants, fuels were molten due to loss of coolant and heat-up of the reactor core. Information on properties of molten fuels (debris) is important to analyze progress of the accident, estimate the status inside the damaged reactors and work on a plan for debris removal. Extensive examinations for properties of debris have been conducted after the accident at the Three Mile Island Unit 2 in 1979. The Japan Atomic Energy Agency conducted a part of the examinations in the frame of the OECD/NEA Three Mile Island Vessel Investigation Program. This issue report outline and main results of the TMI-2 debris examination programs. (author)

  10. Instrumentation and electrical program at the Three Mile Island Unit 2, Technical Integration Office

    International Nuclear Information System (INIS)

    Hecker, L.A.

    1982-01-01

    The Three Mile Island Unit 2 accident of March 28, 1979 presents unique research opportunities that can provide valuable information on nuclear power plant safety philosophy and safety systems performance. The Technical Integration Office at Three Mile Island was established by the Department of Energy to manage a broad-based research and development program. One significant part of this effort is the Instrumentation and Electrical Program, which operates: (1) to identify instruments and electrical components that failed during or since the accident; (2) to test and analyze them in order to identify the causes of failure; and (3) to assess the survivability of those that did not fail. The basis for selection of equipment is discussed, and the testing methodology is described. Also, some results of Instrumentation and Electrical Program work to date are presented

  11. 76 FR 39910 - Nine Mile Point Nuclear Station, LLC; Nine Mile Point Nuclear Station, Unit Nos. 1 and 2; Notice...

    Science.gov (United States)

    2011-07-07

    ... hearing and intervention via electronic submission through the NRC E-filing system. Requests for a hearing... accordance with the NRC E-Filing rule (72 FR 49139, August 28, 2007). The E-Filing process requires... requirements of E-Filing, at least ten (10) days prior to the filing deadline, the [[Page 39912

  12. 75 FR 17970 - Nine Mile Point Nuclear Station, LLC; Nine Mile Point Nuclear Station, Unit No. 2; Draft...

    Science.gov (United States)

    2010-04-08

    ... waste streams include filter sludge, spent ion exchange resin, and dry active waste (DAW). DAW includes... filter sludge. The licensee's analysis indicates that the estimated increase in solid radioactive waste... of Transportation of Fuel and Waste to and from One Light-Water-Cooled Nuclear Power Reactor...

  13. 75 FR 13600 - Nine Mile Point Nuclear Station, LLC, Nine Mile Point Nuclear Station, Unit No. 2; Draft...

    Science.gov (United States)

    2010-03-22

    ... waste streams include filter sludge, spent ion exchange resin, and dry active waste (DAW). DAW includes... filter sludge. The licensee's analysis indicates that the estimated increase in solid radioactive waste... Transportation of Fuel and Waste to and from One Light-Water-Cooled Nuclear Power Reactor. Therefore, there would...

  14. 76 FR 73721 - Nine Mile Point Nuclear Station, LLC, Nine Mile Point Nuclear Station, Unit No. 2, Environmental...

    Science.gov (United States)

    2011-11-29

    .... Solid radioactive waste streams include filter sludge, spent ion exchange resin, and dry active waste... Environmental Impact of Transportation of Fuel and Waste to and from One Light-Water-Cooled Nuclear Power... facilities. NMP2 uses a boiling-water reactor and a nuclear steam supply system designed by General Electric...

  15. Quick look report, entry 4: Three Mile Island Unit 2, November 13, 1980

    International Nuclear Information System (INIS)

    Eidam, G.E.

    1981-06-01

    This report summarizes tasks performed during entry 4 at Three Mile Island Unit 2. During the entry into containment, which was made on November 13, 1980, additional beta and gamma surveys were conducted to supplement data acquired on previous entries. A decontamination test was completed on Elevation 305. Power receptables tested on Elevation 305 were deenergized, but receptacles on Elevation 347 were energized. Still photography was acquired of Elevations 305 and 347. During the entry, 86 still photographs were taken. Videotaping (color and black and white) was done on Elevations 305 and 347, but lighting on both elevations was insufficient for high-quality video

  16. Research and development activities on Three Mile Island Unit Two. Annual report for 1985

    International Nuclear Information System (INIS)

    1986-04-01

    The year 1985 was significant in the cleanup of Three Mile Island Unit 2 (TMI-2). Major milestones in the project included lifting the plenum assembly from the reactor vessel and the start of operations to remove the damaged fuel from the reactor. This report summarizes these milestones and other TMI-2 related cleanup, research, and development activities. Other major topics include the following: waste immobilization and management; fuel shipping cask delivery and testing; sample acquisition and evaluation; and decontamination and dose reduction. 26 figs.

  17. Three Mile Island, Unit 2, radiation protection program: report of the special panel

    International Nuclear Information System (INIS)

    Meinhold, C.B.; Murphy, T.D.; Neely, D.R.; Kathren, R.L.; Rich, B.L.; Stone, G.F.; Casey, W.R.

    1979-12-01

    A special panel was appointed by the Director of Nuclear Reactor Regulation, NRC, to review the radiation protection program at Three Mile Island Unit 2. The Panel confirmed several management and technical deficiencies in the program. Recent major GPU/Met Ed commitments and actions demonstrated a major change in management attitude. The Panel concluded that exposures to personnel can be maintained to as low as is reasonably achievable while limited preparatory recovery work continues and when further needed improvements are implemented as needed, the radiation safety program will be able to support major recovery activities

  18. Data integrity review of Three Mile Island Unit 2. Hydrogen burn data. Volume 3

    International Nuclear Information System (INIS)

    Jacoby, J.K.; Nelson, R.A.; Nalezny, C.L.; Averill, R.H.

    1983-09-01

    About 10 hours after the March 28, 1979 loss-of-coolant accident began at Three Mile Island Unit 2 (TMI-2), a hydrogen burn occurred inside the Reactor Building. This report reviews and presents data from 16 channels of resistance temperature detectors (RTDs), 2 steam generator pressure transmitters, 16 Reactor Building pressure switches, 2 channels of Reactor Building pressure measurements, and measurements of Reactor Building hydrogen, oxygen, and nitrogen concentrations with regard to their usefulness for determining the extent of the burn and the resulting pressure and temperature excursions inside the building

  19. NRC plan for cleanup operations at Three Mile Island Unit 2

    International Nuclear Information System (INIS)

    Lo, R.; Snyder, B.J.

    1980-07-01

    The NRC plan defines the functional role of the NRC in cleanup operations at Three Mile Island Unit 2 to assure that agency regulatory responsibilities and objectives will be fulfilled. The plan outlines NRC functions in TMI-2 cleanup operations in the following areas: (1) the functional relationship of NRC to other government agencies, the public, and the licensee to coordinate activities, (2) the functional roles of these organizations in cleanup operations, (3) the NRC review and decision-making procedure for the licensee's proposed cleanup operation, (4) the NRC/licensee estimated schedule of major actions, and (5) NRC's functional role in overseeing implementation of approved licensee activities

  20. Quick look report, Entry 3: Three Mile Island Unit 2, October 16, 1980

    International Nuclear Information System (INIS)

    1981-07-01

    This report summarizes tasks performed during the third entry at Three Mile Island Unit 2. During the entry into containment, which was made on October 16, 1980, additional beta, gamma, and neutron surveys were performed to supplement data obtained on previous entries. In addition, several maintenance tasks were completed including testing the operation of both equipment hatch doors, replacing a loose parts monitor system pre-amplifier, and removing a source range monitor. The five-man entry team accomplished these tasks in about 1-1/2 hours

  1. Three Mile Island, Unit 2, radiation protection program: report of the special panel

    Energy Technology Data Exchange (ETDEWEB)

    Meinhold, C. B. [Brookhaven National Lab., Upton, NY (United States); Murphy, T. D. [Nuclear Regulatory Commission, Washington, DC (United States); Neely, D. R. [Nuclear Regulatory Commission, Washington, DC (United States); Kathren, R. L. [Batelle Pacific Northwest Lab. (United States); Rich, B. L. [Exxon Nuclear Idaho Co., Inc. ID (United States); Stone, G. F. [Tennessee Valley Authority, Chattanooga, TN (United States); Casey, W. R. [Brookhaven National Lab., Upton, NY (United States)

    1979-12-01

    A special panel was appointed by the Director of Nuclear Reactor Regulation, NRC, to review the radiation protection program at Three Mile Island Unit 2. The Panel confirmed several management and technical deficiencies in the program. Recent major GPU/Met Ed commitments and actions demonstrated a major change in management attitude. The Panel concluded that exposures to personnel can be maintained to as low as is reasonably achievable while limited preparatory recovery work continues and when further needed improvements are implemented as needed, the radiation safety program will be able to support major recovery activities.

  2. Detailed flow analysis for the Three Mile Island unit 2 reactor accident

    International Nuclear Information System (INIS)

    Lillington, J.N.; Lyons, A.J.

    1990-01-01

    Some particular characteristics of the steam flow in the accident at the Three Mile Island unit 2 pressurized water reactor are investigated using the AEA Technology Flow3D code. Natural circulation flows with heat removal from the core and deposition in the upper plenum are predicted during the primary heating phase. The structure of the upper plenum cylinder and core blockage, owing to material relocation, are shown to force the flow into a complex three-dimensional pattern. The flows and temperature distributions from the calculations are shown to be consistent with the observed damage pattern above the core. Despite high core temperatures, damage was limited by the operation of one of the pumps at the end of the initial heating phase. Flow3D calculations are also carried out to demonstrate that the three-dimensional buoyancy driven flows are completely destroyed by the high steam generation rates arising from the pump operation. (author)

  3. The cleanup of Three Mile Island Unit 2: A technical history, 1979--1990

    International Nuclear Information System (INIS)

    Holton, W.C.; Negin, C.A.; Owrutsky, S.L.

    1990-09-01

    The Electric Power Research Institute has sponsored a technical history project to ensure that the logic and consequences of decisions made during the Three Mile Island Unit 2 (TMI-2) cleanup are available for recovery from an accident involving damaged fuel and fission product release. The objectives of the history project are to identify the major questions and challenges facing management; describe the influencing factors and the options available; and present the final decisions and their consequences. This history of decision-making is intended to assist a project manager who must respond to a fuel damage accident, even if the scale is much smaller than TMI-2. The history has focused on decisions related to seven major aspects of the cleanup: cleanup management, postaccident stabilization, personnel protection, data acquisition, radioactive waste management, decontamination, and defueling. A detailed chronology and extensive bibliography accompany the text

  4. Implementation of remote equipment at TMI-2 [Three Mile Island Unit 2

    International Nuclear Information System (INIS)

    Giefer, D.; Jeffries, A.B.

    1988-01-01

    Each of the remote vehicles in use, or planned for use, at Three Mile Island Unit 2 (TMI-2) during the period from 1984 to the present had certain distinct common features. These were proven to be desirable for remote application in the TMI-2 environment. Proper implementation requires consideration of the following: control systems, rigging systems, power supplies, operator/support interface, maintenance concerns, viewing systems, contamination control, and communications. Design and component fabrication of these features allowed deployment of each of the remote devices. This paper discusses these systems and their impact for the use of remote mobile equipment at TMI-2. In most cases, the means of implementation dictated the design features of the devices

  5. Answers to frequently asked questions about cleanup activities at Three Mile Island, Unit 2

    International Nuclear Information System (INIS)

    1984-03-01

    This question-and-answer report provides answers in nontechnical language to frequently asked questions about the status of cleanup activities at Three Mile Island, Unit 2. The answers update information first prepared in 1981, shortly after the cleanup got under way. Since then, a variety of important developments in the cleanup has occurred. The information in the report should be read in conjunction with NUREG 1060, a discussion of increased occupational exposure estimates for the cleanup. The questions and answers in this report cover purpose and community involvement, decontamination of water and reactor, fuel removal, radwaste transport, environmental impact, social and economic effects, worker exposures and safety, radiation monitoring, potential for accidents, and schedule and funding

  6. Thermal-hydraulic analysis of the Three Mile Island Unit 2 reactor accident with THALES code

    International Nuclear Information System (INIS)

    Hashimoto, Kazuichiro; Soda, Kunihisa

    1991-10-01

    The OECD Nuclear Energy Agency (NEA) has established a Task Group in the Committee on the Safety of Nuclear Installations (CSNI) to perform an analysis of Three Mile Island Unit 2 (TMI-2) accident as a standard problem to benchmark severe accident computer codes and to assess the capability of the codes. The TMI-2 Analysis Exercise was performed at the Japan Atomic Energy Research Institute (JAERI) using the THALES (Thermal-Hydraulic Analysis of Loss-of-Coolant, Emergency Core Cooling and Severe Core Damage) - PM1/TMI code. The purpose of the analysis is to verify the capability of THALES-PM1/TMI code to describe accident progression in the actual plant. The present paper describes the final result of the TMI-2 Analysis Exercise performed at JAERI. (author)

  7. Evaluation of Nuclear Facility Decommissioning Projects. Summary Report. Three Mile Island Unit 2 Polar Crane Recovery

    International Nuclear Information System (INIS)

    Doerge, D. H.; Miller, R. L.

    1984-08-01

    This document summarizes information concerning restoration of the Three Mile Island-Unit 2 Polar Crane to a fully operational condition following the loss of coolant accident experienced on March 28, 1979. The data collected from activity reports, reactor containment entry records, and other sources were placed in a computerized information retrieval/manipulation system which permits extraction/manipulation of specific data which could be utilized in planning for recovery activities should a similar accident occur in a nuclear generating plant. The information is presented in both computer output form and a manually assembled summarization. This report contains only the manpower requirements and radiation exposures actually incurred during recovery operations within the reactor containment and does not include support activities or costs. (author)

  8. TMI-2 [Three Mile Island Unit 2] reactor building dose reduction task force

    International Nuclear Information System (INIS)

    Daniels, R.S.

    1988-01-01

    In late October 1982, the director of Three Mile Island Unit 2 (TMI-2) created the dose reduction task force with the objective of identifying the principal radiological sources in the reactor building and recommending actions to minimize the dose to workers on labor-intensive projects. Members of the task force were drawn form various groups at TMI. Findings and recommendations were presented to the US Nuclear Regulatory Commission in a briefing on November 18, 1982. The task force developed a three-step approach toward dose reduction. Step 1 identified the radiological sources. Step 2 modeled the source and estimated its contribution to the general area dose rates. Step 3 recommended actions to achieve dose reductions consistent with general exposure rate goals

  9. Investigation of hydrogen-burn damage in the Three Mile Island Unit 2 reactor building

    International Nuclear Information System (INIS)

    Alvares, N.J.; Beason, D.G.; Eidem, G.R.

    1982-06-01

    About 10 hours after the March 28, 1979 Loss-of-Coolant Accident began at Three Mile Island Unit 2, a hydrogen deflagration of undetermined extent occurred inside the reactor building. Examinations of photographic evidence, available from the first fifteen entries into the reactor building, yielded preliminary data on the possible extent and range of hydrogen burn damage. These data, although sparse, contributed to development of a possible damage path and to an estimate of the extent of damage to susceptible reactor building items. Further information gathered from analysis of additional photographs and samples can provide the means for estimating hydrogen source and production rate data crucial to developing a complete understanding of the TMI-2 hydrogen deflagration. 34 figures

  10. Criteria development of remotely controlled mobile devices for TMI-2 [Three Mile Island Unit 2

    International Nuclear Information System (INIS)

    Fillnow, R.; Bengel, P.; Giefer, D.

    1988-01-01

    Since 1982, GPU Nuclear Corporation has used a series of remote mobile devices for data collection and cleanup of highly contaminated areas in the Three Mile Island Unit 2 (TMI-2) nuclear facilities. This paper describes these devices and the general criteria established for their design. Until 1984, the remote equipment used at TMI was obtained from industry sources. This included devices called SISI, FRED, and later LOUIE-1. Following 1984, the direction was to obtain custom-made devices to assure a design that would be more appropriate for the TMI-2 environment. Along with this approach came more detailed criteria and a need for a thorough understanding of the task to be accomplished by the devices. The following families of equipment resulted: (1) remote reconnaissance vehicles (RRVs), (2) the LOUIE family, and (3) remote working vehicle (RWV) family

  11. NRC plan for cleanup operations at Three Mile Island Unit 2

    International Nuclear Information System (INIS)

    Lo, R.; Snyder, B.

    1982-02-01

    This NRC Plan, which defines NRC's functional role in cleanup operations at Three Mile Island Unit 2 and outlines NRC's regulatory responsibilities in fulfilling this role, is the first revision to the initial plan issued in July 1980 (NUREG-0698). Since 1980, a number of policy developments have occurred which will have an impact on the course of cleanup operations. This revision reflects these developments in the area of NRC's review and approval process with regard to cleanup operations as well as NRC's interface with the Department of Energy's involvement in the cleanup and waste disposal. This revision is also intended to update the cleanup schedule by presenting the cleanup progress that has taken place and NRC's role in ongoing and future cleanup activities

  12. Programmatic changes due to TMI-2 [Three Mile Island Unit 2]: Accident planning

    International Nuclear Information System (INIS)

    Wingert, V.L.

    1988-01-01

    The focus of the paper is lessons learned for emergency planning and preparedness form the Three Mile Island Unit 2 (TMI-2) accident. The lessons learned are examined from two perspectives: (a) lessons learned that have resulted in programmatic changes, and (b) lessons learned that have not been adequately addressed. There is no doubt that the TMI-2 accident is the pivotal event that caused a major rethinking of the pre-TMI emergency preparedness posture and led to a fundamentally different approach to emergency preparedness for commercial nuclear power plant accidents. While this new approach has evolved into a comprehensive, systematic, and even prototypical national program, it has also generated new problems: escalating costs for state and local governments and leveraging of the federal licensing process by state and local governments who do not want specific nuclear power plants to operate. A discussion of the primary lessons learned on emergency preparedness is presented under the following topics: beyond defense-in-depth, predetermined action, mandatory emergency planning and preparedness, and federal coordination

  13. A guide to technical information regarding TMI-2 [Three Mile Island Unit 2

    International Nuclear Information System (INIS)

    Aucliar, K.D.; Epler, J.

    1988-01-01

    A considerable amount of information has been obtained and documented concerning the March 1979 accident and its consequences at the Three Mile Island Unit 2 (TMI-2) nuclear generating station. The information has been essential in (a) understanding the nature, progression, and extent of the damage from the accident; (b) assessing the effects of this damage on the plant's facilities, systems, equipment, and surrounding environment; and (c) planning, preparation, performance, and evaluation of the accident recovery activities. The composite of all of this literature is the technical information available at TMI-2. The issues raised by the accident are far-reaching and complex, and the technical information has usefulness beyond its application at TMI-2. Issues raised as a result of the accident pose questions that are technical, legal, financial, and political in nature. However, because the quantity of information is vast, this paper focuses on the technical data generated as a result of the TMI-2 accident recovery activities. Most of the written information generated during the TMI-2 recovery program was provided to meet the needs of the various key participants in the recovery. The informational needs of these groups varied widely; consequently, their motivation for record retention, content, and structure revolved around serving those needs. This paper provides some guidance to those researchers interested in investigating technical data as it relates to TMI-2

  14. Timing of the Three Mile Island Unit 2 core degradation as determined by forensic engineering

    International Nuclear Information System (INIS)

    Henrie, J.O.

    1988-01-01

    Unlike computer simulation of an event, forensic engineering is the evaluation of recorded data and damaged as well as surviving components after an event to determine progressive causes of the event. Such an evaluation of the 1979 Three Mile Island Unit 2 accident indicates that gas began accumulating in steam, generator A at 6:10, or 130 min into the accident and, therefore, fuel cladding ruptures and/or zirconium-water reactions began at that time. Zirconium oxidation/hydrogen generation rates were highest (∼70 kg of hydrogen per minute) during the core quench and collapse at 175 min. By 180 min, over 85% of the hydrogen generated by the zirconium-water reaction had been produced, and ∼400 kg of hydrogen had accumulated in the reactor coolant system. At that time, hydrogen concentrations at the steam/water interfaces in both steam generators approached 90%. By 203 min, the damaged reactor core had been reflooded and has not been uncovered since that time. Therefore, the core was completely under water at 225 min, when molten core material flowed into the lower head of the reactor vessel. 10 refs., 7 figs., 1 tab

  15. Historical summary of the Three Mile Island Unit 2 core debris transportation campaign

    Energy Technology Data Exchange (ETDEWEB)

    Schmitt, R.C.; Tyacke, M.J. [EG and G Idaho, Inc., Idaho Falls, ID (United States); Quinn, G.J. [Wastren, Inc., Germantown, MD (United States)

    1993-03-01

    Transport of the damaged core materials from the Unit 2 reactor of the Three Mile Island Nuclear Power Station (TMI-2) to the Idaho National Engineering Laboratory (INEL) for examination and storage presented many technical and institutional challenges, including assessing the ability to transport the damaged core; removing and packaging core debris in ways suitable for transport; developing a transport package that could both meet Federal regulations and interface with the facilities at TMI-2 and the INEL; and developing a transport plan, support logistics, and public communications channels suited to the task. This report is a historical summary of how the US Department of Energy addressed those challenges and transported, received, and stored the TMI-2 core debris at the INEL. Subjects discussed include preparations for transport, loading at TMI-2, institutional issues, transport operations, receipt and storage at the INEL, governmental inquiries/investigations, and lessons learned. Because of public attention focused on the TMI-2 Core Debris Transport Program, the exchange of information between the program and public was extensive. This exchange is a focus for parts of this report to explain why various operations were conducted as they were and why certain technical approaches were employed. And, because of that exchange, the program may have contributed to a better public understanding of such actions and may contribute to planning and execution of similar future actions.

  16. Personnel contamination protection techniques applied during the TMI-2 [Three Mile Island Unit 2] cleanup

    International Nuclear Information System (INIS)

    Hildebrand, J.E.

    1988-01-01

    The severe damage to the Three Mile Island Unit 2 (TMI-2) core and the subsequent discharge of reactor coolant to the reactor and auxiliary buildings resulted in extremely hostile radiological environments in the TMI-2 plant. High fission product surface contamination and radiation levels necessitated the implementation of innovative techniques and methods in performing cleanup operations while assuring effective as low as reasonably achievable (ALARA) practices. The approach utilized by GPU Nuclear throughout the cleanup in applying protective clothing requirements was to consider the overall health risk to the worker including factors such as cardiopulmonary stress, visual and hearing acuity, and heat stress. In applying protective clothing requirements, trade-off considerations had to be made between preventing skin contaminations and possibly overprotecting the worker, thus impacting his ability to perform his intended task at maximum efficiency and in accordance with ALARA principles. The paper discusses the following topics: protective clothing-general use, beta protection, skin contamination, training, personnel access facility, and heat stress

  17. Heat stress control in the TMI-2 [Three Mile Island Unit 2] defueling and decontamination activities

    International Nuclear Information System (INIS)

    Schork, J.S.; Parfitt, B.A.

    1988-01-01

    During the initial stages of the Three Mile Island Unit 2 (TMI-2) defueling and decontamination activities for the reactor building, it was realized that the high levels of loose radioactive contamination would require the use of extensive protective clothing by entry personnel. While there was no doubt that layered protective clothing protects workers from becoming contaminated, it was recognized that these same layers of clothing would impose a very significant heat stress burden. To prevent the potentially serious consequences of a severe reaction to heat stress by workers in the hostile environment of the TMI-2 reactor building and yet maintain the reasonable work productivity necessary to perform the recovery adequately, an effective program of controlling worker exposure to heat stress had to be developed. Body-cooling devices produce a flow of cool air, which is introduced close to the skin to remove body heat through convection and increased sweat evaporation. The cooling effect produced by the Vortex tube successfully protected the workers from heat stress, however, there were several logistical and operational problems that hindered extensive use of these devices. The last type of cooling garment examined was the frozen water garment (FWG) developed by Elizier Kamon at the Pennsylvania State University as part of an Electric Power Research Institute research grant. Personal protection, i.e., body cooling, engineering controls, and administrative controls, have been implemented successfully

  18. Evaluation of the Three Mile Island Unit 2 reactor building decontamination process

    International Nuclear Information System (INIS)

    Dougherty, D.; Adams, J.W.

    1983-08-01

    Decontamination activities from the cleanup of the Three Mile Island Unit 2 Reactor Building are generating a variety of waste streams. Solid wastes being disposed of in commercial shallow land burial include trash and rubbish, ion-exchange resins (Epicor-II) and strippable coatings. The radwaste streams arising from cleanup activities currently under way are characterized and classified under the waste classification scheme of 10 CFR Part 61. It appears that much of the Epicor-II ion-exchange resin being disposed of in commerical land burial will be Class B and require stabilization if current radionuclide loading practices continue to be followed. Some of the trash and rubbish from the cleanup of the reactor building so far would be Class B. Strippable coatings being used at TMI-2 were tested for leachability of radionuclides and chelating agents, thermal stability, radiation stability, stability under immersion and biodegradability. Actual coating samples from reactor building decontamination testing were evaluated for radionuclide leaching and biodegradation

  19. Technology transfer and radioactive waste management at TMI-2 [Three Mile Island Unit 2

    International Nuclear Information System (INIS)

    Saunders, J.R.

    1988-01-01

    The accident that occurred on March 28, 1979, at the Three Mile Island Unit 2 (TMI-2) nuclear generating station caused extensive damage to the reactor core and created high radiation contamination levels throughout the facility. The electric power industry, regulators, and government agencies were faced with one of the most technically challenging recovery situations ever encountered in this country. But it was also realized that this adversity presented opportunities for the advancement of state-of-the-art technologies as well as the potential to produce information that could enhance nuclear power plant safety and reliability. Perhaps one of the more significant aspects of the TMI-2 recovery has been the advancement of radioactive waste management technology. The high levels and unusual nature of the TMI-2 radioactive waste necessitated the development of innovative techniques for processing, packaging, shipping, and disposal. The investment in research was rewarded with large volume reductions and associated cost savings. It is anticipated that the TMI-2 radioactive waste management technology will make major contributions to the design of new systems to meet this growing need. The following areas appear particularly suited for this purpose: volume reduction, high-integrity containers, and selective isotope removal

  20. Evaluation of the Three Mile Island Unit 2 reactor building decontamination process

    Energy Technology Data Exchange (ETDEWEB)

    Dougherty, D.; Adams, J. W.

    1983-08-01

    Decontamination activities from the cleanup of the Three Mile Island Unit 2 Reactor Building are generating a variety of waste streams. Solid wastes being disposed of in commercial shallow land burial include trash and rubbish, ion-exchange resins (Epicor-II) and strippable coatings. The radwaste streams arising from cleanup activities currently under way are characterized and classified under the waste classification scheme of 10 CFR Part 61. It appears that much of the Epicor-II ion-exchange resin being disposed of in commerical land burial will be Class B and require stabilization if current radionuclide loading practices continue to be followed. Some of the trash and rubbish from the cleanup of the reactor building so far would be Class B. Strippable coatings being used at TMI-2 were tested for leachability of radionuclides and chelating agents, thermal stability, radiation stability, stability under immersion and biodegradability. Actual coating samples from reactor building decontamination testing were evaluated for radionuclide leaching and biodegradation.

  1. Historical summary of the Three Mile Island Unit 2 core debris transportation campaign

    International Nuclear Information System (INIS)

    Schmitt, R.C.; Tyacke, M.J.; Quinn, G.J.

    1993-03-01

    Transport of the damaged core materials from the Unit 2 reactor of the Three Mile Island Nuclear Power Station (TMI-2) to the Idaho National Engineering Laboratory (INEL) for examination and storage presented many technical and institutional challenges, including assessing the ability to transport the damaged core; removing and packaging core debris in ways suitable for transport; developing a transport package that could both meet Federal regulations and interface with the facilities at TMI-2 and the INEL; and developing a transport plan, support logistics, and public communications channels suited to the task. This report is a historical summary of how the US Department of Energy addressed those challenges and transported, received, and stored the TMI-2 core debris at the INEL. Subjects discussed include preparations for transport, loading at TMI-2, institutional issues, transport operations, receipt and storage at the INEL, governmental inquiries/investigations, and lessons learned. Because of public attention focused on the TMI-2 Core Debris Transport Program, the exchange of information between the program and public was extensive. This exchange is a focus for parts of this report to explain why various operations were conducted as they were and why certain technical approaches were employed. And, because of that exchange, the program may have contributed to a better public understanding of such actions and may contribute to planning and execution of similar future actions

  2. Lessons learned from the Three Mile Island Unit 2 Advisory Panel

    International Nuclear Information System (INIS)

    Lach, D.; Bolton, P.; Durbin, N.; Harty, R.

    1994-08-01

    In response to public concern about the cleanup of the Three Mile Island, Unit 2 (TMI-2) facility after an accident on March 28, 1979 involving a loss of reactor coolant and subsequent damage to the reactor fuel, twelve citizens were asked to serve on an independent Advisory Panel to consult with the Nuclear Regulatory Commission (NRC) on the decontamination and cleanup of the facility. The panel met 78 times over a period of thirteen years, holding public meetings in the vicinity of TMI-2 and meeting regularly with NRC Commissioners in Washington, DC. This report describes the results of a project designed to identify and describe the lessons learned from the Advisory Panel and place those lessons in the context of what we generally know about citizen advisory groups. A summary of the empirical literature on citizen advisory panels is followed by a brief history of the TMI-2 Advisory Panel. The body of the report contains the analysis of the lessons learned, preliminary conclusions about the effectiveness of the Panel, and implications for the NRC in the use of advisory panels. Data for the report include meeting transcripts and interviews with past and present Panel participants

  3. Characterization of solids in the Three Mile Island Unit 2 reactor defueling water

    International Nuclear Information System (INIS)

    Campbell, D.O.

    1987-12-01

    Because of the impact of poor water clarity on defueling operations at the Three Mile Island Unit 2 Nuclear Power Station, a study was undertaken to characterize suspended particulates in the reactor defueling water. The examination included cascade filtration through Nuclepore filters of progressively smaller pore sizes, using three water samples obtained at different times and after varying degrees of clarification. The solids collected on the filters were examined with a scanning electron microscope and analyzed with energy-dispersive x-ray fluorescence. A wide variety of solids was observed, and 26 elements were detected. These included all the materials expected from the reactor system (uranium, zirconium, silver, cadmium, indium, iron, chromium, and nickel), chemicals and zeolites used to decontaminate the water (aluminum, silicon, sodium), common impurities (potassium, chlorine, sulfur, magnesium, calcium, and others), as well as some unexpected metals (molybdenum, manganese, bromine, and lead). There was also evidence for the presence of organic material. A diverse assortment of particles with widely varying surface properties was found to be present

  4. Answers to questions about removing krypton from the Three Mile Island, Unit 2 reactor building. Public information report

    International Nuclear Information System (INIS)

    1980-05-01

    This document presents answers to frequently asked questions about the probable effects of controlled releases of the krypton presently contained within the reactor building of Three Mile Island, Unit 2. Also answered are questions about alternative means for removing the krypton

  5. Title list publicly available documents: Three Mile Island Unit 2, Docket 50-320. Cumulated to May 21, 1979

    International Nuclear Information System (INIS)

    1979-01-01

    This title list of publicly available documents pertaining to Three Mile Island Unit 2, Docket 50-320, includes those preincident and postincident documents filed in the NRC Public Document Room as of May 21, 1979. It is divided into preincident and postincident listings, with both listings subdivided into the categories used for filing and searching in the NRC Public Document Room

  6. Title list, publicly available documents: Three Mile Island Unit 1, Docket 50-289 - cumulated to November 16, 1979

    International Nuclear Information System (INIS)

    1979-01-01

    This title list of publicly available documents pertaining to Three Mile Island Unit 1, Docket 50-289, includes all documents pertaining to this Docket that had been filed in the NRC Public Document Room as of November 16, 1979. The categories used for filing and searching in the NRC Public Document Room are used to catalog the entries

  7. 78 FR 22347 - GPU Nuclear Inc., Three Mile Island Nuclear Power Station, Unit 2, Exemption From Certain...

    Science.gov (United States)

    2013-04-15

    ... 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... and State Materials and Environmental Management Programs, U.S. Nuclear Regulatory Commission...

  8. Peer review of the Three Mile Island Unit 2 Vessel Investigation Project metallurgical examinations

    Energy Technology Data Exchange (ETDEWEB)

    Bohl, R.W.; Gaydos, R.G.; Vander Voort, G.F.; Diercks, D.R. [Argonne National Lab., IL (United States)

    1994-07-01

    Fifteen samples recovered from the lower head of the Three Mile Island (TMI) Unit 2 nuclear reactor pressure vessel were subjected to detailed metallurgical examinations by the Idaho National Engineering Laboratory (INEL), with supporting work carried out by Argonne National Laboratory (ANL) and several of the European participants. These examinations determined that a portion of the lower head, a so-called elliptical ``hot spot`` measuring {approx}0.8 {times} 1 m, reached temperatures as high as 1100{degrees}C during the accident and cooled from these temperatures at {approx}10--100{degrees}C/min. The remainder of the lower head was found to have remained below the ferrite-toaustenite transformation temperature of 727{degrees}C during the accident. Because of the significance of these results and their importance to the overall analysis of the TMI accident, a panel of three outside peer reviewers, Dr. Robert W. Bohl, Mr. Richard G. Gaydos, and Mr. George F. Vander Voort, was formed to conduct an independent review of the metallurgical analyses. After a thorough review of the previous analyses and examination of photo-micrographs and actual lower head specimens, the panel determined that the conclusions resulting from the INEL study were fundamentally correct. In particular, the panel reaffirmed that four lower head samples attained temperatures as high as 1100{degrees}C, and perhaps as high as 1150--1200{degrees}C in one case, during the accident. They concluded that these samples subsequently cooled at a rate of {approx}50--125{degrees}C/min in the temperature range of 600--400{degrees}C, in good agreement with the original analysis. The reviewers also agreed that the remainder of the lower head samples had not exceeded the ferrite-to-austenite transformation temperature during the accident and suggested several refinements and alternative procedures that could have been employed in the original analysis.

  9. Peer review of the Three Mile Island Unit 2 Vessel Investigation Project metallurgical examinations

    International Nuclear Information System (INIS)

    Bohl, R.W.; Gaydos, R.G.; Vander Voort, G.F.; Diercks, D.R.

    1994-07-01

    Fifteen samples recovered from the lower head of the Three Mile Island (TMI) Unit 2 nuclear reactor pressure vessel were subjected to detailed metallurgical examinations by the Idaho National Engineering Laboratory (INEL), with supporting work carried out by Argonne National Laboratory (ANL) and several of the European participants. These examinations determined that a portion of the lower head, a so-called elliptical ''hot spot'' measuring ∼0.8 x 1 m, reached temperatures as high as 1100 degrees C during the accident and cooled from these temperatures at ∼10--100 degrees C/min. The remainder of the lower head was found to have remained below the ferrite-toaustenite transformation temperature of 727 degrees C during the accident. Because of the significance of these results and their importance to the overall analysis of the TMI accident, a panel of three outside peer reviewers, Dr. Robert W. Bohl, Mr. Richard G. Gaydos, and Mr. George F. Vander Voort, was formed to conduct an independent review of the metallurgical analyses. After a thorough review of the previous analyses and examination of photo-micrographs and actual lower head specimens, the panel determined that the conclusions resulting from the INEL study were fundamentally correct. In particular, the panel reaffirmed that four lower head samples attained temperatures as high as 1100 degrees C, and perhaps as high as 1150--1200 degrees C in one case, during the accident. They concluded that these samples subsequently cooled at a rate of ∼50--125 degrees C/min in the temperature range of 600--400 degrees C, in good agreement with the original analysis. The reviewers also agreed that the remainder of the lower head samples had not exceeded the ferrite-to-austenite transformation temperature during the accident and suggested several refinements and alternative procedures that could have been employed in the original analysis

  10. Radiation effects on resins and zeolites at Three Mile Island Unit II

    International Nuclear Information System (INIS)

    Reilly, J.K.; Grant, P.J.; Quinn, G.J.; Hofstetter, K.J.

    1984-01-01

    Radiation effects on resin and zeolite used in the waste cleanup at Three Mile Island Unit II have been examined both experimentally and in-situ. Hydrogen and organic gases are generated due to absorbed radiation as a function of resin material, curie loading and residual water content. Significant oxygen scavaging was demonstrated in the organic resin liners. Hydrogen and oxygen gases in near stoichiometric quantities are generated from irradiation of residual water in inorganic zeolites. Gas generation was determined to be directly proportional to curie content but correlates poorly with residual water content in zeolite vessels. Results of the gas generation analyses of EPICOR II liners show that vessels with less than 166 curies had almost no hydrogen generated during two years of storage and therefore did not require safety measures for shipment or storage. Experimental measurements done at research laboratories predicted similar results associated with hydrogen gas generation and oxygen depletion. X-ray diffraction examinations and ion exchange capacity measurements indicated no evidence of irradiation effects on the structure or cesium exchange capacity for zeolites exposed to 10 10 rads. Darkening and damage of organic resin due to radiation has been identified. Breaking and agglomeration of the purification demineralizer resin is believed to be the result of temperature effects. No damage was identified from radiation effects on zeolite. Organic and inorganic sorbents used in the processing of contaminated waters at TMI-2 have been shown to be effective in maintaining long-term stability under high radiation conditions. The effects of radiolytic degradation have been shown by direct measurements and simulation tests and are of use in their general application throughout the industry

  11. Urban sprawl and miles driven daily by teenagers in the United States.

    Science.gov (United States)

    Trowbridge, Matthew J; McDonald, Noreen C

    2008-03-01

    Urban sprawl's association with increased automobile reliance and daily mileage is well established among adults. However, sprawl's specific impact on teen driving exposure is unknown. Teen driver fatality rates per mile driven are significantly higher than adults, making the identification of environmental influences on travel behavior particularly important in this age group. Driving and demographic data for 4528 teens (weighted=10.5 million) aged 16-19 years were obtained from the 2001 National Household Transportation Survey (NHTS). County-level sprawl was measured using an index developed by Ewing et al. The association between daily miles driven by teens and sprawl, controlling for demographic characteristics, was modeled using ordinal logistic regression. The predicted probability of driving >20 miles in counties with varying degrees of sprawl also was calculated. Of the surveyed teens, 48% did not drive, 27% drove 20 miles/day. Of the 52% of teens who reported driving, the average distance driven was 15.6 miles/day. More-pronounced sprawl was associated with increased daily mileage (psprawling counties were more than twice as likely to drive >20 miles/day than teens in compact counties. This trend was most prominent among the youngest drivers. For example, the predicted probability of boys aged 16-17 years driving >20 miles per day varied from 9% to 24% in compact versus sprawling counties. Sprawl is associated with increased daily mileage by teen drivers. Given the stark relationship between driving exposure and fatality risk among teens, increased efforts to understand and modify the effects of sprawl on adolescent driving behavior are necessary.

  12. Publicly available documents Three Mile Island Unit 2, Docket 50-320. Title list, July 1-October 31, 1979

    Energy Technology Data Exchange (ETDEWEB)

    1979-01-01

    This supplemental title list of publicly available documents pertaining to Three Mile Island Unit 2, Docket 50-320, includes those preincident and postincident documents filed in the NRC Public Document Room between July 1, 1979 and October 31, 1979. It is divided into preincident and postincident listings, with both listings sub-divided into the categories used for filing and searching in the NRC Public Document Room.

  13. Publicly available documents Three Mile Island Unit 2, Docket 50-320. Title list, July 1-October 31, 1979

    International Nuclear Information System (INIS)

    1979-01-01

    This supplemental title list of publicly available documents pertaining to Three Mile Island Unit 2, Docket 50-320, includes those preincident and postincident documents filed in the NRC Public Document Room between July 1, 1979 and October 31, 1979. It is divided into preincident and postincident listings, with both listings sub-divided into the categories used for filing and searching in the NRC Public Document Room

  14. Annual Radiological Environmental Monitoring Program Report for the Three Mile Island, Unit 2, Independent Spent Fuel Storage Installation

    International Nuclear Information System (INIS)

    Hall, Gregory Graham

    2002-01-01

    This report presents the results of the 2001 Radiological Environmental Monitoring Program conducted in accordance with 10 CFR 72.44 for the Three Mile Island, Unit 2, Independent Spent Fuel Storage Installation. A description of the facility and the monitoring program is provided. The results of monitoring the two predominant radiation exposure pathways, potential airborne radioactivity releases and direct radiation exposure, indicate the facility operation has not contributed to any increase in the estimated maximum potential dose commitment to the general public.

  15. Measurement of in-core and recirculation system response to hydrogen water chemistry at Nine Mile Point 1

    International Nuclear Information System (INIS)

    Head, R.A.; Indig, M.E.; Andresen, P.L.

    1991-03-01

    The value of hydrogen water chemistry (HWC) as a mitigation technique for out-of-core piping systems susceptible to intergranular stress corrosion cracking (IGSCC) is well established. However, certain reactor internal components exposed to high levels of radiation are susceptible to a cracking mechanism referred to as irradiation assisted stress corrosion cracking (IASCC). Some of the components potentially affected by IASCC include the top guide, SRM/IRM housings, the core shroud, and control blades. Fortunately, laboratory data indicate that IASCC can be controlled by altering the coolant environment. Hot cell tests performed at GE's Vallecitos Nuclear Center (VNC) on highly irradiated material produced a fracture surface with 99% IGSCC under normal BWR water chemistry. However, under HWC conditions, only ductile failure occurred. With this background, a program was established to determine the chemistry and oxidizing potential of the core bypass coolant at Nine Mile Point-1 (NMP-1) under normal and HWC conditions. The objective of the program was to assess whether HWC could sufficiently modify the core bypass environment to mitigate IASCC. Results showed that with the addition of hydrogen to the feedwater, core bypass dissolved oxygen decreased very rapidly, compared to the recirculation water, indicating very efficient recombination of hydrogen and oxygen in the non-boiling core bypass region. Since low concentrations of dissolved oxygen have been shown to eliminate IASCC, these results are encouraging. 8 figs., 1 tab

  16. Flowsheet development studies for the decontamination of high-activity-level water at Three Mile Island Unit 2

    International Nuclear Information System (INIS)

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

    1980-01-01

    Several chemical processing flowsheets were considered for the decontamination of high-activity-level water at the Three Mile Island (TMI) Unit 2. A zeolite ion exchange process was evaluated and recommended for absorption of the bulk of the highly radioactive cesium and strontium. Standard organic ion-exchange resins were selected to remove the remaining traces of radioactive nuclides (except tritium which cannot be removed by any practical process). Process conditions were evaluated using both synthetic, tracer-level solutions and samples of actual, high-activity level water from TMI Unit 2

  17. Characterization of the Three Mile Island Unit-2 reactor building atmosphere prior to the reactor building purge

    International Nuclear Information System (INIS)

    Hartwell, J.K.; Mandler, J.W.; Duce, S.W.; Motes, B.G.

    1981-05-01

    The Three Mile Island Unit-2 reactor building atmosphere was sampled prior to the reactor building purge. Samples of the containment atmosphere were obtained using specialized sampling equipment installed through penetration R-626 at the 358-foot (109-meter) level of the TMI-2 reactor building. The samples were subsequently analyzed for radionuclide concentration and for gaseous molecular components (O 2 , N 2 , etc.) by two independent laboratories at the Idaho National Engineering Laboratory (INEL). The sampling procedures, analysis methods, and results are summarized

  18. Percolation cooling of the Three Mile Island Unit 2 lower head by way of thermal cracking and gap formation

    DEFF Research Database (Denmark)

    Thomsen, K.L.

    2002-01-01

    Two partial models have been developed to elucidate the Three Mile Island Unit 2 lower head coolability by water percolation from above into the thermally cracking debris bed and into a gap between the debris and the wall The bulk permeability of the cracked top crust is estimated based on simple...... fracture mechanics and application of Poiseuille's law to the fractures. The gap is considered as an abstraction representing an initially rugged interface, which probably expanded by thermal deformation and cracking in connection with the water ingress. The coupled flow and heat conduction problem...

  19. Radiation effects on resins and zeolites at Three Mile Island Unit II

    International Nuclear Information System (INIS)

    Reilly, J.K.; Grant, P.J.; Hofstetter, K.J.; Quinn, G.J.; Runion, T.C.

    1984-01-01

    The March 1979 accident at Three Mile Island created certain waste forms that are not routinely encountered in normal light water reactor plants and were the subject of a research and development program. Fifty EPICOR II organic resin containers were loaded to as much as 2200 Ci (of predominantly cesium plus strontium) in the course of processing contaminated water. Resin samples were taken from two of the EPICOR II vessels and examined. Nineteen zeolite containers loaded with radioactive cesium plus strontium to as much as 55,000 Ci have been analyzed. The makeup and purification system demineralizer resins, highly contaminated by the letdown of reactor coolant, have been radiation surveyed, and gas, liquid, and resin samples have been obtained. On-site sampling and analysis of these wastes indicated that combustible gases (hydrogen and oxygen) were being generated as a result of radiolysis. The results of this work are discussed, compared, and presented

  20. The United States Naval Nuclear Propulsion Program - Over 151 Million Miles Safely Steamed on Nuclear Power

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2015-03-01

    NNSA’s third mission pillar is supporting the U.S. Navy’s ability to protect and defend American interests across the globe. The Naval Reactors Program remains at the forefront of technological developments in naval nuclear propulsion and ensures a commanding edge in warfighting capabilities by advancing new technologies and improvements in naval reactor performance and reliability. In 2015, the Naval Nuclear Propulsion Program pioneered advances in nuclear reactor and warship design – such as increasing reactor lifetimes, improving submarine operational effectiveness, and reducing propulsion plant crewing. The Naval Reactors Program continued its record of operational excellence by providing the technical expertise required to resolve emergent issues in the Nation’s nuclear-powered fleet, enabling the Fleet to safely steam more than two million miles. Naval Reactors safely maintains, operates, and oversees the reactors on the Navy’s 82 nuclear-powered warships, constituting more than 45 percent of the Navy’s major combatants.

  1. 76 FR 32994 - Nine Mile Point 3 Nuclear Project, LLC and Unistar Nuclear Operating Services, LLC; Combined...

    Science.gov (United States)

    2011-06-07

    ... December 1, 2009, UniStar Nuclear Energy (UNE), which is acting on behalf of the COL applicants Nine Mile... impacted by this exemption. Special Circumstances Special circumstances, in accordance with 10 CFR 50.12(a... exemption from 10 CFR 50.71(e)(3)(iii) exist. Eligibility for Categorical Exclusion From Environmental...

  2. A comparison of measured radionuclide release rates from Three Mile Island Unit-2 core debris for different oxygen chemical potentials

    International Nuclear Information System (INIS)

    Baston, V.F.; Hofstetter, K.J.; Ryan, R.F.

    1987-01-01

    Chemical and radiochemical analyses of reactor coolant samples taken during defueling of the Three Mile Island Unit-2 (TMI-2) reactor provide relevant data to assist in understanding the solution chemistry of the radionuclides retained within the TMI-2 reactor coolant system. Hydrogen peroxide was added to various plant systems to provide disinfection for microbial contamination and has provided the opportunity to observe radionuclide release under different oxygen chemical potentials. A comparison of the radionuclide release rates with and without hydrogen peroxide has been made for these separate but related cases, i.e., the fuel transfer canal and connecting spent-fuel pool A with the TMI-2 reactor plenum in the fuel transfer canal, core debris grab sample laboratory experiments, and the reactor vessel fluid and associated core debris. Correlation and comparison of these data indicate a physical parameter dependence (surface-to-volume ratio) affecting all radionuclide release; however, selected radionuclides also demonstrate a chemical dependence release under the different oxygen chemical potentials. Chemical and radiochemical analyses of reactor coolant samples taken during defueling of the Three Mile Island Unit-2 (TMI-2) reactor provide relevant data to assist in understanding the solution chemistry of the radionuclides retained within the TMI-2 reactor coolant system

  3. Development of a high integrity container for storage, transportation, and disposal of radioactive wastes from Three Mile Island unit II

    International Nuclear Information System (INIS)

    Holzworth, R.E.; Chapman, R.L.; Burton, H.M.; Bixby, W.W.

    1981-01-01

    The EPICOR II ion exchange system used to decontaminate approximately 1900 m 3 of contaminated water in the Auxiliary and Fuel Handling Building (AFHB) generated 50 highly loaded and 22 lesser loaded organic resin liners. The 22 lesser loaded resins were shipped to a commercial disposal site, but the highly loaded liners have been stored on the island since their generation. One highly loaded liner, or prefilter, was shipped to Battelle Columbus Laboratories (BCL) in May, 1981 as part of the United States Department of Energy (DOE) Three Mile Island Information and Examination Program. The prefilter is being characterized to determine the behavior of the waste form with respect to time and the internal environment and to provide an information base for use in management and regulatory decisions relative to the storage, processing, and disposal of these wastes. Due to the unique characteristics of these wastes, the US DOE is sponsoring programs, such as the BCL Sorbent Experiments Program, to evaluate their characteristics and to provide a High Integrity Container (HIC) Development Program which would improve waste suitability for disposal at a land burial facility. This paper addresses regulatory considerations, establishment of design criteria, proposed design concepts, system demonstration, and status of the HIC Development Program for storage, transportation, and disposal of high specific activity, low level radioactive wastes from Three Mile Island Unit II as typified by EPICOR II ion exchange media and liners

  4. Evaluation of nuclear facility decommissioning projects: Summary status report: Three Mile Island Unit 2 radioactive waste and laundry shipments

    International Nuclear Information System (INIS)

    Doerge, D.H.; Haffner, D.R.

    1988-06-01

    This document summarizes information concerning radioactive waste and laundry shipments from the Three Mile Island Nuclear Station Unit 2 to radioactive waste disposal sites and to protective clothing decontamination facilities (laundries) since the loss of coolant accident experienced on March 28, 1979. Data were collected from radioactive shipment records, summarized, and placed in a computerized data information retrieval/manipulation system which permits extraction of specific information. This report covers the period of April 9, 1979 through April 19, 1987. Included in this report are: waste disposal site locations, dose rates, curie content, waste description, container type and number, volumes and weights. This information is presented in two major categories: protective clothing (laundry) and radioactive waste. Each of the waste shipment reports is in chronological order

  5. Neutron dosimetry in the Three-Mile Island Unit 2 reactor cavity with solid-state track recorders

    International Nuclear Information System (INIS)

    Gold, R.; Roberts, J.H.; Ruddy, F.H.; Preston, C.C.; McElroy, W.N.; Rao, S.V.; Greenborg, J.; Fricke, V.R.

    1986-01-01

    Solid-state track recorder (SSTR) neutron dosimetry has been conducted in the Three-Mile Island Unit 2 (TMI-2) reactor cavity, for nondestructive assessment of the fuel distribution. Two axial stringers were deployed in the annular gap with 17 SSTR dosimeters located on each stringer. SSTR experimental results reveal that neutron streaming, upward from the bottom of the reactor cavity region, dominates the observed neutron intensity. These absolute thermal neutron flux observations are consistent with the presence of a significant amount of fuel debris lying at the bottom of the reactor vessel. A conservative lower bound estimated from these SSTR data implies that at least 2 tonnes of fuel, which is roughly 4 fuel assemblies, is lying at the bottom of the vessel. This existence of significant neutron streaming also explains the high count rate observed with the source range monitors that are located in the TMI-2 reactor cavity. (author)

  6. Quality assurance in the removal and transport of the TMI-2 [Three Mile Island Unit 2] core

    International Nuclear Information System (INIS)

    Hayes, G.R.; Marsden, J.F.

    1988-01-01

    The March 1979 accident at Three Mile Island Unit 2 (TMI-2) damaged the core of the reactor. One of the major cleanup activities involves removal of the damaged core from the reactor and transporting it from the TMI-2 site near Middletown, Pennsylvania, to the Idaho National Engineering Laboratory (INEL) near Idaho Falls, Idaho. Removal and transport of the damaged core necessitated the development of much specialized equipment. This paper focuses on the role quality assurance (QA) played in the design, fabrication, acceptance, and use of three important pieces of core debris removal and transportation equipment: (1) the core boring machine, (2) the fuel debris canisters, (3) the NuPac 125-B rail cask and handling equipment

  7. Transporting TMI-2 [Three Mile Island Unit 2] core debris to INEL: Public safety and public response

    International Nuclear Information System (INIS)

    Schmitt, R.C.; Reno, H.W.; Young, W.R.; Hamric, J.P.

    1987-01-01

    This paper describes the approach taken by the US Department of Energy (DOE) to ensure that public safety is maintained during transport of core debris from the Unit-2 reactor at the Three Mile Island Nuclear Power Station near Harrisburg, PA, to the Idaho National Engineering Laboratory near Idaho Falls, ID. It provides up-to-date information about public response to the transport action and discusses DOE's position on several institutional issues. The authors advise that planners of future transport operations be prepared for a multitude of comments from all levels of federal, state, and local governments, special interest groups, and private citizens. They also advise planners to keep meticulous records concerning all informational transactions

  8. Nine Mile Point Nuclear Station, Unit 1. Annual report of operation, 1975

    International Nuclear Information System (INIS)

    1976-01-01

    Net electrical power generated was 3,044,948 MWh(e) with the reactor on line 6,238 hrs. Information is presented concerning power generation, shutdowns, corrective maintenance, chemistry and radiochemistry, occupational radiation exposure, release of radioactive materials, reportable occurrences, effluent and waste disposal, meteorological summary, and environmental monitoring

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

    International Nuclear Information System (INIS)

    1977-01-01

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

  10. Venting krypton-85 from the Three Mile Island Unit 2 reactor building

    International Nuclear Information System (INIS)

    Burton, H.M.

    1981-01-01

    To permit the less restricted access to the reactor building necessary to maintain instrumentation and equipment, and to proceed towad the total decontamination of the facility, General Public Utilities, operators of the facility referred to hereafter as GPU, asked the United States Nuclear Regulatory Commission, or NRC, for permission to remove the 85 Kr from the reactor building by venting it to the environment. GPU supported their request with the Safety Analysis and Environmental Assessment Report on the proposed reactor building venting plan. On June 12, 1980, after seven months of licensing deliberations and numerous public hearings, the NRC granted GPU's request. The actual venting took place between June 28 and July 11, 1980. This report presents an overview of the detailed effort involved in the TMI-2 reactor building venting program. The findings reported here are condensed from a published report entitled TMI-2 Reactor Building Purge--Kr-85 Venting

  11. Unauthorized forced entry into the protected area at Three Mile Island Unit 1 on February 7, 1993

    International Nuclear Information System (INIS)

    1993-04-01

    On February 7, 1993, at 6:53 a.m. Eastern Standard Time (EST) an intruder drove into tile site owner-controlled area, through a gate into the protected area of Three Mile Island Nuclear Generating Station, Unit I (TMI-1) and crashed through a roll-up door on the Turbine Building. TMI Security reported this event to the US Nuclear Regulatory Commission's (NRC's) Headquarters operations officer and declared a Security Emergency upon determining that the protected area of the plant had been compromised. At 7:23 a.m., the TMI-1 shift supervisor officially notified the NRC Headquarters operations officer that he had declared a Site Area Emergency effective at 7:05 a.m. Upon considering the possible significance to physical security and the regulatory questions that could result from the event, the NRC Executive Director for Operations established an incident investigation team to determine what happened and make appropriate findings and conclusions. In this report the team described the event and the response to the event, evaluated the regulatory requirements, and presented the team's findings and conclusions

  12. Thermal and stress analyses of the reactor pressure vessel lower head of the Three Mile Island Unit 2

    International Nuclear Information System (INIS)

    Hashimoto, K.; Onizawa, K.; Kurihara, R.; Kawasaki, S.; Soda, K.

    1992-01-01

    Thermal and stress analyses were performed using the finite element analysis code ABAQUS to clarify the factors which caused tears in the stainless steel liner of the reactor pressure vessel lower head of the Three Mile Island Unit 2 (TMI-2) reactor pressure vessel during the accident on 28 March 1979. The present analyses covered the events which occurred after approximately 20 tons of molten core material were relocated to the lower head of the reactor pressure vessel. They showed that the tensile stress was highest in the case where the relocated core material consisting of homogeneous UO 2 debris was assumed to attack the lower head and the debris was then quenched. The peak tensile stress was in the vicinity of the welded zone of the penetration nozzle. This result agrees with the findings from the examination of the TMI-2 reactor pressure vessel that major tears in the stainless steel liner were observed around two penetration nozzles of the lower head. (author)

  13. Assessment of extent and degree of thermal damage to polymeric materials in the Three Mile Island Unit 2 reactor building

    International Nuclear Information System (INIS)

    Alvares, N.J.

    1986-01-01

    This paper describes assumptions and procedures used to perform thermal damage analysis caused by post loss-of-coolant-accident (LOCA) hydrogen deflagration at Three Mile Island Unit 2 Reactor. Examination of available photographic evidence yields data on the extent and range of thermal and burn damage. Thermal damage to susceptible material in accessible regions of the reactor building was distributed in non-uniform patterns. No clear explanation for non-uniformity was found in examined evidence, e.g., burned materials were adjacent to materials that appear similar but were not burned. Because these items were in proximity to vertical openings that extend the height of the reactor building, the authors assume the unburned materials preferentially absorbed water vapor during periods of high, local steam concentration. A control pendant from the polar crane located in the top of the reactor building sustained asymmetric burn damage of decreasing degree from top to bottom. Evidence suggests the polar-crane pendant side that experienced heaviest damage was exposed to intense radiant energy from a transient fire plume in the reactor containment volume. Simple hydrogen-fire-exposure tests and heat transfer calculations approximate the degree of damage found on inspected materials from the containment building and support for an estimated 8% pre-fire hydrogen

  14. Evaluation of nuclear facility decommissioning projects. Three Mile Island Unit 2 reactor defueling and disassembly. Summary status report. Volume 3

    International Nuclear Information System (INIS)

    Doerge, D.H.; Miller, R.L.; Scotti, K.S.

    1986-05-01

    This document summarizes information relating to the preparations for defueling the Three Mile Island Unit 2 (TMI-2) reactor and disassembly activities being performed concurrently with decontamination of the facility. Data have been collected from activity reports, reactor containment entry records, and other sources and entered in a computerized data sysem which permits extraction/manipulation of specific data which can be used in planning for recovery from a loss of coolant event similar to that experienced at TMI-2 on March 28, 1979. This report contains summaries of man-hours, manpower, and radiation exposures incurred during the period of April 23, 1979 to April 16, 1985, in the completion of activities related to preparation for reactor defueling. Support activities conducted outside of radiation areas are not included within the scope of this report. Computerized reports included in this document are: A chronological summary listing work performed for the period; and summary reports for each major task undertaken in connection with the specific scope of this report. Presented in chronological order for the referenced time period. Manually-assembled table summaries are included for: Labor and exposures by department; and labor and exposures by major activity

  15. Solid-state track recorder neutron dosimetry in the Three-Mile Island Unit-2 reactor cavity

    International Nuclear Information System (INIS)

    Gold, R.; Roberts, J.H.; Ruddy, F.H.; Preston, C.C.; McElroy, W.N.

    1985-04-01

    Solid-state track recorder (SSTR) neutron dosimetry has been conducted in the Three-Mile Island Unit (TMI-2) reactor cavity (i.e., the annular gap between the pressure vessel and the biological shield) for nondestructive assessment of the fuel distribution. Two axial stringers were deployed in the annular gap with 17 SSTR dosimeters located on each stringer. SSTR experimental results reveal that neutron streaming, upward from the bottom of the reactor cavity region, dominates the observed neutron intensity. These absolute thermal neutron flux observations are consistent with the presence of a significant amount of fuel debris lying at the bottom of the reactor vessel. A conservative lower bound estimated from these SSTR data implies that there are at least 2 tonnes of fuel, which is roughly 4 fuel assemblies, at the bottom of the vessel. The existence of significant neutron streaming also explains the high count rate observed with the source range monitors (SRMs) that are located in the TMI-2 reactor cavity

  16. Percolation Cooling of the Three Mile Island Unit 2 Lower Head by Way of Thermal Cracking and Gap Formation

    International Nuclear Information System (INIS)

    Thomsen, K.L.

    2002-01-01

    Two partial models have been developed to elucidate the Three Mile Island Unit 2 lower head coolability by water percolation from above into the thermally cracking debris bed and into a gap between the debris and the wall. The bulk permeability of the cracked top crust is estimated based on simple fracture mechanics and application of Poiseuille's law to the fractures. The gap is considered as an abstraction representing an initially rugged interface, which probably expanded by thermal deformation and cracking in connection with the water ingress. The coupled flow and heat conduction problem for the top crust is solved in slab geometry based on the two-phase Darcy equations together with quasi-steady mass and energy conservation equations. The resulting water penetration depth is in good agreement with the depth of the so-called loose debris bed. The lower-head and bottom-crust problem is treated analogously by a two-dimensional axisymmetric model. The notion of a gap is maintained as a useful concept in the flow analysis. Simulations show that a central hot spot with a peak wall temperature of 1075 to 1100 deg. C can be obtained, but the quenching rates are not satisfactory. It is concluded that a three-dimensional model with an additional mechanism to explain the sudden water ingress to the hot spot center would be more appropriate

  17. Neutron dosimetry in the Three-Mile Island Unit 2 reactor cavity with solid-state track recorders

    International Nuclear Information System (INIS)

    Gold, R.; Roberts, J.H.; Ruddy, F.H.; Preston, C.C.; McElroy, W.N.; Rao, S.V.; Greenborg, J.; Fricke, V.R.

    1985-01-01

    Solid-state track recorder (SSTR) neutron dosimetry has been conducted in the Three-Mile Island Unit 2 (TMI-2) reactor cavity (i.e., the annular gap between the pressure vessel and the biological shield) for nondestructive assessment of the fuel distribution. Two axial stringers were deployed in the annular gap with 17 SSTR dosimeters located on each stringer. SSTR experimental results reveal that neutron streaming, upward from the bottom of the reactor cavity region, dominates the observed neutron intensity. These absolute thermal neutron flux observations are consistent with the presence of a significant amount of fuel debris lying at the bottom of the reactor vessel. A conservative lower bound estimated from these SSTR data implies that at least 2 tonnes of fuel, which is roughly 4 fuel assemblies, is lying at the bottom of the vessel. The existence of significant neutron streaming also explains the high count rate observed with the source range monitors (SRMs) that are located in the TMI-2 reactor cavity

  18. 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

  19. Evaluation of nuclear facility decommissioning projects. Three Mile Island Unit 2 reactor building decontamination. Summary status report. Volume 2

    International Nuclear Information System (INIS)

    Doerge, D.H.; Miller, R.L.; Scotti, K.S.

    1986-05-01

    This document summarizes information relating to decontamination of the Three Mile Island Unit 2 (TMI-2) reactor building. The report covers activities for the period of June 1, 1979 through March 29, 1985. The data collected from activity reports, reactor containment entry records, and other sources were entered into a computerized data system which permits extraction/manipulation of specific information which can be used in planning for recovery from an accident similar to that experienced at TMI-2 on March 28, 1979. This report contains summaries of man-hours, manpower, and radiation exposures incurred during decontamination of the reactor building. Support activities conducted outside of radiation areas are excluded from the scope of this report. Computerized reports included in this document are: a chronological summary listing work performed relating to reactor building decontamination for the period specified; and summary reports for each major task during the period. Each task summary is listed in chronological order for zone entry and subtotaled for the number of personnel entries, exposures, and man-hours. Manually-assembled table summaries are included for: labor and exposures by department and labor and exposures by major activity

  20. Assessment of extent and degree of thermal damage to polymeric materials in the Three Mile Island Unit 2 Reactor building

    International Nuclear Information System (INIS)

    Alvares, N.J.

    1985-06-01

    This paper describes assumptions and procedures used to perform thermal damage analysis caused by post loss-of-coolant-accident (LOCA) hydrogen deflagration at Three Mile Island Unit 2 Reactor. Examination of available photographic evidence yields data on the extent and range of thermal and burn damage. Thermal damage to susceptible material in accessible regions of the reactor building was distributed in non-uniform patterns. No clear explanation for non-uniformity was found in examined evidence, e.g., burned materials were adjacent to materials that appear similar but were not burned. Because these items were in proximity to vertical openings that extend the height of the reactor building, we assume the unburned materials preferentially absorbed water vapor during periods of high, local steam concentration. A control pendant from the polar crane located in the top of the reactor building sustained asymmetric burn damage of decreasing degree from top to bottom. Evidence suggests the polar-crane pendant side that experienced heaviest damage was exposed to intense radiant energy from a transient fire plume in the reactor containment volume. Simple hydrogen-fire-exposure tests and heat transfer calculations approximate the degree of damage found on inspected materials from the containment building and support for an estimated 8% pre-fire hydrogen

  1. A nuclear power unit with a Babcock type steam generating system-analysis of the break-down in the Three Mile Island power plant

    International Nuclear Information System (INIS)

    Werner, A.

    1980-01-01

    Installations of the primary and the secondary circuits and basic automatic control and protection systems for a nuclear power unit with Babcock type vertical, once-through steam generator are described. On this background the course of the break-down in the Three Mile Island power plant at Harrisburg is presented and analysed. (author)

  2. Socioeconomic impacts of nuclear generating stations: Nine Mile Point and Fitzpatrick case study. Technical report 1 Oct 78-4 Jan 82

    International Nuclear Information System (INIS)

    Branch, K.; Cochran, R.; Meale, R.

    1982-07-01

    The report documents a case study of the socioeconomic impacts of the construction and operation of the Nine Mile Point and Fitzpatrick nuclear power stations. 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

  3. Characterization of fuel distributions in the Three-Mile Island Unit 2 (TMI-2) reactor system by neutron and gamma-ray dosimetry

    International Nuclear Information System (INIS)

    Gold, R.; Roberts, J.H.; Ruddy, F.H.; Preston, C.C.; McNeece, J.P.; Kaiser, B.J.; McElroy, W.N.

    1984-04-01

    The resolution of technical issues generated by the accident at Three-Mile Island Unit 2 (TMI-2) will inevitably be of long range benefit. Determination of the fuel debris dispersal in the TMI-2 reactor system represents a major technical issue. In reactor recovery operations, such as for the safe handling and final disposal of TMI-2 waste, quantitative fuel assessments are being conducted throughout the reactor core and primary coolant system

  4. Power Dissipation Challenges in Multicore Floating-Point Units

    DEFF Research Database (Denmark)

    Liu, Wei; Nannarelli, Alberto

    2010-01-01

    , we analyze the impact of power dissipation in floating-point (FP) units and we consider different alternatives in the implementation of FP-division that lead to substantial energy savings. We compare the implementation of division in a Fused Multiply-Add (FMA) unit based on the Newton-Raphson...

  5. 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

  6. Evaluation of nuclear facility decommissioning projects. Three Mile Island Unit 2 reactor coolant system and systems decontamination. Summary status report. Volume 1

    International Nuclear Information System (INIS)

    Doerge, D.H.; Miller, R.L.; Scotti, K.S.

    1986-05-01

    This document summarizes information relating to the decontamination and restoration of the Three Mile Island Unit 2 reactor coolant system and other plant systems. Data have been collected from activity reports, reactor containment entry records, and other sources and entered in a computerized data system which permits extraction/manipulation of specific data which can be used in planning for recovery from a loss of coolant event similar to that experienced by the Three Mile Island Unit 2 on March 28, 1979. This report contains a summary of radiation exposures, manpower, and time spent in radiation areas during the referenced period. Support activities conducted outside of radiation areas are not included. Computer reports included are: A chronological listing of all activities related to decomtamination and restoration of the reactor coolant system and other plant systems for the period of April 5, 1979, through December 19, 1984; a summary of labor and exposures by department for the same time period; and summary reports for each major task undertaken in connection with this specific work scope during the referenced time period

  7. FIND: Douglas Point Nuclear Generating Station, Units 1 and 2

    International Nuclear Information System (INIS)

    Moore, M.M.

    1975-12-01

    This index is presented as a guide to microfiche items 1 through 136 in Docket 50448, which was assigned to Potomac Electric Power Company's Application for Licenses to construct and operate Douglas Point Nuclear Generating Station, Units 1 and 2. Information received from August, 1973 through July, 1975 is included

  8. Optimal Design of Fixed-Point and Floating-Point Arithmetic Units for Scientific Applications

    OpenAIRE

    Pongyupinpanich, Surapong

    2012-01-01

    The challenge in designing a floating-point arithmetic co-processor/processor for scientific and engineering applications is to improve the performance, efficiency, and computational accuracy of the arithmetic unit. The arithmetic unit should efficiently support several mathematical functions corresponding to scientific and engineering computation demands. Moreover, the computations should be performed as fast as possible with a high degree of accuracy. Thus, this thesis proposes algorithm, d...

  9. Three Mile Island

    International Nuclear Information System (INIS)

    Wood, M.S.; Shultz, S.M.

    1988-01-01

    This bibliography is divided into the following categories: Accident Overviews, Sequence and Causes; International Commentary and Reaction; Emergency Preparedness and Disaster Planning; Health Effects; Radioactive Releases and the Environment; Accident Investigations/Commissions; Nuclear Industry: Safety, Occupational, and Financial Issues; Media and Communications; Cleanup; Sociopolitical Response and Commentary; Restart; Legal Ramifications; Federal Documents: President's Commission on the Accident at Three Mile Island; Federal Documents: Nuclear Regulatory Commission; Federal Documents: United States Department of Energy; Federal Documents: Miscellaneous Reports; Pennsylvania State Documents; Federal and State Hearings; and Popular Literature

  10. An Asynchronous IEEE Floating-Point Arithmetic Unit

    Directory of Open Access Journals (Sweden)

    Joel R. Noche

    2007-12-01

    Full Text Available An asynchronous floating-point arithmetic unit is designed and tested at the transistor level usingCadence software. It uses CMOS (complementary metal oxide semiconductor and DCVS (differentialcascode voltage switch logic in a 0.35 µm process using a 3.3 V supply voltage, with dual-rail data andsingle-rail control signals using four-phase handshaking.Using 17,085 transistors, the unit handles single-precision (32-bit addition/subtraction, multiplication,division, and remainder using the IEEE 754-1985 Standard for Binary Floating-Point Arithmetic, withrounding and other operations to be handled by separate hardware or software. Division and remainderare done using a restoring subtractive algorithm; multiplication uses an additive algorithm. Exceptionsare noted by flags (and not trap handlers and the output is in single-precision.Previous work on asynchronous floating-point arithmetic units have mostly focused on single operationssuch as division. This is the first work to the authors' knowledge that can perform floating-point addition,multiplication, division, and remainder using a common datapath.

  11. Characterization of fuel distribution in the Three Mile Island Unit 2 (TMI-2) reactor system by neutron and gamma-ray dosimetry

    International Nuclear Information System (INIS)

    Gold, R.; Roberts, J.H.; Ruddy, F.H.; Preston, C.C.; McNeece, J.P.; Kaiser, B.J.; McElroy, W.N.

    1984-01-01

    Neutron and gamma-ray dosimetry are being used for nondestructive assessment of the fuel distribution throughout the Three Mile Island Unit 2 (TMI-2) reactor core region and primary cooling system. The fuel content of TMI-2 makeup and purification Demineralizer A has been quantified with Si(Li) continuous gamma-ray spectrometry and solid-state track recorder (SSTR) neutron dosimetry. For fuel distribution characterization in the core region, results from SSTR neutron dosimetry exposures in the TMI-2 reactor cavity are presented. These SSTR results are consistent with the presence of a significant amount of fuel debris, equivalent to several fuel assemblies or more, lying at the bottom of the reactor vessel. (Auth.)

  12. Flow-induced vibration analysis of Three Mile Island Unit-2 once-through steam generator tubes. Volume 1. Final report

    International Nuclear Information System (INIS)

    Johnson, J.R.; Brown, J.C.; Harris, C.E.; McGuinn, E.J.; Simonis, J.C.; Thoren, D.E.

    1981-06-01

    Tube responses to flow-induced vibration were measured in the top two spans and the tenth span in the B once-through steam generator at Three Mile Island, Unit 2. This program evaluated the effects of flow-induced biration of OTSG tubes during steady-state and transient operation. Twenty-three tubes were instrumented with accelerometers and strain gages in tubes located along the open lane, in the bundle, and at the tenth span. Tube displacements, frequencies, dynamic strains, and mode shapes were determined during steady-state and transient operation. Pressure sensors were installed in the OTSG to measure pressure fluctuations and plant parameters, which were recorded for correlation with tube response. Data analysis results indicate that the steady-state tube response increases with increasing reactor power, with the maximum response (12 mils peak to peak at midspan) at the outer perimeter of the generator in the 16th span

  13. 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

  14. Evaluation of nuclear facility decommissioning projects. Three Mile Island Unit 2. Radioactive waste and laundry shipments. Volume 9. Summary status report

    International Nuclear Information System (INIS)

    Doerge, D.H.; Miller, R.L.; Scotti, K.S.

    1986-05-01

    This document summarizes information concerning radioactive waste and laundry shipments from the Three Mile Island Nuclear Station Unit 2 to radioactive waste disposal sites and to protective clothing decontamination facilities (laundries) since the loss of coolant accident experienced on March 28, 1979. Data were collected from radioactive shipment records, summarized, and placed in a computerized data information retrieval/manipulation system which permits extraction of specific information. This report covers the period of April 9, 1979 to May 5, 1985. Included in this report are: waste disposal site locations, dose rates, curie content, waste description, container type and number, volumes and weights. This information is presented in two major categories: protective clothing (laundry) and radioactive waste. Each of the waste shipment reports is in chronological order

  15. Temporal trends in United States dew point temperatures

    Science.gov (United States)

    Robinson, Peter J.

    2000-07-01

    In this study, hourly data for the 1951-1990 period for 178 stations in the coterminous United States were used to establish temporal trends in dew point temperature. Although the data had been quality controlled previously (Robinson, 1998. Monthly variations of dew point temperatures in the coterminous United States. International Journal of Climatology 18: 1539-1556), comparisons of values between nearby stations suggested that instrumental changes, combined with locational changes, may have modified the results by as much as 1°C during the 40-year period. Nevertheless, seasonally averaged results indicated an increase over much of the area, of slightly over 1°C/100 years in spring and autumn, slightly less than this in summer. Winter displayed a drying of over 1°C/100 years. When only the 1961-1990 period was considered, the patterns were similar and trends increased by approximately 1-2°C/100 years, except in autumn, which displayed a slight drying. Analyses for specific stations indicated periods of both increasing and decreasing Td, the change between them varying with observation hour. No single change point was common over a wide area, although January commonly indicated maximum values early in the period in the east and west, and much later in the north-central portion. Rates of increase were generally higher in daytime than at night, especially in summer. Investigation of the inter-decadal differences in dew point, as a function of wind conditions, indicated that changes during calm conditions were commonly similar in magnitude to that of the overall average changes, suggesting an important role for the local hydrologic cycle in driving changes. Other inter-decadal changes could be attributed to the changes in the frequency and moisture content of invading air-streams. This was particularly clear for the changes in north-south flow in the interior.

  16. Three Mile Island accident

    International Nuclear Information System (INIS)

    Barre, B.; Olivier, E.; Roux, J.P.; Pelle, P.

    2010-01-01

    Deluded by equivocal instrumentation signals, operators at TMI-2 (Three Mile Island - unit 2) misunderstood what was going on in the reactor and for 2 hours were taking inadequate decisions that turned a reactor incident into a major nuclear event that led to the melting of about one third of the core. The TMI accident had worldwide impacts in the domain of nuclear safety. The main consequences in France were: 1) the introduction of the major accident approach and the reinforcement of crisis management; 2) the improvement of the reactor design, particularly that of the pressurizer valves; 3) the implementation of safety probabilistic studies; 4) a better taking into account of the feedback experience in reactor operations; and 5) a better taking into account of the humane factor in reactor safety. (A.C.)

  17. Reliability assessment of Indian Point Unit 3 containment structure

    International Nuclear Information System (INIS)

    Kawakami, J.; Hwang, H.; Chang, M.T.; Reich, M.

    1984-01-01

    In the current design criteria, the load combinations specified for design of concrete containment structures are in the deterministic formats. However, by applying the probability-based reliability method developed by BNL to the concrete containment structures designed according to the criteria, it is possible to evaluate the reliability levels implied in the current design criteria. For this purpose, the reliability analysis is applied to the Indian Point Unit No. 3 containment. The details of the containment structure such as the geometries and the rebar arrangements, etc., are taken from the working drawings and the final safety analysis reports. Three kinds of loads are considered in the reliability analysis. They are, dead load (D), accidental pressure due to a large LOCA (P), and earthquake ground acceleration (E). Reliability analysis of the containment subjected to all combinations of loads is performed. Results are presented in this report

  18. Laser Safety Evaluation of the MILES and Mini MILES Laser Emitting Components; TOPICAL

    International Nuclear Information System (INIS)

    AUGUSTONI, ARNOLD L.

    2002-01-01

    Laser safety evaluation and output emission measurements were performed (during October and November 2001) on SNL MILES and Mini MILES laser emitting components. The purpose, to verify that these components, not only meet the Class 1 (eye safe) laser hazard criteria of the CDRH Compliance Guide for Laser Products and 21 CFR 1040 Laser Product Performance Standard; but also meet the more stringent ANSI Std. z136.1-2000 Safe Use of Lasers conditions for Class 1 lasers that govern SNL laser operations. The results of these measurements confirmed that all of the Small Arms Laser Transmitters, as currently set (''as is''), meet the Class 1 criteria. Several of the Mini MILES Small Arms Transmitters did not. These were modified and re-tested and now meet the Class 1 laser hazard criteria. All but one System Controllers (hand held and rifle stock) met class 1 criteria for single trigger pulls and all presented Class 3a laser hazard levels if the trigger is held (continuous emission) for more than 5 seconds on a single point target. All units were Class 3a for ''aided'' viewing. These units were modified and re-tested and now meet the Class 1 hazard criteria for both ''aided'' as well as ''unaided'' viewing. All the Claymore Mine laser emitters tested are laser hazard Class 1 for both ''aided'' as well as ''unaided'' viewing

  19. Inland Waterway Mile Markers

    Data.gov (United States)

    Department of Homeland Security — Contains 11,201 sequential mile positions of navigable inland waterways and the Gulf Intracoastal Waterway. Records include eight fields; id, latitude, longitude,...

  20. 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

  1. 75 FR 16201 - FPL Energy Point Beach, LLC; Point Beach Nuclear Plant, Units 1 and 2; Exemption

    Science.gov (United States)

    2010-03-31

    ... NUCLEAR REGULATORY COMMISSION [Docket Nos. 50-266 and 50-301; NRC-2010-0123] FPL Energy Point Beach, LLC; Point Beach Nuclear Plant, Units 1 and 2; Exemption 1.0 Background FPL Energy Point Beach.... Borchardt (NRC) to M. S. Fertel (Nuclear Energy Institute) dated June 4, 2009. The licensee's request for an...

  2. Three Mile Island Unit 1 Main Steam Line Break Three-Dimensional Neutronics/Thermal-Hydraulics Analysis: Application of Different Coupled Codes

    International Nuclear Information System (INIS)

    D'Auria, Francesco; Moreno, Jose Luis Gago; Galassi, Giorgio Maria; Grgic, Davor; Spadoni, Antonino

    2003-01-01

    A comprehensive analysis of the double ended main steam line break (MSLB) accident assumed to occur in the Babcock and Wilcox Three Mile Island Unit 1 (TMI-1) has been carried out at the Dipartimento di Ingegneria Meccanica, Nucleare e della Produzione of the University of Pisa, Italy, in cooperation with the University of Zagreb, Croatia. The overall activity has been completed within the framework of the participation in the Organization for Economic Cooperation and Development-Committee on the Safety of Nuclear Installations-Nuclear Science Committee pressurized water reactor MSLB benchmark.Thermal-hydraulic system codes (various versions of Relap5), three-dimensional (3-D) neutronics codes (Parcs, Quabbox, and Nestle), and one subchannel code (Cobra) have been adopted for the analysis. Results from the following codes (or code versions) are assumed as reference:1. Relap5/mod3.2.2, beta version, coupled with the 3-D neutron kinetics Parcs code parallel virtual machine (PVM) coupling2. Relap5/mod3.2.2, gamma version, coupled with the 3-D neutron kinetics Quabbox code (direct coupling)3. Relap5/3D code coupled with the 3-D neutron kinetics Nestle code.The influence of PVM and of direct coupling is also discussed.Boundary and initial conditions of the system, including those relevant to the fuel status, have been supplied by Pennsylvania State University in cooperation with GPU Nuclear Corporation (the utility, owner of TMI) and the U.S. Nuclear Regulatory Commission. The comparison among the results obtained by adopting the same thermal-hydraulic nodalization and the coupled code version is discussed in this paper.The capability of the control rods to recover the accident has been demonstrated in all the cases as well as the capability of all the codes to predict the time evolution of the assigned transient. However, one stuck control rod caused some 'recriticality' or 'return to power' whose magnitude is largely affected by boundary and initial conditions

  3. Three Mile Island revisited

    International Nuclear Information System (INIS)

    MacLeod, G.K.

    1986-01-01

    The accident at Three Mile Island proved that the Pennsylvania Department of Health lacked the tools to deal with the serious health consequences that occurred during and after this emergency. Despite the relative safety of nuclear power generation, we must be better prepared for the health and medical consequences of serous radiation emergencies. The author reviews the Three Mile Island accident through the eyes of newspaper reporters

  4. 75 FR 14206 - FPL Energy Point Beach, LLC; Point Beach Nuclear Plant, Units 1 and 2; Environmental Assessment...

    Science.gov (United States)

    2010-03-24

    ... NUCLEAR REGULATORY COMMISSION [Docket Nos. 50-266 And 50-301; NRC-2010-0123 FPL Energy Point Beach, LLC; Point Beach Nuclear Plant, Units 1 and 2; Environmental Assessment and Finding of No Significant Impact The U.S. Nuclear Regulatory Commission (NRC) is considering issuance of an Exemption, pursuant to...

  5. On Point: The United States Army in Operation Iraqi Freedom

    Science.gov (United States)

    2004-01-01

    to retain operational context. Moreover, times noted in the text have been adjusted from Greenwich Mean Time (“ Zulu ”) to local Kuwait time (+ 3...TF 1-64 AR unit history is composed of short narratives for each subordinate unit. Most cite times in zulu . 34. Ibid. 35. Ibid. Numbers of enemy...places in the world. Inside the city cemetery is the Tomb of Ali, son-in-law and cousin to Mohammed and founder of the Shiite sect. Coalition leaders

  6. 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

  7. Final environmental statement related to operation of Indian Point Nuclear Generating Plant, Unit No. 3: (Docket No. 50-286): Volume 1

    International Nuclear Information System (INIS)

    1975-02-01

    The proposed action is the issuance of a license to consolidated Edison Company of New York, Inc., for the operation of the Indian Point Nuclear Generating Plant, Unit No. 3, located in the State of New York, Westchester County, Village of Buchanan, 24 miles north of the New York City boundary line. Although the present action is the issuance of an operating license for Unit No. 3, this Statement considers the environmental impacts from simultaneous operation of all three Units. A Final Environmental Statement has been issued for Unit No. 2. Furthermore, in view of the proximity to the Indian Point site of existing and presently proposed power plants on the Hudson River, the cumulative environmental benefits and impacts of the plants within a 30-mile reach of the river have been assessed. The proposed action is interreleated to other actions taken by other Federal agencies such as the Environmental Protection Agency, in regard to granting or denying application for discharge permits under the National Pollutant Discharge Elimination System (NPDES) instituted through the Federal Water Pollution Control Act Amendments of 1972, and the Federal Power Commission, in licensing of other facilities on the Hudson River. 128 figs., 210 tabs

  8. Analysis of steam-generator tube-rupture events combined with auxiliary-feedwater control-system failure for Three Mile Island-Unit 1 and Zion-Unit 1 pressurized water reactors

    International Nuclear Information System (INIS)

    Nassersharif, B.

    1986-01-01

    A steam-generator tube-rupture (SGTR) event combined with loss of all offsite alternating-current power and failure of the auxiliary-feedwater (AFW) control system has been investigated for the Three Mile Island-Unit 1 (TMI-1) and Zion-Unit 1 (Zion-1) pressurized water reactors. The Transient Reactor Analysis Code was used to simulate the accident sequence for each plant. The objectives of the study were to predict the plant transient response with respect to tube-rupture flow termination, extent of steam generator overfill, and thermal-hydraulic conditions in the steam lines. Two transient cases were calculated: (1) a TMI-1 SGTR and runaway-AFW transient, and (2) a Zion-1 SGTR and runaway-AFW transient. Operator actions terminated the tube-rupture flow by 1342 s (22.4 min) and 1440 s (24.0 min) for TMI-1 and Zion-1, respectively, but AFW injection was continued. The damaged steam generator (DSG) overfilled by 1273 s (21.2 min) for the TMI-1 calculation and by 1604 s (26.7 min) for the Zion-1 calculation. The DSG steam lines were completely filled by 1500 s (25 min) and 2000 s (33.3 min) for TMI-1 and Zion-1, respectively. The maximum subcooling in the steam lines was approx.63 K (approx.113 0 F) for TMI-1 and approx.44 K (approx.80 0 F) for Zion-1

  9. 77 FR 41454 - Entergy Nuclear Indian Point Unit 2, LLC, Entergy Nuclear Indian Point Unit 3, LLC, Entergy...

    Science.gov (United States)

    2012-07-13

    ... at the Indian Point site. Such effects may include human health, biological, cultural, economic, or..., process, recycle, and dispose of gaseous, liquid, and solid wastes that contain radioactive material in a... within NRC regulatory limits and, therefore, would not be significant. Accident Doses to Members of the...

  10. 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

  11. Corrective action investigation plan for Corrective Action Unit Number 423: Building 03-60 Underground Discharge Point, Tonopah Test Range, Nevada

    International Nuclear Information System (INIS)

    1997-01-01

    This Corrective Action Investigation Plan (CAIP) contains the environmental sample collection objectives and the criteria for conducting site investigation activities at Corrective Action Unit (CAU) Number 423, the Building 03-60 Underground Discharge Point (UDP), which is located in Area 3 at the Tonopah Test Range (TTR). The TTR, part of the Nellis Air Force Range, is approximately 225 kilometers (140 miles) northwest of Las Vegas, Nevada. CAU Number 423 is comprised of only one Corrective Action Site (CAS) which includes the Building 03-60 UDP and an associated discharge line extending from Building 03-60 to a point approximately 73 meters (240 feet) northwest. The UDP was used between approximately 1965 and 1990 to dispose of waste fluids from the Building 03-60 automotive maintenance shop. It is likely that soils surrounding the UDP have been impacted by oil, grease, cleaning supplies and solvents as well as waste motor oil and other automotive fluids released from the UDP

  12. Corrective action investigation plan for Corrective Action Unit Number 423: Building 03-60 Underground Discharge Point, Tonopah Test Range, Nevada

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-10-27

    This Corrective Action Investigation Plan (CAIP) contains the environmental sample collection objectives and the criteria for conducting site investigation activities at Corrective Action Unit (CAU) Number 423, the Building 03-60 Underground Discharge Point (UDP), which is located in Area 3 at the Tonopah Test Range (TTR). The TTR, part of the Nellis Air Force Range, is approximately 225 kilometers (140 miles) northwest of Las Vegas, Nevada. CAU Number 423 is comprised of only one Corrective Action Site (CAS) which includes the Building 03-60 UDP and an associated discharge line extending from Building 03-60 to a point approximately 73 meters (240 feet) northwest. The UDP was used between approximately 1965 and 1990 to dispose of waste fluids from the Building 03-60 automotive maintenance shop. It is likely that soils surrounding the UDP have been impacted by oil, grease, cleaning supplies and solvents as well as waste motor oil and other automotive fluids released from the UDP.

  13. A full ranking for decision making units using ideal and anti-ideal points in DEA.

    Science.gov (United States)

    Barzegarinegad, A; Jahanshahloo, G; Rostamy-Malkhalifeh, M

    2014-01-01

    We propose a procedure for ranking decision making units in data envelopment analysis, based on ideal and anti-ideal points in the production possibility set. Moreover, a model has been introduced to compute the performance of a decision making unit for these two points through using common set of weights. One of the best privileges of this method is that we can make ranking for all decision making units by solving only three programs, and also solving these programs is not related to numbers of decision making units. One of the other advantages of this procedure is to rank all the extreme and nonextreme efficient decision making units. In other words, the suggested ranking method tends to seek a set of common weights for all units to make them fully ranked. Finally, it was applied for different sets holding real data, and then it can be compared with other procedures.

  14. Closure Report for Corrective Action Unit 262: Area 25 Septic Systems and Underground Discharge Point, Nevada Test Site, Nevada

    International Nuclear Information System (INIS)

    Tobiason, D. S.

    2003-01-01

    This Closure Report (CR) documents the activities undertaken to close Corrective Action Unit (CAU) 262: Area 25 Septic Systems and Underground Discharge Point, in accordance with the Federal Facility Agreement and Consent Order (FFACO) of 1996. Site closure was performed in accordance with the Nevada Division of Environmental Protection (NDEP)-approved Corrective Action Plan (CAP) for CAU 262 (U.S. Department of Energy, National Nuclear Security Administration Nevada Operations Office [NNSA/NV, 2002a]). CAU 262 is located at the Nevada Test Site (NTS) approximately 105 kilometers (65 miles) northwest of Las Vegas, Nevada. CAU 262 consists of the following nine Corrective Action Sites (CASs) located in Area 25 of the NTS: CAS 25-02-06, Underground Storage tank CAS 25-04-06, Septic Systems A and B CAS 25-04-07, Septic System CAS 25-05-03, Leachfield CAS 25-05-05, Leachfield CAS 25-05-06, Leachfield CAS 25-05-08, Radioactive Leachfield CAS 25-05-12, Leachfield CAS 25-51-01, Dry Well

  15. Three Mile Island update

    International Nuclear Information System (INIS)

    Snyder, B.J.

    1984-01-01

    Almost six years after the accident at Three Mile Island-2, cleanup operations are proceeding and the financial condition of the owners has improved. The author reviews some of the cleanup activities and notes the milestones ahead before reaching the September, 1988 target date for completion. A decision to decommission or refurbish will follow the completion of fuel removal activities in 1987. The cleanup has produced considerable data and useful information. In particular, the experience of large-scale decontamination and radioactive waste processing, along with information on fission product transport, is relevant for maintenance and safe operation of other plants. Both macro- and microscopic examination of the core could help in developing safer reactors in the future. 3 figures, 1 table

  16. 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

  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). 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

  18. 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

  19. 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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    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)

  20. 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

  1. Three Mile Island

    International Nuclear Information System (INIS)

    2015-01-01

    This document addresses the Three Mile Island accident which resulted in a core partial fusion. It recalls that other reactors of this plant are still being operated. The operation of this PWR is briefly described, and the main events and phases of the accident are briefly presented (failure of the secondary circuit supply pump, failure of a pressurizer component and wrong information about it, mistaken reaction in the control room, core partial fusion due to insufficient cooling means). It shows that the accident occurred because of a combination of technical failures and human mistakes. This situation has put operator education and organisation into question again. The main actors and their mistakes, weaknesses and responsibilities are indicated: Metropolitan Edison (the operator), the NRC (the US nuclear safety authority). Some key figures are recalled, as well as the context of construction of the plant. Impacts and consequences are reviewed: implementation of new standards, population concern. The document outlines that radioactive exposures due to the accident were minor

  2. Corrective Action Plan for Corrective Action Unit 262: Area 25 Septic Systems and Underground Discharge Point, Nevada Test Site, Nevada

    International Nuclear Information System (INIS)

    K. B. Campbell email = campbek@nv.doe.gov

    2002-01-01

    This Corrective Action Plan (CAP) provides selected corrective action alternatives and proposes the closure methodology for Corrective Action Unit (CAU) 262, Area 25 Septic Systems and Underground Discharge Point. CAU 262 is identified in the Federal Facility Agreement and Consent Order (FFACO) of 1996. Remediation of CAU 262 is required under the FFACO. CAU 262 is located in Area 25 of the Nevada Test Site (NTS), approximately 100 kilometers (km) (62 miles [mi]) northwest of Las Vegas, Nevada. The nine Corrective Action Sites (CASs) within CAU 262 are located in the Nuclear Rocket Development Station complex. Individual CASs are located in the vicinity of the Reactor Maintenance, Assembly, and Disassembly (R-MAD); Engine Maintenance, Assembly, and Disassembly (E-MAD); and Test Cell C compounds. CAU 262 includes the following CASs as provided in the FFACO (1996); CAS 25-02-06, Underground Storage Tank; CAS 25-04-06, Septic Systems A and B; CAS 25-04-07, Septic System; CAS 25-05-03, Leachfield; CAS 25-05-05, Leachfield; CAS 25-05-06, Leachfield; CAS 25-05-08, Radioactive Leachfield; CAS 25-05-12, Leachfield; and CAS 25-51-01, Dry Well. Figures 2, 3, and 4 show the locations of the R-MAD, the E-MAD, and the Test Cell C CASs, respectively. The facilities within CAU 262 supported nuclear rocket reactor engine testing. Activities associated with the program were performed between 1958 and 1973. However, several other projects used the facilities after 1973. A significant quantity of radioactive and sanitary waste was produced during routine operations. Most of the radioactive waste was managed by disposal in the posted leachfields. Sanitary wastes were disposed in sanitary leachfields. Septic tanks, present at sanitary leachfields (i.e., CAS 25-02-06,2504-06 [Septic Systems A and B], 25-04-07, 25-05-05,25-05-12) allowed solids to settle out of suspension prior to entering the leachfield. Posted leachfields do not contain septic tanks. All CASs located in CAU 262 are

  3. 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

  4. Environmental assessment for decontamination of the Three Mile Island Unit 2 reactor building atmosphere. Addendum 2. Draft NRC staff report for public comment

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1980-04-01

    The reactor building purge system is an existing system originally installed for purging the reactor building atmosphere during normal operation or maintenance conditions. Use of the reactor building purge system in conjunction with the hydrogen control subsystem evaluated in Section 6.1 represents a variation in the purging alternative for decontaminating the Unit 2 reactor building atmosphere. This variation in the purging alternative would function only under meteorological conditions favorable to atmospheric dispersion. The reactor building purge system is capable of purging the building at flow rates of 5,000-50,000 cfm. Actual purge rates authorized during any time interval would be dependent on meteorological conditions and reactor building concentrations. Like the hydrogen control subsystem, this system would remove reactor building atmosphere through a filter system and discharge it through the 160-ft plant vent stack to the environment. The advantage of using the reactor building purge system in conjunction with the hydrogen control system is that it could decontaminate the reactor building atmosphere in a total elapsed purge time as short as approximately 5 days, as compared with the 60 days that would be required if the hydrogen purge subsystem were used alone. Use of this variation in the purge alternative would result in the release of radioactive materials to the environment. However, calculations based on actual meteorological and release-rate data would be used to monitor radioactive releases so that they do not exceed the requirements of 10 CFR Part 20, the design objectives of 10 CFR Part 50, Appendix 1 and the applicable requirements of 40 CFR 190.10.

  5. Acoustic monitoring systems tests at Indian Point Unit 1. Final report

    International Nuclear Information System (INIS)

    Smith, J.R.; Rao, G.V.; Craig, J.

    1979-12-01

    This report describes the results of a program to test acoustic monitoring systems on Indian Point Unit No. 1 under actual plant operating conditions, less the reactor core. The two types of systems evaluated were the monitoring of acoustic emissions generated by growing flaws and the monitoring of acoustic signals from leaks

  6. 46 CFR 7.120 - Mexican/United States border to Point Fermin, CA.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 1 2010-10-01 2010-10-01 false Mexican/United States border to Point Fermin, CA. 7.120 Section 7.120 Shipping COAST GUARD, DEPARTMENT OF HOMELAND SECURITY PROCEDURES APPLICABLE TO THE PUBLIC... from the southerly tower of the Coronado Hotel in approximate position latitude 32°40.8′ N. longitude...

  7. 77 FR 34211 - Modification of Multiple Compulsory Reporting Points; Continental United States, Alaska and Hawaii

    Science.gov (United States)

    2012-06-11

    ... DEPARTMENT OF TRANSPORTATION Federal Aviation Administration 14 CFR Part 71 [Docket No. FAA-2012-0130; Airspace Docket No. 12-AWA-2] RIN 2120-AA66 Modification of Multiple Compulsory Reporting Points; Continental United States, Alaska and Hawaii AGENCY: Federal Aviation Administration (FAA), DOT. ACTION: Final...

  8. The Three Mile Island Disaster.

    Science.gov (United States)

    Crosby, Emeral

    1980-01-01

    For the past decade, education has been experiencing meltdown, explosions, radiation leaks, heat pollution, and management crises, just like the Three Mile Island disaster. This article offers suggestions on how to deal with these problems. (Author/LD)

  9. Diabetes MILES--The Netherlands

    DEFF Research Database (Denmark)

    Nefs, Giesje; Bot, Mariska; Browne, Jessica L

    2012-01-01

    BACKGROUND: As the number of people with diabetes is increasing rapidly worldwide, a more thorough understanding of the psychosocial aspects of living with this condition has become an important health care priority. While our knowledge has grown substantially over the past two decades with respect...... to the physical, emotional and social difficulties that people with diabetes may encounter, many important issues remain to be elucidated. Under the umbrella of the Diabetes MILES (Management and Impact for Long-term Empowerment and Success) Study International Collaborative, Diabetes MILES--The Netherlands aims...... to examine how Dutch adults with diabetes manage their condition and how it affects their lives. Topics of special interest in Diabetes MILES--The Netherlands include subtypes of depression, Type D personality, mindfulness, sleep and sexual functioning. METHODS/DESIGN: Diabetes MILES--The Netherlands...

  10. Three Mile Island Accident Data

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — Three Mile Island Accident Data consists of mostly upper air and wind observations immediately following the nuclear meltdown occurring on March 28, 1979, near...

  11. Inherently safe SNR shutdown system with Curie point controlled sensor/switch unit

    International Nuclear Information System (INIS)

    Mueller, K.; Norajitra, P.; Reiser, H.

    1987-02-01

    Inherent shutdown due to increase in the sodium temperature at the core outlet is triggered by interruption of the current supply to the electromagnet coupling of absorber elements via curie point controlled sensor/switch units. These switches are arranged above suitable fuel element positions and spatially independent of the shutdown elements. Compared with other similar systems very short response times are achieved. A prototype switch unit has already undergone extensive testing. These tests have confirmed that switching takes place in a very narrow temperature range. (orig./HP) [de

  12. Three Mile Island accident. Local reactions

    International Nuclear Information System (INIS)

    1979-04-01

    Local reactions to the Three Mile Island are presented as well as newspaper articles covering this accident. In addition, this document presents a plan to set forth procedures and guidelines to be utilized by authorized emergency personnel in Middletown, Royalton, Londonderry Township, and Lower Swatara Township located in Pennsylvania, United States. The plan will provide for the orderly and efficient handling of area residents during time of serious incidents emanating from Three Mile Island facility. Emergency personnel in each community should be familiar with portions of the plan that pertain to the other near-by communities. The cooperation of all parties concerned will insure that a maximum effort is being made to help protect the public against injuries and v/ill in some cases keep any damages to communities to a minimum

  13. 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

  14. Reliability assessment of Indian Point Unit 3 containment structure under combined loads

    International Nuclear Information System (INIS)

    Hwang, H.; Shinozuka, M.; Kawakami, J.; Reich, M.

    1984-01-01

    In the current design criteria, the load combinations specified for design of concrete containment structures are in the deterministic format. However, by applying the probability-based reliability analysis method developed by BNL to the concrete containment structures designed according to the criteria, it is possible to evaluate the reliability levels implied in the current design criteria. For this purpose, the reliability analysis is applied to the Indian Point Unit No. 3 containment. The details of the containment structure such as the geometries and the rebar arrangements, etc., are taken from the working drawings and the Final Safety Analysis Report. Three kinds of loads are considered in the reliability analysis. They are, dead load, accidental pressure due to a large LOCA, and earthquake ground acceleration. This paper presents the reliability analysis results of the Indian Point Unit 3 containment subjected to all combinations of loads

  15. Nonpoint and Point Sources of Nitrogen in Major Watersheds of the United States

    Science.gov (United States)

    Puckett, Larry J.

    1994-01-01

    Estimates of nonpoint and point sources of nitrogen were made for 107 watersheds located in the U.S. Geological Survey's National Water-Quality Assessment Program study units throughout the conterminous United States. The proportions of nitrogen originating from fertilizer, manure, atmospheric deposition, sewage, and industrial sources were found to vary with climate, hydrologic conditions, land use, population, and physiography. Fertilizer sources of nitrogen are proportionally greater in agricultural areas of the West and the Midwest than in other parts of the Nation. Animal manure contributes large proportions of nitrogen in the South and parts of the Northeast. Atmospheric deposition of nitrogen is generally greatest in areas of greatest precipitation, such as the Northeast. Point sources (sewage and industrial) generally are predominant in watersheds near cities, where they may account for large proportions of the nitrogen in streams. The transport of nitrogen in streams increases as amounts of precipitation and runoff increase and is greatest in the Northeastern United States. Because no single nonpoint nitrogen source is dominant everywhere, approaches to control nitrogen must vary throughout the Nation. Watershed-based approaches to understanding nonpoint and point sources of contamination, as used by the National Water-Quality Assessment Program, will aid water-quality and environmental managers to devise methods to reduce nitrogen pollution.

  16. Corrective Action Investigation Plan for Corrective Action Unit No. 423: Building 03-60 Underground Discharge Point, Tonopah Test Range, Nevada

    Energy Technology Data Exchange (ETDEWEB)

    DOE/NV

    1997-10-01

    This Corrective Action Investigation Plan (CAIP) has been developed in accordance with the Federal Facility Agreement and Consent Order (FFACO) that was agreed to by the US Department of Energy, Nevada Operations Office (DOE/NV), the State of Nevada Division of Environmental Protection (NDEP), and the US Department of Defense. The CAIP is a document that provides or references all of the specific information for investigation activities associated with Corrective Action Units (CAUS) or Corrective Action Sites (CASs) (FFACO, 1996). As per the FFACO (1996), CASs are sites potentially requiring corrective action(s) and may include solid waste management units or individual disposal or release sites. Corrective Action Units consist of one or more CASs grouped together based on geography, technical similarity, or agency responsibility for the purpose of determining corrective actions. This CAIP contains the environmental sample collection objectives and the criteria for conducting site investigation activities at CAU No. 423, the Building 03-60 Underground Discharge Point (UDP), which is located in Area 3 at the Tonopah Test Range (TTR). The TTR, part of the Nellis Air Force Range, is approximately 225 kilometers (km) (140 miles [mi]) northwest of Las Vegas, Nevada (Figures 1-1 and 1-2). Corrective Action Unit No. 423 is comprised of only one CAS (No. 03-02-002-0308), which includes the Building 03-60 UDP and an associated discharge line extending from Building 03-60 to a point approximately 73 meters (m) (240 feet [ft]) northwest as shown on Figure 1-3.

  17. Three Mile Island: prologue or epilogue

    International Nuclear Information System (INIS)

    Martin, D.

    1980-01-01

    This book contains a minute-by-minute account of the opening hours of the Three Mile Island accident. The testimony of technicians in the plant, people in the state emergency system, and federal observers given before the President's Commission, Congress, and the Pennsylvania Select Committee is documented here. Basic information about the theory and structure of a reactor is explained so clearly that the reader grasps the full meaning of the mechanical failure at Three Mile Island. As the development of the accident is chronicled, details of the governmental response are given. Particular attention is focused on communication difficulties between the state and federal government and on jurisdictional disputes among agencies involved in emergency response and public health. The licensing and inspection processes for nuclear reactors is described, and in particular, the history of Three Mile Island's Unit II, to elucidate the weaknesses in the Nuclear Regulatory Commissions's safety procedures. The qualifications and training requirements for nuclear powerplant operators are also examined. Beyond structural and regulatory problems, the author argues that reactors can never be made fail-safe; the assumption that we can envision all possible combinations of multiple system failures is unreasonable. We must then decide whether the benefits of nuclear energy warrant the risks

  18. Understanding Victims of Technological Disaster: Beliefs and Worries of Three Mile Island.

    Science.gov (United States)

    Prince-Embury, Sandra; Rooney, James

    The primary purpose of the present study was to examine how prevalent were concerns about restarting Three Mile Island nuclear reactor Unit I among people within a five-mile radius of the plant four years after the accident involving reactor Unit II. Also explored were concerns related to expectations about the restart of Unit I, perception of…

  19. Final environmental impact statement for the construction and operation of an independent spent fuel storage installation to store the Three Mile Island Unit 2 spent fuel at the Idaho National Engineering and Environmental Laboratory. Docket Number 72-20

    International Nuclear Information System (INIS)

    1998-03-01

    This Final Environmental Impact Statement (FEIS) contains an assessment of the potential environmental impacts of the construction and operation of an Independent Spent Fuel Storage Installation (ISFSI) for the Three Mile Island Unit 2 (TMI-2) fuel debris at the Idaho National Engineering and Environmental laboratory (INEEL). US Department of Energy-Idaho Operations Office (DOE-ID) is proposing to design, construct, and operate at the Idaho Chemical Processing Plant (ICPP). The TMI-2 fuel debris would be removed from wet storage, transported to the ISFSI, and placed in storage modules on a concrete basemat. As part of its overall spent nuclear fuel (SNF) management program, the US DOE has prepared a final programmatic environmental impact statement (EIS) that provides an overview of the spent fuel management proposed for INEEL, including the construction and operation of the TMI-2 ISFSI. In addition, DOE-ID has prepared an environmental assessment (EA) to describe the environmental impacts associated with the stabilization of the storage pool and the construction/operation of the ISFSI at the ICPP. As provided in NRC's NEPA procedures, a FEIS of another Federal agency may be adopted in whole or in part in accordance with the procedures outlined in 40 CFR 1506.3 of the regulations of the Council on Environmental Quality (CEQ). Under 40 CFR 1506.3(b), if the actions covered by the original EIS and the proposed action are substantially the same, the agency adopting another agency's statement is not required to recirculate it except as a final statement. The NRC has determined that its proposed action is substantially the same as actions considered in DOE's environmental documents referenced above and, therefore, has elected to adopt the DOE documents as the NRC FEIS

  20. Three Mile Island accident technical support

    International Nuclear Information System (INIS)

    Long, R.L.; Crimmins, T.M.; Lowe, W.W.

    1981-01-01

    A large number of technical support personnel were required to respond to the Three Mile Island Unit 2 (TMI-2) accident of March 28, 1979. Under the leadership of General Public Utilities personnel, onsite (round-the-clock shift) technical support began the evening of March 29 and within a week the TMI Recovery Organization incorporated all of the essential technical capability to implement the Base Plan for Cooldown, manage the radioactive waste problem, and begin the steps toward long-range plant recovery. These steps toward recovery are described in some detail. 1 refs

  1. A New Test Unit for Disintegration End-Point Determination of Orodispersible Films.

    Science.gov (United States)

    Low, Ariana; Kok, Si Ling; Khong, Yuet Mei; Chan, Sui Yung; Gokhale, Rajeev

    2015-11-01

    No standard time or pharmacopoeia disintegration test method for orodispersible films (ODFs) exists. The USP disintegration test for tablets and capsules poses significant challenges for end-point determination when used for ODFs. We tested a newly developed disintegration test unit (DTU) against the USP disintegration test. The DTU is an accessory to the USP disintegration apparatus. It holds the ODF in a horizontal position, allowing top-view of the ODF during testing. A Gauge R&R study was conducted to assign relative contributions of the total variability from the operator, sample or the experimental set-up. Precision was compared using commercial ODF products in different media. Agreement between the two measurement methods was analysed. The DTU showed improved repeatability and reproducibility compared to the USP disintegration system with tighter standard deviations regardless of operator or medium. There is good agreement between the two methods, with the USP disintegration test giving generally longer disintegration times possibly due to difficulty in end-point determination. The DTU provided clear end-point determination and is suitable for quality control of ODFs during product developmental stage or manufacturing. This may facilitate the development of a standardized methodology for disintegration time determination of ODFs. © 2015 Wiley Periodicals, Inc. and the American Pharmacists Association.

  2. Change-Point and Trend Analysis on Annual Maximum Discharge in Continental United States

    Science.gov (United States)

    Serinaldi, F.; Villarini, G.; Smith, J. A.; Krajewski, W. F.

    2008-12-01

    Annual maximum discharge records from 36 stations representing different hydro-climatic regimes in the continental United States with at least 100 years of records are used to investigate the presence of temporal trends and abrupt changes in mean and variance. Change point analysis is performed by means of two non- parametric (Pettitt and CUSUM), one semi-parametric (Guan), and two parametric (Rodionov and Bayesian Change Point) tests. Two non-parametric (Mann-Kendall and Spearman) and one parametric (Pearson) tests are applied to detect the presence of temporal trends. Generalized Additive Model for Location Scale and Shape (GAMLSS) models are also used to parametrically model the streamflow data exploiting their flexibility to account for changes and temporal trends in the parameters of distribution functions. Additionally, serial correlation is assessed in advance by computing the autocorrelation function (ACF), and the Hurst parameter is estimated using two estimators (aggregated variance and differenced variance methods) to investigate the presence of long range dependence. The results of this study indicate lack of long range dependence in the maximum streamflow series. At some stations the authors found a statistically significant change point in the mean and/or variance, while in general they detected no statistically significant temporal trends.

  3. 75 FR 77010 - Nextera Energy Point Beach, LLC; Point Beach Nuclear Plant, Units 1 and 2, Draft Environmental...

    Science.gov (United States)

    2010-12-10

    ... waste is low-level radioactive waste which includes sludge, oily waste, bead resin, spent filters, and... Impact of Transportation of Fuel and Waste to and from One Light-Water-Cooled Nuclear Power Reactor..., wetlands, and open areas. Each of the two units at PBNP use Westinghouse pressurized water reactors...

  4. The Three Mile Island crisis

    International Nuclear Information System (INIS)

    Houts, P.S.; Cleary, P.D.; Hu, T.W.

    1988-01-01

    Since the March 1979 accident at the Three Mile Island (TMI) nuclear power plant, many studies have assessed its impacts. Compiled and summarized in this book are the results of five related surveys, all aimed at the scientific assessment of the psycho-socio-economic behavior of the residents around the TMI facility. These studies are based on a randomly selected, large sample of the population (with telephones) around TMI

  5. Three Mile Island accident. Local reactions; L'accident de Three Mile Island. Reactions locales

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1979-04-15

    Local reactions to the Three Mile Island are presented as well as newspaper articles covering this accident. In addition, this document presents a plan to set forth procedures and guidelines to be utilized by authorized emergency personnel in Middletown, Royalton, Londonderry Township, and Lower Swatara Township located in Pennsylvania, United States. The plan will provide for the orderly and efficient handling of area residents during time of serious incidents emanating from Three Mile Island facility. Emergency personnel in each community should be familiar with portions of the plan that pertain to the other near-by communities. The cooperation of all parties concerned will insure that a maximum effort is being made to help protect the public against injuries and v/ill in some cases keep any damages to communities to a minimum.

  6. Corrective Action Investigation Plan for Corrective Action Unit 406: Area 3 Building 03-74 and Building 03-58 Under ground Discharge Points and Corrective Action Unit 429: Area 3 Building 03-55 and Area 9 Building 09-52 Underground Discharge Points, Tonopah Test Range, Nevada

    Energy Technology Data Exchange (ETDEWEB)

    DOE/NV

    1999-05-20

    This Corrective Action Investigation Plan (CAIP) has been developed in accordance with the Federal Facility Agreement and Consent Order (FFACO) that was agreed to by the US Department of Energy, Nevada Operations Office (DOE/NV); the State of Nevada Division of Environmental Protection (NDEP); and the US Department of Defense (FFACO, 1996). The CAIP is a document that provides or references all of the specific information for investigation activities associated with Corrective Action Units (CAUs) or Corrective Action Sites (CASs). According to the FFACO (1996), CASs are sites potentially requiring corrective action(s) and may include solid waste management units or individual disposal or release sites. Corrective Action Units consist of one or more CASs grouped together based on geography, technical similarity, or agency responsibility for the purpose of determining corrective actions. This CAIP contains the environmental sample collection objectives and the criteria for conducting site investigation activities at the Underground Discharge Points (UDPs) included in both CAU 406 and CAU 429. The CAUs are located in Area 3 and Area 9 of the Tonopah Test Range (TTR). The TTR, included in the Nellis Air Force Range, is approximately 255 kilometers (km) (140 miles [mi]) northwest of Las Vegas, Nevada.

  7. Point-of-purchase tobacco environments and variation by store type--United States, 1999.

    Science.gov (United States)

    2002-03-08

    To promote its products, the tobacco industry spent $8.2 billion on marketing in 1999, an increase of $1.5 billion over the previous year. Tobacco advertising in various media increases tobacco consumption and adolescents are more susceptible than adults to being influenced by some forms of tobacco advertising. To describe the retail tobacco advertising and marketing environment, researchers from the Robert Wood Johnson Foundation-sponsored ImpacTeen Project collected and analyzed store observation data in 163 communities throughout the United States. This report summarizes the extent of point-of-purchase (POP) tobacco advertising and marketing found in various types of stores. The findings in this report indicate that certain retail environments frequented by teenagers heavily promote tobacco use. To reduce demand for tobacco products among adolescents, public health efforts should address POP environment exposure to tobacco advertising and marketing.

  8. RETRAN applications in pressurized thermal shock analysis of turkey point units 3 and 4

    International Nuclear Information System (INIS)

    Arpa, J.; Fatemi, A.S.; Mathavan, S.K.

    1985-01-01

    A methodology to assess the impact of overcooling transients on vessel wall integrity with respect to pressurized thermal shock conditions has been developed at Florida Power and Light Company for the Turkey Point Nuclear Units. Small break loss-of-coolant and small steamline break events have been simulated with the RETRAN code. Highly conservative assumptions, such as engineered safeguards with minimum temperature and maximum flow, have been made to maximize cooldown and thermal stress in the vessel wall. Temperatures, pressures, and flows obtained with RETRAN provide input for stress and fracture mechanics analyses that evaluate reactor vessel integrity. The results of the RETRAN analyses compare well with generic calculations performed by the Westinghouse Owners Group for a similar type of plant

  9. Effects of shutdown chemistry on steam generator radiation levels at Point Beach Unit 2. Interim report

    International Nuclear Information System (INIS)

    Kormuth, J.W.

    1982-05-01

    A refueling shutdown chemistry test was conducted at a PWR, Point Beach Unit 2. The objective was to yield reactor coolant chemistry data during the cooldown/shutdown process which might establish a relationship between shutdown chemistry and its effects on steam generator radiation fields. Of particular concern were the effects of the presence of hydrogen in the coolant as contrasted to an oxygenated coolant. Analysis of reactor coolant samples showed a rapid soluble release (spike) in Co-58, Co-60, and nickel caused by oxygenation of the coolant. The measurement of radioisotope specific activities indicates that the material undergoing dissolution during the shutdown originated from different sources which had varying histories of activation. The test program developed no data which would support theories that oxygenation of the coolant while the steam generators are full of water contributes to increased steam generator radiation levels

  10. Monthly variations of dew point temperature in the coterminous United States

    Science.gov (United States)

    Robinson, Peter J.

    1998-11-01

    The dew point temperature, Td, data from the surface airways data set of the U.S. National Climatic Data Center were used to develop a basic dew point climatology for the coterminous United States. Quality control procedures were an integral part of the analysis. Daily Td, derived as the average of eight observations at 3-hourly intervals, for 222 stations for the 1961-1990 period were used. The annual and seasonal pattern of average values showed a clear south-north decrease in the eastern portion of the nation, a trend which was most marked in winter. In the west, values decreased inland from the Pacific Coast. Inter-annual variability was generally low when actual mean values were high. A cluster analysis suggested that the area could be divided into six regions, two oriented north-south in the west, four aligned east-west in the area east of the Rocky Mountains. Day-to-day variability was low in all seasons in the two western clusters, but showed a distinct winter maximum in the east. This was explained in broad terms by consideration of air flow regimes, with the Pacific Ocean and the Gulf of Mexico acting as the major moisture sources. Comparison of values for pairs of nearby stations suggested that Td was rather insensitive to local moisture sources. Analysis of the patterns of occurrence of dew points exceeding the 95th percentile threshold indicated that extremes in summer tend to be localized and short-lived, while in winter they are more widespread and persistent.

  11. The accident at the Three Mile Island nuclear power plant

    International Nuclear Information System (INIS)

    Butragueno, J.L.

    1980-01-01

    The sequence of events in the Three Mile Island, Unit 2, accident on the March 28, 1979 is analyzed. In this plant a loss of feed-water transient became a small LOCA that caused a serious core damage. A general emergency situation was declared after uncontrolled radioactive releases were detectec. (author)

  12. Three Mile Island ambient-air-temperature sensor measurements

    International Nuclear Information System (INIS)

    Fryer, M.O.

    1983-01-01

    Data from the ambient-air-temperature sensors in Three Mile Island-Unit 2 (TMI-2) reactor containment building are analyzed. The data were for the period of the hydrogen burn that was part of the TMI-2 accident. From the temperature data, limits are placed on the duration of the hydrogen burn

  13. Fission product transport at Three Mile Island

    International Nuclear Information System (INIS)

    Owen, D.E.; Cox, T.E.; Broughton, J.M.

    1985-01-01

    Three Mile Island Unit 2 radionuclide analyses are reviewed and summarized in order to determine how fission products moved to various parts of the reactor system at the time of the accident. Despite high fuel temperatures and major core damage, the core retained a very large fraction of most radionuclides. Reactor coolant, either remaining in the primary system or released to various sumps and tanks, retained significant quantities of cesium and iodine. Noble gases were effectively retained within the containment building with the exception of small releases to the environment. Long-term deposition and retention on vessel, piping, and bulding surfaces were insignificant for all isotopes examined. The measured partitioning of radionuclides within these systems is tabulated and recommendations for additional analyses are presented

  14. An Optimized Multicolor Point-Implicit Solver for Unstructured Grid Applications on Graphics Processing Units

    Science.gov (United States)

    Zubair, Mohammad; Nielsen, Eric; Luitjens, Justin; Hammond, Dana

    2016-01-01

    In the field of computational fluid dynamics, the Navier-Stokes equations are often solved using an unstructuredgrid approach to accommodate geometric complexity. Implicit solution methodologies for such spatial discretizations generally require frequent solution of large tightly-coupled systems of block-sparse linear equations. The multicolor point-implicit solver used in the current work typically requires a significant fraction of the overall application run time. In this work, an efficient implementation of the solver for graphics processing units is proposed. Several factors present unique challenges to achieving an efficient implementation in this environment. These include the variable amount of parallelism available in different kernel calls, indirect memory access patterns, low arithmetic intensity, and the requirement to support variable block sizes. In this work, the solver is reformulated to use standard sparse and dense Basic Linear Algebra Subprograms (BLAS) functions. However, numerical experiments show that the performance of the BLAS functions available in existing CUDA libraries is suboptimal for matrices representative of those encountered in actual simulations. Instead, optimized versions of these functions are developed. Depending on block size, the new implementations show performance gains of up to 7x over the existing CUDA library functions.

  15. Draft environmental statement for selection of the preferred closed cycle cooling system at Indian Point Unit No. 3: (Docket No. 50-286)

    International Nuclear Information System (INIS)

    1977-08-01

    The proposed action is the issuance of an amendment to the Facility Operating License No. DPR-64 for Indian Point Unit No. 3, located in the State of New York, Westchester County, Village of Buchanan, 24 miles north of the New York City boundary line. This facility is owned by the Power Authority of the State of New York and operated by the Consolidated Edison Company of New York, Inc. There will be drift (0.002%) deposited in small amounts over a substantial area, resulting in increased salt concentrations. There is a small possibility that injury may occur occasionally to certain species of plants. There may be a small increase (a matter of hours per year) in the amount of fogging and icing in the area, which are considered negligible. During construction, noise levels and traffic will be increased; however, these are temporary conditions. A monetary direct cost of approximately $245 million (present value) will be incurred by the licensee and the average annual plant capacity will be reduced by 33.5 MWe (4% of the total) while peak generating capability will be reduced by 77.5 MWe (9% of the total). Water taken from the river for cooling purposes will be reduced to approximately one-tenth that taken for once-through cooling of Unit No. 3. This will reduce impingement and entrapment of aquatic species by a similar amount and, thus, aid in the maintenance of biotic populations. The increased tax base will provide additional monies to various communities. 120 refs., 90 figs., 55 tabs

  16. Three-Mile Island Program

    International Nuclear Information System (INIS)

    Malinauskas, A.P.

    1983-01-01

    Activities associated with the Three-Mile Island (TMI) Program were of two types. One involved providing technical review and guidance for specific recovery efforts at TMI, whereas the second was concerned more directly with providing technical assistance to recovery operations through detailed analyses and experimental activities. The work was divided into four elements: Task I - coordination of and participation in the operation of the Technical Advisory Group (TAG) for the cleanup of aqueous streams at TMI; Task II - participation in the Technical Assistance and Advisory Group (TAAG) on TMI operations; Task III - chemical development and other technical support to TMI recovery operations; and Task IV - development of inorganic sorbents for the decontamination of aqueous streams. At the program review that was conducted approximately mid-fiscal year, it was decided to curtail the Task IV activities in favor of studies of more-urgent problems. Technical progress for each of the tasks of this program is presented

  17. U.S. Navigated Waterway Mile Marker Locations from USCOE source data, Geographic NAD83, LOSCO (2000) [river_mile_markers_USACE_1994

    Data.gov (United States)

    Louisiana Geographic Information Center — This is a point dataset representing 10,044 sequential mile positions of navigable inland waterways and the Gulf Intracoastal Waterway. These data were developed as...

  18. Closure Report for Corrective Action Unit 516: Septic Systems and Discharge Points, Nevada Test Site, Nevada

    International Nuclear Information System (INIS)

    NSTec Environmental Restoration

    2007-01-01

    Corrective Action Unit (CAU) 516 is located in Areas 3, 6, and 22 of the Nevada Test Site. CAU 516 is listed in the Federal Facility Agreement and Consent Order of 1996 as Septic Systems and Discharge Points, and is comprised of six Corrective Action Sites (CASs): (sm b ullet) CAS 03-59-01, Bldg 3C-36 Septic System (sm b ullet) CAS 03-59-02, Bldg 3C-45 Septic System (sm b ullet) CAS 06-51-01, Sump and Piping (sm b ullet) CAS 06-51-02, Clay Pipe and Debris (sm b ullet) CAS 06-51-03, Clean Out Box and Piping (sm b ullet) CAS 22-19-04, Vehicle Decontamination Area The Nevada Division of Environmental Protection (NDEP)-approved corrective action alternative for CASs 06-51-02 and 22-19-04 is no further action. The NDEP-approved corrective action alternative for CASs 03-59-01, 03-59-02, 06-51-01, and 06-51-03 is clean closure. Closure activities included removing and disposing of total petroleum hydrocarbon (TPH)-impacted septic tank contents, septic tanks, distribution/clean out boxes, and piping. CAU 516 was closed in accordance with the NDEP-approved CAU 516 Corrective Action Plan (CAP). The closure activities specified in the CAP were based on the recommendations presented in the CAU 516 Corrective Action Decision Document (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, 2004). This Closure Report documents CAU 516 closure activities. During closure activities, approximately 186 tons of hydrocarbon waste in the form of TPH-impacted soil and debris, as well as 89 tons of construction debris, were generated and managed and disposed of appropriately. Waste minimization techniques, such as field screening of soil samples and the utilization of laboratory analysis to characterize and classify waste streams, were employed during the performance of closure work

  19. Enhanced static ground power unit based on flying capacitor based h-bridge hybrid active-neutral-point-clamped converter

    DEFF Research Database (Denmark)

    Abarzadeh, Mostafa; Madadi Kojabadi, Hossein; Deng, Fujin

    2016-01-01

    Static power converters have various applications, such as static ground power units (GPUs) for airplanes. This study proposes a new configuration of a static GPU based on a novel nine-level flying capacitor h-bridge active-neutral-point-clamped (FCHB_ANPC) converter. The main advantages of the p......Static power converters have various applications, such as static ground power units (GPUs) for airplanes. This study proposes a new configuration of a static GPU based on a novel nine-level flying capacitor h-bridge active-neutral-point-clamped (FCHB_ANPC) converter. The main advantages...

  20. Three Mile Island Startup program and its contributions to plant performance

    International Nuclear Information System (INIS)

    Brill, R.A.; Barton, J.J.

    1976-01-01

    The General Public Utilities Service Corporation Startup Organization provided a specialized group for startup testing, coordination, and management of the Three Mile Island Unit No. 1 nuclear power plant. This organization conducted an extensive test program which contributed to Three Mile Island's high first year plant availability

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

    International Nuclear Information System (INIS)

    1977-01-01

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

  2. A dual-unit pressure sensor for on-chip self-compensation of zero-point temperature drift

    International Nuclear Information System (INIS)

    Wang, Jiachou; Li, Xinxin

    2014-01-01

    A novel dual-unit piezoresistive pressure sensor, consisting of a sensing unit and a dummy unit, is proposed and developed for on-chip self-compensation for zero-point temperature drift. With an MIS (microholes inter-etch and sealing) process implemented only from the front side of single (1 1 1) silicon wafers, a pressure sensitive unit and another identically structured pressure insensitive dummy unit are compactly integrated on-chip to eliminate unbalance factors induced zero-point temperature-drift by mutual compensation between the two units. Besides, both units are physically suspended from silicon substrate to further suppress packaging-stress induced temperature drift. A simultaneously processes ventilation hole-channel structure is connected with the pressure reference cavity of the dummy unit to make it insensitive to detected pressure. In spite of the additional dummy unit, the sensor chip dimensions are still as small as 1.2 mm × 1.2 mm × 0.4 mm. The proposed dual-unit sensor is fabricated and tested, with the tested sensitivity being 0.104 mV kPa −1 3.3 V −1 , nonlinearity of less than 0.08% · FSO and overall accuracy error of ± 0.18% · FSO. Without using any extra compensation method, the sensor features an ultra-low temperature coefficient of offset (TCO) of 0.002% °C −1 · FSO that is much better than the performance of conventional pressure sensors. The highly stable and small-sized sensors are promising for low cost production and applications. (paper)

  3. High accuracy attitude reference stabilization and pointing using the Teledyne SDG-5 gyro and the DRIRU II inertial reference unit

    Science.gov (United States)

    Green, K. N.; van Alstine, R. L.

    This paper presents the current performance levels of the SDG-5 gyro, a high performance two-axis dynamically tuned gyro, and the DRIRU II redundant inertial reference unit relating to stabilization and pointing applications. Also presented is a discussion of a product improvement program aimed at further noise reductions to meet the demanding requirements of future space defense applications.

  4. Invasion Dynamics and Genotypic Diversity of Cogongrass (Imperata cylindrica) at the Point of Introduction in the Southeastern United States

    Science.gov (United States)

    Ludovic J. A. Capo-chichi; Wilson H. Faircloth; A. G. Williamson; Michael G. Patterson; James H. Miller; Edzard van Santen

    2008-01-01

    Nine sites of cogongrass were included in a study of genotypic dimity and spread dynamics at the point of introduction and its adjacent areas in the southern United States. Clones evaluated with two primer pairs yielded a total of 137 amplified fragment length polymorphism (AFLP) hi of which 102 (74.4%) were polymorphic. Genetic diversity was measured as the percentage...

  5. 76 FR 31992 - In the Matter of Nine Mile Point Nuclear Station, LLC; Nine Mile Point Nuclear Station...

    Science.gov (United States)

    2011-06-02

    ... another active U.S. Government-granted security clearance (i.e., Top Secret, Secret, or Confidential). d...'' clearances or possess another active U.S. Government granted security clearance, i.e., Top Secret, Secret or... another active U.S. Government granted security clearance, i.e., Top Secret, Secret or Confidential. 6...

  6. Turkey Point Plant, Units 3 and 4. Semiannual operating report No. 6, January--June 1975

    International Nuclear Information System (INIS)

    1975-01-01

    Net electrical power generated by Unit 3 was 2,676,523 MWH(e) with the plant on line 4,148.8 hrs. Unit 4 generated 1,429,108 MWH(e) and was on line 2,232.0 hrs. Information is presented concerning power generation, shutdowns, corrective maintenance, chemistry and radiochemistry, occupational radiation exposure, release of radioactive materials, abnormal occurrences, and environmental radiation monitoring. (FS)

  7. Turkey Point Plant, Units 3 and 4. Semiannual operating report No. 7, July--December 1975

    International Nuclear Information System (INIS)

    1976-01-01

    Unit 3 generated 1,968,074 MWh(e) net electric power and the generator was on line 2,802.9 hrs. Unit 4 generated 2,560,476 MWh(e) and was on line 3,944.8 hrs. Information is presented concerning operations, power generation, shutdowns, maintenance, changes, tests, experiments, radioactive effluent releases, radiological environmental monitoring, and occupational personnel radiation monitoring

  8. Testing of an End-Point Control Unit Designed to Enable Precision Control of Manipulator-Coupled Spacecraft

    Science.gov (United States)

    Montgomery, Raymond C.; Ghosh, Dave; Tobbe, Patrick A.; Weathers, John M.; Manouchehri, Davoud; Lindsay, Thomas S.

    1994-01-01

    This paper presents an end-point control concept designed to enable precision telerobotic control of manipulator-coupled spacecraft. The concept employs a hardware unit (end-point control unit EPCU) that is positioned between the end-effector of the Space Shuttle Remote Manipulator System and the payload. Features of the unit are active compliance (control of the displacement between the end-effector and the payload), to allow precision control of payload motions, and inertial load relief, to prevent the transmission of loads between the end-effector and the payload. This paper presents the concept and studies the active compliance feature using a simulation and hardware. Results of the simulation show the effectiveness of the EPCU in smoothing the motion of the payload. Results are presented from initial, limited tests of a laboratory hardware unit on a robotic arm testbed at the l Space Flight Center. Tracking performance of the arm in a constant speed automated retraction and extension maneuver of a heavy payload with and without the unit active is compared for the design speed and higher speeds. Simultaneous load reduction and tracking performance are demonstrated using the EPCU.

  9. A perspective on the Three Mile Island incident

    International Nuclear Information System (INIS)

    Hensley, G.

    1979-01-01

    An account is given of the accident on March 28, 1979, in the No. 2 unit of the Three Mile Island nuclear power station. The sequence is described, beginning with the loss of secondary coolant to the PWR's steam generators. Equipment failure and the consequences of human actions are analyzed, and lessons to be learned are discussed. Some conclusions are reached with particular reference to the accident and to nuclear power. (U.K.)

  10. Three Mile Island zeolite vitirification demonstration program

    International Nuclear Information System (INIS)

    Siemens, D.H.; Knowlton, D.E.; Shupe, M.W.

    1981-06-01

    The cleanup of the high-activity-level water at Three Mile Island (TMI) provides an opportunity to further develop waste management technology. Approximately 790,000 gallons of high-activity-level water at TMI's Unit-2 Nuclear Power Station will be decontaminated at the site using the submerged demineralizer system (SDS). In the SDS process, the cesium and strontium in the water are sorbed onto zeolite that is contained within metal liners. The Department of Energy has asked the Pacific Northwest Laboratory (PNL) to take a portion of the zeolite from the SDS process and demonstrate, on a production scale, that this zeolite can be vitrified using the in-can melting process. This paper is a brief overview of the TMI zeolite vitrification program. The first section discusses the formulation of a glass suitable for immobilizing SDS zeolite. The following section describes a feed system that was developed to feed zeolite to the in-can melter. It also describes the in-can melting process and the government owned facilities in which the demonstrations will take place. Finally, the schedule for completing the program activities is outlined

  11. Indian Point Nuclear Generating Plant Unit No. 3 (Docket No. 50-286): Final environmental statement: Volume 2

    International Nuclear Information System (INIS)

    1975-02-01

    This document contains nine appendices to Volume I, The Final Environmental Impact Statement for the Indian Point Nuclear Generating Plant Unit Number Three. Topics covered include thermal discharges to the Hudson River; supplemental information relating to biological models; radiation effects on aquatic biota; conditions, assumptions, and parameters used in calculating radioactive releases; meteorology for radiological dispersion calculations; life history information of important fish species in the Hudson River near Indian Point; additional information on cooling towers considered as alternatives; data and calculations for assessment of predicted electrical demand; and comments on draft environmental statement

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

    International Nuclear Information System (INIS)

    1975-01-01

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

  13. A nitrogen triple-point thermal storage unit for cooling a SQUID magnetometer

    NARCIS (Netherlands)

    Rijpma, A.P.; Meenderink, D.J.; Reincke, H.A.; Venhorst, G.C.F.; Holland, H.J.; Brake, ter H.J.M.

    2005-01-01

    In order to achieve turnkey operation, the use is planned of cryocoolers to cool a SQUID magnetometer system. To minimize the magnetical and mech. interference from the coolers, they are switched off during the actual measurements. Consequently, a thermal storage unit (TSU) is required with

  14. A nitrogen triple-point thermal storage unit for cooling a SQUID magnetometer

    NARCIS (Netherlands)

    Rijpma, A.P.; Meenderink, D.J.; Reincke, H.A.; Venhorst, G.C.F.; Venhorst, G.C.F.; Holland, Herman J.; ter Brake, Hermanus J.M.

    2005-01-01

    In order to achieve turnkey operation, we plan to use cryocoolers to cool a SQUID magnetometer system. To minimize the magnetical and mechanical interference from the coolers, we intend to switch them off during the actual measurements. Consequently, a thermal storage unit (TSU) is required with

  15. The problem of nuclear wastes. A possible point of conflict between Mexico and the United States

    International Nuclear Information System (INIS)

    Rosas Poblano, A.

    1993-01-01

    The objectives of this research were: a) To analyse the problem of nuclear wastes, and the importance of their safe handling; b) To investigate the best and safest technologies for the treatment of radioactive wastes and two relevant international laws or regulations; c) To study whether the wastes produced in the United States represent an environmental problem for Mexico

  16. Destructive examination of 3-cycle LWR fuel rods from Turkey Point Unit 3 for the Climax-Spent Fuel Test

    International Nuclear Information System (INIS)

    Atkin, S.D.

    1981-06-01

    The destructive examination results of five light water reactor rods from the Turkey Point Unit 3 reactor are presented. The examinations included fission gas collection and analyses, burnup and hydrogen analyses, and a metallographic evaluation of the fuel, cladding, oxide, and hydrides. The rods exhibited a low fission gas release with all other results appearing representative for pressurized water reactor fuel rods with similar burnups (28 GWd/MTU) and operating histories

  17. 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

  18. In the Shadow of Three Mile Island.

    Science.gov (United States)

    Blair-Clough, Ida; Wheeler, Brenda

    1979-01-01

    Describes how teachers turned the reality of the nuclear reactor incident at Three Mile Island into a learning experience for children by recreating the sequence of events through creative dramatics. (CM)

  19. A Chemistry Lesson at Three Mile Island.

    Science.gov (United States)

    Mammano, Nicholas J.

    1980-01-01

    Details the procedures used in utilizing the hydrogen bubble incident at Three Mile Island to relate these basic chemical principles to nuclear chemistry: gas laws, Le Chatelier's principle and equilibrium, and stoichiometry. (CS)

  20. Siren system designed for Three Mile Island

    International Nuclear Information System (INIS)

    Lee, V.M.

    1984-01-01

    Since the Three Mile Island (TMI) incident in 1979, the Federal Emergency Management Agency (FEMA) and Nuclear Regulatory Commission (NRC) guidelines require utilities operating nuclear reactors to warn all civilian populations within a 10-mile radius by audible alarms in the event of a nuclear plant emergency. The case history presented involves the planning and implementation of a suitable siren-alarm system by General Public Utilities and its consultant firm. 1 figure

  1. Simultaneous reconstruction of multiple depth images without off-focus points in integral imaging using a graphics processing unit.

    Science.gov (United States)

    Yi, Faliu; Lee, Jieun; Moon, Inkyu

    2014-05-01

    The reconstruction of multiple depth images with a ray back-propagation algorithm in three-dimensional (3D) computational integral imaging is computationally burdensome. Further, a reconstructed depth image consists of a focus and an off-focus area. Focus areas are 3D points on the surface of an object that are located at the reconstructed depth, while off-focus areas include 3D points in free-space that do not belong to any object surface in 3D space. Generally, without being removed, the presence of an off-focus area would adversely affect the high-level analysis of a 3D object, including its classification, recognition, and tracking. Here, we use a graphics processing unit (GPU) that supports parallel processing with multiple processors to simultaneously reconstruct multiple depth images using a lookup table containing the shifted values along the x and y directions for each elemental image in a given depth range. Moreover, each 3D point on a depth image can be measured by analyzing its statistical variance with its corresponding samples, which are captured by the two-dimensional (2D) elemental images. These statistical variances can be used to classify depth image pixels as either focus or off-focus points. At this stage, the measurement of focus and off-focus points in multiple depth images is also implemented in parallel on a GPU. Our proposed method is conducted based on the assumption that there is no occlusion of the 3D object during the capture stage of the integral imaging process. Experimental results have demonstrated that this method is capable of removing off-focus points in the reconstructed depth image. The results also showed that using a GPU to remove the off-focus points could greatly improve the overall computational speed compared with using a CPU.

  2. The Small Area Health Statistics Unit: a national facility for investigating health around point sources of environmental pollution in the United Kingdom.

    Science.gov (United States)

    Elliott, P; Westlake, A J; Hills, M; Kleinschmidt, I; Rodrigues, L; McGale, P; Marshall, K; Rose, G

    1992-01-01

    STUDY OBJECTIVE--The Small Area Health Statistics Unit (SAHSU) was established at the London School of Hygiene and Tropical Medicine in response to a recommendation of the enquiry into the increased incidence of childhood leukaemia near Sellafield, the nuclear reprocessing plant in West Cumbria. The aim of this paper was to describe the Unit's methods for the investigation of health around point sources of environmental pollution in the United Kingdom. DESIGN--Routine data currently including deaths and cancer registrations are held in a large national database which uses a post code based retrieval system to locate cases geographically and link them to the underlying census enumeration districts, and hence to their populations at risk. Main outcome measures were comparison of observed/expected ratios (based on national rates) within bands delineated by concentric circles around point sources of environmental pollution located anywhere in Britain. MAIN RESULTS--The system is illustrated by a study of mortality from mesothelioma and asbestosis near the Plymouth naval dockyards during 1981-87. Within a 3 km radius of the docks the mortality rate for mesothelioma was higher than the national rate by a factor of 8.4, and that for asbestosis was higher by a factor of 13.6. CONCLUSIONS--SAHSU is a new national facility which is rapidly able to provide rates of mortality and cancer incidence for arbitrary circles drawn around any point in Britain. The example around Plymouth of mesothelioma and asbestosis demonstrates the ability of the system to detect an unusual excess of disease in a small locality, although in this case the findings are likely to be related to occupational rather than environmental exposure. PMID:1431704

  3. 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

  4. A thousand miles from sea

    International Nuclear Information System (INIS)

    Polczer, S.

    1999-01-01

    The success of Dreco Rig Systems, a division of National Oilwell Canada Ltd., in becoming the foremost international designers and manufacturers of offshore drilling equipment is discussed. Dreco has been at the same Edmonton location since 1972, starting out as a rig mast repair shop, eventually expanding into building components such as draw-works and mud pumps and still later to full-blown drilling rigs. Following the drastic curtailment of exploration in Alberta in 1982, the company began specializing in high-end equipment for international markets for use in some of the most extreme environments in the world, including offshore, Arctic, desert and jungle terrain. Today, the Edmonton and Nisku facilities of the company subcontract 61,000 man-hours of employment per month, and turn out some 7,000 tons of fabricated steel annually. Most notable accomplishments include the rig towers for the Hibernia platform, various unconventional offshore units used in exploration in the high Arctic, the jack-up rig packages for the Sable Offshore Energy Project, and the drilling package on the Royal Dutch Shell Troll natural gas platform, considered to be the largest gravity-based offshore platform in the world. Additional design and manufacturing of equipment was done for Syncrude Canada, Imperial Oil Resources at Cold Lake, and parts for the Epcor Genesse electrical generating station west of Edmonton. The company's latest project is a 1,000-horse power wheeled rig for use in the desert of Oman, a project which adds considerably to the company's reputation for innovation and design of equipment for use in extreme environments

  5. Impact abroad of the accident at the Three Mile Island nuclear power plant: March-September 1979. Prepared for the Subcommittee on Energy, Nuclear Proliferation and Federal Services of the Committee on Governmental Affairs, United States Senate by the Congressional Research Service, Library of Congress

    International Nuclear Information System (INIS)

    Anon.

    1980-01-01

    On March 28, 1979, an accident occurred in a nuclear power plant at Three Mile Island, near Harrisburg, Pennsylvania. It caused widespread fears of catastrophe and raised doubts as to the adequacy of what some nuclear utilities and the U.S. Nuclear Regulatory Commission have done to assure safe operation of nuclear power plants. Now, some ten months after the accident, its effects on Federal regulation and upon the public's attitude toward nuclear power are still evolving. The final effects remain hidden in the future. They can be expected to have an impact on the development of nuclear power in the United States and also abroad. The accident at Three Mile island has been investigated and analyzed exhaustively by the NRC, by the nuclear industry, by a Presidential commission (the Kemeny Commission), and by two committees of Congress. Some of these studies are still in progress. Many foreign governments sent teams to analyze and report on the accident and reactions to it. Because the future of nuclear power abroad seems likely to bear imprint of the accident, and because of the inescapable interconnection between nuclear power in the United States and in other countries, Senator John Glenn's Subcommittee on Energy, Nu-Proliferation and Federal Services of the Senate Committee on Government Affairs, asked the Congressional Research Service (CRS) to arrange for reviews of the impacts abroad. The CRS contracted for this review with two well-situated analysts. One is Geoffrey Greenhalgh, an Englishman who has had a long association with the nuclear power industry in Europe and is a support of it. The other is Walter C. Patterson, who is one of the leading articulate critics of nuclear power and has long been associated with Friends of the Earth, in London

  6. Mental health effects of the Three Mile Island nuclear reactor restart.

    Science.gov (United States)

    Dew, M A; Bromet, E J; Schulberg, H C; Dunn, L O; Parkinson, D K

    1987-08-01

    Controversy over potential mental health effects of the Three Mile Island Unit-1 restart led the authors to examine prospectively the pattern of psychiatric symptoms in a sample of Three Mile Island area mothers of young children. Symptom levels after restart were elevated over previous levels; a sizable subcohort of the sample reported relatively serious degrees of postrestart distress. History of diagnosable major depression and generalized anxiety following the Three Mile Island accident, plus symptoms and beliefs about personal risk prior to the restart, best predicted postrestart symptoms.

  7. Mental health effects of the Three Mile Island nuclear reactor restart

    International Nuclear Information System (INIS)

    Dew, M.A.; Bromet, E.J.; Schulberg, H.C.; Dunn, L.O.; Parkinson, D.K.

    1987-01-01

    Controversy over potential mental health effects of the Three Mile Island Unit-1 restart led the authors to examine prospectively the pattern of psychiatric symptoms in a sample of Three Mile Island area mothers of young children. Symptom levels after restart were elevated over previous levels; a sizable subcohort of the sample reported relatively serious degrees of postrestart distress. History of diagnosable major depression and generalized anxiety following the Three Mile Island accident, plus symptoms and beliefs about personal risk prior to the restart, best predicted postrestart symptoms

  8. Simulation of the Three Mile Island transient in Semiscale

    International Nuclear Information System (INIS)

    Larson, T.K.; Loomis, G.G.; Shumway, R.W.

    1979-07-01

    This report presents the results of a preliminary review and analysis of the data obtained from eight simulations of the Three Mile Island Unit 2 Nuclear Power Generating Station transient (March 28, 1979) that have been conducted in the Semiscale Mod-3 System. The Semiscale simulations of the Three Mile Island (TMI) transient were basically conducted from the same sequence of events as those recorded in the plant. System initial conditions representative of those in the TMI system were established and the transient was initiated by terminating steam generator feedwater and steam valve flow. The steam generator secondaries were drained to control primary to secondary heat transfer. The pressurizer power operated relief valve, pressurizer code safety valve, and core power trip were operated on system pressure. High pressure safety injection was activated for about one minute during the Semiscale simulations. In addition, both primary loop coolant pumps were shut off in the Semiscale simulation at the same time that the Three Mile Island loop 2A pump was shut off

  9. Miles-Ezzell's WACC Approach Yields Arbitrage

    OpenAIRE

    Löffler, Andreas

    2002-01-01

    A simple counterexample shows the the widely used WACC approach to value leverage firms developed by Miles and Ezzell can create an arbitrage opportunity. The only consequence to be drawn is that their WACC approach cannot be applied under the circumstances assumed by Miles and Ezzell. We show how the WACC has to be modified in order to obtain proper results. We develop a theory in continuous as well as discrete time. In discrete time it turns out that with a further assumption on the cash fl...

  10. Pharmaceutics, Drug Delivery and Pharmaceutical Technology: A New Test Unit for Disintegration End-Point Determination of Orodispersible Films.

    Science.gov (United States)

    Low, Ariana; Kok, Si Ling; Khong, Yuetmei; Chan, Sui Yung; Gokhale, Rajeev

    2015-11-01

    No standard time or pharmacopoeia disintegration test method for orodispersible films (ODFs) exists. The USP disintegration test for tablets and capsules poses significant challenges for end-point determination when used for ODFs. We tested a newly developed disintegration test unit (DTU) against the USP disintegration test. The DTU is an accessory to the USP disintegration apparatus. It holds the ODF in a horizontal position, allowing top-view of the ODF during testing. A Gauge R&R study was conducted to assign relative contributions of the total variability from the operator, sample or the experimental set-up. Precision was compared using commercial ODF products in different media. Agreement between the two measurement methods was analysed. The DTU showed improved repeatability and reproducibility compared to the USP disintegration system with tighter standard deviations regardless of operator or medium. There is good agreement between the two methods, with the USP disintegration test giving generally longer disintegration times possibly due to difficulty in end-point determination. The DTU provided clear end-point determination and is suitable for quality control of ODFs during product developmental stage or manufacturing. This may facilitate the development of a standardized methodology for disintegration time determination of ODFs. © 2015 Wiley Periodicals, Inc. and the American Pharmacists Association J Pharm Sci 104:3893-3903, 2015. Copyright © 2015 Wiley Periodicals, Inc. and the American Pharmacists Association.

  11. 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

  12. Evaluation of carbons exposed to the Three Mile Island accident

    International Nuclear Information System (INIS)

    Deitz, V.R.; Romans, J.B.; Bellamy, R.R.

    1981-01-01

    One of the lines of defense that served to mitigate the radiological effects of the accident at Three Mile Island was the activated carbon installed in ventilation air flows. Filters in the Auxiliary and Fuel Handling Buildings of Unit 2 adsorbed tens to hundreds of curies of iodine-131, preventing the release to the environment. The carbon exposed to the accident has been replaced and the spent carbon has been analyzed in the laboratory. Independent analyses were performed for the two filter trains in both the Auxiliary and Fuel Handling Buildings, replaced at various times after the accident. The results of these analyses are compared to new (unexposed) carbons

  13. An analysis of the Three Mile Island accident

    International Nuclear Information System (INIS)

    Brooks, G.L.; Siddal, E.

    1980-09-01

    Starting with a systematic analysis of the chain of events that took place during the Three Mile Island accident, the authors assess the significance of the four distinct phases of the accident. Inferences that can be drawn with respect to the safety of CANDU reactors are discussed. A rational reaction to the accident is suggested, and several factors are shown not to have played an important part, contrary to public impressions. The authors point out that over-reaction to the accident could detract from public safety. The Canadian response to the accident is discussed. (auth)

  14. Normal Accident at Three Mile Island.

    Science.gov (United States)

    Perrow, Charles

    1981-01-01

    Discusses some aspects of the accident at the Three Mile Island nuclear power plant. Explains a number of factors involved including the type of accident, warnings, design and equipment failure, operator error, and negative synergy. Presents alternatives to systems with catastrophic potential. (MK)

  15. Mile-A-Minute (Pest Alert)

    Science.gov (United States)

    Denise Binion; William Jackson

    2009-01-01

    Mile-a-minute weed (Persicaria perfoliata (L.) H. Gross, formerly Polygonum perfoliatum, L.) is an annual vine in the Polygonaceae or Buckwheat family. It is native to eastern Asia including India, Bhutan, Nepal, China, Burma, Japan, Korea, Indonesia, Bangladesh, Siberia, the Philippines, New Guinea, the Malay peninsula and the...

  16. The Three-Mile Island incident

    International Nuclear Information System (INIS)

    Davies, L.M.

    1979-10-01

    A description is given of the engineering design principles of the PWR (Pressurized Water Reactor) of the Three Mile Island-2 power plant. The successive stages of the incident are recounted, with diagrammatic illustrations, and graphs showing the reactor coolant system parameters at various times after the incident. The consequential events and core damage are discussed. (U.K.)

  17. Good Engineering + Poor Communication = Three Mile Island.

    Science.gov (United States)

    Mathes, J. C.

    The accident at the Three Mile Island nuclear power plant resulted from a communication failure. Following an incident at an Ohio plant a year and a half earlier, B. M. Dunn, manager of Emergency Core Cooling Systems Analysis at Babcock and Wilcox (engineers), wrote a memorandum making specific recommendations on written instructions for nuclear…

  18. Émile Durkheims politiske teori

    DEFF Research Database (Denmark)

    Harste, Gorm

    2009-01-01

    Émile Durkheim skabte en af de mest koherænte teorier om moderne samfunds udvikling og ikke mindst om udviklinger i stat og demokrati. Demokrati defineres som deliberativt demokrati, dvs. at demokrati ikke skal forstås blot som flertalsstyre, men som kommunikationen i forhandlingerne om samfundets...

  19. The Coarse-Grained/Fine-Grained Logic Interface in FPGAs with Embedded Floating-Point Arithmetic Units

    Directory of Open Access Journals (Sweden)

    Chi Wai Yu

    2008-01-01

    Full Text Available This paper examines the interface between fine-grained and coarse-grained programmable logic in FPGAs. Specifically, it presents an empirical study that covers the location, pin arrangement, and interconnect between embedded floating point units (FPUs and the fine-grained logic fabric in FPGAs. It also studies this interface in FPGAs which contain both FPUs and embedded memories. The results show that (1 FPUs should have a square aspect ratio; (2 they should be positioned near the center of the FPGA; (3 their I/O pins should be arranged around all four sides of the FPU; (4 embedded memory should be located between the FPUs; and (5 connecting higher I/O density coarse-grained blocks increases the demand for routing resources. The hybrid FPGAs with embedded memory required 12% wider channels than the case where embedded memory is not used.

  20. Optimization of a Nucleic Acids united-RESidue 2-Point model (NARES-2P) with a maximum-likelihood approach

    International Nuclear Information System (INIS)

    He, Yi; Scheraga, Harold A.; Liwo, Adam

    2015-01-01

    Coarse-grained models are useful tools to investigate the structural and thermodynamic properties of biomolecules. They are obtained by merging several atoms into one interaction site. Such simplified models try to capture as much as possible information of the original biomolecular system in all-atom representation but the resulting parameters of these coarse-grained force fields still need further optimization. In this paper, a force field optimization method, which is based on maximum-likelihood fitting of the simulated to the experimental conformational ensembles and least-squares fitting of the simulated to the experimental heat-capacity curves, is applied to optimize the Nucleic Acid united-RESidue 2-point (NARES-2P) model for coarse-grained simulations of nucleic acids recently developed in our laboratory. The optimized NARES-2P force field reproduces the structural and thermodynamic data of small DNA molecules much better than the original force field

  1. Point-of-purchase alcohol marketing and promotion by store type--United States, 2000-2001.

    Science.gov (United States)

    2003-04-11

    Alcohol consumption is the third leading preventable cause of death in the United States, accounting for approximately 100,000 deaths annually. Efforts to reduce the adverse health and social consequences from alcohol use include policies to restrict access to alcohol among underaged persons (i.e., persons aged Point-of-purchase (POP) (i.e., on-site) marketing, including alcohol advertising and placement, can increase alcohol sales and consumption substantially, thereby increasing the risk for various alcohol-related health outcomes, including alcohol-impaired driving and interpersonal violence. To assess the type and frequency of POP alcohol marketing, researchers with the ImpacTeen Project collected and analyzed store observation data during 2000-2001 from 3,961 alcohol retailers in 329 communities throughout the United States. This report summarizes the results of the study, which indicate that POP alcohol marketing is extensive in certain store types frequented by teenagers and young adults. Public health agencies and policy makers should work with liquor control boards to reduce POP marketing that could promote risky or underage drinking.

  2. Evacuation decision-making at Three Mile Island

    International Nuclear Information System (INIS)

    Zeigler, D.J.; Johnson, J.H. Jr.

    1987-01-01

    During the emergency at the Three Mile Island generating station in the United States, evacuation became a common adaptive response among the local population. The planning for nuclear emergencies in the US has proceeded as if there were no significant differences between nuclear and other types of disasters requiring evacuation. In the United Kingdom, emergency planning for a new generation of pressurized water reactors, about which there is legitimate safety concern, has been influenced not at all by the experience with the Three Mile Island PWR in 1979. The TMI accident has been the US's most serious experience with a nuclear plant accident and therefore is an appropriate analogy for predicting the evacuation response to future nuclear emergencies. In this light, the authors accept the need to develop models that will enable them to predict the magnitude of the evacuation shadow phenomenon around other nuclear power sites and estimate its impact on our plans to remove the threatened population from the hazard zone in the minimum amount of time. Rather than depend on education and information control to stifle evacuation response, the authors believe that evacuation plans need to build on people's natural behavioural inclinations to protect themselves in response to the nuclear hazard

  3. Three mile island. The silent disaster.

    Science.gov (United States)

    Smith, J S; Fisher, J H

    1981-04-24

    From Wednesday, March 28, 1979, to Wednesday, April 4, 1979, Dauphin County, Pennsylvania, was in a state of near-panic in response to the Three Mile Island nuclear accident. The Dauphin County Office of Emergency Preparedness quickly attempted to develop a plan to evacuate not only the population of an area 20 miles in radius from the plant but the short-term and long-term care medical facilities as well. For medical evacuation, a system of classification of patients was defined and matched to needed transportation. Furthermore, a critical coordinating link was established with the Hospital Association of Pennsylvania to identify and categorize relocation beds in receiving hospitals far from the incident site in the event of evacuation. Just as this incident was unusual, so too were the planning activities unique since they were never before conceived or accomplished.

  4. Three Mile Island. The silent disaster

    International Nuclear Information System (INIS)

    Smith, J.S. Jr.; Fisher, J.H.

    1981-01-01

    From Wednesday, March 28, 1979, to Wednesday, April 4, 1979, Dauphin County, Pennsylvania, was in a state of near-panic in response to the Three Mile Island nuclear accident. The Dauphin County Office of Emergency Preparedness quickly attempted to develop a plan to evacuate not only the population of an area 20 miles in radius from the plant but the short-term and long-term care medical facilities as well. For medical evacuation, a system of classification of patients was defined and matched to needed transportation. Furthermore, a critical coordinating link was established with the Hospital Association of Pennsylvania to identify and categorize relocation beds in receiving hospitals far from the incident site in the event of evacuation. Just as this incident was unusual, so too were the planning activities unique since they were never before conceived or accomplished

  5. FirstMile US Fall 2005 Conference

    Science.gov (United States)

    2005-12-01

    Moore, Virginia Tech 5. Broadband Delivery means Living Longer and Living Better a. The First Mile in Healthcare, Michael Ackerman, National Library of...deal with it and interact with it." The Internet will be delivered by a wide variety of means and go to places where people may not have access to...Fall 2005 Conference Proceedings First Regional Commnunity Network - OneCleveland Steven Brand, OneCleveland 4U -ýýeý L ECommunity Computing -Thin

  6. Facts on Three Mile Island. I

    International Nuclear Information System (INIS)

    Hermansky, B. et al.

    1980-01-01

    The accident in the Three Mile Island nuclear power plant is discussed with respect to media reporting and availability of correct information at the time of the accident. It is shown that while the accident itself was by far not so serious as it was purported to be the panic surrounding it was caused by misinforming the public about its true nature and extent. (M.S.)

  7. Evacuation behavior and Three Mile Island.

    Science.gov (United States)

    Cutter, S; Barnes, K

    1982-06-01

    The responses of the residents to the nuclear power plant arcident at Three Mile Island, Pennsylvania illustrate the factors influencing pre-impact coping responses of populations exposed to technological hazards. Confusion itnd ambiguous information influenced both the decision to evaluate and to remain in place. Proximity to the facility, stage in life cycle and the actions of friends and neighbors influenced the decision to evacuate.

  8. The lessons of Three Mile Island

    International Nuclear Information System (INIS)

    McKee, K.C.

    1990-01-01

    This article looks at the lessons learned from the Three Mile Island incident in 1979 from the perspective of the manager of public affairs for General Public Utilities. A review of what was done, the types of information presented, the interfaces to the press, public and local and state government and why it did not work is presented. The article addresses communications and crisis management

  9. Instructor development program at Three Mile Island

    International Nuclear Information System (INIS)

    Irizarry, C.A.; Jones, J.W.; Knief, R.

    1981-01-01

    The Three Mile Island (TMI) Training Department has prepared and conducted Instructor Development Programs which have upgraded the capabilities of its instructors and provided more uniformity among its diverse efforts. The week-long course was prepared in-house by a staff that combined college teaching experience in both education and technical subjects with strong background in industrial training. Through the first two offerings of the course, twenty-five individuals have participated and eight have served on the course staff

  10. The Three Mile Island Population Registry.

    Science.gov (United States)

    Goldhaber, M K; Tokuhata, G K; Digon, E; Caldwell, G G; Stein, G F; Lutz, G; Gur, D

    1983-01-01

    Shortly after the March 28, 1979, accident at the Three Mile Island (TMI) nuclear plant outside Harrisburg, Pa., the Pennsylvania Department of Health, in conjunction with the Centers for Disease Control and the U.S. Bureau of the Census, conducted a census of the 35,930 persons residing within 5 miles of the plant. With the help of 150 enumerators, demographic and health-related information was collected on each person to provide baseline data for future short- and long-term epidemiologic studies of the effects of the accident. Individual radiation doses were estimated on the basis of residential location and the amount of time each person spent in the 5-mile area during the 10 days after the accident. Health and behavioral resurveys of the population will be conducted approximately every 5 years. Population-mobility, morbidity, and mortality will be studied yearly by matching the TMI Population Registry with postal records, cancer registry records, and death certificate data. Because the radiation dose from TMI was extremely small, any increase in morbidity or mortality attributable to the accident would be so small as not to be measurable by present methods; however, adverse health effects as a result of psychological stress may occur. Also, a temporary increase in reporting of disease could occur because of increased surveillance and attention to health.

  11. Analysis of Three Mile Island Unit 2 accident

    International Nuclear Information System (INIS)

    Anon.

    1979-01-01

    NSAC is conducting a detailed review of this accident and of the lessons to be learned. So far it has concentrated primarily on events during the sixteen hours following initiation of the accident. A sequence of events has been developed and is being verified and annotated by comparing oral and written statements with instrumentation records, data logs, operator logs, and inferences which can be made from these records. This report is being developed with the expectation that, while not completed or fully verified, it may be useful at this time. Supplements may be issued later as the analyses which are still under way are completed

  12. Technology transfer at Three Mile Island Unit 2

    International Nuclear Information System (INIS)

    Burton, H.M.; Bixby, W.W.

    1982-01-01

    The Department of Energy (DOE) formulated a program at TMI-2 in concert with the Coordination Agreement. The DOE TME-2 Information and Examination Program (TI and EP) aims to fulfill three general objectives. First, the TI and EP aims to obtain information from the TMI-2 accidient for resolving specific safety and licensing concerns; modifying applicable standards, specifications, and regulations; and defining changes in design, maintenance, operation, and personnel training. Second, the TI and EP uses TMI-2 information to advance technology in decontamination work; radioactive waste immobilization and disposal; system requalification; damaged fuel handling; and plant, reactor, and safety engineering. Finally, the TI and EP distributes the information gained from the Program to others that are engaged in research and development, design, construction, operation, maintenance, and regulation of nuclear power plants

  13. Potential Effectiveness of Point-of-Use Filtration to Address Risks to Drinking Water in the United States.

    Science.gov (United States)

    Brown, Kathleen Ward; Gessesse, Bemnet; Butler, Lindsey J; MacIntosh, David L

    2017-01-01

    Numerous contemporary incidents demonstrate that conventional control strategies for municipal tap water have limited ability to mitigate exposures to chemicals whose sources are within distribution systems, such as lead, and chemicals that are not removed by standard treatment technologies, such as perfluorooctanoic acid (PFOA)/perfluorooctanesulfonic acid (PFOS). In these situations, point-of-use (POU) controls may be effective in mitigating exposures and managing health risks of chemicals in drinking water, but their potential utility has not been extensively examined. As an initial effort to fill this information gap, we conducted a critical review and analysis of the existing literature and data on the effectiveness of POU drinking water treatment technologies for reducing chemical contaminants commonly found in tap water in the United States. We found that many types of water treatment devices available to consumers in the United States have undergone laboratory testing and often certification for removal of chemical contaminants in tap water, but in most cases their efficacy in actual use has yet to be well characterized. In addition, the few studies of POU devices while "in use" focus on traditional contaminants regulated under the Safe Drinking Water Act, but do not generally consider nontraditional contaminants of concern, such as certain novel human carcinogens, industrial chemicals, pesticides, pharmaceuticals, personal care products, and flame retardants. Nevertheless, the limited information available at present suggests that POU devices can be highly effective when used prophylactically and when deployed in response to contamination incidents. Based on these findings, we identify future areas of research for assessing the ability of POU filters to reduce health-related chemical contaminants distributed through public water systems and private wells.

  14. Novel high accurate sensorless dual-axis solar tracking system controlled by maximum power point tracking unit of photovoltaic systems

    International Nuclear Information System (INIS)

    Fathabadi, Hassan

    2016-01-01

    Highlights: • Novel high accurate sensorless dual-axis solar tracker. • It has the advantages of both sensor based and sensorless solar trackers. • It does not have the disadvantages of sensor based and sensorless solar trackers. • Tracking error of only 0.11° that is less than the tracking errors of others. • An increase of 28.8–43.6% depending on the seasons in the energy efficiency. - Abstract: In this study, a novel high accurate sensorless dual-axis solar tracker controlled by the maximum power point tracking unit available in almost all photovoltaic systems is proposed. The maximum power point tracking controller continuously calculates the maximum output power of the photovoltaic module/panel/array, and uses the altitude and azimuth angles deviations to track the sun direction where the greatest value of the maximum output power is extracted. Unlike all other sensorless solar trackers, the proposed solar tracking system is a closed loop system which means it uses the actual direction of the sun at any time to track the sun direction, and this is the contribution of this work. The proposed solar tracker has the advantages of both sensor based and sensorless dual-axis solar trackers, but it does not have their disadvantages. Other sensorless solar trackers all are open loop, i.e., they use offline estimated data about the sun path in the sky obtained from solar map equations, so low exactness, cloudy sky, and requiring new data for new location are their problems. A photovoltaic system has been built, and it is experimentally verified that the proposed solar tracking system tracks the sun direction with the tracking error of 0.11° which is less than the tracking errors of other both sensor based and sensorless solar trackers. An increase of 28.8–43.6% depending on the seasons in the energy efficiency is the main advantage of utilizing the proposed solar tracking system.

  15. Nonlinear pre-coding apparatus of multi-antenna system, has pre-coding unit that extents original constellation points of modulated symbols to several constellation points by using limited perturbation vector

    DEFF Research Database (Denmark)

    2008-01-01

    A Coding/Modulating units (200-1-200-N) outputs modulated symbols by modulating coding bit streams based on certain modulation scheme. The limited perturbation vector is calculated by using distribution of perturbation vectors. The original constellation points of modulated symbols are extended t...

  16. Facts on Three Mile Island. IV

    International Nuclear Information System (INIS)

    Hermansky

    1980-01-01

    A number of commissions and committees were established in the USA following the Three Mile Island-2 accident, charged with investigating the causes of the accident and suggesting precautions which would limit future possible occurrences of such accidents. The recommendations by the most significant bodies are briefly outlined, including the: (1) instructions by NRC for the operators of PWR type nuclear power plants; (2) recommendations by the Kemeny commission appointed by president Carter; (3) recommendations by the Advisory Committee for Reactor Safety (ACRS); (4) measures taken by the Tennessee Valley Authority. (Ha)

  17. Fair Miles? The concept of 'food miles' through a sustainable development lens

    Energy Technology Data Exchange (ETDEWEB)

    MacGregor, James; Vorley, Bill

    2006-10-15

    The concept of 'food miles' presents an argument to buy goods which have travelled the shortest distance from farm to table, and to discriminate against long-haul transportation, especially air-freighted goods. The long-distance transport of food is associated with additional emissions due to increased transportation coupled with greater packaging, as well as a disconnection between the public and local farming. Furthermore, 'food miles' encapsulates (and is at the vanguard of) the climate change debate in the UK. In light of growing international concern over the speed and scale of climate change, the concept of 'food miles' has captured public attention and apparently is changing some consumers' behaviour, although only around one-third of shoppers know of the concept.

  18. Improvements in BTS estimation of ton-miles

    Science.gov (United States)

    2004-08-01

    Ton-miles (one ton of freight shipped one mile) is the primary physical measure of freight transportation output. This paper describes improved measurements of ton-miles for air, truck, rail, water, and pipeline modes. Each modal measure contains a d...

  19. Point Beach Nuclear Plant, Units 1 and 2. Semiannual operating report No. 10, January--June 1975

    International Nuclear Information System (INIS)

    1975-01-01

    Unit 1 operated at an average capacity factor of 65.2 percent with a net efficiency of 31.41 percent. Unit 2 operted at an average capacity factor of 88.6 lpercent with a net efficiency of 32.28 percent. Unit 1 was essentially base loaded while Unit 2 operated on load follow. 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)

  20. Point sources of emerging contaminants along the Colorado River Basin: Source water for the arid Southwestern United States

    Science.gov (United States)

    Jones-Lepp, Tammy L.; Sanchez, Charles; Alvarez, David A.; Wilson, Doyle C.; Taniguchi-Fu, Randi-Laurant

    2012-01-01

    Emerging contaminants (ECs) (e.g., pharmaceuticals, illicit drugs, personal care products) have been detected in waters across the United States. The objective of this study was to evaluate point sources of ECs along the Colorado River, from the headwaters in Colorado to the Gulf of California. At selected locations in the Colorado River Basin (sites in Colorado, Utah, Nevada, Arizona, and California), waste stream tributaries and receiving surface waters were sampled using either grab sampling or polar organic chemical integrative samplers (POCIS). The grab samples were extracted using solid-phase cartridge extraction (SPE), and the POCIS sorbents were transferred into empty SPEs and eluted with methanol. All extracts were prepared for, and analyzed by, liquid chromatography–electrospray-ion trap mass spectrometry (LC–ESI-ITMS). Log DOW values were calculated for all ECs in the study and compared to the empirical data collected. POCIS extracts were screened for the presence of estrogenic chemicals using the yeast estrogen screen (YES) assay. Extracts from the 2008 POCIS deployment in the Las Vegas Wash showed the second highest estrogenicity response. In the grab samples, azithromycin (an antibiotic) was detected in all but one urban waste stream, with concentrations ranging from 30 ng/L to 2800 ng/L. Concentration levels of azithromycin, methamphetamine and pseudoephedrine showed temporal variation from the Tucson WWTP. Those ECs that were detected in the main surface water channels (those that are diverted for urban use and irrigation along the Colorado River) were in the region of the limit-of-detection (e.g., 10 ng/L), but most were below detection limits.

  1. Corrective Action Decision Document for Corrective Action Unit 516: Septic Systems and Discharge Points, Nevada Test Site, Nevada: Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office

    2004-04-28

    This Corrective Action Decision Document (CADD) identifies and rationalizes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office's selection of a recommended corrective action alternative appropriate to facilitate the closure of Corrective Action Unit (CAU) 516: Septic Systems and Discharge Points, Nevada Test Site (NTS), Nevada, under the Federal Facility Agreement and Consent Order. Located in Areas 3, 6, and 22 on the NTS, CAU 516 includes six Corrective Action Sites (CASs) consisting of two septic systems, a sump and piping, a clean-out box and piping, dry wells, and a vehicle decontamination area. Corrective action investigation activities were performed from July 22 through August 14, 2003, with supplemental sampling conducted in late 2003 and early 2004. The potential exposure pathways for any contaminants of concern (COCs) identified during the development of the DQOs at CAU 516 gave rise to the following objectives: (1) prevent or mitigate exposure to media containing COCs at concentrations exceeding PALs as defined in the corrective action investigation plan; and (2) prevent the spread of COCs beyond each CAS. The following alternatives have been developed for consideration at CAU 516: Alternative 1 - No Further Action; Alternative 2 - Clean Closure; and Alternative 3 - Closure in Place with Administrative Controls. Alternative 1, No Further Action, is the preferred corrective action for two CASs (06-51-02 and 22-19-04). Alternative 2, Clean Closure, is the preferred corrective action for four CASs (03-59-01, 03-59-02, 06-51-01, and 06-51-03). The selected alternatives were judged to meet all requirements for the technical components evaluated, as well as meeting all applicable state and federal regulations for closure of the site and will further eliminate the contaminated media at CAU 516.

  2. Point-of-care testing on admission to the intensive care unit: lactate and glucose independently predict mortality.

    Science.gov (United States)

    Martin, Jan; Blobner, Manfred; Busch, Raymonde; Moser, Norman; Kochs, Eberhard; Luppa, Peter B

    2013-02-01

    The aim of the study was to retrospectively investigate whether parameters of routine point-of-care testing (POCT) predict hospital mortality in critically ill surgical patients on admission to the intensive care unit (ICU). Arterial blood analyses of 1551 patients on admission to the adult surgical ICU of the Technical University Munich were reviewed. POCT was performed on a blood gas analyser. The association between acid-base status and mortality was evaluated. Metabolic acidosis was defined by base excess (BE) lactate >50% of BE, anion gap (AG)-acidosis by AG >16 mmol/L, hyperchloraemic acidosis by chloride >115 mmol/L. Metabolic alkalosis was defined by BE ≥3 mmol/L. Logistic regression analysis identified variables independently associated with mortality. Overall mortality was 8.8%. Mortality was greater in male patients (p=0.012). Mean age was greater in non-survivors (p55 mm Hg (mortality 23.1%). Three hundred and seventy-seven patients presented with acidosis (mortality 11.4%), thereof 163 patients with lactic acidosis (mortality 19%). Mortality for alkalosis (174 patients) was 12.1%. Mean blood glucose level for non-survivors was higher compared to survivors (plactate, glucose, age, male gender as independent predictors of mortality. Lactate and glucose on ICU admission independently predict mortality. BE and AG failed as prognostic markers. Lactic acidosis showed a high mortality rate implying that lactate levels should be obtained on ICU admission. Prevalence of hyperchloraemic acidosis was low. Metabolic alkalosis was associated with an increased mortality. Further studies on this disturbance and its attendant high mortality are warranted.

  3. A summary of the Three Mile Island accident: from zero hour to lessons for the future

    International Nuclear Information System (INIS)

    Oliveira, L.F.S. de; Oliveira Barroso, A.C. de

    The accident that occured at the Three Mile Island nuclear power plant, unit 2 (TMI-2) in March 1979 is analysed. The main events that occured during the accident are described in detail. The main project features of TMI-2 and Angra-1 nuclear power plant, Brazil are compared and analysed. (L.F.S.) [pt

  4. US Department of Energy Three Mile Island research and development program: Annual report, 1986

    Energy Technology Data Exchange (ETDEWEB)

    None

    1987-04-01

    Defueling of the Three Mile Island Unit 2 (TMI-2) reactor continued through 1986. This report summarizes this work and other TMI-2 related cleanup, research, and development activities. Other major topics include: core stratification sampling and other data acquisition tasks, the fuel shipping program, waste immobilization and management, decontamination and dose reduction, and future uses and applications of TMI-2 data.

  5. The lessons of Three Mile Island - public acceptance of nuclear power

    International Nuclear Information System (INIS)

    Jordan, T.R.

    1979-01-01

    An evaluation is given of the effects which the accident at Three Mile Island has had on public acceptance of nuclear power in the United States. Furthermore the impact of the changes in public acceptance on the financing of nuclear power projects is assessed. (author)

  6. US Department of Energy Three Mile Island research and development program: Annual report, 1986

    International Nuclear Information System (INIS)

    1987-04-01

    Defueling of the Three Mile Island Unit 2 (TMI-2) reactor continued through 1986. This report summarizes this work and other TMI-2 related cleanup, research, and development activities. Other major topics include: core stratification sampling and other data acquisition tasks, the fuel shipping program, waste immobilization and management, decontamination and dose reduction, and future uses and applications of TMI-2 data

  7. Three Mile Island technical information and examination program instrumentation and electrical summary report

    International Nuclear Information System (INIS)

    Meininger, R.D.

    1985-07-01

    This report summarizes the investigations on instrumentation and electrical systems that were subjected to a loss-of-coolant accident environment during and following the accident at Three Mile Island Unit-2 (TMI-2) on March 28, 1979. The report is a summary of information previously published in GEND-INF reports, plus current knowledge of the investigators

  8. Implementation of hazard analysis and critical control point (HACCP) system in a food service unit serving immuno-suppressed patient diets / E.E. Vermeulen

    OpenAIRE

    Vermeulen, Emma Emmerenza

    2006-01-01

    Main aim: To supply recommendations to implement a Hazard Analysis of Critical Control Points (HACCP) system in a hospital food service unit serving low bacterial diets in order to prevent or decrease the infection rates in Hematopoietic Stem Cell Transplant (HSCT) patients. Objectives: Firstly, to investigate the current food safety and hygiene status in a hospital food service unit, serving low bacterial diets, by means of a questionnaire and bacterial swabs taken from the...

  9. Use of the submerged demineralizer system at Three Mile Island

    International Nuclear Information System (INIS)

    Hofstetter, K.J.; Hitz, C.G.

    1983-01-01

    The Submerged Demineralizer System (SDS) has been used at Three Mile Island-Unit 2 (TMI-2) to process more than 1.5 million gallons of water contaminated as a result of the March, 1979 accident. The SDS has processed approximately 315,000 gallons of water accumulated in tanks in the Auxiliary Building, approximately 650,000 gallons of water that existed in the Reactor Containment Building basement, approximately 90,000 gallons of primary reactor coolant (processed in a bleed and feed mode) and approximately 169,000 gallons of water used in the large scale decontamination of the Reactor Building. During its operation, the SDS has immobilized approximately 340,000 curies of the principal fission products 137 Cs, 134 Cs and 90 Sr on inorganic media (zeolite). Processing summaries and performance evaluations are presented. 12 references, 1 figure, 6 tables

  10. Drop tests of the Three Mile Island knockout canister

    International Nuclear Information System (INIS)

    Box, W.D.; Aaron, W.S.; Shappert, L.B.; Childress, P.C.; Quinn, G.J.; Smith, J.V.

    1987-01-01

    A type of Three Mile Island Unit 2 (TMI-2) defueling canister, called a ''knockout'' canister, was subjected to a series of drop tests at the Oak Ridge National Laboratory's Drop Test Facility. These tests confirmed the structural integrity of internal fixed neutron poisons in support of a request for NRC licensing of this type of canister for the shipment of TMI-2 reactor fuel debris to the Idaho National Engineering Laboratory (INEL) for the Core Examination R and D Program. This report presents the data generated and the results obtained from a series of four drop tests that included two drops with the test assembly in the vertical position and two drops with the assembly in the horizontal position

  11. SOLIDARIEDADE SOCIAL : as ponderações de Émile Durkheim

    Directory of Open Access Journals (Sweden)

    Marta do Socorro Sousa de Araujo

    2005-01-01

    Full Text Available Analysis of the forms of social solidarity pointed by Émile Durkheim as a part of the principle of the social integration through as the balance and of t he social cohesion, indispensable considered aspects to the good operation of the society.

  12. US Department of Energy Three Mile Island research and development program. 1985 annual report

    International Nuclear Information System (INIS)

    Brown, G.R.

    1986-04-01

    In 1985, the US Department of Energy's Three Mile Island Research and Development Program at Three Mile Island Unit 2 (TMI-2), the Idaho National Engineering Laboratory, and other supporting laboratories, concentrated on three major areas: fuel and waste handling and disposition, accident evaluation, and reactor evaluation. While the general technology being developed is of direct benefit to the recovery operations at TMI-2, this technology will be of generic benefit to the entire nuclear power industry. Others engaged in research and development, design, construction, operation, maintenance, and regulation of nuclear plants will have access to this technology to enhance plant safety and reliability

  13. Nitel Veri Analizinde Miles-Huberman Modeli

    OpenAIRE

    Baltacı, Ali

    2018-01-01

    Buaraştırmada, nitel araştırmalarda kullanılan veri analizi yöntemlerindenMiles-Huberman modelinin kuramsal temelleri ve uygulamaya yönelik stratejileriele alınmıştır. Bu çalışma özünde nitelveri analizinde araştırmacıların sıklıkla yöntembilim eksikliklerinden doğanuygulama sorunlarına karşı kavramsal bir zemin oluşturmayı hedeflemiştir.Çalışma ile nitel araştırma verilerinin analizinde eksikliği hissedilen kavramsalzemin oluşturulacak ve uygulamaya dönük stratejiler üzerinde durulacaktır. B...

  14. the accident at Three Mile Island

    International Nuclear Information System (INIS)

    Torrey, L.

    1979-01-01

    The recently published final report of the President's Commision on the accident at Three Mile Island (TMI) is considered. In the report the power utilities and the US Nuclear Regulatory Commission (NRC) are severely criticised for being 'unable to provide an acceptable level of safety in nuclear power' which is reflected in the operators lack of training and understanding in depth. The 44 recommendations of the Commission include the abolition of the NRC, periodic renewal of operating licences, the siting of all future nuclear power plants away from large population centres, emergency response procedures to be improved and the revamping of warning display panels in control rooms. The commission also evaluated the severity of the accident and endeavoured to determine how close TMI came to a total catastrophic meltdown. The role of the media in the accident was also considered. (UK)

  15. 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

  16. Wolf Point Substation, Roosevelt County, Montana

    International Nuclear Information System (INIS)

    1991-05-01

    The Western Area Power Administration (Western), an agency of the United States Department of Energy, is proposing to construct the 115-kV Wolf Point Substation near Wolf Point in Roosevelt County, Montana (Figure 1). As part of the construction project, Western's existing Wolf Point Substation would be taken out of service. The existing 115-kV Wolf Point Substation is located approximately 3 miles west of Wolf Point, Montana (Figure 2). The substation was constructed in 1949. The existing Wolf Point Substation serves as a ''Switching Station'' for the 115-kV transmission in the region. The need for substation improvements is based on operational and reliability issues. For this environmental assessment (EA), the environmental review of the proposed project took into account the removal of the old Wolf Point Substation, rerouting of the five Western lines and four lines from the Cooperatives and Montana-Dakota Utilities Company, and the new road into the proposed substation. Reference to the new proposed Wolf Point Substation in the EA includes these facilities as well as the old substation site. The environmental review looked at the impacts to all resource areas in the Wolf Point area. 7 refs., 6 figs

  17. Experimenting with sodar in support of emergency preparedness at Three Mile Island-1

    International Nuclear Information System (INIS)

    Heck, W.J.

    1989-01-01

    In November 1988 at Three Mile Island Unit 1 (TMI-1), GPU Nuclear successfully completed the annual drill-for-grade that, from a modeling point of view, broke new ground for this plant. The meteorological and modeling aspects of the drill scenario were unprecedented for two reasons. First, the plume was buoyant and rose far above the height of the meteorological tower located at TMI. Second, the wind direction data from the meteorological tower were not representative of the wind direction at plume height. In the drill scenario, the buoyant plume resulted from a steam generator tube rupture where the steam ejects directly into the atmosphere via safety relief valves. Plume modeling indicated that the plume would rise to 400 ft, given the scenario meteorology. Wind data from the on-site meteorological tower, however, was only available up to 150 ft. Comparisons of sodar and tower winds were made for various weather conditions. Sodar results were studied in detail during light, moderate, and high winds; various wind directions; occurrences of rain and snow; and by time of day to determine effects of diurnal meteorological conditions on sodar performance

  18. Entiat 4Mile WELLs Completion Report, 2006.

    Energy Technology Data Exchange (ETDEWEB)

    Malinowksi, Richard

    2007-01-01

    The Entiat 4-mile Wells (Entiat 4-mile) project is located in the Entiat subbasin and will benefit Upper Columbia steelhead, spring Chinook and bull trout. The goal of this project is to prevent juvenile fish from being diverted into an out-of-stream irrigation system and to eliminate impacts due to the annual maintenance of an instream pushup dam. The objectives include eliminating a surface irrigation diversion and replacing it with two wells, which will provide Bonneville Power Administration (BPA) and the Bureau of Reclamation (Reclamation) with a Federal Columbia River Power System (FCRPS) BiOp metric credit of one. Wells were chosen over a new fish screen based on biological benefits and costs. Long-term biological benefits are provided by completely eliminating the surface diversion and the potential for fish entrainment in a fish screen. Construction costs for a new fish screen were estimated at $150,000, which does not include other costs associated with implementing and maintaining a fish screening project. Construction costs for a well were estimated at $20,000 each. The diversion consisted of a pushup dam that diverted water into an off-channel pond. Water was then pumped into a pressurized system for irrigation. There are 3 different irrigators who used water from this surface diversion, and each has multiple water right claims totaling approximately 5 cfs. Current use was estimated at 300 gallons per minute (approximately 0.641 cfs). Some irrigated acreage was taken out of orchard production less than 5 years ago. Therefore, approximately 6.8 acre-feet will be put into the State of Washington Trust Water Right program. No water will be set aside for conservation savings. The construction of the two irrigation wells for three landowners was completed in September 2006. The Lower Well (Tippen/Wick) will produce up to 175 gpm while the Upper Well (Griffith) will produce up to 275 gpm during the irrigation season. The eight inch diameter wells were

  19. Memories of MilesMiles Blackwell and his contribution to South African librarianship

    Directory of Open Access Journals (Sweden)

    A.S.C. Hooper

    2010-01-01

    Full Text Available The contribution of BH Blackwell (BHB, and specifically of Miles Blackwell, to the development of libraries and librarians in South Africa is explored based on available literature sources and personal reminiscences. This article tells how Miles was true to his personal values and how he demonstrated his integrity in the exercise of his office. Miles integrated in his mind the history of the “firm” of BHB and the times that it lived though with his sense of his responsibility to his customers. He was prepared to stand up against enormous political pressure from his peers in Europe and North America, and perhaps his fellow board members in BHB, to make sure that the channels of published information flow remained open to his customers in South Africa. The value of books and information was what he believed in. His service to his customers in South Africa reflected the self-sacrificing service ethic that he understood to be the essence of the family firm of which he had the great privilege of leading. He contributed to the development of the new, post-apartheid South Africa by ensuring that the people who needed the enlightened word to become part of the global society, benefited by what he had done.

  20. Unit 1 and Unit 2 Nuclear Power Plant Mochovce construction finishing from primary contractor of technological part. Skoda Praha a. s. point of view

    International Nuclear Information System (INIS)

    Horky, F.

    2000-01-01

    In this paper the history of delivery of technological part for NPP V-1 Mochovce as well as of reconstruction and safety improvements by the Skoda Praha a.s. is presented. Primary contractor of technological part Skoda Praha together with its final suppliers proved ability to realize under hard conditions such a complicated work what was indisputedly Units 1 and 2 finishing. Company proved capability to conform itself flexibly in the course of work to requirements of customer for realization of safety measures which means that Units 1 and 2 fully satisfy international standards. By fulfilment of primary contractor of technology obligations and above all by takeover of complex responsibility for both Units putting in operation including responsibility for 'past' Skoda Praha put away one of basic problems which occurred in decision making to whom will be assigned construction finishing contract. These facts fully qualify Skoda Praha to be selected for possible Units 3 and 4 construction finishing as one of chief construction finishing participant

  1. Arms control is everyone`s business: The United States and the United Nations at the mid-point of the 1990`s

    Energy Technology Data Exchange (ETDEWEB)

    Lehman, R.F. II

    1993-03-01

    This presentation encourages current efforts in arms control, non- proliferation, and peacekeeping. Verification is heralded as a confidence building method to bring about more openness in international relations. It is purported that openness has already enhanced democratic forces around the world. The insistence on strict compliance with the decisions of the United Nations Security Council is a show of support for international law. It is recommended that international norms on human rights, non-proliferation, and non-aggression be strengthened.

  2. 77 FR 16278 - License Renewal Application for Indian Point Nuclear Generating Units 2 and 3; Entergy Nuclear...

    Science.gov (United States)

    2012-03-20

    ... contacting the NRC about the availability of information regarding this document. You may access information... the Village of Buchanan, New York. The current operating licenses for IP2 and IP3 expire on September... units of measure; (2) a new thermal study that characterizes the thermal plume of cooling water...

  3. Draft environmental statement related to steam-generator repair at Point Beach Nuclear Plant, Unit No. 1. Docket No. 50-266

    International Nuclear Information System (INIS)

    1983-07-01

    The staff has considered the environmental impacts and economic costs of the proposed steam generator repair at the Point Beach Nuclear Plant Unit No. 1 along with reasonable alternatives to the proposed action. The staff has concluded that the proposed repair will not significantly affect the quality of the human environment and that there are no preferable alternatives to the proposed action. Furthermore, any impacts from the repair program are outweighed by its benefits

  4. Final environmental statement related to steam-generator repair at Point Beach Nuclear Plant, Unit No. 1 (Docket No. 50-266)

    International Nuclear Information System (INIS)

    1983-09-01

    The staff hhas considered the environental impacts and economic costs of the proposed steam generator repair at the Point Beach Nuclear Plant, Unit No. 1 along with reasonable alternatives to the proposed action. The staff has concluded that the proposed repair will not significantly affect the quality of the human environment and that there are no preferable alternatives to the proposed action. Furthermore, any impacts from the repair program are outweighed by its benefits

  5. Chronic Stress and Three Mile Island: Toxic Exposure and Uncertainty.

    Science.gov (United States)

    Davidson, Laura M.; And Others

    Although many researchers expected the psychological effects of the accident at the Three Mile Island (TMI) nuclear plant to be short-lived, area residents continued to show elevated levels of stress. To examine stress levels of TMI residents 28 months after the accident, 141 subjects were chosen from nearby areas, and from a town 80 miles away.…

  6. Infection control in neonatal intensive care unit : from a certified nurse in infection control's point of view

    OpenAIRE

    坂木, 晴世

    2007-01-01

    Neonates, especially those in neonatal intensive care units (NICU), are at high risk for infection. And nosocomial infections are responsible for almost 50% of the deaths that occur beyond 2 weeks of age. Advances in neonatal intensive care have resulted in survival of more low birth weight and sick infants. On the other hand, infection control measures in NICU are hard to say that we established. Therefore it is often that infection control measure in NICU of our country is taken in original...

  7. WWER-1000 unit reliability problems from the point of view of the main supplier of technological equipment

    International Nuclear Information System (INIS)

    Bursa, V.; Holousova, M.; Turnik, S.

    1990-01-01

    At Skoda Works in Plzen, data from the period of construction of nuclear power plants are processed on an ICL DRS 300 computer. The database systems DBASE II and DATAFLEX are available for creating reliability information systems. The information system that is being developed for WWER-1000 units is tested at the WWER-440 units of the Dukovany and Mochovce nuclear power plants. Activities in the field of evaluation of structure reliability of WWER-1000 nuclear power plants are aimed at two major goals, viz., developing a methodology for testing the reliability of the whole unit and its subsystems, and performing reliability analysis and calculations of reliability indices of the secondary circuit of a WWER-1000 nuclear power plant. The reason for the latter concern is the fact that in 1984-1986, secondary circuits contributed 46% to failures of Czechoslovak WWER-440 nuclear power plants. According to existing analyses, the time fluctuations of reliability indices obey no rule that could be employed for inferring indices expected in steady-state operating conditions from indices established in the starting stage of operation. (Z.M.). 10 refs

  8. What does it mean to be average? : the miles per gallon versus gallons per mile paradox revisited

    NARCIS (Netherlands)

    Haans, A.

    2008-01-01

    In the efficiency paradox, which was introduced by Hand (1994; J R Stat Soc A, 157, 317-356), two groups of engineers are in disagreement about the average fuel efficiency of a set of cars. One group measured efficiency on a miles per gallon scale, the other on a gallons per mile scale. In the

  9. 78 FR 77592 - Safety Zone; Lower Mississippi River Mile 94.1-Mile 95.1; New Orleans, LA

    Science.gov (United States)

    2013-12-24

    ... 1625-AA00 Safety Zone; Lower Mississippi River Mile 94.1-Mile 95.1; New Orleans, LA AGENCY: Coast Guard... zone is prohibited unless specifically authorized by the Captain of the Port New Orleans or a... temporary rule, call Lieutenant Commander (LCDR) Brandon Sullivan, Sector New Orleans, at (504) 365-2281 or...

  10. 78 FR 36660 - Safety Zone; Mississippi River Mile 95.5-Mile 96.5; New Orleans, LA

    Science.gov (United States)

    2013-06-19

    ...-AA00 Safety Zone; Mississippi River Mile 95.5-Mile 96.5; New Orleans, LA AGENCY: Coast Guard, DHS... of the Port New Orleans or a designated representative. DATES: This rule is effective from 9:45 p.m... email Lieutenant Commander (LCDR) Brandon Sullivan, Sector New Orleans, U.S. Coast Guard; telephone (504...

  11. Miles better? how 'fair miles' stack up in the sustainable supermarket

    Energy Technology Data Exchange (ETDEWEB)

    Garside, Ben; MacGregor, James; Vorley, Bill

    2007-12-15

    In 2007, 'food miles' shot to the top of consumer concerns in the UK. Buying goods that took the shortest route from farm to table was widely seen as a way of shrinking carbon footprints. This left airfreighted produce singled out as the epitome of unsustainable consumption, and some UK retailers began to label flown items such as green beans from Kenya. Yet looking at the bigger picture, fresh produce airfreighted from Africa accounts for less than 0.1 per cent of UK emissions, and per capita emissions from sub-Saharan Africa are minuscule compared to those in industrialised countries. Against this background are the million-plus African livelihoods supported by growing the produce. Within the grocery supply chain the time is ripe for 'fair miles' — a working idea that puts development in the South on the environmental agenda, and allows UK retailers a more balanced response on behalf of their millions of customers.

  12. Contemporary management of cleft lip and palate in the United Kingdom. Have we reached the turning point?

    Science.gov (United States)

    Colbert, S D; Green, Ben; Brennan, P A; Mercer, N

    2015-09-01

    Babies born with clefts of the lip, and the alveolus or palate, or both, require multidisciplinary, highly specialised treatment from birth to early adulthood. We review the contemporary management of clefts and outline the current treatment protocol adopted by cleft networks in the United Kingdom. We also look at the level of evidence and the restructuring of services that has defined current practice. In light of the recent Cleft Care UK study, we ask whether it is now time to adopt a new philosophy towards the surgical techniques that are used. Copyright © 2015 The British Association of Oral and Maxillofacial Surgeons. Published by Elsevier Ltd. All rights reserved.

  13. US Department of Energy Three Mile Island Research and Development Program: 1987 annual report

    International Nuclear Information System (INIS)

    1988-04-01

    Defueling of the Three Mile Island Unit 2 (TMI-2) reactor continued through 1987. This report summarizes this work and other TMI-2 related cleanup, research, and development activities. Other major topics include: Waste immobilization; Core transportation, receipt, and storage; Abnormal waste; Accident Evaluation and Technical Integration Programs; and Future uses and applications of TMI-2 data. While the technology being developed is of direct benefit to the recovery operations at TMI-2, it will also benefit the entire nuclear power industry

  14. Three Mile Island - The hour-by-hour account of what really happened

    International Nuclear Information System (INIS)

    Stephens, M.

    1980-01-01

    An hour-by-hour account is given of the progression of events leading up to and during the accident at the Three Mile Island Unit 2 reactor. The emergency procedures followed, the evacuation of local residents and the decisions taken as the possibility of a meltdown became apparent are recorded in detail together with aspects of the media coverage and the problems of communication. (U.K.)

  15. Drop tests of the Three Mile Island knockout canister

    International Nuclear Information System (INIS)

    Box, W.D.; Aaron, W.S.; Shappert, L.B.; Childress, P.C.; Quinn, G.J.; Smith, J.V.

    1986-09-01

    A type of Three Mile Island Unit 2 (TMI-2) defueling canister, called a ''knockout'' canister, was subjected to a series of drop tests at the Oak Ridge National Laboratory's Drop Test Facility. These tests were designed to confirm the structural integrity of internal fixed neutron poisons in support of a request for NRC licensing of this type of canister for the shipment of TMI-2 reactor fuel debris to the Idaho National Engineering Laboratory (INEL) for the Core Examination R and D Program. Work conducted at the Oak Ridge National Laboratory included (1) precise physical measurements of the internal poison rod configuration before assembly, (2) canister assembly and welding, (3) nondestructive examination (an initial hydrostatic pressure test and an x-ray profile of the internals before and after each drop test), (4) addition of a simulated fuel load, (5) instrumentation of the canister for each drop test, (6) fabrication of a cask simulation vessel with a developed and tested foam impact limiter, (7) use of refrigeration facilities to cool the canister to well below freezing prior to three of the drops, (8) recording the drop test with still, high-speed, and normal-speed photography, (9) recording the accelerometer measurements during impact, (10) disassembly and post-test examination with precise physical measurements, and (11) preparation of the final report

  16. [Reducing occupational burnout and enhancing job performance in new nurses: the efficacy of "last mile" programs].

    Science.gov (United States)

    Wu, Hsiu-Mei; Liu, Pei-Fen; Ho, Hsueh-Hua; Chen, Ping-Ling; Chao, Hui-Lin; Chen, Hsiao-Lien

    2012-08-01

    -commitment, with associated Cronbach's α ranging from .84-.90. Data was collected at one, three, and six months after employment. Repeated measures ANOVA and an independent t-test were used to analyze data. The average age of the 123 participants surveyed was 23 years, with no differences identified between last-mile and non-last-mile groups in terms of education level, work unit, or other demographic variables. New nurses who participated in the last mile program achieved significantly higher performance scores for job-task support, volunteering for additional duties, and overall task and contextual performance than those who did not. Last-mile-program group participants also had significantly lower client-related burnout than their non-last-mile-program peers. The last mile program facilitates new nurses' contextual performance and reduces incidence of care burnout. The cooperative education model linking universities and hospitals can be a positive component in a new nurse retention strategy for hospital administrators and educators.

  17. Technical evaluation of the electrical, instrumentation, and control design aspects of the low temperature overpressure protection system for the Point Beach Nuclear Power Plant, Units 1 and 2

    International Nuclear Information System (INIS)

    Laudenbach, D.H.

    1979-03-01

    The technical evaluation is presented for the electrical, instrumentation, and control design aspects of the low temperature overpressure protection system for the Point Beach nuclear power plant, Units 1 and 2. Design basis criteria used to evaluate the acceptability of the system included operator action, system testability, single failure criterion, and seismic Category I and IEEE Std-279-1971 criteria. This report is supplied as part of the Selected Electrical, Instrumentation, and Control Systems Issues Support Program being conducted for the U.S. Nuclear Regulatory Commission by Lawrence Livermore Laboratory

  18. Technical evaluation of the electrical, instrumentation, and control design aspects of the low temperature overpressure protection system for the Point Beach Nuclear Power Plant, Units 1 and 2

    Energy Technology Data Exchange (ETDEWEB)

    Laudenbach, D.H.

    1979-03-01

    The technical evaluation is presented for the electrical, instrumentation, and control design aspects of the low temperature overpressure protection system for the Point Beach nuclear power plant, Units 1 and 2. Design basis criteria used to evaluate the acceptability of the system included operator action, system testability, single failure criterion, and seismic Category I and IEEE Std-279-1971 criteria. This report is supplied as part of the Selected Electrical, Instrumentation, and Control Systems Issues Support Program being conducted for the U.S. Nuclear Regulatory Commission by Lawrence Livermore Laboratory.

  19. Nuclear power in the United States of America and in Europe - a market survey from a vendor's point of view

    International Nuclear Information System (INIS)

    Christopher, T.A.; Gueldner, R.

    2002-01-01

    A world population continuing to grow must be provided with sufficient energy supplies at acceptable prices and so as to affect the environment and the climate as little as possible. A growing energy requirement can be met sustainably by a diversified energy mix. Globally, there is a reassessment of nuclear power. Under aspects of the economy, protection of the environment and the climate, geological availability, and geopolitics, nuclear power will make valuable contributions to a solution. In the United States, the use of nuclear power has become attractive again in the course of deregulation and as a result of massive increases in plant availability. The nuclear power plants currently in operation offer a promising outlook for the future, also because of the current price increases for natural gas. As a consequence of the Green Paper by the EU Commission on the continuity of supply, nuclear power is being reassessed also in Europe. As a result of deregulation of the electricity market, efforts have been made to increase the competitiveness of existing generating capacities. In accordance with changed market conditions, producers have adapted to the requirements of the market by establishing strategic partnerships. The envisaged construction of a nuclear power plant in Finland shows that also new nuclear power plants can be attractive in deregulated European markets and that, e.g., also the problems of spent fuel and waste management can be solved if the political will exists to do so. In Germany, on the other hand, the political framework conditions for nuclear power continue to be difficult. Unless Germany is willing to fall behind internationally in power generation, all available types of power generation will have to be advanced and combined into a mix serving future needs also in this country. There must be no disruption of technological know-how. Nuclear power must be an important option kept open under reasonable political boundary conditions. (orig.) [de

  20. General description of the Three Mile Island nuclear power plant

    International Nuclear Information System (INIS)

    Figueras, J.M.

    1980-01-01

    A general description of systems and components of the Three Mile Island-2 nuclear power plant is presented, for the primary system (NSSS), the secondary system (BOP), the energy generation system and for other auxiliaries in the plant. (author)

  1. The psychological impact of the Three Mile Island incident.

    Science.gov (United States)

    Cleary, P D; Houts, P S

    1984-01-01

    This study examines the psychological impact of the Three Mile Island incident. The results are based on data from a panel study of 403 persons living within five miles of Three Mile Island (TMI), and a telephone survey of 1,506 people living within 55 miles of that area. Active coping strategies were associated with continued high levels of distress. Having more friends was related to reduced distress, but introspection, taking protective actions, being active in organizations, and seeking out others were all related to higher levels of distress. High self-esteem was related to a decrease in symptoms and psychotropic drug use, and avoidance behaviors were related to higher than expected numbers of symptoms. Efforts to profile those who used different coping strategies were relatively unsuccessful. The results emphasize the need to consider the nature of the stressor when developing models of coping and response to stressful situations.

  2. The health effects of the accident at Three Mile Island

    International Nuclear Information System (INIS)

    Fabrikant, J.I.

    1988-01-01

    The major healt effect of the accident at Three Mile Island was that of a pronounced demoralizing effect on the general population living in the Three Mile Island area, including teenagers and mothers of preschool children, and the nuclear plant workers. However, this effect has proved transient in all groups studied except the nuclear workers, who continued to show relatively high levels of demoralization some months after the accident. Moreover, the groups in the general population and the workers, in their differen ways, had continuing problems of trust that stemmed directly from the Three Mile Island accident. For both the nuclear workers and general population, the mental health and behavioral effects are understandable in terms of the objective realities of the threats they faced during the nuclear accident at Three Mile Island

  3. Psychological impact of the Three Mile Island incident

    International Nuclear Information System (INIS)

    Cleary, P.D.; Houts, P.S.

    1984-01-01

    This study examines the psychological impact of the Three Mile Island incident. The results are based on data from a panel study of 403 persons living within five miles of Three Mile Island (TMI), and a telephone survey of 1,506 people living within 55 miles of that area. Active coping strategies were associated with continued high levels of distress. Having more friends was related to reduced distress, but introspection, taking protective actions, being active in organizations, and seeking out others were all related to higher levels of distress. High self-esteem was related to a decrease in symptoms and psychotropic drug use, and avoidance behaviors were related to higher than expected numbers of symptoms. Efforts to profile those who used different coping strategies were relatively unsuccessful. The results emphasize the need to consider the nature of the stressor when developing models of coping and response to stressful situations

  4. Nuclear safety after Three Mile Island and Chernobyl

    International Nuclear Information System (INIS)

    Ballard, G.M.

    1988-01-01

    This book contains the proceedings on nuclear safety after Three Mile island and Chernobyl. Topics covered include: Design for safety; Man-machine interaction; Source terms and consequence; and accident response

  5. 33 CFR 207.249 - Ouachita and Black Rivers, Ark. and La., Mile 0.0 to Mile 338.0 (Camden, Ark.) above the mouth of...

    Science.gov (United States)

    2010-07-01

    ... not provided as part of the Red River Locks and Dams. When water levels rise to within 2 feet of the.... and La., Mile 0.0 to Mile 338.0 (Camden, Ark.) above the mouth of the Black River; the Red River, La., Mile 6.7 (Junction of Red, Atchafalaya and Old Rivers) to Mile 276.0 (Shreveport, La.); use...

  6. Health effects of the nuclear accident at Three Mile Island

    International Nuclear Information System (INIS)

    Fabrikant, J.I.

    1980-05-01

    Between March 28 and April 15, 1979 the collective dose resulting from the radioactivity released to the population living within a 50-mile radius of the Three Mile Island nuclear plant was about 2000 person-rems, less than 1% of the annual natural background level. The average dose to a person living within 5 miles of the nuclear plant was less than 10% of annual background radiation. The maximum estimated radiation dose received by any one individual in the general population (excluding the nuclear plant workers) during the accident was 70 mrem. The doses received by the general population as a result of the accident were so small that there will be no detectable additional cases of cancer, developmental abnormalities, or genetic ill-health. Three Three Mile Island nuclear workers received radiation doses of about 3 to 4 rem, exceeding maximum permissible quarterly dose of 3 rem. The major health effect of the accident at Three Mile Island was that of a pronounced demoralizing effect on the general population in the Three Mile Island area, including teenagers and mothers of preschool children and the nuclear plant workers. However, this effect proved transient in all groups studied except the nuclear workers

  7. Miles of Pipeline, Millimetres of Pool

    DEFF Research Database (Denmark)

    Mathieu, Chris

    2005-01-01

    This paper examines how basic cognitive processes lead to the non-recognition of processes that lead to or sustain gender inequality in the Information technology sector. The paper is based on empirical research carried out in Sweden and Ireland from 2001-2004. The central thesis is that "delusions...... can be overcome within organizations, and how this could lead to a greater recognition of the processes facilitating or causing gender inequality in a branch that frequently sees itself as "gender neutral" as well as measures to actively promote gender equality. Keywords: gender inequality......" about gender equality in the IT sector are sustained by positional factors (governing what one can see from a vantage point and what type of data one can, and one is encouraged to, gather and process); ideological factors (how information is "fit" into pre-existing frameworks to which one has political...

  8. Three Mile Island: a report to the commissioners and to the public

    International Nuclear Information System (INIS)

    Rogovin, M.

    1979-01-01

    Within weeks of the March 28, 1979 accident at Three Mile Island, the Nuclear Regulatory Commission (NRC) decided to institute a Special Inquiry to review and report on the accident. THe principal objectives of the inquiry were determined what happened and why, to assess the actions of utility and NRC personnel before and during the accident, and to identify deficiencies in the system and areas where further investigation might be warranted. The work of the Special Inquiry was not intended to duplicate the efforts of the President's Commission on the Accident at Three Mile Island. It was designed to enable the NRC to fulfill its regulatory responsibilities by achieving the fullest possible understanding of the accident, both from a technical point of view and from the standpoint of how the NRC's own regulatory processes functioned

  9. A comprehensive evaluation of two MODIS evapotranspiration products over the conterminous United States: using point and gridded FLUXNET and water balance ET

    Science.gov (United States)

    Velpuri, Naga M.; Senay, Gabriel B.; Singh, Ramesh K.; Bohms, Stefanie; Verdin, James P.

    2013-01-01

    Remote sensing datasets are increasingly being used to provide spatially explicit large scale evapotranspiration (ET) estimates. Extensive evaluation of such large scale estimates is necessary before they can be used in various applications. In this study, two monthly MODIS 1 km ET products, MODIS global ET (MOD16) and Operational Simplified Surface Energy Balance (SSEBop) ET, are validated over the conterminous United States at both point and basin scales. Point scale validation was performed using eddy covariance FLUXNET ET (FLET) data (2001–2007) aggregated by year, land cover, elevation and climate zone. Basin scale validation was performed using annual gridded FLUXNET ET (GFET) and annual basin water balance ET (WBET) data aggregated by various hydrologic unit code (HUC) levels. Point scale validation using monthly data aggregated by years revealed that the MOD16 ET and SSEBop ET products showed overall comparable annual accuracies. For most land cover types, both ET products showed comparable results. However, SSEBop showed higher performance for Grassland and Forest classes; MOD16 showed improved performance in the Woody Savanna class. Accuracy of both the ET products was also found to be comparable over different climate zones. However, SSEBop data showed higher skill score across the climate zones covering the western United States. Validation results at different HUC levels over 2000–2011 using GFET as a reference indicate higher accuracies for MOD16 ET data. MOD16, SSEBop and GFET data were validated against WBET (2000–2009), and results indicate that both MOD16 and SSEBop ET matched the accuracies of the global GFET dataset at different HUC levels. Our results indicate that both MODIS ET products effectively reproduced basin scale ET response (up to 25% uncertainty) compared to CONUS-wide point-based ET response (up to 50–60% uncertainty) illustrating the reliability of MODIS ET products for basin-scale ET estimation. Results from this research

  10. Development of 80- and 100- Mile Work Day Cycles Representative of Commercial Pickup and Delivery Operation

    Energy Technology Data Exchange (ETDEWEB)

    Duran, Adam W [National Renewable Energy Laboratory (NREL), Golden, CO (United States); Kelly, Kenneth J [National Renewable Energy Laboratory (NREL), Golden, CO (United States); Kresse, John [Cummins; Li, Ke [Cummins

    2018-04-03

    When developing and designing new technology for integrated vehicle systems deployment, standard cycles have long existed for chassis dynamometer testing and tuning of the powertrain. However, to this day with recent developments and advancements in plug-in hybrid and battery electric vehicle technology, no true 'work day' cycles exist with which to tune and measure energy storage control and thermal management systems. To address these issues and in support of development of a range-extended pickup and delivery Class 6 commercial vehicle, researchers at the National Renewable Energy Laboratory in collaboration with Cummins analyzed 78,000 days of operational data captured from more than 260 vehicles operating across the United States to characterize the typical daily performance requirements associated with Class 6 commercial pickup and delivery operation. In total, over 2.5 million miles of real-world vehicle operation were condensed into a pair of duty cycles, an 80-mile cycle and a 100-mile cycle representative of the daily operation of U.S. class 3-6 commercial pickup and delivery trucks. Using novel machine learning clustering methods combined with mileage-based weighting, these composite representative cycles correspond to 90th and 95th percentiles for daily vehicle miles traveled by the vehicles observed. In addition to including vehicle speed vs time drive cycles, in an effort to better represent the environmental factors encountered by pickup and delivery vehicles operating across the United States, a nationally representative grade profile and key status information were also appended to the speed vs. time profiles to produce a 'work day' cycle that captures the effects of vehicle dynamics, geography, and driver behavior which can be used for future design, development, and validation of technology.

  11. Sengstaken-Blakemore Tube: an extra mile

    Directory of Open Access Journals (Sweden)

    Tawfiq Taki Al Lawati

    2017-12-01

    Full Text Available Upper gastrointestinal bleeding (UGIB in children has multiple etiologies but fortunately is not encountered commonly by pediatricians. Aorto-esophageal fistula (AEF in children is a rare cause of UGIB and it is mainly secondary to accidental ingestion of foreign bodies, particularly disc batteries, or after cardiothoracic surgery. In this study, we report a case of a 3-year-old child who developed de novo AEF with no prior injury to the esophagus. The child presented with massive UGIB leading to hypovolemic shock, acute kidney injury, and cardiac arrest. The torrential bleed was controlled using a Sengstaken–Blakemore Tube (SBT, which allowed urgent chest CT angiography as well as subsequent thoracotomy and repair of the fistula Unfortunately, the child succumbed to repeated cardiac arrests secondary to the renal injury and severe acidosis. This case highlights the need for the early recognition of massive UGIB in children and the requirement to make appropriately sized SBTs available in all pediatric gastroenterology units.

  12. Inter-laboratory assessment by trained panelists from France and the United Kingdom of beef cooked at two different end-point temperatures.

    Science.gov (United States)

    Gagaoua, Mohammed; Micol, Didier; Picard, Brigitte; Terlouw, Claudia E M; Moloney, Aidan P; Juin, Hervé; Meteau, Karine; Scollan, Nigel; Richardson, Ian; Hocquette, Jean-François

    2016-12-01

    Eating quality of the same meat samples from different animal types cooked at two end-point cooking temperatures (55°C and 74°C) was evaluated by trained panels in France and the United Kingdom. Tenderness and juiciness scores were greater at 55°C than at 74°C, irrespective of the animal type and location of the panel. The UK panel, independently of animal type, gave greater scores for beef flavour (+7 to +24%, PFrench panel was higher at 74°C than at 55°C (+26%, Pcooking beef at a lower temperature increased tenderness and juiciness, irrespective of the location of the panel. In contrast, cooking beef at higher temperatures increased beef flavour and decreased abnormal flavour for the UK panelists but increased abnormal flavour for the French panel. Copyright © 2016 Elsevier Ltd. All rights reserved.

  13. The characters God and Hamlet by Jack Miles

    Directory of Open Access Journals (Sweden)

    Tania de Fátima da Silva

    2015-04-01

    Full Text Available In the book “God - A Biography,” Jack Miles aims to introduce ourselves Creator-God as a literary character. Miles developed a narrative based on concept aristotelian, in other words, the structure of the work is made from beginning to end. This procedure established a harmony arising from the interaction between the parties, which contributes to scrutinize the precise details of the story of the main protagonist. We decided to highlight that time some characteristics of the main character of the work and compare them to the character Hamlet, by William Shakespeare, because from the beginning of the narrative to completion Miles calls the reader’s attention to the play Shakespeare.

  14. Dr Kathryn Beers, Assistant Director Physical Sciences and Engineering, Office of Science and Technology Policy Executive Office of the President United States of America visit the CMS experiment at point 5.

    CERN Multimedia

    Maximilien Brice

    2007-01-01

    Dr Kathryn Beers, Assistant Director Physical Sciences and Engineering, Office of Science and Technology Policy Executive Office of the President United States of America visit the CMS experiment at point 5.

  15. H.E. Mr Ichiro Fujisaki Ambassador Extraordinary and Plenipotentiary Permanent Representative of Japan to the Office of the United Nations and the other international organisations in Geneva visit the LHCb Experiment at point 8.

    CERN Multimedia

    Maximilien Brice

    2007-01-01

    H.E. Mr Ichiro Fujisaki Ambassador Extraordinary and Plenipotentiary Permanent Representative of Japan to the Office of the United Nations and the other international organisations in Geneva visit the LHCb Experiment at point 8.

  16. 20 January 2014 - Members of the Regional Assemblies and Parliaments United Kingdom of Great Britain and Northern Ireland visiting the LHC tunnel at Point 8 with Technology Department, Vacuum, Surfaces and Coatings Group P. Cruikshank.

    CERN Document Server

    Pantelia, Anna

    2014-01-01

    20 January 2014 - Members of the Regional Assemblies and Parliaments United Kingdom of Great Britain and Northern Ireland visiting the LHC tunnel at Point 8 with Technology Department, Vacuum, Surfaces and Coatings Group P. Cruikshank.

  17. Corrective Action Decision Document for Corrective Action Unit 516: Septic Systems and Discharge Points, Nevada Test Site, Nevada, Rev. No.: 1 with ROTC 1

    Energy Technology Data Exchange (ETDEWEB)

    Alfred N. Wickline

    2004-04-01

    This Corrective Action Decision Document (CADD) has been prepared for Corrective Action Unit (CAU) 516, Septic Systems and Discharge Points, Nevada Test Site, Nevada, in accordance with the ''Federal Facility Agreement and Consent Order'' (1996). Corrective Action Unit 516 is comprised of the following Corrective Action Sites (CASs): (1) 03-59-01 - Bldg 3C-36 Septic System; (2) 03-59-02 - Bldg 3C-45 Septic System; (3) 06-51-01 - Sump and Piping; (4) 06-51-02 - Clay Pipe and Debris; (5) 06-51-03 - Clean Out Box and Piping; and (7) 22-19-04 - Vehicle Decontamination Area. The purpose of this CADD is to identify and provide the rationale for the recommendation of an acceptable corrective action alternative for each CAS within CAU 516. Corrective action investigation activities were performed between July 22 and August 14, 2003, as set forth in the Corrective Action Investigation Plan. Supplemental sampling was conducted in late 2003 and early 2004.

  18. Risk cognition and the public: case of Three Mile Island

    International Nuclear Information System (INIS)

    Cutter, S.L.

    1984-01-01

    Residents of within 50 miles of the nuclear power plant at Three Mile Island (TMI), Pennsylvania, were surveyed in 1979, 1980, and 1982 to assess their general attitudes toward nuclear power, to assess their individual coping responses to the March 1979 accident, and to monitor changes in attitudes over the three-year period. Most respondents feel that future accidents like TMI will occur one or twice more in their lifetimes, that operating nuclear power stations should have improved safeguards and should continue operating, and that major insitutions - government and utility companies - are experiencing a continued erosion of public trust

  19. Analysis of economic break-even point of the biogas utilization for electrical power conversion: case study in a swine terminated unit

    International Nuclear Information System (INIS)

    Cervi, Ricardo Ghantous; Pinotti, Elvio Brasil; Esperancini, Maura Seiko Tsutsui; Bueno, Osmar de Carvalho

    2010-01-01

    This work aimed to develop a study to estimate the break-even point in financial units of the electrical power generation using biogas from swine wastes. The analyzed biodigester is a continuous tubular model with brick concrete duct and plastic covering with a gasometer, and where the waste of 2,300 fattening pigs are deposited daily. The initial investment estimate for the installation was R$ 51,537.17. The system annual costs were R$ 5,708.20, for maintenance, R$ 4,390.40 for depreciation and R$ 1,366.77 for interests. It was noticed that with an average of consumption of 17.1 kW.hour -1 the system presents an annual loss of R$ 1,592.14 because the consumption of 27.85 kW.hour -1 is the minimum that should be consumed to achieve a corresponded financial break-even point of R$ 15,054.40.year -1 . It was concluded that the correct technical dimensioning greatly influences on the economic results. (author)

  20. Co-creation of market expansion in point-of-care testing in the United States: Industry leadership perspectives on the community pharmacy segment.

    Science.gov (United States)

    Hohmeier, Kenneth C; McDonough, Sharon L K; Wang, Junling

    Point-of-care testing (POCT) is a specialty of laboratory medicine that occurs at the bedside or near the patient when receiving health services. Despite its established clinical utility and consumer demand in the community pharmacy, the implementation of POCT within this setting has remained modest for a variety of reasons. One possible solution to this problem is the concept of co-creation - the partnership between consumer and manufacturer in the development of value for a service or device. Using the theoretical underpinning of co-creation, this study aimed to investigate perceptions of point-of-care-testing (POCT) industry leadership on the community pharmacy market in the United States to uncover reasons for limited implementation within community pharmacies. Participants were recruited for this study through the use of snowball sampling. A series of semi-structured interviews were conducted with the participants via telephone. Interviews were recorded, transcribed, and entered into a qualitative analysis software program to summarize the data. Five key themes were uncovered: gaps in understanding, areas of positive impact, barriers to implementation, facilitators of implementation, and community pharmacy - a potential major player. Through uncovering gaps in perceptions, it may be possible to leverage the U.S. pharmacy industry's size, potential for scalability, and ease of patient access to further patient care. Copyright © 2016 Elsevier Inc. All rights reserved.

  1. A Review of Last Mile Logistics Innovations in an Externalities Cost Reduction Vision

    Directory of Open Access Journals (Sweden)

    Luigi Ranieri

    2018-03-01

    Full Text Available In this paper, a review of the recent scientific literature contributions on innovative strategies for last mile logistics, focusing on externalities cost reduction, is presented. Transport is causing problems in urban areas, in particular in freight transport: modern cities need solutions to reduce externalities costs such as congestion, pollution and others, which have increased in the last few years, especially due to the growth of goods delivery. Online sales and globalization lead to new trends in freight transport, and moreover, a larger quantity of goods is expected to be delivered in the next future. In this context, most of the delivered goods end up in the city centers. Last mile logistics is the least efficient stage of the supply chain and comprises up to 28% of the total delivery cost. Therefore, the improvement of last mile logistics and a significant externalities reduction are very important challenges for researchers. New technologies and transport means, innovative techniques and organizational strategies allow handling in a more effective way the last mile delivery in urban areas. Based on the Systematic Literature Review (SLR method, recent papers that significantly contributed, with original proposals, to the reduction of externalities in urban logistics are identified and analyzed in this work. Furthermore, a classification of the papers dealing with the externality reduction problem is presented. It is consistent with a general formulation proposed to evaluate external costs in urban area. The innovative contributions are classified into five main categories: innovative vehicles, proximity stations or points, collaborative and cooperative urban logistics, optimization of transport management and routing, innovations in public policies and infrastructures. The new paradigm of smart logistics is based on the combination of these concepts and on the proposed innovations.

  2. Who pays the costs of industrial accidents like Three Mile Island

    International Nuclear Information System (INIS)

    Doub, W.O.; Shoemaker, J.R.

    1985-01-01

    The accident at Three Mile Island (TMI) nuclear unit 2 generating plant in Pennsylvania provides a case study on how losses resulting from large industrial accidents are allocated in society. TMI demonstrated that industry regulation, no matter how pervasive, can fail to prevent social harm, and that there are often costs beyond personal injuries and property damage. Although the Price-Anderson Act compensated the public, other insurance was inadequate to cover the losses of shareholders and ratepayers. When the $300 million property insurance proved inadequate, the industry raised property damage insurance to $1 billion and replacement power insurance to $250 million

  3. Three Mile Island nuclear generating station accident of March 28, 1979

    International Nuclear Information System (INIS)

    Aitken, J.H.; Johnson, A.C.; Kelly, R.J.; Wong, K.Y.

    1979-04-01

    The government of Ontario dispatched a Scientific Assessment Team to the Three Mile Island nuclear power plant to assess the consequences of an accident which occurred at unit 2 on 1979 March 28. The team's objectives were to acquire up-to-the-minute information concerning the accident, study the potential for environmental impacts on Ontario, observe the outcome of off-site emergency procedures, and offer assisance from Ontario should it appear of value. The findings, observations, and impressions of the team are summarized. (OST)

  4. Some public health lessons from Three Mile Island: a case study in chaos

    Energy Technology Data Exchange (ETDEWEB)

    Macleod, G K

    1981-01-01

    The March 28, 1979, nuclear reactor accident at Three Mile Island near Harrisburg, illustrated the inadequacy of Pennsylvania's public health sector in implementing emergency measures. Throughout the crisis, decisions impacting public health were made by engineers and physicists rather than by physicians. Recommendations to improve the preparedness of the state's public health department to handle future nuclear accidents include: developing a radiological emergency response plan for the health aspects of an accident/ establishing a radiation health unit/ collecting baseline data on the incidence of hypothyroidism around nuclear power plants/ and preparing potassium iodide for deployment and distribution.

  5. System calculations related to the accident at Three-Mile Island using TRAC

    International Nuclear Information System (INIS)

    Ireland, J.R.

    1980-01-01

    The Three Mile Island nuclear plant (Unit 2) was modeled using the Transient Reactor Analysis Code (TRAC-P1A) and a base case calculation, which simulated the initial part of the accident that occurred on March 28, 1979, was performed. In addition to the base case calculation, several parametric calculations were performed in which a single hypothetical change was made in the system conditions, such as assuming the high pressure injection (HPI) system operated as designed rather than as in the accident. Some of the important system parameter comparisons for the base case as well as some of the parametric case results are presented

  6. The East European Press and Three-Mile Island.

    Science.gov (United States)

    Johnson, Owen V.

    This report of the investigation into East European newspaper treatment of the accident at Pennsylvania's Three Mile Island nuclear power plant in the spring of 1979 focuses on the Czech and Slovak media, particularly on the Slovak Communist Party's daily newspaper, "Pravda." The response of the media of other East European countries to…

  7. Heads from "Post" and "Times" on Three-Mile Island.

    Science.gov (United States)

    Fenichel, Michael; Dan, Peter

    1980-01-01

    Reports that during the week of the 1979 crisis at the Three Mile Island nuclear power plant, the "New York Post" gave less factual information than "The New York Times" in both its main headlines and subheadlines; also notes that the information the "Post" did give was more sensationalized. (GT)

  8. Local Coverage of Three Mile Island during 1981-82.

    Science.gov (United States)

    Friedman, Sharon M.

    Local newspaper coverage of the Three Mile Island (TMI) nuclear power plant accident was examined in a study to determine what changes, if any, were made by local media and what lessons they had learned from it. Data were collected through interviews with 21 media representatives. TMI coverage in the six newspapers was examined using each…

  9. A brief review of the accident at Three Mile Island

    International Nuclear Information System (INIS)

    Corey, G.R.

    1979-01-01

    A question-and-answer format is used to discuss the Three Mile Reactor accident and the lessons learned. The aspects touched upon include the hydrogen bubble, the radiation levels the public was exposed to, and the consequences of the accident to the nuclear power program

  10. Some reactions to the accident at Three Mile Island

    International Nuclear Information System (INIS)

    Dunster, H.J.

    1980-01-01

    The accident at Three Mile Island is reviewed and those features which ought to encourage changes in UK practices identified. Emergency measurements, both on site and in the environment, siting considerations and possible trends in regulatory policy are dealt with. (author)

  11. Saving American democracy: the lessons of Three Mile Island

    International Nuclear Information System (INIS)

    Kemeny, J.C.

    1980-01-01

    The author's experience of serving with a presidential commission investigating the Three Mile Island nuclear accident leads to an observation that the only way to save American democracy is to change the fundamental decision-making process, at the Federal level, so that it can come to grips with the enormous and complex issues that face this nation

  12. Evolutionary Pattern of Improved 1-Mile Running Performance

    NARCIS (Netherlands)

    Foster, C.S.; de Koning, J.J.; Thiel, C.

    2014-01-01

    The official world records (WR) for the 1-mile run for men (3: 43.13) and for women (4: 12.58) have improved 12.2% and 32.3%, respectively, since the first WR recognized by the International Association of Athletics Federations. Previous observations have suggested that the pacing pattern for

  13. The Association of Exposure to Point-of-Sale Tobacco Marketing with Quit Attempt and Quit Success: Results from a Prospective Study of Smokers in the United States

    Science.gov (United States)

    Siahpush, Mohammad; Shaikh, Raees A.; Smith, Danielle; Hyland, Andrew; Cummings, K. Michael; Sikora Kessler, Asia; Dodd, Michael D.; Carlson, Les; Meza, Jane; Wakefield, Melanie

    2016-01-01

    The aim was to assess the association of exposure to point-of-sale (POS) tobacco marketing with quit attempt and quit success in a prospective study of smokers in the United States. Data were collected via telephone-interview on exposure to POS tobacco marketing, sociodemographic and smoking-related variables from 999 smokers in Omaha, Nebraska, in the United States. Exposure to POS tobacco marketing was measured by asking respondents three questions about noticing pack displays, advertisements, and promotions in their respective neighborhoods stores. These three variables were combined into a scale of exposure to POS tobacco marketing. About 68% of the respondents participated in a six-month follow-up phone interview and provided data on quit attempts and smoking cessation. At the six-month follow-up, 39.9% of respondents reported to have made a quit attempt, and 21.8% of those who made a quit attempt succeeded in quitting. Exposure to POS marketing at baseline was not associated with the probability of having made a quit attempt as reported at the six-month follow-up (p = 0.129). However, higher exposure to POS marketing was associated with a lower probability of quit success among smokers who reported to have attempted to quit smoking at six-month follow-up (p = 0.006). Exposure to POS tobacco marketing is associated with lower chances of successfully quitting smoking. Policies that reduce the amount of exposure to POS marketing might result in higher smoking cessation rates. PMID:26861379

  14. The Association of Exposure to Point-of-Sale Tobacco Marketing with Quit Attempt and Quit Success: Results from a Prospective Study of Smokers in the United States

    Directory of Open Access Journals (Sweden)

    Mohammad Siahpush

    2016-02-01

    Full Text Available The aim was to assess the association of exposure to point-of-sale (POS tobacco marketing with quit attempt and quit success in a prospective study of smokers in the United States. Data were collected via telephone-interview on exposure to POS tobacco marketing, sociodemographic and smoking-related variables from 999 smokers in Omaha, Nebraska, in the United States. Exposure to POS tobacco marketing was measured by asking respondents three questions about noticing pack displays, advertisements, and promotions in their respective neighborhoods stores. These three variables were combined into a scale of exposure to POS tobacco marketing. About 68% of the respondents participated in a six-month follow-up phone interview and provided data on quit attempts and smoking cessation. At the six-month follow-up, 39.9% of respondents reported to have made a quit attempt, and 21.8% of those who made a quit attempt succeeded in quitting. Exposure to POS marketing at baseline was not associated with the probability of having made a quit attempt as reported at the six-month follow-up (p = 0.129. However, higher exposure to POS marketing was associated with a lower probability of quit success among smokers who reported to have attempted to quit smoking at six-month follow-up (p = 0.006. Exposure to POS tobacco marketing is associated with lower chances of successfully quitting smoking. Policies that reduce the amount of exposure to POS marketing might result in higher smoking cessation rates.

  15. The Association of Exposure to Point-of-Sale Tobacco Marketing with Quit Attempt and Quit Success: Results from a Prospective Study of Smokers in the United States.

    Science.gov (United States)

    Siahpush, Mohammad; Shaikh, Raees A; Smith, Danielle; Hyland, Andrew; Cummings, K Michael; Kessler, Asia Sikora; Dodd, Michael D; Carlson, Les; Meza, Jane; Wakefield, Melanie

    2016-02-06

    The aim was to assess the association of exposure to point-of-sale (POS) tobacco marketing with quit attempt and quit success in a prospective study of smokers in the United States. Data were collected via telephone-interview on exposure to POS tobacco marketing, sociodemographic and smoking-related variables from 999 smokers in Omaha, Nebraska, in the United States. Exposure to POS tobacco marketing was measured by asking respondents three questions about noticing pack displays, advertisements, and promotions in their respective neighborhoods stores. These three variables were combined into a scale of exposure to POS tobacco marketing. About 68% of the respondents participated in a six-month follow-up phone interview and provided data on quit attempts and smoking cessation. At the six-month follow-up, 39.9% of respondents reported to have made a quit attempt, and 21.8% of those who made a quit attempt succeeded in quitting. Exposure to POS marketing at baseline was not associated with the probability of having made a quit attempt as reported at the six-month follow-up (p = 0.129). However, higher exposure to POS marketing was associated with a lower probability of quit success among smokers who reported to have attempted to quit smoking at six-month follow-up (p = 0.006). Exposure to POS tobacco marketing is associated with lower chances of successfully quitting smoking. Policies that reduce the amount of exposure to POS marketing might result in higher smoking cessation rates.

  16. The association of graduated driver licensing with miles driven and fatal crash rates per miles driven among adolescents.

    Science.gov (United States)

    Zhu, Motao; Cummings, Peter; Zhao, Songzhu; Coben, Jeffrey H; Smith, Gordon S

    2015-04-01

    Graduated driver licensing (GDL) laws are associated with reduced crash rates per person-year among adolescents. It is unknown whether adolescents crash less per miles driven or drive less under GDL policies. We used data from the US National Household Travel Survey and Fatality Analysis Reporting System for 1995-1996, 2001-2002 and 2008-2009. We compared adolescents subject to GDL laws with those not by estimating adjusted IRRs for being a driver in a crash with a death per person-year (aIRRpy) and per miles driven (aIRRm), and adjusted miles driven ratios (aMR) controlling for changes in rates over time. Comparing persons subject to GDL policies with those not, 16 year olds had fewer fatal crashes per person-year (aIRRpy 0.63, 95% CI 0.47 to 0.91), drove fewer miles (aMR 0.79, 95% CI 0.63 to 0.98) and had lower crash rates per miles driven (aIRRm 0.83, 95% CI 0.65 to 1.06). For age 17, the aIRRpy was 0.83 (95% CI 0.60 to 1.17), the aMR 0.80 (95% CI 0.63 to 1.03) and the aIRRm 1.03 (95% CI 0.80 to 1.35). For age 18, the aIRRpy was 0.93 (95% CI 0.72 to 1.19), the aMR 0.92 (95% CI 0.77 to 1.09) and the aIRRm 1.01 (95% CI 0.84 to 1.23). If these associations are causal, GDL laws reduced crashes per person-year by about one-third among 16 year olds; half the reduction was due to fewer crashes per miles driven and half to less driving. For ages 17 and 18, there was no evidence of reduced crash rates per miles driven. Published by the BMJ Publishing Group Limited. For permission to use (where not already granted under a licence) please go to http://group.bmj.com/group/rights-licensing/permissions.

  17. A Point Source of a Different Color: Identifying a Gap in United States Regulatory Policy for “Green” CSO Treatment Using Constructed Wetlands

    Directory of Open Access Journals (Sweden)

    Zeno F. Levy

    2014-04-01

    Full Text Available Up to 850 billion gallons of untreated combined sewer overflow (CSO is discharged into waters of the United States each year. Recent changes in CSO management policy support green infrastructure (GI technologies as “front of the pipe” approaches to discharge mitigation by detention/reduction of urban stormwater runoff. Constructed wetlands for CSO treatment have been considered among suites of GI solutions. However, these wetlands differ fundamentally from other GI technologies in that they are “end of the pipe” treatment systems that discharge from a point source, and are therefore regulated in the U.S. under the National Pollution Discharge Elimination System (NPDES. We use a comparative regulatory analysis to examine the U.S. policy framework for CSO treatment wetlands. We find in all cases that permitting authorities have used best professional judgment to determine effluent limits and compliance monitoring requirements, referencing technology and water quality-based standards originally developed for traditional “grey” treatment systems. A qualitative comparison with Europe shows less stringent regulatory requirements, perhaps due to institutionalized design parameters. We recommend that permitting authorities develop technical guidance documents for evaluation of “green” CSO treatment systems that account for their unique operational concerns and benefits with respect to sustainable development.

  18. La comprensión clásica del suicidio. De Émile Durkheim a nuestros días. // The classic understanding of suicide. From Émile Durkheim to the present day.

    OpenAIRE

    Andrés Felipe Palacio.

    2010-01-01

    This text is an approach to several ideas stated by the sociologist Émile Durkheim dealing with suicide, especially the question about how his idea of suicidogenic societies and anomic suicide has probably contributed to the psychoanalytical conception of suicide. The objective is to clarify, at the same time, the usefulness of a broad concept like discourse, from a critical point of view of contemporary cognitive sciences, as well as how they define and tackle the issue of suicide in general...

  19. Evacuation decision-making at three mile island

    International Nuclear Information System (INIS)

    Zeigler, Donald. J.; Johnson, James. H.

    1987-01-01

    The accident at the Three Mile Island nuclear power plant in 1979 provoked an unanticipated and unprecedented spontaneous evacuation of people living in the area. Following the accident, revised and upgraded emergency preparedness and response regulations were issued by the Nuclear Regulatory Commission (NRC) and the Federal Emergency Management Agency. (FEMA). This includes the assumption that public education and awareness will minimise the tendency of people to evacuate spontaneously from the vicinity of an accident. This assumption is challenged. Results of an empirical test of a casual model of emergency evacuation decision-making are given. This test was devised to aid understanding of the public behaviour at the time of the Three Mile Island incident. The emergency plans for the Sizewell-B reactor are subject to brief critical consideration. It is concluded that evacuation plans need to reflect people's natural inclinations to move away from a nuclear hazard. (UK)

  20. Numerical simulation of the accident of Three Mile Island

    International Nuclear Information System (INIS)

    Perrin, M.H.; Kastelanski, P.

    1981-01-01

    The chief object of the present study was to assess the ability of our numerical code for the dynamic behavior of power plants, SICLE, to handle the simulation of small accidents in PWRs. In the first part of the paper the authors introduce the main principles, equations and numerical methods of the code. In the second part those of the elements of Three Mile Island Power Plant which were simulated, the different phases of the accident and the results obtained with the code are described. These results are compared to the values recorded in the plant and generally a good agreement is found (for instance the primary pressure). As a conclusion SICLE is the minimum code for representing accidents such as Three Mile Island; its main advantage lies in its ability to take into account all the elements of the plant which are important in the study

  1. Northern part, Ten Mile and Taunton River basins

    Science.gov (United States)

    Williams, John R.; Willey, Richard E.

    1967-01-01

    The northern part of the Ten Mile and Taunton River basins is an area of about 195 square miles within Norfolk, Plymouth, and Bristol Counties in southeastern Massachusetts. The northern boundary of the area (plate 1) is the drainage divide separating these basins from that of the Charles, Neponset, and Weymouth River basins. The western boundary is, for the most part, the divide separating the basins from the Blackstone River basin. The eastern boundary is at the edge of the Brockton-Pembroke area (Petersen, 1962; Petersen and Shaw, 1961). The southern boundary in Seekonk is the northern limit of the East Providence quadrangle, for which a ground-water map was prepared by Allen and Gorman (1959); eastward, the southern boundaries of the city of Attleboro and the towns of Norton, Easton, and West Bridgewater form the southern boundary of the area.

  2. Cancer near the Three Mile Island nuclear plant: radiation emissions.

    Science.gov (United States)

    Hatch, M C; Beyea, J; Nieves, J W; Susser, M

    1990-09-01

    As a public charge, cancers among the 159,684 residents living within a 10-mile (16-km) radius of the Three Mile Island nuclear plant were studied relative to releases of radiation during the March 28, 1979, accident as well as to routine plant emissions. The principal cancers considered were leukemia and childhood malignancies. Estimates of the emissions delivered to small geographic study tracts were derived from mathematical dispersion models which accounted for modifying factors such as wind and terrain; the model of accident emissions was validated by readings from off-site dosimeters. Incident cancers among area residents for the period 1975-1985 (n = 5,493) were identified by a review of the records at all local and regional hospitals; preaccident and postaccident trends in cancer rates were examined. For accident emissions, the authors failed to find definite effects of exposure on the cancer types and population subgroups thought to be most susceptible to radiation. No associations were seen for leukemia in adults or for childhood cancers as a group. For leukemia in children, the odds ratio was raised, but cases were few (n = 4), and the estimate was highly variable. Moreover, rates of childhood leukemia in the Three Mile Island area are low compared with national and regional rates. For exposure to routine emissions, the odds ratios were raised for childhood cancers as a whole and for childhood leukemia, but confidence intervals were wide and included 1.0. For leukemia in adults, there was a negative trend. Trends for two types of cancer ran counter to expectation. Non-Hodgkin's lymphoma showed raised risks relative to both accident and routine emissions; lung cancer (adjusted only indirectly for smoking) showed raised risks relative to accident emissions, routine emissions, and background gamma radiation. Overall, the pattern of results does not provide convincing evidence that radiation releases from the Three Mile Island nuclear facility influenced

  3. The accident of the Three Mile Island nuclear power plant

    International Nuclear Information System (INIS)

    Llory, M.

    1999-01-01

    This book questions which statement can be made twenty years after the accident of the Three Mile Island reactor (USA) on the performances of complex reactor safety systems and on their evolutions and improvements. It questions also todays limits of reactors security and how such a reactor accident can be possible today. It presents also an analysis of the organizations which propose new perspectives in nuclear safety. (J.S.)

  4. Defuelling at Three Mile Island 2 continues on schedule

    International Nuclear Information System (INIS)

    Frew, J.E.

    1987-01-01

    In September GPU Nuclear announced that it had extracted half of the debris from the reactor vessel at Three Mile Island 2 and loaded it into casks for transport from the site. The work has been speeded by the development of special tools and working methods and has been accompanied by a continuous programme of decontamination. The health risks to workers are now considered to be no greater than those at operating plants. (author)

  5. Managing Nuclear Reactor Accidents: Issues Raised by Three Mile Island

    OpenAIRE

    Hamilton, G.W.

    1980-01-01

    This paper provides a descriptive account of significant events in the accident at the Three Mile Island nuclear power plant in March, 1979. It is based upon documents collected as background materials for the IIASA workshop: Procedural and Organizational Measures for Accident Management: Nuclear Reactors. In addition to the references listed, information was supplied by John Lathrop, who conducted interviews with government and industry officials involved in the crisis. There have been ...

  6. Utilization of medical care following the Three Mile Island crisis.

    Science.gov (United States)

    Houts, P S; Hu, T W; Henderson, R A; Cleary, P D; Tokuhata, G

    1984-02-01

    Four studies are reported on how utilization of primary health care was affected by the Three Mile Island (TMI) crisis and subsequent distress experienced by persons living in the vicinity of the plant. The studies concerned: 1) Blue Cross-Blue Shield records of claims by primary care physicians in the vicinity of TMI; 2) utilization rates in a family practice located near the facility; 3) interviews with persons living within five miles of TMI following the crisis; and 4) responses to a questionnaire by primary care physicians practicing within 25 miles of TMI. All four studies indicated only slight increases in utilization rates during the year following the crisis. One study found that persons who were upset during the crisis tended to be high practice utilizers both before and after the crisis. These results suggest that, while patterns of physician utilization prior to the TMI crisis predicted emotional response during the crisis, the impact of the TMI crisis on subsequent physician utilization was small.

  7. Utilization of medical care following the Three Mile Island crisis

    International Nuclear Information System (INIS)

    Houts, P.S.; Hu, T.W.; Henderson, R.A.; Cleary, P.D.; Tokuhata, G.

    1984-01-01

    Four studies are reported on how utilization of primary health care was affected by the Three Mile Island (TMI) crisis and subsequent distress experienced by persons living in the vicinity of the plant. The studies concerned: 1) Blue Cross-Blue Shield records of claims by primary care physicians in the vicinity of TMI; 2) utilization rates in a family practice located near the facility; 3) interviews with persons living within five miles of TMI following the crisis; and 4) responses to a questionnaire by primary care physicians practicing within 25 miles of TMI. All four studies indicated only slight increases in utilization rates during the year following the crisis. One study found that persons who were upset during the crisis tended to be high practice utilizers both before and after the crisis. These results suggest that, while patterns of physician utilization prior to the TMI crisis predicted emotional response during the crisis, the impact of the TMI crisis on subsequent physician utilization was small

  8. Nuclear power after three mile island. Last of four articles

    International Nuclear Information System (INIS)

    Faltermayer, E.

    1979-01-01

    This final and fourth article on nuclear power reviews the March 28, 1979 accident at Three Mile Island-2 Reactor. The most lasting effect will probably be the jarring of the public's confidence and acceptance of nuclear technology. Even before Three Mile Island, electric utilities were starting to desert uranium and switch to coal-fired power plants. Cost overruns, Federal indecision on fuel reprocessing and waste disposal, long licensing procedures, and many other regulatory mandates are cited as deterrents to nuclear power. Coal is the only real alternative for utilities in the U.S., at least for some time to come, even though it is hazardous to mine and dirty to burn. Its use will probably cause far more fatalities than all the nuclear mishaps that may occur. Most unbiased studies indicate economic advantages of nuclear plants over coal-fired plants, even when decommissioning costs are added; it is felt, though, that the somewhat debatable advantages might easily disappear with the new safety and regulatory costs that will be imposed. It remains to be seen how many insurance claims will result from Three Mile Island and whether Congress may raise, or even remove, the controversial $560-million liability limit for nuclear power plants

  9. Social survey of Three Mile Island area residents. Final report

    International Nuclear Information System (INIS)

    Brunn, S.D.; Johnson, J.H. Jr; Zeigler, D.J.

    1979-08-01

    Recognizing that there is concern among government officials, utility company officials, engineers, physical, social, and behavioral scientists, and the general public about the consequences of the Three Mile Island accident, the overall objective of this report is to examine how the accident affected TMI area residents. This final report is a detailed analysis and description of the summary results published previously. A questionnaire was mailed to a sample of residents in the Three Mile Island area within one month of the accident. The survey instrument and sampling design are discussed in a subsequent chapter. Because of the nature of the accident and individual memories about dates, places, and events, it was necessary to conduct a survey as soon as possible after the accident. Area residents were asked a variety of questions including: (1) when and how they learned about the accident; (2) where they evacuated and why; (3) what confidence they placed in reports by the government and utility companies; (4) how their attitudes toward nuclear power have changed as a result of the accident; and (5) what impact the accident is likely to have on themselves and the Three Mile Island area. These questions and others are examined in this report. The results are analyzed in light of a number of social, economic, and political characteristics. Both statistical tests and a graphical presentation of the results are included

  10. Three Mile Island serious but not fatal to nuclear

    International Nuclear Information System (INIS)

    Anon.

    1979-01-01

    The Three Mile Island nuclear incident will cause some delays in the construction of nuclear plants. But when the emotion dies down, people will realize there is still an obvious need for nuclear power in the long term, even as President Carter indicated in his press conference after his television energy message. This was the conclusion arrived at by several top officials of electric utilities in a spot check on the President's energy message and on their views on Three Mile Island. The officials also commented on decontrol of oil prices and wheeling power to oil-fired regions. Karl H. Rudolph of Cleveland Electric Illuminating Company says that Three Mile Island was a serious event, but the industry tries to place the event in perspective, particularly in view of its continuing dramatization in the news media. The truth of the matter is that, despite human error and mechanical failures, the redundant safety systems in the plant worked...because of what happened, nuclear constuction, both now and in the future, will include even better safety systems. As more is learned about nuclear power, says Aaron E. Autry of Central Power and Light, Corpus Christi, the relative safety of nuclear will be greater than any other option, including coal. Many other comments are made concerning coal, and executives from Detroit Edison and Co. and Consumers Power Co. agree that the President will have to improve rail transportation and relax tax air quality regulations if he wants electricity to be produced by coal in the future

  11. Commercial disposal of High Integrity Containers (HICs) containing EPICOR-II prefilters from Three Mile Island

    International Nuclear Information System (INIS)

    McConnell, J.W. Jr.; Lynch, R.J.; Tyacke, M.J.

    1985-09-01

    This report describes the processes of loading, transporting, and commercially disposing of 45 High Integrity Containers (HICs), each containing an EPICOR-II prefilter. Also described are the improvements that were applied in the disposition of the 45 commercial EPICOR-II prefilters at the Idaho National Engineering Laboratory (INEL), versus those used for the demonstration unit. The significance of this effort was that the commercial disposal campaign involved the first-of-a-kind production use of a reinforced concrete HIC at the US Ecology, Inc. facility in the State of Washington. This allowed for safe disposal of high-specific-activity ion exchange material in EPICOR-II prefilters generated during the cleanup of the Unit-2 Auxiliary and Fuel Handling Building of the Three Mile Island Nuclear Power Station. 26 figs

  12. Evaluation of the i-STAT Portable Clinical Analyzer for point-of-care blood testing in the intensive care units of a university children's hospital.

    Science.gov (United States)

    Papadea, Christine; Foster, Joyce; Grant, Sharon; Ballard, Sandra A; Cate, John C; Southgate, W Michael; Purohit, Dilip M

    2002-01-01

    We evaluated the analytical performance of the i-STAT Portable Clinical Analyzer (PCA), a point-of-care testing system consisting of a hand-held analyzer and single-use cartridges that measure different panels of electrolytes, metabolites, blood gases, and hematocrit in 65-100 microl of blood. Our objective was to determine whether PCA measurements at the bedside of patients in the neonatal and pediatric intensive care units of the MUSC Children's Hospital would be as reliable as those performed by the clinical laboratory's primary methods (Radiometer ABL 725 blood gas analyzer; Vitros 750 chemistry analyzer; and Coulter STKS hematology analyzer). Four cartridge types: (a) EC8+ (sodium; potassium; chloride; urea; glucose; pH; blood gases [PO2; pCO2]), (b) EC6+ (sodium; potassium; ionized calcium; glucose; hematocrit; pH), (c) G3+ (pH; PO2; pCO2), and (d) creatinine, were assessed for reproducibility, linearity, and method comparisons using aqueous samples, blood samples supplemented with several analytes, and -225 blood samples from patients. Reproducibility (CV) was good ( or < 3 mo) showed that agreement between the PCA and the primary methods was clinically acceptable. After the PCA was implemented for clinical testing, the observation of discrepant results of creatinine concentrations in neonatal blood samples that would have affected clinical management led to a second creatinine comparison study (59 additional samples) and to our eventual discontinuation of the PCA creatinine assay. This problem notwithstanding, the successful implementation of the PCA is attributed to careful analytical evaluations and ongoing communication with the clinical staff.

  13. Working Together to Define Antibiotic Appropriateness: Point Prevalence Survey in 47 Intensive Care Units from 12 US Hospitals, Partnership for Quality Care, March 2017

    Science.gov (United States)

    Trivedi, Kavita K; Ostrowsky, Belinda; Abbo, Lilian M; Srinivasan, Arjun; Bartash, Rachel; Cassera, Fred; Fleisher, Jorge; Kubiak, David W; Letourneau, Alyssa R; Nori, Priya; Parodi, Stephen; Aragon, Laura; Dollard, Eliza; Gagliardo, Christina; Ghitan, Monica; Giles, Amber; Mayer, Suri; Quevedo, Jennifer; Rieg, Gunter; Shteyman, Galina; Vargas, Jaclyn; Kelley, Shannon; Silver, Phyllis

    2017-01-01

    Abstract Background A national assessment of antibiotic appropriateness in intensive care units (ICUs) with benchmarking was performed to assist antibiotic stewardship programs (ASPs) identify improvement opportunities. Methods A Centers for Disease Control and Prevention tool was adapted by an expert panel from the Partnership for Quality Care (PQC), a coalition dedicated to high quality care in US hospitals, to validate appropriate antibiotic use measurement via a point prevalence survey on a single day. Data were collected by ASP personnel at each hospital, de-identified and submitted in aggregate to PQC for benchmarking. Hospitals identified reasons for inappropriate antibiotic use by category and antibiotics misused. Results Forty-seven ICUs from 12 PQC hospitals participated: California (2), Florida (2), Massachusetts (3), Minnesota (1), and New York (4). Most hospitals identified as teaching (83%) with 252-1550 bed size (median: 563) and 20–270 licensed ICU beds (median: 70). All hospitals reported a formal ASP. On March 1, 2017, 362 (54%) of 667 patients in participating ICUs were on antibiotics (range: 8-81 patients); 1 patient was not assessed. Of the remaining 361 antibiotic regimens, 112 (31%) were identified as inappropriate from among all 12 hospitals (range: 9-82%) (figure). The table displays inappropriate antibiotic use by ICU type. Reasons for inappropriate use included unnecessarily broad spectrum of activity (29%), duration longer than necessary (21%), and treatment of a non-infectious syndrome (19%). The antibiotic most commonly misused was vancomycin in 7 (58%) hospitals. Conclusion Up to 80% of antibiotic use in some ICUs is inappropriate, underscoring the need for ASP interventions, standardized assessment tools and benchmarking. Strategies should focus on de-escalation of broad-spectrum antibiotics and reducing duration of therapy. Disclosures D. W. Kubiak, Shionogi: Consultant, Consulting fee. Astellas Pharma: Consultant, Consulting

  14. Corrective Action Decision Document/ Closure Report for Corrective Action Unit 556: Dry Wells and Surface Release Points, Nevada Test Site, Nevada with Errata Sheet, Revision 0

    Energy Technology Data Exchange (ETDEWEB)

    Grant Evenson

    2008-09-01

    This Corrective Action Decision Document (CADD)/Closure Report (CR) has been prepared for Corrective Action Unit 556, Dry Wells and Surface Release Points, located at the Nevada Test Site, Nevada, in accordance with the Federal Facility Agreement and Consent Order (FFACO, 1996; as amended February 2008). Corrective Action Unit (CAU) 556 is comprised of four corrective action sites (CASs): • 06-20-04, National Cementers Dry Well • 06-99-09, Birdwell Test Hole • 25-60-03, E-MAD Stormwater Discharge and Piping • 25-64-01, Vehicle Washdown and Drainage Pit The purpose of this CADD/CR is to provide justification and documentation supporting the recommendation for closure of CAU 556 with no further corrective action. To achieve this, corrective action investigation (CAI) activities began on February 7 and were completed on June 19, 2008, as set forth in the Corrective Action Investigation Plan for Corrective Action Unit 556: Dry Wells and Surface Release Points, Nevada Test Site, Nevada (NNSA/NSO, 2007). The purpose of the CAI was to fulfill the following data needs as defined during the data quality objective (DQO) process: • Determine whether contaminants of concern (COCs) are present. • If COCs are present, determine their nature and extent. • Provide sufficient information and data to complete appropriate corrective actions. The CAU 556 data were evaluated based on the data quality assessment process, which demonstrated the quality and acceptability of the data for use in fulfilling the DQO data needs. Analytes detected during the CAI were evaluated against appropriate final action levels (FALs) to identify the COCs for each CAS. The results of the CAI identified COCs at one of the four CASs in CAU 556 that required the completion of a corrective action. Assessment of the data generated from investigation activities conducted at CAU 556 revealed the following: • Corrective Action Sites 06-20-04, 06-99-09, and 25-64-01 do not contain contamination at

  15. Urban distribution centers : a means to reducing freight vehicle miles traveled.

    Science.gov (United States)

    2011-02-01

    The present study examines the model of freight consolidation platforms, and urban distribution centers (UDCs) in particular, as a means to solve the last mile problem of urban freight while reducing vehicle miles traveled and associated environmenta...

  16. Sensitivity of Coastal Environments and Wildlife to Spilled Oil: Hudson River: RVRMILES (River Mile Marker Lines)

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — This data set contains human-use resource data for river miles along the Hudson River. Vector lines in this data set represent river mile markers. This data set...

  17. 27 June 2012 - Ambassador K. Pierce, Permanent Representative of the United Kingdom of Great Britain and Northern Ireland to the United Nations Office and other international organisations in Geneva visiting the LHC tunnel at Point 5 with Department Head P. Collier and CMS control room with Former Collaboration Spokesperson J. Virdee.

    CERN Multimedia

    Laurent Egli

    2012-01-01

    27 June 2012 - Ambassador K. Pierce, Permanent Representative of the United Kingdom of Great Britain and Northern Ireland to the United Nations Office and other international organisations in Geneva visiting the LHC tunnel at Point 5 with Department Head P. Collier and CMS control room with Former Collaboration Spokesperson J. Virdee.

  18. Three Mile Island: a report to the commissioners and to the public. Volume II, Part 1

    International Nuclear Information System (INIS)

    1979-01-01

    This is part one of three parts of the second volume of the Special Inquiry Group's report to the Nuclear Regulatory Commission on the accident at Three Mile Island. The first volume contained a narrative description of the accident and a discussion of the major conclusions and recommendations. This second volume is divided into three parts. Part 1 of Volume II focuses on the pre-accident licensing and regulatory background. This part includes an examination of the overall licensing and regulatory system for nuclear powerplants viewed from different perspectives: the system as it is set forth in statutes and regulations, as described in Congressional testimony, and an overview of the system as it really works. In addition, Part 1 includes the licensing, operating, and inspection history of Three Mile Island Unit 2, discussions of relevant regulatory matters, a discussion of specific precursor events related to the accident, a case study of the pressurizer design issue, and an analysis of incentives to declare commercial operation

  19. Cancer near the Three Mile Island nuclear plant: Radiation emissions

    International Nuclear Information System (INIS)

    Hatch, M.C.; Beyea, J.; Nieves, J.W.; Susser, M.

    1990-01-01

    As a public charge, cancers among the 159,684 residents living within a 10-mile (16-km) radius of the Three Mile Island nuclear plant were studied relative to releases of radiation during the March 28, 1979, accident as well as to routine plant emissions. The principal cancers considered were leukemia and childhood malignancies. Estimates of the emissions delivered to small geographic study tracts were derived from mathematical dispersion models which accounted for modifying factors such as wind and terrain; the model of accident emissions was validated by readings from off-site dosimeters. Incident cancers among area residents for the period 1975-1985 (n = 5,493) were identified by a review of the records at all local and regional hospitals; preaccident and postaccident trends in cancer rates were examined. For accident emissions, the authors failed to find definite effects of exposure on the cancer types and population subgroups thought to be most susceptible to radiation. No associations were seen for leukemia in adults or for childhood cancers as a group. For leukemia in children, the odds ratio was raised, but cases were few (n = 4), and the estimate was highly variable. Moreover, rates of childhood leukemia in the Three Mile Island area are low compared with national and regional rates. For exposure to routine emissions, the odds ratios were raised for childhood cancers as a whole and for childhood leukemia, but confidence intervals were wide and included 1.0. For leukemia in adults, there was a negative trend. Trends for two types of cancer ran counter to expectation. Non-Hodgkin's lymphoma showed raised risks relative to both accident and routine emissions; lung cancer (adjusted only indirectly for smoking) showed raised risks relative to accident emissions, routine emissions, and background gamma radiation

  20. Three Mile Island - the challenge, the saga, the outlook

    International Nuclear Information System (INIS)

    Coffman, F.E.; Feinroth, H.

    1982-01-01

    Progress which has been made in tackling some of the problems raised by the accident at Three Mile Island 2 is discussed. Improvements in the design, operation, management and regulation of nuclear plants are described. An assessment is given of the challenge facing the nuclear industry to explain the accident to the public and to demonstrate that a catastrophe was never close since significant barriers still existed to prevent major releases of radioactivity. The job of cleaning up the contaminated plant is described and the lessons to be learnt from this task are outlined. (U.K.)

  1. Three Mile Island Nuclear Station steam generator chemical cleaning

    International Nuclear Information System (INIS)

    Hansen, C.A.

    1992-01-01

    The Three Mile Island-1 steam generators were chemically cleaned in 1991 by the B and W Nuclear Service Co. (BWNS). This secondary side cleaning was accomplished through application of the EPRI/SGOG (Electric Power Research Institute - Steam Generator Owners Group) chemical cleaning iron removal process, followed by sludge lancing. BWNS also performed on-line corrosion monitoring. Corrosion of key steam generator materials was low, and well within established limits. Liquid waste, subsequently processed by BWNS was less than expected. 7 tabs

  2. Immobilization of Three-Mile Island core debris

    International Nuclear Information System (INIS)

    Welch, J.M.; Miller, R.L.; Flinn, J.E.

    1983-01-01

    The immobilization of Three-Mile Island core debris in iron-enriched basalt (IEB), a fused-cast nuclear waste form, was considered. The amount of zirconium clad UO 2 fuel assemblies that can be dissolved in IEB using the Zr to UO 2 ratio present in the core was bracketed between 25 and 30% at 1500 0 C. The factors controlling the rate of dissolution of fuel pellets and Inconel, a structural component of the core, were investigated. Since the UO 2 dissolved in IEB could be a valuable resource in the future, the recovery of uranium from IEB using conventional ore-dressing and leaching techniques was assessed

  3. Attenuation in the dubbing and subtitling of The Green Mile

    OpenAIRE

    Lidia Rodríguez; Gabriela S. Alanís Uresti

    2015-01-01

    This paper is part of the doctoral thesis entitled “Critique of translation for film dubbing and subtitling from the perspective of discourse analysis. A study applied to "The Green Mile”, written by Ph.D. student Gabriela Saturnina Alanís Uresti, directed by Ph.D. Lidia Rodríguez. It is a qualitative and descriptive study where we contrasted The Green Mile - a 1999 Hollywood film, original in American English - with its translated versions: dubbed and subtitled into Spanish of Mexico. We sta...

  4. Evaluation of environmental data relating to selected nuclear power plant sites: the Three Mile Island Nuclear Station Site

    International Nuclear Information System (INIS)

    Murarka, I.P.

    1976-08-01

    Environmental monitoring data for the years 1973 and 1974 pertaining to the Three Mile Island Nuclear Station Unit 1, which began operation in early 1974, were analyzed by the most practical qualitative and quantitative methods. Terrestrial biotic resources were considered for this plant. The effects of the operation of Unit 1 on the local terrestrial organisms were found to be undetectable. Although the plant has not operated long enough to reveal long-term deleterious effects, the present indications do not lead to a concerned prediction that any are developing. The data acquired, method of analysis, and results obtained are presented in detail along with recommendations for improving monitoring techniques

  5. 77 FR 72737 - Drawbridge Operation Regulation; Mile 359.4, Missouri River, Kansas City, MO

    Science.gov (United States)

    2012-12-06

    ... Operation Regulation; Mile 359.4, Missouri River, Kansas City, MO AGENCY: Coast Guard, DHS. ACTION: Notice... River, mile 359.4, at Kansas City, Missouri. The deviation is necessary to allow the replacement of 64... deviation for the Harry S. Truman Railroad Drawbridge, across the Missouri River, mile 359.4, at Kansas City...

  6. 77 FR 24147 - Drawbridge Operation Regulation; Mile 359.4, Missouri River, Kansas City, MO

    Science.gov (United States)

    2012-04-23

    ... Operation Regulation; Mile 359.4, Missouri River, Kansas City, MO AGENCY: Coast Guard, DHS. ACTION: Notice... River, mile 359.4, at Kansas City, Missouri. The deviation is necessary to allow the replacement of... Railroad Drawbridge, across the Missouri River, mile 359.4, at Kansas City, Missouri to remain in the...

  7. 33 CFR 165.554 - Security Zone; Three Mile Island Generating Station, Susquehanna River, Dauphin County...

    Science.gov (United States)

    2010-07-01

    ... 33 Navigation and Navigable Waters 2 2010-07-01 2010-07-01 false Security Zone; Three Mile Island... Areas Fifth Coast Guard District § 165.554 Security Zone; Three Mile Island Generating Station... waters of the Susquehanna River in the vicinity of the Three Mile Island Generating Station bounded by a...

  8. Human reliability data, human error and accident models--illustration through the Three Mile Island accident analysis

    International Nuclear Information System (INIS)

    Le Bot, Pierre

    2004-01-01

    Our first objective is to provide a panorama of Human Reliability data used in EDF's Safety Probabilistic Studies, and then, since these concepts are at the heart of Human Reliability and its methods, to go over the notion of human error and the understanding of accidents. We are not sure today that it is actually possible to provide in this field a foolproof and productive theoretical framework. Consequently, the aim of this article is to suggest potential paths of action and to provide information on EDF's progress along those paths which enables us to produce the most potentially useful Human Reliability analyses while taking into account current knowledge in Human Sciences. The second part of this article illustrates our point of view as EDF researchers through the analysis of the most famous civil nuclear accident, the Three Mile Island unit accident in 1979. Analysis of this accident allowed us to validate our positions regarding the need to move, in the case of an accident, from the concept of human error to that of systemic failure in the operation of systems such as a nuclear power plant. These concepts rely heavily on the notion of distributed cognition and we will explain how we applied it. These concepts were implemented in the MERMOS Human Reliability Probabilistic Assessment methods used in the latest EDF Probabilistic Human Reliability Assessment. Besides the fact that it is not very productive to focus exclusively on individual psychological error, the design of the MERMOS method and its implementation have confirmed two things: the significance of qualitative data collection for Human Reliability, and the central role held by Human Reliability experts in building knowledge about emergency operation, which in effect consists of Human Reliability data collection. The latest conclusion derived from the implementation of MERMOS is that, considering the difficulty in building 'generic' Human Reliability data in the field we are involved in, the best

  9. Abandoned Uranium Mine (AUM) Points, Navajo Nation, 2016, US EPA Region 9

    Data.gov (United States)

    U.S. Environmental Protection Agency — This GIS dataset contains point features of all Abandoned Uranium Mines (AUMs) on or within one mile of the Navajo Nation. Points are centroids developed from the...

  10. Three Mile Island Commission and the language of legitimacy

    International Nuclear Information System (INIS)

    Fingrutd, M.A.

    1984-01-01

    This work is an exploration in discourse. It assumes that discourse is constitutive of and constituted by social organization. The research site for this investigation is provided by transcripts from the President's Commission to investigate the accident at Three Mile Island. The transcripts cover five days of meetings where 12 Commissioners discussed the content, nuance, tone and scope of the report they would submit to the President. The analytical goal of the research is to understand four features of the dialogue: (1) formal structure of conversation: how utterances are organized into an orderly, rational, meaningful conversation; (2) meaning or content of the talk; (3) the way conversational form and content act together to create a form of rationality or orientation to task and (4) social context surrounding the talk. The approach to the transcripts relies upon a variety of discourse analysis techniques in order to examine four essential disputes - places of deep level disagreement among the Commissioners. For each dispute, the forces that constrained and/or compelled the dialogue toward resolution are noted. The work concludes by asserting that the linguistic practices used by the Commissioners indicate a techno-bureaucratic approach to understanding the accident at Three Mile Island and formulating recommendations for public policy toward nuclear power

  11. The Mile Deep Muon Detector at Sanford Underground Laboratory

    Science.gov (United States)

    McMahan, Margaret; Gabriel, Steve

    2012-03-01

    For educating students and teachers about basic nuclear and particle physics, you can't go wrong with cosmic rays muons as a cheap and reliable source of data. A simple and relatively inexpensive detector gives a myriad of possibilities to cover core material in physical science, chemistry, physics, and statistics and gives students opportunities to design their own investigations. At Sanford Underground Laboratory at Homestake, in Lead, SD, cosmic ray muon detectors are being used to answer the first question always asked by any visitor to the facility, ``Why are you building the lab a mile underground'' A conventional Quarknet-style detector is available in the education facility on the surface, with a much larger companion detector, the Mile Deep Muon Detector, set up 4850 feet below the surface. Using the Quarknet data acquisition board, the data will be made available to students and teachers through the Cosmic Ray E-lab website. The detector was tested and installed as part of a summer program for students beginning their first or second year of college.

  12. Vegetation survey of Pen Branch and Four Mile Creek wetlands

    Energy Technology Data Exchange (ETDEWEB)

    1992-01-01

    One hundred-fifty plots were recently sampled (vegetational sampling study) at the Savannah River Site (SRS). An extensive characterization of the vascular flora, in four predetermined strata (overstory, Understory, shrub layer, and ground cover), was undertaken to determine dominance, co-dominance, and the importance value (I.V.) of each species. These results will be used by the Savannah River Laboratory (SRL) to evaluate the environmental status of Four Mile Creek, Pen Branch, and two upland pine stands. Objectives of this study were to: Describe in detail the plant communities previously mapped with reference to the topography and drainage, including species of plants present: Examine the successional trends within each sampling area and describe the extent to which current vegetation communities have resulted from specific earlier vegetation disturbances (e.g., logging and grazing); describe in detail the botanical field techniques used to sample the flora; describe the habitat and location of protected and/or rare species of plants; and collect and prepare plant species as herbarium quality specimens. Sampling was conducted at Four Mile Creek and Pen Branch, and in two upland pine plantations of different age growth.

  13. Vegetation survey of Pen Branch and Four Mile Creek wetlands

    Energy Technology Data Exchange (ETDEWEB)

    1992-10-01

    One hundred-fifty plots were recently sampled (vegetational sampling study) at the Savannah River Site (SRS). An extensive characterization of the vascular flora, in four predetermined strata (overstory, Understory, shrub layer, and ground cover), was undertaken to determine dominance, co-dominance, and the importance value (I.V.) of each species. These results will be used by the Savannah River Laboratory (SRL) to evaluate the environmental status of Four Mile Creek, Pen Branch, and two upland pine stands. Objectives of this study were to: Describe in detail the plant communities previously mapped with reference to the topography and drainage, including species of plants present: Examine the successional trends within each sampling area and describe the extent to which current vegetation communities have resulted from specific earlier vegetation disturbances (e.g., logging and grazing); describe in detail the botanical field techniques used to sample the flora; describe the habitat and location of protected and/or rare species of plants; and collect and prepare plant species as herbarium quality specimens. Sampling was conducted at Four Mile Creek and Pen Branch, and in two upland pine plantations of different age growth.

  14. Address Points, The Address Point layer contains an address point for almost every structure over 200 square feet and for some vacant properties. Attributes include addresses, sub-units, address use, LAT/LONG, 10-digit SDAT taxpins, political areas and more., Published in 2013, 1:2400 (1in=200ft) scale, Baltimore County Government.

    Data.gov (United States)

    NSGIC Local Govt | GIS Inventory — Address Points dataset current as of 2013. The Address Point layer contains an address point for almost every structure over 200 square feet and for some vacant...

  15. Three Mile Island epidemiologic radiation dose assessment revisited: 25 years after the accident.

    Science.gov (United States)

    Field, R William

    2005-01-01

    Over the past 25 years, public health concerns following the Three Mile Island (TMI) accident prompted several epidemiologic investigations in the vicinity of TMI. One of these studies is ongoing. This commentary suggests that the major source of radiation exposure to the population has been ignored as a potential confounding factor or effect modifying factor in previous and ongoing TMI epidemiologic studies that explore whether or not TMI accidental plant radiation releases caused an increase in lung cancer in the community around TMI. The commentary also documents the observation that the counties around TMI have the highest regional radon potential in the United States and concludes that radon progeny exposure should be included as part of the overall radiation dose assessment in future studies of radiation-induced lung cancer resulting from the TMI accident.

  16. Impact of Federal R and D funding on Three Mile Island cleanup costs

    International Nuclear Information System (INIS)

    1982-01-01

    The Chairman and the Ranking Minority Member of the House Committee on Interior and Insular Affairs requested that GAO respond to several questions concerning the administration's proposed $123 million in Federal funding for data acquisition and research and development activities during the cleanup of the Three Mile Island nuclear reactor Unit 2. GAO found that: adequate legislative authority exists to support DOE's proposed data acquisition and research and development activities during the cleanup process; adherence to the estimated timetable for cleanup completion will allow DOE to meet its program objectives within the proposed budget, but slippages would probably make additional funding necessary; and the DOE program will reduce the utility company's financial needs by an estimated $66 to $69 million, about one-third of the Federal share proposed by the Governor of Pennsylvania on July 9, 1981

  17. Evaluation of the Three Mile Island accident in the context of WASH-1400

    International Nuclear Information System (INIS)

    Burns, R.D. III.

    1980-01-01

    The accident at unit 2 of the Three Mile Island nuclear station (TMI-2) on March 28, 1979, occurred after approximately 400 reactor years (RY) of commercial nuclear reactor operation in the US. The purpose of work summarized here was to evaluate the probability statements in the WASH-1400 reactor safety study (RSS) in view of the TMI-2 event and to estimate the likely public impact of TMI-2. The RSS probability estimate for such a release was found to be consistent with the fact that the TMI-2 accident occurred. The expected health effects are consistent with those for a low-level category of radioactivity release as described in the RSS and they are immeasurably small. However, the public perception of the health effects of the release is likely to be much more severe than the estimated health effects

  18. Preparations to load, transport, receive, and store the damaged TMI-2 [Three Mile Island] reactor core

    International Nuclear Information System (INIS)

    Reno, H.W.; Schmitt, R.C.; Quinn, G.J.; Ayers, A.L. Jr.; Lilburn, B.J. Jr.; Uhl, D.L.

    1986-03-01

    The March 1979 incident at the Three Mile Island Nuclear Power Station (TMI) which damaged the core of the Unit 2 reactor resulted in numerous scientific and technical challenges. Some of those challenges involve removing, packaging, and transporting the core debris to the Idaho National Engineering Laboratory (INEL) for storage, examination, and preparation for final disposal. This paper highlights preparations for transporting the core debris from TMI to INEL and receiving and storing that material at INEL. Issues discussed include interfacing of equipment and facilities at TMI, loading operations, transportation activities using a newly designed cask, receiving and storing operations at INEL, and criticality control during storage. Key to the transportation effort was designing, testing, fabricating, and licensing two rail casks which individually provide double containment of the damaged fuel. 27 figs

  19. Three Mile Island epidemiologic radiation dose assessment revisited: 25 years after the accident

    International Nuclear Information System (INIS)

    Field, R. W.

    2005-01-01

    Over the past 25 years, public health concerns following the Three Mile Island (TMI) accident prompted several epidemiologic investigations in the vicinity of TMI. One of these studies is ongoing. This commentary suggests that the major source of radiation exposure to the population has been ignored as a potential confounding factor or effect modifying factor in previous and ongoing TMI epidemiologic studies that explore whether or not TMI accidental plant radiation releases caused an increase in lung cancer in the community around TMI. The commentary also documents the observation that the counties around TMI have the highest regional radon potential in the United States and concludes that radon progeny exposure should be included as part of the overall radiation dose assessment in future studies of radiation-induced lung cancer resulting from the TMI accident. (authors)

  20. Processing and removal of the Three Mile Island makeup and purification system resins

    International Nuclear Information System (INIS)

    Reilly, J.K.; McIntosh, T.W.; Northey, L.M.; GaTanto, J.J.; Osterhoudt, T.R.; Thompson, J.D.

    1985-01-01

    The accident at Three Mile Island Unit 2 in March 1979 left the makeup and purification demineralizers inaccessible to workers. These demineralizers contained the highest concentrations of radioactive isotopes outside the Reactor Building. Additionally, unknown quantities of fuel were in the demineralizers. Other concerns centered on the unknown condition of the demineralizer resins, the possible loss of system integrity, and the presence of hydrogen due to the radiolytic breakdown of water contained in the demineralizers. GPU Nuclear, with the US Department of Energy and its contractors EG and G Idaho, Inc., Oak Ridge National Laboratory, and Westinghouse Hanford Company, remotely measured the fuel and fission product inventory of the demineralizers and demonstrated a practical chemical processing method using samples acquired from the demineralizers. Equipment was developed and installed to elute the radioactive cesium from the demineralizers. And elution, which began in September 1984 now nears completion

  1. International experience in the implementation of the lessons learned from the Three Mile Island incident

    International Nuclear Information System (INIS)

    1983-08-01

    This document consists of two parts and an Appendix. Part I provides a summary of worldwide experiences and subsequent recommendations regarding the implementation of the Three Mile Island-Unit 2 incident lessons learned. Part II gives in a summary fashion, specific responses and actions of the mentioned countries and international organizations as categorized into ten (10) subject areas. The Appendix, on the other hand, contains examples of the experiences of Brazil, Germany (F.R.), Hungary, and the Philippines, on the implementation of TMI lessons learned. This document should be useful to countries with nuclear power development programmes in that it provides a means for comparison of their actions with others. For countries which are embarking on their first nuclear power project, the document should provide a useful reference for specific TMI-related issues that need to be considered in their nuclear programmes

  2. Electric-utility returns and risk in the light of Three Mile Island

    International Nuclear Information System (INIS)

    Brooks, L.D.; D'Souza, R.E.

    1982-01-01

    The impact of the Three Mile Island nuclear-generating-unit failure on the performance of nuclear-dependent electric utilities is examined in this article. A comparative examination of the time series of abnormal returns and risk measures on nuclear-dependent utilities and nondependent utilities prior to the TMI incident, at the time of the incident, and subsequent to it was performed by the authors. The results are consistent with a hypothesis that investors associate a decline in future profitability or increased risk with nuclear-associated utilities. However, the more-objective measures indicate a clear reduction in risk for nuclear-associated utilities since the TMI incident, both in relation to the market as a whole and in relation to electric utilities which are not nuclear-associated. 4 references, 1 figure, 3 tables

  3. 49 CFR 228.105 - Additional requirements; construction within one-third mile (1,760 feet) (536 meters) of certain...

    Science.gov (United States)

    2010-10-01

    ... employee safety from toxic gases or explosions such as employee training and evacuation plans, availability... TRANSPORTATION HOURS OF SERVICE OF RAILROAD EMPLOYEES Construction of Employee Sleeping Quarters § 228.105... within 3 miles (15,840 feet) (4,827 meters) of the reporting point for the employees who are to be housed...

  4. Radionuclide analyses taken during primary coolant decontamination at Three Mile Island indicate general circulation

    International Nuclear Information System (INIS)

    Hofstetter, K.J.; Baston, V.F.; Hitz, C.G.; Malinauskas, A.P.

    1983-01-01

    Radionuclide concentration data taken during decontamination of the primary reactor coolant system at Three Mile Island by a feed-and-bleed process have provided information on future defueling operations. Analysis of the radiocesium concentrations in samples taken at the letdown point indicates general circulation within the primary system, including the reactor vessel and both steam generators. A standard dilution model with parameters consistent with engineering estimates (volume, flow rate, etc.) accurately predicts the radiocesium decontamination rates. Unlike cesium, the behavior of other principal soluble radionuclides ( 90 Sr and 3 H) cannot be readily described by dilution theory. A significant appearance rate is observed for 90 Sr suggesting a chemical solubility mechanism. The use of processed water containing high 3 H for makeup causes uncertainty in the interpretation of the 3 H analysis

  5. 77 FR 31725 - Safety Zone; Belle Pass Dredge Operations, Belle Pass, Mile Marker 1.0 to Mile Marker (−0.2...

    Science.gov (United States)

    2012-05-30

    ... Environmental Health Risks and Safety Risks. This rule is not an economically significant rule and does not create an environmental risk to health or risk to safety that may disproportionately affect children. 11...-AA00 Safety Zone; Belle Pass Dredge Operations, Belle Pass, Mile Marker 1.0 to Mile Marker (-0.2), Port...

  6. R2 & NE: NAVTEQ 2011 Q3 Exit Points for the United States, including Puerto Rico and the US Virgin Islands in SDC Format

    Data.gov (United States)

    U.S. Environmental Protection Agency — The EXITS layer contains point representations of the locations of exits, typically on controlled access roads such as motorways and freeways. Controlled access...

  7. Consumer Perceptions of Mobile and Traditional Point-of-Sale Credit/Debit Card Systems in the United States: A Survey

    OpenAIRE

    Saxena, Nitish; Sloan, John. J.; Godbole, Manasvee; Yu, Jun; Cai, Jacinta; Goergescu, Michael; Harper, Olive Nick; Schwebel, David, C.

    2016-01-01

    In recent years, rapidly emerging technology has introduced mobile Point-Of-Sale (MPOS) systems to the North American market. These systems allow merchants to process transactions conveniently and quickly using mobile phones or tablets rather than “traditional” point-of-sale (TPOS) credit card-processing systems. However, the long-term success of these new payment systems relies on consumers perceiving the device to be secure, accurate, and free from criminal activity. We present a case vs. c...

  8. Nuclear reactor safety research since Three Mile Island

    International Nuclear Information System (INIS)

    Mynatt, F.R.

    1982-01-01

    The Three Mile Island nuclear power plant accident has resulted in redirection of reactor safety research priorities. The small release to the environment of radioactive iodine-13 to 17 curies in a total radioactivity release of 2.4 million to 13 million curies-has led to a new emphasis on the physical chemistry of fission product behavior in accidents; the fact that the nuclear core was severely damaged but did not melt down has opened a new accident regime-that of the degraded core; the role of the operators in the progression and severity of the accident has shifted emphasis from equipment reliability to human reliability. As research progresses in these areas, the technical base for regulation and risk analysis will change substantially

  9. Nuclear reactor safety research since three mile island.

    Science.gov (United States)

    Mynatt, F R

    1982-04-09

    The Three Mile Island nuclear power plant accident has resulted in redirection of reactor safety research priorities. The small release to the environment of radioactive iodine-13 to 17 curies in a total radioactivity release of 2.4 million to 13 million curies-has led to a new emphasis on the physical chemistry of fission product behavior in accidents; the fact that the nuclear core was severely damaged but did not melt down has opened a new accident regime-that of the degraded core; the role of the operators in the progression and severity of the accident has shifted emphasis from equipment reliability to human reliability. As research progresses in these areas, the technical base for regulation and risk analysis will change substantially.

  10. Adrenal cortical response to stress at Three Mile Island.

    Science.gov (United States)

    Schaeffer, M A; Baum, A

    1984-01-01

    The present study examined the relationship between biochemical, psychologic, and behavioral components of chronic stress associated with living near the damaged nuclear power plant at Three Mile Island (TMI). Relative to control subjects, TMI subjects had higher levels of urinary cortisol, which correlated significantly with urinary catecholamines, self-report of physical and mental symptoms, and decrements in task performance. Further, it was found that males had higher urinary cortisol levels than females at TMI, while at the control sites, levels of cortisol were comparable between males and females. Finally, no significant relationship between coping style and urinary cortisol was detected. Levels of stress response among TMI are residents, though significantly greater than control subjects, were within normal ranges and thus should be considered subclinical in intensity. Their persistence over 17 months, however, suggests some cause for concern.

  11. Three Mile Island and Chernobyl: what happened. What did not

    International Nuclear Information System (INIS)

    Rasmussen, N.C.

    1994-01-01

    Three Mile Island (TMI) melted 20 tons of fuel and Chernobyl melted 190 tons of fuel. Contrary to some prior predictions, the fuel at TMI collected in the bottom head but did not melt through the vessel. At Chernobyl, about 130 tons of fuel remained in the reactor cavity after the explosion. It took nine days for this fuel to melt through 6 m of serpentine gravel after which it quickly spread on the floor below the reactor and solidified. It caused no damage to piping or building structures. Again, this was much less damage than expected. Information from these two events should be used to see if more realistic models of core melt can be developed

  12. Psychological adaptation among residents following restart of Three Mile Island.

    Science.gov (United States)

    Prince-Embury, S; Rooney, J F

    1995-01-01

    Psychological adaptation is examined in a sample of residents who remained in the vicinity of Three Mile Island following the restart of the nuclear generating facility which had been shut down since the 1979 accident. Findings indicate a lowering of psychological symptoms between 1985 and 1989 in spite of increased lack of control, less faith in experts and increased fear of developing cancer. The suggestion is made that reduced stress might have been related to a process of adaptation whereby a cognition of emergency preparedness was integrated by some of these residents as a modulating cognitive element. Findings also indicate that "loss of faith in experts" is a persistently salient cognition consistent with the "shattered assumptions" theory of victimization.

  13. Chronic stress, catecholamines, and sleep disturbance at Three Mile Island.

    Science.gov (United States)

    Davidson, L M; Fleming, R; Baum, A

    1987-01-01

    The present study was concerned with the relationship between chronic stress and sleep disturbance. Previous research has provided evidence of chronic stress responding among people living near the Three Mile Island nuclear generating facility. Compared to control subjects, the TMI group has exhibited greater symptom reporting, poorer performance on behavioral measures of concentration, and elevated levels of urinary norepinephrine and epinephrine. Other research has suggested a relationship between arousal and insomnia. The extent to which stress and sleep disturbances were experienced by residents at TMI was examined and compared to levels of stress and sleep disturbance among a group of control subjects. The relationship between stress and sleep disturbances was also examined. Results indicated that TMI area residents exhibited more stress than the controls and reported greater disturbance of sleep. Modest relationships among stress and sleep measures suggested that the symptoms of stress measured in this study were not primary determinants of sleep problems.

  14. Chronic stress, catecholamines, and sleep disturbance at Three Mile Island

    International Nuclear Information System (INIS)

    Davidson, L.M.; Fleming, R.; Baum, A.

    1987-01-01

    The present study was concerned with the relationship between chronic stress and sleep disturbance. Previous research has provided evidence of chronic stress responding among people living near the Three Mile Island nuclear generating facility. Compared to control subjects, the TMI group has exhibited greater symptom reporting, poorer performance on behavioral measures of concentration, and elevated levels of urinary norepinephrine and epinephrine. Other research has suggested a relationship between arousal and insomnia. The extent to which stress and sleep disturbances were experienced by residents at TMI was examined and compared to levels of stress and sleep disturbance among a group of control subjects. The relationship between stress and sleep disturbances was also examined. Results indicated that TMI area residents exhibited more stress than the controls and reported greater disturbance of sleep. Modest relationships among stress and sleep measures suggested that the symptoms of stress measured in this study were not primary determinants of sleep problems

  15. Operator/instrumentation interactions during the Three Mile Island incident

    International Nuclear Information System (INIS)

    Cummings, G.E.

    1979-10-01

    A discussion is presented of the operator/instrumentation interactions which had an effect on the course of the incident at the Three Mile Island-2 Nuclear Power Plant. A brief review of the sequence of occurrences at TMI-2 over the first 16 hours of the incident is given with particular emphasis on operator/instrumentation interactions. A breakdown of the six major items that seemed to have contributed to the characteristics of the incident is then given and also an outline of some of the currently proposed operator/instrumentation improvements. The six major items involve water level indication in the reactor, electromatic relief valve operation, auxiliary feed-water flow indication, containment isolation, extended range instrumentation, and computer readout

  16. Tourist visitation impacts of the accident at Three Mile Island

    International Nuclear Information System (INIS)

    Himmelberger, J.J.; Ogneva-Himmelberger, Y.A.; Baughman, M.L.

    1993-01-01

    This paper analyzes tourist visitation impacts of the March 27, 1979 accident at Three Mile Island. A review of the literature, supplemented with recollections from Pennsylvanian public officials, are used to specify a conventional tourism impact model which holds that depressed 1979 summer tourism season was more influenced by gasoline shortages and possibly other confounding variables (such as rainy local weather conditions and a polio outbreak) than by the nuclear accident. Regression analysis using monthly visitation data for Hershey Chocolate World, Gettysburg National Park, The Pennsylvania Dutch Convention and Visitor Bureau, and several state parks as dependent variables provide support for this model. Potential tourism implications of an accident at Yucca Mountain are briefly discussed in light of our findings

  17. Safety culture and the accident at Three Mile Island

    International Nuclear Information System (INIS)

    Erp, Jan B. van

    2002-01-01

    Prior to the accident at Three Mile Island, little attention was being paid to the human role in the safe operation of civilian nuclear power plants. The investigation of the TMI accident showed that its root causes were primarily human-related. The Kemeny Report on the TMI accident does not use the term 'safety culture'; however, it fully identifies all relevant aspects of safety culture. It was only after the accident at Chernobyl that the term 'safety culture' came into widespread use. However, it should be noted that, during the years after TMI and before Chernobyl, already major changes had been instituted concerning human factors and human reliability in the civilian nuclear energy programs of many countries. Greater credit should be given to the remarkable insights developed by the Kemeny Commission as contained in the Kemeny Report. (author)

  18. Analysis of the Three Mile Island (TMI-2) hydrogen burn

    International Nuclear Information System (INIS)

    Henrie, J.; Postma, A.

    1983-01-01

    As a basis for the analysis of the hydrogen burn which occurred in the Three Mile Island Containment on March 28, 1979, a study of recorded temperatures and pressures was made. Long-term temperature information was obtained from the multipoint temperature recorder which shows 12 containment atmosphere temperatures plotted every 6 min. The containment atmosphere pressure recorder provided excellent long and short-term pressure information. Short-term information was obtained from the multiplex record of 24 channels of data, recorded every 3 sec, and the alarm printer record which shows status change events and prints out temperatures, pressures, and the time of the events. The timing of these four data recording systems was correlated and pertinent data were tabulated, analyzed and plotted to show average containment temperature and pressure versus time. The data used have not been qualified and accuracy is not fully assured. Photographs and videotapes of the containment entries provided qualitative burn information

  19. Accident at Three Mile Island: the human dimensions

    International Nuclear Information System (INIS)

    Sills, D.L.; Wolf, C.P.; Shelanski, V.B.

    1982-01-01

    A separate abstract was prepared for each of the 19 chapters, divided according to the following Parts: (1) Public Perceptions of Nuclear Energy; (2) Local Responses to Nuclear Plants; (3) Institutional Responsibilities for Nuclear Energy; (4) The Interaction of Social and Technical Systems; and (5) Implications for Public Policy. All of the abstracts will appear in Energy Abstracts for Policy Analysis (EAPA); three will appear in Energy Research Abstracts (ERA). At the request of the President's Commission on the Accident at Three Mile Island (the Kemeny Commission), the Social Science Research Council commissioned social scientists to write a series of papers on the human dimensions of the event. This volume includes those papers, in revised and expanded form, and a comprehensive bibliography of published and unpublished social science research on the accident and its aftermath

  20. The Three Mile Island accident. Diagnosis and prognosis

    International Nuclear Information System (INIS)

    Toth, L.M.; Malinauskas, A.P.; Eidam, G.R.; Burton, H.M.

    1986-01-01

    The Three Mile Island accident occurred on March 29, 1979. The decision to hold a symposium on the TMI accident aftermath was reached when it was realized that enough information had been gathered during the past 6 years to provide a fairly complete picture of the damage and of the activities required for eventual recovery. The symposium was organized into three sessions: the first dealt with a description of the accident, the second focused on the chemical aspects involved, and the third addressed the strategy and progress made toward recovery. The symposium was intended to focus on these three subjects and leave the environmental considerations to future meetings and reports. Although it might appear shortsighted to exclude the environmental impact, the exclusion was considered necessary in order to maintain the focus we sought

  1. The Three Mile Island - 2 incident and damage to pheasants

    International Nuclear Information System (INIS)

    Boeck, H.

    1981-01-01

    In popular Austrian TV show deformed pheasants were shown hatched from eggs which were purchased by an Austrian pheasants breeder from a pheasantry about 60 miles from Harrisburg. The case was presented in such a way that the public could have correlated the deformed pheasants to the TMI-2 incident. As detailed investigations showed that the radiation dose after the TMI-2 incident was rather low even very close to the nuclear power plant such an effect seems highly unlikely. Analyses of the hatch percentages of other pheasants breeder using eggs from the very same flock showed no abnormal behaviour whatsoever. Therefore, the negative hatch result of the Austrian breeder must originate in other environmental effects either during transport or breeding. (author)

  2. Adrenal cortical response to stress at Three Mile Island

    International Nuclear Information System (INIS)

    Schaeffer, M.A.; Baum, A.

    1984-01-01

    The present study examined the relationship between biochemical, psychologic, and behavioral components of chronic stress associated with living near the damaged nuclear power plant at Three Mile Island (TMI). Relative to control subjects, TMI subjects had higher levels of urinary cortisol, which correlated significantly with urinary catecholamines, self-report of physical and mental symptoms, and decrements in task performance. Further, it was found that males had higher urinary cortisol levels than females at TMI, while at the control sites, levels of cortisol were comparable between males and females. Finally, no significant relationship between coping style and urinary cortisol was detected. Levels of stress response among TMI are residents, though significantly greater than control subjects, were within normal ranges and thus should be considered subclinical in intensity. Their persistence over 17 months, however, suggests some cause for concern

  3. First Mile Challenges for Large-Scale IoT

    KAUST Repository

    Bader, Ahmed

    2017-03-16

    The Internet of Things is large-scale by nature. This is not only manifested by the large number of connected devices, but also by the sheer scale of spatial traffic intensity that must be accommodated, primarily in the uplink direction. To that end, cellular networks are indeed a strong first mile candidate to accommodate the data tsunami to be generated by the IoT. However, IoT devices are required in the cellular paradigm to undergo random access procedures as a precursor to resource allocation. Such procedures impose a major bottleneck that hinders cellular networks\\' ability to support large-scale IoT. In this article, we shed light on the random access dilemma and present a case study based on experimental data as well as system-level simulations. Accordingly, a case is built for the latent need to revisit random access procedures. A call for action is motivated by listing a few potential remedies and recommendations.

  4. Post Three Mile Island shielding review - a case history

    International Nuclear Information System (INIS)

    Isakari, H.H.; Shaw, H.C.

    1983-01-01

    The radiation shielding review of the Diablo Canyon Nuclear Power Plant was performed in accordance with the requirement of the Three Mile Island Action Plan. The review covered plant shielding and environmental qualification of equipment for spaces and systems which may be used in post-accident operations. Radiation doses during postulated loss-of-coolant accident and high-energy-line-break accident were calculated for equipment located both inside and outside the containment. Vital areas, those requiring post-accident access and occupancy, were identified and their associated dose rates and integrated doses were calculated. It was found that all four of the vital areas (Control Room, Technical Support Center, Switchgear Room, and Emergency Sampling Compartment) are shielded from external sources of radiation sufficiently to permit personnel access and occupancy that would not be unduly limited by the radiation environment caused by the postulated accidents. (author)

  5. Sociologismo e individualismo em Émile Durkheim

    Directory of Open Access Journals (Sweden)

    Sidnei Ferreira de Vares

    Full Text Available O presente trabalho pretende analisar o tema do individualismo na teoria sociológica de Émile Durkheim com vistas a compreender a validade das críticas direcionadas por seus principais comentadores à primazia do campo social, à preocupação com a ordem e à adoção de uma postura anti-individualista que permearia toda a extensão de sua obra. Para tanto, promovemos um diálogo entre as abordagens mais recentes da obra durkheimiana e as interpretações consagradas pela tradição sociológica, com o objetivo de verificar o peso que o sociólogo francês atribuía ao indivíduo e à sociedade em sua teoria.

  6. NSAC: in-depth look at Three Mile Island

    International Nuclear Information System (INIS)

    Lihach, N.; Zebroski, E.

    1979-01-01

    The Nuclear Safety Analysis Center (NSAC) is hoping to learn what caused the reactor accident at Three Mile Island, what happened during the accident, and how to take advantage of what is learned to prevent future incidents. When the Electric Power Research Institute (EPRI) was asked to make an independent assessment, the NSAC was organized with a separate identity and funded by special contributions from the electric utilities. The Center has nearly completed the first phase of organization and data gathering on the sequence of events. This will be followed by a safety analysis to determine causes and to look for ways to improve nuclear power plant technology. The Center will also serve as a clearing house for studies on the effects of radiation, improvements in instrumentation, and emergency response systems

  7. Tipping Point

    Medline Plus

    Full Text Available ... en español Blog About OnSafety CPSC Stands for Safety The Tipping Point Home > 60 Seconds of Safety (Videos) > The Tipping Point The Tipping Point by ... danger death electrical fall furniture head injury product safety television tipover tv Watch the video in Adobe ...

  8. Effects of the accident at Three Mile Island on the mental health and behavioral responses of the general population and nuclear workers

    International Nuclear Information System (INIS)

    Fabrikant, J.I.

    1983-02-01

    On March 28, 1979, an accident occurred at the Three Mile Island nuclear power plant Unit No. 2 near Middletown, PA. A Presidential Commission was established to investigate the incident and was given the responsibility to evaluate the actual and potential impact of the events on the health and safety of the workers and the public. A main conclusion of the investigation was that the most serious health effect was severe, short-lived mental stress. This paper describes the study and the findings for four different study groups: (1) the general population of heads of households located within 20 miles of the plant; (2) mothers of preschool children from the same area; (3) teenagers in the 7th, 9th, and 11th grades from the area; and (4) nuclear workers employed at the Three Mile Island nuclear power plant

  9. Technical evaluation report on the Third 10-year Interval Inservice Inspection Program Plan: Florida Power and Light Company, Turkey Point Nuclear Power Plant, Units 3 and 4 (Docket Numbers 50-250 and 50-251)

    International Nuclear Information System (INIS)

    Brown, B.W.; Feige, E.J.; Galbraith, S.G.; Porter, A.M.

    1995-02-01

    This report presents the results of the evaluation of the Turkey Point Nuclear Power Plant, Units 3 and 4, Third 10-Year Interval Inservice Inspection Program Plan, Revision 0, submitted September 9, 1993, including the requests for relief from the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section XI, requirements that the licensee has determined to be impractical. The Turkey Point Nuclear Power Plant, Units 3 and 4, Third 10-Year Interval Inservice Inspection Program Plan is evaluated in Section 2 of this report. The inservice inspection (ISI) program plan is evaluated for (a) compliance with the appropriate edition/addenda of Section XI, (b) acceptability of the examination sample, (c) correctness of the application of system or component examination exclusion criteria, and (d) compliance with ISI-related commitments identified during previous Nuclear Regulatory Commission (NRC) reviews. The requests for relief are evaluated in Section 3 of this report

  10. Proposed design modifications and technical specification changes on grid voltage degradation for the Point Beach Nuclear Plant, Units 1 and 2 (Docket Nos. 50-266 and 50-301). Technical evaluation report

    International Nuclear Information System (INIS)

    White, R.L.

    1981-01-01

    This report documents the technical evaluation of the proposed design mofifications and Technical Specification changes for protection of Class 1E equipment from grid voltage degradation for the Point Beach Nuclear Plant, Units 1 and 2. The review criteria are based on several IEEE standards and the Code of Federal Regulations. The evaluation compares the submittals made by the licensee with the NRC staff positions and the review criteria and presents the reviewer's conclusion on the acceptability of the proposed system

  11. Analysis of effects on plant performance by major measuring points in the secondary systems of Kori nuclear power plant units 3 and 4

    International Nuclear Information System (INIS)

    Lee, Jung Woon; Park, Jae Chang; Lee, Jung Woon; Kim, Jung Taek; Chang, Soon Heung; Lee, Gwang Gu; Heo, Gyun Young; Lee, Sung Jin; Han, Kyu Hyun; Shin, Byung Soo

    2003-06-01

    In this study, correlation analysis was achieved for the major sensor position and the behavior of secondary system in Kori NPP unit 3, 4. Using the data from simulation model, the correlation between sensor position and electrical output, the correlation between sensor position and heat rate, and the correlation between different sensor positions were analyzed. On the basis of study results, a performance evaluation model was proposed, which can carry out secondary system performance diagnosis

  12. Free space optics: a viable last-mile alternative

    Science.gov (United States)

    Willebrand, Heinz A.; Clark, Gerald R.

    2001-10-01

    This paper explores Free Space Optics (FSO) as an access technology in the last mile of metropolitan area networks (MANs). These networks are based in part on fiber-optic telecommunications infrastructure, including network architectures of Synchronous Optical Network (commonly referred to as SONET), the North American standard for synchronous data transmission; and Synchronous Digital Hierarchy (commonly referred to as SDH), the international standard and equivalent of SONET. Several converging forces have moved FSO beyond a niche technology for use only in local area networks (LANs) as a bridge connecting two facilities. FSO now allows service providers to cost effectively provide optical bandwidth for access networks and accelerate the extension of metro optical networks bridging what has been termed by industry experts as the optical dead zone. The optical dead zone refers to both the slowdown in capital investment in the short-term future and the actual connectivity gap that exists today between core metro optical networks and the access optical networks. Service providers have built extensive core and minimal metro networks but have not yet provided optical bandwidth to the access market largely due to the non-compelling economics to bridge the dead zone with fiber. Historically, such infrastructure build-out slowdowns have been blamed on a combination of economics, time-to-market constraints and limited technology options. However, new technology developments and market acceptance of FSO give service providers a new cost-effective alternative to provide high-bandwidth services with optical bandwidth in the access networks. Merrill Lynch predicts FSO will grow into a $2 billion market by 2005. The drivers for this market are a mere 5%- 6% penetration of fiber to business buildings; cost effective solution versus RF or fiber; and significant capacity which can only be matched by a physical fiber link, Merrill Lynch reports. This paper will describe FSO

  13. Investigating last mile distribution challenges of wine suppliers in Lagos, Nigeria

    OpenAIRE

    2014-01-01

    M.Com. (Business Management) The last mile distribution is the final link of successful supply chain operations. The high demand for products, lead time uncertainties and replenishment time complicate the distribution task. In order to achieve a competitive business edge, suppliers need to work at developing and improving their last mile distribution link. The aim of this study was to investigate the effectiveness of the last mile wine distribution in Lagos Island, Nigeria, and to determin...

  14. 78 FR 54168 - Special Local Regulation, Cumberland River, Mile 157.0 to 159.0; Ashland City, TN

    Science.gov (United States)

    2013-09-03

    ... Local Regulation, Cumberland River, Mile 157.0 to 159.0; Ashland City, TN AGENCY: Coast Guard, DHS... Special local regulation; Cumberland River, Miles 157.0 to 159.0, Ashland City, TN. (a) Location. The... regulation for the waters of the Cumberland River beginning at mile marker 157.0 and ending at mile marker...

  15. Four Mile Creek bottomland restoration program. Final report

    Energy Technology Data Exchange (ETDEWEB)

    McLeod, K.W.

    1995-12-31

    On the Savannah River Site (SRS), nuclear production reactors were cooled by a once-through cooling cycle, using water from the Savannah River and discharging the effluent to small tributaries of the Savannah River. Four Mile Creek (also known as Fourmile Branch) is a third order tributary of the Savannah River on the upper coastal plain of South Carolina. It received thermal effluent from C Reactor from 1955 to 1985, which increased the flow rate, water depth and water temperature. Prior to 1955, the base flow was approximately one cubic meter per second, but increased, with the reactor effluent, to approximately 11 cubic meters per second, raising the water depth in the channel by 15 to 30 cm. Effluent temperature at the outfall was approximately 60 C and at the delta was 40 to 45 C, depending on the operation level of the reactor, the season of the year and the specific meteorological conditions. The increased flow rate also increased erosion in the upper reaches of the stream with deposition of this eroded material occurring in the delta averaging 60 cm of newly deposited sand on top of the former substrate.

  16. Vegetation survey of Four Mile Creek wetlands. [Savannah River Plant

    Energy Technology Data Exchange (ETDEWEB)

    Loehle, C.

    1990-11-01

    A survey of forested wetlands along upper Four Mile Creek was conducted. The region from Road 3 to the creek headwaters was sampled to evaluate the composition of woody and herbaceons plant communities. All sites were found to fall into either the Nyssa sylvatica (Black Gum) -- Persea borbonia (Red Bay) or Nyssa sylvatica -- Acer rubrum (Red Maple) types. These community types are generally species-rich and diverse. Previous studies (Greenwood et al., 1990; Mackey, 1988) demonstrated contaminant stress in areas downslope from the F- and H-Area seepage basins. In the present study there were some indications of contaminant stress. In the wetland near H-Area, shrub basal area, ground cover stratum species richness, and diversity were low. In the area surrounding the F-Area tree kill zone, ground cover stratum cover and shrub basal area were low and ground cover stratum species richness was low. The moderately stressed site at F-Area also showed reduced overstory richness and diversity and reduced ground cover stratum richness. These results could, however, be due to the very high basal area of overstory trees in both stressed F-Area sites that would reduce light availability to understory plants. No threatened or endangered plant species were found in the areas sampled. 40 refs., 4 figs., 8 tabs.

  17. Radiological impacts of transporting Three Mile Island core debris

    International Nuclear Information System (INIS)

    Cox, N.D.

    1986-01-01

    This document presents an assessment of the radiological impacts of one cask shipment. It focuses on potential effects of the shipment on the public along the route. The document begins with a description of the shipping cask, followed by a description of the survivability tests required to confirm the cask design. Some actual accidents that similar casks have survived wholly intact are described. Next considered is the limit of radiation exposure dose rate that is imposed by regulatory agencies under normal conditions. No shipping of radioactive material is allowed unless the container is at or below the normal limit. A comparison is made between the normal radiation exposure limit and the radiation dose received annually by individuals from natural sources. Then, estimates of the radiation dose received by persons along the rail route in urban, suburban, and rural areas during normal transport are presented. Those times when the train stops for whatever reason (called rest stops) are considered also. Next, potential accident events are considered. Recent accident statistics are presented, and chances for an accident at different train velocities are estimated for any mile of track. The alternative of truck transport is considered briefly

  18. Four Mile Creek bottomland restoration program. Final report

    International Nuclear Information System (INIS)

    McLeod, K.W.

    1995-01-01

    On the Savannah River Site (SRS), nuclear production reactors were cooled by a once-through cooling cycle, using water from the Savannah River and discharging the effluent to small tributaries of the Savannah River. Four Mile Creek (also known as Fourmile Branch) is a third order tributary of the Savannah River on the upper coastal plain of South Carolina. It received thermal effluent from C Reactor from 1955 to 1985, which increased the flow rate, water depth and water temperature. Prior to 1955, the base flow was approximately one cubic meter per second, but increased, with the reactor effluent, to approximately 11 cubic meters per second, raising the water depth in the channel by 15 to 30 cm. Effluent temperature at the outfall was approximately 60 C and at the delta was 40 to 45 C, depending on the operation level of the reactor, the season of the year and the specific meteorological conditions. The increased flow rate also increased erosion in the upper reaches of the stream with deposition of this eroded material occurring in the delta averaging 60 cm of newly deposited sand on top of the former substrate

  19. Fixed Points

    Indian Academy of Sciences (India)

    Home; Journals; Resonance – Journal of Science Education; Volume 5; Issue 5. Fixed Points - From Russia with Love - A Primer of Fixed Point Theory. A K Vijaykumar. Book Review Volume 5 Issue 5 May 2000 pp 101-102. Fulltext. Click here to view fulltext PDF. Permanent link:

  20. Tipping Point

    Medline Plus

    Full Text Available ... OnSafety CPSC Stands for Safety The Tipping Point Home > 60 Seconds of Safety (Videos) > The Tipping Point ... 24 hours a day. For young children whose home is a playground, it’s the best way to ...

  1. Tipping Point

    Medline Plus

    Full Text Available ... 60 Seconds of Safety (Videos) > The Tipping Point The Tipping Point by CPSC Blogger September 22, 2009 appliance child Childproofing CPSC danger death electrical fall furniture head injury product safety television tipover tv Watch the video in Adobe Flash ...

  2. Understanding the Role of Built Environment in Reducing Vehicle Miles Traveled Accounting for Spatial Heterogeneity

    Directory of Open Access Journals (Sweden)

    Chuan Ding

    2014-01-01

    Full Text Available In recent years, increasing concerns over climate change and transportation energy consumption have sparked research into the influences of urban form and land use patterns on motorized travel, notably vehicle miles traveled (VMT. However, empirical studies provide mixed evidence of the influence of the built environment on travel. In particular, the role of density after controlling for the confounding factors (e.g., land use mix, average block size, and distance from CBD still remains unclear. The object of this study is twofold. First, this research provides additional insights into the effects of built environment factors on the work-related VMT, considering urban form measurements at both the home location and workplace simultaneously. Second, a cross-classified multilevel model using Bayesian approach is applied to account for the spatial heterogeneity across spatial units. Using Washington DC as our study area, the home-based work tour in the AM peak hours is used as the analysis unit. Estimation results confirmed the important role that the built environment at both home and workplace plays in affecting work-related VMT. In particular, the results reveal that densities at the workplace have more important roles than that at home location. These findings confirm that urban planning and city design should be part of the solution in stabilizing global climate and energy consumption.

  3. 75 FR 38845 - Exelon Generation Company, LLC; Three Mile Island Nuclear Station, Unit No. 1; Exemption

    Science.gov (United States)

    2010-07-06

    ... available, the method of communication will be face-to-face or using radios via line-of-sight (i.e., no repeaters). The licensee simulated face-to-face communication was simulated by having operators start the... hand held radio or installed phones but may also be reported by face-to-face communication if plant...

  4. Three Mile Island unit 2 vessel investigation project. Conclusions and significance

    International Nuclear Information System (INIS)

    Beckjord, E.S.

    1994-01-01

    At the conclusion of the TMI-2 Vessel Investigation Project, additional insights about the accident have been gained, specifically in the area of reactor vessel integrity and the conditions of the lower head of the reactor vessel. This paper discusses three topics: the evolving views about the TMI-2 accident scenario over time, the technical conclusions of the TMI-2 VIP (recovery of samples from the vessel lower head), and the broad significance of these findings (accident management). 4 refs

  5. Investigation of intergranular stress corrosion cracking in the fuel pool at Three Mile Island Unit 1

    International Nuclear Information System (INIS)

    Czajkowski, C.J.

    1985-01-01

    An intergranular stress corrosion cracking failure of 304 stainless steel pipe in 2000 ppM B as H 3 BO 3 + H 2 O at 100 0 C has been investigated. Constant extension rate testing has produced an intergranular type failure in material in air. Chemical analysis was performed on both the base metal and weld material, in addition to fractography, EPR testing and optical microscopy in discerning the mode of failure. Various effects of Cl - , O 2 , and MnS are discussed. The results have indicated that the cause of failure was the severe sensitization coupled with probable contamination by S and possibly by Cl ions

  6. TMI-2 [Three-Mile Island-Unit 2] rail cask and railcar maintenance

    International Nuclear Information System (INIS)

    Tyacke, M.J.; Ayers, A.L. Jr.; Ball, L.J.; Anselmo, A.A.

    1988-02-01

    This paper describes the NuPac 125-B cask system (i.e., cask and railcar), and the maintenance and inspection requirements for that system. The paper discusses the operations being done to satisfy those requirements and how, in some cases, it has been efficient for the operations to be more rigorous than the requirements. Finally, this paper discusses the experiences gained from those operations and how specific hardware and procedural enhancements have resulted in a reliable and continuous shipping campaign. 2 refs., 2 figs

  7. Evaluation of long-term post-accident core cooling of Three Mile Island Unit 2

    Energy Technology Data Exchange (ETDEWEB)

    None

    1979-04-15

    On the basis of current understanding of the accident scenario and available data, the staff reports here on its evaluation of the condition of the core and the core flow resistance as it might affect ability to cool the core by natural circulation. The natural circulation cooling capability of TMI-2 for the estimated core flow resistance and a variety of other conditions is evaluated and a comparison of the Base Case and off-nominal plant configurations is presented. The potential for and effects of natural convection core cooling are addressed, and the staff recommendations for reactor performance acceptance criteria upon initiation of natural convection are presented.

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

    International Nuclear Information System (INIS)

    1976-01-01

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

  9. TMI-2 [Three Mile Island Unit 2] primary coolant mass flowrate data report

    International Nuclear Information System (INIS)

    McCormick, R.D.

    1986-12-01

    This is a report on the preparation of data from the TMI-2 primary coolant mass flowrate meters for inclusion into the TMI Data Base. The sources of the as-recorded data are discussed, and a description of the instrument is given. An explanation is given of how corrections were made to the as-recorded data and how the uncertainties were calculated. The identifiers attached to each data set in the TMI Data Base are given

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

    International Nuclear Information System (INIS)

    1977-01-01

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

  11. Neutronic analysis of the Three Mile Island Unit 2 ex-core detector response

    International Nuclear Information System (INIS)

    Malloy, D.J.; Chang, Y.I.

    1981-10-01

    A neutronic analysis has been made with respect to the ex-core neutron detector response during the TMI-2 incident. A series of transport theory calculations quantified the impact upon the detector count rate of various core and downcomer conditions. In particular, various combinations of coolant void content and spatial distributions were investigated to yield the resulting transmission of the photoneutron source to the detector. The impact of a hypothetical distributed source within the downcomer region was also examined in order to simulate the potential effect of the release of neutron producing fission products into the coolant. These results are then offered as potential explanations for the anomalous behavior of the detector during the period of approx. 20 minutes through approx. 3 hours following the reactor scram

  12. The Necessity of Implementing a Quality Management System in the Romanian Medical Units. An Approach from the Patient’s Point of View

    Directory of Open Access Journals (Sweden)

    Roxana Sârbu

    2011-11-01

    Full Text Available The medical services organizations activate in a specific featured environment, extremely sensitive, dynamic and most of the times unpredictable. In order to develop their activity at a high qualitative level, medical units must possess the ability of accepting the changes that might occur, of identifying and valorizing the possible opportunities and, at the same time, they must have the ability of avoiding risks as much as possible. The medical field considers quality a variable which is hard to quantify and which could be perceived as the result of the comparison between the medical service desired/requested by the client and the provided health service or the extent to which the provided service corresponds to the client’s expectations. The current paper refers to the growing problems of the Romanian health system and it also takes into consideration the deficiencies which influence the quality of the provided services. The approach manner of this particular theme is realized by taking into account the quality management system. At the same time, there is made an analysis of the consumer’s perception regarding both the quality of health services and the necessity of implementing a quality management system in all units providing health services. The research is based on a rich study of the professional literature, on articles and scientific papers in this field of activity. The data was collected by applying a questionnaire to the population which has been provided medical services over the past year.

  13. Point-prevalence survey of healthcare facility-onset healthcare-associated Clostridium difficile infection in Greek hospitals outside the intensive care unit: The C. DEFINE study.

    Science.gov (United States)

    Skoutelis, Athanasios; Pefanis, Angelos; Tsiodras, Sotirios; Sipsas, Nikolaos V; Lelekis, Moyssis; Lazanas, Marios C; Gargalianos, Panagiotis; Dalekos, George N; Roilides, Emmanuel; Samonis, George; Maltezos, Efstratios; Hatzigeorgiou, Dimitrios; Lada, Malvina; Metallidis, Symeon; Stoupis, Athena; Chrysos, Georgios; Karnesis, Lazaros; Symbardi, Styliani; Loupa, Chariclia V; Giamarellou, Helen; Kioumis, Ioannis; Sambatakou, Helen; Tsianos, Epameinondas; Kotsopoulou, Maria; Georgopali, Areti; Liakou, Klairi; Perlorentzou, Stavroula; Levidiotou, Stamatina; Giotsa-Toutouza, Marina; Tsorlini-Christoforidou, Helen; Karaiskos, Ilias; Kouppari, Georgia; Trikka-Graphakos, Eleftheria; Ntrivala, Maria-Anna; Themeli-Digalaki, Kate; Pangalis, Anastasia; Kachrimanidou, Melina; Martsoukou, Maria; Karapsias, Stergios; Panopoulou, Maria; Maraki, Sofia; Orfanou, Anagnostina; Petinaki, Efthymia; Orfanidou, Maria; Baka, Vasiliki; Stylianakis, Antonios; Spiliopoulou, Iris; Smilakou, Stavroula; Zerva, Loukia; Vogiatzakis, Evangelos; Belesiotou, Eleni; Gogos, Charalambos A

    2017-01-01

    The correlation of Clostridium difficile infection (CDI) with in-hospital morbidity is important in hospital settings where broad-spectrum antimicrobial agents are routinely used, such as in Greece. The C. DEFINE study aimed to assess point-prevalence of CDI in Greece during two study periods in 2013. There were two study periods consisting of a single day in March and another in October 2013. Stool samples from all patients hospitalized outside the ICU aged ≥18 years old with diarrhea on each day in 21 and 25 hospitals, respectively, were tested for CDI. Samples were tested for the presence of glutamate dehydrogenase antigen (GDH) and toxins A/B of C. difficile; samples positive for GDH and negative for toxins were further tested by culture and PCR for the presence of toxin genes. An analysis was performed to identify potential risk factors for CDI among patients with diarrhea. 5,536 and 6,523 patients were screened during the first and second study periods, respectively. The respective point-prevalence of CDI in all patients was 5.6 and 3.9 per 10,000 patient bed-days whereas the proportion of CDI among patients with diarrhea was 17% and 14.3%. Logistic regression analysis revealed that solid tumor malignancy [odds ratio (OR) 2.69, 95% confidence interval (CI): 1.18-6.15, p = 0.019] and antimicrobial administration (OR 3.61, 95% CI: 1.03-12.76, p = 0.045) were independent risk factors for CDI development. Charlson's Comorbidity Index (CCI) >6 was also found as a risk factor of marginal statistical significance (OR 2.24, 95% CI: 0.98-5.10). Median time to CDI from hospital admission was shorter with the presence of solid tumor malignancy (3 vs 5 days; p = 0.002) and of CCI >6 (4 vs 6 days, p = 0.009). The point-prevalence of CDI in Greek hospitals was consistent among cases of diarrhea over a 6-month period. Major risk factors were antimicrobial use, solid tumor malignancy and a CCI score >6.

  14. Dew Point

    OpenAIRE

    Goldsmith, Shelly

    1999-01-01

    Dew Point was a solo exhibition originating at PriceWaterhouseCoopers Headquarters Gallery, London, UK and toured to the Centre de Documentacio i Museu Textil, Terrassa, Spain and Gallery Aoyama, Tokyo, Japan.

  15. Tipping Point

    Medline Plus

    Full Text Available ... Point by CPSC Blogger September 22, 2009 appliance child Childproofing CPSC danger death electrical fall furniture head injury product safety television tipover tv Watch the video in Adobe Flash ...

  16. Tipping Point

    Science.gov (United States)

    ... Point by CPSC Blogger September 22, 2009 appliance child Childproofing CPSC danger death electrical fall furniture head injury product safety television tipover tv Watch the video in Adobe Flash ...

  17. Tipping Point

    Medline Plus

    Full Text Available ... Point by CPSC Blogger September 22, 2009 appliance child Childproofing CPSC danger death electrical fall furniture head ... see news reports about horrible accidents involving young children and furniture, appliance and tv tip-overs. The ...

  18. Tipping Point

    Medline Plus

    Full Text Available ... Point by CPSC Blogger September 22, 2009 appliance child Childproofing CPSC danger death electrical fall furniture head ... TV falls with about the same force as child falling from the third story of a building. ...

  19. Tipping Point

    Medline Plus

    Full Text Available ... Tipping Point by CPSC Blogger September 22, 2009 appliance child Childproofing CPSC danger death electrical fall furniture ... about horrible accidents involving young children and furniture, appliance and tv tip-overs. The force of a ...

  20. Thyroid cancer characteristics in the population surrounding Three Mile Island.

    Science.gov (United States)

    Goyal, Neerav; Camacho, Fabian; Mangano, Joseph; Goldenberg, David

    2012-06-01

    To determine differences in disease characteristics between the thyroid cancer populations in the area around the Three Mile Island (TMI) nuclear power plant and the rest of the state of Pennsylvania. Retrospective cross-sectional study. Data from the Pennsylvania Cancer Registry from 1985 to 2008 were reviewed and information regarding age at diagnosis, sex, race, residential status, county of residence, thyroid pathology, thyroid surgery, and staging was recorded. Dauphin, Lancaster, and York counties were defined as the TMI area. Records of 26,357 thyroid cancer patients were reviewed, with 2,611 patients within the TMI area. A higher proportion of papillary thyroid cancer (P < .001) and lower proportion of follicular thyroid cancer (P < .001) were noted in the TMI area population. Thyroid cancer cases from the TMI area were found to be more likely to be diagnosed before the age of 65 years (P < .001), be Pennsylvania born (P < .001), be well differentiated (P < .001), be <10 mm in size (P < .001), and be localized without spread (P < .001). Although the TMI area shows a higher incidence of thyroid cancer as compared to the rest of the state, this was not statistically significant. The TMI population showed a higher proportion of papillary thyroid cancer and less aggressive pathology and earlier diagnosis compared to the rest of Pennsylvania. No statistically significant difference in thyroid cancer incidence was noted. Overall, the study does not show a clear link with more advanced thyroid cancer and proximity to the TMI nuclear reactors. Copyright © 2012 The American Laryngological, Rhinological, and Otological Society, Inc.

  1. Attenuation in the dubbing and subtitling of The Green Mile

    Directory of Open Access Journals (Sweden)

    Lidia Rodríguez

    2015-12-01

    Full Text Available This paper is part of the doctoral thesis entitled “Critique of translation for film dubbing and subtitling from the perspective of discourse analysis. A study applied to "The Green Mile”, written by Ph.D. student Gabriela Saturnina Alanís Uresti, directed by Ph.D. Lidia Rodríguez. It is a qualitative and descriptive study where we contrasted The Green Mile - a 1999 Hollywood film, original in American English - with its translated versions: dubbed and subtitled into Spanish of Mexico. We start from the presupposition that in film translation, some references such as the ones related to sexual behaviors and offensive language are attenuated in order to be strategically polite. Specifically, we analyzed two mechanisms of attenuation: lexical selection whereby a euphemism is used, and discursive modalization. These mechanisms constitute strategies of linguistic, pragmatic and semiotic nature as they appear in original (OV, dubbed (DV and subtitled (SV versions; both in acoustic and visual channels. Therefore, we examine these occurrences on verbal, para-verbal, and non-verbal codes. The theoretical basis includes studies of attenuation, politeness, euphemisms, and linguistic taboos. This paper is based on methodological proposals by Gutiérrez (2008, Nájar (2009, Brown y Levinson (1987, Goffman (1967, Leech (1983, Fraser (1980 Haverkate (1994, Bravo (2001, Albelda (2010, (2005, Albelda y Briz (2010, Briz (2002a; 2002b, Allan y Burridge (2006, Chamizo (2008, Foucault (1987, Seiciuc (2010, Dubois (1969, Dubois et al (1973, and Rodríguez (2004.

  2. Big Rock Point: 35 years of electrical generation

    International Nuclear Information System (INIS)

    Petrosky, T.D.

    1998-01-01

    On September 27, 1962, the 75 MWe boiling water reactor, designed and built by General Electric, of the Big Rock Point Nuclear Power Station went critical for the first time. The US Atomic Energy Commission (AEC) and the plant operator, Consumers Power, had designed the plant also as a research reactor. The first studies were devoted to fuel behavior, higher burnup, and materials research. The reactor was also used for medical technology: Co-60 radiation sources were produced for the treatment of more than 120,000 cancer patients. After the accident at the Three Mile Island-2 nuclear generating unit in 1979, Big Rock Point went through an extensive backfitting phase. Personnel from numerous other American nuclear power plants were trained at the simulator of Big Rock Point. The plant was decommissioned permanently on August 29, 1997 after more than 35 years of operation and a cumulated electric power production of 13,291 GWh. A period of five to seven years is estimated for decommissioning and demolition work up to the 'green field' stage. (orig.) [de

  3. 78 FR 46258 - Safety Zone; Upper Mississippi River, Mile 662.8 to 663.9

    Science.gov (United States)

    2013-07-31

    ...-AA00 Safety Zone; Upper Mississippi River, Mile 662.8 to 663.9 AGENCY: Coast Guard, DHS. ACTION: Temporary final rule. SUMMARY: The Coast Guard is establishing a temporary safety zone for all waters of the Upper Mississippi River, from mile 662.8 to 663.9, extending the entire width of the river. This safety...

  4. 75 FR 55973 - Safety Zone; Illinois River, Mile 000.5 to 001.5

    Science.gov (United States)

    2010-09-15

    ...-AA00 Safety Zone; Illinois River, Mile 000.5 to 001.5 AGENCY: Coast Guard, DHS. ACTION: Temporary final rule. SUMMARY: The Coast Guard is establishing a temporary safety zone for all waters of the Illinois River, Mile 000.5 to 001.5, extending the entire width of the river. This safety zone is needed to...

  5. 75 FR 53193 - Safety Zone; Mississippi River, Mile 427.3 to 427.5

    Science.gov (United States)

    2010-08-31

    ... Zone; Mississippi River, Mile 427.3 to 427.5 AGENCY: Coast Guard, DHS. ACTION: Temporary final rule. SUMMARY: The Coast Guard is establishing a temporary safety zone for all waters of the Upper Mississippi River, Mile 427.3 to 427.5, extending the entire width of the river. This safety zone is needed to...

  6. 75 FR 41764 - Safety Zone; Mississippi River, Mile 840.0 to 839.8

    Science.gov (United States)

    2010-07-19

    ...-AA00 Safety Zone; Mississippi River, Mile 840.0 to 839.8 AGENCY: Coast Guard, DHS. ACTION: Temporary final rule. SUMMARY: The Coat Guard is establishing a temporary safety zone for all waters of the Upper Mississippi River, Mile 840.0 to 839.8, extending the entire width of the river. This safety zone is needed to...

  7. 75 FR 55272 - Safety Zone; Mississippi River, Mile 212.0 to 214.5

    Science.gov (United States)

    2010-09-10

    ...-AA00 Safety Zone; Mississippi River, Mile 212.0 to 214.5 AGENCY: Coast Guard, DHS. ACTION: Temporary final rule. SUMMARY: The Coast Guard is establishing a temporary safety zone for waters of the Upper Mississippi River, Mile 212.0 to 214.5, extending West of Portage Island to the right descending bank of the...

  8. Development of 1-Mile Walk Tests to Estimate Aerobic Fitness in Children

    Science.gov (United States)

    Sung, Hoyong; Collier, David N.; DuBose, Katrina D.; Kemble, C. David; Mahar, Matthew T.

    2018-01-01

    To examine the reliability and validity of 1-mile walk tests for estimation of aerobic fitness (VO[subscript 2max]) in 10- to 13-year-old children and to cross-validate previously published equations. Participants (n = 61) walked 1-mile on two different days. Self-reported physical activity, demographic variables, and aerobic fitness were used in…

  9. Corrective Action Investigation Plan for Corrective Action Unit 262: Area 25 Septic Systems and Underground Discharge Point, Nevada Test Site, Nevada, Revision No. 1 (9/2001)

    International Nuclear Information System (INIS)

    2000-01-01

    This corrective action investigation plan contains the U.S. Department of Energy, Nevada Operations Office's approach to collect data necessary to evaluate corrective action alternatives appropriate for the closure of Corrective Action Unit (CAU) 262 under the Federal Facility Agreement and Consent Order. Corrective Action Unit 262 consists of nine Corrective Action Sites (CASs): Underground Storage Tank (25-02-06), Septic Systems A and B (25-04-06), Septic System (25-04-07), Leachfield (25-05-03), Leachfield (25-05-05), Leachfield (25-05-06), Radioactive Leachfield (25-05-08), Leachfield (25-05-12), and Dry Well (25-51-01). Situated in Area 25 at the Nevada Test Site (NTS), sites addressed by CAU 262 are located at the Reactor-Maintenance, Assembly, and Disassembly (R-MAD); Test Cell C; and Engine-Maintenance, Assembly, and Disassembly (E-MAD) facilities. The R-MAD, Test Cell C, and E-MAD facilities supported nuclear rocket reactor and engine testing as part of the Nuclear Rocket Development Station. The activities associated with the testing program were conducted between 1958 and 1973. Based on site history collected to support the Data Quality Objectives process, contaminants of potential concern (COPCs) for the site include oil/diesel-range total petroleum hydrocarbons, volatile organic compounds, semivolatile organic compounds, polychlorinated biphenyls, Resource Conservation and Recovery Act metals, and gamma-emitting radionuclides, isotopic uranium, isotopic plutonium, strontium-90, and tritium. The scope of the corrective action field investigation at the CAU will include the inspection of portions of the collection systems, sampling the contents of collection system features in situ of leachfield logging materials, surface soil sampling, collection of samples of soil underlying the base of inlet and outfall ends of septic tanks and outfall ends of diversion structures and distribution boxes, collection of soil samples from biased or a combination of

  10. A human reliability analysis of the Three Mile power plant accident considering the THERP and ATHEANA methodologies; Uma analise da confiabilidade humana do acidente na Usina de Three Mile Island II considerando as metodologias Therp e Atheana

    Energy Technology Data Exchange (ETDEWEB)

    Fonseca, Renato Alves da

    2004-03-15

    The main purpose of this work is the study of human reliability using the THERP (Technique for Human Error Prediction) and ATHEANA methods (A Technique for Human Error Analysis), and some tables and also, from case studies presented on the THERP Handbook to develop a qualitative and quantitative study of nuclear power plant accident. This accident occurred in the TMI (Three Mile Island Unit 2) power plant, PWR type plant, on March 28th, 1979. The accident analysis has revealed a series of incorrect actions, which resulted in the Unit 2 shut down and permanent loss of the reactor. This study also aims at enhancing the understanding of the THERP method and ATHEANA, and of its practical applications. In addition, it is possible to understand the influence of plant operational status on human failures and of these on equipment of a system, in this case, a nuclear power plant. (author)

  11. Technical-evaluation report on the proposed technical-specification changes for the inservice surveillance of safety-related hydraulic and mechanical snubbers at the Indian Point Nuclear Power Plant, Unit 3 (Docket No. 50-286)

    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 Indian Point Nuclear Power Plant, Unit 3. 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

  12. 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

  13. Cross-sectional point prevalence survey to study the environmental contamination of nosocomial pathogens in intensive care units under real-life conditions.

    Science.gov (United States)

    Wille, I; Mayr, A; Kreidl, P; Brühwasser, C; Hinterberger, G; Fritz, A; Posch, W; Fuchs, S; Obwegeser, A; Orth-Höller, D; Lass-Flörl, C

    2018-01-01

    In intensive care units (ICUs), inanimate surfaces and equipment may be contaminated by nosocomial pathogens, including multi-drug-resistant micro-organisms. To assess the degree of environmental contamination close to and distant from patients, and contamination of healthcare workers' (HCWs) hands with nosocomial pathogens under real-life conditions and to investigate potential transmission events. Over the course of three weeks, agar contact samples were taken close to and distant from patient areas and from HCWs' hands in eight ICUs of a tertiary care hospital in Innsbruck, Austria. Each ICU was visited once without announcement. Species identification and antimicrobial susceptibility testing were performed according to standard methods, and corresponding strains from patient, environment and hand samples were genotyped using pulsed-field gel electrophoresis. Among 523 samples, HCWs' hands were most frequently contaminated with potentially pathogenic bacteria (15.2%), followed by areas close to patients (10.9%) and areas distant from patients (9.1%). Gram-positive bacteria were identified most often (67.8%), with Enterococcus spp. being the most prevalent species (70% vancomycin sensitive and 30% vancomycin resistant) followed by Staphylococcus aureus, of which 64% were classified as meticillin-resistant Staphylococcus aureus. Molecular typing documented identical strains among patient, environment and hand isolates. This study found widespread contamination of the ICU environment with clinically relevant pathogens, including multi-drug-resistant micro-organisms, despite cleaning and disinfection. The bioburden might not be restricted to areas close to patients. The role of extended environmental disinfection of areas distant from patients in order to improve infection prevention needs further discussion. Copyright © 2017 The Healthcare Infection Society. Published by Elsevier Ltd. All rights reserved.

  14. 78 FR 23845 - Drawbridge Operation Regulations; Narrow Bay, Smith Point, NY

    Science.gov (United States)

    2013-04-23

    ... Operation Regulations; Narrow Bay, Smith Point, NY AGENCY: Coast Guard, DHS. ACTION: Notice of temporary... deviation from the regulation governing the operation of the Smith Point Bridge, mile 6.1, across Narrow Bay, between Smith Point and Fire Island, New York. The deviation is necessary to facilitate the Smith Point...

  15. The public whole body counting program following the Three Mile Island accident. Technical report, April-September 1979

    International Nuclear Information System (INIS)

    Gotchy, R.L.; Bores, R.J.

    1980-12-01

    In early April, 1979 the U.S. Nuclear Regulatory instituted a program to determine whether any radioactivity released as a result of the March 28, 1979 accident at the Three Mile Island Unit-2 was accumulating in members of the general public living near Unit-2. The program used a device called a whole body counter which has the capability of measuring very small quantities of radioactivity in people. There were 753 men, women and children successfully counted; nine of these people were counted a second time, leading to a total of 762 whole body counts. There was no radioactivity identified in any member of the public which could have originated from the radioactive materials released following the accident. Several people with higher than average levels of naturally occurring radioactivity were identified. The counting systems used are briefly described. Technical problems encountered, results and conclusions are discussed

  16. A human reliability analysis of the Three Mile power plant accident considering the THERP and ATHEANA methodologies

    International Nuclear Information System (INIS)

    Fonseca, Renato Alves da

    2004-03-01

    The main purpose of this work is the study of human reliability using the THERP (Technique for Human Error Prediction) and ATHEANA methods (A Technique for Human Error Analysis), and some tables and also, from case studies presented on the THERP Handbook to develop a qualitative and quantitative study of nuclear power plant accident. This accident occurred in the TMI (Three Mile Island Unit 2) power plant, PWR type plant, on March 28th, 1979. The accident analysis has revealed a series of incorrect actions, which resulted in the Unit 2 shut down and permanent loss of the reactor. This study also aims at enhancing the understanding of the THERP method and ATHEANA, and of its practical applications. In addition, it is possible to understand the influence of plant operational status on human failures and of these on equipment of a system, in this case, a nuclear power plant. (author)

  17. Analysis of modular dynamic formation test results from the Mount Elbert-01 stratigraphic test well, Milne Point unit, North Slope Alaska

    Energy Technology Data Exchange (ETDEWEB)

    Anderson, B.J. [National Energy Technology Laboratory, Morgantown, WV (United States)]|[West Virginia Univ., Morgantown, WV (United States). Dept. of Chemical Engineering; Rose, K.; Boswell, R. [National Energy Technology Laboratory, Morgantown, WV (United States); Wilder, J.W. [Akron Univ., Akron, OH (United States). Dept. of Theoretical and Applied Math; Kurihara, M. [Japan Oil Engineering Co. Ltd., Kachidoki, Chuo-ku, Tokyo (Japan); White, M.D. [Pacific Northwest National Laboratory, Richland, WA (United States). Hydrology Group; Moridis, G.J. [California Univ., Lawrence Berkeley National Laboratory, Berkeley, CA (United States). Earth Sciences Division; Wilson, S.J. [Ryder Scott Co. LP., Denver, CO (United States); Pooladi-Darvish, M. [Fekete Associates Inc., Calgary, AB (Canada); Masuda, Y. [Tokyo Univ., Tokyo (Japan). Dept. of Geosystem Engineering; Collett, T.S. [United States Geological Survey, Denver, CO (United States). Denver Federal Center; Hunter, R.B. [ASRC Energy Services, Anchorage, AK (United States); Narita, H. [National Inst. of Advanced Industrial Science and Technology, Toyohiraku, Sapporo, Hokkaido (Japan). Methane Hydrate Research Laboratory

    2008-07-01

    The National Energy Technology Laboratory (NETL) and the United States Geological Survey (USGS) are leading an international effort to compare methane hydrate reservoir simulators. The purpose of the research is to exchange information regarding gas hydrate dissociation and physical properties enabling improvements in methane hydrate reservoir modeling, to build confidence in all the leading simulators through exchange of ideas and cross-validation of simulator results on common datasets of escalating complexity, and to establish a depository of gas hydrate related experiment/production scenarios with the associated predictions of these established simulators that can be used for ongoing and future comparison purposes. In order to accomplish these objectives, a team of researchers was brought together to construct a series of problems designed to test/compare the performance of the leading gas hydrate simulators. This paper discussed a project that involved history matches of one 12-hour test that included an initial stage of pressure drawdown and response in which pressures were maintained above the level where gas hydrate dissociation would occur; a second stage with 15 min of flow and 97 min buildup that included gas hydrate dissociation and gas production; and a third stage of 116 min of flow and 266 min of buildup. The test also included temperature measurements taken by a device attached to the modular dynamics formation tester's (MDT) intake screen. The paper presented the MDT data, MDT flow test, and history matching setup and results including estimates of initial formation permeability and analyses of the various unique features exhibited by the MDT results. Five different simulators were used to conduct the history matches. Simulations utilized detailed information collected across the reservoir either obtained or determined from geophysical well logs, including thickness, porosity, hydrate saturation, intrinsic permeability, pore water salinity

  18. Critique of source term and environmental measurement at Three Mile Island

    International Nuclear Information System (INIS)

    Hull, A.P.

    1979-01-01

    The most serious malfunction to date at an operating power reactor in the US occurred at Unit 2 of the Three Mile Island Nuclear Power Station (TMI) at 0400 est on March 28, 1979. Subsequently, between 3X and 10 x 10 6 Ci of radiogases (principally 133 Xe) were released to the atmosphere from the plant vent in decreasing concentrations over the next few weeks, accompanied by abut 10 Ci of 131 I. During this period, the plant's typical effluent monitors and field radiation monitoring program were unable to supply prompt and reliable radiological information. In order to provide a sufficient radioanalytical capability for the large number of in-plant and environmental samples (air, water, soil, vegetation and milk) which were obtained, the existing on-site facilities were augmented by mobile laboratories. The laboratory facilities of the Bureau of Radiological Health (BRH-PA) of the Pennsylvania Department of Environmental Conservation were supplemented by a nearby temporary facility for gamma analysis set up by the Department of Energy (DOE). Many environmental samples, principally of milk, were also transported to more remotely established radioanalytical laboratories of state and federal agencies

  19. Metallurgical examination of, and resin transfer from, Three Mile Island prefilter liners

    Energy Technology Data Exchange (ETDEWEB)

    McConnell, Jr, J W; Spaletta, H W

    1984-08-01

    Metallurgical examinations were performed on two EPICOR-II prefilter liners at the Idaho National Engineering Laboratory (INEL) to determine conditions of the liners and identify the minimum expected lifetime of those and other liners stored at INEL. The research work was accomplished by EG and G Idaho, Inc. for the EPICOR-II Research and Disposition Program, which is funded by the US Department of Energy. The EPICOR-II prefilter liners were used to filter radionuclides from contaminated water during cleanup of Three Mile Island Unit 2 (TMI-2). The liners were constructed of carbon steel with a phenolic protective coating and contained organic and inorganic ion-exchange filtration media. Program plans call for interim storage of EPICOR-II prefilters at INEL for up to ten years, before final disposal in high integrity containers at the Hanford, Washington commercial disposal site. This report describes the (a) resin transfer process used to empty liners for examination, (b) removal of metallographic sections from those liners, (c) specimen preparation, and (d) findings from metallographic examination of those specimens. A minimum lifetime for the liners is determined and recommendations are given for storage of wastes from future TMI-2 activities.

  20. Effects of urban sprawl and vehicle miles traveled on traffic fatalities.

    Science.gov (United States)

    Yeo, Jiho; Park, Sungjin; Jang, Kitae

    2015-01-01

    Previous research suggests that urban sprawl increases auto-dependency and that excessive auto use increases the risk of traffic fatalities. This indirect effect of urban sprawl on traffic fatalities is compared to non-vehicle miles traveled (VMT)-related direct effect of sprawl on fatalities. We conducted a path analysis to examine the causal linkages among urban sprawl, VMT, traffic fatalities, income, and fuel cost. The path diagram includes 2 major linkages: the direct relationship between urban sprawl and traffic fatalities and the indirect effect on fatalities through increased VMT in sprawling urban areas. To measure the relative strength of these causal linkages, path coefficients are estimated using data collected nationally from 147 urbanized areas in the United States. Through both direct and indirect paths, urban sprawl is associated with greater numbers of traffic fatalities, but the direct effect of sprawl on fatalities is more influential than the indirect effect. Enhancing traffic safety can be achieved by impeding urban sprawl and encouraging compact development. On the other hand, policy tools reducing VMT may be less effective than anticipated for traffic safety.

  1. The legacy of Three Mile Island: Implications for today's U.S. Department of Energy challenges

    International Nuclear Information System (INIS)

    Coe, R.P.; Conaway, W.T.; Williams, M.S.

    1996-01-01

    Over the course of the 16 year period following the accident at Three Mile Island-Unit-2, much has been learned and volumes have been written regarding the cause and massive cleanup activities of the incident. Because of these Lessons Learned, important changes have been made and the US commercial nuclear industry is safer and more reliable as a result. It is important to recognize that two major sources of information emerged from this event. First and foremost were the important safety issues that required immediate answers and the addition of the modifications to plants that these answers generated. Second and of considerable significance to the US Department of energy (US DOE) in today's post-cold war environment are the frequently hard-won lessons involved with the recovery, clean-up, and defueling of TMI-2 and its unprecedented transition into long-term, monitored storage. While the commercial industry, regulatory authorities, and the public saw an immediate need for instituting the important safety lessons from TMI-2, these new systems, improved training and operating practices have paid off in increased reliability and extended operations. However, there was no such immediate application for the second source of information, that being the application of the deactivation and long-term storage technology learned at TMI-2 to a current condition. The tasks and methods used in the TMI-2 recovery have strong parallels in the present-day DOE cleanup program

  2. Metallurgical examination of, and resin transfer from, Three Mile Island prefilter liners

    International Nuclear Information System (INIS)

    McConnell, J.W. Jr.; Spaletta, H.W.

    1984-08-01

    Metallurgical examinations were performed on two EPICOR-II prefilter liners at the Idaho National Engineering Laboratory (INEL) to determine conditions of the liners and identify the minimum expected lifetime of those and other liners stored at INEL. The research work was accomplished by EG and G Idaho, Inc. for the EPICOR-II Research and Disposition Program, which is funded by the US Department of Energy. The EPICOR-II prefilter liners were used to filter radionuclides from contaminated water during cleanup of Three Mile Island Unit 2 (TMI-2). The liners were constructed of carbon steel with a phenolic protective coating and contained organic and inorganic ion-exchange filtration media. Program plans call for interim storage of EPICOR-II prefilters at INEL for up to ten years, before final disposal in high integrity containers at the Hanford, Washington commercial disposal site. This report describes the (a) resin transfer process used to empty liners for examination, (b) removal of metallographic sections from those liners, (c) specimen preparation, and (d) findings from metallographic examination of those specimens. A minimum lifetime for the liners is determined and recommendations are given for storage of wastes from future TMI-2 activities

  3. Comprehensive Analysis of MILE Gene Expression Data Set Advances Discovery of Leukaemia Type and Subtype Biomarkers.

    Science.gov (United States)

    Labaj, Wojciech; Papiez, Anna; Polanski, Andrzej; Polanska, Joanna

    2017-03-01

    Large collections of data in studies on cancer such as leukaemia provoke the necessity of applying tailored analysis algorithms to ensure supreme information extraction. In this work, a custom-fit pipeline is demonstrated for thorough investigation of the voluminous MILE gene expression data set. Three analyses are accomplished, each for gaining a deeper understanding of the processes underlying leukaemia types and subtypes. First, the main disease groups are tested for differential expression against the healthy control as in a standard case-control study. Here, the basic knowledge on molecular mechanisms is confirmed quantitatively and by literature references. Second, pairwise comparison testing is performed for juxtaposing the main leukaemia types among each other. In this case by means of the Dice coefficient similarity measure the general relations are pointed out. Moreover, lists of candidate main leukaemia group biomarkers are proposed. Finally, with this approach being successful, the third analysis provides insight into all of the studied subtypes, followed by the emergence of four leukaemia subtype biomarkers. In addition, the class enhanced DEG signature obtained on the basis of novel pipeline processing leads to significantly better classification power of multi-class data classifiers. The developed methodology consisting of batch effect adjustment, adaptive noise and feature filtration coupled with adequate statistical testing and biomarker definition proves to be an effective approach towards knowledge discovery in high-throughput molecular biology experiments.

  4. The Sizewell B inquiry and East Anglia: the legacy of Three Mile Island

    International Nuclear Information System (INIS)

    Kemp, R.V.

    1985-01-01

    This paper argues that the great length and cost of the Public Inquiry into the proposed Sizewell-B PWR reactor is due to its investigatory style. This style became necessary because of the complexity of the issues, the difference in resources between the proponents and objectors and because of delays in licensing of the PWR by the Nuclear Installations Inspectorate. The fears about the safety of the PWR type reactors followed the accident at Three Mile Island in 1979, and the Major of Harrisburg was called by the local residents opposed to the siting to give evidence at the Inquiry. The ways in which the Sizewell-B Inquiry has attempted to come to terms with the fears and concerns of local objectors to the project are looked at. The paper considers how these can be properly weighed when the government is committed to nuclear power. The Inquiry is only advisory - the final decision will be taken by the Ministers after Parliamentary debate. The procedures and facilities adopted by the Inquiry are listed and, in particular, the two evening public meetings held in nearby towns to hear the views of local residents outside the formal main hearing are noted. The two main safety aspects of concern were the incidence of leukemia in East Suffolk, and the planning in case of an emergency at Sizewell-B. The experience of the Mayor of Harrisburg was relevant to this point. (U.K.)

  5. Radwaste reduction experience at Oyster Creek and Three Mile Island Nuclear Power Plants

    International Nuclear Information System (INIS)

    Ross, M.

    1993-01-01

    True radwaste minimization at an operating nuclear power plant means straddling the line between ''what is'' and ''what-can-be'' and then regularly moving that line so that dreams become reality. This effort involves keeping track of and maintaining successful programs of the past while searching out and incorporating the best of the upcoming processes, equipment, and contractors. Some of the tactics used for waste minimization have appreciable results and some have small direct results. But even those with small results add to a final total of volume saved. In addition, the approaches with smaller results demonstrate an unmistakable attitude on the part of management that any unnecessary radwaste production is not acceptable. This attitude is understood and assimilated by engineering, operations, and maintenance in such a way that it becomes a matter of pride to reduce radwaste production to quantities below those officially projected. The GPUN plants at Oyster Creek and Three Mile Island Unit-1 limit the quantity of materials allowed onsite under the premise that an item that stays out of contaminated areas cannot become radwaste. For material exiting contaminated zones, the plants have used a combination of preventative avoidance of radwaste generation and careful processing. This includes sorting and screening of materials leaving contaminated areas to reduce the number of items to eventually be treated, preplanning of work efforts to minimize radwaste that must be generated, wood planning, onsite decontamination units, onsite contractor supplied equipment, and offsite radwaste processors in order to minimize the final amount of radwaste to be buried. Sometimes when employing one of these methods, it is necessary to consider not only the waste generated by the process directly but also secondary wastes caused by interactions with other areas of plant operation, such as equipment maintenance

  6. Simulation of ridesourcing using agent-based demand and supply regional models : potential market demand for first-mile transit travel and reduction in vehicle miles traveled in the San Francisco Bay Area.

    Science.gov (United States)

    2016-01-01

    In this study, we use existing modeling tools and data from the San Francisco Bay Area : (California) to understand the potential market demand for a first mile transit access service : and possible reductions in vehicle miles traveled (VMT) (a...

  7. Three Mile Island telephone survey: preliminary report on procedures and findings

    International Nuclear Information System (INIS)

    Flynn, C.B.

    1979-10-01

    This report describes the methodology used in, and the results of, a telephone survey conducted in the vicinity of the Three Mile Island nuclear power plant. The survey is part of a study of the socioeconomic impacts of nuclear power plant construction and operation at Three Mile Island, and eleven other nuclear power plant sites. The survey covers the areas of evacuation behavior, information processing, short-term accident effects, continuing effects of the accident, and respondent's evaluation of TMI and nuclear power in general. Approximately 1500 households in the vicinity of the Three Mile Island nuclear power plant participated in the survey, which was conducted in July and August 1979

  8. La comprensión clásica del suicidio. De Émile Durkheim a nuestros días. // The classic understanding of suicide. From Émile Durkheim to the present day.

    Directory of Open Access Journals (Sweden)

    Andrés Felipe Palacio.

    2010-06-01

    Full Text Available This text is an approach to several ideas stated by the sociologist Émile Durkheim dealing with suicide, especially the question about how his idea of suicidogenic societies and anomic suicide has probably contributed to the psychoanalytical conception of suicide. The objective is to clarify, at the same time, the usefulness of a broad concept like discourse, from a critical point of view of contemporary cognitive sciences, as well as how they define and tackle the issue of suicide in general terms. // El siguiente texto aborda algunas de las ideas expuestas por el sociólogo Émile Durkheim con respecto al suicidio, pero sobre todo, cuál podría ser el aporte que su idea de las sociedades suicidógenas y del suicidio anómico haría a la concepción misma del suicidio para el psicoanálisis. Todo ello con el objetivo de aclarar, de paso, cuál podría ser la utilidad de un concepto amplio como el de discurso, desde una posición crítica de las ciencias cognitivas contemporáneas y su definición y abordaje del fenómeno del suicidio en general.

  9. 78 FR 4879 - Nine Mile Point 3 Nuclear Project, LLC and UniStar Nuclear Operating Services, LLC Combined...

    Science.gov (United States)

    2013-01-23

    ... Analysis Report (FSAR). On December 1, 2009, UniStar Nuclear Energy (UNE), acting on behalf of the COL... Exclusion From Environmental Review With respect to the exemption's impact on the quality of the human... relation to security issues. Therefore, the common defense and security is not impacted by this exemption...

  10. 2016 NOAA NGS Ortho-rectified Mean High Water Color Mosaic of St. Johns River at Mile Point Turn, Florida

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — This data set contains ortho-rectified mosaic tiles, created as a product from the NOAA Integrated Ocean and Coastal Mapping (IOCM) initiative. The source imagery...

  11. Atmospheric Release Advisory capability (ARAC) response to the Three Mile Island accident

    International Nuclear Information System (INIS)

    Dickerson, M.H.; Gudiksen, P.H.

    1979-10-01

    This paper discusses the three general classes of support provided by the Atmospheric Release Advisory Capability (ARAC) and describes the role played by ARAC in support of DOE during the Three Mile Island accident in March and April of 1979

  12. The Economic Benefits of Vehicle Miles Traveled (VMT)-Reducing Placemaking: Synthesizing a New View

    Science.gov (United States)

    2017-11-01

    This paper analyzes evidence on the economic benefits of placemaking efforts that prioritize pedestrian and non-motorized access and that, at times, reduce vehicle miles traveled. The previous literature on the economic impacts of transportation has ...

  13. Lessons of the accident at Three Mile Island nuclear power plant

    International Nuclear Information System (INIS)

    Veksler, L.M.

    1983-01-01

    Measures taken in the USA for improving safety of NPPs after the accident at ''Three Mile Island'' nuclear power plant are considered. Activities, related to elimination of accident consequences are analyzed. Perspectives of resuming the NPP operation are discussed

  14. Radiation mapping helps in the Three Mile Island 2 clean up

    International Nuclear Information System (INIS)

    Nightingale, Brian

    1986-01-01

    Modelling to depict the location and nature of the radiation measurements needed before surveys are undertaken can save personnel exposure and improve the quality of the radiation data itself, as experience at Three Mile Island 2 has shown. (author)

  15. NASA Green Flight Challenge: Conceptual Design Approaches and Technologies to Enable 200 Passenger Miles per Gallon

    Science.gov (United States)

    Wells, Douglas P.

    2011-01-01

    The Green Flight Challenge is one of the National Aeronautics and Space Administration s Centennial Challenges designed to push technology and make passenger aircraft more efficient. Airliners currently average around 50 passenger-miles per gallon and this competition will push teams to greater than 200 passenger-miles per gallon. The aircraft must also fly at least 100 miles per hour for 200 miles. The total prize money for this competition is $1.65 Million. The Green Flight Challenge will be run by the Comparative Aircraft Flight Efficiency (CAFE) Foundation September 25 October 1, 2011 at Charles M. Schulz Sonoma County Airport in California. Thirteen custom aircraft were developed with electric, bio-diesel, and other bio-fuel engines. The aircraft are using various technologies to improve aerodynamic, propulsion, and structural efficiency. This paper will explore the feasibility of the rule set, competitor vehicles, design approaches, and technologies used.

  16. Phosphorus Loading and Compositional Characteristics in Eight-Mile Run Watershed, Wisconsin

    National Research Council Canada - National Science Library

    James, William

    2004-01-01

    The purpose of this research was to describe and quantify biologically labile and refractory phosphorus runoff in Eight-Mile Run, a small watershed in west-central Wisconsin that is impacted by dairy...

  17. National Emissions Inventory Vehicle Miles Traveled, U.S., 2014, EPA/OAR/OAQPS/AQAD

    Data.gov (United States)

    U.S. Environmental Protection Agency — This web service contains layers that depict gridded Vehicle Miles Traveled (VMT) for 2014 from the National Emission Inventory (NEI). The default 2014 National...

  18. Three Mile Island nuclear reactor accident of March 1979. Environmental radiation data: Volume III. A report to the President's Commission on the Accident at Three Mile Island

    International Nuclear Information System (INIS)

    Bretthauer, E.W.; Grossman, R.F.; Thome, D.J.; Smith, A.E.

    1981-03-01

    This report contains a listing of environmental radiation monitoring data collected in the vicinity of Three Mile Island (TMI) following the March 28, 1979 accident. These data were collected by the EPA, NRC, DOE, HHS, the Commonwealth of Pennsylvania, or the Bethlehem Steel Corporation. This volume consists of Table 9 Computer printout of environmental data collected NRC

  19. Emergency preparedness and response in the Commonwealth of Pennsylvania - the Three Mile Island incident

    International Nuclear Information System (INIS)

    Henderson, O.K.

    1981-01-01

    This paper addresses the emergency response mechanism and legal basis in effect in the Commonwealth of Pennsylvania at the time of the Three Mile Island incident. It reviews the sequence of events as they directly affected the Pennsylvania Emergency Management Agency and examines the method used by the Agency to discharge its responsibilities. Finally, the paper lists some of the lessons learned from the Three Mile Island experience. (author)

  20. The Presence of the invasive Lionfish Pterois miles in the Mediterranean Sea

    Directory of Open Access Journals (Sweden)

    M. BARICHE

    2013-06-01

    Full Text Available Here we report the occurrence of Pterois miles in the Mediterranean Sea, based on the capture of two specimens along the coast of Lebanon. Previously, only one record of the species from the Mediterranean Sea had been documented. The new records highlight the arrival of new propagules of P. miles, more than two decades later, hinting to a future potential invasion of the Mediterranean Sea.

  1. The metabolic equivalents of one-mile walking by older adults; implications for health promotion

    Directory of Open Access Journals (Sweden)

    Mandy Lucinda Gault

    2017-09-01

    Full Text Available Background: Instructions for older adults regarding the intensity of walking may not elicit an intensity to infer health gains. We recorded the metabolic equivalents (METs during a 1-mile walk using constant and predicted values of resting MET in older adults to establish walking guidelines for health promotion and participation.Methods: In a cross-sectional design study, participants (15 men, 10 women walked 1-mile over ground, in a wooden floored gymnasium, wearing the Cosmed K4b2 for measurement of energy expenditure. Constant or predicted values for resting MET were used to calculate the number of 1-mile walks to meet 450-750 MET∙min∙wk-1.Results: Participants had MET values higher than 3 for both methods, with 29% and 64% of the participants higher than 6 for a constant and predicted MET value, respectively. The METs of the1-mile walk were (mean ± SD 6 ± 1 and 7 ± 1 METs using constant and predicted resting MET,and similar for men (constant: 6 ± 1 METs; predicted: 7 ± 1 METs and women (constant: 5±1METs; predicted: 6 ± 1 METs (P > 0.05.Conclusion: Older adults that are instructed to walk 1-mile at a fast and constant pace meet the minimum required intensity for physical activity, and public health guidelines. Health professionals, that administer exercise, could encourage older adults to accumulate between six and nine 1-mile walks per week for health gains.

  2. Technical evaluation of the susceptibility of safety-related systems to flooding caused by the failure of non-Category I systems for Turkey Point Nuclear Power Plant, Units 3 and 4

    International Nuclear Information System (INIS)

    Collins, E.K.

    1979-08-01

    Three separate reviews of the Turkey Point Units 3 and 4 were conducted by the FPLCO between 1972 and 1975. Initially, at the request of NBC in 1972, the FPLCO reviewed several water systems as sources of flooding. Subsequently, as a result of an abnormal occurrence, the drainage system was reviewed. Finally, the facilities were again reviewed at NRC's request and both the potential sources of flooding and safety-related equipment which could be damaged by flooding were identified. The sources of flooding and the appropriate safety equipment are discussed. An evaluation is presented of measures that were taken by FPLCO to minimize the danger of flooding and to protect safety-related equipment

  3. Lessons of Three Mile Island for the health care community

    International Nuclear Information System (INIS)

    Wald, N.

    1986-01-01

    The author discusses the key points that we should have learned from the TMI accident. There has to be one responsible decision maker; otherwise conflicting decision increase the stress and anxiety levels. There has to be a realistic appraisal and clear communication of the situation with all of the people involved. Both overoptimistic and overpessimistic views are deleterious in promoting realistic responses from the population at risk. There has to be an action plan on paper that is credible, one which people can believe will work. Adequate time, thought, and resources have to be dedicated to the plan. It is not simply a matter of putting words on paper. Education for radiation emergencies is critically important. All professional (including governors, their staffs, and health care personnel) and the general public must know something about radiation before they are caught in the middle of a crisis

  4. Montgomery Point Lock and Dam, White River, Arkansas

    Science.gov (United States)

    2016-01-01

    the time of this study was James E. Walker, Chief, Navigation Branch, HQUSACE. W. Jeff Lillycrop, CHL, was the ERDC Technical Director for... Fischer , and J. Mewes. 2011. Montgomery Point Lock and Dam HSR model, White River miles 4.0 – 0.0; Hydraulic sediment response model investigation

  5. BIOLOGICAL AND ENVIRONMENTAL RADIATION EXPERIENCE AT INDIAN POINT STATION

    Energy Technology Data Exchange (ETDEWEB)

    Nelson, H. F.

    1963-09-15

    The environs monitoring program at Indian Point Station is presented. Thirty sampling stations within a circle of approximately 10 miles of the station are used for the collection of samples of air, water, vegetation, and soil that are then analyzed for gross beta-gamma activity. Data are tabulated. (P.C.H.)

  6. Evaluating the Least Cost Selection of Agricultural Management Practices in the Five Mile Creek area of Fort Cobb Watershed, Oklahoma, USA

    Science.gov (United States)

    Rasoulzadeh Gharibdousti, S.; Stoecker, A.; Storm, D.

    2017-12-01

    One of the main causes of water quality impairment in the United States is human induced Non-Point Source (NPS) pollution through intensive agriculture. The Fort Cobb Reservoir (FCR) watershed located in west-central Oklahoma, United States is a rural agricultural catchment with known issues of NPS pollution including suspended solids, siltation, nutrients, and pesticides. Recently, several Best Management Practices (BMPs) have been implemented in the watershed (such as no-tillage and cropland to grassland conversion) to improve water quality. The objective in this study is to estimate the most cost effective selection and placement of BMPs on farmlands to mitigate soil erosion and the delivery of sediment and nutrient loads to the FCR from Five Mile Creek (FMC) area of the FCR watershed. We employed the Soil and Water Assessment Tool (SWAT) to develop the hydrological model of the study area. The watershed was delineated using the 10 m National Elevation Dataset and divided into 43 sub-basins with an average area of 8 km2. Through a combination of Soil Survey Geographic Database- SSURGO soil data, the US Department of Agriculture crop layer and the slope information, the watershed was further divided into 15,217 hydrologic response units (HRUs). The historical climate pattern in the watershed was represented by two different weather stations. The model was calibrated for the 1991 - 2000 period and validated over the 2001 - 2010 period against the monthly USGS observations of streamflow and suspended sediment concentration recorded at the watershed outlet. Model parametrization resulted in satisfactory values for the R2 (0.64, 0.35) and NS (0.61, 0.34) in calibration period and an excellent model performance (R2 = 0.79, 0.38; NS = 0.75, 0.43) in validation period for streamflow and sediment concentration respectively. We have selected 20 BMPs to estimate their efficacy in terms of water, sediment, and crop yields. Linear Programming (LP) was used to determine the

  7. Disposal demonstration of a high integrity container (HIC) containing an EPICOR-II prefilter from Three Mile Island

    International Nuclear Information System (INIS)

    McConnell, J.W. Jr.; Tyacke, M.J.; Schmitt, R.C.; Reno, H.W.

    1985-02-01

    A high integrity container (HIC) was developed, tested, and certified for use in disposing of unusual low-level radioactive waste from Three Mile Island Unit 2 (TMI-2). The work was coordinated by EG and G Idaho, Inc. and funded by the US Department of Energy. A disposal demonstration using an HIC containing an EPICOR-II prefilter from TMI-2 was completed at the commercial disposal facility in the State of Washington. A Certification of Compliance was issued by the Department of Social and Health Services of the State of Washington to use the HIC in disposing of up to 50 EPICOR-II prefilters. That Certification of Compliance was issued after rigorous review of the HIC design and test program by the State and by the US Nuclear Regulatory Commission. This report describes the processes of loading, transporting, and disposing of the demonstration HIC and briefly describes the design, testing, and approval effort leading up to the demonstration

  8. TMI-2 [Three Mile Island Nuclear Power Station] fuel canister and core sample handling equipment used in INEL hot cells

    International Nuclear Information System (INIS)

    McConnell, J.W. Jr.; Shurtliff, W.T.; Lynch, R.J.; Croft, K.M.; Whitmill, L.J.; Allen, S.M.

    1987-01-01

    This paper describes the specialized remote handling equipment developed and used at the Idaho National Engineering Laboratory (INEL) to handle samples obtained from the core of the damaged Unit 2 reactor at Three Mile Island Nuclear Power Station (TM-2). Samples of the core were removed, placed in TMI-2 fuel canisters, and transported to the INEL. Those samples will be examined as part of the analysis of the TMI-2 accident. The equipment described herein was designed for removing sample materials from the fuel canisters, assisting with initial examination, and processing samples in preparation for detailed examinations. The more complex equipment used microprocessor remote controls with electric motor drives providing the required force and motion capabilities. The remaining components were unpowered and manipulator assisted

  9. Aerial radiological survey of the Three Mile Island Nuclear Station and surrounding area, Middletown, Pennsylvania

    International Nuclear Information System (INIS)

    Colton, D.P.

    1983-08-01

    An aerial radiological survey was performed over the area surrounding the Three Mile Island Nuclear Station during October 26 to 30, 1982. The survey covered an 82-square-kilometer area centered on the nuclear plant and encompassed the communities of Middletown, York Haven, Goldsboro and Royalton, Pennsylvania. The highest radiation exposure rates, up to a maximum of 200 microroentgens per hour (μR/h), were inferred from data measured directly over the TMI facilities. This detected radiation was due to the presence of cobalt-58, cobalt-60 and cesium-137, which was consistent with normal plant operations. Similar activity is routinely observed in aerial surveys over nuclear power plants which have been or are presently in an operational mode. For the remainder of the survey area, the inferred radiation exposure rates varied from 6 to 14 μR/h. The reported exposure rate values include an estimated cosmic ray contribution of 3.7 μR/h. Ground-based measurements, conducted during the time of the aerial survey, were compared to the aerial results. Pressurized ionization chamber readings and a group of soil samples were acquired at several locations within the survey area, along the river banks upstream and downstream of the survey area, and at the ground-based locations used for a previous aerial survey which was conducted in 1976. The exposure rate values obtained from these measurements were in agreement with the corresponding aerial data. With the exception of the activity observed within the TMI facilities, no evidence of any contamination which might have occurred as a result of past reactor operations or the 1979 TMI Unit 2 accident was detected from the aerial survey data. This was further supported by the results of the soil sample analyses and the comparison with the 1976 aerial survey data. 7 references, 12 figures, 4 tables

  10. Predictors of temporal patterns of psychiatric distress during 10 years following the nuclear accident at Three Mile Island.

    Science.gov (United States)

    Dew, M A; Bromet, E J

    1993-04-01

    The present study examines psychiatric symptom levels during a 10-year period in a community sample of mothers of young children. All were identified in the early aftermath of the 1979 Three Mile Island nuclear accident, and followed through the accident's 1989 anniversary. Cluster analysis was used to identify long-term distress profiles during the study period; women's temporal profiles were found to be either (a) stable and at low, clinically nonsignificant levels of distress across all measurement points or (b) at consistently elevated, clinically significant levels that varied with the timing of postaccident events such as the restart of the undamaged reactor and the 10th anniversary. Subsequent multivariate analyses indicated that preaccident characteristics, as well as parameters reflecting respondents' initial involvement with, and reactions to the accident, were important for distinguishing between women within the two temporal profile groups. Implications of the results for both policy formulation and continued research on significant environmental stressors is discussed.

  11. Heilbronn problem for five points

    International Nuclear Information System (INIS)

    Yang Lu; Zhang Jingzhong; Zeng Zhenbing

    1991-08-01

    Put 5 points in a unit square, then there must be at least one triangle, formed by three of these points, with an area not greater than √3/9. And the upper bound √3/9 is the best. Unexpectedly, this disproves an old conjecture posed twenty years ago. (author). 15 refs, 19 figs

  12. The Philosophy of Turning Points

    DEFF Research Database (Denmark)

    Turcan, Romeo V.

    2013-01-01

    business and management field, the turning point is seen as a valuable unit of analysis within the research field. It is expected that this paper will encourage a dynamic scholarly conversation about the concept of turning point and how it can aid international business researchers in the development...

  13. Three Mile Island nuclear reactor accident of March 1979. Environmental radiation data: Update. A report to the President's Commission on the Accident at Three Mile Island

    International Nuclear Information System (INIS)

    Bretthauer, E.W.; Grossman, R.F.; Thome, D.J.; Smith, A.E.

    1981-03-01

    This report contains a listing of environmental radiation monitoring data collected in the vicinity of Three Mile Island (TMI) following the March 28, 1979 accident. These data were collected by the EPA, NRC, DOE, HHS, the Commonwealth of Pennsylvania, or the Bethlehem Steel Corporation. The original report was printed in September 1979 and the update was released in December 1979. Also included in this update is a listing of whole-body counting data obtained by the NRC to assess the quantity of internally deposited radionuclides in TMI workers and volunteer residents within a three-mile-radius of TMI. No reactor-related radionuclides were identified in any of the whole-body counting data

  14. Three Mile Island nuclear reactor accident of March 1979. Environmental radiation data: Volume I. A report to the President's Commission on the Accident at Three Mile Island

    International Nuclear Information System (INIS)

    Bretthauer, E.W.; Grossman, R.F.; Thome, D.J.; Smith, A.E.

    1981-03-01

    This report contains a listing of environmental radiation monitoring data collected in the vicinity of Three Mile Island (TMI) following the March 28, 1979 accident. These data were collected by the EPA, NRC, DOE, HHS, the Commonwealth of Pennsylvania, or the Bethlehem Steel Corporation. The original report was printed in September 1979 and the update was released in December 1979. Volume 1 consists of the following 5 tables: Table 1-Measurements made by principal participants; Table 2-Cross-check program instituted by US Environmental Protection Agency (EPA) for iodine-131 in milk. Table 3-Comparison of EPA and US Nuclear Regulatory Commission (NRC) air data collected at the Three Mile Island (TMI) Observation Center; Table 4-Summary of EPA Environmental Monitoring Systems Laboratory-Las Vegas (EMSL-LV) and EPA Eastern Environmental Radiation Facility-Montgomery (EERF-Montgomery) sampling and analytical procedures; Table 5-Computer printout of environmental data collected by EPA

  15. Three Mile Island nuclear reactor accident of March 1979. Environmental radiation data: Volume V. A report to the President's Commission on the Accident at Three Mile Island

    International Nuclear Information System (INIS)

    Bretthauer, E.W.; Grossman, R.F.; Thome, D.J.; Smith, A.E.

    1981-03-01

    This report contains a listing of environmental radiation monitoring data collected in the vicinity of Three Mile Island (TMI) following the March 28, 1979 accident. These data were collected by the EPA, NRC, DOE, HHS, the Commonwealth of Pennsylvania, or the Bethlehem Steel Corporation. This volume consists of the following 2 volumes: Table 16 Summary of Metropolitan Edison Company (Met-Ed) sampling and analytical procedures; and Table 17 Computer printout of data collected by Met-Ed

  16. Incidence of thyroid cancer in residents surrounding the Three Mile Island nuclear facility.

    Science.gov (United States)

    Levin, Roger J

    2008-04-01

    On March 28, 1979, the worst nuclear exposure incident in U.S. history occurred near Harrisburg, PA. Small quantities of xenon and iodine radioisotopes were released into the environment from the Three Mile Island (TMI) nuclear power plant. The Pennsylvania Department of Health (PDoH) implemented a TMI Population Registry, including 32,135 individuals within a 5-mile radius of TMI, to track possible health effects to the local population. Although no increase in cancer mortality has been noted in this cohort, cancer incidence has not been tracked. Given the long latency period for the development of thyroid cancer after exposure to low-level radiation exposure, it is plausible that an increase in thyroid cancer incidence might just now be occurring. Retrospective analysis of the Pennsylvania Cancer Registry Dataset for Thyroid Cancer using the Epidemiological Query and Mapping System (EpiQMS) search engine. EpiQMS is an interactive health statistics Website that can produce numbers, rates, graphs, charts, maps, and county profiles using various demographic variables (age, sex, race, etc.) from birth, death, cancer, and population datasets for the state and counties or regions of Pennsylvania. Eighteen years of data (1985-2002) on thyroid cancer incidence were obtained from the PDoH. The three at-risk counties of Dauphin, York, and Lancaster were analyzed with regard to observed numbers of thyroid cancer cases versus expected incidence. Although the nuclear accident at TMI occurred in 1979, 1985 was chosen as the starting point for data analysis because that is when the PDoH began maintaining cancer incidence records. In the first year available for evaluation (1985), there were 11 new thyroid cancer cases in each of the at-risk counties (Dauphin, York, Lancaster). By 2002, the incidence had increased to 29 in Dauphin County, 81 in Lancaster County, and 69 in York County. The increase in thyroid cancer in Dauphin County is not above what would be expected for both

  17. The impact of a tobacco point-of-sale display ban on youth in the United Kingdom: findings from a repeat cross-sectional survey pre-, mid- and post-implementation

    Directory of Open Access Journals (Sweden)

    Allison Ford

    2018-03-01

    Full Text Available Background The display of tobacco products at the point-of-sale (POS allows tobacco companies to showcase their products and communicate with consumers. Evidence suggests that exposure to POS tobacco displays is associated with impulse tobacco purchasing among adult smokers and smoking susceptibility among never smoking youth. In the United Kingdom (UK a ban on the open display of tobacco products was phased in between 2012 and 2015. Three waves of the Youth Tobacco Policy Survey were used to examine the impact of the ban on youth pre-, mid- and post-implementation. Methods A repeat cross-sectional survey was conducted with 11-16 year olds across the UK. Data was collected via an in-home face-to-face interview and self-completion questionnaire at three time points: pre- (2011, n=1373, mid- (2014, n=1205, and post-display ban (2016, n=1213. We examined whether the salience of displays was associated with smoking susceptibility among never smokers. Measures also explored cigarette brand awareness, attractiveness of displays and support for a display ban. Results In 2011, pre-ban, susceptibility to smoke was positively associated with noticing cigarettes displayed at POS and higher brand awareness. Susceptibility to smoke decreased from 28% in 2011 (pre-ban to 18% in 2016 (post-ban, with the mean number of brands recalled falling from 1.56 (SD=1.88 in 2011 to 1.01 (SD=1.42 in 2016. With respect to support for the ban, in 2016 the vast majority of our sample (87% indicated that shops should have to keep cigarettes behind closed shutters. They also felt that having them behind closed shutters made them seem unappealing (73% and made them think that it's not ok to smoke (83%. Conclusions That smoking susceptibility was lower following the ban suggests that placing tobacco out of sight helps safeguard young people and justifies this policy approach in the UK and elsewhere.

  18. 137Cs levels in deer following the Three Mile Island accident.

    Science.gov (United States)

    Field, R W

    1993-06-01

    White-tailed deer (Odocoileus virgianus) tongues were assayed to assess whether or not significant widespread 137Cs contamination occurred in the vicinity of Three Mile Island Nuclear Station as a result of the 1979 accident. White-tailed deer tongues harvested from 10 Pennsylvania counties more than 88 km away from Three Mile Island had significantly higher 137Cs levels than deer tongues harvested from counties surrounding the nuclear plant. The mean deer tongue 137Cs levels found in Pennsylvania white-tailed deer were lower than 137Cs levels found in deer from other parts of the U.S. sampled shortly after culmination of major atmospheric nuclear testing. These findings support the conclusions of previous studies suggesting that only minimal quantities of 137Cs escaped from the damaged Three Mile Island plant after the accident.

  19. Walter Miles, Pop Warner, B. C. Graves, and the psychology of football.

    Science.gov (United States)

    Baugh, Frank G; Benjamin, Ludy T

    2006-01-01

    In 1926-1927, a graduate student, B. C. Graves, working with Stanford University psychologist Walter Miles and legendary football coach Pop Warner, conducted an investigation of variations in signal calling as they affected the charging times of football players. The study was one of two that involved Miles and the ingenious multiple chronograph that he had invented to time the reactions of seven players simultaneously. These studies represented a brief digression in the career of Miles, who certainly was no sport psychologist. They tell of an interesting collaboration between scientist and coaches that produced one of the richest studies in sport psychology in the first half of the twentieth century. Copyright 2006 Wiley Periodicals, Inc.

  20. Post-accident cleanup of radioactivity at the Three Mile Island Nuclear Power Station

    International Nuclear Information System (INIS)

    Brooksbank, R.E.; Armento, W.J.

    1980-02-01

    The technical staff of the President's Commission on the Accident at Three Mile Island (TMI) requested that Oak Ridge National Laboratory (ORNL) prepare documentation concerned with the cleanup of radioactivity on the Three Mile Island site following the March 28, 1979 accident. The objective of this report is to provide information in a summarized form, which will be of direct usefulness to the commissioners. The information contained herein includes discussion of on-site assistance and accomplishments following the accident, flowsheet development for the TMI recovery team (by the Technical Advisory Group), and the numerous reports already generated on the TMI cleanup and recovery

  1. Note on the stock market's reaction to the accident at Three Mile Island

    International Nuclear Information System (INIS)

    Spudeck, R.E.; Moyer, C.R.

    1989-01-01

    This note provides new information regarding the market reaction toward electric utility stocks that resulted both from the accident at Three Mile Island, and the events predating and postdating the accident. The results suggest that some of the market reaction heretofore ascribed to the accident resulted instead from regulatory activity occurring before the accident. We also provide results suggesting that regulatory activity by the Pennsylvania Public Utilities Commission in the wake of the accident served to offset a majority of the increased systematic risk resulting from the accident. Our results imply that previously reported lingering effects of the accident at Three Mile Island may be regulatory effects from events predating the accident

  2. Variation in the annual unsatisfactory rates of selected pathogens and indicators in ready-to-eat food sampled from the point of sale or service in Wales, United Kingdom.

    Science.gov (United States)

    Meldrum, R J; Garside, J; Mannion, P; Charles, D; Ellis, P

    2012-12-01

    The Welsh Food Microbiological Forum "shopping basket" survey is a long running, structured surveillance program examining ready-to-eat food randomly sampled from the point of sale or service in Wales, United Kingdom. The annual unsatisfactory rates for selected indicators and pathogens for 1998 through 2008 were examined. All the annual unsatisfactory rates for the selected pathogens were <0.5%, and no pattern with the annual rate was observed. There was also no discernible trend observed for the annual rates of Listeria spp. (not moncytogenes), with all rates <0.5%. However, there was a trend observed for Esherichia coli, with a decrease in rate between 1998 and 2003, rapid in the first few years, and then a gradual increase in rate up to 2008. It was concluded that there was no discernible pattern to the annual unsatisfactory rates for Listeria spp. (not monocytogenes), L. monocytogenes, Staphylococcus aureus, and Bacillus cereus, but that a definite trend had been observed for E. coli.

  3. DALI: Defining Antibiotic Levels in Intensive care unit patients: a multi-centre point of prevalence study to determine whether contemporary antibiotic dosing for critically ill patients is therapeutic.

    Science.gov (United States)

    Roberts, Jason A; De Waele, Jan J; Dimopoulos, George; Koulenti, Despoina; Martin, Claude; Montravers, Philippe; Rello, Jordi; Rhodes, Andrew; Starr, Therese; Wallis, Steven C; Lipman, Jeffrey

    2012-07-06

    The clinical effects of varying pharmacokinetic exposures of antibiotics (antibacterials and antifungals) on outcome in infected critically ill patients are poorly described. A large-scale multi-centre study (DALI Study) is currently underway describing the clinical outcomes of patients achieving pre-defined antibiotic exposures. This report describes the protocol. DALI will recruit over 500 patients administered a wide range of either beta-lactam or glycopeptide antibiotics or triazole or echinocandin antifungals in a pharmacokinetic point-prevalence study. It is anticipated that over 60 European intensive care units (ICUs) will participate. The primary aim will be to determine whether contemporary antibiotic dosing for critically ill patients achieves plasma concentrations associated with maximal activity. Secondary aims will compare antibiotic pharmacokinetic exposures with patient outcome and will describe the population pharmacokinetics of the antibiotics included. Various subgroup analyses will be conducted to determine patient groups that may be at risk of very low or very high concentrations of antibiotics. The DALI study should inform clinicians of the potential clinical advantages of achieving certain antibiotic pharmacokinetic exposures in infected critically ill patients.

  4. DALI: Defining Antibiotic Levels in Intensive care unit patients: a multi-centre point of prevalence study to determine whether contemporary antibiotic dosing for critically ill patients is therapeutic

    Directory of Open Access Journals (Sweden)

    Roberts Jason A

    2012-07-01

    Full Text Available Abstract Background The clinical effects of varying pharmacokinetic exposures of antibiotics (antibacterials and antifungals on outcome in infected critically ill patients are poorly described. A large-scale multi-centre study (DALI Study is currently underway describing the clinical outcomes of patients achieving pre-defined antibiotic exposures. This report describes the protocol. Methods DALI will recruit over 500 patients administered a wide range of either beta-lactam or glycopeptide antibiotics or triazole or echinocandin antifungals in a pharmacokinetic point-prevalence study. It is anticipated that over 60 European intensive care units (ICUs will participate. The primary aim will be to determine whether contemporary antibiotic dosing for critically ill patients achieves plasma concentrations associated with maximal activity. Secondary aims will compare antibiotic pharmacokinetic exposures with patient outcome and will describe the population pharmacokinetics of the antibiotics included. Various subgroup analyses will be conducted to determine patient groups that may be at risk of very low or very high concentrations of antibiotics. Discussion The DALI study should inform clinicians of the potential clinical advantages of achieving certain antibiotic pharmacokinetic exposures in infected critically ill patients.

  5. A reevaluation of cancer incidence near the Three Mile Island nuclear plant: the collision of evidence and assumptions.

    Science.gov (United States)

    Wing, S; Richardson, D; Armstrong, D; Crawford-Brown, D

    1997-01-01

    Previous studies concluded that there was no evidence that the 1979 nuclear accident at Three Mile Island (TMI) affected cancer incidence in the surrounding area; however, there were logical and methodological problems in earlier reports that led us to reconsider data previously collected. A 10-mile area around TMI was divided into 69 study tracts, which were assigned radiation dose estimates based on radiation reading and models of atmospheric dispersion. Incident cancers from 1975 to 1985 were ascertained from hospital records and assigned to study tracts. Associations between accident doses and incidence rates of leukemia, lung cancer, and all cancer were assessed using relative dose estimates calculated by the earlier investigators. Adjustments were made for age, sex, socioeconomic characteristics, and preaccident variation in incidence. Considering a 2-year latency, the estimated percent increase per dose unit +/- standard error was 0.020 +/- 0.012 for all cancer, 0.082 +/- 0.032 for lung cancer, and 0.116 +/- 0.067 for leukemia. Adjustment for socioeconomic variables increased the estimates to 0.034 +/- 0.013, 0.103 +/- 0.035, and 0.139 +/- 0.073 for all cancer, lung cancer, and leukemia, respectively. Associations were generally larger considering a 5-year latency, but were based on smaller numbers of cases. Results support the hypothesis that radiation doses are related to increased cancer incidence around TMI. The analysis avoids medical detection bias, but suffers from inaccurate dose classification; therefore, results may underestimate the magnitude of the association between radiation and cancer incidence. These associations would not be expected, based on previous estimates of near-background levels of radiation exposure following the accident.

  6. A reevaluation of cancer incidence near the Three Mile Island nuclear plant: The collision of evidence and assumptions

    International Nuclear Information System (INIS)

    Wing, S.; Richardson, D.; Armstrong, D.; Crawford-Brown, D.

    1997-01-01

    Previous studies concluded that there was no evidence that the 1979 nuclear accident at Three Mile Island (TMI) affected cancer incidence in the surrounding area; however, there were logical and methodological problems in earlier reports that led us to reconsider data previously collected. A 10-mile area around TMI was divided into 69 study tracts, which were assigned radiation dose estimates based on radiation readings and models of atmospheric dispersion. Incident cancers from 1975 to 1985 were ascertained from hospital records and assigned to study tracts. Associations between accident doses and incidence rates of leukemia, lung cancer, and all cancer were assessed using relative dose estimates calculated by the earlier investigators. Adjustments were made for age, sex, socioeconomic characteristics, and preaccident variation in incidence. Considering a 2-year latency, the estimated percent increase per dose unit ± standard error was 0.020 ± 0.012 for all cancer, 0.082 ± 0.032 for lung cancer, and 0.116 ± 0.067 for leukemia. Adjustment for socioeconomic variables increased the estimates to 0.034 ± 0.013, 0.103 ± 0.035, and 0.139 ± 0.073 for all cancer, lung cancer, and leukemia, respectively. Associations were generally larger considering a 5-year latency, but were based on smaller numbers of cases. Results support the hypothesis that radiation doses are related to increased cancer incidence around TMI. The analysis avoids medical detection bias, but suffers from inaccurate dose classification; therefore, results may underestimate the magnitude of the association between radiation and cancer incidence. These associations would not be expected, based on previous estimates of near-background levels of radiation exposure following the accident. 35 refs., 3 tabs

  7. 76 FR 13209 - United States and State of Texas v. United Regional Health Care System; Proposed Final Judgment...

    Science.gov (United States)

    2011-03-10

    ... of Texas v. United Regional Health Care System, Civil Action No. 7:11-cv- 00030-O. On February 25..., ambulatory surgery center or radiology center in [a] 15 mile radius of United Regional Health Care System... 95% of billed charges for all inpatient and outpatient services at United Regional Health Care System...

  8. Methodology for Calculating Cost-per-Mile for Current and Future Vehicle Powertrain Technologies, with Projections to 2024: Preprint

    Energy Technology Data Exchange (ETDEWEB)

    Ruth, M.; Timbario, T. A.; Timbario, T. J.; Laffen, M.

    2011-01-01

    Currently, several cost-per-mile calculators exist that can provide estimates of acquisition and operating costs for consumers and fleets. However, these calculators are limited in their ability to determine the difference in cost per mile for consumer versus fleet ownership, to calculate the costs beyond one ownership period, to show the sensitivity of the cost per mile to the annual vehicle miles traveled (VMT), and to estimate future increases in operating and ownership costs. Oftentimes, these tools apply a constant percentage increase over the time period of vehicle operation, or in some cases, no increase in direct costs at all over time. A more accurate cost-per-mile calculator has been developed that allows the user to analyze these costs for both consumers and fleets. The calculator was developed to allow simultaneous comparisons of conventional light-duty internal combustion engine (ICE) vehicles, mild and full hybrid electric vehicles (HEVs), and fuel cell vehicles (FCVs). This paper is a summary of the development by the authors of a more accurate cost-per-mile calculator that allows the user to analyze vehicle acquisition and operating costs for both consumer and fleets. Cost-per-mile results are reported for consumer-operated vehicles travelling 15,000 miles per year and for fleets travelling 25,000 miles per year.

  9. Consumer Airfare Report: Table 5 - Detailed Fare Information For Highest and Lowest Fare Markets Under 750 Miles

    Data.gov (United States)

    Department of Transportation — Provides detailed fare information for highest and lowest fare markets under 750 miles. For a more complete explanation, please read the introductory information at...

  10. 76 FR 35104 - Safety Zone; Waterway Closure, Atchafalaya River From Mile Marker 117 (Morgan City Railroad...

    Science.gov (United States)

    2011-06-16

    ...-AA00 Safety Zone; Waterway Closure, Atchafalaya River From Mile Marker 117 (Morgan City Railroad Bridge... with rising flood water in the Atchafalaya River. Basis and Purpose Captain of the Port Morgan City... safety zone is located on the specified waters of the Atchafalaya River between MM 117 (Morgan City...

  11. 77 FR 28255 - Safety Zone; Upper Mississippi River, Mile 183.0 to 183.5

    Science.gov (United States)

    2012-05-14

    ... on the Upper Mississippi River. Discussion of Rule The Coast Guard is establishing a temporary safety...-AA00 Safety Zone; Upper Mississippi River, Mile 183.0 to 183.5 AGENCY: Coast Guard, DHS. ACTION: Temporary final rule. SUMMARY: The Coast Guard is establishing a temporary safety zone for all waters of the...

  12. Emotional, Behavioral, and Physiological Effects of Chronic Stress at Three Mile Island.

    Science.gov (United States)

    Baum, Andrew; And Others

    1983-01-01

    Evaluated the psychophysiological impact of Three Mile Island on nearby residents (N=38) compared to people living near an undamaged nuclear plant (N=32), a coal-fired plant (N=24) and a control group. Results indicated that residents of the TMI area exhibited more symptoms of stress a year after the accident. (WAS)

  13. Blueprint for Breakdown: Three Mile Island and the Media before the Accident.

    Science.gov (United States)

    Friedman, Sharon M.

    1981-01-01

    Discusses media coverage of the Three Mile Island nuclear power plant before and during the disaster. Concludes that there was a communication breakdown prior to the accident. Outlines the causes and offers suggestions for avoiding similar breakdowns in the future. (JMF)

  14. A Content Analysis of News Media Coverage of the Accident at Three Mile Island.

    Science.gov (United States)

    Stephens, Mitchell; Edison, Nadyne G.

    A study was conducted for the President's Commission on the Accident at Three Mile Island to analyze coverage of the accident by ten news organizations: two wire services, three commercial television networks, and five daily newspapers. Copies of all stories and transcripts of news programs during the first week of the accident were examined from…

  15. Planning for large-scale accidents: learning from the Three Mile Island accident

    International Nuclear Information System (INIS)

    Fischer, D.W.

    1981-01-01

    Decision-making issues raised at the Three Mile Island nuclear accident in Pennsylvania are explored. The organizations involved, their interconnections, and decisions are described. The underlying issues bearing on allocation of effort to pre-accident planning and actual accident responses are also noted. Finally, a framework from this effort is used for guiding the planning of operations for future accidents. (author)

  16. Three Mile Island: a report to the commissioners and to the public. Volume II, Part 3

    International Nuclear Information System (INIS)

    1979-01-01

    This is the third and final part of the second volume of a study of the Three Mile Island accident. Part 3 of Volume II contains descriptions and assessments of responses to the accident by the utility and by the NRC and other government agencies

  17. Selection, training, qualification and licensing of Three Mile Island reactor operating personnel

    International Nuclear Information System (INIS)

    Eytchison, R.M.

    1980-01-01

    The various programs which were intended to staff Three Mile Island with competent, trained operators and supervisors are reviewed. The analysis includes a review of the regulations concerning operator training and licensing, and describes how the requirements were implemented by the NRC, Metropolitan Edison Company, and Babcock and Wilcox Company. Finally the programs conducted by these three organisations are evaluated. (U.K.)

  18. Use of photographic film to estimate exposure near the Three Mile Island Nuclear Power Station

    International Nuclear Information System (INIS)

    Shuping, R.E.

    1981-02-01

    This report documents the methodology and results of a Bureau of Radiological Health study of the use of photographic film samples for estimating exposure levels near the Three Mile Island nuclear power station. The study was conducted to provide an independent assessment of the radiation levels near TMI following the accident on March 28, 1979

  19. Atmospheric Release Advisory Capability (ARAC) response to the Three Mile Island accident

    International Nuclear Information System (INIS)

    Dickerson, M.H.; Gudiksen, P.H.

    1980-01-01

    A discussion is presented of the three general classes of support provided by the Atmospheric Release Advisory Capability (ARAC) and describes the role played by ARAC in support of DOE during the Three Mile Island accident in March and April of 1979. 6 refs

  20. The Three Mile Island accident, a world premiere for nuclear energy

    International Nuclear Information System (INIS)

    Bouvier, Yves

    2015-01-01

    When it happened on 28 March 1979, the accident at the Three Mile Island nuclear power station in Pennsylvania took experts and operators by surprise. Although human losses were minor, this world shaking media event significantly changed public attitudes towards nuclear energy and put a definitive stop to the development of nuclear power in the USA. (author)