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Sample records for catawba nuclear station

  1. Catawba nuclear station preoperational ALARA review

    International Nuclear Information System (INIS)

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1989-04-01

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

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

    International Nuclear Information System (INIS)

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

  4. Liquid radwaste process optimization at Catawba Nuclear Station

    International Nuclear Information System (INIS)

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

  5. Seismic margin assessment of the Catawba Nuclear Station: Volume 1, Main report: Final report

    Energy Technology Data Exchange (ETDEWEB)

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

    1989-04-01

    The Electric Power Research Institute (EPRI) has sponsored a two part program for evaluation of nuclear power plant seismic margin. The two parts consist of criteria development and criteria application. Criteria development is documented by EPRI. This report documents the application of the Seismic Margin Assessment (SMA) criteria to the Catawba Unit 2 Nuclear Station. Catawba is owned and operated by the Duke Power Company. It is a two unit, 1145 MW Westinghouse pressurized water reactor. The two units are housed in ice condenser containments and are located on Lake Wylie in South Carolina about 20 miles SW of Charlotte, NC. This study was specifically conducted for Unit 2 but is believed to be almost totally applicable to Unit 1. Unit 2 was first operational in September 1986. 55 refs., 76 figs., 31 tabs.

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

    International Nuclear Information System (INIS)

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

  7. Post-accident streaming analysis for the reactor building electrical penetrations at McGuire and Catawba Nuclear Stations

    International Nuclear Information System (INIS)

    Following an accident, radiation can stream through the electrical penetrations in the Reactor Building wall at Duke Power Company's McGuire and Catawba Nuclear Stations. These penetrations are fairly large and are sealed with materials that provide minimal shielding. Sensitive safety-related pieces of electrical equipment are located in the adjacent room. A very short turnaround time precluded the use of Monte Carlo techniques. Also, due to the high concentration of penetrations, computer costs would have become exorbitant with Monte Carlo. For these reasons, the point kernel code KAP-VI was used for the analysis. Note that no industry standard guidance was found for penetration streaming analysis

  8. Full-scale test of ethanolamine at Catawba Nuclear Station Units 1 and 2

    International Nuclear Information System (INIS)

    This document reports on the full scale test at Catawba Unit 1 and 2, that was performed to determine the effects of ethanolamine as a pH additive to the secondary side of pressurized water reactors. Ethanolamine was injected into the feedwater at both units at Catawba to control the pH in the secondary system. Cation conductance, specific conductance, pH, soluble and insoluble metals, and anions and cations were measured throughout the test. The purpose of this work was to measure the performance of ethanolamine compared to morpholine

  9. Application of risk-informed decision making to the steam generator overfill design basis for the Catawba Nuclear Station (PSAM 5)

    International Nuclear Information System (INIS)

    Preventing steam generator overfill following a steam generator tube rupture (SGTR) is part of the design basis for the Catawba Nuclear Station. A small number of single failures have been identified that are more limiting, with respect to steam generator overfill, than the single failure assumed in the design basis SGTR evaluation. The purpose of this work is to assess the risk significance of these failures and evaluate the appropriateness of excluding these failures from the design basis. The risk significance of these single failures is judged by the contributions to core damage frequency (CDF) and large early release frequency (LERF) associated with their occurrence in conjunction with an SGTR event. The resulting CDF and LERF constituents are estimated to be less than lE09/RY for each single failure. It is concluded that the single failures considered in this analysis are appropriate for exclusion from the design basis for the Catawba Nuclear Station. (author)

  10. Safety evaluation report related to the operation of Catawba Nuclear Station, Units 1 and 2 (Docket Nos. 50-413 and 50-414)

    International Nuclear Information System (INIS)

    This report supplements the Safety Evaluation Report (NUREG-0954) issued in February 1983 by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission with respect to the application filed by Duke Power Company, North Carolina Municipal Power Agency Number 1, North Carolina Membership Corporation, and Saluda River Electric Cooperative, Inc., as applicants and owners, for licenses to operate the Catawba Nuclear Station, Units 1 and 2 (Docket Nos. 50-413 and 50-414, respectively). The facility is located in York County, South Carolina, approximately 9.6 km (6 mi) north of Rock Hill and adjacent to Lake Wylie. This supplement provides additional information supporting the license for initial criticality and power ascension to full-power opertion for Unit 1

  11. Safety evaluation report related to the operation of Catawba Nuclear Station, Units 1 and 2 (Docket Nos. 50-413 and 50-414)

    International Nuclear Information System (INIS)

    The report supplements the Safety Evaluation Report (NUREG-0954) issued in February 1983 by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission with respect to the application filed by Duke Power Company, North Carolina Municipal Power Agency Number 1, North Carolina Membership Corporation, and Saluda River Electric Cooperative, Inc. as applicants and owners, for licenses to operate the Catawba Nuclear Station, Units 1 and 2 (Docket Nos. 50-413 and 50-414, respectively). The facility is located in York County, South Carolina, approximately 9.6 km (6 mi) north of Rock Hill and adjacent to Lake Wylie. This supplement provides additional information supporting the license for fuel loading and precriticality testing for Unit 1

  12. Safety evaluation report related to the operation of Catawba Nuclear Station, Units 1 and 2. Docket Nos. 50-413 and 50-414. Suppl. 1

    International Nuclear Information System (INIS)

    This reort supplements the Safety Evaluation Report (NUREG-0954) issued in February 1983 by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission with respect to the application filed by Duke Power Company, North Carolina Municipal Power Agency Number 1, North Carolina Membership Corporation, and Saluda River Electric Cooperative, Inc. as applicants and owners, for licenses to operate the Catawba Nuclear Station, Units 1 and 2 (Docket Nos. 50-413 and 50-414, respectively). The facility is located in York County, South Carolina, approximately 9.6 km (6 mi) north of Rock Hill and adjacent to Lake Wylie. This supplement provides more recent information regarding resolution or updating of some of the open and confirmatory items and license conditions identified in the Safety Evaluation Report, and discusses the recommendations of the Advisory Committee on Reactor Safeguards in its report dated March 15, 1983

  13. Safety evaluation report related to the operation of Catawba Nuclear Station, Units 1 and 2 (Docket Nos. 50-413 and 50-414). Supplement 2

    International Nuclear Information System (INIS)

    This report supplements the Safety Evaluation Report (NUREG-0954) and Supplement 1 with respect to the application filed by Duke Power Company, North Carolina Municipal Power Agency Number 1, North Carolina Membership Corporation, and Saluda River Electric Cooperative, Inc., as applicants and owners, for licenses to operate the Catawba Nuclear Station, Units 1 and 2 (Docket Nos., 50-413 and 50-414, respectively). The facility is located in York County, South Carolina, approximately 9.6 km (6 mi) north of Rock Hill and adjacent to Lake Wylie. This supplement provides more recent information regarding resolution or updating of some of the open and confirmatory issues and license conditions identified in the Safety Evaluation Report

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

    International Nuclear Information System (INIS)

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

  15. Final environmental statement related to the operation of Catawba Nuclear Station, Units 1 and 2. Docket Nos. 50-413 and 50-414, Duke Power Company, et al

    International Nuclear Information System (INIS)

    This Final Environmental Statement contains the second assessment of the environmental impact associated with the operation of the Catawba Nuclear Station, Units 1 and 2, pursuant to the National Environmental Policy Act of 1969 (NEPA) and 10 CFR 51, as amended, of the NRC regulations. This statement examines: the affected environment, environmental consequences and mitigating actions, and environmental and economic benefits and costs. Land use and terrestrial and aquatic-ecological impacts will be small. Operational impacts to historic and archeological sites will be negligible. The effects of routine operations, energy transmission, and periodic maintenance of rights-of-way and transmission facilities should not jeopardize any populations of endangered or threatened species. No significant impacts are anticipated from normal operational releases of radioactivity. The risk associated with accidental radiation exposure is very low. The net socioeconomic effects of the project will be beneficial

  16. 78 FR 58880 - Safety Zone; Catawba Island Club Wedding Event, Catawba Island Club, Catawba Island, OH

    Science.gov (United States)

    2013-09-25

    ... DHS Department of Homeland Security FR Federal Register NPRM Notice of Proposed Rulemaking TFR... SECURITY Coast Guard 33 CFR Part 165 RIN 1625-AA00 Safety Zone; Catawba Island Club Wedding Event, Catawba Island Club, Catawba Island, OH ACTION: Temporary final rule. SUMMARY: The Coast Guard is...

  17. Nuclear power stations licensing

    International Nuclear Information System (INIS)

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

  18. The nuclear power station

    International Nuclear Information System (INIS)

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

  19. Isotopic Details of the Spent Catawba-1 MOX Fuel Rods at ORNL

    Energy Technology Data Exchange (ETDEWEB)

    Ellis, Ronald James [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2015-04-01

    The United States Department of Energy funded Shaw/AREVA MOX Services LLC to fabricate four MOX Lead Test Assemblies (LTA) from weapons-grade plutonium. A total of four MOX LTAs (including MX03) were irradiated in the Catawba Nuclear Station (Unit 1) Catawba-1 PWR which operated at a total thermal power of 3411 MWt and had a core with 193 total fuel assemblies. The MOX LTAs were irradiated along with Duke Energy s irradiation of eight Westinghouse Next Generation Fuel (NGF) LEU LTAs (ref.1) and the remaining 181 LEU fuel assemblies. The MX03 LTA was irradiated in the Catawba-1 PWR core (refs.2,3) during cycles C-16 and C-17. C-16 began on June 5, 2005, and ended on November 11, 2006, after 499 effective full power days (EFPDs). C-17 started on December 29, 2006, (after a shutdown of 48 days) and continued for 485 EFPDs. The MX03 and three other MOX LTAs (and other fuel assemblies) were discharged at the end of C-17 on May 3, 2008. The design of the MOX LTAs was based on the (Framatome ANP, Inc.) Mark-BW/MOX1 17 17 fuel assembly design (refs. 4,5,6) for use in Westinghouse PWRs, but with MOX fuel rods with three Pu loading ranges: the nominal Pu loadings are 4.94 wt%, 3.30 wt%, and 2.40 wt%, respectively, for high, medium, and low Pu content. The Mark-BW/MOX1 (MOX LTA) fuel assembly design is the same as the Advanced Mark-BW fuel assembly design but with the LEU fuel rods replaced by MOX fuel rods (ref. 5). The fabrication of the fuel pellets and fuel rods for the MOX LTAs was performed at the Cadarache facility in France, with the fabrication of the LTAs performed at the MELOX facility, also in France.

  20. Biblis nuclear power station

    International Nuclear Information System (INIS)

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

  1. Fessenheim nuclear power station

    International Nuclear Information System (INIS)

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

  2. Discharges from nuclear power stations

    International Nuclear Information System (INIS)

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

  3. Islands for nuclear power stations

    International Nuclear Information System (INIS)

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

  4. Checking nuclear power station safety

    International Nuclear Information System (INIS)

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

  5. Balakovo nuclear power station

    International Nuclear Information System (INIS)

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

  6. Safeguarding nuclear power stations

    International Nuclear Information System (INIS)

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

  7. Reviewing nuclear power station achievement

    International Nuclear Information System (INIS)

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

  8. Pumps for nuclear power stations

    International Nuclear Information System (INIS)

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

  9. Construction costs - nuclear power stations

    International Nuclear Information System (INIS)

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

  10. Technical specifications, Catawba Nuclear Station, Unit 1 (Docket No. 50-413). Appendix A to License No. NPF-35

    International Nuclear Information System (INIS)

    Information is presented concerning safety limits for operation of reactor control systems, power distribution, instrumentation, reactor coolant system, emergency core cooling system, containment system, electrical power systems, refueling operations, radioactive effluents, environmental monitoring, reactor site, and administrative aspects

  11. Technical specifications Catawba Nuclear Station, Unit 1 (Docket No. 50-413). Appendix A to License No. NPF-31

    International Nuclear Information System (INIS)

    This appendix includes: definitions, safety limits and limiting safety system settings, limiting conditions for operation and surveillance requirements, bases, design features, and administrative controls

  12. Technical specifications, Catawba Nuclear Station, Unit 1 (Docket No. 50-413). Appendix A to License No. NPF-24

    International Nuclear Information System (INIS)

    This appendix comprises the following: definitions, safety limits and limiting safety system settings, limiting conditions for operation and surveillance requirements, design features, and administrative controls

  13. Insurance of nuclear power stations

    International Nuclear Information System (INIS)

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

  14. Safety Evaluation Report related to the operation of Cartawba Nuclear Station, Units 1 and 2 (Docket Nos. 50-413 and 50-414). Supplement No. 5

    International Nuclear Information System (INIS)

    This report supplements the Safety Evaluation Report (NUREG-0954) issued in February 1983 by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission with respect to the application filed by Duke Power Company, North Carolina Municipal Power Agency Number 1, North Carolina Membership Corporation, Saluda River Electric Cooperative, Inc., and Piedmont Municipal Power Agency, as applicants and owners, for licenses to operate the Catawba Nuclear Station, Units 1 and 2 (Docket Nos. 50-413 and 50-414, respectively). The facility is located in York County, South Carolina, approximately 9.6 km (6 mi) north of Rock Hill and adjacent to Lake Wylie. This supplement provides additional information supporting the license for initial criticality and power ascension to full-power operation for Unit 2

  15. 76 FR 4724 - Catawba Sox, LLC Formerly Known as Catawba Sox, Inc. Including Workers Whose Unemployment...

    Science.gov (United States)

    2011-01-26

    ... published in the Federal Register on August 2, 2010 (75 FR 45162). At the request of the State agency, the... Whose Unemployment Insurance UI) Wages Are Paid Through Ellis Hosiery Mill, LLC, Newton, NC; Amended... unemployment insurance (UI) tax account under the name Ellis Hosiery Mill, LLC, formerly known as Catawba...

  16. 78 FR 27877 - Safety Zone; McAloon Wedding Fireworks, Catawba Island Club, Catawba Island, OH

    Science.gov (United States)

    2013-05-13

    ... Department of Homeland Security FR Federal Register NPRM Notice of Proposed Rulemaking TFR Temporary Final... public dockets in the January 17, 2008 issue of the Federal Register (73 FR 3316). 4. Public Meeting We... SECURITY Coast Guard 33 CFR Part 165 RIN 1625-AA00 Safety Zone; McAloon Wedding Fireworks, Catawba...

  17. Improving nuclear power station output

    International Nuclear Information System (INIS)

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

  18. Simulators of nuclear power stations

    International Nuclear Information System (INIS)

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

  19. Safety of Russia's nuclear power stations

    International Nuclear Information System (INIS)

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

  20. Socioeconomic impacts: nuclear power station siting

    International Nuclear Information System (INIS)

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

  1. Guangdong Daya Bay nuclear power station project

    International Nuclear Information System (INIS)

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

  2. 77 FR 18271 - Terrestrial Environmental Studies for Nuclear Power Stations

    Science.gov (United States)

    2012-03-27

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

  3. Nuclear Generating Stations and Transmission Grid Reliability

    International Nuclear Information System (INIS)

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

  4. Underground location of nuclear power stations

    International Nuclear Information System (INIS)

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

  5. Starting of nuclear power stations

    International Nuclear Information System (INIS)

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

  6. Series: Information pavilions of nuclear power stations

    International Nuclear Information System (INIS)

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

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

    OpenAIRE

    Varshavsky, Leonid

    2013-01-01

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

  8. Principles of nuclear power station control

    International Nuclear Information System (INIS)

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

  9. Comissioning of Fessenheim nuclear power station

    International Nuclear Information System (INIS)

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

  10. Staff Organization in Nuclear Power Stations

    International Nuclear Information System (INIS)

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

  11. 75 FR 75706 - Dresden Nuclear Power Station, Units 2 and 3 and Quad Cities Nuclear Power Station, Unit Nos. 1...

    Science.gov (United States)

    2010-12-06

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

  12. Distributed systems for protecting nuclear power stations

    International Nuclear Information System (INIS)

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

  13. Phasing out Britain's nuclear power stations

    International Nuclear Information System (INIS)

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

  14. Technological development of Guangdong nuclear power station

    International Nuclear Information System (INIS)

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

  15. Robot equipment for nuclear power stations

    International Nuclear Information System (INIS)

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

  16. Requirement profile for nuclear power station personnel

    International Nuclear Information System (INIS)

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

  17. Report on Darlington nuclear generating station

    International Nuclear Information System (INIS)

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

  18. Multivariable control in nuclear power stations

    International Nuclear Information System (INIS)

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

  19. 78 FR 35646 - Byron Nuclear Station, Units 1 and 2, and Braidwood Nuclear Station, Units 1 and 2

    Science.gov (United States)

    2013-06-13

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

  20. Commentary: childhood cancer near nuclear power stations

    Directory of Open Access Journals (Sweden)

    Fairlie Ian

    2009-09-01

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

  1. Tethered nuclear power for the space station

    International Nuclear Information System (INIS)

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

  2. Underground construction of nuclear power stations

    International Nuclear Information System (INIS)

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

  3. Delayed Station Blackout Event and Nuclear Safety

    OpenAIRE

    Andrija Volkanovski; Andrej Prošek

    2015-01-01

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

  4. Limerick Nuclear Generating Station vibration monitoring system

    International Nuclear Information System (INIS)

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

  5. Trustworthiness test of nuclear power station employees

    International Nuclear Information System (INIS)

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

  6. Forecasting Canadian nuclear power station construction costs

    International Nuclear Information System (INIS)

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

  7. Living near a nuclear power station

    International Nuclear Information System (INIS)

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

  8. Engineering blasting and vibration monitor near nuclear power station

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  11. Nuclear power stations located around Latvia

    International Nuclear Information System (INIS)

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

  12. Grohnde nuclear power station in operation

    International Nuclear Information System (INIS)

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

  13. Aging assessment of nuclear generating station cables

    International Nuclear Information System (INIS)

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

  14. Location and security of nuclear power stations

    International Nuclear Information System (INIS)

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

  15. Ardennes nuclear power station. Annual report, 1976

    International Nuclear Information System (INIS)

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

  16. Water chemistry in nuclear power station

    International Nuclear Information System (INIS)

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

  17. 75 FR 2164 - Entergy Nuclear Operations, Inc.; Pilgrim Nuclear Power Station; Environmental Assessment and...

    Science.gov (United States)

    2010-01-14

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

  18. Human reliability analysis of Lingao Nuclear Power Station

    International Nuclear Information System (INIS)

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

  19. Computer management of refueling for nuclear power station

    International Nuclear Information System (INIS)

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

  20. Delayed Station Blackout Event and Nuclear Safety

    Directory of Open Access Journals (Sweden)

    Andrija Volkanovski

    2015-01-01

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

  1. Corrosion protection at a nuclear power station

    International Nuclear Information System (INIS)

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

  2. Review of radioactive discharges from nuclear power stations

    International Nuclear Information System (INIS)

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

  3. The safety reinforcement measures at Shika Nuclear Power Station

    International Nuclear Information System (INIS)

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

  4. 76 FR 50274 - Terrestrial Environmental Studies for Nuclear Power Stations

    Science.gov (United States)

    2011-08-12

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

  5. Electrical wire for use in nuclear generating stations

    International Nuclear Information System (INIS)

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

  6. Reload Startup Physics Tests for Tianwan Nuclear Power station

    International Nuclear Information System (INIS)

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

  7. Application of additional diesel generators in nuclear power stations

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  9. Inspection program for Embalse Nuclear Generating Station

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  11. 77 FR 35080 - Entergy Nuclear Operations, Inc., Pilgrim Nuclear Power Station; Record of Decision and Issuance...

    Science.gov (United States)

    2012-06-12

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

  12. Erection all risks insurance for nuclear power station

    International Nuclear Information System (INIS)

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

  13. Nuclear power generation modern power station practice

    CERN Document Server

    1971-01-01

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

  14. 78 FR 61400 - Entergy Nuclear Operations, Inc., Pilgrim Nuclear Power Station, Issuance of Director's Decision

    Science.gov (United States)

    2013-10-03

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

  15. 77 FR 76541 - Entergy Nuclear Operations, Inc.; Pilgrim Nuclear Power Station

    Science.gov (United States)

    2012-12-28

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

  16. The risks at nuclear power stations and their insurance

    International Nuclear Information System (INIS)

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

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

    Institute of Scientific and Technical Information of China (English)

    Li Qiankun

    2006-01-01

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

  18. Activity transport in nuclear generating stations

    International Nuclear Information System (INIS)

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

  19. Construction of Dukovany nuclear power station

    International Nuclear Information System (INIS)

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

  20. 75 FR 38147 - FirstEnergy Nuclear Operating Company; Davis-Besse Nuclear Power Station; Exemption

    Science.gov (United States)

    2010-07-01

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

  1. 77 FR 47680 - Entergy Nuclear Operations, Inc.; Pilgrim Nuclear Power Station Receipt of Request for Action

    Science.gov (United States)

    2012-08-09

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

  2. Preventive maintenance activities for nuclear power station

    International Nuclear Information System (INIS)

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

  3. Nuclear power station and environmental protection

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  5. Bid invitations for nuclear power stations

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  7. Surry nuclear power station: 25th anniversary

    International Nuclear Information System (INIS)

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

  8. Model of a nuclear power station

    International Nuclear Information System (INIS)

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

  9. Tritium releases and impact about EDF nuclear power stations

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  12. Ozone for purification of water in nuclear power stations

    International Nuclear Information System (INIS)

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

  13. Experience in increasing power at Grohnde nuclear power station

    International Nuclear Information System (INIS)

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

  14. Safety of CANDU nuclear power stations

    International Nuclear Information System (INIS)

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

  15. Feasibility study on floating nuclear power station

    International Nuclear Information System (INIS)

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

  16. 75 FR 14209 - Entergy Nuclear Operations, Inc.; Vermont Yankee Nuclear Power Station; Exemption

    Science.gov (United States)

    2010-03-24

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

  17. 75 FR 14208 - Entergy Nuclear Operations, Inc.; Pilgrim Nuclear Power Station; Exemption

    Science.gov (United States)

    2010-03-24

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

  18. 75 FR 16523 - FirstEnergy Nuclear Operating Company; Davis-Besse Nuclear Power Station; Exemption

    Science.gov (United States)

    2010-04-01

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

  19. 75 FR 80549 - FirstEnergy Nuclear Operating Company, Davis-Besse Nuclear Power Station; Exemption

    Science.gov (United States)

    2010-12-22

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

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

    Energy Technology Data Exchange (ETDEWEB)

    1976-01-01

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  4. Large containment vessel for nuclear power station

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  6. Computer based training simulator for Hunterston Nuclear Power Station

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  8. The Technical Training Programme for Nuclear Power Station Personnel

    International Nuclear Information System (INIS)

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

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

    OpenAIRE

    I. A. Bokoun

    2014-01-01

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

  10. Organization of radiation protection in German nuclear power stations

    International Nuclear Information System (INIS)

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

  11. Port construction works in the Sendai Nuclear Power Station

    International Nuclear Information System (INIS)

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

  12. 76 FR 82201 - General Site Suitability Criteria for Nuclear Power Stations

    Science.gov (United States)

    2011-12-30

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

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

    OpenAIRE

    Kari, Uday Shankar

    1990-01-01

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

  14. Distributed systems for the protection of nuclear stations

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  16. Nuclear power stations: uneasiness about them and democracy

    International Nuclear Information System (INIS)

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

  17. Online control loop tuning in Pickering Nuclear Generating Stations

    International Nuclear Information System (INIS)

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

  18. Benefits from self-assessments in nuclear stations

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  4. 75 FR 10833 - In the Matter of Entergy Nuclear Operations; Vermont Yankee Nuclear Power Station; Demand for...

    Science.gov (United States)

    2010-03-09

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

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

    International Nuclear Information System (INIS)

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

  6. Expansion potential for existing nuclear power station sites

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  9. 78 FR 71675 - License Amendment Application for Vermont Yankee Nuclear Power Station

    Science.gov (United States)

    2013-11-29

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  17. The Gundremmingen B and C nuclear power station

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  19. 78 FR 66965 - In the Matter of Exelon Generation Company, LLC; Dresden Nuclear Power Station Confirmatory Order...

    Science.gov (United States)

    2013-11-07

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

  20. Radioactive graphite management at UK Magnox nuclear power stations

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  4. Recent trends of hydraulic snubbers for nuclear power station

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  7. 76 FR 39134 - ZIONSOLUTIONS, LLC; Zion Nuclear Power Station, Units 1 and 2 Exemption From Recordkeeping...

    Science.gov (United States)

    2011-07-05

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

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

    International Nuclear Information System (INIS)

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

  9. Reliability estimation for important nuclear power station safety equipment

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  12. Upgrading of HP turbines for nuclear power stations

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2008-07-01

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

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

    International Nuclear Information System (INIS)

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

  16. Technical Specifications, Catawba Nuclear Station, Unit Nos. 1 and 2 (Docket Nos. 50-413 and 50-414). Appendix ''A'' to License Nos. NPF-35 and NPF-52

    International Nuclear Information System (INIS)

    These specifications cover: definitions, safety limits and limiting safety system settings, bases, limiting conditions for operation and surveillance requirements, design features, and administrative controls

  17. Technical Specifications, Catawba Nuclear Station, Unit Nos. 1 and 2 (Docket Nos. 50-413 and 50-414). Appendix ''A'' to License Nos. NPF-35 and NPF-48

    International Nuclear Information System (INIS)

    These specifications cover: definitions, safety limits and limiting safety system settings, bases, limiting conditions for operation and surveillance requirements, design features, and administrative controls

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  1. Medical Actions in Emergencies at Nuclear Power Stations

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  4. Nuclear instrument upgrade at Connecticut Yankee Atomic Power Station

    International Nuclear Information System (INIS)

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

  5. Probabilistic safety analysis for the Unterweser Nuclear Power Station

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  7. Performance of Durasil 70 media Salem Nuclear Generating Station

    International Nuclear Information System (INIS)

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

  8. Waste minimization successes at McGuire Nuclear Station

    International Nuclear Information System (INIS)

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

  9. Accounting and cost control of a nuclear power station

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  12. Response robot and Fukushima Daiichi Nuclear Power Station

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  14. Design Provisions for Station Blackout at Nuclear Power Plants

    International Nuclear Information System (INIS)

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

  15. Safety aspects of station blackout at nuclear power plants

    International Nuclear Information System (INIS)

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

  16. Prevention of human errors in nuclear power stations

    International Nuclear Information System (INIS)

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

  17. Operating Experience at the Aagesta Nuclear Power Station

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  19. Climatographic analysis of the Zion Nuclear Power Station site

    International Nuclear Information System (INIS)

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

  20. Climatographic analysis of the Zion nuclear power station site

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    Science.gov (United States)

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

    2008-11-01

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

  9. 76 FR 44376 - Vermont Yankee Nuclear Power Station; Notice of Withdrawal of Application for Amendment to...

    Science.gov (United States)

    2011-07-25

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  13. Radiocarbon mass balance for a Magnox nuclear power station

    International Nuclear Information System (INIS)

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

  14. Safety culture program for the Cofrentes nuclear power station

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  16. Torness nuclear power station. From folly to fiasco

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  19. The Fukushima Nuclear Power Station incident and marine pollution

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Hall, J

    1999-12-01

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

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

    Science.gov (United States)

    2013-04-15

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  9. Design, construction and erection of the biological shield wall for the Caorso nuclear power station

    International Nuclear Information System (INIS)

    This article describes the major aspects of the design, construction and erection of the biological shield wall encircling the reactor pressure vessel of the Caorso nuclear power station (Italy) (BWR-Mark 2, 840MWe)

  10. New high-temperature transducer for sound and vibration measurements in nuclear power stations

    International Nuclear Information System (INIS)

    With the ever increasing demands made concerning the monitoring of nuclear power stations, sound and vibration measurement is of growing importance. Prerequisites for its successful application are transducers of sufficient sensitivity, high-temperature, radiation and corrosion resistivity, as well as high reliability. In sodium-cooled nuclear power stations, these transducers may be used for integral and local boiling detection. Vibration and sound measurements in all types of nuclear power stations have lately begun to play an important part, too. The different conditions of application in sodium-cooled fast breeders, light-water-cooled plants, and high-temperature nuclear power stations can be accounted for by two physical methods: the piezoelectric and the magnetostrictive technique. Both of these methods are discussed. (orig./AK)

  11. Welding of stainless steel pool of pressurized water reactor nuclear power station

    International Nuclear Information System (INIS)

    The construction of stainless steel lining of million kilowatt grade pressurized water reactor nuclear power station is a new technology. The author introduces its welding method, parameter verification measure and key factors of construction quality control and so on

  12. 76 FR 48184 - Exelon Nuclear, Peach Bottom Atomic Power Station, Unit 1; Exemption From Certain Security...

    Science.gov (United States)

    2011-08-08

    ... (76 FR 37842). Based upon the environmental assessment, the Commission has determined that issuance of... COMMISSION Exelon Nuclear, Peach Bottom Atomic Power Station, Unit 1; Exemption From Certain Security... issued for Peach Bottom Atomic Power Station (PBAPS), Unit 1, located in York County, PA. PBAPS Unit 1...

  13. Radioactive waste disposals and personal radiation doses resulting from operation of CEGB nuclear power stations

    International Nuclear Information System (INIS)

    The discharge of radioactive effluents, both aqueous and airborne, and the disposal of radioactive solid wastes from the CEGB nuclear power stations are reviewed. Resulting radiation doses to members of the public are discussed. Radiation doses incurred by power station employees are also reviewed briefly. It is concluded that discharges and disposals have been controlled satisfactorily. (U.K.)

  14. FAPIG's activities for public acceptance of nuclear energy. Analytical results of questionnaire executed at organized visits to nuclear power stations

    International Nuclear Information System (INIS)

    An organized visits to Kashiwazaki Kariwa nuclear power stations was carried out on 15 and 16th November 2001. They visited the nuclear power station after conducting seminar. The same questionnairing were conducted on 20 participants before joining the seminar, and after visiting the nuclear power stations. The object and effects of these organized visits are explained in this paper. The outline of the organized visits, the questions, results of questionnaire are explained. Almost members had not taken part of nuclear power and they obtained information about nuclear power by means of mass media. 17 members felt uneasy about safety of nuclear power because of accident. However, 10 members changed to be safe after confirmation of defense in depth and the controlled system in the power station. 16 members did not understand the mechanism of nuclear power. So that we hope that the mechanism of nuclear power is studied in the school. They recognize the need of nuclear power because of small energy source in Japan. (S.Y.)

  15. The introduction of an integral quality assurance system in the Beznau nuclear power station

    International Nuclear Information System (INIS)

    The Nordostschweizerische Kraftwerke AG decided in 1982 to introduce an integral quality assurance system for the operational phase of the Beznau nuclear power station. The post of Quality Assurance Agent was created. Together with a team of representatives from all departments at the Beznau nuclear power station this person was responsible for writing and introducing the quality assurance manual. The system is practice-oriented and comprises all the work which is involved in the operation of the power plants. 2 figs

  16. Planning the closure of nuclear power stations: theoretical rationale and practical factors

    International Nuclear Information System (INIS)

    The question of closing nuclear power stations is at the centre of ongoing debates regarding a Parliamentary bill on energy transition in France. This calls into question the role of the State in the management of all the existing nuclear facilities. What are the economic arguments that justify public intervention with regard to determining the electricity mix and the calendar for the planned closing down of these stations? (authors)

  17. Research and development activities for cleanup of the Fukushima Daiichi Nuclear Power Station

    OpenAIRE

    佐々木 紀樹; 上西 修司; 宮本 泰明; 船坂 英之

    2013-01-01

    The Fukushima Daiichi Nuclear Power Station accident and restoration works have produced significant volume of radioactive waste. The waste has very different characteristics from usual radioactive waste produced in nuclear power stations and it requires extensive research and development for management of the waste. R&D works such as radionuclide analysis of the waste, hydrogen generation/diffusion analysis of a storage vessel, corrosion evaluation of storage vessels, etc. have been performe...

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

    International Nuclear Information System (INIS)

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

  19. Application of nuclear power station design criteria to non-nuclear installations

    International Nuclear Information System (INIS)

    The nuclear industry is multi faceted, in that it includes large and complex chemical plants, a large number of different types of nuclear power stations, and on shore ship maintenance facilities, each with its own unique problems. Since the early days the industry has been aware of the additional problem which is superimposed on what may be classed as traditional fire risks, that is, the risk of an uncontrolled release of radioactivity. This has led to the development of sophisticated fire prevention and control techniques which are applied to new plants, and to the backfitting of older plants. The techniques of analysis, design and operation can be applied to both nuclear and non-nuclear installations. Passive protection is preferred backed up by active techniques. Segregation of essential plant to increase the probability of sufficient surviving to ensure safety systems operate and the provision of smoke free, protected escape routes are important aspects of layout and design. Reliability assessments, venting of smoke and hot gases, fire severity analysis, application of mathematical models contribute to the final design to protect against fires. Experiences built up in the fire fighting profession is integrated into the numerical approach by frequent involvement of the local Fire Officers at each stage of the design and layout of installations. (author)

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

    International Nuclear Information System (INIS)

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

  1. District heating system of Beznau nuclear power station - foundation of REFUNA AG

    International Nuclear Information System (INIS)

    The author describes a district heating system supplied with heat from the Beznau nuclear power stations. The system will eventually reduce heating oil consumption in the area by 16,000 tonnes/year. At present, 70,000 kW of heat are available for 8 towns totalling 15,000 inhabitants. The maximum distance from the power station is 10 km, the maximum level difference 100 m. The hot water (1200C) from the two nuclear power stations passes through a distribution network with pumping stations to homes and businesses in the area. The maximum consumption of heat (52 MW) corresponds to 1.2% of the output of the power stations. (J.S.)

  2. A fully electrified society powered by light water nuclear stations

    International Nuclear Information System (INIS)

    The purpose of this paper is to stress that recent developments around the world favor nuclear power as the most effective countermeasure against global warming. All other means have severe limitations. Solar power and wind power are both much higher in generating cost than nuclear. Only nuclear can greatly reduce world CO2 emission at a cost comparable to fossil fuels. The biggest and probably the only obstacle to expanded use of nuclear power is public opinion or zeitgeist against nuclear power. It can, however, be overcome by a powerful national leadership. (author)

  3. The duty health physicist program at Byron Nuclear Power Station

    International Nuclear Information System (INIS)

    The Duty Health Physicist Program at Byron Station was established to deal with routine health physics tasks and provide an interface between frontline and upper radiation-chemistry management. The program consists of a weekly rotation of selected members of the health physics staff into the duty health physicist position to handle the assigned duty tasks. The tasks include, but are not limited to, daily isotopic and air sample review, effluent release package review, maximum permissible concentration calculations, dose approvals, as-low-as-reasonably-achievable action review of pending jobs, and general availability to answer questions and address problems in health-physics-related areas of plant operation. The daily attendance of the duty health physicist at the radiation-chemistry and station plan-of-the-day meetings has increased the overall presence and visibility of the health physics program to upper station management and other station departments. Since its inception in July of 1985, the Duty Health Physics Program has been a major contributor to the observed 50% reduction in reportable personnel errors in the radiation-chemistry department (based on personnel-error-related deviation reports and license event reports generated on the radiation-chemistry department at Byron Station). Although difficulty to quantify, other important benefits of this program are also discussed in this paper

  4. AECB staff annual assessment of the Bruce B Nuclear Generating Station for the year 1996

    International Nuclear Information System (INIS)

    The Atomic Energy Control Board is the independent federal agency that controls all nuclear activities in Canada. A major use of nuclear energy in Canada is electricity production. The AECB assesses every station's performance against legal requirements, including the conditions in the operating licence. Each station is inspected and all aspects of the station's operation and management is reviewed. This report is the AECB staff assessment of reactor safety at the Bruce Nuclear Generating Station B for 1996. It was concluded that Ontario Hydro operated Bruce B safely in 1996. Although the Bruce B plant is safe,it was noted that the number of outages and the number of secondary and tertiary equipment failures during reactor unit upsets increased. Ontario Hydro needs to pay special attention to prevent such a decrease in the safety performance at Bruce B

  5. AECB staff annual assessment of the Bruce A Nuclear Generating Station for the year 1996

    International Nuclear Information System (INIS)

    The Atomic Energy Control Board is the independent federal agency that controls all nuclear activities in Canada. A major use of nuclear energy in Canada is electricity production. The AECB assesses every station's performance against legal requirements, including the conditions in the operating licence. Each station is inspected and all aspects of the station's operation and management is reviewed. This report is the AECB staff assessment of reactor safety at the Bruce Nuclear Generating Station A for 1996. Ontario Hydro operated Bruce A safely in 1996, maintaining the risk to workers and the public at an acceptably low level. Special safety system performance at Bruce A was adequate. Availability targets were all met. Improvement is needed to reduce the number of operating licence non-compliances

  6. Technology, safety and costs of decommissioning nuclear reactors at multiple-reactor stations

    International Nuclear Information System (INIS)

    Safety and cost information is developed for the conceptual decommissioning of large (1175-MWe) pressurized water reactors (PWR) and large (1155-MWe) boiling water reactors (BWR) at multiple-reactor stations. Three decommissioning alternatives are studied: DECON (immediate decontamination), SAFSTOR (safe storage followed by deferred decontamination), and ENTOMB (entombment). Safety and costs of decommissioning are estimated by determining the impact of probable features of multiple-reactor-station operation that are considered to be unavailable at a single-reactor station, and applying these estimated impacts to the decommissioning costs and radiation doses estimated in previous PWR and BWR decommissioning studies. The multiple-reactor-station features analyzed are: the use of interim onsite nuclear waste storage with later removal to an offsite waste disposal facility, the use of permanent onsite nuclear waste disposal, the dedication of the site to nuclear power generation, and the provision of centralized services

  7. Plant computer systems betterment strategy for nuclear power stations in Taiwan

    International Nuclear Information System (INIS)

    Taiwan Power Company operates three nuclear power stations and is currently in the process of building a fourth one. In 1989, TPC started surveys and evaluations of computer systems for nuclear power stations, and continuously performs this task once every two years. To match up with the fast pace of changes in technology, TPC has to upgrade the plant computer systems frequently to avoid equipment obsolescence. On the other hand, to save the investment and maximize the cost benefits, TPC has to appropriately use its limited resources. Therefore TPC developed an overall plan. The strategy proposed in this plan will continue to prove effective, both in existing station betterment projects and in new nuclear power station projects. TPC's challenge of implementing this strategy is subject now and will be subject in the future to the dynamic adjustments of the rapid technology changes. (author)

  8. Necessity of installing hydrogen plant in Ling'ao Nuclear Power Station

    International Nuclear Information System (INIS)

    In the equipment bid inviting for Ling'ao Nuclear Power Station, the French specialists engaged by the station proposed that the hydrogen plant should not be built and hydrogen be purchased from outside the station. The necessity of constructing a hydrogen plant by the station itself is expounded in terms of safety, reliability, economics and applicability. It is pointed out that purchasing hydrogen from the outside has latent safety faults in transportation and operation; the quality and supply of hydrogen can not be guaranteed when the hydrogen supply has not been commercialized; the geographical position of the station can not fulfil the regulatory requirements for purchasing hydrogen from the outside; technologically-economically, the return on investment in constructing the hydrogen plant is not low. Therefore, the plan of generating hydrogen by the station itself is more practical

  9. Developments in health physics at Electricite de France, implementation at Guangdong Nuclear Power Station

    International Nuclear Information System (INIS)

    The Guangdong Nuclear Power Station intend to apply the same organization and the same principle in health physics as EDF (ELECTRICITE DE FRANCE). The permanent 'clean plant' objective has ensured that the internal exposure of nuclear plant workers has remained virtually zero. This, then, is the basis on which EDF is now continuing to develop health physics in its plants

  10. EDF experimental test facilities for main components of nuclear power stations

    International Nuclear Information System (INIS)

    Several facilities essentially designed to test nuclear power plant equipment, whose purpose is to improve the availability of nuclear power stations, are described: test loop for water reactor primary pumps, test rig for separators, wet steam test turbine, test loop for Super-Phenix pumps

  11. The safety and siting of nuclear power stations

    International Nuclear Information System (INIS)

    The main safety legislation, and corresponding executive responsibilities, governing the health and safety standards at nuclear installations in the United Kingdom, are outlined. The paper discusses in more detail the arrangements by which the Nuclear Installations Inspectorate carries out its regulatory functions on behalf of the Health and Safety Executive, under the headings: nuclear site licenses; design safety assessment; safety in operation; siting. (U.K.)

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

    International Nuclear Information System (INIS)

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

  13. Efforts toward enhancing seismic safety at Kashiwazaki Kariwa nuclear power station

    Energy Technology Data Exchange (ETDEWEB)

    Yamashita, Kazuhiko

    2010-09-15

    Kashiwazaki-Kariwa Nuclear Power Station, 8212MW, was struck by M6.8 quakes in July 2007. TEPCO has steadily been conducting restoration and post-earthquake equipment integrity assessment, aiming to make it a disaster-resistant power station. 2 units among 7 resumed commercial operation by June 2010. This earthquake has provided a great deal of knowledge and information useful for nuclear safety improvement. It has also served as a valuable reference for the IAEA in developing earthquake-related guidelines. TEPCO would like to share the knowledge and information thereby contributing to improving the safety of nuclear power generation. We will introduce some of our activities.

  14. Aseismic design of the Heysham II Nuclear Power Station

    International Nuclear Information System (INIS)

    A brief description of the seismic criteria established for use with the Steam Generating Heavy Water Reactor (SCHWR) and taken for the Heysham II Project is given. The qualification strategy adopted for Heysham II is described, and a brief overview is given of some of the more important design changes required for seismic purposes on that station

  15. Leukaemia and lymphoma mortality in the vicinity of nuclear power stations in Japan, 1973-1987

    International Nuclear Information System (INIS)

    In many countries, studies have been carried out on cancer mortality near nuclear facilities. In the present paper, we examine the standardised mortality ratios (SMR) and the relative risks (RR) of five malignant neoplasms (leukaemia, malignant lymphoma, non-Hodgkin's lymphoma, multiple myeloma and acute non-lymphatic leukaemia) for two age groups (0-14 years and all ages) during different periods (1973-1977), 1978-1982, 1983-1987 and 1973-1987) in the 18 site municipalities and in the four control municipalities selected near each nuclear power station site in Japan. For some sites, as well as for control groups, SMRs of certain malignant neoplasms were sometimes high, even before the startup of a nuclear power station. It is concluded that leukaemia and lymphoma mortality in the Japanese municipalities containing nuclear power stations is not significantly different from the control areas. (author)

  16. Five years of partnership between nuclear power stations in Germany and the CIS and Central European states

    International Nuclear Information System (INIS)

    For five years, partnerships have existed between German nuclear power stations and nuclear power stations in the CIS and central European states with the object of increasing the nuclear safety and reliability of nuclear power stations through the interchange of experience by experts at all operational organisational levels. In this period, about 200 reciprocal meetings, exchanges of groups of experts, secondments into the partners' plants and seminars, of which about two-thirds have been in German nuclear power stations, have taken place. Improvements and a change in safety-responsibility awareness are clearly established. In this area, the partnerships have made an important contribution. (orig.)

  17. Criteria Applied in the Recent Choice of Site for the First Argentine Nuclear Power Station

    International Nuclear Information System (INIS)

    The basic requirements for the site of a nuclear power station with lower electricity generation costs than those of an equivalent conventional plant are fulfilled, in Argentina, in the area known as Gran Buenos Aires-Litoral. In 1965, the power grid of this area linked together stations with a total installed capacity of 2200 MW, and a further 1300 MW will have to be added during the period 1966-1972. On the basis of estimated power requirements a nuclear station of up to 500 MW could be installed in 1971-1972, and the grid could bear this increase in capacity. The criteria applied in the choice of site fall under two main headings: (a ) station construction, and (b) station operation. The first heading covers, in addition to proper integration of the station into the grid, the availability of cooling water, favourable topography, suitable foundations, easy access, and acceptable hydrological, soil and meteorological conditions. The second heading covers, apart from measures relating to the prevention of reactor accidents and the containment of the radioactivity, such items as the features of the site in relation to centres of population, assuming that the safety measures cannot entirely prevent an escape of fission products. Careful consideration of the criteria falling under these two headings has led to the choice, as most suitable site for the first Argentina nuclear power station, of the locality known as ''Atucla'', some 100 km northwest of Buenos Aires, on-the banks of the Rio Paraná de Las Palmas. (author)

  18. Study of the legal problems raised by the siting of nuclear power stations in artificial islands

    International Nuclear Information System (INIS)

    The creation and operation of a nuclear power station on an artificial island in French waters are governed by domestic law and are subject to two types of procedure: the first concerns erection of the artificial island and the second the control of the public authorities over creation and operation of the nuclear power station. At administrative level, the setting up of an artificial island requires that it be attached to a commune as well as permission for occupancy from the maritime authorities. Furthermore, setting up of a nuclear power station on an artificial island is subject to the licensing procedure for large nuclear installations and to delivery of the licenses required for release of gaseous and liquid radioactive effluents. Given the proximity of the high seas and eventually, the borders of other States, siting of a nuclear power station on an artificial island imposes obligations at international level. These requirements, which concern prevention of transfrontier pollution, stem from the London (1972) and Paris (1974) Conventions on marine pollution. The third party liability regime for a nuclear incident caused by an installation sited in territorial seas is that of the 1960 Paris Convention on third party liability in the nuclear field and the 1963 Brussels Supplementary Convention. Another problem likely to be raised is that of the right of innocent passage of ships near such installations

  19. General technical characteristics of the Paks nuclear power station

    International Nuclear Information System (INIS)

    The power station is planned to have 1760 MW; it will consist of 4 power units of 440 MW each. The energy source for the power station is a heterogeneous pressurized water reactor of the type V-213 representing a thermal output of 1375 MW. The reactor will use moderately enriched uranium as a fuel. As to its technological scheme the power plant will have two circuits. The radioactive primary circuit, accomodated in a hermetic box, will contain the reactor, the six loops including the steam generators, main circulating pumps, gate valves, pipings. The non-radioactive secondary circuit accomodates the turbogenerator sets, all their ancillary equipment and heat supply installations. Associated to the reactor hall an auxiliary building serves to store temporarily the liquid and solid radioactive waste. The power plant will be connected to the national grid at voltages of 120 and 400 kV. (author)

  20. 76 FR 81542 - In the Matter of ZIONSOLUTIONS, LLC; Zion Nuclear Power Station; Independent Spent Fuel Storage...

    Science.gov (United States)

    2011-12-28

    ... COMMISSION In the Matter of ZIONSOLUTIONS, LLC; Zion Nuclear Power Station; Independent Spent Fuel Storage..., Licensing and Inspection Directorate, Division of Spent Fuel Storage and Transportation, Office of Nuclear... providing notice, in the matter of Zion Nuclear ] Power Station Independent Spent Fuel Storage...

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

    Science.gov (United States)

    2013-12-27

    ... COMMISSION Zion Solutions, LLC; Zion Nuclear Power Station, Units 1 and 2; Exemption From Certain Physical Security Requirements 1.0 Background Zion Nuclear Power Station (ZNPS) Units 1 and 2 were permanently shut... ``Requirements for physical protection of licensed activities in nuclear power reactors against...

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

    Science.gov (United States)

    2011-11-21

    ... COMMISSION ZionSolutions, LLC; Zion Nuclear Power Station, Units 1 and 2; Exemption From Certain Security Requirements 1.0 Background Zion Nuclear Power Station (ZNPS or Zion), Unit 1, is a Westinghouse 3250 MWt... activities in nuclear power reactors against radiological sabotage,'' paragraph (b)(1) states, ``The...

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

    International Nuclear Information System (INIS)

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

  4. Natural Disasters and Safety Risks at Nuclear Power Stations

    Science.gov (United States)

    Tutnova, T.

    2012-04-01

    In the aftermath of Fukushima natural-technological disaster the global opinion on nuclear energy divided even deeper. While Germany, Italy and the USA are currently reevaluating their previous plans on nuclear growth, many states are committed to expand nuclear energy output. In China and France, where the industry is widely supported by policymakers, there is little talk about abandoning further development of nuclear energy. Moreover, China displays the most remarkable pace of nuclear development in the world: it is responsible for 40% of worldwide reactors under construction, and aims at least to quadruple its nuclear capacity by 2020. In these states the consequences of Fukushima natural-technological accident will probably result in safety checks and advancement of new reactor technologies. Thus, China is buying newer reactor design from the USA which relies on "passive safety systems". It means that emergency power generators, crucial for reactor cooling in case of an accident, won't depend on electricity, so that tsunami won't disable them like it happened in the case of Fukushima. Nuclear energy managed to draw lessons from previous nuclear accidents where technological and human factors played crucial role. But the Fukushima lesson shows that the natural hazards, nevertheless, were undervalued. Though the ongoing technological advancements make it possible to increase the safety of nuclear power plants with consideration of natural risks, it is not just a question of technology improvement. A necessary action that must be taken is the reevaluation of the character and sources of the potential hazards which natural disasters can bring to nuclear industry. One of the examples is a devastating impact of more than one natural disaster happening at the same time. This subject, in fact, was not taken into account before, while it must be a significant point in planning sites for new nuclear power plants. Another important lesson unveiled is that world nuclear

  5. Review and studies of gas treatment and ventilation systems in Ontario Hydro's nuclear generating stations

    International Nuclear Information System (INIS)

    Gas treatment systems for Ontario Hydro's major nuclear generating stations, namely Pickering A and B, Bruce A and B, and Darlington, are briefly described and compared. The Off-Gas Management System, the Reactor Ventilation System (or Contaminated Exhaust System) and the D2O Vapour Recovery System reduce gaseous radioactive emissions during normal station operation whereas the Emergency Filtered Air Discharge System is designed for post-accident containment clean-up. RandD areas to improve gaseous radionuclide control are also briefly discussed. A study at Bruce A using the tracer gas technique to determine the effectiveness of a modification to the ventilation system to induce air flow in the desired direction is discussed in detail. Results showed that the technique provided quantitative data of air movement in the station. Other applications of the tracer gas technique in nuclear generating stations have also been implemented or developed. (author)

  6. Spare parts procurement program for Byron/Braidwood Nuclear Power Stations

    International Nuclear Information System (INIS)

    This paper outlines the engineering effort being undertaken for Byron/Braidwood Nuclear Power Station to develop a comprehensive Spare Parts Procurement Program which will significantly reduce the maintenance costs associated with the Plants' safety-related components. The Byron and Braidwood Nuclear Power Stations are owned and operated by Commonwealth Edison Company (CECO), Chicago, Illinois. Each station consists of two Westinghouse, Four Loop PWR units, with 1176 MW gross electrical output for each unit. The two stations are identical in design, except for the ultimate heat sink. Byron utilizes cooling towers, whereas Braidwood uses a cooling lake. This paper describes the reasons behind this effort, the objectives, and the approach adopted to accomplishing the goals

  7. AECB staff annual assessment of the Point Lepreau Nuclear Generating Station

    International Nuclear Information System (INIS)

    The Atomic Energy Control Board is the independent federal agency that controls all nuclear activities in Canada. A major use of nuclear energy in Canada is electricity production. The AECB assesses every station's performance against legal requirements, including the conditions in the operating licence. Each station is inspected and all aspects of the station's operation and management is reviewed. This report is the AECB staff assessment of reactor safety at the Point Lepreau Generating Station in 1996. Point Lepreau operated safely but the worsening trends in NB Power's safety performance leads to the conclusion that urgent action is required. NB Power is required to report formally to the AECB on progress with measures to improve safety management every six months. Further licensing action will be taken on NB Power if it fails to make the improvements

  8. Monitoring of radioactivity in the environs of Finnish nuclear power stations in 1986

    International Nuclear Information System (INIS)

    Results of the environmental programmes monitoring radioactivity around the Finnish nuclear power stations in 1986 are reported. After the end of April the fallout nuclides from the Chernobyl accident predominated in all samples taken from the environs of the two power stations Loviisa and Olkiluoto. Radionuclides originating from the Finnish power stations were detected mainly in samples taken from the aquatic environment. The concentrations of the locally discharged nuclides were very low in comparison with the fallout nuclides and their impact on the radiation doses of the population was insignificant. Both nuclear power stations are situated in the main fallout area in Finland. The results of these large monitoring programmes give a good picture of the behaviour of the Chernobyl fallout in the specific areas in Finland

  9. The UK's nuclear power stations: what are they worth?

    International Nuclear Information System (INIS)

    The answer to this question should be known by mid-July when the UK government hopes to have sold shares in the seven AGRs and lone PWR that produce around 20% of the country's electricity. This will be a real test of the private investor's confidence in the economics of nuclear energy and has required nothing less than complete transformation in the culture and performance of Britain's nuclear power industry. (author)

  10. Training of technical staff for nuclear power stations

    International Nuclear Information System (INIS)

    Nine papers presented at the Seminar are printed. All are indexed separately. Two of the papers cover the facilities and training programmes for British naval personnel operating powered submarines. Four are concerned with the Central Electicity Board's training of nuclear power plant personnel, one specifically for the Hinckley Point-B reactor. Italian and Swedish nuclear power plant operator training programmes are reviewed in the other two papers. (U.K.)

  11. Production of electricity in nuclear power stations with high efficiencies

    International Nuclear Information System (INIS)

    Today nuclear energy makes an important contribution to the global supply of electricity. Present systems of nuclear reactors are available, some of them are highly developed. In the long term the use of nuclear energy will significantly gain importance when aspects of resource protection, economy and ecology - especially the reduction of CO2-emissions - are taken seriously. In this case high demands for the security as well as for the reactors and in the disposal of nuclear waste have to be made. With regard to these aspects, the High Temperature Reactor (HTR) offers great potentials. In this report first the achieved efficiencies and expectations for the future of fossil and nuclear power plants are discussed. Different processes of nuclear power plants based on an HTR are described in regard to the improvement of efficiencies. The optimization problem of power plants while considering aspects of engineering, economy, ecology and the reasonable use of resources is subject of a further consideration. After an intensive discussion of the different concepts based on an HTR (steam turbine-process, gas turbine-process and combined gas- and steam turbine-process) detailed questions considering construction, heat engineering and security are intensely regarded. (orig.)

  12. Development of a risk-informed safety management system at the Gentilly-2 Nuclear Generating Station

    Energy Technology Data Exchange (ETDEWEB)

    Komljenovic, D.; Hotte, G.; Beaudet, M. [Hydro-Quebec, Nuclear Generating Station Gentilly-2, Gentilly, Quebec (Canada)], E-mail: komljenovic.dragan@hydro.qc.ca

    2009-07-01

    The paper presents an overview regarding current and future activities related to the management of safety and regulatory framework at the Gentilly-2 Nuclear Generating Station. The paper discusses alignment of these activities with the best Canadian and international practices. It also proposes manners to develop a consistent risk-informed safety management system. The paper takes particularly into consideration the impact of this new framework on the refurbishment project, and the operations after the refurbishment of the station. (author)

  13. Method for the determination of active sulphur in the graphite packing of nuclear power station

    International Nuclear Information System (INIS)

    The determination of the active sulphur soluble from the graphite packing under the operating conditions of a nuclear power station is a very important task. In the new method presented here a reproducible and reliable sample preparation technique (HPA, High Pressure Asher) was used by which the operating conditions of the power station could be approached very well. The soluble active sulphur content was determined with an ARL 3410 ICP-OES vacuum spectrometer. (author) 6 refs.; 5 figs.; 2 tabs

  14. Demolition of the Rheinsberg nuclear power station. Current status, special occurrences, experience

    International Nuclear Information System (INIS)

    The Rheinsberg nuclear power station (KKR), like the Greifswald nuclear power station (KGR), is part of Energiewerke Nord GmbH (EWN). Consequently, the demolition strategy, the licensing strategy, the waste management strategy, and project management of both demolition projects follow the principles valid at EWN. As KKR and KGR are located in different federal states, 2 nuclear supervisory authorities in the respective federal states are competent. One licensing procedure applying to both locations was out of the question. In addition to the administrative setup and the technical parameters, there are also differences and special features in the technical equipment of the 2 nuclear power plants and the conditions applying at the locations of KGR and KKR, which must be taken into account. The article refers to some key items of decommissioning the Rheinsberg nuclear power station in the period between 2002 and 2007. On the whole, demolition of the Rheinsberg nuclear power station has progressed well. By late 2007, approx. 76% of the equipment to be demolished has been dismantled. Demolition of the equipment of KKR is to be completed probably by 2012. Since the closure of the Morsleben repository for radioactive waste (ERAM) in September 1998, the solid radioactive waste arising has been disposed of in the Nord interim store (ZLN) near Lubmin. (orig.)

  15. The outline of decommissioning plan for Hamaoka Nuclear Power Station's Unit 1 and Unit 2

    International Nuclear Information System (INIS)

    In Japan, terminated nuclear power stations must be dismantled and removed, and doing this requires establishing a nuclear reactor facility decommissioning plan as based on the Law on the Regulation of Nuclear Source Material, Nuclear Fuel Material and Reactors, and getting the approval of the national government. Termination Hamaoka Nuclear Power Station's Unit 1 and Unit 2 on January 30, 2009 Chubu Electric submitted an 'Application for Approval of Hamaoka Nuclear Power Station's Unit 1 and Unit 2 Decommissioning Plan' to the Minister of Economy, Trade and Industry in keeping with the stipulations of Article 43, Paragraph 3-2-2, of the Law on the Regulation of Nuclear Source Material, Nuclear Fuel Material and Reactors. On June 1, 2009 As the application was authorized on November 18, 2009, Chubu Electric started to dismantle. The application includes an overall plan for dismantling reactor facilities safely and surely, a description of tasks to be performed during the period Chubu Electric is preparing to dismantle the facilities in the coming years (system decontamination, survey of facility contamination, etc.) and safety assurance measures, among other information. (author)

  16. Radioactive emission data from Canadian nuclear generating stations 1972 to 1994

    International Nuclear Information System (INIS)

    All nuclear generating stations release small quantities of radioactivity in a controlled manner into both the atmosphere (as gaseous effluents) and adjoining water bodies(as liquid effluents). The purpose of this document is to report on the magnitude of these emissions for each nuclear generating station (NGS) in Canada and to indicate how these emissions compare with the relevant limitations imposed by the AECB as part of its regulatory and licensing program. The data show that the levels of emissions of gaseous and liquid effluents from all currently operating nuclear generating stations are well below the values mandated by the AECB. In fact, since 1987 no emissions have exceeded 1% of those values. 3 tabs., 10 figs

  17. Design and layout of nuclear heating stations provided for cogeneration of hot water and process steam

    International Nuclear Information System (INIS)

    In this paper possibilities of extending supply mission of nuclear heating stations by provision of both hot water for district heating and steam for industrial consumers are studied. Based on applying a method developed for hot water generation only, trends in the heat-engineering design of a nuclear heating station designated to cogeneration of hot water and process steam are derived. Results of calculations show that in the case of larger amounts of process steam to be generated modifications of the reactor of the AST-500 type nuclear heating station developed in the USSR for hot water generation only would have to be provided. Lower amounts of steam might be provided by slightly increasing core pressure with no changes in the design of the primary coolant circuit. (author)

  18. Compensation for the risk of a nuclear power station. Distances and people's perceptions

    International Nuclear Information System (INIS)

    Geographic patterns of citizens' perceptions of the risk and benefit of a nuclear power station are determined using two social surveys. In the neighborhood area, perceived risk reduces slowly as the distance from the power station increases. The reduction pace accelerates as the distance reaches 20-30 kilometers and the pace slows down again in the farther areas. Perceived benefits are relevant to the townships where the respondents reside. Those geographic patterns explain citizens' views in each area of whether the benefit is enough to compensate for the risk of the power station. (author)

  19. Maintenance in the conventional plant sections of Beznau and Muehleberg nuclear power stations

    International Nuclear Information System (INIS)

    First, the conventional plant at both nuclear power stations is briefly introduced. It is emphasized that they are similar to each other and differ in essence only in respect of the occurrence of radio-activity in one of the two stations. In addition the objectives of each maintenance programme and the strategy applied to achieving these objectives are described. Inspection as a major aspect of maintenance, its object and purpose, the scope of inspection and intervals between inspection in both stations are considered. (orig.)

  20. Fish cultures in the area of the nuclear power station Dukovany and their prospects

    International Nuclear Information System (INIS)

    The results of investigating the fishery production and measurements of radiation background in the ecosystem of the Jihlava river, in the area of a nuclear power station being built near Dukovany are evaluated with regard to the prospects of fish cultures when the power station operates in full extent. Basic data were provided for calculating the burden of significant groups of the population, resulting from the ingestion of fish of local provenance. All available information shows that under normal operating conditions, the power station should not exert a negative influence on the quality of fish food and that in the area under study it would be possible to manage intensive fish cultures. (author)

  1. Information management for nuclear power stations: System Design Concept

    International Nuclear Information System (INIS)

    A study of the information management structure required to support nuclear power plant construction was performed by a joint university-industry group under the sponsorship of the Department of Energy (DOE), formerly the Energy Research and Development Administration (ERDA). The purpose of this study was (1) to study methods for the control of information during the construction and start-up of nuclear power plants, and (2) identify those data elements intrinsic to nuclear power plants which must be maintained in a structured format for quick access and retrieval. Maintenance of the massive amount of data needed for control of a nuclear project during design, procurement, construction, start-up/testing, and operational phases requires a structuring which allows immediate update and retrieval based on a wide variety of access criteria. The objective of the research described has been to identify design concepts which support the development of an information control system responsive to these requirements. A conceptual design of a Management Information Data Base System which can meet the project control and information exchange needs of today's large nuclear power plant construction projects has been completed and an approach recommended for development and implementation of a complete operational system

  2. Estimated doses from decommissioning activities at commercial nuclear power stations

    International Nuclear Information System (INIS)

    This paper reviews generic population dose estimates for decommissioning reference boiling water reactors (BWRs) and pressurized water reactors (PWRs) and provides extrapolated estimates of the total collective dose resulting from decommissioning commercial nuclear reactors operated in the United States. Decontamination and decommissioning of retired nuclear power reactors is a necessary part of the nuclear fuel cycle. During decommissioning of large facilities, radioactivity will be encountered in activated reactor components and in contaminated piping, equipment, and building surfaces. The US Nuclear Regulatory Commission (NRC) sponsored a series of studies to evaluate the technology, safety, and costs of decommissioning a variety of nuclear fuel cycle facilities. The NRC adopted the following standardized definitions concerning decommissioning: (1) decommissioning: the measures taken at the end of a facility's operating lifetime to ensure the protection of the public from any residual radioactivity or other hazards present in the facility; (2) DECON: immediate decontamination leading to the release of the facility for unrestricted use; (3) SAFSTOR: safe storage plus deferred decontamination leading to release of the facility for unrestricted use; and (4) ENTOMB: entombment plus decay leading to release of the facility for unrestricted use. In the NRC studies, the most likely decommissioning alternative for most facilities was assumed to be DECON or SAFSTOR

  3. Quality assurance for nuclear power stations in Japan

    International Nuclear Information System (INIS)

    The quality assurance programmes of the Japanese industry show some special features, both in the nuclear field and in non-nuclear technology. Among them e.g. the meticulous care given by Japanese workers to their work and duties, and the high training level and skill of employees in the development and other departments. Another important feature is the common practice of Japanese firms, to guarantee lifetime employment to workers and employees. The quality assurance programme for nuclear power plants covers such aspects as basic design features, detailed planning and construction, fuel element fabrication, basic research, licensing and operation. The responsibility for efficient execution of the programmes lies with the administration, the utilities, the suppliers, as well as all other contractors to a project. The tasks to be fulfilled by organisations, firms, etc., are briefly explained. (orig./HSCH)

  4. Slovak power stations, Nuclear Power Plants Mochovce (Annual report 1997)

    International Nuclear Information System (INIS)

    A brief account of activities carried out by the Nuclear power plants Mochovce in 1997 is presented. These activities are reported under the headings: (1) Director's foreword; (2) Power plant management; (3) Highlights of 1997; (4) Capital construction; (5) Nuclear safety; (6) Radiation safety; (7) Work safety and health protection at work; (9) Fire protection; (10) Units upgrading - safety measures; (11) Maintenance; (12) Operation; (13) Environmental impacts of operations; (14) List of balances; (15) Human sources; (16) International co-operation; (17) Public relations

  5. Computer analysis of failures in nuclear power station

    International Nuclear Information System (INIS)

    Computer analysis of minor failures at nuclear power plants have been carried out in the Institute for Electrical Power Research (VEIKI) since 1976. The research work was mainly directed to the computer based application of methods to be used at the Paks Nuclear Power Plant; the proposed procedures, however, can also be used at traditional power plants. The paper describes the general aims and main steps of failure analysis and summarizes the state of the art and perspectives of R and D in Hungary. (N.I.)

  6. Use of high-speed separators (MOPS/SCRUPS) at Beznau 1 nuclear power station

    International Nuclear Information System (INIS)

    In nuclear power stations, the circulating steam at the outlet from the high-pressure turbine demonstrates a moisture of 10 to 15% by weight. In the water separators/reheaters, this steam is mechanically dried and then reheated before it reaches the low-pressure turbines. Alternative high-speed separators separate, at an early stage, a large part of the resulting condensate as a constituent of the steam lines and thereby significantly relieve the subsequent main water separator. Using as an example Beznau I Nuclear Power Station (Switzerland), it is shown how such high-speed separators are applied and the advantages they have. (orig.)

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

    International Nuclear Information System (INIS)

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

  8. Risk of loss power for ATWT in Daya Bay and Ling'ao nuclear power stations

    International Nuclear Information System (INIS)

    In order to analyze the differences between the Anticipated Transient Without Reactor Trip (ATWT) and other reactor protection methods, this paper analyzes in detail the realizing means of ATWT and the effect of lost of power supply on the units based on Daya Bay and Ling'ao Nuclear Power Stations by system wiring diagram. Based on the comprehensive analysis,this paper proposes the sequence for powering when recovering the power source after ATWT power supply (LCC/LNE) loss for Daya Bay and Ling'ao Nuclear Power Stations. (authors)

  9. Applicability of JIS SPV 50 steel to primary containment vessels of nuclear power stations

    International Nuclear Information System (INIS)

    The fracture toughness of JIS SPV 50 steel and its weldment has been examined in order to verify the applicability of these materials to primary containment vessels of nuclear power stations. Test results were evaluated using elastic plastic fracture mechanics through the COD and the J integral concepts for non ductile fracture initiation characteristics. Linear fracture mechanics was employed for propagation arrest characteristics. Results showed that the materials tested here have a sufficient fracture toughness to prevent nonductile fracture and that this steel is a suitable material for use in construction of primary containment vessels of nuclear power stations. (author)

  10. Migration and biological effect of radionuclides in forest biogeocenozes of the Chernobyl Nuclear Power Station region

    International Nuclear Information System (INIS)

    The results are presented of radioecological and radiobiological investigations in forest biogeocenozes of the 30 kilometer zone of failure in the Chernobyl Nuclear Power Station. The authors present the quantitative evaluation of the distribution of radionuclei in the main component of the soil-plant layer in landscape areas linked in the drainage flow. The morphophysiological special features and hidden variations of the seeds of certain representatives of woody and herbaceous plants of the 30 kilometer zone of the Chernobyl Nuclear Power Station are determined. 12 refs., 5 figs., 3 tabs

  11. Fire protection devices in the controlled region of GKN nuclear power station

    International Nuclear Information System (INIS)

    In the GKN nuclear power station ('Neckar reactor'), an 805 MW PWR reactor whose start-up is scheduled for the near future, fire protection measures have been realized that go far beyond those realized in other German nuclear power stations until now. One of the main reasons is that the authorities have been sensibilized by a fire in the refuelling cavity during construction and by the Browns Ferry fire and are therefore extremely thorough in their examination. Further subsections have been added to the fire prevention sections in order to provide better quenching devices for potential fire sites. (orig./AK)

  12. A study of condition monitoring systems in nuclear power stations

    International Nuclear Information System (INIS)

    The study is an inventory of the continuously working condition monitoring systems in the Swedish nuclear power plants. Methods for detecting defects on moving components as pumps and valves have been discussed. Figures are given for safety related occurrences and reactor shutdowns. (GBn)

  13. Results of INPO management review of nuclear power stations

    International Nuclear Information System (INIS)

    Managing a nuclear plant might well be the toughest industrial job in the United States today. Everyday, nuclear plant managers must deal with the twin concerns of producing megawatts reliably and protecting the safety of the plant personnel and the public. A nuclear plant manager must possess a combination of special technical and managerial skills to do his job well. He also must be supported fully and actively by his utility's corporate management and organization. For more than five years, INPO teams have observed nuclear plant performance and on-site management. For nearly three years, we have been looking at corporate management support. The authors review the results of these plant and corporate evaluations from a management standpoint. More specifically, they look at two areas: One, how and why INPO evaluates plant performance and plant and corporate management, and two, what INPO evaluators have been during these evaluations. Or, to put it another way, what are the characteristics of good management at the best plants we've visited, and what are the areas for improvement that INPO sees most often

  14. Large steam turbines for nuclear power stations. Output growth prospects

    International Nuclear Information System (INIS)

    The rapid growth of the output of nuclear reactors, even if temporary settlement occurs, leads the manufacturer to evaluate, at a given time, technological limitations encountered. The problems dealing with the main components of turbines: steam path, rotors and stators steam valves, controle devices, shafts and bearings, are reviewed

  15. Deformation resistance of steels for pressure vessels for nuclear power stations

    International Nuclear Information System (INIS)

    The development of nuclear power engineering in Czechoslovakia results in the increase in the number of produced components for nuclear power stations, such as rings, pipe bends, and dished ends produced from low- and high-alloy steels, etc. The systems produced for the VVER 1000 type nuclear power stations are considerably larger than those for VVER 440. The results show that many of these systems must be produced by hot pressing and, because of the dimensions, the initial material must have the form of thick plates or forgings. Pressing is carried out in high-power forging presses, often at the upper limit of the technological possibilities of the existing systems. It is therefore essential to have sufficient data on the strain capacity of the steels used for the production of components for nuclear power stations which can then be used to determine the optimum forming conditions. The components for the nuclear power stations are usually produced from 10GN2MFA low-alloy steel and 08Kh18N10T high-alloy steel. The aim of this work was to determine the mathematical dependences of the deformation resistance of these steels in the thermomechanical conditions in hot deformation. The results of torsion tests were used for this purpose. (author)

  16. Operating experience with the WWER-440/W 230 reactor units of the Greifswald nuclear power station

    International Nuclear Information System (INIS)

    After seventeen years of operation, almost to the day, unit 1 of the Greifswald nuclear power station was shut down in December 1990 as the last of the units still in operation. This step completed the decommissioning of all units as ordered by the authorities. The use of nuclear power for energy generation in the eastern part of Germany, which began when the Rheinsberg nuclear power station was commissioned in 1966, has thus been brought to a temporary end. The Greifswald (4x440 MW) and Rheinsberg (70 MW) nuclear power stations covered an annual average of 10 to 12% of the electricity requirement of the GDR in the past ten years, thus contributing to a stable energy supply over a prolonged period of time. For security reasons of the then GDR government there was hardly any possibility to report about the performance and operating records of the plants in former years. The 1990 press reports consequently were bound to create the impression as if these reactor plants had not been very successful and had been operated at high risk. In order to put these impressions on a more objective base, this report presents important findings made during the operation of the Greifswald nuclear power station and evaluates them. (orig.)

  17. Retrieval of Intermediate Level Waste at Trawsfyndd Nuclear Power Station

    Energy Technology Data Exchange (ETDEWEB)

    Wall, S.; Shaw, I.

    2002-02-25

    In 1996 RWE NUKEM Limited were awarded two contracts by BNFL Magnox Generation as part of the decommissioning programme for the Trawsfynydd power station. From the normal operations of the two Magnox reactors, intermediate level waste (ILW) had accumulated on site, this was Miscellaneous Activated Components (MAC) and Fuel Element Debris (FED). The objective of these projects is retrieval of the waste from storage vaults, monitoring, packaging and immobilization in a form suitable for on site storage in the medium term and eventual disposal to a waste repository. The projects involve the design, supply, commissioning and operation of equipment to retrieve, pack and immobilize the waste, this includes recovery from vaults in both reactor and pond locations and final decommissioning and removal of plant from site after completion of waste recovery.

  18. Importance of safety engineering: the Zwentendorf nuclear power station

    International Nuclear Information System (INIS)

    The biological effects of radiation, especially on the incidence of leukaemia and other cancers, are compared with fatalities due to traffic accidents and other industrial activities. The author comments that absolute safety is unachievable and that aeroplane flights would never take place if absolute prevention of crashes needed to be guaranteed. The safety aspects of the reactor are discussed, with special reference to containment and control room protection. Procedures for dealing with radioactive waste are described, radiation detection systems are listed and, finally, a detailed technical specification for the station is presented, dealing with the light water moderated and cooled boiling water reactor which has 2100 MW thermal output, the coolant pumping system, turbines and with the 700 MW hydrogen cooled alternator. (G.M.E.)

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

    International Nuclear Information System (INIS)

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

  20. Permanent sealing: Valve stuffing boxes in nuclear power stations

    International Nuclear Information System (INIS)

    Water in nuclear powerstations contains up to 2000 ppm of boric acid. If a valve leaks, the boric acid crystallises out around the stuffing box and the packing is destroyed. Replacement is very problematical, particularly because of radiation, takes a long time and is very expensive (possible shutdown). Electricite de France has therefore developed stuffing boxes made of expanding graphite. Before E.d.F. uses a seal permanently in a nuclear powerstation, intensive tests are carried out such as the investigation of dynamic sealing for boric acid solutions at 200 bar and 3000C (JAPET experimental plant), corrosion tests (6 months life test a 3000C and 90 bar) and test of deformation characteristics under pressure and pressure transients. ''Lattygraf E1'', a packing made of expanding graphite, was selected as the best product. The construction and operation are discussed. (DOMA)

  1. Can Belgian nuclear power stations work for longer?

    International Nuclear Information System (INIS)

    In 2008 Paul Magnette, former Minister of Climate and Energy, requested the GEMIX Commission - a team of Belgian and international energy specialists - to examine the energy future of Belgium. Within this framework, it was planned to examine ideal energy mixes to ensure the energy supplies of Belgium, to secure our competitive position and to ensure that environmental and climate objectives are achieved. In the framework of this study, the GEMIX Commission asked SCK-CEN to evaluate the lifetime of the commercial nuclear power plants at Doel and Tihange. In particular, the Commission wanted to know whether it is technically feasible and safe to keep these power plants open for longer than 40 years, the lifetime stipulated in the 2003 Nuclear Energy Extrication Act. The article gives a summary overview of the expert opinion of SCK-CEN to the Gemix Commission.

  2. Health physics training at V.C. Summer Nuclear Station

    International Nuclear Information System (INIS)

    Health Physics training for radiation workers and Health Physics Specialists continues to receive full attention by regulatory agencies such as the NRC and ANI. Guidance for such training continues to develop in a direction which forces utilities to continuously increase the quality and quantity of their Health Physics Training Program. This occurs at a time when our rapidly growing industry is placing greatly increased demands on the available work force of highly trained nuclear workers

  3. Reliability-centered maintenance in nuclear generating stations

    International Nuclear Information System (INIS)

    This paper describes experiences in implementing RCM programs within the nuclear power group. It addresses how this engineered approach provided more direction for predictive maintenance efforts, and a better application of personnel, skills, and limited maintenance dollars. This has resulted in cost savings in terms of plant availability, lessened radiation exposure of staff, and intangibles among other areas. Payback times of such programs are on the level of one year at present

  4. Biological disturbs in thermal and nuclear power stations water supply

    International Nuclear Information System (INIS)

    Biological handicaps have been examinated in the runs pump and heat exchange equipment on the some thermal and nuclear power plant in the Ukraine. It is shown that overgrowing of different system of the water supply by invertebrates, as biological handicap factor, is insignificant. The most essential handicaps arise as a result of hydro transport of biogenic particles through the water-supply system as well as from formation of a bacterial film on heat exchange equipment

  5. System of small nuclear power stations with an appropriate infrastructure

    International Nuclear Information System (INIS)

    The future of human society and that economic situation which will be developed in the world will depend substantially on availability, quantity and quality of energy, a way of its production, and consequently also shares of nuclear energy (NE) in the general balance of manufacture of energy. Showing its attitude to NE, the society now forms not only the future of NE, but also its own future (author)

  6. Review of 12-hour shifts at nuclear generating stations

    International Nuclear Information System (INIS)

    This project reviewed the practice of 12-hour shift work schedules at nuclear power plants, and its relationship to safety. The current literature was examined for information on accidents, fatigue and personal preferences. Interviews with operators and maintainers showed that these groups had attitude and preference differences related to both 12 hour shift schedules and overtime work opportunities. Several factors related to 12-hour schedules were identified which could affect safety, but which have not been adequately considered. (24 refs.)

  7. In situ decommissioning - the radical approach for nuclear power stations

    International Nuclear Information System (INIS)

    In situ decommissioning (ISD) is a radical approach to the disposal of nuclear reactors by burying them on-site beneath a mound of suitable material. The engineering and construction of the mound is dealt with and the selection of suitable material. The radiological impact of leaving radioactive materials on-site is studied and it is concluded that ISD could be a solution for some sites. (Author)

  8. Palo Verde nuclear generating station EASEplus SIMULATE model

    International Nuclear Information System (INIS)

    The Palo Verde on-site reactor engineers have an extremely powerful and accurate tool for quickly predicting the effects of reactor power maneuvers on core axial shape index (ASI) and xenon worth. They can analyze postulated future power maneuvers quickly and supply the reactor operators with valuable predictions without having to consult with the off-site nuclear analysis group. The tool developed by the nuclear analysis group was an advanced nodal code with a graphic user interface (GUI) driver for ease of use. The advanced nodal code used was the Studsvik of America SIMULATE-3 Version 2.20-DSI. This SIMULATE version was compiled for use on a personal computer (PC) with a Definicon Systems' 50-MHz coprocessor board. The GUI face used was Expert-EASE Systems' EASE+SIM3 Version 3.0 pre-/postprocessor. The system was installed on Compaq Deskpro 386/20e PCs located in the control room of each of the three units, in the reactor engineering office, in the nuclear analysis office, and in the control room of the training simulator

  9. Techno-economic study of coupling desalination plant and nuclear power stations

    International Nuclear Information System (INIS)

    This work is an update of the technical and economical feasibility study of coupling a desalination station and a nuclear power plant to fulfil the Tunisian Electricity and fresh water needs in the years beyond 2020. This project also presents an introduction to nuclear safety and risk assessment using probabilistic methods. Furthermore, this work represents a first step in the field of preventive maintenance to avoid incidents that may affect the normal operation of the installations.

  10. Economic results of a joint venture to construct a nuclear power station

    International Nuclear Information System (INIS)

    The paper discusses (1) the incorporation of Guangdong Nuclear Power Joint Venture Co., Ltd by Guangdong Province and Hong Kong jointly to invest in and operate the Guangdong nuclear power station (GNPS); (2) the GNPS project plan and construction progress status; (3) the financing, construction cost and economic results of GNPS, and (4) principles of schedule control and cost control. Some of the data provided in this paper are only estimates, as the project was only recently started. (author). 3 tabs

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

    International Nuclear Information System (INIS)

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

  12. License Amendment Request for Storing Exelon Sister Nuclear Stations Class B/C LLRW in the LaSalle Station Interim Radwaste Storage Facility - 13620

    International Nuclear Information System (INIS)

    Exelon Nuclear (Exelon) designed and constructed an Interim Radwaste Storage Facility (IRSF) in the mid-1980's at LaSalle County Nuclear Station (LaSalle). The facility was designed to store low-level radioactive waste (LLRW) on an interim basis, i.e., up to five years. The primary reason for the IRSF was to offset lack of disposal in case existing disposal facilities, such as the Southeast Compact's Barnwell Disposal Facility in Barnwell, South Carolina, ceased accepting radioactive waste from utilities not in the Southeast Compact. Approximately ninety percent of the Radwaste projected to be stored in the LaSalle IRSF in that period of time was Class A, with the balance being Class B/C waste. On July 1, 2008 the Barnwell Disposal Facility in the Southeast Compact closed its doors to out of- compact Radwaste, which precluded LaSalle from shipping Class B/C Radwaste to an outside disposal facility. Class A waste generated by LaSalle is still able to be disposed at the 'Envirocare of Utah LLRW Disposal Complex' in Clive, Utah. Thus the need for utilizing the LaSalle IRSF for storing Class B/C Radwaste for an extended period, perhaps life-of-plant or more became apparent. Additionally, other Exelon Midwest nuclear stations located in Illinois that did not build an IRSF heretofore also needed extended Radwaste storage. In early 2009, Exelon made a decision to forward Radwaste from the Byron Nuclear Station (Byron), Braidwood Nuclear Station (Braidwood), and Clinton Nuclear Station (Clinton) to LaSalle's IRSF. As only Class B/C Radwaste would need to be forwarded to LaSalle, the original volumetric capacity of the LaSalle IRSF was capable of handling the small number of additional expected shipments annually from the Exelon sister nuclear stations in Illinois. Forwarding Class B/C Radwaste from the Exelon sister nuclear stations in Illinois to LaSalle would require an amendment to the LaSalle Station operating license. Exelon submitted the License Amendment Request

  13. Avian radioecology on a nuclear power station site. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Levy, C.K.; Maletskos, C.J.; Youngstrom, K.A.

    1975-01-01

    A summary of a six-year avian radioecology study at the site of a nuclear power plant in Massachusetts is reported. A completed historical summary is followed by a description of mathematical models developed to calculate the effects on bird body burdens of various changes in environmental radionuclide levels. Examples are presented. Radionuclide metabolism studies in which acute doses of /sup 131/I and /sup 137/Cs were administered to four species of wild birds are presented. Radionuclides were administered both intravenously and orally; no apparent differences in uptake or elimination rates were observed between the two methods.

  14. Avian radioecology on a nuclear power station site. Final report

    International Nuclear Information System (INIS)

    A summary of a six-year avian radioecology study at the site of a nuclear power plant in Massachusetts is reported. A completed historical summary is followed by a description of mathematical models developed to calculate the effects on bird body burdens of various changes in environmental radionuclide levels. Examples are presented. Radionuclide metabolism studies in which acute doses of 131I and 137Cs were administered to four species of wild birds are presented. Radionuclides were administered both intravenously and orally; no apparent differences in uptake or elimination rates were observed between the two methods

  15. Ultrafiltration treatment for liquid laundry wastes from nuclear power stations

    International Nuclear Information System (INIS)

    The authors conduct a comprehensive analysis of the waste constituents--radioactive and organic--of the laundry water resulting from the on-site laundering and decontamination of clothing worn in nuclear power plants. The primary isotope contaminants consist of niobium and zirconium 95, manganese 54, cobalt 60, iron 59, and cesium 134 and 137. A variety of filter and adsorbent materials used in an ultrafiltration process are comparatively tested for their effectiveness in removing not only these isotopes but also the organic contaminants in the process of recycling the water. Those materials consist of copper hexacyanoferrate, polyacrylophosphonic acid, and several metal-polymer complexes

  16. Decommissioning of Fort St. Vrain nuclear generating station

    International Nuclear Information System (INIS)

    In the U.S.A., a licensee can propose decontaminating a nuclear power plant using any of three methods: DECON, SAFSTOR, or ENTOMB. For the Fort St. Vrain reactor, DECON was chosen. According to this option, portions of the facility, containing radioactive contaminants, are dismantled and removed, or else decontaminated, soon after the cessation of power. The work to be done is of three kinds: decontamination and dismantlement of the pre-stressed concrete reactor vessel; decontamination or dismantling of actually or potentially contaminated balance of plant; and site cleanup and final site radiation survey. Each of these elements of the work is discussed

  17. Development of expert evaluation system for advanced nuclear power stations

    International Nuclear Information System (INIS)

    The wheels of the nuclear power industry in China are going to roll on the fast rails soon: It is important to establish an expert evaluation system for optimally selecting new types of NPPs in the future based on scientific evaluation. Under such a background, an expert evaluation system is developed to evaluate Various types of NPPs for the following two decades by taking into account the advices of selected top specialists in Chinese nuclear power industry, and by adopting different evaluation methods. The evaluation system is designed to use the database-MS-SQL Server or Oracle for manipulating experts' knowledge and objective data for scaling NPPs by user-selected evaluation methods for evaluating NPPs. The system includes two subsystems: one is called the Data Management Module and the other called the Evaluation Arithmetic Module. The Data Management Module is used to manage expert knowledge in forms of item marks of the NPPs given by experts of nuclear engineering. The Evaluation Arithmetic Module is used to analyze and deal with the evaluation based on the data in the Database by certain designed evaluation method, and to provide the evaluation results. Based on the users' selection, the evaluation of the NPPs is processed, and the results can be dynamically listed in table or displayed in graphics. So it can be used as a consulting tool to help users make optimal selection of prospective NPPs. The system is developed in architecture of the mixture framework C/S(Client/Server) and B/S(Browse/Server), thus is safe, advanced, extensible and user- friendly. The present system is computer network based, so it can be used not only in personal PC and local network, but also in the Web Server which can be browsed by remote users. To develop such an evaluation system is an initiative R and D project in Chinese nuclear R and D activities. Although the evaluation system is far from perfect, however, the preliminary evaluation results produced by the evaluation

  18. Improvements in instrumentation for neutron control of nuclear power stations

    International Nuclear Information System (INIS)

    A significant effort has been made for some years in instrumentation for controlling nuclear reactors. Indications are given on the change in and development of neutron detectors such as miniature fission ionization chambers and self powered detectors. Information is given on various electronic assemblies: d.c. linear and logarithmic measuring systems, high dynamic measuring systems working by pulse and fluctuation or pulse and current, measurement control and safety reactivity meters, digital processing of the signal, continuous measurement of boron concentration in the water, measuring assemblies of the self powered detectors, general design of the items of equipment and a bibliography

  19. The Temelin nuclear power station project in a changing environment

    International Nuclear Information System (INIS)

    CEZ AG is in the process of building a nuclear power plant in Temelin which is to be equipped with two Russian reactors of the VVER-1000/W-320 type. The first unit is to be commissioned in 1997. The plant was subjected to major design modifications to match Western safety standards. Considerable administrative problems in construction management arose from the country's separation from Russia and the revolutions it experienced. The modifications to the original design also are having a negative impact on the timetable and the budget. (orig.)

  20. A method and installation for reducing radioactive emissions in a nuclear power station

    International Nuclear Information System (INIS)

    The invention relates to an installation for reducing radioactive emissions in a nuclear power station. The radioactive emissions resulting from leakages between the primary and secondary liquids in a steam-generator of a pressurized-water nuclear power-station are reduced by placing a demineralizer in the exhaust of the draining tank and also by sending the draining tank steam towards the condenser. In case of major failures leading to the power station stoppage, an auxiliary turbine is used, the latter being designed for being actuated by the steam derived from the main steam conduit. The auxiliary turbine drives the pumps for pumping the cooling-water intended for the condenser. The steam driving the auxiliary turbine is exhausted towards the condenser, too. Condensed water is returned to the steam generator and is evacuated through the draining tank

  1. San Onofre Nuclear Generating station simulator life cycle

    International Nuclear Information System (INIS)

    This paper reports that the SONGS Unit 2/3 simulator was built by the Singer Link Company and delivered to Southern California Edison in July of 1983. Over the first seven years of its life, the fidelity and capabilities of the SONGS simulator have been substantially increased. The major modifications and upgrades which so far have been implemented into the SONGS 2/3 simulator include: Combustion Engineering's Critical Function Monitoring System upgrade and Qualified Safety Parameter Display System addition. Addition of Wide Range Gas Monitors, Steam Line and Containment High Range Radiation Monitor Cabinet. Gould 32/97-80 Computer and Shared Memory System addition to the 32/77-80 Master/Slave simulator computer configuration. Gould/Ce PACE system Plant Monitoring System upgrade. Singer-Link's Space Time Kinetic Reactor Core Model upgrade. Control Room design Review Board Modification upgrade. Installation of Singer-Link's Simulator Software Support System (S3) on SONGS 32/97-80 computer. Singer-Link-Miles' Reactor Coolant System and Steam Generator RETACT Model and Containment Multinode Model upgrade. Singer-Link-Miles' PC based Advanced Man Machine Interface Instructor Station upgrade. The major software tasks undertaken to provide these enhancements are reviewed in this paper. The authors' presentation focuses on the approach utilized by SCE to: achieve high fidelity and performance with the available computer processing power; and maximize simulation improvements and training features within the available outage times and allocated budget

  2. Cause analysis of cracks in circulating water culvert of Daya Bay Nuclear Power Station

    International Nuclear Information System (INIS)

    In view of the widespread cracks discovered in the reinforced-concrete circulating water culvert of Daya Bay Nuclear Power Station, cause analysis for the cracks is made in terms of construction and design. It is concluded that the cracks mainly resulted from shrinkage and temperature. Corresponding countermeasures are put forward thereafter for reference of similar projects

  3. Idea of computer supervision and control system in electrical system for nuclear power station

    International Nuclear Information System (INIS)

    The author elucidates the necessity and feasibility that computer supervision and control system is used in the electrical system of Nuclear Power Station. It puts forward the idea of electrical equipment control mode, explains and discusses its function, reliability and economy

  4. Ageing and life-time management in nuclear power stations - concept and examples

    International Nuclear Information System (INIS)

    Knowledge, assessment and understanding of phenomena caused by ageing, together with systematic utilization and extension of the technical life-time of components and systems, are of critical importance to the safety and economy of electricity generation in nuclear power stations. Economic use can be optimized by integrated ageing and life-time management; it can also be used to improve performance characteristics. (orig.)

  5. Removal and immobilization of tritium from Ontario hydro's nuclear generating stations

    Energy Technology Data Exchange (ETDEWEB)

    Sood, S.K.; Kveton, O.K.; Sissingh, R.A.P.

    1985-09-01

    Ontario Hydro is constructing a Tritium Removal Facility at its Darlington Nuclear Generating Station. The facility uses the Vapour Phase Catalytic Exchange and Cryogenic Distillation process to remove tritium from heavy water. This paper describes the background and design of Tritium Removal Facility.

  6. The integral lifting of sky-dome of 2RX security cover of nuclear power station

    International Nuclear Information System (INIS)

    The experiences of the integral lifting of sky-dome of 2RX security cover, weighted 170.5 tons, in the second period construction of Qinshan Nuclear Power Station is introduced, especially in four aspects of preparing jobs of lifting, simulating lifting, testing lifting, and formal lifting

  7. Trouble shooting fuel leak at Shika Nuclear Power Station Unit No.2

    International Nuclear Information System (INIS)

    Power Suppression Testing (PST) is recommend for BWR in fuel leak occur. Operation by PST allows to identify leaked fuel bundle, suppresses its power and continue plant operation safely. Shika Nuclear Power Station Unit No.2 (Shika-2) has an experience fuel leak in its 2nd operation cycle, April 2009. This paper describes experience of trouble shooting fuel leak at Shika-2. (author)

  8. Water supply and water treatment plants for the nuclear power station at Stendal

    International Nuclear Information System (INIS)

    The layout of water supply and water treatment plants in the nuclear power station being erected at Stendal is presented. Modern procedures of two-component filtration and ion exchange in a fixed bed will be used. The step-wise manner of construction ensures the introduction of the latest scientific and technological progress when the plants have to be extended

  9. Application and discussion of charging pump decontamination for pressurized water reactor nuclear power station

    International Nuclear Information System (INIS)

    This paper reports the process of charging pump decontamination during the refueling outage of nuclear power station. The phenomena and results of Martensite stainless steel decontamination were discussed and analyzed. By summarizing the successful experience of decontamination, some suggestions for future work were offered. (authors)

  10. The Italian nuclear power station at Alto Lazio using the 'Doka' construction technique

    International Nuclear Information System (INIS)

    The firm Doka with 15 years of experience in the construction of nuclear power stations have succeeded in providing an efficient systematic building programme. To optimise the duration of the building programme, which is detailed, the construction company have employed modern control and monitoring techniques. The problems posed by this project are discussed in some detail. (G.W.)

  11. 75 FR 9619 - South Carolina Electric & Gas Company; Virgil C. Summer Nuclear Station; Environmental Assessment...

    Science.gov (United States)

    2010-03-03

    ... COMMISSION South Carolina Electric & Gas Company; Virgil C. Summer Nuclear Station; Environmental Assessment..., issued to South Carolina Electric & Gas Company (SCE&G, the licensee), for operation of the Virgil C... radiological hazard beyond those previously analyzed in the Final Environmental Statement for the Virgil...

  12. 75 FR 36700 - Exelon Generation Company, LLC; Three Mile Island Nuclear Station, Unit 1; Environmental...

    Science.gov (United States)

    2010-06-28

    ... Island Nuclear Station, Unit 1 (TMI-1), located in Dauphin County, Pennsylvania. Therefore, as required... accordance with its stated policy, on March 29, 2010, the NRC staff consulted with the Pennsylvania State official, Dennis Dyckman, of the Pennsylvania State Department of Environmental Protection, regarding...

  13. Return flow of experience from operating and maintenance work in the Biblis nuclear power station

    International Nuclear Information System (INIS)

    The return flow of experience is discussed on the basis of the KTA1401 regulations. An exchange of information is produced by attendance at external and internal committees. Details of the operating and organisation manual of the Biblis nuclear power station are presented. The return flow of experience from maintenance orders and plant damage statistics are other topic covered in this article. figs

  14. Observed radioactive materials in rain water after accident of the Fukushima Daiichi Nuclear Power Station

    International Nuclear Information System (INIS)

    On March 11, 2011, Fukushima Daiichi Nuclear Power Station had been damaged by massive earthquake and huge tsunami, named as 'The 2011 earthquake off the Pacific coast of Tohoku'. A lot of radioactive materials were released from the power station into the environment. In order to observe radioactive materials and those fluctuations, rain water was measured by using gamma-ray spectrometer. 134Cs, 136Cs, 137Cs, 131I, 132I, 133I, 129mTe, 132Te, 133Xe, 140Ba, and 140La were observed in the collected rain water at Tokai-mura which is located at 100-km in the south of the power station. The release of radioactive materials from the power station into the atmosphere has not been observed since April 11 as a result of measuring the fluctuation for radioactivity of 137Cs that is a typical radioactive material. (author)

  15. The update of the Fukushima Daiichi Nuclear Station accident. March 11 through May 31, 2011

    International Nuclear Information System (INIS)

    The unprecedentedly massive earthquake and tsunami hit the Fukushima Daiichi Nuclear Power Station (the Fukushima Daiichi), operated by Tokyo Electric Power Company (TEPCO), in Fukushima Prefecture on March 11, 2011. Two months later TEPCO revealed that No.1, 2 and 3 reactors had melted at the level 7 on the rank of International Nuclear and Radiological Events (INES) scale, as par with the Chernobyl accident in 1986. Complexities of the Fukushima Daiichi's fiasco have grappled with those of question including nuclear safety standard, reactor and backup safety technology, radioactive disaster and contamination on land and at sea, spread of false rumors at home and abroad and also nuclear governance risks. The accident is a huge challenge we have to deal with immediately. A ground-breaking public awareness embraces fundamental change in nuclear world. Foremost rethinking is required to combine a smaller or zero growth of nuclear electricity with a safer world in the future. (author)

  16. 78 FR 48724 - Virgil C. Summer Nuclear Station, Units 2 and 3; South Carolina Electric and Gas; Change to the...

    Science.gov (United States)

    2013-08-09

    ..., 2013 (78 FR 14126). The supplements had no effect on the no significant hazards consideration... COMMISSION Virgil C. Summer Nuclear Station, Units 2 and 3; South Carolina Electric and Gas; Change to the... operation of the Virgil C. Summer Nuclear Station (VCSNS), Units 2 and 3 located in Fairfield County,...

  17. 75 FR 12312 - South Carolina Electric and Gas Company; Virgil C. Summer Nuclear Station, Unit 1; Exemption

    Science.gov (United States)

    2010-03-15

    ... published in the Federal Register on March 3, 2010 (75 FR 9619). This exemption is effective upon issuance... COMMISSION South Carolina Electric and Gas Company; Virgil C. Summer Nuclear Station, Unit 1; Exemption 1.0... Operating License No. NPF-12 which authorizes operation of the Virgil C. Summer Nuclear Station, Unit...

  18. 78 FR 41117 - Virgil C. Summer Nuclear Station, Units 2 and 3; South Carolina Electric and Gas; Change to...

    Science.gov (United States)

    2013-07-09

    ... 13, 2012 (77 FR 67679). The supplements had no effect on the no significant hazards consideration... COMMISSION Virgil C. Summer Nuclear Station, Units 2 and 3; South Carolina Electric and Gas; Change to... Cooper) (the licensee), for construction and operation of the Virgil C. Summer Nuclear Station...

  19. 78 FR 63504 - Virgil C. Summer Nuclear Station, Units 2 and 3; South Carolina Electric and Gas; Changes to the...

    Science.gov (United States)

    2013-10-24

    ... hearing in connection with these actions, was published in the Federal Register on March 4, 2013 (78 FR... COMMISSION Virgil C. Summer Nuclear Station, Units 2 and 3; South Carolina Electric and Gas; Changes to the... Cooper) (the licensee), for construction and operation of the Virgil C. Summer Nuclear Station...

  20. 78 FR 47426 - Virgil C. Summer Nuclear Station, Units 2 and 3; South Carolina Electric and Gas; Change to the...

    Science.gov (United States)

    2013-08-05

    ... 16, 2012 (77 FR 63343). The supplement had no effect on the no significant hazards consideration... COMMISSION Virgil C. Summer Nuclear Station, Units 2 and 3; South Carolina Electric and Gas; Change to the... Virgil C. Summer Nuclear Station (VCSNS), Units 2 and 3 located in Fairfield County, South Carolina....

  1. 77 FR 21593 - V. C. Summer Nuclear Station, Units 2 and 3 Combined Licenses and Record of Decision

    Science.gov (United States)

    2012-04-10

    ... Evaluation Report for Combined Licenses for Virgil C. Summer Nuclear Station, Units 2 and 3'' ML11098A044 NUREG-1939, Vol 1, ``Final Environmental Impact Statement for Combined Licenses for Virgil C. Summer... Combined Licenses for Virgil C. Summer Nuclear Station, Units 2 and 3'' ML11187A127 VCSNS COL...

  2. 75 FR 10839 - South Carolina Electric and Gas Company; Virgil C. Summer Nuclear Station, Unit 1; Exemption

    Science.gov (United States)

    2010-03-09

    ... environment 75 FR 8756; dated February 25, 2010. This exemption is effective upon issuance. Dated at Rockville... COMMISSION South Carolina Electric and Gas Company; Virgil C. Summer Nuclear Station, Unit 1; Exemption 1.0... License No. NPF-12, which authorizes operation of the Virgil C. Summer Nuclear Station, Unit 1...

  3. The new 1500 MW turbine 'Arabelle' for nuclear power stations

    International Nuclear Information System (INIS)

    In France's nuclear programme a new design series of 1500 MW units is following the series of 900 MW and 1300 MW units. The turbine for this unit has been developed by building on experience accumulated hitherto, with particular reference to economic operation, ease of maintenance and operational security: optimization of the steam channel by sub-division into single-flow high and intermediate pressure sections (arranged together in one casing); low pressure turbine with reduced number of stages; last stage blades fitted with support vanes; no fixed connection between low pressure internal and external casing; inlet valves stabilized by protective shields. These designs involve, for the manufacturer and operator, few foundation and building costs, improved economy in operation and greater operational security. (orig.)

  4. Our response to the earthquake at Onagawa Nuclear Power Station

    International Nuclear Information System (INIS)

    When the Miyagi Offshore earthquake occurred on August 16, 2005, all three units at the Onagawa NPS were shut down automatically according to the Strong Seismic Acceleration' signal. Our inspection after the earthquake confirmed there was no damage to the equipment of the nuclear power plants, but the analysis of the response spectrum observed at the bedrock showed the earthquake had exceeded the 'design-basis earthquake', at certain periods, so that we implemented a review of the seismic safety of plant facilities. In the review, the ground motion of Miyagi Offshore Earthquake which are predicted to occur in the near future were reexamined based on the observation data, and then 'The Ground Motion for Safety Check' surpassing the supposed ground motion of the largest earthquake was established. The seismic safety of plant facilities, important for safety, was assured. At present, No.1 to No.3 units at Onagawa NPS have returned to normal operation. (author)

  5. Childhood cancer mortality in relation to the St Lucie nuclear power station

    International Nuclear Information System (INIS)

    An unusual county-wide excess of childhood cancers of brain and other nervous tissue in the late 1990s in St Lucie County, Florida, prompted the Florida Department of Health to conduct a case-control study within the county assessing residential chemical exposures. No clear associations were found, but claims were then made that the release of radioactive substances such as strontium 90 from the St Lucie nuclear power station, which began operating in 1976, might have played a role. To test the plausibility of this hypothesis, we extended by 17 years a previous study of county mortality conducted by the National Cancer Institute. Rates of total cancer, leukaemia and cancer of brain and other nervous tissue in children and across all ages in St Lucie County were evaluated with respect to the years before and after the nuclear power station began operation and contrasted with rates in two similar counties in Florida (Polk and Volusia). Over the prolonged period 1950-2000, no unusual patterns of childhood cancer mortality were found for St Lucie County as a whole. In particular, no unusual patterns of childhood cancer mortality were seen in relation to the start-up of the St Lucie nuclear power station in 1976. Further, there were no significant differences in mortality between the study and comparison counties for any cancer in the time period after the power station was in operation. Relative rates for all childhood cancers and for childhood leukaemia were higher before the nuclear facility began operating than after, while rates of brain and other nervous tissue cancer were slightly lower in St Lucie County than in the two comparison counties for both time periods. Although definitive conclusions cannot be drawn from descriptive studies, these data provide no support for the hypothesis that the operation of the St Lucie nuclear power station has adversely affected the cancer mortality experience of county residents

  6. Technology, Safety and Costs of Decommissioning Nuclear Reactors At Multiple-Reactor Stations

    Energy Technology Data Exchange (ETDEWEB)

    Wittenbrock, N. G.

    1982-01-01

    Safety and cost information is developed for the conceptual decommissioning of large (1175-MWe) pressurized water reactors (PWRs) and large (1155-MWe) boiling water reactors {BWRs) at multiple-reactor stations. Three decommissioning alternatives are studied: DECON (immediate decontamination), SAFSTOR (safe storage followed by deferred decontamination), and ENTOMB (entombment). Safety and costs of decommissioning are estimated by determining the impact of probable features of multiple-reactor-station operation that are considered to be unavailable at a single-reactor station, and applying these estimated impacts to the decommissioning costs and radiation doses estimated in previous PWR and BWR decommissioning studies. The multiple-reactor-station features analyzed are: the use of interim onsite nuclear waste storage with later removal to an offsite nuclear waste disposal facility, the use of permanent onsite nuclear waste disposal, the dedication of the site to nuclear power generation, and the provision of centralized services. Five scenarios for decommissioning reactors at a multiple-reactor station are investigated. The number of reactors on a site is assumed to be either four or ten; nuclear waste disposal is varied between immediate offsite disposal, interim onsite storage, and immediate onsite disposal. It is assumed that the decommissioned reactors are not replaced in one scenario but are replaced in the other scenarios. Centralized service facilities are provided in two scenarios but are not provided in the other three. Decommissioning of a PWR or a BWR at a multiple-reactor station probably will be less costly and result in lower radiation doses than decommissioning an identical reactor at a single-reactor station. Regardless of whether the light water reactor being decommissioned is at a single- or multiple-reactor station: • the estimated occupational radiation dose for decommissioning an LWR is lowest for SAFSTOR and highest for DECON • the estimated

  7. Measures to ensure the possibility of future heat supply from the Kaiseraugst Nuclear Power Station

    International Nuclear Information System (INIS)

    The present paper demonstrates which measures need to be taken in such a case when the utilization of nuclear heat is envisaged, but will become possible only many years after the construction of a nuclear power plant, in this case the Kaiseraugst reactor on the border of Switzerland and Germany. It has been shown that it is reasonable to assure the future possibility of long distance heat supply from the reactor. The necessary preliminary investment for this nuclear station presently being built is small as compared with the plants total investment. (M.S.)

  8. Seismic risk assessment as applied to the Zion Nuclear Generating Station

    International Nuclear Information System (INIS)

    To assist the US Nuclear Regulatory Commission (NRC) in its licensing and evaluation role, the NRC funded the Seismic Safety Margins Research Program (SSMRP) at Lawrence Livermore National Laboratory (LLNL) with the goal of developing tools and data bases to evaluate the risk of earthquake caused radioactive release from a commercial nuclear power plant. This paper describes the SSMRP risk assessment methodology and the results generated by applying this methodology to the Zion Nuclear Generating Station. In addition to describing the failure probabilities and risk values, the effects of assumptions about plant configuration, plant operation, and dependence will be given

  9. Fire protection equipment in the area of control of the Neckar Community Nuclear Power Station

    International Nuclear Information System (INIS)

    In the Neckar Community Nuclear Power Station - an 805 MW pressurised water reactor shortly to reach the stage of nuclear operation - fire protection measures have been realised to an extent hitherto uncommon in German nuclear power plants. The reason is to be sought from the authorities who have become more sensitive because of a fire in a reactor vessel during the construction stage and the fire at Browns Ferry and have consequently become extremely expert. Apart from the fire regulations hitherto normal further subregulations have been created in order to be able to make better provision of extinguishing devices against fire hazards. (orig.)

  10. Sodium coolant purification systems for a nuclear power station equipped with a BN-1200 reactor

    Science.gov (United States)

    Alekseev, V. V.; Kovalev, Yu. P.; Kalyakin, S. G.; Kozlov, F. A.; Kumaev, V. Ya.; Kondrat'ev, A. S.; Matyukhin, V. V.; Pirogov, E. P.; Sergeev, G. P.; Sorokin, A. P.; Torbenkova, I. Yu.

    2013-05-01

    Both traditional coolant purification methods (by means of traps and sorbents for removing cesium), the use of which supported successful operation of nuclear power installations equipped with fast-neutron reactors with a sodium coolant, and the possibility of removing oxygen from sodium through the use of hot traps are analyzed in substantiating the purification system for a nuclear power station equipped with a BN-1200 reactor. It is shown that a cold trap built into the reactor vessel must be a mandatory component of the reactor plant primary coolant circuit's purification system. The use of hot traps allows oxygen to be removed from the sodium coolant down to permissible concentrations when the nuclear power station operates in its rated mode. The main lines of works aimed at improving the performance characteristics of cold traps are suggested based on the results of performed investigations.

  11. Swedish approaches to radiation protection at nuclear power stations

    International Nuclear Information System (INIS)

    This paper compares Swedish health physics programs at nuclear power plants to U.S. programs. Analysis of the Swedish programs includes examination of health physics staff training, size and longevity. Health physics practices are discussed, especially practices during refueling outages. The paper is based on site visits to Ringhals and Oskarshamn by U.S. radiation protection managers in October, 1995, under the sponsorship of the North American Regional Technical Center, ISOE, NEA/IAEA. The reactor vessel decontamination at Oskarshamn 1 BWR is discussed including good health physics practices and radiological results. Ringhals unique management organization is discussed with respect to health physics division of responsibilities and differences between in-plant and on-site health physics groups. Analytical results of failed fuel events at Ringhals is also presented including the observed occurrence of cobalt knock-off. Finally, trends in Swedish plants collective doses are summarized. Comprehensive Swedish studies of potential collective doses over the next 20 years are discussed including management options related to dose reduction options

  12. Development of cables for nuclear power generating station

    International Nuclear Information System (INIS)

    Results of LOCA simulation test and vertical tray combustion test of cables for nuclear power plant are reported. Radiation resistance of polyethylene, crosslinked polyethylene and ethylene-propylene (EP) rubber was tested. The crosslinked polyethylene and the ethylene-propylene rubber showed a good resistance. The first step heat aging temperature was determined as 1500C-3 days for 800C-40 years of ethylene-propylene rubber by Arrhenius's method in the case of PWR, and determined by the method specified in IPCEA-S-66-524 in the case of BWR. The irradiation test was performed at about 0.7 x 106 Rad/hr with Co-60 gamma radiations. Deterioration of elongation of EP rubber, flame retarded EP rubber and silicon rubber after irradiation in the test of PWR was very large, but they could resist to bending test, so there seemed no problem for practical use. Silicon rubber for sheath cracked at bending test. Flame retarded chlorosulfonpolyethylene showed better characteristics than the flame retarded chloroprene rubber. In the vertical tray test, the conventional cables burned after 5 to 6 minutes, but the flame retarded cables was not burned. In the LOCA test, a simultaneous testing of both irradiation and high temperature-high pressure exposure is desired. (Iwakiri, K.)

  13. Steam generator management at Ontario Hydro Nuclear Stations

    Energy Technology Data Exchange (ETDEWEB)

    Nickerson, J. [Atomic Energy of Canada Limited, Mississauga, Ontario (Canada); Maruska, C.C. [Ontario Hydro, Toronto, Ontario (Canada)

    1998-07-01

    Managing ageing steam generators involves costly decisions for the utility, both in terms of the cost of the maintenance activities andin terms of having the unit shutdown and consequent power loss while performing these activities. The benefits of these activities are seldom guaranteed and are sometimes very intangible. For nuclear utilities the most pertinent questions that arise are have we identified all the problem(s), can we predict the risk due to these problems? Can we implement corrective and preventive activities to manage the problem and what is the optimum timing of implementation? Is the money spent worthwhile, i.e. has it given us a return in production and safety? Can we avoid surprises? How can we tangibly measure success? This paper touches briefly on all the questions mentioned above but it mainly addresses the last question: 'how can we tangibly measure success?' by using several success indicators proposed by EPRI and by applying them to actual Ontario Hydro experience. The appropriateness of these success indicators as the means to assess the success of these programs, to feed back the results, and to enhance or revise the programs will be discussed. (author)

  14. Computer-based systems for nuclear power stations

    International Nuclear Information System (INIS)

    The published intentions of vendors are for extensive touch-screen control and computer-based protection. The software features needed for acceptance in the UK are indicated. The defence in depth needed is analyzed. Current practice in aircraft flight control systems and the software methods available are discussed. Software partitioning and mathematically formal methods are appropriate for the structures and simple logic needed for nuclear power applications. The potential for claims of diversity and independence between two computer-based subsystems of a protection system is discussed. Features needed to meet a single failure criterion applied to software are discussed. Conclusions are given on the main factors which a design should allow for. The work reported was done for the Health and Safety Executive of the UK (HSE), and acknowledgement is given to them, to NNC Ltd and to GEC-Marconi Avionics Ltd for permission to publish. The opinions and recommendations expressed are those of the authors and do not necessarily reflect those of HSE. (Author)

  15. V. C. Summer Nuclear Station steam generator replacement

    International Nuclear Information System (INIS)

    The Virgil C. Summer Steam Generator Replacement Project involved the first-ever replacement of an existing steam generator with a different and later vintage component from the original equipment manufacturer (OEM), in this case Westinghouse Model Delta-75 steam generators to replace Westinghouse Model D-3 steam generators, which had been plaguing South Carolina Electric and Gas Company's (SCE and G) Virgil C. Summer Nuclear Plant since shortly after initial operation in 1982. This project also involved the first use of laser metrology technology for steam generator-to-reactor coolant system severance cutting, machining, and component fitup and the first use of an impregnated sponge blast media for reactor coolant system pipe end decontamination. The sequence of events leading to the decision to replace steam generators and during the replacement process is described. Intensive planning and teamwork, combined with input from SCE and G and the use of mockups to train the work force in a simulated radiological environment, were instrumental in achieving world-record schedule performance and setting a new US record for the lowest accumulated radiation exposure during a steam generator replacement project while completing the project without a single lost workday case incident

  16. Steam generator management at Ontario Hydro Nuclear Stations

    International Nuclear Information System (INIS)

    Managing ageing steam generators involves costly decisions for the utility, both in terms of the cost of the maintenance activities and in terms of having the unit shutdown and consequent power loss while performing these activities. The benefits of these activities are seldom guaranteed and are sometimes very intangible. For nuclear utilities the most pertinent questions that arise are have we identified all the problem(s), can we predict the risk due to these problems? Can we implement corrective and preventive activities to manage the problem and what is the optimum timing of implementation? Is the money spent worthwhile, i.e. has it given us a return in production and safety? Can we avoid surprises? How can we tangibly measure success? This paper touches briefly on all the questions mentioned above but it mainly addresses the last question: 'how can we tangibly measure success?' by using several success indicators proposed by EPRI and by applying them to actual Ontario Hydro experience. The appropriateness of these success indicators as the means to assess the success of these programs, to feed back the results, and to enhance or revise the programs will be discussed. (author)

  17. The Wm. H. Zimmer Nuclear Power Station: Draft environmental statement (Docket No. 50-358)

    International Nuclear Information System (INIS)

    The proposed action is the issuance of an operating license to the Cincinnati Gas and Electric Company, the Columbus and Southern Ohio Electric Company, and the Dayton Power and Light Company for the startup and operation of the Wm. H. Zimmer Nuclear Power Station (Docket No. 50-358) (the station), located on the Ohio River in Clermont County, about 24 miles southeast of Cincinnati, Ohio. The information in this statement represents the second assessment of the environmental impact associated with the Zimmer Nuclear Power Station pursuant to the guidelines of the National Environmental Policy Act of 1969 (NEPA) and 10 CFR Part 51 of the Commission's Regulations. After receipt of an application in 1970 to construct this plant, the staff carried out a review of impact that would occur during the plant's construction and operation. This evaluation was issued as a final environmental statement in September 1972. As the result of this environmental review, a safety review, an evaluation by the Advisory Committee on Reactor Safeguards, and a public hearing in Cincinnati, Ohio, the AEC (now NRC) issued a permit in October 1972 for the construction of Unit 1 of the Zimmer Nuclear Power Station. As of June 1976, the construction of the plant was 54% complete. With a proposed fuel-loading data of April 1978, the applicant has petitioned for license to operate Unit 1 and has submitted (September 1975) the required safety and environmental reports to substantiate this petition. 96 refs., 17 figs., 34 tabs

  18. Operating experience with the Fort St. Vrain Nuclear Power Station

    International Nuclear Information System (INIS)

    Since entering into commercial operation in 1979, the 330 MW(e) Fort St. Vrain HTGR has performed increasingly well, and it is now demonstrating the real promise of this advanced reactor type. As of this writing, the plant has operated routinely at 70% power with 38% thermal efficiency, the highest nuclear plant efficiency in the United States of America, and has generated over 2,500,000 MW.h of electricity. Monthly availability factors have reached 99%. The plant has operated in a testing mode over 90% power and reached full power on 6 November 1981. Fuel performance has continued to exceed expectations and the second refuelling was carried out in 1981 (the first was in 1979). Radioactivity levels in the helium coolant and around the plant are very low. Personnel exposure during 1979-80, computed on a unit electricity generated basis, was a few per cent of the average exposure at LWR plants. This paper reviews the lessons learned during the startup and first five years of operation of Fort St. Vrain, including core behaviour, fuel handling, helium coolant cleanup, primary system and balance-of-plant component and systems operation, and plant operation and maintenance experience. In addition, the ways in which the new regulations resulting from the accident at Three Mile Island have been implemented in this HTGR plant are described. Public Service Co. of Colorado and General Atomic Co. have, through Fort St. Vrain, generated a large base of experience in HTGR technology that can be applied to future projects in the United States and elsewhere. (author)

  19. Implications of Extension of Station Blackout Cooping Capability on Nuclear Power Plant Safety

    International Nuclear Information System (INIS)

    The safety of the nuclear power plant depends on the availability of the continuous and reliable sources of electrical energy during all modes of operation of the plant. The station blackout corresponds to a total loss of all alternate current (AC) power as a result of complete failure of both offsite and on-site AC power sources. The electricity for the essential systems during station blackout is provided from the batteries installed in the nuclear power plant. The results of the probabilistic safety assessment show that station blackout is one of the main and frequently the dominant contributor to the core damage frequency. Results of the analysis of the implications of the strengthening of the SBO mitigation capability on safety of the NPP will be presented. The assessment is done with state-of-art deterministic and probabilistic methods and tolls with application on reference models of nuclear power plants. The safety analysis is done on reference model of the nuclear power plant. Obtained results show large decrease of the core damage frequency with strengthening of the station blackout mitigation capability. The time extension of blackout coping capability results in the delay of the core heat up for at least the extension time interval. Availability and operation of the steam driven auxiliary feedwater system maintains core integrity up to 72 h after the successful shutdown, even in the presence of the reactor coolant pumps seal leakage. The largest weighted decrease of the core damage frequency considering the costs for the modification is obtained for the modification resulting in extension of the station blackout coping capability. The importance of the common cause failures of the emergency diesel generators for the obtained decrease of the core damage frequency and overall safety of the plant is identified in the obtained results. (authors)

  20. The applicability of nuclear engineering safety principles and criteria to thermal-electric generation stations generally

    International Nuclear Information System (INIS)

    The consistently high capacity factors for the Pickering Generating Station provide solid evidence of sound engineering and high quality of component manufacture, construction, maintenance and operation. The achievement of this high level of performance is due to a number of contributing factors, one of which is the observance of the nuclear safety principles and criteria developed over the last two decades. The application of these principles and of the relevant criteria to thermal-electric stations generally would appear to be worthy of serious consideration. (author)

  1. A sensitive structure on rocks of the Tygerberg formation: Koeberg nuclear power station

    International Nuclear Information System (INIS)

    Koeberg Nuclear Power Station is located on the beach at Duynefontein near Melkbosstrand, some 25 km from Cape Town. Investigations of the bedrock underlying the beach sands were undertaken at various stages in order (1) to assess the feasibility of constructing intake tunnels to bring cooling water from the offshore intake towers, (2) to assess the potential for surface movement at the site due to faulting following the historical records of seismic events in the region, and (3) to provide data on the dynamic response characteristics of the near-surface bedrock for use in the seismic response analysis for the power station

  2. AECB staff annual assessment of the Bruce B Nuclear Generating Station for the year 1995

    International Nuclear Information System (INIS)

    This report is the Atomic Energy Control Board (AECB) staff assessment of reactor safety at the Bruce Nuclear Generating Station B for 1995. Our on-site Project Officers and Ottawa-based specialists monitored the station during the year. AECB staff conclude that Ontario Hydro operated Bruce B safely in 1995. Radiation doses to workers and the public were well below the legal limits and remained well within Ontario Hydro's internal targets. Worker radiation doses increased slightly but were comparable to previous years. 7 tabs., 3 figs

  3. Preparing for the future by improving the performance of today's nuclear stations: The WANO perspective

    International Nuclear Information System (INIS)

    The World Association of Nuclear Operators, (WANO) was established in 1989 in the aftermath of the Chernobyl accident with the mission of maximizing the safety and reliability of nuclear power plants by exchanging information and encouraging communication, comparison and emulation among its members. All nuclear power stations in the world are WANO members. WANO conducted an Internal Review in 1997 and its report issued this January confirms that the WANO mission is still valid. As a result of the Internal Review, WANO is taking actions to further improve its programmes. WANO's effort to keep members conscious of safety culture in their daily work at plants is a key element for improving operational safety. WANO will be able to contribute to the future of the nuclear industry by encouraging members to actively participate in WANO programmes which are aimed at improving nuclear safety and plant performance. (author)

  4. Nuclear stations: a sufficient safety standard and no demand for immediate outage, according to ASN

    International Nuclear Information System (INIS)

    The complementary safety assessments (CSA) that have been made for each nuclear station have shown, according to the ASN (French Nuclear Safety Authority), first that all nuclear power plants have a sufficient safety standard and secondly that some solutions exist to increase the safety margin. The ASN proposes: -) the setting of new measures, adapted to each nuclear plant for assuring the basic safety requirements in case of extreme situations as described in CSA; -) the setting of a force made of qualified teams and equipment to intervene on a nuclear accident very quickly; -) the reinforcing of dispositions for avoiding the dewatering of fuels in spent fuel pools; -) the carrying out of feasibility studies for reinforcing the protection of underground and surface waters in case of a major accident. (A.C.)

  5. A survey of the development of Nuclear Power Stations in Asia

    International Nuclear Information System (INIS)

    Thanks to its direct correlation with economic development, the power industry has got a boost in the Asian countries. The development of the power industry in Asia hinges predominantly on the construction of nuclear power stations. The capacity of nuclear plants is expected to reach to 51-67 gigawatts in 2010, compared with 22.5 gigawatts in 1999. As the nuclear technology is supplied by the Western economies especially the US, Canada and France, the construction of new nuclear plants would make the Asian states even more dependant on the Western nations. It seems the willingness of the western countries in providing nuclear power technology to the Asian states, among other factors stems from their ambition of controlling price and supply of oil and gas in the region. This is actually a threat to the fossil fuel holders

  6. Standardization of the method of evaluating aseismatic capability of the ground for nuclear power stations

    International Nuclear Information System (INIS)

    As for the ground for nuclear power stations, it is required to carry out high reliable construction based on the analysis and design by detailed investigation and test and reliable procedure. The fundamental policy is shown in ''Guide for aseismatic design examination regarding power reactor facilities'' decided by Japan Society of Civil Engineers, and ''Guide for safety examination regarding geological features and ground for nuclear power stations'' decided by the Committee on Examination of Nuclear Reactor Safety. However, geological features and ground are diverse, accordingly, it is significant to systematize the relation among investigation, test, analysis, evaluation, design and construction for the works of civil engineers and for obtaining the understanding and trust of people. The Ground Subcommittee was organized in September, 1979, and concluded the examination in March, 1984. The result is ''Method of investigation and test of geological features and ground, and method of evaluating aseismatic stability of ground for nuclear power stations''. The contents are general remarks, the method of investigating geological features, the method of investigating and testing ground, and the method of evaluating aseismatic stability of foundation ground for reactor buildings, surrounding slopes and important outdoor structures. (Kako, I.)

  7. Electrical system design and reliability at Ontario Hydro nuclear generating stations

    International Nuclear Information System (INIS)

    This paper provides an overview of design practice and the predicted and actual reliability of electrical station service Systems at Ontario Nuclear Generating Stations. Operational experience and licensing changes have indicated the desirability of improving reliability in certain instances. For example, the requirement to start large emergency coolant injection pumps resulted in the turbine generator units in a multi-unit station being used as a back-up power supply. Results of reliability analyses are discussed. To mitigate the effects of common mode events Ontario Hydro adopted a 'two group' approach to the design of safety related Systems. This 'two group' approach is reviewed and a single fully environmentally qualified standby power supply is proposed for future use. (author)

  8. Man-machine interface systems for the Sizewell B Nuclear Power Station

    International Nuclear Information System (INIS)

    Sizewell B is the first nuclear power station to be built in the United Kingdom using the Pressurised Water Reactor or PWR system. The design is based on stations operating in the United States, but many changes and new features have been introduced to bring it up to date, and to meet United Kingdom practice and regulatory requirements. The Man-Machine Interfaces (MMIs) in the control rooms have been newly designed from first principles, with special attention paid to human factors and the role of the operators. The instrumentation and control (1 and C) systems which interface the MMIs to the process plant, and automate the operation of the station, use advanced technology to achieve high performance and availability. This paper describes the development of the control rooms and 1 and C systems, explaining the thinking that lay behind the principal decisions. (author)

  9. Accumulation of 137Cs in commercial fish of the Belyarsk nuclear power station cooling supply

    International Nuclear Information System (INIS)

    Results are presented of a comparative study of the accumulation of 137Cs in basic species of commercial fish of the Beloyarsk reservoir which is used as the cooling supply for the Beloyarsk nuclear power station. Possible reasons for interspecies differences in accumulation of the radionuclide are indicated, and the increased accumulation of 137Cs by free-living fish in the zone of heated water effluent from the station and the reduced accumulation of the emitter in carp, which are cultivated on artificial food in cages, are noted. Levels of the content of the radionuclide are compared in roach and farm carp from the cooling supplies of the Beloyarsk station and the Reftinsk power plant in the Urals

  10. Results of environmental radioactivity surveys around the Onagawa Nuclear Power Station

    International Nuclear Information System (INIS)

    The results, i.e. nuclide analysis data, of environmental radioactivity surveys carried out around the Onagawa Nuclear Power Station of Tohoku Electric Power Co., Inc., from October, 1981, to December, 1982, are presented in tables; fallout, airborne dust, land water (source water for water service), soil, agricultural products (Japanese radish, rice), index plants (white Dutch clover, mugwort), seawater, sea-bottom deposit, fishes and shellfishes (rock trout, ear shell, ascidian, oyster), index marine products (gulfweed, edible seaweed, purplish Washington clan) seaweed (wakame seaweed) were examined. The Onagawa Nuclear Power Station is in the stage of construction at present, as of March, 1983, therefore, the data are for grasping the background levels in the areas concerned. For this same purpose, certain samples were also taken from other localities in Miyagi Prefecture. (Mori, K.)

  11. The operator's environmental monitoring programme for the Grohnde nuclear power station

    International Nuclear Information System (INIS)

    In accordance with the BMI 'Guiding rules for emission and immission monitoring of nuclear installations', a two-year measuring programme has been carried out prior to commissioning of the plant. Since the first initiation of the self-sustaining chain reaction in the power reactor, the legally required monitoring programmes for normal operation and as a precautionary measure against incidents are carried out. The monitoring programme for the area close to the installation, which is under the responsibility of the operator, uses fixed equipment in three measuring stations, mobile equipment available in a car, and also includes according to the tasks stated in the loose-leaf collection of remote monitoring tasks, the sampling of environmental material and sample measurement in external laboratories. The measured data recorded so far are within the scope of natural environmental radioactivity and there are no data indicating an artificial increase of environmental radioactivity due to the operation of the nuclear power station. (orig./PW)

  12. Optimization and analysis of main coolant pump decontamination schemes in Tianwan Nuclear Power Station

    International Nuclear Information System (INIS)

    The overhaul of main coolant pumps (MCP) is one of important work during the general overhaul of nuclear power station, and the main measure taken to reduce collective dose is to decontaminate the hydraulic component of MCP. Tianwan Nuclear Power Station has taken three decontamination technologies in former overhauls, including ultrasonic decontamination, oxidation-deoxidization and ultrasonic and oxidation-deoxidization. This paper analyses the merits and demerits of decontamination technologies, and evaluates these technologies' influence on collective dose and the time limit for MCP overhaul. It is concluded that ultrasonic and oxidation-deoxidization technology is the optimum choice. This technology could achieve a maximum decontamination factor, and could markedly reduce collective dose. (authors)

  13. Implicit attitudes toward nuclear power and mobile phone base stations: support for the affect heuristic.

    Science.gov (United States)

    Siegrist, Michael; Keller, Carmen; Cousin, Marie-Eve

    2006-08-01

    The implicit association test (IAT) measures automatic associations. In the present research, the IAT was adapted to measure implicit attitudes toward technological hazards. In Study 1, implicit and explicit attitudes toward nuclear power were examined. Implicit measures (i.e., the IAT) revealed negative attitudes toward nuclear power that were not detected by explicit measures (i.e., a questionnaire). In Study 2, implicit attitudes toward EMF (electro-magnetic field) hazards were examined. Results showed that cell phone base stations and power lines are judged to be similarly risky and, further, that base stations are more closely related to risk concepts than home appliances are. No differences between experts and lay people were observed. Results of the present studies are in line with the affect heuristic proposed by Slovic and colleagues. Affect seems to be an important factor in risk perception. PMID:16948694

  14. High frequency, high amplitude and low energy earthquake study at V.C. Summer Nuclear Station

    International Nuclear Information System (INIS)

    The impoundment of Monticello Reservoir, adjacent to the Virgil C. Summer Nuclear Station, produced a large number of small earthquakes in the near-field. Several of these earthquakes were recorded by a USGS strong motion accelerometer located on an earthen dam abutment approximately 1 mile from the nuclear station. The recorded earthquakes contained high frequency, high amplitude (maximum horizontal acceleration of 0.36 g), and low energy. To resolve Atomic Safety and Licensing Board (ASLB) and Advisory Committee on Reactor Safeguards (ACRS) concerns relative to these earthquakes, the Utility was requested to compare the response spectra of the recorded earthquakes to the plant design response spectra to verify that adequate safety margins exist for plant components necessary for shutdown and residual heat removal. (orig.)

  15. Decommissioning situation and research and development for the decommissioning of the commercial nuclear power station in Japan

    International Nuclear Information System (INIS)

    There are 48 commercial nuclear power stations in operation in Japan as of January 1, 1995, which supplies about 28% (2.2 x 108 MWh) of total annual electricity generation in FY 1992. Accordingly, as the nuclear power contributes so much in electricity generation, there is a growing concern in the public toward the safety on decommissioning nuclear power station. It is gravely important to secure the safety throughout the decommissioning. This paper discusses: the decommissioning situation in Japan; the Japanese national policy for decommissioning of commercial nuclear power stations; R and D for decommissioning of commercial nuclear power stations in Japan; and the present conditions of low-level radioactive wastes disposal in Japan

  16. The effects of solar-geomagnetically induced currents on electrical systems in nuclear power stations

    Energy Technology Data Exchange (ETDEWEB)

    Subudhi, M. [Brookhaven National Lab., Upton, NY (United States); Carroll, D.P. [Florida Univ., Gainesville, FL (United States); Kasturi, S. [MOS, Inc., Melville, NY (United States)

    1994-01-01

    This report presents the results of a study to evaluate the potential effects of geomagnetically induced currents (GICs) caused by the solar disturbances on the in-plant electrical distribution system and equipment in nuclear power stations. The plant-specific electrical distribution system for a typical nuclear plant is modeled using the ElectroMagnetic Transient Program (EMTP). The computer model simulates online equipment and loads from the station transformer in the switchyard of the power station to the safety-buses at 120 volts to which all electronic devices are connected for plant monitoring. The analytical model of the plant`s electrical distribution system is studied to identify the transient effects caused by the half-cycle saturation of the station transformers due to GIC. This study provides results of the voltage harmonics levels that have been noted at various electrical buses inside the plant. The emergency circuits appear to be more susceptible to high harmonics due to the normally light load conditions. In addition to steady-state analysis, this model was further analyzed simulating various plant transient conditions (e.g., loss of load or large motor start-up) occurring during GIC events. Detail models of the plant`s protective relaying system employed in bus transfer application were included in this model to study the effects of the harmonic distortion of the voltage input. Potential harmonic effects on the uniterruptable power system (UPS) are qualitatively discussed as well.

  17. The effects of solar-geomagnetically induced currents on electrical systems in nuclear power stations

    International Nuclear Information System (INIS)

    This report presents the results of a study to evaluate the potential effects of geomagnetically induced currents (GICs) caused by the solar disturbances on the in-plant electrical distribution system and equipment in nuclear power stations. The plant-specific electrical distribution system for a typical nuclear plant is modeled using the ElectroMagnetic Transient Program (EMTP). The computer model simulates online equipment and loads from the station transformer in the switchyard of the power station to the safety-buses at 120 volts to which all electronic devices are connected for plant monitoring. The analytical model of the plant's electrical distribution system is studied to identify the transient effects caused by the half-cycle saturation of the station transformers due to GIC. This study provides results of the voltage harmonics levels that have been noted at various electrical buses inside the plant. The emergency circuits appear to be more susceptible to high harmonics due to the normally light load conditions. In addition to steady-state analysis, this model was further analyzed simulating various plant transient conditions (e.g., loss of load or large motor start-up) occurring during GIC events. Detail models of the plant's protective relaying system employed in bus transfer application were included in this model to study the effects of the harmonic distortion of the voltage input. Potential harmonic effects on the uniterruptable power system (UPS) are qualitatively discussed as well

  18. Beryllium-7 activity at Comprehensive Nuclear-Test-Ban Treaty stations hosted by the United Kingdom

    International Nuclear Information System (INIS)

    The Comprehensive Nuclear-Test-Ban Treaty (CTBT) is supported by a global network of monitoring stations that perform high-resolution gamma-spectrometry on air filter samples for the identification of radionuclides indicative of nuclear weapons tests and reactor incidents. These daily measurements have created an invaluable resource for understanding variations in natural background radioactivity, including the contribution of 7Be. Statistical analysis has been performed on 7Be data collected by CTBT stations hosted by the United Kingdom including at British Indian Ocean Territory (RN66), St Helena (RN67) and Tristan da Cunha (RN68) during 2005-2013. The results have been found to follow a lognormal distribution which implies that the 7Be activity is the multiplicative product of many small independent factors, such as meteorology, elevation, local station conditions, sample acquisition and analysis. This has the potential to identify discrepant measurements not attributable to the intrinsic variability of the distribution and indicative of station malfunction. Variations in 7Be activity have been considered on monthly, weekly and daily timescales and characterised using the geometric mean in accordance with the properties of the lognormal probability density function. Seasonal variations have been identified, with summer maxima and winter minima that are attributable to changes in mixing within the stratosphere and troposphere. Such fluctuations have been examined using the Fast Fourier Transform which may indicate variations associated with the 27 day solar cycle. (author)

  19. Computerized training program usage at the Fort Calhoun Nuclear Power Station

    International Nuclear Information System (INIS)

    The increased US Nuclear Regulatory Commission and Institute of Nuclear Power Operations (INPO) interest in the nuclear power industry training programs resulted in the Omaha Public Power District staff at the Fort Calhoun Nuclear Power Station investigating the potential for computerizing their recently accredited training records, student training requirements, and the process of determining student certification status. Additional areas that were desirable were a computerized question data bank with random test generation, maintaining history of question usage, and tracking of the job task analysis process and course objectives. SCI Software's online personnel training information management system (OPTIM) was selected, subsequent to a bid evaluation, to provide these features while operating on the existing corporate IBM mainframe

  20. [Evaluating psychophysiologic adaptation state in operators of Bilibino nuclear power station].

    Science.gov (United States)

    Isaeva, N A; Torubarov, F S; Denisova, E A; Zvereva, Z F; Koronotova, M A

    2014-01-01

    The study revealed that 60% operators of Bilibino nuclear power station suffer from psychosomatic diseases, 41.7% of them are assigned to occupational group of workers, and major part of the examinees with psychosomatic diseases (45.82%) are aged 41-50, high integral level ofpsychophysiologic adaptation is revealed in 5 examinees (12.5%), medium integral level--in 12 examinees (30%). Lower integral level of psychophysiologic adaptation manifested in decrease in psychophysiologic and physiologic levels. PMID:25845144

  1. The regulation of the commissioning of the Sizewell B nuclear power station

    International Nuclear Information System (INIS)

    This paper describes the regulatory aspects of the control of the commissioning of Sizewell B. The way in which the legislation has been used in dealing with commissioning and the early phases of operation is also discussed, with particular emphasis on the manner in which it has been applied to control all aspects of nuclear safety during the transition from a construction to an operational power station. (author)

  2. Radiation effects of Fukushima Dai-ichi nuclear power station accident on fishes on offshore area

    International Nuclear Information System (INIS)

    The dynamic modeling of 137Cs accumulation by the fish, as reference aquatic biota species, was developed for evaluating dynamic concentration process, based on monitoring data of 137Cs concentrations in the sea water offshore and long shore after the accident at Fukushima Dai-ichi Nuclear Power Station. The dependence of 137Cs dynamic concentration by the fish was provided on 137Cs concentration in the water and fish age. (authors)

  3. Power plant engineering. Steam generator replacement at the Beznau nuclear power station

    International Nuclear Information System (INIS)

    In 1993, two steam generators were replaced in a single run within only 44 days at the Beznau Nuclear Power Station. Already in 1971 it had been necessary to plug up heating tubes. For replacement, the outer and the inner concrete cylinders of the containment together with the protective shield had to be opened. Radiation exposure of the personnel was kept low throughout the entire replacement work, the total dose remaining below 1100 mSv. (orig.)

  4. Daya Bay Nuclear Power Station outdoors electrical equipment pollution status analysis and improving

    International Nuclear Information System (INIS)

    According to the practice operation experience of the outdoors electrical equipment in Guangdong Daya Bay Nuclear Power Station, following to the engineering technical standard applied in China, by analysis and assessment of pollution classes, it is considered that the class four is reasonable. And indicated the voltage distance should be more than 3.5 cm/kV. Some improvements had been executed and effects are good. And further suggest some improving comments

  5. Ecological problems of a nuclear power station: a basis for comparing offshore sites

    OpenAIRE

    Broekhoven, L. van; Bastin, A.; Lefevere, S.J.

    1983-01-01

    Seven possible sitings of a nuclear power station on the Belgian coast, or offshore, were postulated and compared in 1975 in a technology assessment approach. In addition, a more detailed ecological case-study was made for one of these seven sites. An ecological (biological, sedimentological and geophysical) inventory was compiled together with evaluation of possible effects of the warm water outfall in the particular area. To facilitate a more accurate prediction model, and an eventual contr...

  6. Security of electricity supply for next winter: Leibstadt nuclear power station is essential

    International Nuclear Information System (INIS)

    Electricity consumption in Switzerland for the last winter (1st October to 31 March) increased by 1400 million kilowatt hours, a 6 per cent increase on the same period the previous year. The Leibstadt nuclear power station coming on stream will reach an output of some 3100 million kilowatt hours. Nevertheless, if the current consumption pattern continues, in a few years the surplus provided by Leibstadt will be swallowed up. (A.E.W.)

  7. Discussion about the application of treatment process for dehydrated wet waste at nuclear power station

    International Nuclear Information System (INIS)

    In nuclear power station, the most popular treatment about low level radioactive wet waste generated during the unit operating and maintenance is embedded by cement. For radioactive waste minimization, this article introduces a new treatment process to dehydrate and compress wet waste. According to the development and application of the treatment process for the wet waste, and comparing with the formerly treatment-the cement embedding, prove that the new treatment can meet the purpose for volume reduction of wet waste. (authors)

  8. Improving the reliability modeling concerning the emergency core cooling system at Gentilly-2 Nuclear Generating Station

    Energy Technology Data Exchange (ETDEWEB)

    Komljenovic, D.; Vaillancourt, R.; Croteau, M. [Hydro Quebec, Gentilly-2, Nuclear Generating Station, Quebec (Canada); Abdul-Nour, G.; Darragi, M. [Univ. du Quebec a Trois Rivieres, Trois Rivieres, Quebec (Canada)

    2003-07-01

    This technical paper presents an approach to improving the reliability modeling concerning the performance of the Emergency Core Cooling (ECC) System at Gentilly-2 Nuclear Generating Station following a loss of coolant accident (LOCA). It includes a quantitative unavailability analysis based on the current system design and operation. The study is performed as a part of a project with regard to an extension of the plant planned outage period. (author)

  9. Cracked shaft diagnosis and detection on reactor recirculation pumps at Grand Gulf Nuclear Station

    International Nuclear Information System (INIS)

    By utilizing state-of-the-art analysis techniques, instrumentation and vibration information, a cracked shaft was hypothesized and confirmed for one of two Reactor Recirculation Pumps at Grand Gulf Nuclear Station (GGNS). This experience confirmed many previous observations and expected behavior patterns for cracked shafts and, not unexpectedly, provided another unique set of data which can be added to the data base being developed for cracked shaft occurrences

  10. Modifications and addition of an auxiliary feedwater pump to SONGS [San Onofre nuclear generating station] 1

    International Nuclear Information System (INIS)

    This paper discusses the recent modifications and equipment additions to the auxiliary feedwater (AFW) system at San Onofre nuclear generating station (SONGS) Unit 1. As a result of the Three Mile Island accident, several modifications to the AFW system were required. The addition of a third auxiliary feedwater pump was necessary to allow auxiliary feedwater operation following a main steam-line break concurrent with a single active failure

  11. The complementary factors of nuclear and hydraulic energy in western Europe: the role of pumping stations

    International Nuclear Information System (INIS)

    The nuclear choice results from the determination to be politically independent and a calculation of competitivity, which in France's case are emphasized by the chronological concord between the 1973-74 oil crisis and the Messmer Plan. Hydraulic equipment is not the result of an authentic choice, it is linked to the existence of the availability of water power. Our article deals with the role of pumping stations, the evolution of the role of pumping and its geography

  12. Views on ASSET guidelines from event 'T5' of Daya Bay Nuclear Power Station

    International Nuclear Information System (INIS)

    The event assessment methodology adopted by ASSET (Assessment of Safety Significant Events Team) of IAEA, and event 'T5' (abnormal control rod drop time) occurred in Daya Bay Nuclear Power Station, including the causes and the corrective actions are briefly presented. The assessment of the event is performed by using the ASSET methodology, some advantages and limits of the methodology in practice are pointed out

  13. Welding and nondestructive examination issues at Seabrook Nuclear Station: An independent review team report

    International Nuclear Information System (INIS)

    In response to congressional concerns about the adequacy of the welding and nondestructive examination (NDE) programs at the Seabrook Nuclear Station, NRC senior management established an independent review team (IRT) to conduct an assessment. The IRT focused on the quality of the finished hardware and associated records, as well as on the adequacy of the overall quality assurance program as applied to the fabrication and NDE programs for pipe welds. This report documents the findings of that investigation

  14. Maintenance model for the No. 2 1300 MW unit at Philippsburg nuclear power station

    International Nuclear Information System (INIS)

    In 1979 a maintenance model to the scale 1:1 was constructed for the second extension of Philippsburg Nuclear Power Station. The objective of this model, the building of which was completed at the end of 1982, the physical arrangement of the overall maintenance regime and the practice-oriented application of the ergonomics, in particular in relation to the optimization of the man-machine interface, are described. (orig.)

  15. An approach for risk informed safety culture assessment for Canadian nuclear power stations

    International Nuclear Information System (INIS)

    One of the most important components of effective safety and risk management for nuclear power stations is a healthy safety culture. DNV has developed an approach for risk informed safety culture assessment that combines two complementary paradigms for safety and risk management: loss prevention - for preventing and intervening in accidents; and critical function management - for achieving safety and performance goals. Combining these two paradigms makes it possible to provide more robust systems for safety management and to support a healthy safety culture. This approach is being applied to safety culture assessment in partnership with a Canadian nuclear utility. (author)

  16. Validation of seismic soil structure interaction (SSI) methodology for a UK PWR nuclear power station

    International Nuclear Information System (INIS)

    The seismic loading information for use in the seismic design of equipment and minor structures within a nuclear power plant is determined from a dynamic response analysis of the building in which they are located. This dynamic response analysis needs to capture the global response of both the building structure and adjacent soil and is commonly referred to as a soil structure interaction (SSI) analysis. NNC have developed a simple and cost effective methodology for the seismic SSI analysis of buildings in a PWR nuclear power station at a UK soft site. This paper outlines the NNC methodology and describes the approach adopted for its validation

  17. An approach for risk informed safety culture assessment for Canadian nuclear power stations

    Energy Technology Data Exchange (ETDEWEB)

    Nelson, W.R. [Det Norske Veritas (U.S.A.), Inc., Katy, Texas (United States)

    2010-07-01

    One of the most important components of effective safety and risk management for nuclear power stations is a healthy safety culture. DNV has developed an approach for risk informed safety culture assessment that combines two complementary paradigms for safety and risk management: loss prevention - for preventing and intervening in accidents; and critical function management - for achieving safety and performance goals. Combining these two paradigms makes it possible to provide more robust systems for safety management and to support a healthy safety culture. This approach is being applied to safety culture assessment in partnership with a Canadian nuclear utility. (author)

  18. Report of NII investigation into allegations of faulty welding at Hinkley 'B' nuclear power station

    International Nuclear Information System (INIS)

    This reports the procedure and findings of the Nuclear Installations Inspectorate's investigation into allegations of welding and radiography malpractice at Hinkley Point-B power station. These concerned welds and their radiographic testing made on pipework carrying water or steam associated with one of the main electricity turbo generators, during construction in 1971. The water or steam is not radioactive and pipe failure would have no nuclear safety significance. Both the Central Electricity Generating Board and the NII investigated the allegations. Both investigations concluded that there was no evidence to support the allegations. (U.K.)

  19. A survey study about what an exhibition hall of nuclear power station should be

    International Nuclear Information System (INIS)

    The exhibition hall of nuclear power station contributes to understand the visitors about organizations or safety systems through displays and explanations without difficulty. In addition to that, there will be some effect that they give informations to other people after the inspection, so the exhibition hall of nuclear power station plays a vital role of public information considering tens of thousands of yearly visitors. According to that, we made inquiries to the visitors and tried to search what it should be, intending to investigate their actual situation of attitudes or needs, and to accurate effectivities of the present displays in the center of explanations about the organization of nuclear power plant. As a result, the opinion that 'I want to know the organization of nuclear power plant' accounts over 60%, differing from other data of research. And also the opinion after the inspection that 'I am satisfied with acquiring knowledge about the organization' accounts nearly 60%, much higher compared with other choices. In view of these facts, the efficiency of the exhibition hall was certified. The visitor's attitudes of nuclear power is more affirmative than public's one. Even though considering the differences of the survey method, there must be a difference from the first. Besides that, we gained a discernment that educational functions is important through researches for other company. (author)

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

    International Nuclear Information System (INIS)

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

  1. Investigation on efficiency of stable iodine distribution around Golfech nuclear power station

    International Nuclear Information System (INIS)

    Background. In order to prevent thyroid cancer radio induced during civil nuclear accident french regulations plan stable iodine distribution for populations living near nuclear power stations. We evaluate availability of stable iodine and understanding of such measure with investigation around Golfech nuclear power station. Methods. In 2001, 1148 families living in a 10 km perimeter around power station were questioned through their schooled child. Our anonymous questionnaire (22 questions, 91 items) was linked with stable iodine availability, organ protection, most exposed persons, dosage and time of stable iodine ingestion. Results. 72,1 % families replied. Among them, 60,8% could easily and quickly find stable iodine in case of emergency, 87,8% know that such measure is to protect thyroid, 80,5% know that children and pregnant women (62,7%) are the most exposed people, 82,3% know that such ingestion is allowed by Prefect order. Conclusion. Answer rate and stable iodine prophylaxis knowledge are satisfactory. On the other hand, in case of necessity about 40% of the concerned families don't have a rapid access to stable iodine, which will forced authorities to distribute as a matter of urgency supplementary stable iodine. Statistical analysis of the answers demonstrate that the most iodine prophylaxis ignorant people are the most refractory to this approach. (author)

  2. Numerical analysis of transient pressure variation in the condenser of a nuclear power station

    Energy Technology Data Exchange (ETDEWEB)

    Wang, Xinjun; Zhou, Zijie; Song, Zhao [Xi' an Jiaotong University, Xi' an (China); Lu, Qiankui; Li, Jiafu [Dong Fang Turbine Co., Ltd, Deyang (China)

    2016-02-15

    To research the characteristics of the transient variation of pressure in a nuclear power station condenser under accident condition, a mathematical model was established which simulated the cycling cooling water, heat transfer and pressure in the condenser. The calculation program of transient variation characteristics was established in Fortran language. The pump's parameter, cooling line's organization, check valve's feature and the parameter of siphonic water-collecting well are involved in the cooling water flow's mathematical model. The initial conditions of control volume are determined by the steady state of the condenser. The transient characteristics of a 1000 MW nuclear power station's condenser and cooling water system were examined. The results show that at the condition of plant-power suspension of pump, the cooling water flow rate decreases rapidly and refluxes, then fluctuates to 0. The variation of heat transfer coefficient in the condenser has three stages: at start it decreases sharply, then increases and decreases, and keeps constant in the end. Under three conditions (design, water and summer), the condenser pressure goes up in fluctuation. The time intervals between condenser's pressure signals under three conditions are about 26.4 s, which can fulfill the requirement for safe operation of nuclear power station.

  3. Nuclear Power Station Kalkar, 300 MWe Nuclear Prototype Power Station with Fast Sodium Cooled Reactor (SNR-300), Short Description of the Reactor Core Mark-Ia

    International Nuclear Information System (INIS)

    The nuclear power station Kalkar is a prototype with a sodium cooled fast reactor (SNR-300) and a thermal power of 762 MW. The initial licensing procedure in 1972 was based on the so-called Mark-I core. During the following years, this core underwent some changes, for instance the thickness of the radial blanket was reduced to lower the electricity generation costs, the design of the absorber systems had been further optimized, and it became clear, that a full core with plutonium from MAGNOX-reactors could not be realized and that fuel from light-water reactors had also to be used. In this licensing document the modified reactor core Mark-Ia is described, and the radiological consequences of the core modification are quantified to be tolerable

  4. [Water-soluble anions of atmosphere on Tianwan nuclear power station].

    Science.gov (United States)

    Zhao, Heng-Qiang; He, Ying; Zheng, Xiao-Ling; Chen, Fa-Rong; Pang, Shi-Ping; Wang, Cai-Xia; Wang, Xiao-Ru

    2010-11-01

    Three major water-soluble anions (Cl-, SO4(2-) and NO3-) in the atmosphere of the Tianwan nuclear power station in Lianyungang were determined by ion chromatography from June 2005 to May 2006. The results showed that the annual average concentration of Cl-, SO4(2-) and NO3- in the atmosphere of Tianwan nuclear power station was (33.12 +/- 53.63) microg x m(-3), (53.34 +/- 30.34) microg x m(-3) and (8.34 +/- 4.47) microg x m(-3), respectively. The concentrations of the three water-soluble anions showed evident trend of seasonal variation. The concentrations of Cl-, SO4(2-) reached the highest level in summer and the lowest level in winter, while the concentration of NO3- in autumn and winter was higher than those in summer and spring. Meteorological parameters such as wind direction, wind speed, temperature and relative humidity were studied and showed definite influence to the anions concentration of the atmosphere. This is the first simultaneous monitoring of corrosive anions in the atmosphere of Chinese coastal nuclear power plant, and it will provide basis for the prevention of marine atmospheric corrosion, which will ensure the safely operating of our nuclear power industry. PMID:21250433

  5. Instrument drift study station San Onofre Nuclear Generating Units 2 and 3

    International Nuclear Information System (INIS)

    This is a summary of an analysis of instrument transmitter drift that has been performed by Southern California Edison, Reference 5.5. The purpose of the study was to quantify the magnitude of transmitter drift that is occurring at the San Onofre Nuclear Generating Station (SONGS), Unit 2 and 3, in order to increase the required calibration interval of certain instrumentation. The Nuclear Regulatory Commission established the required calibration intervals and documents these requirements in the Technical Specifications for each nuclear unit. SONGS Unit 2 and 3 has recently increased the nominal time between outages to 24 months, however, the Technical Specification calibration requirements would require a shutdown. Quantifying the magnitude of transmitter drift is important when justifying the extension of transmitter calibration intervals to 30 months. This paper describes an analysis of the historical calibration data of certain instrumentation used at the San Onofre Nuclear Generating Station (SONGS) Units 2 and 3. The purpose of this paper is to provide a reference document of an investigation into extending the calibration interval of this instrumentation from the current Technical Specification requirement of 11 1/2 months to 30 months

  6. 76 FR 25378 - Exelon Generation Company, LLC; PSEG Nuclear, LLC; Peach Bottom Atomic Power Station, Units 2 and...

    Science.gov (United States)

    2011-05-04

    ... December 14, 2010 (75 FR 77913). However, by letter dated April 26, 2011, the licensee withdrew the... COMMISSION Exelon Generation Company, LLC; PSEG Nuclear, LLC; Peach Bottom Atomic Power Station, Units 2 and... Nos. DPR-44 and DPR-56 for the Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3, located...

  7. 75 FR 6071 - Exelon Generation Company, LLC; PSEG Nuclear, LLC; Peach Bottom Atomic Power Station Units 2 and...

    Science.gov (United States)

    2010-02-05

    ..., 2009 (74 FR 20744). However, by letter dated January 19, 2010, the licensee withdrew the proposed... COMMISSION Exelon Generation Company, LLC; PSEG Nuclear, LLC; Peach Bottom Atomic Power Station Units 2 and 3... Operating License Nos. DPR-44 and DPR-56 for the Peach Bottom Atomic Power Station (PBAPS), Units 2 and...

  8. AECB staff annual assessment of the Pickering A and B Nuclear Generating Stations for the year 1994

    International Nuclear Information System (INIS)

    The Pickering Nuclear Generating Station (PNGS) is located on the north shore of Lake Ontario, about 32 km east of downtown Toronto. It consists of two stations, PNGS-A and PNGS-B. Each station contains four reactor units. PNGS-A consists of Units 1 to 4, while PNGS-B consists of Units 5 to 8. Each unit can generate about 540 megawatts of electricity. All eight units are located within a single enclosure. Ontario Hydro's Pickering Nuclear Division has assigned one Station Director with authority over both stations, but each station has its own organization. AECB issue a separate operating licence for each station. This report presents the Atomic Energy Control Board staff assessment of the Pickering stations' safety performance in 1994 and other aspects that they consider to have significant impact on nuclear safety. AECB based their conclusions on their observations, audits, inspections and review of information that Ontario Hydro submits to them as required by the station Operating Licences. 11 tabs., 8 figs

  9. Comparison and evaluation of nuclear power plant options for geosynchronous power stations

    International Nuclear Information System (INIS)

    A solution to the safety, safeguards, and radwaste disposal problems of nuclear power is to locate the breeder reactor power plants far out in geosynchronous orbit and beam the power to earth with microwaves. The generation of nuclear power in space is technologically feasible and has already been demonstrated on a small scale. It has also been shown that high efficiency microwave transmission of power from synchronous orbit to earth is feasible and is not hazardous. The reactor safety problem would be virtually eliminated because of the remoteness of the satellite power station in geosynchronous orbit. The worst possible accident at such a plant would have negligible effect on the earth, certainly less than the high altitude nuclear explosions which have been conducted in the past. Accidental re-entry from geosynchronous orbit could not occur because of the very large velocity change required. The safeguards problem can be virtually eliminated by adopting the following procedures: 1) The plant is initially started up using U-235 fuel or bred plutonium or U-233 from another geosynchronous power plant, 2) Once the plant is operating, only nonhazardous fertile materials (thorium or depleted uranium) are shipped up from earth, 3) The fissile fuel is bred and used in space, and none of this highly toxic fissile material is ever returned to earth. The radioactive waste could be concentrated and ejected in canisters into deep space away from the earth. The geosynchronous nuclear power plant offers unlimited nuclear power without nuclear hazards or nuclear pollution, but at somewhat higher cost. Whether or not society will be willing to pay these higher costs of nuclear power from space, or whether new energy resources such as nuclear fusion or solar power become feasible, remains to be seen. A prudent course to follow would be to give careful consideration to all future options for large scale energy generation, including the option of nuclear power from space

  10. Determination of personal doses during maintenance work at Beznau nuclear power station with the object of dosage reduction

    International Nuclear Information System (INIS)

    The desire of all parties to reduce dosages suffered by personnel in nuclear power stations has led to a study designed to expose general possibilities for reducing dosages during maintenance work, using as an example the nuclear power station at Beznau in Switzerland. Although the evaluation phase of the study has still to be undertaken, it can be recognized already that knowledge about dosage reduction is obtainable from the method of investigation applied. (orig.)

  11. Experience with primary water cleaning and waste water treatment plant in nuclear power stations with pressurised and boiling water reactors

    International Nuclear Information System (INIS)

    Powder resin alluvial filtration using structured filter layers permits constantly improving adaption of the water treatment technology to even the most demanding problem situations - particularly in the field of primary water and waste water treatment in nuclear power stations. From experience in operation the authors show the advantages of this technique compared to other techniques, which can be deduced from theoretical concepts, taking into account the various target figures decisive in operating nuclear power stations. (orig.)

  12. The economic performance of nuclear thermal power station in southeast area of our country

    International Nuclear Information System (INIS)

    This paper is a supplementary to ''An Economic Comparison between Nuclear and Coal Electric Power Station in Southeast Area of Our Country'', written by Luo Anren. As the efficiency of a co-generation power plant is much higher than that of the conventional one, a small or medium-sized steam supplying nuclear power plant will be also more economic than a fuel-fired power plant even with a capacity of 1000MWe. It is more suitable to the situation in China to develop a series of small and medium-sized nuclear power plants supplying process steam or hot water for district heating. This will be beneficial to energy saving as well as to environmental protection. (Author)

  13. Integrated Plant Safety Assessment, Systematic Evaluation Program: Yankee Nuclear Power Station (Docket No. 50-29)

    International Nuclear Information System (INIS)

    The US Nuclear Regulatory Commission (NRC) has prepared Supplement 1 to the final Integrated Plant Safety Assessment Report (IPSAR) (NUREG-0825), under the scope of the Systematic Evaluation Program (SEP), for Yankee Atomic Electric Company's Yankee Nuclear Power Station located in Rowe, Massachusetts. The SEP was initiated by the NRC to review the design of older operating nuclear power plants to reconfirm and document their safety. This report documents the review completed under the SEP for those issues that required refined engineering evaluations or the continuation of ongoing evaluations after the Final IPSAR for the Yankee plant was issued. The review has provided for (1) an assessment of the significance of differences between current technical positions on selected safety issues and those that existed when Yankee was licensed, (2) a basis for deciding how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety. 2 tabs

  14. Cycle for fuel elements. Uranium production, programs for nuclear power stations and capital expenditure involved

    International Nuclear Information System (INIS)

    A number of different possible programs for nuclear power stations of various types are presented in this survey. These programs are established in relation to the use of uranium and thorium in amounts similar to those that shall probably be produced in France during the next fifteen years. As it is possible to draw plans for nuclear power stations in which several processes exist simultaneously, an unlimited number of variations being thinkable, this survey is limited to successive analysis of the results obtained by use of only one of each of the following three systems: - system natural uranium-graphite, - system natural uranium-heavy water, -system enriched uranium-pressurised light water. All schemes are considered as assemblages of these three simple systems. The effects of plutonium recycling are also considered for each system. The electric power installed and the capacity of stations situated up-stream and down-stream have been calculated by this method and an attempt has been made to establish the sum to be invested during the fifteen years necessary for the launching of the programs scheduled. A table of timing for the investments groups the results obtained. Considering the fact that French availabilities in capital shall not be unlimited during the coming years, this way of presenting the results seems to be interesting. (author)

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

    International Nuclear Information System (INIS)

    This document is the final report on operation of the Garigliano Nuclear Power Station as required under the participation contract between Enel and Euratom and refers to the first ten years of commercial operation (1 May 1964-31 December 1973) of the power station. In the decade in question the Garigliano Power Station has assumed an important position in the world spectrum of nuclear energy since it was the first thermal-power reactor in the world to have irradiated considerable quantities of plutonium as a fuel in its own core for the production of energy. An experimental programme on this was started in 1966 with theoretical study of plutonium recycling and was followed by the charging of the Garigliano reactor with some mixed oxide elements (PuO2-UO2) in 1968 and 1970. The excellent performance of these prototype elements, which among other things were examined in detail at the end of each radiation cycle, prompted Enel to decide in favour of the use of entire batches of recycled fuel elements of the PuO2-UO2 type in the reactor from 1975 onwards

  16. Manufacture and quality control of concrete for Ikata Nuclear Power Station, Shikoku Electric Power Co., Inc

    International Nuclear Information System (INIS)

    Ikata Nuclear Power Station, only one nuclear power station in Shikoku, is located at the root of Sada Peninsula on Seto Inland sea side. At present, No.1 and No.2 plants of 566 MW each are in commercial operation, and on the east side, No.3 plant is under construction. No.3 plant is a PWR type plant of 890 MWe output, and the start of commercial operation is scheduled in March, 1995. In the construction of No.3 plant, the concrete used for civil engineering and building works is about 430,000 m3, and for the improvement of the quality control of concrete, the pursuit of economic efficiency, the fostering of concrete technology of employee and the coprosperity with local industries, the facilities for manufacturing concrete were constructed within the premise of the power station. The amount of use of concrete and respective materials classified by respective fiscal years, and the amount of manufacture of concrete that determines the scale of the concrete plant are shown. As to the construction of the concrete plant, the foundation work was started in March, 1987, and the machine foundation and building works were started in May, 1987. The acceptance was completed on August 17, 1987. The facilities of manufacturing concrete, the manufacture of concrete, and the quality control of materials and concrete are reported. (author)

  17. Abundance and distribution of radionuclides discharged from a BWR nuclear power station into a marine bay

    International Nuclear Information System (INIS)

    This article summarizes a portion of one of a series of radiological surveillance studies conducted by the U.S. Environmental Protection Agency (EPA) at nuclear power stations. Radionuclide concentrations were measured in Barnegat Bay at the New Jersey shore during EPA's 2-year radiological surveillance study at the Oyster Creek Nuclear Generating Station. The station discharges batches of radioactive liquid waste into effluent condenser cooling water, which flows through Oyster Creek into Barnegat Bay 3 km from the point of discharge. The bay is long, narrow, and shallow, with few passages to the Atlantic Ocean. Radionuclide concentrations were measured repeatedly in water, sediment, marine vegetation, fish, clams, and crabs at various sampling points. Measured values were compared to calculated values based on bioaccumulation factors, and both sets were used to compute dose equivalent rates to the most exposed persons in the environment. The two observed critical radiation exposure pathways - fish consumption and standing on beaches - resulted in dose equivalents of less than 1 mrem/year; the critical radionucides were 90Sr and 60Co, respectively. Indicator radionuclides were identified, and environmental radiological monitoring activities were recommended

  18. Experience in simulating radioactive air pollution around nuclear power stations in complex terrain

    International Nuclear Information System (INIS)

    For the licencing procedure of power stations the analytical Gauss-solution to the advection-diffusion-equation is still required. But for simulating the atmospheric dispersion of radionuclides over complex terrain advanced numerical methods are need. Of course, any influence of the local orography to the atmospheric dispersion process is of highest priority for preparing emergency plans. Likewise the site-specific features should be known to place the remote radiological control system around nuclear plants effectively. Starting from detailed observations of the wind field e.g. by Doppler SODAR measurements the application of the mass consistent model is the first choice for simulating three-dimensional wind fields. We summarize our experience gained in treating the complex local sites of the nuclear power stations GKN (Neckarwestheim) and KWO (Obrigheim). We implemented the code system SPEEDI of JAERI on our CRAY-2 and developed a special procedure to couple mesoscale calculations with imbedded local fine mesh calculations around the power stations. The topographical data as well as the surface roughness could be represented by pixel sizes of 100 m x 100 m needed to simulate the local details of the Neckar valley. In such inhomogeneous wind fields the dispersion and deposition of the pollutants can best be described by a Monte Carlo procedure as applied in SPEEDI. Finally the dose rate of the external gamma-radiation from the contamination in the atmosphere and on the ground is calculated by two- and three-dimensional SN-programmes as used for radiation transport problems

  19. Quality control for the construction of Ikata Nuclear Power Station No. 2 Unit

    International Nuclear Information System (INIS)

    In the construction of No. 2 unit in Ikata Nuclear Power Station, Shikoku Electric Power Co., the quality control was practiced making effective use of the experience in preceding stations including the Three Mile Island station, U.S., and improving those. The construction works were also performed in consideration of ensuring the safe running of No. 1 unit in commercial operation. In this report, first the outline of No. 2 unit facility and the quality control in the construction processes are described sequentially. For the comprehensive quality control activity over a series of plant design, manufacturing, installation and commissioning processes, the quality control policy was fixed, the system was established, the plan was prepared, and the quality control was promoted as planned and systematically. The outline of the quality control in each stage is described as follows. Design stage: It was implemented for the confirmation of applicable standards and references, the management of drawings submitted for approval, the selection of materials used, the coordination among sub-contractors, design change and the reflection of experience in preceding stations. Manufacturing stage. It was performed for material control, manufacturing management, factory test and control. Installation stage. It was practiced for the management of installation works, the inspection during the installation, and the check-up and control after the installation. Several quality control items were implemented also in the method of construction works and construction management. (Wakatsuki, Y.)

  20. Palo Verde Nuclear Generating Station: an example of the state role in regional nuclear projects

    International Nuclear Information System (INIS)

    A nuclear power plant siting policy which confines new construction to existing sites will lead to the formation of large regional power centers, each involving many utilities from several states. The Palo Verde Nuclear Project in Arizona has been examined in terms of the role state regulation plays in large regional nuclear projects. State regulatory processes do not reflect the regional nature of large power centers. Decisions and actions by individual state regulatory commissions create risk and uncertainty for all the utility participants in regional projects. A climate and mechanism to encourage and facilitate interstate cooperation are needed to enhance the viability of the confined siting policy and the regional power center concept

  1. Nuclear powered submarines and the Space Station: A comparison of ECLSS requirements

    International Nuclear Information System (INIS)

    The NASA Space Station holds remarkable similarity to the modern nuclear powered submarine. Both are required to provide a 90-day mission capability during which all aspects of human habitation must be accommodated. The requirements for environmental control, and failure tolerance of environmental control systems, are also quite similar. Although the resources, operating environments, and mission objectives for the submarine and space station are distinctly different, the problems faced by the environmental control and life support system (ECLSS) engineer require application of the same technologies and design principles. This paper addresses the resources and mission requirements specific to the two vehicles, and discusses their influence on the design of the ECLSS. The design constraints for individual ECLSS subsystems are discussed with the resultant impact on design approach selected for each vehicle

  2. Experiences of occupational dose reduction at the Fugen nuclear power station

    International Nuclear Information System (INIS)

    Occupational radiation dose has been effectively suppressed by efforts against both internal and external exposure in the Fugen nuclear power station. The tritium internal dose is completely suppressed by developments of high sensitivity tritium monitors with hollow fiber radon filters, comfortable tritium protection suits, and established working procedure for equipment maintenance of the heavy water system. The internal occupational dose has been suppressed to a negligible level comparing to the external dose. The external occupational dose had increased with dose rates of the primary cooling system. Establishment of radiation work procedure for maintenance works and development of chemical decontamination has been effectively saving the external occupational dose. The chemical decontaminations carried out in 1989 and 1991 are the first applications to the whole primary cooling system of operating power stations in Japan. This paper describes these efforts and effects on occupational dose reduction in Fugen. (author)

  3. Planning and realisation of a radio-communications system for a nuclear generating station

    International Nuclear Information System (INIS)

    The article describes the radio-communications system, including sub-systems for fire brigade, station personnel and paging, of the nuclear generating station at Goesgen-Daeniken. The design was based upon a very thorough survey of field strength in and around the buildings, made with an automatic recorder, which is described. The system consists of a large number of transmitters operating in parallel, each of which has a frequency synthesiser driven from a single central point; the frequency tolerance in the UHF bands is of the order of 1:108. Each receiver has an automatic signal selector that picks out the transmitter, which at the receiving point in question, produces the highest signal/noise ratio. (C.J.O.G.)

  4. Radiological impact of nuclear power stations in India on their environment

    International Nuclear Information System (INIS)

    There are five sites in India where nuclear power plants (NPPs) are operating. Two of them (Tarapur and Kalpakkam) are situated on the coast and the other three (Rawatbhata, Narora and Kakrapar) are situated inland. Except for the first power station at Tarapur, which has two BWR units, all other stations have PHW type reactors. Under normal operation, the low level radioactive wastes produced in the plants are diluted and dispersed in the environment after monitoring and treatment, if necessary. Gaseous wastes are discharged through a high stack and liquid wastes are diluted with condenser cooling water or coolant blowdown water (using cooling towers) and discharged to a water body (sea or reservoir). 3 refs

  5. Design of full speed 985 MW turbine for Daya Bay nuclear station, China

    International Nuclear Information System (INIS)

    Daya Bay will be the first utility-operated nuclear power station in the People's Republic of China. It will be situated some 30 miles north-east of Hong Kong. The station will consist of two power units, each based on pressurized water reactors of 2905 MWth power output supplied by Framatome of France. The two conventional islands complete with their civil, mechanical and electrical designs and plants and comprising two 985 MWe, 3000 rpm steam turbines will be supplied by GEC Turbine Generators of the UK. The turbines are the largest full speed machines ever built in Britain. The steam cycle and plant layout are illustrated. The construction and operation of the turbines and associated valves etc are explained. The turbine control is discussed. (author)

  6. Is there a measurably higher radiation risk for the personnel of a nuclear therapy station?

    International Nuclear Information System (INIS)

    Data for the internal and external radiation burden for the personnel of a nuclear therapy station have been evaluated retrospectively for 51 months. The therapy station is in a provisional state, with minimum constructional radiation protection. The data were compared with persons using open radionuclides for diagnosis. The latter persons had higher whole body as well as partial body burdens. The data collected for incorporation, the thyroid burden from I131 (used exclusively in the therapy) can be estimated to below 20mGy. In none of the two groups were the limit doses exceeded. The radiation risk assessed does not justify further expensive constructional means. Organisation is sufficient for keeping the radiation burden low. 3 refs., 2 tabs. (Author)

  7. Pre-license team training at San Onofre Nuclear Generating Station

    International Nuclear Information System (INIS)

    Team Training at San Onofre Nuclear Generating Station (SONGS) Units 2 and 3 has been developed to enhance the performance of station operations personnel. The FACT Training Program (Formality, Attention to Detail, Consistency and Team Effort) is the common denominator for operations team training. Compliance with good operating practices is enhanced by operators working as a team toward the same goal, using the same language, practicing the same operating and communication skills, possessing a clear understanding of individual roles and responsibilities of team members and practicing attention to detail in every task. These elements of effective teamwork are emphasized by the processes and criteria used in the Pre-License Operator Training Program at SONGS

  8. Processing of sump sludges at the Commonwealth Edison Byron Nuclear Generating Station

    International Nuclear Information System (INIS)

    A basic criterion for the disposal of radioactive waste by shallow land burial is that the material must not contain free liquids. In addition burial sites' requirements regarding radioactive waste containing oils, even though solidified, are restrictive. At Commonwealth Edison Byron Nuclear Generating Station a methodology for processing treated waste sludges, originating form the turbine building's floor drains was developed and implemented. As a result of this effort, 322 drums of oil and water sludge were processed. A dry cake, i.e., no free liquids, was produced, packaged, and readied for disposal. The dry cake contained less than 2% oil. The liquid phases resulting from the processing of the treated waste sludge were oil (that was to be processed for disposal as non-radioactive) and filtrate containing less than 5 ppm total suspended solids (TSS) and oil/grease. The filtrate TSS was below the Station's National Pollution Discharge Elimination System (NPDES) permit release limits. 4 figs

  9. In-situ tests on absolute filters at the Fessenheim nuclear power station

    International Nuclear Information System (INIS)

    The Fessenheim nuclear power station is of the PWR type and is situated on the Alsace Grand Canal near the village of Fessenheim (Upper Rhine). It comprises two blocks, each with a capacity of 900 MWe, the first of which should be commissioned before the end of 1976. The absolute filters installed in the power station ventilation systems (individual systems for the auxiliary equipment block, the fuel store, the containment penetration zone, and the control room will be in-situ tested before start-up using the sodium fluoresceinate method as developed by the Commissariat a l'Energie Atomique. Following a brief review of the principles of this method, a description is given of the circuits and equipment installed at Fessenheim (injection and sampling points) which permit checks to be carried out

  10. Cost comparison of 4x500 MW coal-fuelled and 4x850 MW CANDU nuclear generating stations

    International Nuclear Information System (INIS)

    The lifetime costs for a 4x850 MW CANDU generating station are compared to those for 4x500 MW bituminous coal-fuelled generating stations. Two types of coal-fuelled stations are considered; one burning U.S. coal which includes flue gas desulfurization and one burning Western Canadian coal. Current estimates for the capital costs, operation and maintenance costs, fuel costs, decommissioning costs and irradiated fuel management costs are shown. The results show: (1) The accumulated discounted costs of nuclear generation, although initially higher, are lower than coal-fuelled generation after two or three years. (2) Fuel costs provide the major contribution to the total lifetime costs for coal-fuelled stations whereas capital costs are the major item for the nuclear station. (3) The break even lifetime capacity factor between nuclear and U.S. coal-fuelled generation is projected to be 5%; that for nuclear and Canadian coal-fuelled generation is projected to be 9%. (4) Large variations in the costs are required before the cost advantage of nuclear generation is lost. (5) Comparison with previous results shows that the nuclear alternative has a greater cost advantage in the current assessment. (6) The total unit energy cost remains approximately constant throughout the station life for nuclear generation while that for coal-fuelled generation increases significantly due to escalating fuel costs. The 1978 and 1979 actual total unit energy cost to the consumer for several Ontario Hydro stations are detailed, and projected total unit energy costs for several Ontario Hydro stations are shown in terms of escalated dollars and in 1980 constant dollars

  11. P.R. Halls in Tokai and Tsuruga Nuclear Power Stations of The Japan Atomic Power Company

    International Nuclear Information System (INIS)

    (1) P.R. (Public Relations) Hall in Tokai Nuclear Power Station, JAPC. The P.R. Hall in Tokai Nuclear Power Station is in Tokai Village, Ibaraki Prefecture. On the site are the GCR Plant of 166 MWe and a BWR plant of 1,100 MWe. The P.R. Hall is visited especially by local people around nuclear power stations all over Japan. Explanation of nuclear power generation, exhibitions, movies, etc. are presented in the hall. The P.R. Hall is a two-story ferro-concrete building with floor space of 880 m2. (2) The P.R. Hall in Tsuruga Nuclear Power Station, JAPC. The P.R. Hall in Tsuruga Nuclear Power Station is in Tsuruga City, Fukui Prefecture. A BWR plant of 357 MWe is on the site. The P.R. Hall is visited as sightseeing as well as the survey on nuclear power generation. It is a one-story steel frame building with floor space of about 600 m2. (J.P.N.)

  12. The Palo Verde story: a foundation for future multi-station nuclear power plants

    International Nuclear Information System (INIS)

    In 1973, the design and planning for the Palo Verde Nuclear Generating Station Was started featuring three 3800 MWt Combustion Engineering Standard System 80 Nuclear Steam Supply Systems. Arizona Public Service Company (APS) was the Project Manager and Operating Agent and Bechtel Power Corporation the architect/engineer and constructor. The Palo Verde units are located in a desert environment some 50 miles west of Phoenix, Arizona. It is a 'dry site' in that there are no liquid discharges from the site. The cooling tower makeup water sewage is waste effluent from the City of Phoenix treated at an on site reclamation facility. The effluent has had primary and secondary treatment at the Phoenix plant prior to delivery to PVNGS. The units are physically separate from each other but are of identical design. There are no shared safety systems between the units. Unit 1 and Unit 2 are both in commercial operation (January, 1986 and September, 1986 respectively). Unit 3 is scheduled to load fuel late in the first quarter of 1987. This paper presents some of the engineering and management practices used during design, construction, and startup and operational experiences and other unique features of this multi-unit nuclear station. The site arrangement is shown in Figure 1

  13. Palo verde story: a foundation for future multi-station nuclear power plants

    International Nuclear Information System (INIS)

    In 1973, the design and planning for the Palo Verde Nuclear Generating Station was started featuring three 3800 MWt Combustion Engineering Standard System 80 Nuclear Steam Supply Systems. Arizona Public Service Company (APS) was the Project Manager and Operating Agent and Bechtel Power Corporation the architect/engineer and constructor. The Palo Verde units are located in a desert environment some 50 miles west of Phoenix, Arizona. It is a dry site in that there are no liquid discharges from the site. The cooling tower makeup water sewage is waste effluent from the City of Phoenix treated at an on site reclamation facility. The effluent has had primary and secondary treatment at the Phoenix plant prior to delivery to PVNGS. The units are physically separate from each other but are of identical design. There are no shared safety systems between the units. This paper presents some of the engineering and management practices used during design, construction, and startup and operational experiences and other unique features of this multi-unit nuclear station

  14. Safety improvement and responses to renewed regulations in case of Kashiwazakikariwa Nuclear Power Station

    International Nuclear Information System (INIS)

    In response to the accident of TEPCO Fukushima Daiichi Nuclear Power Station, various initiatives have been advancing for the safety of nuclear power generation. Amid this, the application for conformance review on the new regulatory standards of Kashiwazakikariwa Nuclear Power Station units 6 and 7 has been made. This paper firstly explains the following three items as the basic policy of safety measures that were set from the lessons of the accident: (1) strengthening of defense in depth, (2) security of flexibility and responsiveness against incidents beyond assumption, and (3) strengthening of management and organizational skills in case of an accident. Then, it explains the evaluation and measures against earthquake and tsunami, such as the assessment of fault activity, and the evaluation and measures against tsunami. For the protection and reliability assurance of design criteria subject facilities, it mainly explains the evaluation and measures from the standpoints of protection from external incidents and reliability assurance. In addition, it explains the facilities countering a serious accident, and the technical capacity at the time of an accident, on the basis of several study examples of accident countermeasures. (A.O.)

  15. Environmental radiological studies in 1989 near the Rancho Seco Nuclear Power Generating Station

    International Nuclear Information System (INIS)

    In December 1988, the Sacramento Municipal Utilities District (SMUD) asked the Lawrence Livermore National Laboratory's (LLNL) Environmental Sciences Division (ENV) to collect sediment, water,and fish samples downstream from the Rancho Seco Nuclear Power Generating Station for analysis of radionuclides to compare with results from earlier surveys in 1984 through 1987 (1--8). ENV was, however, asked to reduce the total number of sample collections to a minimum in this study because of financial constraints. The proposal ENV submitted for the 1989 Environmental Radiological Studies downstream of the Rancho Seco Nuclear Power Generating Station reflected this reduction, but we believe, nevertheless, the 1989 efforts do allow us to make some meaningful comparisons with the previous studies. Cesium-137 is the most significant radionuclide still observed downstream from the Rancho Seco Nuclear Power Plant. Only occasionally is 134Cs or 60CO observed. In 1989, the concentration of 137Cs in the water and fish decreased with distance from the plant to the same level that is was in 1987, and was lower than it had been from 1984 through 1986. The concentration ratio (CR) for 137Cs in fish is between 1000 and 1500, which is below the NRC default value of 2000. Physical mixing in the creek environment has moved the 137Cs deeper into the sediment column, thereby reducing the concentration in the top 12 cm relative to that in previous years. 8 refs., 18 figs., 9 tabs

  16. Nuclear power station siting experience in the United Kingdom: past and present and proposals for the future

    International Nuclear Information System (INIS)

    Foremost of the many factors in site selection considerations are population distribution, cooling-water availability and amenity. Others are safety of potable water sources, geological stability and the risk of external hazards. Where cooling-water supplies are a limiting factor, the choica of reactor system is of major importance. To determine as early as possible the effect a station might have on its environment, desk studies, visual surveys and wind-tunnel tests are carried out. The Central Electricity Generating Board places great importance on obtaining the fullest degree of acceptance by the public for its nuclear stations and ensures that full consultation is provided with the relevant authorities at all stages of power-station development. It also provides public exhibitions, public meetings and liaison with the local inhabitants. Recruitment of station staff where possible from the immediate area of the station and formation of sports and social clubs are two of the practical steps which help to integrate the station into the local community. Whilst the current energy crisis has reinforced the need for a substantial nuclear programme, possible ways of further reducing the impact of nuclear stations on the environment are being considered. The paper concludes that sufficient nuclear sites can be provided for future needs but that continuing effort will be required to ensure public acceptance. (author)

  17. Meteorological survey for the siting of a nuclear power station in the southern coastal plain: Pt. 1

    International Nuclear Information System (INIS)

    A meteorological survey was carried out in the framework of an overall examination of the optimal siting of an inland nuclear power station. Its object was to provide the information required for the siting of such a power station, the evaluation of the hazards involved in it and the design of the reactor and of its cooling towers. The survey is based on data collected at the Sde Moshe, Lahav and Havat Habessor meteorological stations. This report presents the procedure, the raw data handling, their computerized processing, the checking of the results and the subsequent calculations that yielded the basic data for the survey. The report also presents the results of the analysis of the data gathered at the Sde-Moshe station. The results are given in a form appropriate for the determination of general climatic background, the design of cooling towers and other installations, and the optimal siting of a nuclear power station and for hazard evaluation

  18. The AP1000{sup R} nuclear power plant innovative features for extended station blackout mitigation

    Energy Technology Data Exchange (ETDEWEB)

    Vereb, F.; Winters, J.; Schulz, T.; Cummins, E.; Oriani, L. [Westinghouse Electric Company LLC, 1000 Westinghouse Drive, Cranberry Township, PA 16066 (United States)

    2012-07-01

    Station Blackout (SBO) is defined as 'a condition wherein a nuclear power plant sustains a loss of all offsite electric power system concurrent with turbine trip and unavailability of all onsite emergency alternating current (AC) power system. Station blackout does not include the loss of available AC power to buses fed by station batteries through inverters or by alternate AC sources as defined in this section, nor does it assume a concurrent single failure or design basis accident...' in accordance with Reference 1. In this paper, the innovative features of the AP1000 plant design are described with their operation in the scenario of an extended station blackout event. General operation of the passive safety systems are described as well as the unique features which allow the AP1000 plant to cope for at least 7 days during station blackout. Points of emphasis will include: - Passive safety system operation during SBO - 'Fail-safe' nature of key passive safety system valves; automatically places the valve in a conservatively safe alignment even in case of multiple failures in all power supply systems, including normal AC and battery backup - Passive Spent Fuel Pool cooling and makeup water supply during SBO - Robustness of AP1000 plant due to the location of key systems, structures and components required for Safe Shutdown - Diverse means of supplying makeup water to the Passive Containment Cooling System (PCS) and the Spent Fuel Pool (SFP) through use of an engineered, safety-related piping interface and portable equipment, as well as with permanently installed onsite ancillary equipment. (authors)

  19. Two decades of commercial nuclear power. A review of nuclear power station performance in the United Kingdom

    International Nuclear Information System (INIS)

    In the 20 years since the start of the commercial nuclear power programme in the United Kingdom, the initial activities concerned with the achievement of high availability on plants of a new design have given way to those concerned with the improvement of maintenance methods and modifications to overcome obsolescence. Gas-cooled reactor designs have evolved and construction techniques have been developed to improve reactor output and steam conditions. Modern methods of engineering analysis and in-service inspection are being applied to plants conceived in the early 1950s in order to re-evaluate their adequacy in the light of current practice. One of the outstanding successes of the Magnox programme has been the reliability of the fuel. Fuel development and post-irradiation inspection programmes have given rise to increased endurance and utilization without loss of plant availability. The substantial economic advantage provided by nuclear generation dictates that the plant should be operated at high load factors to the end of its life. Recruitment policies, organization structures and training schemes have been designed to provide adequate numbers of suitably qualified staff and to ensure succession in an ageing staff population. A power station cannot be operated in isolation from the community in which it is situated. The means by which the community is kept informed in both normal and emergency conditions have been developed to match the changing attitudes of the population towards nuclear power. This paper reviews briefly the evolution of gas-cooled reactors in the UK, describes the improvements in fuel performance which have been achieved, discusses factors which will determine the life of plants and identifies significant features of the operation and maintenance of nuclear stations. (author)

  20. The emergency medical programs of japan and foreign countries for radiation accidents in nuclear power stations

    International Nuclear Information System (INIS)

    In our country, the medical emergency programs for the people living near nuclear power stations are well organized, however, preparation of medical staffs who are well trained is considered to be not sufficient. In the USA, on call 24 hours response to a radiological emergency is provided and funded by Department of Energy(DOE) or electric companies. Especially, REAC/TS is a part of DOE response network, in which there are provided well-trained physicians, nurses, health physicists, coordinators and support personnels. In United Kingdom, National Radiological Protection Board(NRPB) is responsible to a radiological emergency program. Each nuclear power station has its own emergency program consisting of a team of physicians, nurses and health physicists. In France, French Atomic Energy Commission (CEA) is a responsible agency for a radiological emergency program. On call 24 hours response to a radiological emergency is provided in Fontenay-aux Roses Institute and Curie Institute. Curie Institute also responds to radiological emergencies in other countries at the request of WHO. In Germany(West Germany), compulsory assurance system covers a radiological emergency program and a radiological protection. There are seven centers in West Germany, in which well-trained medical staffs are provided against radiological injuries. In this report, I tried to propose a new concept about emergency medical programs for nuclear power station accidents in Japan. I think it is a very urgent theme to provide on call 24 hours radiological emergency program, in which patients suffered from acute radiation sickness with internal contamination or contaminated radiation burns will be treated without any trouble. We have to make our best efforts to complete basic or clinical research about radiation injuries including bone marrow transplantation, radioprotectors, chelating agents and radiation burns etc. (J.P.N.)

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  3. Population distribution, food production and other aspects in the vicinity of the Embalse Nuclear Power Station

    International Nuclear Information System (INIS)

    The paper presents some of the results of the pre-operational studies carried out in the vicinity of the site of the Embalse Nuclear Power Station, which is being built in the Province of Cordoba, Rio Tercero, next to the lake Embalse. The studies cover population distribution, food production, and other local aspects. The low population in the vicinity of the site increases in summer due to tourism. Main use of the land is grazing and cereal production. Milk production is small, but some is produced near the site. Other aspects of the study are presented in other papers of the Seminar. (author)

  4. Estimating the efficiency from using hydrogen toppings at nuclear power stations

    Science.gov (United States)

    Portyankin, A. V.; Khrustalev, V. A.

    2011-09-01

    A low-cost version of modernizing a nuclear power station is considered in which the main profile (standard size) of the power unit is retained and insignificant changes are made in the turbine unit's operational parameters. These changes consist in that steam supplied to the high-pressure cylinder is subjected to slight initial superheating, and that that the design superheating of steam upstream of the low-pressure cylinder is increased to some extent. In addition, different versions that can be used for heating the working steam to the required temperatures in the H2/O2 steam generator's mixing chamber are analyzed.

  5. Enhancements to inventory control procedures used at Koeberg nuclear power station

    International Nuclear Information System (INIS)

    In industry today, industrial engineers are forced to seek new and innovative ideas to reduce costs. This can often be accomplished by simplified or modernized operational procedures. With the advancement in computer technology, operational procedures can be enhanced. Despite the fact that Eskom's Koeberg nuclear power station is one of a kind in Africa, it, like most other industries requires a large stock holding capacity. There are currently 25 000 stock items in the Koeberg Stores Information System. Controlling all of these items is no minor task and management is continually trying to optimise the inventory control procedures. One of these procedures is described. 3 refs., 1 fig

  6. Reasons for above average operating results at Beznau and Muehleberg nuclear power stations

    International Nuclear Information System (INIS)

    The operational performance of a nuclear power station is determined by the interaction of many different factors. Consequently no simple or plausible reasons can be quoted for the above average operating results of the first three Swiss nucelar power plants, Beznau I, Beznau II und Muehleberg. Various points, which, according to the opinion of the author, have the greatest influence on the operating results, are indicated. Theses aspects include quality of plant, design features, qualifications and trainung of personnel, organization, operational management, maintenance planning, applicability of the state of technology and supervision by the authorities. (orig.)

  7. Establishment of high ground power supply center at Onagawa Nuclear Power Station

    International Nuclear Information System (INIS)

    A large earthquake occurred on March 11, 2011 and tsunami was generated following it. The East Japan suffered serious damage by the earthquake and tsunami. This is called the Great East Japan Earthquake. Onagawa Nuclear Power Station (NPS) is located closest to the epicenter of Great East Japan Earthquake. We experienced intense shake by the earthquake and some flooding from the tsunami, however, we have succeeded safely cold shutdown of the reactors. In this paper, we introduce the reinforcement of power supply to increase reliability and power supply center with high voltage electric power supply trucks which is original treatment at Onagawa NPS. (author)

  8. Activities of seismic safety enhancement on equipments and components in Kashiwazaki Kariwa Nuclear Power Station

    International Nuclear Information System (INIS)

    This article introduced seismic safety enhancement measures and upgrade of seismic evaluation methods on equipments and components in Kashiwazaki Kariwa Nuclear Power Station. Reinforcement works for seismic safety against the earthquake of 1000 gal at the bed rock of reactor building had been made on pipe support structure, fuel handling machine and ceiling mounted crane of reactor building using upgraded seismic response analysis. As for upgrade of seismic evaluation methods, hysteresis characteristics of reactor base structure and seismic affected fatigue of piping had been evaluated as well as forced vibration test of component base anchorage zone and underwater vibration test of spent fuel storage rack to obtain damping constant. (T. Tanaka)

  9. Measuring device for determining the radiation in a nuclear power station

    International Nuclear Information System (INIS)

    One can use an ionization chamber to determine the radiation in a nuclear power-station, whose electrodes are connected via a plug and socket connection to a cable. To make the plug and socket connection resistant to a LOCA (loss of coolant accident), a tubular case is provided with a centring flange projecting into a baseplate of the ionisation chamber. Cable cores with a screen passing through the tube are taken through sleeves, which are cast with a silicon casting mass completely penetrating the screen. (orig.)

  10. Determination of stability of saturated sands of Bredasdorp and Varswater Formations: Koeberg nuclear power station

    International Nuclear Information System (INIS)

    The planning of the Koeberg nuclear power station was postulated on the basis of possible seismic ground movements of sufficient intensity to cause liquefaction of the sand overlying the bedrock. Where seismic instability may occur, it is normally necessary for the potentially liquefiable soils to be removed and replaced with a stable material. The site investigations were therefore designed to evaluate the soils parameters necessary for the safe excavation of sand. The properties of potential backfill materials were studied and requirements for selective stockpiling of material from the excavation defined

  11. Effects of entrainment through Oconee Nuclear Station on carbon-14 assimilation rates of phytoplankton

    International Nuclear Information System (INIS)

    Carbon assimilation rates of phytoplankton communities entrained through Oconee Nuclear Station were measured on six dates during 1974. Thermal, mechanical, condenser, and multiple entrainment effects on uptake rates were compared by incubating samples in vitro in controlled-temperature water baths. Duplicate light and dark bottles containing water from four cooling-system locations were exposed to temperatures approximating intake and discharge temperatures. The relationships were variable, but exposure of the hypolimnetic intake water at near-discharge temperatures (thermal effect) stimulated primary productivity in four of six experiments. Multiple entrainment and mechanical effects caused no consistent change in assimilation rates

  12. Summary of startup test of Shika Nuclear Power Station Unit No.2

    International Nuclear Information System (INIS)

    The Shika Nuclear Power Station Unit No.2 was put into commercial operation in March 2006, which is the 1358 MWe advanced boiling water reactor (ABWR) incorporating plant experiences and latest technologies of more improved stable operation, reliability and maintenance. For example, SUMIT (Spectral Unit Module Initial Core) was equipped to flatten power peaking for fuel burnup extension and also compact ASD (Adjustable Speed Drive) for recirculation internal pumps using insulated gate bipolar transistor elements. The reactor start-up tests were performed step-by-step about for eleven months from April 2005 to confirm the required performance with safe and stable operation. (T. Tanaka)

  13. Summary of Great Japan Earthquake response at Onagawa Nuclear Power Station and further safety improvement measures

    International Nuclear Information System (INIS)

    A large earthquake occurred on March 11, 2011 and tsunami was generated following it. The East Japan suffered serious damage by the earthquake and tsunami. This is called the Great East Japan Earthquake. Onagawa Nuclear Power Station (NPS) is located closest to the epicenter of Great East Japan Earthquake. We experienced intense shake by the earthquake and some flooding from the tsunami, however, we have succeeded safely cold shutdown of the reactors. In this paper, we introduce summary of Great East Japan Earthquake response at Onagawa NPS and safety improvement measures which are based on both experience of Onagawa NPS and lesson from Fukushima Daiichi NPS accident. (author)

  14. Treatment of accidents in the operating manual of the Gundremmingen Nuclear Power Station

    International Nuclear Information System (INIS)

    The reactor protection panel and the accident instrument systems (KTA 3502) are the principal means available to the shift personnel to detect accident conditions. The most important written document to be referred to is Part 3 of the Operating Manual, which contains a detailed outline of the measures to be taken by personnel in case of an accident. When those paragraphs were written for the two new boiling water reactor units of the Gundremmingen Nuclear Power Station, it was decided to give up to so-called event-oriented method and replace it by a method based on the objectives to be achieved by protective measures. (orig.)

  15. Applicability of radioactive waste treatment using ceramics at Fukushima Daiichi Nuclear Power Station

    International Nuclear Information System (INIS)

    The present report concerns investigation of the radioactive waste treatment using specifically ceramics to find out the applicability for remediation of the environment contaminated with radioactivity followed by the reactor accident at Fukushima Daiichi Nuclear Power Station and to investigate its plausibility as a treatment process. Radioactive wastes (waste zeolite, crystalline silicotitanates, and Ni-ferrocyanide with some organic coagulating materials) presumably produced during treatment processes are listed, potential applicability of ceramics are investigated from the point of view of waste-volume reduction and immobilization of radioactive materials and process flows are made. Decontamination methods of waste metals and concretes are summarized. (S. Ohno)

  16. Problems of implementing a large contract abroad: the Cordoba nuclear power station

    Energy Technology Data Exchange (ETDEWEB)

    Caruso, P.

    1984-11-01

    The building of Argentina's second nuclear power station proved to be a true test of project-management skills: the contract was to be a joint effort between an Italian and a Canadian company, to be implemented in a country thousands of miles away; the Argentinian government changed four times during the course of the project; and the local currency was always unstable and unpredictable. The various difficulties that arose, and how they were solved, are described, and the role of the project management is evaluated.

  17. Problems of implementing a large contract abroad: the Cordoba nuclear power station

    International Nuclear Information System (INIS)

    The building of Argentina's second nuclear power station proved to be a true test of project-management skills: the contract was to be a joint effort between an Italian and a Canadian company, to be implemented in a country thousands of miles away; the Argentinian government changed four times during the course of the project; and the local currency was always unstable and unpredictable. The various difficulties that arose, and how they were solved, are described, and the role of the project management is evaluated. (author)

  18. Liquid relief valve failure simulation in the Embalse nuclear power station

    International Nuclear Information System (INIS)

    Simulations of the failure (open) of a liquid relief valve in the Embalse Nuclear Power Station primary heat transport system have been performed using the Firebird III computer code. Results show that, without any action by the operators, and if the degasser 'bottles up', then pressure will increase, causing the relief degasser condenser valve to open. Several actions that might be taken to prevent this and the resulting loss of heavy water have been analyzed. The results of the simulations indicate that the best action is to reduce power when the pressurizer level stops decreasing. 1 ref., 10 figs

  19. Replacement of bearing journals on heat transport pumps at the Wolsung nuclear generating station

    International Nuclear Information System (INIS)

    The major details of the inspection and replacement of the bearing journals on each of the four heat transport pumps (HTPs) at Wolsung nuclear generating station in Korea are presented in this paper. Investigation following fracture of one of the journals in 1985 revealed that it was excessively hard. The journal material (ASTM A296 CA 40) is considered to be prone to stress corrosion fatigue if the hardness exceeds Rc 40. In 1986 May, during a planned outage, the HTPs were disassembled, the journals were inspected, found to be excessively hard, and all were replaced. At the same time, the pump to motor couplings were all refurbished to ensure proper alignment

  20. Gas-turbine plants for nuclear power stations with CO2 as working medium

    International Nuclear Information System (INIS)

    The study deals with designing and optimizing gas-turbine plants for nuclear power stations with carbon dioxide as working fluid. Only such CO2 processes were studied in detail where compression takes place near the saturation curve. The first part of the paper is concerned with the selection of favorable cyclic processes. The second part deals with the optimization of the selected processes with regard to thermal efficiency and economy where the optimal turbine-inlet pressure and the most favorable expansion ratio are to be found. (orig./HP)

  1. VANTAGE 5 PWR fuel assembly demonstration program at Virgil C. Summer nuclear station

    International Nuclear Information System (INIS)

    VANTAGE 5 is an improved PWR fuel product designed and manufactured by Westinghouse Electric Corporation. The VANTAGE 5 fuel design features integral fuel burnable absorbers, intermediate flow mixer grids, axial blankets, high burnup capability, and a reconstitutable top nozzle. A demonstration program for this fuel design commenced in late 1984 in cycle 2 of the Virgil C. Summer Nuclear Station. Objectives for VANTAGE 5 fuel are reduced fuel cycle costs, better core operating margins, and increased design and operating flexibility. Inspections of the VANTAGE 5 demonstration assemblies are planned at each refueling outage

  2. Sizewell nuclear power station: investigation of radiation exposure pathways from liquid effluents. Local habits survey 1981

    International Nuclear Information System (INIS)

    A habits and consumption survey to review radiation exposure pathways due to liquid effluents released from the CEGB Sizewell site is described. It is relevant to both the Sizewell A and proposed Sizewell B nuclear power stations. The main objectives are to provide input data to a radiological assessment by means of identifying critical groups and to provide data for guidance in a review of environmental monitoring programmes. The way in which data for the different pathways should be combined in order to aid the subsequent radiological assessment is discussed. Recommendations are made for adjustments to the present monitoring programmes. (U.K.)

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  6. The Iran-1 and Iran-2 nuclear power station on the Persian Gulf

    International Nuclear Information System (INIS)

    Iran is a country with large oil reserves which, however, are exploited only very carefully because of ther importance for exports. In the light of this policy it was decided to make increasing use of nuclear energy for the country's electricity supply. Under the 8th Iranian five year plan, a total installed generating capacity of 56,000 MW is foreseen by 1993, of which 24,400 MW will be in nuclear power plants. This large construction program of nuclear power stations is implemented by the Atomic Energy Organization of Iran, AEOI, which started negotiations with potent nuclear industries of various industrialized countries in early 1974. In November 1974, these discussions led to a letter of intent with the German Kraftwerk Union AG (KWU) for the turnkey erection of the first Iranian nuclear power plant, Iran-1 and Iran-2, with two units of 1,300 MW on a site on the Persian Gulf. The siting decision was taken in favor of the Halileh area located some 18 km from the seaport of Bushehr. Construction work on the site began in July 1975. The delivery dates are December 1, 1980 for Iran-1 and November 1, 1981 for Iran-2. (orig.)

  7. Radiation monitoring using manned helicopter around the Fukushima Daiichi Nuclear Power Station in the fiscal year 2013 (Contract research)

    International Nuclear Information System (INIS)

    By the nuclear disaster of Fukushima Daiichi Nuclear Power Station (NPS), Tokyo Electric Power Company (TEPCO), caused by the East Japan earthquake and the following tsunami occurred on March 11, 2011, a large amount of radioactive materials was released from the NPS. These results of the aerial radiation monitoring using the manned helicopter in the fiscal 2013 were summarized in the report. (author)

  8. Construction progress of Shimane Nuclear Power Station Unit No.3 supplied for the Chugoku Electric Power Co., Inc

    International Nuclear Information System (INIS)

    Hitachi-GE Nuclear Energy, Ltd. is now constructing Shimane nuclear power station unit No.3 supplied for The Chugoku Electric Power Co., Inc. Commercial operation is planned to start in December 2011. Hitachi's state-of-the-art construction technologies are applied and all construction milestones have been on schedule without any problems. (author)

  9. On registration of previously unannounced USA underground nuclear tests by seismic stations of the former Soviet Union

    International Nuclear Information System (INIS)

    Materials, related to registration by the former USSR seismic stations of 61 out of 204 newly-announced low-capacity underground nuclear tests at the USA Nevada test site are presented. The explosions seismograms are also given. Attention is paid to the efficiency of identification and accuracy of determination of the parameters of underground nuclear explosions

  10. 76 FR 30204 - Exelon Nuclear, Dresden Nuclear Power Station, Unit 1; Exemption From Certain Security Requirements

    Science.gov (United States)

    2011-05-24

    ..., 2009 (74 FR 13926). The revised regulation stated that it was applicable to all Part 50 licensees. The... FR 28480). Based upon the environmental assessment, the Commission has determined that issuance of... From the Federal Register Online via the Government Publishing Office NUCLEAR...

  11. 75 FR 11205 - Entergy Nuclear Operations, Inc; Pilgrim Nuclear Power Station Environmental Assessment and...

    Science.gov (United States)

    2010-03-10

    ... revisions to 10 CFR Part 73, as discussed in a Federal Register notice dated March 27, 2009 (74 FR 13967... Requirements, 74 FR 13926, 13967 (March 27, 2009)]. The NRC staff's safety evaluation will be provided in the... From the Federal Register Online via the Government Publishing Office NUCLEAR...

  12. Safety of Eastern-European nuclear power stations - an interim statement

    International Nuclear Information System (INIS)

    Since the beginning of the nineties, the western industrial nations have strengthened their efforts to institute national and international support programmes in order to enhance the safety of the WWER-440/230, WWER-440/213, WWER-1000/320, and RBMK-1000 type reactors in the new independent states of the former Soviet Union and the central- and eastern-European states. At the Kozloduy nuclear power station, for instance, measures were taken that enhance the technical safety of the plant. Moreover, contributions were made towards strengthening the authorities in charge of nuclear safety and improving infra-structure. In spite of this, there are still considerable safety deficits, which the economic situation, especially in the Ukraine, will not permit to remedy quickly. (DG)

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

    International Nuclear Information System (INIS)

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

  14. Stages in planning and construction of the Muelheim-Kaerlich nuclear power station

    International Nuclear Information System (INIS)

    On October 23, 1972, RWE gave a letter of intent and on January 9, 1973 an order for the construction of a nuclear power plant on a turn-key basis to the consortium of BBC, BBR and Hochtief. The power plant in question was the Muelheim-Kaerlich nuclear power station with a pressurized-water reactor of a gross efficiency of 1,295 MWe. After considerable delay of the project, the first building permit was issued to the builder-owner on January 15, 1975, and the constructional work on the building site started immediately afterwards. As the planning and constructional work has so far been carried out according to schedule and the consortium intends to keep the effects of the belated license as small as possible, the start-off of the plant will probably be in summer 1979 if the constructional work is not interrupted. (orig./AK)

  15. Experience with reactor power cutback system at Palo Verde nuclear generating station

    International Nuclear Information System (INIS)

    Palo Verde Nuclear Generating Station (PVNGS) is a three unit site which illustrates System 80 nuclear steam supply system (NSSS) design. The System 80 NSSS is the Combustion Engineering (C-E) standard design rated at 3817 Mwth. PVNGS Units 1 and 2 achieved commercial operation on February 13, 1986 and September 22, 1986, respectively, while Unit 3 has a forecast date for commercial operation in the third quarter of 1987. The System 80 design incorporates a reactor power cutback system (RPCS) feature which reduces plant trips caused by two common initiating events: loss of load/turbine trip (LOL) and loss of one main feedwater pump (LOMFWP). The key design objective of the RPCS is to improve overall plant availability and performance, while minimizing challenges to the plant safety system

  16. Evaluation of the radiological impact due to the operation of nuclear power stations in Argentina

    International Nuclear Information System (INIS)

    There are at present in Argentina two commercial nuclear power stations in operation, Atucha I and Embalse, generating about 10% of the total electrical energy output. Atucha I NPP, equipped with a pressure vessel reactor, has an output capacity of 345 MW(e), while Embalse NPP is equipped with Candu-type reactor and its output capacity is 670 MW(e). Both plants operate with natural uranium as a fuel, and heavy water as a coolant and as a moderator. During the operation of both nuclear installations, radioactive fission and activation products are produced. These radioactive materials are for the most part retained within the fuel elements. Most of the radionuclides with diffuse into or are formed within the coolant are removed by the gaseous and liquid waste processing systems. Low-level releases which occur during normal operation are controlled and monitored. Radionuclides may reach the environment through either the gaseous or liquid effluents streams

  17. Radioprotection training of personnel from firms involved with nuclear power stations

    International Nuclear Information System (INIS)

    In view of the training obligations implied in the clauses of the decree of April 28th 1975, relative to the protection of workers against the dangers of ionizing radiations in basic nuclear installations, the APAVE were asked very early to take on the radioprotection training of personnel from firms involved with Nuclear Power Stations. Over more than three years nearly 5.000 people have followed these training courses. To accomplish this programme the APAVE adopted a special procedure, i.e: formation of a preparatory group; analysis and definition of the programme; plan of action and working out of teaching methods and tools; organisation and animation of the courses. This report attemps to retrace these proceedings and sums up the action so far

  18. IEEE standard: criteria for protection systems for nuclear power generating stations

    International Nuclear Information System (INIS)

    These criteria establish minimum requirements for the safety-related functional performance and reliability of protection systems for stationary, land-based nuclear reactors producing steam for electric power generation. Fulfillment of these requirements does not necessarily fully establish the adequacy of protective system functional performance and reliability. On the other hand, omission of any of these requirements will, in most instances, be an indication system inadequacy. For purposes of these criteria, the nuclear power generating station protection system encompasses all electric and mechanical devices and circuitry (from sensors to actuation device input terminals) involved in generating those signals associated with the protective function. These signals include those that actuate reactor trip and that, in the event of a serious reactor accident, actuate engineered safeguards such as containment isolation, core spray, safety injection, pressure reduction, and air cleaning

  19. Review of safety system performance and its safety implications at Bruce A nuclear generating station

    International Nuclear Information System (INIS)

    The reactor shutdown system performance with respect to meeting all nuclear safety and regulatory requirements is discussed for the Bruce A nuclear generating station. The operating experience at Bruce A spans over 17 years starting from September 1977. The two shutdown systems have performed well over the years in spite of constantly more stringent safety requirements for the safe operating envelope and new regulatory requirements. The system surveillance programme has been effective in identifying problems. As a result, several changes to system design, operating procedures and testing and maintenance have been made to improve the system performance. A life-cycle management programme is in place, in which ageing-related problems are closely monitored. Testing programmes are being reassessed and system upgrade for environmental qualification is in progress. Lessons learned over the years and corrective actions taken are discussed. (author). 4 figs, 1 tab

  20. Experimental and analytical qualification of elastomeric seals in nuclear power stations

    International Nuclear Information System (INIS)

    During refueling of the pressurized water reactor type of nuclear power stations, the cavity surrounding the top of the reactor is filled with water to maintain acceptable levels of radiation while fuel is being transferred from the reactor. A generic illustration of this type of seal is shown which was a commonly used pneumatic seal. This particular seal has continued to receive some attention since I ampersand E Bulletin 84-03 was issued. While most plants addressed this issue at some time in the past, some plants continue to address concerns about other types of seals located in the plant. At the time of the I ampersand E Bulletin 84-03, other elastomeric-type seals were examined at meetings such as those held under the auspices of the Institute of Nuclear Power Operations. This paper addresses the testing performed on the seal used in refueling as well as the analytical method employed to accomplish the same purpose

  1. An aerial radiological survey of the Quad Cities Nuclear Power Station and surrounding area, Cordova, Illinois

    International Nuclear Information System (INIS)

    An aerial radiological survey was conducted over the Quad Cities Nuclear Power Station in Cordova, Illinois, during the period May 9 through May 18, 1989. The survey was conducted at an altitude of 61 meters (200 feet) over a 65-square-kilometer (25-square-mile) area centered on the power station. The purpose of the survey was to document the terrestrial gamma environment of the Quad Cities Power Station and surrounding area and to determine any radiological impact on the area over the past twenty years. The results of the aerial survey are reported as inferred gamma radiation exposure rates at 1 meter above ground level in the form of a contour map. Outside the plant boundary, exposure rates were found to vary between 5 and 15 microroentgens per hour (μR/h) and were attributed to naturally-occurring uranium, thorium, and radioactive potassium gamma emitters. The aerial data were compared to ground-based ''benchmark'' exposure rate measurements and radionuclide assay of soil samples obtained within the survey boundary. The ground-based measurements were found to be in good agreement with those inferred from the aerial measuring system

  2. Draft environmental impact statement. Virgil C. Summer Nuclear Station, Unit No. 1

    International Nuclear Information System (INIS)

    Operation of the Virgil C. Summer Nuclear Station Unit 1 in Fairfield County, South Carolina is proposed. The station, situated one mile east of the Broad River near Parr, would employ a pressurized water reactor to produce a maximum of 2775 megawatts (MW) of thermal energy. A steam turbine-generator would use this heat to produce a net ouptut of 900 MW of electrical energy. Cooling water, removed from and returned to the Monticello Reservoir at a rate of 534,000 gallons per minute, would dissipate the unit's excess heat. The unit woulld transmit electrical energy through 2.6 miles of 115-kilovolt (kV) line and 117.5 miles of 230-kV line. The station would generate 475 million kilowatt-hours of electricity, contribute $18.5 million county, state, and federal taxes, add 362 jobs to the local employement rolls, and create a 300-acre subimpoundment for recreational use. Land required for site development and transmission line rights-of-way would remove 399 acres of farmland as well as 2217 acres of forestland, resulting in a loss of 20 million board feet of timber over the 30-year life of the facilities. Water releases from the cooling system would raise the temperature of the reservoir

  3. Experimental and Theoretical Dynamic Study of the Aagesta Nuclear Power Station

    International Nuclear Information System (INIS)

    The report presents a final review and summary of all dynamic investigations of the Aagesta nuclear power station. Special attention is paid to the final and unpublished experiments performed in 1965-66. These experiments are discussed and compared to the theoretical predictions. Transfer functions and step responses were measured by perturbations in reactivity and steam load. Three methods were used for transfer function measurements: step functions, trapeze waves and multifrequency functions based on the pseudo-random binary sequence (PRBS). From the frequency analysis we found that the different perturbation methods led to quite consistent results. For the Agesta application the PRBS method is demonstrated to be an accurate and practical method for obtaining experimental transfer functions. The step technique did not give satisfactory results for frequencies above approximately 0.01 Hz. From the static check of the model we may conclude that the experiments agree fairly well mutually and with theory. The measured reactivity coefficients tend to be smaller than the predicted ones. The predicted transients compare well with the measured ones. However, there is a tendency to more peaked power transients from the model. This is believed to be due to the assumption that the moderator could be regarded as one channel. The dynamic experiments carried out at the Agesta nuclear power station demonstrate both the inherent stability and the safety of this plant

  4. Personnel exposure control system with auto thermoluminescence dosimeter in Shimane Nuclear Power Station

    International Nuclear Information System (INIS)

    In the past, film badges and pocket dosimeters were put on the persons who enter a controlled area in a nuclear power station to measure the external radiation exposure. For these, read out error or mistake, delay in taking out the result, trouble for monitoring many persons, etc. were problems. To solve these problems, the auto thermoluminescence dosimeter (ATLD) system has been introduced in Shimane Nuclear Power Station in place of pocket dosimeters since the second half of fiscal 1978. The outline of the system and the composition and software of the TLD automatic readout system are described. For the control of access to controlled areas, workers are forced to pass the check point where watchmen check everyone's ID card, and subjected to the check-up with the TLD automatic readout device. The checking items in the case of entering the areas are: (1) confirmation of licensee, (2) confirmation of the term of validity for the medical examination on ionizing radiation, (3) checking for exposure dose compared to the controlled exposure level, (4) confirmation of time limit to stay in controlled areas, and (5) TLD element annealing condition. The checking items in the case of leaving the areas are: (1) checking for identifying the TLD element that the personnel has brought in, (2) exposure dose compared to the controlled exposure level, (3) time for which the personnel stayed in controlled areas. (Wakatsuki, Y.)

  5. The development of access control system in Fukushima No.2 nuclear power station

    Energy Technology Data Exchange (ETDEWEB)

    Ookubo, S.; Nakai, Y.; Oohira, N.; Kishishita, S. [Tokyo Electric power Co., Tokyo (Japan); Kobayashi, H.; Sano, F. [Fuji Electric Co., Tokyo (Japan); Masuda, M.; Tajima, T.; Oohira, K. [Toshiba Corporation, Tokyo (Japan)

    2002-07-01

    A new radiation work control system has been developed for controlling the entrance and exit of workers from the radiation controlled area in a nuclear power station and has been run in the Fukushima No. 2 Nuclear Power Station of Tokyo Electric Power Co., Inc. since October, 1999. The system is designed to reduce workers burden by simplifying the operation of each equipment that controls access to radiation controlled areas, and to minimize radiation exposure by automatically acquiring dose data during each access and each task. The new system adopted electronic personal dosimeters (gamma radiation EPD) which permit data collection by radio communication, thus improving the conventional alarm-equipped personal dosimeter (EPD) and increasing reliability as primary dosimeters. Furthermore, additional electronic personal dosimeters capable of measuring beta radiation (gamma and beta radiations EPD) were also utilized in specific tasks in October 2001. After a six-month test run of these EPDs, the film badges were discontinued in April 2002 and replaced solely with the EPDs. EPDs are now used as the primary dosimetry for radiation workers.

  6. Deep foundation rebound instrumentation at the Grand Gulf Nuclear Power Station

    International Nuclear Information System (INIS)

    Removing an extensive amount of overburden can initiate adjustments in the foundation mass. Rebound adjustments induced by this removal include, in addition to elastic response, elements of visco-elastic and plastic response which have to be taken into account when the foundation is loaded by subsequent construction. The accurate measurement of foundation response can be important in the design and construction of deep foundations and can be essential in the construction of very deep foundations. In 1974, a large foundation excavation was undertaken for the two unit Grand Gulf Nuclear Station. Overburden removal ranged in depth from 65 feet in the turbine area to 110 feet in the containment area. Very long, rod-type Multiple Position Borehole Extensometers measured the rebound. The design of the extensometers, and the dimensions of the installed instruments, are discussed. Graphs are included which show the adjustments measured by each extensometer during the deepening of the excavation. The measured rebound for each transducer package of each extensometer is summarized. The data are compared to predicted values based on a mathematical model developed using laboratory test results and empirical methods. The resulting information forms part of the permanent record of construction for the nuclear power station

  7. Design and construction of seabed water intake and discharge tunnels in Shika Nuclear Power Station

    International Nuclear Information System (INIS)

    As the intake and discharge channels for cooling seawater in the Shika Nuclear Power Station, Hokuriku Electric Power Co., Inc., seabed tunnel type was adopted. In these seabed tunnels, the earth covering under seabed surface is shallow (about 25 m at minimum), and the distribution of the ground quality with relatively many joints though it is hard is observed, so because the water permeability as the seabed tunnels is relatively high, the fine executing technology is required. In this report, the design of these seabed tunnels and the results of construction at the present stage are outlined. No.1 plant in the Shika Nuclear Power Station is a BWR plant with 540 MWe, and the site of about 1.6 million m2 is located on the west coast of Noto Peninsula. The start of commercial operation is scheduled in March, 1993. The cooling seawater required for the operation is about 40 m3/s, and it is taken from the intakes installed at about 300 m offshore, and discharged in the sea at about 500 m offshore. The topography and geological features, the planning and design of intake and discharge tunnels and their construction at present stage are reported. (K.I.)

  8. Lessons learned in digital upgrade projects digital control system implementation at US nuclear power stations

    International Nuclear Information System (INIS)

    AREVA NP has gained significant experience during the past five years in digital upgrades at operating nuclear power stations in the US. Plants are seeking modernization with digital technology to address obsolescence, spare parts availability, vendor support, increasing age-related failures and diminished reliability. New systems offer improved reliability and functionality, and decreased maintenance requirements. Significant lessons learned have been identified relating to the areas of licensing, equipment qualification, software quality assurance and other topics specific to digital controls. Digital control systems have been installed in non safety-related control applications at many utilities within the last 15 years. There have also been a few replacements of small safety-related systems with digital technology. Digital control systems are proving to be reliable, accurate, and easy to maintain. Digital technology is gaining acceptance and momentum with both utilities and regulatory agencies based upon the successes of these installations. Also, new plants are being designed with integrated digital control systems. To support plant life extension and address obsolescence of critical components, utilities are beginning to install digital technology for primary safety-system replacement. AREVA NP analyzed operating experience and lessons learned from its own digital upgrade projects as well as industry-wide experience to identify key issues that should be considered when implementing digital controls in nuclear power stations

  9. Simulation of the operation of a 900 MW PWR nuclear power station in the Casoar project

    International Nuclear Information System (INIS)

    The aim of EDF's CASOAR project is to monitor and control all generation of electricity and most of its transportation in France with a view to technical and economic optimization of its power stations connected to the grid. This monitoring takes new operating constraints into account for PWR nuclear power stations: as a consequence, a new automatic boration and dilution system will be implemented. In these conditions, it should be checked in all cases that the plants are operating normally. For a purpose of studying and simulating the interactions between the CASOAR system and a nuclear power plant, a model named OSICA has been developed by the Research and Development Division of Electricite de France. The simulation model comprises the main components presented below: - thermo-hydraulic model of a 900 MWe PWR unit with its associated regulations, - model of the reactor core, - partial representation of the interface computer, - model of the automatic boration and dilution system, - predictive computation routine used by the interface computer to ascertain the feasibility of electric programs. (authors). 9 refs

  10. Pressure-dependent fragilities for piping components: Pilot study on Davis-Besse Nuclear Power Station

    International Nuclear Information System (INIS)

    The capacities of four, low-pressure fluid systems to withstand pressures and temperatures above the design levels were established for the Davis-Besse Nuclear Power Station. The results will be used in evaluating the probability of plant damage from Interfacing System Loss of Coolant Accidents (ISLOCA) as part of the probabilistic risk assessment of the Davis-Besse nuclear power station undertaken by EG ampersand G Idaho, Inc. Included in this evaluation are the tanks, heat exchangers, filters, pumps, valves, and flanged connections for each system. The probabilities of failure, as a function of internal pressure, are evaluated as well as the variabilities associated with them. Leak rates or leak areas are estimated for the controlling modes of failure. The pressure capacities for the pipes and vessels are evaluated using limit-state analyses for the various failure modes considered. The capacities are dependent on several factors, including the material properties, modeling assumptions, and the postulated failure criteria. The failure modes for gasketed-flange connections, valves, and pumps do not lend themselves to evaluation by conventional structural mechanics techniques and evaluation must rely primarily on the results from ongoing gasket research test programs and available vendor information and test data. 21 refs., 7 figs., 52 tabs

  11. Environment and ecology in the design and construction of a nuclear power station

    International Nuclear Information System (INIS)

    The purpose of the studies on the environment of nuclear stations is to reduce changes to the surroundings as much as possible in order not to interfere with ecosystems and consequently impede human activities. A nuclear power station implies heat discharges, radioactive effluent and wastes, produces a certain sound level and creates aesthetic problems of space occupation. The main questions dealt with are those of heat discharge and noise, together with architectural and aesthetic problems. In the first two cases the intention is to define as accurately as possible the levels reached by the temperature or noise parameter. Where noise is concerned it is enough to know these levels in order to define an eventual hindrance to the target in question, the human being in this case. For heat fluxes man is not directly involved and further research is planned to identify the sensitivity of plants and animals. Since the environment also covers aesthetics, an effort is made to safeguard and improve the quality of the landscape

  12. Investigation of radioactive contamination at non-radioactive drains of the Tsuruga Nuclear Power Station

    International Nuclear Information System (INIS)

    In April, 1981, it was disclosed that a drainage area at the Tsuruga Nuclear Power Station was so much contaminated with radioactivites. Although Ministry of International Trade and Industry (MITI) officially provided an explanation of a process that resulted in the contamination, many problems remain unsolved on account of insufficient and limited investigations. The authors collected mud samples from contaminated manholes and examined radioactivities in them through the measurement of #betta#- and #betta#-spectra. Chemical separation of the samples was carried out in order to obtain precise concentration of radioactive cesium. Results are as follows: i) the concentration of radioactivities does not show monotonous decrease along the stream line but an anomalous peak at downstream manholes, ii) at the manhole specified No. 6 located rather downstream, 137Cs concentration is significantly high and the composition of radioactive nuclides is quite different from that in the other manholes, and iii) additional radioactive contamination was observed in other manholes of non-radioactive drains which would not be influenced by the accident explained by MITI. Our present work has provided much more data than by MITI and made it clear that the overall data cnnot be consistent with the simple MITI explanation; a single radioactive release accident caused the disclosed contamination. It is concluded that non-radioactive water drains at the Tsuruga Nuclear Power Station had been under continual contamination. (author)

  13. Ergonomic evaluation of CRT display in new control panels for nuclear power stations

    International Nuclear Information System (INIS)

    New control panels are to support powerfully the synthetic judgement function of operators by processing enormous plant data in the normal operation and at the time of accidents in nuclear power stations, and displaying the results in collective and ordered form on CRTs. This time, by carrying out the evaluation of new control panels using human engineering method, it was able to be confirmed that the new control panels have achieved the initial objectives, and to determine the criteria for the ergonomic evaluation of central control panels mainly with CRT display. Besides, it is considered that the application to wide range can be expected for this evaluation, not only to the CRT display system of the new control panels for nuclear power stations but also to other CRT images, therefore, the outline is reported. Chubu Electric Power Co., Inc. plans to adopt the new control panels with CRT display effectively utilizing process computers hereafter. It is necessary to give sufficient consideration to the method of using CRT images, the kinds of displayed images, colors and the form and arrangement of letters and symbols. 12 CRTs are used for the new control panel. The results are reflected to the control panel for Hamaoka No.3 plant. (Kako, I.)

  14. Management of Low Level Rad-Waste Arising From Nuclear Power Stations in Japan

    International Nuclear Information System (INIS)

    In nuclear power stations in Japan, in order to reduce radioactivity release into the environment based on the concept of ALARA, various improvements of the gaseous and liquid waste treatment systems have been made in both aspects of facilities and operations as follows: In order to reduce the release of gaseous waste, the following facilities were introduced: Charcoal bed typed noble gas holdup facility, Clean steam supply system for turbine gland seal, No leak typed valve In order to reduce the release of liquid waste, the following measures were taken: Evaporating floor drain, Evaporating laundry drain;, Demoralizing plant surplus water by a mix bed typed ion exchange resin. As a result of these counter measures, the release of gaseous and liquid radioactivity into the environment has been reduced gradually, and is now virtually 'zero' as shown in Islet. 1. Contrary to reduction in radioactivity release into the environment, residual radioactivity inside nuclear power station has made consequent increase of low level radioactive wastes in the form of solid

  15. Optimization of feedwater pump configuration for the M310 nuclear power station

    International Nuclear Information System (INIS)

    After reviewing the selection of the feed water pump configuration for Ling'ao I Nuclear Power Station and its operation, and based on the study results for several feedwater pump configurations which have been used in domestic and foreign nuclear power stations, several typical feed water pump configurations are compared and analyzed technically and economically. Considering the economics and reliability, the authors think the configuration of 2 x 50% turbine driven feedwater pump plus 2 x 25% electrical driven feedwater pump is better than that of 2 x 75% turbine driven feedwater pump plus 2 x 50% electrical driven feedwater pump. If the capability of one motor of feedwater pump can be increased from 10 MW to 14-15 MW and the voltage can be increased from 6.6 kV to 11 kV, the capacity of one electrical driven feedwater pump can reach 75% of the total capacity, then the configuration of 3 x 50% electrical driven feedwater pump is also accepted. (authors)

  16. Socio-economic impacts of nuclear generating stations: Peach Bottom case study

    International Nuclear Information System (INIS)

    This report documents a case study of the socio-economic impacts of the construction and operation of the Peach Bottom nuclear power station. It is part of a major post-licensing study of the socio-economic impacts at twelve nuclear power stations. The case study covers the period beginning with the announcement of plans to construct the reactor and ending in the period 1980 to 1981. The case study deals with changes in the economy, population, settlement patterns and housing, local government and public services, social structure, and public response in the study area during the construction/operation of the reactor. A regional modeling approach is used to trace the impact of 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

  17. Control rod cluster drop time anomaly Guandong nuclear power station (Daya bay) and Electricite de France nuclear power stations (1450 MWe N4 Series)

    International Nuclear Information System (INIS)

    The anomaly of control rod cluster drop time revealed at Guandong Nuclear Power Station in Daya Bay and in the Chooz B1 pilot unit for the N4 series, led to the replacement of the M1 type control rod cluster guide tubes with 1300 MWe PWR type guide tubes, adapted to the geometry of the Guandong reactors and the 1450 MWe reactors of the N4 series. The comparison of the drop times obtained with the 1300 MWe type control rod cluster guide 1300 MWe type control rod cluster guide tubes gave satisfactory results. These met the safety criterion for N4 series control rod cluster drop times (2.15 under hot shutdown conditions). The drop time tests which will be carried out in middle of and at the end of cycle 1 of Chooz B1 should make it possible to finally validate the solution already successfully implemented at Guandong. However, this anomaly has revealed the limits of representativeness of the experimental test loops with regard to the real reactor configuration. In view of this, it has been deemed necessary to ask Electricite de France to pursue its analysis both on the understanding of the phenomena which led to this anomaly and on the limits of the representativeness of the experimental test loops. (authors)

  18. Nuclear Power Station Kalkar, 300 MWe Nuclear Prototype Power Station with Fast Sodium Cooled Reactor (SNR-300), Safety Report Reactor Core Mark-Ia

    International Nuclear Information System (INIS)

    The nuclear power station Kalkar is a prototype with a sodium cooled fast reactor (SNR-300) and a thermal power of 762 MW. The initial licensing procedure in 1972 was based on the so-called Mark-I core. During the following years, this core underwent some changes, for instance the thickness of the radial blanket was reduced to lower the electricity generation costs, the design of the absorber systems had been further optimized, and it became clear, that a full core with plutonium from MAGNOX-reactors could not be realized and that fuel from light-water reactors had also to be used. In this licensing document the modified reactor core Mark-Ia is described together with its assemblies and their loading procedure. The content of radioactive materials and the irradiation protection measures are discussed and those accidents are describe in an enveloping manner, from which an influence of the core modification cannot be excluded. Finally, both core versions (Mark-I and Mark-Ia) are compared with each other

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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