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Sample records for atomic power company main yankee

  1. 78 FR 58571 - Maine Yankee Atomic Power Company, Connecticut Yankee Atomic Power Company, and The Yankee Atomic...

    Science.gov (United States)

    2013-09-24

    ... Yankee Companies'') from the foreign ownership, control, or domination (FOCD) requirements. ADDRESSES... law, will not present an undue risk to the public health and safety, and are consistent with the... Presents no Undue Risk to Public Health and Safety The staff finds the requirements of 10 CFR 50.38 are...

  2. Integrated Plant Safety Assessment: Systematic Evaluation Program. Yankee Nuclear Power Station, Yankee Atomic Electric Company, Docket No. 50-29. Final report

    International Nuclear Information System (INIS)

    1983-06-01

    The Systematic Evaluation program was initiated in February 1977 by the US Nuclear Regulatory Commission to review the designs of older operating nuclear reactor plants to confirm and document their safety. The review provides: (1) an assessment of how these plants compare with current licensing safety requirements relating to selected issues, (2) a basis for deciding on how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety. This report documents the review of Yankee Nuclear Power Station, operated by Yankee Atomic Electric Company. The Yankee plant is one of 10 plants reviewed under Phase II of this program. This report indicates how 137 topics selected for review under Phase I of the program were addressed. Equipment and procedural changes have been identified as a result of the review

  3. Integrated Plant Safety Assessment, Systematic Evaluation Program. Yankee Nuclear Power Station, Yankee Atomic Electric Company, Docket No. 50-29. Draft report

    International Nuclear Information System (INIS)

    1983-02-01

    The Systematic Evaluation Program was initiated in February 1977 by the US Nuclear Regulatory Commission to review the designs of older operating nuclear reactor plants to confirm and document their safety. The review provides (1) an assessment of how these plants compare with current licensing safety requirements relating to selected issues, (2) a basis for deciding on how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety. This report documents the review of Yankee Nuclear Power Station, operated by Yankee Atomic Electric Company. The Yankee plant is one of 10 plants reviewed under Phase II of this program. This report indicates how 137 topics selected for review under Phase I of the program were addressed. Equipment and procedural changes have been identified as a result of the review

  4. Seismic margin review of the Maine Yankee Atomic Power Station: Fragility analysis

    International Nuclear Information System (INIS)

    Ravindra, M.K.; Hardy, G.S.; Hashimoto, P.S.; Griffin, M.J.

    1987-03-01

    This Fragility Analysis is the third of three volumes for the Seismic Margin Review of the Maine Yankee Atomic Power Station. Volume 1 is the Summary Report of the first trial seismic margin review. Volume 2, Systems Analysis, documents the results of the systems screening for the review. The three volumes are part of the Seismic Margins Program initiated in 1984 by the Nuclear Regulatory Commission (NRC) to quantify seismic margins at nuclear power plants. The overall objectives of the trial review are to assess the seismic margins of a particular pressurized water reactor, and to test the adequacy of this review approach, quantification techniques, and guidelines for performing the review. Results from the trial review will be used to revise the seismic margin methodology and guidelines so that the NRC and industry can readily apply them to assess the inherent quantitative seismic capacity of nuclear power plants

  5. Seismic margin review of the Maine Yankee Atomic Power Station: Fragility analysis

    Energy Technology Data Exchange (ETDEWEB)

    Ravindra, M. K.; Hardy, G. S.; Hashimoto, P. S.; Griffin, M. J.

    1987-03-01

    This Fragility Analysis is the third of three volumes for the Seismic Margin Review of the Maine Yankee Atomic Power Station. Volume 1 is the Summary Report of the first trial seismic margin review. Volume 2, Systems Analysis, documents the results of the systems screening for the review. The three volumes are part of the Seismic Margins Program initiated in 1984 by the Nuclear Regulatory Commission (NRC) to quantify seismic margins at nuclear power plants. The overall objectives of the trial review are to assess the seismic margins of a particular pressurized water reactor, and to test the adequacy of this review approach, quantification techniques, and guidelines for performing the review. Results from the trial review will be used to revise the seismic margin methodology and guidelines so that the NRC and industry can readily apply them to assess the inherent quantitative seismic capacity of nuclear power plants.

  6. RETRAN experience with BWR transients at Yankee Atomic Electric Company

    International Nuclear Information System (INIS)

    Ansari, A.A.F.; Cronin, J.T.; Slifer, B.C.

    1981-01-01

    Yankee Atomic Electric Company is actively involved in the development of licensing methods for BWR's. The computer code chosen for analyzing system response under transient conditions is RETRAN. This paper describes the RETRAN model developed for Vermont Yankee, and the results of the RETRAN checkout and qualification that has been achieved at YAEC through comparison of RETRAN predictions to the startup test results performed at the plant as part of the 100% power startup test program. In addition, abnormal operational transients typically analyzed for licensing are also presented

  7. 78 FR 26401 - Connecticut Yankee Atomic Power Company, Haddam Neck Plant, Environmental Assessment and Finding...

    Science.gov (United States)

    2013-05-06

    ... Atomic Power Company, Haddam Neck Plant, Environmental Assessment and Finding of No Significant Impact... Neck Plant (HNP) Independent Spent Fuel Storage Installation (ISFSI). CYAPCO stated that the exemption...-rm/adams.html . From this site, you can access the NRC's ADAMS, which provides text and image files...

  8. Integrated plant safety assessment: systematic evaluation program. Haddam Neck Plant, Connecticut Yankee Atomic Power Company. Docket No. 50-213

    International Nuclear Information System (INIS)

    1983-03-01

    The Systematic Evaluation Program was initiated in February 1977 by the US Nuclear Regulatory Commission to review the designs of older operating nuclear reactor plants to confirm and document their safety. The review provides: (1) an assessment of how these plants compare with current licensing safety requirements relating to selected issues, (2) a basis for deciding on how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety. This report documents the review of Haddam Neck Plant, operated by Connecticut Yankee Atomic Power Company. The Haddam Neck Plant is one of 10 plants reviewed under Phase II of this program. This report indicates how 137 topics selected for review under Phase I of the program were addressed. Equipment and procedural changes have been identified as a result of the review

  9. Maine Yankee Atomic Power Plant. Annual operating report: January--December 1976

    International Nuclear Information System (INIS)

    1977-01-01

    Net electrical energy generated was 5,928,868 MWH with the generator on line 8,347.6 hrs. Information is presented concerning operating experience; specification procedural, and design changes; surveillance tests; containment leak testing; maintenance; licensee events reports; power generation, shutdowns and load reductions; personnel radiation exposures; and primary coolant chemistry

  10. 75 FR 33653 - Connecticut Yankee Atomic Power Company; Notice of Consideration of Issuance of Amendment to...

    Science.gov (United States)

    2010-06-14

    ... Company; Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards; Consideration Determination, and Opportunity for a Hearing The U.S. Nuclear Regulatory... the amendment request involves no significant hazards consideration. Under the Commission's...

  11. Development, assessment, licensing, and application of RELAP5YA at Yankee Atomic Electric Company

    International Nuclear Information System (INIS)

    Husain, A.

    1984-01-01

    Since 1975, Yankee Atomic Electric Company (YAEC) has been licensed to perform LOCA analyses (large and small breaks) for PWRs. The methods are based upon the WREM package, comprised of RELAP4-MOD 3, RELAP4-FLOOD, and TOODEE-2EM. Significant efforts were expended to compare WREM models against Appendix K criteria, and to incorporate changes for compliance with the criteria and for improved representation of LOCA phenomena. /SUP 2,3,4/ This internalized capability has been used extensively for licensing the Yankee and Maine Yankee plants, and for timely resolution of LOCA issues which frequently arose. The value of this internalized analysis capability was well recognized by the Yankee management. In 1979, Yankee embarked upon another LOCA Methods Development Program. One objective was to remove extra conservatisms inherent in older codes to provide additional operational flexibility for our plants. Also, we needed a code which could be used in a production mode to provide realistic response for off-normal conditions to be used in operator training and emergency guideline assessment. This program resulted in the development of RELAP5YA. The development, assessment, licensing, and application of RELAP5YA at YAEC is briefly described in this paper

  12. Integrated Plant Safety Assessment: Systematic Evaluation Program. Haddam Neck Plant, Connecticut Yankee Atomic Power Company, Docket No. 50-213. Final report

    International Nuclear Information System (INIS)

    1983-01-01

    The Systematic Evaluation Progam was initiated in February 1977 by the US Nuclear Regulatory Commission review the designs of older operating nuclear reactor plants to confirm and document their safety. The review provides: (1) an assessment of how these plants compare with curent licensing safety requirements relating to selected issues, (2) a basis for deciding on how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety. This report documents the review of Haddam Neck Plant, operated by Connecticut Yankee Atomic Power Company. The Haddam Neck Plant is one of 10 plants reviewed under Phase II of this program. This report indicates how 137 topics selected for review under Phase I of the program were addressed. Equipment and procedural changes have been identified as a result of the review

  13. 77 FR 48565 - Maine Yankee Atomic Power Company, Maine Yankee Independent Spent Fuel Storage Installation...

    Science.gov (United States)

    2012-08-14

    ... reduction in a margin of safety nor creates a new or different kind of accident from any accident previously... the probability or consequences of an accident previously evaluated; (ii) granting the exemption would... would not result in a significant construction impact because there are no construction activities...

  14. Preliminary irradiation test results from the Yankee Atomic Electric Company reactor vessel test irradiation program

    International Nuclear Information System (INIS)

    Biemiller, E.C.; Fyfitch, S.; Campbell, C.A.

    1993-01-01

    The Yankee Atomic Electric Company test irradiation program was implemented to characterize the irradiation response of representative Yankee Rowe reactor vessel beltline plate materials and to remove uncertainties in the analysis of existing irradiation data on the Yankee Rowe reactor vessel steel. Plate materials each containing 0.24 w/o copper, but different nickel contents at 0.63 w/o and 0.19 w/o, were heat treated to simulate the Yankee vessel heat treatment (austenitized at 1800 deg F) and to simulate Regulatory Guide 1.99 database materials (austenitized at 1600 deg. F). These heat treatments produced different microstructures so the effect of microstructure on irradiation damage sensitivity could be tested. Because the nickel content of the test plates varied and the copper level was constant, the effect of nickel on irradiation embrittlement was also tested. Correlation monitor material, HSST-02, was included in the program to benchmark the Ford Nuclear Reactor (U. of Michigan Test Reactor) which had never been used for this type of irradiation program. Materials taken from plate surface locations (vs. 1/4T) were included to test whether or not the improved toughness properties of the plate surface layer, resulting from the rapid quench, is maintained after irradiation. If the improved properties are maintained, pressurized thermal shock calculations could utilize this margin. Finally, for one experiment, irradiations were conducted at two irradiation temperatures (500 deg. F and 550 deg. F) to determine the effect of irradiation temperature on embrittlement. The preliminary results of the irradiation program show an increase in T 30 shift of 69 deg. F for a decrease in irradiation temperature of 50 deg. F. The results suggest that for nickel bearing steels, the superior toughness of plate surface material is maintained after irradiation and for the copper content tested, nickel had no apparent effect on irradiation response. No apparent microstructure

  15. Nuclear instrument upgrade at Connecticut Yankee Atomic Power Station

    International Nuclear Information System (INIS)

    Brothers, M.H.; Flynn, B.J.; Shugars, H.G.

    1989-01-01

    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

  16. Preliminary irradiation test results from the Yankee Atomic Electric Company reactor vessel test irradiation program

    International Nuclear Information System (INIS)

    Biemiller, E.C.; Fyfitch, Stephen; Campbell, C.A.

    1994-01-01

    The Yankee Atomic Electric Company test irradiation program was implemented to characterize the irradiation response of representative Yankee Rowe reactor vessel beltline plate materials and to remove uncertainties in the analysis of existing irradiation data on the Yankee Rowe reactor vessel steel. Plate materials each containing 0.24 w/o copper, but different nickel contents at 0.63 w/o and 0.19 w/o, were heat treated to simulate the Yankee vessel heat treatment (austenitized at 982 o C (1800 o F)) and to simulate Regulatory Guide 1.99 database materials (austenitized at 871 o C (1600 o F)). These heat treatments produced different microstructures so the effect of microstructure on irradiation damage sensitivity could be tested. Because the nickel content of the test plates varied and the copper level was constant, the effect of nickel on irradiation embrittlement was also tested. Correlation monitor material, HSST-02, was included in the program to benchmark the Ford Nuclear Reactor (University of Michigan Test Reactor) which had never been used before for this type of irradiation program. Materials taken from plate surface locations (versus 1/4 T) were included to test whether or not the improved toughness properties of the plate surface layer, resulting from the rapid quench, are maintained after irradiation. If the improved properties are maintained, pressurized thermal shock calculations could utilize this margin. Finally, for one experiment, irradiations were conducted at two irradiation temperatures (260 o C and 288 o C) to determine the effect of irradiation temperature on embrittlement. (Author)

  17. Stakeholder involvement in the decommissioning of Trojan and Maine Yankee nuclear power plants

    International Nuclear Information System (INIS)

    Watson, Bruce A.; Orlando, Dominick A.

    2006-01-01

    Trojan Nuclear Plant (Trojan) and Maine Yankee Nuclear Plant (Maine Yankee) were the first two power reactors to complete decommissioning under the U. S. Nuclear Regulatory Commission's (NRC's) License Termination Rule (LTR), 10 CFR Part 20, Subpart E. The respective owners' decisions to decommission the sites resulted in different approaches to both the physical aspects of the decommissioning, and the approach for obtaining approval for completing the decommissioning in accordance with regulations. Being in different States, the two single-unit pressurized water reactor sites had different State requirements and levels of public interest that impacted the decommissioning approaches. This resulted in significant differences in the decommissioning planning, the conduct of decommissioning operations, the volume of low-level radioactive waste, and the final status survey (FSS) program. While both licensees have Independent Spent Fuel Storage Installations (ISFSIs), Trojan obtained a separate license for the ISFSI in accordance with the requirements of 10 CFR Part 72 and terminated its 10 CFR Part 50 license. Maine Yankee elected to reduce the 10 CFR Part 50 license to only the requirements for the ISFSI. While the NRC regulations are flexible and allow different approaches to ISFSI licensing, there are separate licensing requirements that must be addressed. In 10 CFR 50.82, the NRC mandates public participation in the decommissioning process. For Maine Yankee, stakeholder and public input resulted in the licensee entering into an agreement with a citizen group and resulted in State legislation that lowered the dose limit below the NRC radiological criteria of 0.25 milli-Sievert/year (mSv/yr) (25 mrem/yr) in 10 CFR 20.1402 for unrestricted use. The lowering of the radiological criteria resulted in a significant dose modeling effort using site-specific Derived Concentrations Guideline Levels (DCGLs) that were well below the NRC DCGL screening values. This contributed to

  18. Maine Yankee: Making the Transition from an Operating Plant to an Independent Spent Fuel Storage Installation (ISFSI)

    International Nuclear Information System (INIS)

    Norton, W.; McGough, M. S.

    2002-01-01

    The purpose of this paper is to describe the challenges faced by Maine Yankee Atomic Power Company in making the transition from an operating nuclear power plant to an Independent Spent Fuel Storage Installation (ISFSI). Maine Yankee (MY) is a 900-megawatt Combustion Engineering pressurized water reactor whose architect engineer was Stone and Webster. Maine Yankee was put into commercial operation on December 28, 1972. It is located on an 820-acre site, on the shores of the Back River in Wiscasset, Maine about 40 miles northeast of Portland, Maine. During its operating life, it generated about 1.2 billion kilowatts of power, providing 25% of Maine's electric power needs and serving additional customers in New England. Maine Yankee's lifetime capacity factor was about 67% and it employed more than 450 people. The decision was made to shutdown Maine Yankee in August of 1997, based on economic reasons. Once this decision was made planning began on how to accomplish safe and cost effective decommissioning of the plant by 2004 while being responsive to the community and employees

  19. 75 FR 33853 - Maine Yankee Atomic Power Company; Independent Spent Fuel Storage Installation; Issuance of...

    Science.gov (United States)

    2010-06-15

    ... previously evaluated by the NRC, and it was determined to pose no increased risk to health and safety. The... has the potential to cause effects on historic or cultural properties, assuming such properties are... differences in environmental impact between the proposed action and the alternative considered and that the...

  20. Examination of failed studs from No. 2 steam generator at the Maine Yankee Nuclear Power Station

    International Nuclear Information System (INIS)

    Czajkowski, C.

    1983-02-01

    Three studs removed from service on the primary manway cover from steam generator No. 2 of the Maine Yankee station were sent to Brookhaven National Laboratory (BNL) for examination. The examination consisted of visual/dye penetrant examination, optical metallography and Scanning Electron Microscopy/Energy Dispersive Spectroscopy (SEM/EDS) evaluation. One bolt was through cracked and its fracture face was generally transgranular in nature with numerous secondary intergranular cracks. The report concludes that the environmenally assisted cracking of the stud was due to the interaction of the various lubricants used with steam leaks associated with this manway cover

  1. Auxiliary feedwater system risk-based inspection guide for the Maine Yankee Nuclear Power Plant

    International Nuclear Information System (INIS)

    Gore, B.F.; Vo, T.V.; Moffitt, N.E.; Bumgardner, J.D.

    1992-10-01

    In a study sponsored by the US Nuclear Regulatory Commission (NRC), Pacific Northwest Laboratory has developed and applied a methodology for deriving plant-specific risk-based inspection guidance for the auxiliary feedwater (AFW) system at pressurized water reactors that have not undergone probabilistic risk assessment (PRA). This methodology uses existing PRA results and plant operating experience information. Existing PRA-based inspection guidance information recently developed for the NRC for various plants was used to identify generic component failure modes. The information was then combined with plant-specific and industry-wide component information and failure data to identify failure modes and failure mechanisms for the AFW system at the selected plants. Maine Yankee was selected as one of a series of plants for study. ne product of this effort is a prioritized listing of AFW failures which have occurred at the plant and at other PWRs. This listing is intended for use by NRC inspectors in the preparation of inspection plans addressing AFW risk-important components at the Maine Yankee plant

  2. 76 FR 41532 - Yankee Atomic Electric Company, Yankee Nuclear Power Station (Yankee-Rowe); Notice of...

    Science.gov (United States)

    2011-07-14

    ... electronic submission through the NRC E-filing system. Requests for a hearing and petitions for leave to... entities participating under 10 CFR 2.315(c), must be filed in accordance with the NRC E-Filing rule (72 FR 49139, August 28, 2007). The E-Filing process requires participants to submit and serve all adjudicatory...

  3. An overview of ALARA considerations during Yankee Atomic`s Component Removal Project

    Energy Technology Data Exchange (ETDEWEB)

    Granados, B.; Babineau, G.; Colby, B.; Cox, B. [Yankee Nuclear Power Station, Rowe, MA (United States)

    1995-03-01

    In Februrary 1992, Yankee Atomic Electric Company (YAEC) permanently shutdown Yankee Nuclear Power Station in Rowe, Massachusetts, after thirty-two years of efficient operation. Yankee`s plan decommissioning is to defer dismantlement until a low level radioactive waste (LLRW) disposal facility is available. The plant will be maintained in a safe storage condition until a firm contract for the disposal of LLRW generated during decommissioning can be secured. Limited access to a LLRW disposal facility may occur during the safe storage period. Yankee intends to use these opportunities to remove components and structures. A Component Removal Project (CRP) was initiated in 1993 to take advantage of one of these opportunities. A Componenet Removal Project (CRP) was initiated in 1993 to take advantage of one of these opportunities. The CRP includes removal of four steam generators, the pressurizer, and segmentation of reactor vessel internals and preparation of LLRW for shipment and disposal at Chem-Nuclear`s Barnwell, South Carolina facility. The CRP is projected to be completed by June 1994 at an estimated total worker exposure of less than 160 person-rem.

  4. Technical evaluation of the electrical, instrumentation, and control design aspects of the low temperature overpressure protection system for the Maine Yankee nuclear power plant

    International Nuclear Information System (INIS)

    Latorre, V.R.; Mayn, B.G.

    1979-08-01

    This report documents the technical evaluation of the electrical, instrumentation, and control design aspects for the low temperature overpressure protection system of the Maine Yankee nuclear power plant. Design basis criteria used to evaluate the acceptability of the system included operator action, system testability, single failure criterion, and seismic Category I and IEEE Std-279-1971 criteria

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

    International Nuclear Information System (INIS)

    1987-10-01

    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

  6. Technical evaluation of the susceptibility of safety-related systems to flooding caused by the failure of non-category 1 systems for the Yankee Rowe Nuclear Power Station

    International Nuclear Information System (INIS)

    Epps, R.C.

    1980-11-01

    This report documents the technical evaluation of the Maine Yankee Atomic Power Station. The purpose of this evaluation was to determine whether the failure of any non-Class I (seismic) equipment could result in a condition, such as flooding, that might adversely affect the performance of the safety-related equipment required for the safe shutdown of the facility, or to mitigate the consequences of an accident. Criteria developed by the US Nuclear Regulatory Commission were used to evaluate the acceptability of the existing protection system as well as measures taken by Maine Yankee Atomic Power Company (MYAPC) to minimize the danger of flooding and to protect safety-related equipment

  7. Yankee atomic experience with coastdown. Report YAEC-1270

    International Nuclear Information System (INIS)

    Quan, B.L.; Malone, J.P.; Pilat, E.E.

    1981-05-01

    This report summarizes Yankee Atomic's operating experience with 19 coastdowns in three different nuclear power plants. The observed effects of coastdown on plant capacity factor, efficiency, maneuverability, and fuel integrity are demonstrated. Calculations of resource requirements and fuel cycle economics for equilibrium cycles show typical savings of 3 to 5% for cycles using coastdown compared to those which produce the same energy without coastdown

  8. Yankee links computing needs, increases productivity

    International Nuclear Information System (INIS)

    Anon.

    1994-01-01

    Yankee Atomic Electric Company provides design and consultation services to electric utility companies that operate nuclear power plants. This means bringing together the skills and talents of more than 500 people in many disciplines, including computer-aided design, human resources, financial services, and nuclear engineering. The company was facing a problem familiar to many companies in the nuclear industry.Key corporate data and applications resided on UNIX or other types of computer systems, but most users at Yankee had personal computers on their desks. How could Yankee enable the PC users to share the data, applications, and resources of the larger computing environment such as UNIX, while ensuring they could still use their favorite PC applications? The solution was PC-NFS from Sunsoft, of Chelmsford, Mass., which links PCs to UNIX and other systems. The Yankee computing story is an example of computer downsizing-the trend of moving away from mainframe computers in favor of lower-cost, more flexible client/server computing. Today, Yankee Atomic has more than 350 PCs on desktops throughout the company, using PC-NFS, which enables them t;o use the data, applications, disks, and printers of the FUNIX server systems. This new client/server environment has reduced Yankee's computing costs while increasing its computing power and its ability to respond to customers

  9. 78 FR 50458 - Entergy Nuclear Operations, Inc., James A. Fitzpatrick Nuclear Power Plant, Vermont Yankee...

    Science.gov (United States)

    2013-08-19

    ... Nuclear Operations, Inc., James A. Fitzpatrick Nuclear Power Plant, Vermont Yankee Nuclear Power Station... that the NRC take action with regard to James A. Fitzpatrick Nuclear Power Plant, Vermont Yankee.... Fitzpatrick Nuclear Power Plant (Fitzpatrick), Vermont Yankee Nuclear Power Station (Vermont Yankee), and...

  10. Expanded spent fuel storage project at Yankee Atomic Electric Plant

    International Nuclear Information System (INIS)

    Chin, S.L.

    1980-01-01

    A detailed discussion on the project at the Yankee Rowe power reactor for expanding the capacity of the at-reactor storage pool by building double-tier storage racks. Various alternatives for providing additional capacity were examined by the operators. Away-from-reactor alternatives included shipment to existing privately owned facilities, a regional independent storage facility, and transshipments to other New England nuclear power plant pools. At-reactor alternatives evaluated included a new pool modification of the existing structure and finally, modification of the spent fuel pit. The establishment of a federal policy precluding transshipment of spent fuel prohibited the use of off-site alternatives. The addition of another pool was too expensive. The possibility of modifying an existing on-site structure required a new safety evaluation by the regulatory group with significant cost and time delays. Therefore, the final alternative - utilizing the existing spent fuel pool with some modification - was chosen due to cost, licensing possibility, no transport requirements, and the fact that the factors involved were mainly under the control of the operator. Modification of the pool was accomplished in phases. In the first phase, a dam was installed in the center of the pool (after the spent fuel was moved to one end). In the second phase, the empty end of the pool was drained and lined with stainless steel and the double-tier rack supports were added. In the third phase, the pool was refilled and the dam was removed. Then the spent fuel was moved into the completed end. In the fourth phase, the dam was replaced and the empty part of the pool was drained. The liner and double-tier rack supports were installed, the pool was refilled, and the dam was removed.The project demonstrated that the modification of existing spent fuel fuel pools for handling double-tier fuel racks is a viable solution for increasing the storage capacity at the reactor

  11. Safety Evaluation Report, pump and valve inservice testing program, Yankee Rowe Nuclear Power Station (Docket No. 50-29). Revision 1

    International Nuclear Information System (INIS)

    Ransom, C.B.; Rockhold, H.C.

    1985-10-01

    The staff reviewed the Yankee Rowe IST program submittal dated October 2, 1981 and evaluated the proposed tests for compliance with the requirements of the ASME Boiler and Pressure Vessel Code, Section XI, 1977 Edition, through the Summer of 1978 Addenda. Those items not in compliance were discussed in a working session with Yankee Atomic Electric Company personnel, USNRC representatives, and EG and G Idaho reviewers on June 22, 1982. The evaluations presented in this SER of the Yankee Rowe pump and valve inservice testing program and the associated relief requests are those of the NRC staff. These findings apply only to component testing

  12. 76 FR 41530 - Connecticut Yankee Atomic Power Company, Haddam Neck Plant; Notice of Consideration of Approval...

    Science.gov (United States)

    2011-07-14

    ... intervention via electronic submission through the NRC E-filing system. Requests for a hearing and petitions... entities participating under 10 CFR 2.315(c), must be filed in accordance with the NRC E-Filing rule (72 FR 49139, August 28, 2007). The E-Filing process requires participants to submit and serve all adjudicatory...

  13. 77 FR 33005 - Connecticut Yankee Atomic Power Company; Haddam Neck Independent Spent Fuel Storage Installation...

    Science.gov (United States)

    2012-06-04

    ... margin of safety nor creates a new or different kind of accident from any accident previously evaluated... probability or consequences of an accident previously evaluated; (ii) granting the exemptions would not... in a significant construction impact because there are no construction activities associated with the...

  14. 75 FR 54400 - Florida Power and Light Company; Establishment of Atomic Safety and Licensing Board

    Science.gov (United States)

    2010-09-07

    ...] Florida Power and Light Company; Establishment of Atomic Safety and Licensing Board Pursuant to delegation..., notice is hereby given that an Atomic Safety and Licensing Board (Board) is being established to preside over the following proceeding: Florida Power & Light Company (Turkey Point Units 6 and 7) This...

  15. Data logger system of Tokai (I) Nuclear Power Station, the Japan Atomic Power Company

    International Nuclear Information System (INIS)

    Machida, Akira; Chikahata, Kiyomitsu; Nakamura, Mamoru; Nanbu, Taketoshi; Kawakami, Hiroshi

    1977-01-01

    The Tokai(I) nuclear power station, the Japan Atomic Power Company, was commissioned in July, 1966. In this station, temperatures of about 700 points are monitored and recorded with a data logger. However, the logger was manufactured some 15 years ago, therefore it is now old-fashioned, and has caused frequent failures these 2 or 3 years. So it was decided to replace it with a new one, and the process control computer, U-300 system including CRT display, has been adopted considering the latest trend in U.K. The control and monitoring system in this station is not a centralized control system, but a distributed control system divided into three control rooms, namely main control room, turbine generator control room and fuel exchanger (cask machine) control room. Therefore for grasping the complete plant conditions at the main control room, the system has not been convenient, and the centralization of data processing has been desired from the viewpoint of operation. The new logger system is composed so as to facilitate the centralized monitoring in the main control room, considering the above requirement. It has been improved so as to have seven important functions in addition to the existing functions. Hardware and software of this system are briefly explained. The new system was started up in February 1977, and is now operating well, though some early failures were experienced. (Wakatsuki, Y.)

  16. 76 FR 51065 - Florida Power & Light Company; Establishment of Atomic Safety and Licensing Board

    Science.gov (United States)

    2011-08-17

    ... & Light Company; Establishment of Atomic Safety and Licensing Board Pursuant to delegation by the... hereby given that an Atomic Safety and Licensing Board (Board) is being established to preside over the following proceeding: Florida Power & Light Company (St. Lucie Plant, Unit 1) This proceeding involves a...

  17. Review of reactor pressure vessel evaluation report for Yankee Rowe Nuclear Power Station (YAEC No. 1735)

    International Nuclear Information System (INIS)

    Cheverton, R.D.; Dickson, T.L.; Merkle, J.G.; Nanstad, R.K.

    1992-03-01

    The Yankee Atomic Electric Company has performed an Integrated Pressurized Thermal Shock (IPTS)-type evaluation of the Yankee Rowe reactor pressure vessel in accordance with the PTS Rule (10 CFR 50. 61) and a US Regulatory Guide 1.154. The Oak Ridge National Laboratory (ORNL) reviewed the YAEC document and performed an independent probabilistic fracture-mechnics analysis. The review included a comparison of the Pacific Northwest Laboratory (PNL) and the ORNL probabilistic fracture-mechanics codes (VISA-II and OCA-P, respectively). The review identified minor errors and one significant difference in philosophy. Also, the two codes have a few dissimilar peripheral features. Aside from these differences, VISA-II and OCA-P are very similar and with errors corrected and when adjusted for the difference in the treatment of fracture toughness distribution through the wall, yield essentially the same value of the conditional probability of failure. The ORNL independent evaluation indicated RT NDT values considerably greater than those corresponding to the PTS-Rule screening criteria and a frequency of failure substantially greater than that corresponding to the ''primary acceptance criterion'' in US Regulatory Guide 1.154. Time constraints, however, prevented as rigorous a treatment as the situation deserves. Thus, these results are very preliminary

  18. ASME XI stroke time testing of solenoid valves at Connecticut Yankee Station

    Energy Technology Data Exchange (ETDEWEB)

    Martin, C.W.

    1996-12-01

    Connecticut Yankee Atomic Power Company has developed the capability of measuring the stroke times of AC and DC solenoid valves. This allows the station to measure the stroke time of any solenoid valve in the plant, even those valves which do not have valve stem position indicators. Connecticut Yankee has adapted the ITI MOVATS Checkmate 3 system, using a signal input from a Bruel and Kjaer (B&K) Model 4382 acoustic accelerometer and the Schaumberg Campbell Associates (SCA) Model SCA-1148 dual sensor, which is a combined accelerometer and gaussmeter.

  19. ASME XI stroke time testing of solenoid valves at Connecticut Yankee Station

    International Nuclear Information System (INIS)

    Martin, C.W.

    1996-01-01

    Connecticut Yankee Atomic Power Company has developed the capability of measuring the stroke times of AC and DC solenoid valves. This allows the station to measure the stroke time of any solenoid valve in the plant, even those valves which do not have valve stem position indicators. Connecticut Yankee has adapted the ITI MOVATS Checkmate 3 system, using a signal input from a Bruel and Kjaer (B ampersand K) Model 4382 acoustic accelerometer and the Schaumberg Campbell Associates (SCA) Model SCA-1148 dual sensor, which is a combined accelerometer and gaussmeter

  20. Flexibility analysis of main primary heat transport system : Narora Atomic Power Project

    International Nuclear Information System (INIS)

    Rastogi, S.K.

    1975-01-01

    The paper presents flexibility analysis problem of main primary heat transport system and the approximate analysis that has been made to estimate the loads coming on major equipments. The primary heat transport system for Narora Atomic Power Project is adopting vertical steam generators and pumps equally divided on either side of the reactor with inter-connecting pipes and feeders. Since the system is mainly spring supported with movement of a few points in certain direction defined but no anchorage, it represents a good problem for flexibility analysis which can only be solved in one step by developing a good computer programme. (author)

  1. Fabrication data package for HEDL-RI dosimetry in the Maine Yankee Replacement Surveillance Capsule 263 and cavity positions

    International Nuclear Information System (INIS)

    Kellogg, L.S.; Ulseth, J.A.; Lippincott, E.P.; Oliver, B.; Farrar, H.

    1982-12-01

    This document provides a complete description of dosimetry fabricated for the Maine Yankee Surveillance Capsule Number 263 and three azimuthal positions in the reactor cavity. Surveillance Capsule 263 was originally scheduled for insertion in October 1982, but will be held in reserve for future use, pending establishment of an equilibrium low leakage core burnup distribution. The cavity dosimetry is scheduled for insertion in November 1982

  2. Effort to grapple with improvement of security and reliability of nuclear power plant. Actions of the Japan Atomic Power Company

    International Nuclear Information System (INIS)

    Ishiguma, Kazuo

    2012-01-01

    Following the Great Tohoku Earthquake in 2011, Tokai No.2 reactor was shut down automatically. Three of emergency diesel generators worked automatically at loss-of-offsite-power and began to work the cooling system of reactor. The reactor could be kept stable and safe in cold state by management of power from the gas turbine electric generator and power source car. Actions of Japan Atomic Power Company (JAPC) for cold shutdown and Tsunami were stated. Inspection results after the earthquake and testimony of staff was described. Countermeasure of improvement of safety of nuclear power station is explained by ensuring of power source and water supply, crisis management system, countermeasure of accident, ensuring, and training of workers, and action for better understanding of reliance. (S.Y.)

  3. An aerial radiological survey of the Vermont Yankee Nuclear Power Station and surrounding area, Vernon, Vermont

    International Nuclear Information System (INIS)

    Reiman, R.; Bluitt, C.M.

    1993-10-01

    An aerial radiological survey was conducted over the Vermont Yankee Nuclear Power Station in Vernon, Vermont, during the period August 7 through August 17, 1989. The survey was conducted at an altitude of 300 feet (91 meters) over a 65-square-mile (168-square-kilometer) area centered on the power station. The purpose of the survey was to document the terrestrial gamma radiation environment of the Vermont Yankee Power Station and surrounding area. 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 6 and 10 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 open-quotes benchmarkclose quotes exposure rate measurements and radionuclide assays 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

  4. An aerial radiological survey of the Yankee Rowe Nuclear Power Station and surrounding area, Rowe, Massachusetts

    International Nuclear Information System (INIS)

    Boyns, P.K.; Bluitt, C.M.

    1993-09-01

    An aerial radiological survey was conducted over the Yankee Rowe Nuclear Power Station in Rowe, Massachusetts, during the period August 17--24, 1989. The survey was conducted at an altitude of 300 feet (91 meters) over an 87-square-mile (225-square-kilometer) area centered on the power station. The purpose of the survey was to document the terrestrial gamma radiation environment of the Yankee Rowe Power Station and the surrounding area. 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 6 and 10 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 assays 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

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

    International Nuclear Information System (INIS)

    1976-01-01

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

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

    Science.gov (United States)

    2010-03-09

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

  7. Determination of the neutron flux for the Yankee Rowe experiment in the Ford Nuclear Reactor

    International Nuclear Information System (INIS)

    Cacciapouti, R.J.; Petrusha, L.

    1994-01-01

    Yankee Atomic Electric Company undertook a Test Irradiation Program at the Ford Nuclear Reactor of the University of Michigan. The program was implemented to characterize the irradiation response of representative Yankee Rowe reactor vessel beltline plate materials. The program was also intended to remove uncertainties in the existing reactor vessel fluence and damage predictions on the Yankee Rowe reactor vessel steel. Since this is the first in-core experiment of this type for the Ford Nuclear Reactor, the measurement of the reaction rate and the estimate of the fluence are presented

  8. Evaluation of BWROG EPG level/power control strategy for Vermont Yankee

    International Nuclear Information System (INIS)

    Chandola, V.; Robichaud, J.D.

    1987-01-01

    The current Boiling Water Reactor Owner's Group (BWROG) emergency procedure guidelines (EPGs) direct reactor operators to manually lower the reactor pressure vessel (RPV) water level to the top of active fuel (TAF) during an anticipated transient without scram (ATWS) event. Lowering the water level reduces the core inlet flow, thereby reducing core power. However, reducing water level is contrary to current operator training, which requires that normal RPV water level be maintained to assure core cooling. In addition, the indicated water level near TAF using cold calibrated level instrumentation may not be reliable, which could potentially result in uncovering the core. This paper evaluates the EPGs' level/power control strategy for the Vermont Yankee plant and proposes alternative to the BWROG guidelines as applied to ATWS response

  9. Analysis of Dust Samples Collected from an In-Service Interim Storage System at the Maine Yankee Nuclear Site.

    Energy Technology Data Exchange (ETDEWEB)

    Bryan, Charles R.; Enos, David

    2016-10-01

    In July, 2016, the Electric Power Research Institute and industry partners performed a field test at the Maine Yankee Nuclear Site, located near Wiscasset, Maine. The primary goal of the field test was to evaluate the use of robots in surveying the surface of an in-service interim storage canister within an overpack; however, as part of the demonstration, dust and soluble salt samples were collected from horizontal surfaces within the interim storage system. The storage system is a vertical system made by NAC International, consisting of a steel-lined concrete overpack containing a 304 stainless steel (SS) welded storage canister. The canister did not contain spent fuel but rather greater-than-class-C waste, which did not generate significant heat, limiting airflow through the storage system. The surfaces that were sampled for deposits included the top of the shield plug, the side of the canister, and a shelf at the bottom of the overpack, just below the level of the pillar on which the canister sits. The samples were sent to Sandia National Laboratories for analysis. This report summarizes the results of those analyses. Because the primary goal of the field test was to evaluate the use of robots in surveying the surface of the canister within the overpack, collection of dust samples was carried out in a qualitative fashion, using paper filters and sponges as the sampling media. The sampling focused mostly on determining the composition of soluble salts present in the dust. It was anticipated that a wet substrate would more effectively extract soluble salts from the surface that was sampled, so both the sponges and the filter paper were wetted prior to being applied to the surface of the metal. Sampling was accomplished by simply pressing the damp substrate against the metal surface for two minutes, and then removing it. It is unlikely that the sampling method quantitatively collected dust or salts from the metal surface; however, both substrates did extract a

  10. RETRAN-02 analysis of upper head cooling during controlled natural circulation cooldown of Yankee Nuclear Power Station

    International Nuclear Information System (INIS)

    Fujita, N.; Helrich, R.E.; Bergeron, P.A.

    1982-01-01

    RETRAN-02 is particularly well-suited for investigating the fluid conditions in the upper head during a natural circulation cooldown. The RETRAN input model was developed with four basic objectives: (1) accurate description of the upper head cooling mechanisms; (2) proper simulation of natural circulation; (3) respresentations of operator actions required to proceed from full-power to shutdown-cooling-system conditions using both automatic and manual controls; and (4) reduction of the computer cost of simulating this evolution of approximately 10-hour duration. The response of the upper head fluid temperature calculated by RETRAN was in close agreement with measured data obtained from a natural circulation cooldown experiment performed for the Connecticut Yankee Plant, whose design is very similar to the Yankee Nuclear Power Station

  11. Evaluation of Haddam Neck (Connecticut Yankee) Nuclear Power Plant, environmental impact prediction, based on monitoring programs

    International Nuclear Information System (INIS)

    Gore, K.L.; Thomas, J.M.; Kannberg, L.D.; Mahaffey, J.A.; Waton, D.G.

    1976-12-01

    A study was undertaken by the U.S. Nuclear Regulatory Commission (NRC) to evaluate the nonradiological environmental data obtained from three nuclear power plants operating for a period of one year or longer. The document presented reports the second of three nuclear power plants to be evaluated in detail by Battelle, Pacific Northwest Laboratories. Haddam Neck (Connecticut Yankee) Nuclear Power Plant nonradiological monitoring data were assessed to determine their effectiveness in the measurement of environmental impacts. Efforts were made to determine if: (1) monitoring programs, as designed, can detect environmental impacts, (2) appropriate statistical analyses were performed and if they were sensitive enough to detect impacts, (3) predicted impacts could be verified by monitoring programs, and (4) monitoring programs satisfied the requirements of the Environmental Technical Specifications. Both preoperational and operational monitoring data were examined to test the usefulness of baseline information in evaluating impacts. This included an examination of the methods used to measure ecological, chemical, and physical parameters, and an assessment of sampling periodicity and sensitivity where appropriate data sets were available. From this type of analysis, deficiencies in both preoperational and operational monitoring programs may be identified and provide a basis for suggested improvement

  12. Exxon Nuclear Company WREM-based generic PWR ECCS evaluation model. Appendix C to Volume II. Yankee Rowe example problem

    International Nuclear Information System (INIS)

    1975-01-01

    Core 12, of the Yankee Rowe (YR), plant is to be licensed with the Exxon Nuclear Co. PWR Evaluation Model. This appendix presents methodology and results of an example calculation for the YR plant using the ENC Evaluation Model. This example problem is for the double-ended guillotine cold leg break with a discharge coefficient of 0.6 assuming loss of one emergency diesel. The NSSS supplier has determined this case to give the highest peak cladding temperature (PCT) for Core 11. The YR example problem was performed to determine the maximum acceptable local peak heating rate (Kw/ft). The blowdown was performed with beginning-of-cycle (BOC) ENC fuel at full power with the hot assembly power corresponding to the design peak rod heating rate of 12.9 Kw/ft. The HOT CHANNEL, TOODEE2, and RELAP4-FLOOD runs were made at several reduced hot assembly radial peaks, holding axial peaking constant, until an acceptable PCT was achieved. This procedure results in a PCT of 1834 0 F at a reduced peak linear heating rate of 10.5 Kw/ft for the ENC fuel at BOC. (auth)

  13. The roles played by the Canadian General Electric Company's Atomic Power Department in Canada's nuclear power program: work, organization and success in APD, 1955-1995

    International Nuclear Information System (INIS)

    Cantello, G.W.

    2003-01-01

    This thesis explores the roles played by the Canadian General Electric Company's Atomic Power Department (APD) in Canada's distinctive nuclear power program. From the establishment of APD in 1955 until the completion of the KANUPP project in Pakistan in 1972, the company's strategy encompassed the design, manufacture, and commissioning of entire nuclear power projects in Canada and abroad. APD then developed a specialized role in the design and supply of complete nuclear fuel handling systems, nuclear fuel bundles, and service work, that sustained a thriving workplace. Five key factors are identified as the reasons behind the long and successful history of the department: (1) Strong, capable and efficient management from the start, (2) Flexible organizational structure, (3) Extremely competent design group, (4) Excellent manufacturing, test, commissioning and service capabilities, (5) Correctly identifying, at the right time, the best fields in which to specialize. (author)

  14. Setting of cesium residual ratio of molten solidified waste produced in Japan Atomic Power Company Tokai and Tokai No.2 Power Stations

    International Nuclear Information System (INIS)

    2013-02-01

    JNES investigated the appropriateness of a view of the Japan Nuclear Fuel Co. on cesium residual content and the radioactivity measurement precision regarding the molten solidified (with lowered inorganic salt used) radioactive wastes which were produced from Japan Atomic Power Company Tokai and Tokai No. 2 Power Stations. Based on the written performance report from the request and past disposal confirmation experience, a view of the JNFC is confirmed as appropriate that setting of 15% cesium residual ratio for molten solidified with volume ratio larger than 4% and less than 10% cases. (S. Ohno)

  15. Technical evaluation of the electrical, instrumentation, and control design aspects of the low temperature overpressure protection system for the Yankee Rowe nuclear power plant

    International Nuclear Information System (INIS)

    Latorre, V.R.; Mayn, B.G.

    1979-08-01

    This report documents the technical evaluation of the electrical, instrumentation, and control design aspects for the low temperature overpressure protection system of the Yankee Rowe nuclear power plant. Design basis criteria used to evaluate the acceptability of the system included operator action, system testability, single failure criterion, and seismic Category I and IEEE Std-279-1971 criteria

  16. The state of improvement of security management setup in the Japan Atomic Power Company and improvement of facilities in its Tsuruga Nuclear Power Station

    International Nuclear Information System (INIS)

    1982-01-01

    In connection with the series of accidents in the Tsuruga Nuclear Power Station of the Japan Atomic Power Company, the state of security management in JAPC and the safety of facilities in the Tsuruga Nuclear Power Station, which have resulted from improvement efforts, are described on the following items: security management setup - communication and reporting in emergency, the management of inspection and maintenance records, work control and supervision in repair, improvement, etc., functional authority and responsibility in maintenance management, operation management, radiation control, personnel education; improvement of facilities - feed water heaters, laundry waste-water filter room, radioactive waste treatment facility, general drainage, concentrated waste liquid storage tanks in newly-built waste treatment building, etc. (Mori, K.)

  17. 76 FR 19148 - Entergy Nuclear Operations, Inc., Entergy Nuclear Vermont Yankee, LLC, Vermont Yankee Nuclear...

    Science.gov (United States)

    2011-04-06

    ... NUCLEAR REGULATORY COMMISSION [Docket No. 50-271; License No. DPR-28; NRC-2011-0074] Entergy Nuclear Operations, Inc., Entergy Nuclear Vermont Yankee, LLC, Vermont Yankee Nuclear Power Station..., ``Requests for Action under this Subpart,'' the U.S. Nuclear Regulatory Commission (NRC) take action with...

  18. Yankee Rowe SPDS development and its validation and verification

    International Nuclear Information System (INIS)

    Candon, D.; Cain, D.

    1986-01-01

    The decision to proceed with EPRI on a prototypical Safety Parameter Display System (SPDS) was made by Yankee Atomic Electric Company management. The general direction to the implementors was to decide from whom would the SPDS be designed, to decide how the SPDS would coincidentally support the twin goals of meeting the regulations and the corporate objective to generate electricity safely and efficiently, and to decide what was known and proven in the arena of computer graphics to minimize cognitive dissonance between the final product SPDS and the operators

  19. Interim safety evaluation report related to operation of Enrico Fermi Atomic Power Plant, Unit 2, Detroit Edison Company

    International Nuclear Information System (INIS)

    1977-09-01

    This interim report summarizes the scope and results of the radiological safety review performed to date by the NRC staff with respect to the operating license phase for the Enrico Fermi Atomic Power Plant, Unit 2. The major effort was the review of the facility design and proposed operating procedures described in applicant's Final Safety Analysis Report. In the course of the review, several meetings were held with representatives of the applicant to discuss plant design, construction and proposed operation. Additional information was requested, which the applicant provided through Amendment 7 to the Final Safety Analysis Report. A chronology of the principal actions relating to the review of the application is attached as Appendix A to the report. The Final Safety Analysis Report and amendments thereto are available for public inspection at the Nuclear Regulatory Commission Public Document Room, 1717 H Street, N. W., Washington, D.C. and at Monroe County Library System, 3700 South Custer Road, Monroe, Michigan 48161

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

    International Nuclear Information System (INIS)

    1975-01-01

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

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

    International Nuclear Information System (INIS)

    1977-01-01

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

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

    International Nuclear Information System (INIS)

    1976-01-01

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

  3. Summary final report: Contract between the Japan atomic power company and the U.S. Department of Energy Improvement of core safety - study on GEM (III)

    International Nuclear Information System (INIS)

    Burke, T.M.; Lucoff, D.M.

    1997-01-01

    This report provides a summary of activities associated with the technical exchange between representatives of the Japan Atomic Power Company (JAPC) and the United States Department of Energy (DOE) regarding the development and testing of Gas Expansion Modules (GEM) at the Fast Flux Test Facility (FFTF). Issuance of this report completes the scope of work defined in the original contract between JAPC and DOE titled ''Study on Improvement of Core Safety - Study on GEM (III).'' Negotiations related to potential modification of the contract are in progress. Under the proposed contract modification, DOE would provide an additional report documenting FFTF pump start tests with GEMs and answer additional JAPC questions related to core safety with and without GEMs

  4. Summary final report: Contract between the Japan atomic power company and the U.S. Department of Energy Improvement of core safety - study on GEM (III)

    Energy Technology Data Exchange (ETDEWEB)

    Burke, T.M.; Lucoff, D.M.

    1997-03-18

    This report provides a summary of activities associated with the technical exchange between representatives of the Japan Atomic Power Company (JAPC) and the United States Department of Energy (DOE) regarding the development and testing of Gas Expansion Modules (GEM) at the Fast Flux Test Facility (FFTF). Issuance of this report completes the scope of work defined in the original contract between JAPC and DOE titled ''Study on Improvement of Core Safety - Study on GEM (III).'' Negotiations related to potential modification of the contract are in progress. Under the proposed contract modification, DOE would provide an additional report documenting FFTF pump start tests with GEMs and answer additional JAPC questions related to core safety with and without GEMs.

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

    International Nuclear Information System (INIS)

    1977-01-01

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

  6. Joint Regulation of Radionuclides at Connecticut Yankee Haddam Neck Plant - Finding Common Ground and Lessons Learned

    International Nuclear Information System (INIS)

    Peters, J.; Glucksberg, N.; Fogg, A.; Couture, B.

    2006-01-01

    During the site closure of nuclear facilities where both radionuclides and chemicals are present in environmental media, state and federal regulatory agencies other than the Nuclear Regulatory Commission often have a stake in the regulation of the site closure process. At the Connecticut Yankee Atomic Power Company (CYAPCO) Haddam Neck Plant in Haddam, Connecticut, the site closure process includes both radiological and chemical cleanup which is regulated by two separate divisions within the state and two federal agencies. Each of the regulatory agencies has unique closure criteria which pertain to radionuclides and, consequently, there is overlapping and in some cases disparate regulation of radionuclides. Considerable effort has been expended by CYAPCO to find common ground in meeting the site closure requirements for radionuclides required by each of the agencies. This paper discusses the approaches that have been used by CYAPCO to address radionuclide site closure requirements. Significant lessons learned from these approaches include the demonstration that public health cleanup criteria for most radionuclides of concern at nuclear power generation facilities are protective for chemical toxicity concerns and are protective for ecological receptors and, consequently, performing a baseline ecological risk assessment for radionuclides at power generation facilities is not generally necessary. (authors)

  7. Company Secretaries: Their duties and powers

    OpenAIRE

    2009-01-01

    Every company must have a company secretary. Their main role is to: carry out the directors’ instructions; help ensure that the company obeys the law and its own constitutional rules; and prepare and maintain the associated company documents.

  8. Offshore atomic power plants

    International Nuclear Information System (INIS)

    Anon.

    1975-01-01

    Various merits of offshore atomic power plants are illustrated, and their systems are assessed. The planning of the offshore atomic power plants in USA is reviewed, and the construction costs of the offshore plant in Japan were estimated. Air pollution problem may be solved by the offshore atomic power plants remarkably. Deep water at low temperature may be advantageously used as cooling water for condensers. Marine resources may be bred by building artificial habitats and by providing spring-up equipments. In the case of floating plants, the plant design can be standardized so that the construction costs may be reduced. The offshore plants can be classified into three systems, namely artificial island system, floating system and sea bottom-based system. The island system may be realized with the present level of civil engineering, but requires the development of technology for the resistance of base against earthquake and its calculation means. The floating system may be constructed with conventional power plant engineering and shipbuilding engineering, but the aseismatic stability of breakwater may be a problem to be solved. Deep water floating system and deep water submerging system are conceivable, but its realization may be difficult. The sea bottom-based system with large caissons can be realized by the present civil engineering, but the construction of the caissons, stability against earthquake and resistance to waves may be problems to be solved. The technical prediction and assessment of new plant sites for nuclear power plants have been reported by Science and Technology Agency in 1974. The construction costs of an offshore plant has been estimated by the Ministry of International Trade and Industry to be yen71,026/kW as of 1985. (Iwakiri, K.)

  9. Atomic power plant

    International Nuclear Information System (INIS)

    Kawakami, Hiroto.

    1975-01-01

    Object: To permit decay heat to be reliably removed after reactor shut-down at such instance as occurrence of loss of power by means of an emergency water supply pump. Structure: An atomic power plant having a closed cycle constructed by connecting a vapor generator, a vapor valve, a turbine having a generator, a condenser, and a water supply pump in the mentioned order, and provided with an emergency water supply pump operated when there is a loss of power to the water supply pump, a degasifier pressure holding means for holding the pressure of the degasifier by introducing part of the vapor produced from said vapor generator, and a valve for discharge to atmosphere provided on the downstream side of said vapor generator. (Kamimura, M.)

  10. Vermont Yankee simulator BOP model upgrade

    International Nuclear Information System (INIS)

    Alejandro, R.; Udbinac, M.J.

    2006-01-01

    The Vermont Yankee simulator has undergone significant changes in the 20 years since the original order was placed. After the move from the original Unix to MS Windows environment, and upgrade to the latest version of SimPort, now called MASTER, the platform was set for an overhaul and replacement of major plant system models. Over a period of a few months, the VY simulator team, in partnership with WSC engineers, replaced outdated legacy models of the main steam, condenser, condensate, circulating water, feedwater and feedwater heaters, and main turbine and auxiliaries. The timing was ideal, as the plant was undergoing a power up-rate, so the opportunity was taken to replace the legacy models with industry-leading, true on-line object oriented graphical models. Due to the efficiency of design and ease of use of the MASTER tools, VY staff performed the majority of the modeling work themselves with great success, with only occasional assistance from WSC, in a relatively short time-period, despite having to maintain all of their 'regular' simulator maintenance responsibilities. This paper will provide a more detailed view of the VY simulator, including how it is used and how it has benefited from the enhancements and upgrades implemented during the project. (author)

  11. Bettis Atomic Power Laboratory

    International Nuclear Information System (INIS)

    1992-01-01

    The Bettis Atomic Power Laboratory (Bettis) is owned by the US Department of Energy (DOE) and has been operated under Government contract by the Westinghouse Electric Corporation since 1949. The Bettis Site in West Mifflin, Pennsylvania conducts research and development work on improved nuclear propulsion plants for US Navy warships and is the headquarters for all of the Laboratory's operations. For many years, environmental monitoring has been performed to demonstrate that the Bettis Site is being operated in accordance with environmental standards. While the annual report describes monitoring practices and results, it does not describe the nature and environmental aspects of work and facilities at the Bettis Site nor give a historical perspective of Bettis' operations. The purpose of this report is to provide this information as well as background information, such as the geologic and hydrologic nature of the Bettis Site, pertinent to understanding the environmental aspects of Bettis operations. Waste management practices are also described

  12. Power companies international year book 1997

    International Nuclear Information System (INIS)

    Anon.

    1996-12-01

    The Power Companies International Yearbook covers around 250 major international power generating and distributing companies worldwide, giving a comprehensive overview of this dynamic global industry. Both publicly and privately owned companies are features. It details financial performance, ownership status, affiliated businesses, activities, operations, key personnel, type/capacity of generation, subsidiary activities and plans for diversification within and outside the global power sector. (Author)

  13. Radioactivity leakage accidents in the feed water heater and the general drainage of the Tsuruga Nuclear Power Station of Japan Atomic Power Company

    International Nuclear Information System (INIS)

    1981-01-01

    In the Tsuruga Nuclear Power Station, JAPC on the shell on extracted-steam side in B system of No. 4 feed water heater, drain water leakage occurred twice in January, 1981. Then, 61 pCi/g cobalt-60 and 10 pCi/g manganese-54 were detected in soil at the outlet of general drainage on April 17, 1981. The cause was found to be the overflow of radioactive liquid waste in the filter sludge storage tank on March 8, the same year. On-the-spot inspection was subsequently made by the Agency of Natural Resources and Energy on both leakage accidents. The results of inspections are described as follows: the course of leakage accident, and also the measures taken to JAPC in connection with the two leakage accidents. (J.P.N.)

  14. Human factors in atomic power plant

    International Nuclear Information System (INIS)

    Kawano, Ryutaro

    1997-01-01

    To ensure safety should have priority over all other things in atomic power plants. In Chernobyl accident, however, various human factors including the systems for bulb check after inspection and communication, troubles in the interface between hardwares such as warning speakers and instruments, and their operators, those in education and training for operators and those in the general management of the plant have been pointed out. Therefore, the principles and the practical measures from the aspect of human factors in atomic power plants were discussed here. The word, ''human factor'' was given a definition in terms of the direct cause and the intellectual system. An explanatory model for human factors, model SHEL constructed by The Tokyo Electric Power Co., Ltd., Inc. was presented; the four letter mean software(S), hardware(H), environment(E) and liveware(L). In the plants of the company, systemic measures for human error factors are taken now in all steps not only for design, operation and repairing but also the step for safety culture. Further, the level required for the safety against atomic power is higher in the company than those in other fields. Thus, the central principle in atomic power plants is changing from the previous views that technology is paid greater importance to a view regarding human as most importance. (M.N.)

  15. Efficiency of Finish power transmission network companies

    International Nuclear Information System (INIS)

    Anon.

    2001-01-01

    The Finnish Energy Market Authority has investigated the efficiency of power transmissions network companies. The results show that the intensification potential of the branch is 402 million FIM, corresponding to about 15% of the total costs of the branch and 7.3 % of the turnout. Energy Market Authority supervises the reasonableness of the power transmission prices, and it will use the results of the research in supervision. The research was carried out by the Quantitative Methods Research Group of Helsinki School of Economics. The main objective of the research was to create an efficiency estimation method for electric power distribution network business used for Finnish conditions. Data of the year 1998 was used as basic material in the research. Twenty-one of the 102 power distribution network operators was estimated to be totally efficient. Highest possible efficiency rate was 100, and the average of the efficiency rates of all the operators was 76.9, the minimum being 42.6

  16. Transforming Ontario's Power Generation Company

    International Nuclear Information System (INIS)

    Manley, J.; Epp, J.; Godsoe, P.C.

    2004-01-01

    The OPG Review Committee was formed by the Ontario Ministry of Energy to provide recommendations and advice on the future role of Ontario Power Generation Inc. (OPG) in the electricity sector. This report describes the future structure of OPG with reference to the appropriate corporate governance and senior management structure. It also discusses the potential refurbishing of the Pickering A nuclear generating Units 1, 2 and 3. The electricity system in Ontario is becoming increasingly fragile. The province relies heavily on electricity imports and the transmission system is being pushed to near capacity. Three nuclear generating units are out of service. The problems can be attributed to the fact that the electricity sector has been subjected to unpredictable policy changes for more than a decade, and that the largest electricity generator (OPG) has not been well governed. OPG has had frequent senior management change, accountability has been weak, and cost overruns have delayed the return to service of the Pickering nuclear power Unit 4. It was noted that the generating assets owned and operated by OPG are capable of providing more than 70 per cent of Ontario's electricity supply. Decisive action is needed now to avoid a potential supply shortage of about 5,000 to 7,000 megawatts by 2007. In its current state, OPG risks becoming a burden on ratepayers. Forty recommendations were presented, some of which suggest that OPG should become a rate-regulated commercial utility focused on running and maintaining its core generating assets. This would require that the government act as a shareholder, and the company operate like a commercial business. It was also emphasized that the market must be allowed to bring in new players. refs., tabs., figs

  17. Anticipated corrosion in the Vermont Yankee spent fuel pool

    International Nuclear Information System (INIS)

    Weeks, J.R.

    1977-06-01

    The report provides additional information relating to a proposed modification to the spent fuel pool at the Vermont Yankee Nuclear Power Station (VYNPS) and addresses corrosion of spent fuel pool storage materials and zircaloy, and provides an analysis of the effectiveness of the Boral sealing

  18. Maine Tidal Power Initiative: Environmental Impact Protocols For Tidal Power

    Energy Technology Data Exchange (ETDEWEB)

    Peterson, Michael Leroy [Univ. of Maine, Orono, ME; Zydlewski, Gayle Barbin [Univ. of Maine, Orono, ME; Xue, Huijie [Univ. of Maine, Orono, ME; Johnson, Teresa R. [Univ. of Maine, Orono, ME

    2014-02-02

    The Maine Tidal Power Initiative (MTPI), an interdisciplinary group of engineers, biologists, oceanographers, and social scientists, has been conducting research to evaluate tidal energy resources and better understand the potential effects and impacts of marine hydro-kinetic (MHK) development on the environment and local community. Project efforts include: 1) resource assessment, 2) development of initial device design parameters using scale model tests, 3) baseline environmental studies and monitoring, and 4) human and community responses. This work included in-situ measurement of the environmental and social response to the pre-commercial Turbine Generator Unit (TGU®) developed by Ocean Renewable Power Company (ORPC) as well as considering the path forward for smaller community scale projects.

  19. The main factor affecting the competitiveness of Contractor Company

    Science.gov (United States)

    Nurisra; Malahayati, Nurul; Mahmuddin

    2018-05-01

    Contractor companies must have the competitive advantage to compete in maintaining the survival of the company. Problems arise because quite a lot of advantages can be used and these advantages must be used appropriately to produce competitiveness for the company to continue to compete and to win the competition. This study aims to determine the main factors affecting the competitiveness of medium-class contractors in Banda Aceh. Data collection was obtained through questionnaires distributed to 31 middle-class contractors in Banda Aceh. Data processing and analysis is done by using descriptive analysis. Based on the result of descriptive analysis, it can be concluded that the most important competitiveness factor with a mean score value 4.52 is the relationship, and the factor that has the highest mean score value is the relationship with the government of 4.97, while the result of the ranking analysis is obtained 25 factor that is critical to the competitiveness of medium-class contractors in Banda Aceh.

  20. Atomic Power | Taylor | Zede Journal

    African Journals Online (AJOL)

    Zede Journal. Journal Home · ABOUT THIS JOURNAL · Advanced Search · Current Issue · Archives · Journal Home > Vol 3 (1968) >. Log in or Register to get access to full text downloads. Username, Password, Remember me, or Register. Atomic Power. D Taylor. Abstract. No Abstract. Full Text: EMAIL FREE FULL TEXT ...

  1. THE MAIN OPERATIONS OF REORGANIZATION THROUGH MERGERS OF TRADING COMPANIES

    Directory of Open Access Journals (Sweden)

    Alexandra-Gabriela Rolea

    2013-11-01

    Full Text Available Notwithstanding the optimistic forecasts issued by experts a couple of years ago, the economic predicaments of the European Union’s member states, including Romania, are far from being settled. The extension of the economic and financial dowturn, the continuing process of globalization and the financial markets’ volatility have imposed an unparalleled flexibility upon the economic agents, in that the amount of mergers and acquisitions has risen at a both national and international level. This background calls for a detailed but nonetheless approachable study of the reorganization of the trading companies though mergers, aimed mainly at the business environment. In order to reach the aforementioned objectives, the theoretical endeavor seeks to explore the relevant legal provisions, including the European Directives. The juridical and accounting operations of mergers, their legal consequences and concrete implications on the activity of the trading companies will also be analysed. Some particular approaches embraced by the legal practice are to be presented, as in Romania mergers are submitted to the control of the court. The study will have a positive impact on the economic agents, who are fostered to conclude this type of restructuring, by altering the line of thought shaped a few years ago, according to which mergers are difficult, isolated and sometimes even unacceptable operations.

  2. The Canadian Niagara Power Company story

    International Nuclear Information System (INIS)

    Ball, N.R.

    2005-01-01

    This book chronicles the history and contributions of the Canadian Niagara Power Company and its employees toward the establishment of electricity generation and distribution in Niagara Falls and Fort Erie, Ontario, dating back to its founding in 1892. Through historical photographs, maps and drawings, the book demonstrates the impact of electricity on the Niagara region. It emphasizes the many skills and jobs required to run the company that generated electricity and maintained a complete system to deliver power, metering, and billing services through the depression, wars, and postwar booms, even during lightning, snow and ice storms. The company began producing power in 1905 with what had been the world's largest-capacity turbines and generators that supplied power to both sides of the Niagara River. Initially, most of the electricity was exported to New York State. The company eventually expanded its Canadian customer service area from Niagara Falls, Ontario, to Fort Erie, Bridgeburg, Amigari, Ridgeway, Stevensville, Crystal Beach and Point Abino. Throughout its history, the Canadian Niagara Power Company provided power at a lower cost than its neighbouring competitors. The William Birch Rankine Generating Station became an important tourist attraction, showcasing the latest electrical appliances of the time in an effort to promote the use of electricity in homes and offices. Today, the station remains a tribute to the fact that natural beauty can coincide with industry. The book also chronicles the difficult business challenges caused by restructuring in the electric power industry in the 1990s, repairing aging equipment and applying the latest in automation and remote sensing technology. Today, the company as FortisOntario is expanding to other communities around Ontario. refs., tabs., figs

  3. Structural reliability of atomic power plant

    International Nuclear Information System (INIS)

    Klemin, A.I.; Polyakov, E.F.

    1980-01-01

    In 1978 the first specialized technical manual ''Technique of Calculating the Structural Reliability of an Atomic Power Plant and Its Systems in the Design Stage'' was developed. The present article contains information about the main characteristics and capabilities of the manual. The manual gives recommendations concerning the calculations of the reliability of such specific systems as the reactor control and safety system, the system of instrumentation and automatic control, and safety systems. 2 refs

  4. Results of small break LOCA analysis for Kuosheng nuclear power plant using the RELAP5YA computer code

    International Nuclear Information System (INIS)

    Wang, L.C.; Jeng, S.C.; Chung, N.M.

    2004-01-01

    One lesson learned from the Three Mile Island (TMI) accident was the analysis methods used by Nuclear Steam Supply System (NSSS) vendors and/or nuclear fuel suppliers for small break Loss Of Coolant Accident (LOCA) analysis for compliance with appendix K to 10CFR50 should be revised, documented and submitted for USNRC approval and the plant-specific calculations using NRC-approved models for small-break LOCA to show compliance with 10CFR50.46 should be submitted for NRC approval. A study by Taiwan Power Company (TPC) under the guidance of Yankee Atomic Electric Company (YAEC) has been undertaken to perform this analysis for Kuosheng nuclear power plant. This paper presents the results of the analysis that are useful in satisfying the same requirements of the Republic Of China Atomic Energy Commission (ROCAEC). (author)

  5. Atomic power project, Kakrapar, Gujarat

    International Nuclear Information System (INIS)

    Varadarajan, G.

    1992-01-01

    The atomic power project at Kakrapar, comprising of two units of 235 MW each, went critical very recently in September 1992. The work consisted of construction of reactor and turbine buildings, outer and inner containment walls, calandria vault, natural draught cooling tower, etc. Nearly 152,000m 3 of normal aggregate concrete and 3,500m 3 of heavy aggregate concrete were produced and poured. The paper describes salient innovative construction features of the project. Incidentally, the project received a Certificate of Merit in the Excellence in Concrete competition held by the Maharashtra India Chapter of the American Concrete Institute. (author). 7 figs

  6. 76 FR 59482 - The New Brunswick Railway Company-Continuance in Control Exemption-Maine Northern Railway Company...

    Science.gov (United States)

    2011-09-26

    ... requirements of 49 U.S.C. 11323-25, for Eastern Maine Railway, a Class III rail common carrier to continue in... Exemption-- Montreal, Maine & Atlantic Railway, Ltd.; Maine Northern Railway Company--Modified Rail...

  7. The development strategies of the european electric power companies

    International Nuclear Information System (INIS)

    Heddebaud, D.

    2005-01-01

    This study takes stock on the european market of the electric power and of its development perspectives. It details the strategy and the place of the main operators and shows their forces and weaknesses. It provides a comparison of the financial performances of 28 companies (growth, margins, profitability, debt and war chest). (A.L.B.)

  8. Georgia Power Company's college degree program

    International Nuclear Information System (INIS)

    Coggin, C.L.

    1988-01-01

    The purpose of this paper is to describe Georgia Power Company's on-site college degree program for nuclear power plant personnel. In February 1986, the US Nuclear Regulatory Commission issued a policy statement concerning engineering expertise on shift (Generic Letter 86-04), which appeared in Volume 50, Number 208 of the October 28, 1985 Federal Register. One of the options available to nuclear power plant personnel to meet the requirement was the combined senior reactor operator/shift technical adviser position. One of the methods for meeting the option included a bachelor's degree in engineering technology for an accredited institution, including course work in the physical, mathematical, or engineering sciences

  9. Results of special security inspection on improvement of security management setup in Head Office and Tsuruga Nuclear Power Station of the Japan Atomic Power Company and improvement of facilities in Tsuruga Nuclear Power Station

    International Nuclear Information System (INIS)

    1982-01-01

    In connection with the series of accidents in the Tsuruga Nuclear Power Station, the Agency of Natural Resources and Energy had instructed JAPC to make comprehensive inspection on the security management setup and to take improvement measures in the nuclear power station. The results of the subsequent inspection by ANRE confirmed that the improvements made by JAPC are adequate, and the following items are described: improvement of security management setup - communication and reporting in emergency, the management of inspection and maintenance records, work control and supervision in repair, improvement, etc., functional authority and responsibility in maintenance management, operation management, radiation control, personnel education; improvement of facilities - feed water heaters, laundry waste-water filter room, radioactive waste treatment facility, general drainage, concentrated waste liquid storage tanks in newly-built waste treatment building, etc. (J.P.N.)

  10. Practical PRA applications at Consumers Power Company

    International Nuclear Information System (INIS)

    Blanchard, D.P.

    1985-01-01

    Consumers Power Company has completed two probabilistic risk assessments (PRAs), one each at its Big Rock Point and Midland plants and is in the process of performing a third study at its Palisades Plant. Each PRA is summarized briefly in this paper. Each PRA has been used to evaluate specific plant design features and make operating and design recommendations to plant and Company management as well as to the regulator. This paper is a sumary of those issues on which Consumers Power Company has applied PRAs to date. The technique used in applying PRA to these issues has varied as more was learned about the plants from the PRA and about PRA itself. Some issue resolutions involved deriving technical arguments from small parts of the PRA only, such as the logic models or consequence analysis. Still others required use of the entire PRA including sequence quantification, plant and containment response, consequence analysis and eventually cost-benefit evaluation of proposed resolutions. The benefits derived from these analyses have also varied and include not only a perceived reduction in the risks associated with plant operation but also economic benefit to the Company in that cost-effective alternatives to resolving safety issues have been permitted

  11. Nuclear power station main control room habitability

    International Nuclear Information System (INIS)

    Paschal, W.B.; Knous, W.S.

    1989-01-01

    The main control room at a nuclear power station must remain habitable during a variety of plant conditions and postulated events. The control room habitability requirement and the function of the heating, ventilating, air-conditioning, and air treatment system are to control environmental factors, such as temperature, pressure, humidity, radiation, and toxic gas. Habitability requirements provide for the safety of personnel and enable operation of equipment required to function in the main control room. Habitability as an issue has been gaining prominence with the Advisor Committee of Reactor Safeguards and the Nuclear Regulatory Commission since the incident at Three Mile Island. Their concern is the ability of the presently installed habitability systems to control the main control room environment after an accident. This paper discusses main control room HVAC systems; the concern, requirements, and results of NRC surveys and notices; and an approach to control room habitability reviews

  12. Isolated systems with wind power. Main report

    DEFF Research Database (Denmark)

    Lundsager, P.; Bindner, Henrik W.; Clausen, Niels-Erik

    2001-01-01

    The overall objective of this research project is to study the development of methods and guidelines rather than "universal solutions" for the use of wind energy in isolated communities. The main specific objective of the project is to develop and present amore unified and generally applicable...... approach for assessing the technical and economical feasibility of isolated power supply systems with wind energy. As a part of the project the following tasks were carried out: Review of literature, fieldmeasurements in Egypt, development of an inventory of small isolated systems, overview of end...... for Isolated Systems with Wind Power, applicable for international organisations such as donoragencies and development banks....

  13. Comparison of BR3 Surveillance and Vessel Plates to the Surrogate Plates Representative of the Yankee Rowe PWR Vessel

    Energy Technology Data Exchange (ETDEWEB)

    Fabry, A.; Chaouadi, R.; Puzzolante, J.L.; Van de Velde, J.; Biemiller, E.C.; Rosinski, S.T.; Carter, R.G

    1998-07-01

    The sister pressure vessels at the BR3 and Yankee Rowe PWR plants were operated at lower-than-usual temperature ( 260 degrees Celsius) and their plates were austenitized a higher-than-usual temperature (970 degrees Celsius) - a heat treatment leading to a coarser microstructure than is typical for the fine grain plates considered in development of USNRC Regulatory Guide 1.99. The surveillance programs provided by Westinghouse for the two plants were limited to the same A302-B plate representative of the Rowe vessel upper shell plate; this material displayed outlier behaviour characterized by a 41 J Charpy-V Notch shift significantly larger than predicted by Regulatory Guide 1.99. Because lower irradiation temperature and nickel alloying are generally considered detrimental to irradiation sensitivity, there was a major concern that the nickel-modified lower Rate plate and the nickel-modified BR3 plate may become too embrittled to satisfy the toughness requirements embodied in the PTS screening criterion. This paper compares free complementary studies undertaken to clarify these uncertainties: (1) The accelerated irradiation and test program launched in 1990 by Yankee Atomic Electric Company using typical vessel plate materials containing 0.24% copper at two nickel levels: YA1, 0.63 % (A533-B) and YA9, 0.19 (A302-B). These were heat-treated to produce the coarse and fine grain microstructures representative of the Yankee/BR3 and the Regulatory Guide plates, respectively; (2) The BR3 surveillance and vessel testing program: this vessel was wet-annealed in 1984, relicensed for operation till the plant shutdown in 1987, and was trepanned in early 1995; (3) The accelerated irradiations in the Belgian test reactor BR2 of the Yankee coarse grain plates YA1 and YA9 together with BR3 vessel specimens extracted at nozzle elevation, a location with negligible radiation exposure. It is contended that the PTS screening criterion was never attained by the BR3 and Rowe plates, and

  14. Comparison of BR3 Surveillance and Vessel Plates to the Surrogate Plates Representative of the Yankee Rowe PWR Vessel

    International Nuclear Information System (INIS)

    Fabry, A.; Chaouadi, R.; Puzzolante, J.L.; Van de Velde, J.; Biemiller, E.C.; Rosinski, S.T.; Carter, R.G.

    1998-07-01

    The sister pressure vessels at the BR3 and Yankee Rowe PWR plants were operated at lower-than-usual temperature ( 260 degrees Celsius) and their plates were austenitized a higher-than-usual temperature (970 degrees Celsius) - a heat treatment leading to a coarser microstructure than is typical for the fine grain plates considered in development of USNRC Regulatory Guide 1.99. The surveillance programs provided by Westinghouse for the two plants were limited to the same A302-B plate representative of the Rowe vessel upper shell plate; this material displayed outlier behaviour characterized by a 41 J Charpy-V Notch shift significantly larger than predicted by Regulatory Guide 1.99. Because lower irradiation temperature and nickel alloying are generally considered detrimental to irradiation sensitivity, there was a major concern that the nickel-modified lower Rate plate and the nickel-modified BR3 plate may become too embrittled to satisfy the toughness requirements embodied in the PTS screening criterion. This paper compares free complementary studies undertaken to clarify these uncertainties: (1) The accelerated irradiation and test program launched in 1990 by Yankee Atomic Electric Company using typical vessel plate materials containing 0.24% copper at two nickel levels: YA1, 0.63 % (A533-B) and YA9, 0.19 (A302-B). These were heat-treated to produce the coarse and fine grain microstructures representative of the Yankee/BR3 and the Regulatory Guide plates, respectively; (2) The BR3 surveillance and vessel testing program: this vessel was wet-annealed in 1984, relicensed for operation till the plant shutdown in 1987, and was trepanned in early 1995; (3) The accelerated irradiations in the Belgian test reactor BR2 of the Yankee coarse grain plates YA1 and YA9 together with BR3 vessel specimens extracted at nozzle elevation, a location with negligible radiation exposure. It is contended that the PTS screening criterion was never attained by the BR3 and Rowe plates, and

  15. Comparison of BR3 surveillance and vessel plates to the surrogate plates representative of the Yankee Rowe PWR vessel

    International Nuclear Information System (INIS)

    Fabry, A.; Chaouadi, R.; Puzzolante, J.L.; Van de Velde, J.; Biemiller, E.C.; Rosinski, S.T.; Carter, R.G.

    1999-01-01

    The sister pressure vessels at the BR3 and Yankee Rowe PWR plants were operated at lower-than-usual temperature (∼260 C) and their plates were austenitized at higher-than-usual temperature (∼970 C) -- a heat treatment leading to a coarser microstructure than is typical for the fine grain plates considered in development of USNRC Regulatory Guide 1.99. The surveillance programs provided by Westinghouse for the two plants were limited to the same A302-B plate representative of the Rowe vessel upper shell plate; this material displayed outlier behavior characterized by a 41J. Charpy-V Notch shift significantly larger than predicted by Regulatory Guide 1.99. Because lower irradiation temperature and nickel alloying are generally considered detrimental to irradiation sensitivity, there was a major concern that the nickel-modified lower Rowe plate and the nickel-modified BR3 plate may become too embrittled to satisfy the toughness requirements embodied in the PTS screening criterion. This paper compares three complementary studies undertaken to clarify these uncertainties: (1) The accelerated irradiation and test program launched in 1990 by Yankee Atomic Electric Company using typical vessel plate materials containing 0.24% copper at two nickel levels: YA1, 0.63% (A533-B) and YA9, 0.19% (A302-B). These were heat-treated to produce the coarse and fine grain microstructures representative of the Yankee/BR3 and the Regulatory Guide plates, respectively; (2) The BR3 surveillance and vessel testing program; this vessel was wet-annealed in 1984, relicensed for operation till the plant shutdown in 1987, and was trepanned in early 1995; (3) The accelerated irradiations in the Belgian test reactor BR2 of the Yankee coarse grain plates YA1 and YA9 together with BR3 vessel specimens extracted at nozzle elevation, a location with negligible radiation exposure. It is contended that the PTS screening criterion was never attained by the BR3 and Rowe plates, and that the BR3 vessel

  16. Atomic power development in USA

    International Nuclear Information System (INIS)

    Wiggin, E.

    1976-01-01

    Many problems concerning the atomic power development in USA are investigated and discussed. (Introduction of fast breeder reactors is not considered in this paper). The first problem is the raising of capital for plant construction. The second problem is the supply of uranium. Estimated amount of yellow cake and its price are presented and compared with estimated demands. It is concluded that 3.5x10 6 tons of yellow coke is sufficient for generating 7x10 8 KW of electric power up to about 2000. The third problem is the enrichment service. Balance of supply and demand is discussed together with the projected extension of existing plants and the construction of new plants. The completion of nuclear fuel cycle is discussed as the fourth problem. According to the author's opinion, technological problems of reprocessing, storing, waste disposal, and the utilization of mixed oxide fuel are not difficult to solve. Definite judgement of NRC and ERDA is strongly required. The last problem discussed in this paper is the public acceptance. The movements of anti-nuclear groups and the opinion of general public are analyzed and the role of AIF in presenting paper informations is discussed. (Aoki, K.)

  17. Biomass utilization at Northern States Power Company

    International Nuclear Information System (INIS)

    Ellis, R.P.

    1994-01-01

    Northern States Power Company (open-quotes NSPclose quotes) generates, transmits and distributes electricity and distributes natural gas to customers in Minnesota, Wisconsin, North Dakota, South Dakota and Michigan. An important and growing component of the fuel needed to generate steam for electrical production is biomass. This paper describes NSP's historical use of biomass, current biomass resources and an overview of how NSP plans to expand its use of biomass in the future

  18. Isolated systems with wind power. Main report

    Energy Technology Data Exchange (ETDEWEB)

    Lundsager, P.; Bindner, H.; Clausen, N.E.; Frandsen, S.; Hansen, L.H.; Hansen, J.C.

    2001-06-01

    The overall objective of this research project is to study the development of methods and guidelines rather than 'universal solutions' for the use of wind energy in isolated communities. The main specific objective of the project is to develop and present a more unified and generally applicable approach for assessing the technical and economical feasibility of isolated power supply systems with wind energy. As a part of the project the following tasks were carried out: Review of literature, field measurements in Egypt, development of an inventory of small isolated systems, overview of end-user demands, analysis of findings and development of proposed guidelines. The project is reported in one main report and four topical reports, all of them issued as Risoe reports. This is the Main Report Risoe-R-1256, summing up the activities and findings of the project and outlining an Implementation Strategy for Isolated Systems with Wind Power, applicable for international organisations such as donor agencies and development banks. (au)

  19. Physical decommissioning of the Shippingport Atomic Power Station

    International Nuclear Information System (INIS)

    Crimi, F.P.

    1988-01-01

    The Shippingport Atomic Power Station consists of the nuclear steam supply system and associated radioactive waste processing systems, which are owned by the United States Department of Energy (USDOE), and the turbine-generator and balance of plant which is owned by the Duquesne Light Company. The station is located at Shippingport, Pennsylvania on seven acres of land leased by USDOE from the Duquesne Light Company. The Shippingport Station Decommissioning Project (SSDP) is being managed for the USDOE by the General Electric Company and its integated subcontractor, Morrison Knudsen-Ferguson (MK-F) Company. The objectives of the Shippingport Station Decommissioning Project (SSDP) are to: Demonstrate the safe and cost effective dismantlement of a large scale nuclear power plant; Provide useful data for future decommissioning projects

  20. Power Company No 2. Activity Report 1992 - 1994

    International Nuclear Information System (INIS)

    1995-01-01

    The Power Company No.2 is in charge of power generation and distribution for the southern area of Vietnam. Status and development plans of the Company is presented in the report. (NHA). 10 figs, 2 tabs, 17 photos, 2 maps

  1. Applications of MAAP at Duke Power Company

    International Nuclear Information System (INIS)

    Barrett, M.

    1991-01-01

    The Modular Accident Analysis Program (MAAP) is a fast running, easy to use code for modeling accidents at nuclear power plants. These attributes make MAAP ideal for a number of applications. At Duke Power Company, MAAP has been used extensively in the performance of probabilistic risk assessment (PRA). Applications have also been found in the areas of emergency preparedness, training, and severe accident management. Specific applications of MAAP are presented in this paper with special attention to examples in the area of PRA success criteria development and severe accident management strategies selection. The application of MAAP to developing success criteria for ECCS performance during a large LOCA is presented. Additionally, an example of how MAAP has been used in the assessment of an alternative feed and bleed strategy is provided

  2. Duke Power Company's control rod wear program

    International Nuclear Information System (INIS)

    Culp, D.C.; Kitlan, M.S. Jr.

    1990-01-01

    Recent examinations performed at several foreign and domestic pressurized water reactors have identified significant control rod cladding wear, leading to the conclusion that previously believed control rod lifetimes are not attainable. To monitor control rod performance and reduce safety concerns associated with wear, Duke Power Company has developed a comprehensive control rod wear program for Ag-In-Cd and boron carbide (B 4 C) rods at the McGuire and Catawba nuclear stations. Duke Power currently uses the Westinghouse 17 x 17 Ag-In-Cd control rod design at McGuire Unit 1 and the Westinghouse 17 x 17 hybrid B 4 C control rod design with a Ag-In-Cd tip at McGuire Unit 2 and Catawba Units 1 and 2. The designs are similar, with the exception of the absorber material and clad thickness. There are 53 control rods per unit

  3. Power control device of an atomic power plant

    International Nuclear Information System (INIS)

    Ootsuka, Shiro; Ito, Takero.

    1980-01-01

    Purpose: To improve the power controllability of an atomic power plant by improving the controllability, response and stability of the recirculation flow rate. Constitution: The power control device comprises a power detector of the reactor, which detects and operates the reactor power from the thermal power, neutron flux or the process quantity controlling the same, and a deviation detector which seeks deviation between the power signal of the power detector and the power set value of the reactor or power station. By use of the power control device constituted in this manner, the core flow rate is regulated by the power signal of the deviation detector thereby to control the power. (Aizawa, K.)

  4. CBA main magnet power supply ripple reduction

    International Nuclear Information System (INIS)

    Bagley, G.; Edwards, R.J.

    1983-01-01

    The preliminary results of a development program to minimize beam perturbation resulting from ripple current generated by the CBA Main Magnet Power Supply are presented. The assessment of the magnitude and causes of the ripple generated led to a modification of the SCR Gate Driver and the addition of a bandpass amplifier correction loop which gave significant improvement. A description of the changes made and the results obtained are included. A second design approach was developed in which the timing of the SCR gate pulses is directly determined by a VCO. The results reported with this VCO Loop indicate superior performance particularly at frequencies below 60 Hz. A shunt transistor regulator design is proposed to minimize higher SCR switching frequency harmonics

  5. The AGS main magnet power supply upgrade

    International Nuclear Information System (INIS)

    Sandberg, J.N.; Casella, R.; Geller, J.; Marneris, I.; Soukas, A.; Schumburg, N.

    1995-01-01

    The AGS Main Magnet Power Supply consists of a group of thyristor controlled power converters that operate from full rectify to full invert. In order to minimize ripple during the critical periods of injection and extraction 24 pulse converters are used for these portions of the cycle. The maximum voltage available in this mode is nominally 2,000 volts. The converters that are functional during this portion of the cycle are called the flat-top bank or ''F'' bank modules. During acceleration and invert where voltages of up to 12,000 volts are needed and where the ripple requirements are less stringent, groups of twelve pulse converters are operational. These converters are called the Pulsed bank or ''P'' bank modules. The original controlled rectifier system consisted of 96 large mercury filled excitron tubes divided equally between the P bank and F bank converters. These devices were extremely durable and ran successfully for over twenty years. It was, decided to replace the excitron farm with multiple arrangements of three-phase, full-wave, bridge modules that utilize silicon controlled rectifiers (SCR's or thyristors) as the switching element. In order to match the existing transformer connections and buswork, eight identical modules were required; four for the P bank system and four for the F bank system. In order to reduce noise pickup and provide electrical isolation the high level SCR gate triggers are provided via fiberoptic cable. The status of various parameters such as water flow, auxiliary power supply performance, trigger circuitry failure, over voltage, overcurrent, and loss of phase reference are monitored via a programmable logic controller (PLCs). The PLCs use isolated input and output modules for various voltage levels from TTL to 150 Vdc to 125 Vac. These devices are extremely flexible and have allowed modifications and improvements that have enhanced the performance over any equivalent hard wired system

  6. Atomic power engineering under falsified safety standards

    International Nuclear Information System (INIS)

    Ackerman, A.J.

    1974-01-01

    In July 1970 the United States Department of Justice accused the American Society of Mechanical Engineers (ASME) of violating the Sherman Antitrust Act and of acting in restraint of trade by restricting the ASME Certificate of Authorization and the use of the Code Symbol Stamps to boilers and pressure vessels manufactured in the United States and Canada. During the succeeding two years attorneys for the parties in the case formulated a Consent Decree without a public confrontation in the Court. Furthermore, the membership of ASME was kept uninformed until October of 1972, after the Consent and Final Judgment had become effective and new procedures had been developed for allowing foreign manufacturers to apply the ASME Code Symbol Stamps to their products. As a consequence, a breakdown in engineered safety standards has been sanctioned and this is undermining the engineering profession's overriding reponsibility to protect the public health and safety. This breakdown of professional responsibility is especially serious in the new technology of atomic power. American insurance companies, which have traditionally written 100% insurance coverage for property damage and third party liability against explosions of high pressure steam boilers bearing the ASME Code Stamp, have refused to write such insurance coverage on nuclear reactors. In the author's opinion there is evidence that the Consent was formulated under collusive proceedings and he calls on the members and the Council of ASME to appeal for dismissal of the Consent Decree. 24 refs

  7. Main Causes Of Mortality Of Companies In Central Region Of Ecuador

    Directory of Open Access Journals (Sweden)

    Jorge Vladimir Núñez Grijalva

    2015-12-01

    Full Text Available Most of the studies concerning trading companies, addressing aspects of the initial stage in the life of these, such as its formation stage. However, few studies have examined the final stage of a company and especially the causes of mortality and closing. This article analyzes the main causes of mortality trading companies from three different and complementary disciplines at once: legal, administrative and financial accounting in commercial companies of the Central Region of Ecuador. This research provides a summary of the major causes of mortality, which should be considered by the current and future employers, in order to strengthen their decisions regarding the survival of companies.

  8. Teollisuuden Voima Oy - Industrial Power Company Ltd. Local information activity

    International Nuclear Information System (INIS)

    Engros, Taina

    1989-01-01

    There are two nuclear power producers in Finland - the state-owned power company Imatran Voima Oy which operates two 440 MW Soviet-made PWR units in southern Finland, east of Helsinki and the Teollisuuden Voima Oy - Industrial Power Company Ltd, or TVO, owned by Finnish industrial companies. TVO operates two 710 MW ABB ATOM BWR units producing about one fifth of the country's electricity consumption. Operating experiences are extremely good from all Finnish nuclear power plants. The Finns' attitude towards nuclear power has changed into a positive direction in recent times. This can probably be noted as an international trend now that the Chernobyl accident is becoming an incident of the past. The Finnish citizens and politicians are facing two questions; first, what is their attitude towards nuclear power as a source of energy, in other words, do they approve of the plants currently in operation. The second question is how they stand on the building of new plants. It is probably another universal phenomenon that the attitudes of people living in the vicinity of nuclear power plants are less critical than the attitudes of those living farther away. This does not, by any means, result in local information activity being easier or less important than nationwide information activity. On the contrary, local decision-makers, local media and inhabitants are those who can, and through whom we can, influence also wider circles. The Nuclear Energy Act, which became effective in Finland last year, defines that the final decision on whether nuclear power plants can be built inside a municipality, is made at local level. As far as TVO is concerned one factor making local information activity easier is the small size of the locality. The difficulty TVO has to face is the people's suspicion of information activity. All information is considered propaganda, regardless of its form, and only negative news are considered information. Also, a large proportion of people are passive

  9. Teollisuuden Voima Oy - Industrial Power Company Ltd. Local information activity

    Energy Technology Data Exchange (ETDEWEB)

    Engros, Taina [Department of Information, TVO, Olkiluoto FIN-27160 (Finland)

    1989-07-01

    There are two nuclear power producers in Finland - the state-owned power company Imatran Voima Oy which operates two 440 MW Soviet-made PWR units in southern Finland, east of Helsinki and the Teollisuuden Voima Oy - Industrial Power Company Ltd, or TVO, owned by Finnish industrial companies. TVO operates two 710 MW ABB ATOM BWR units producing about one fifth of the country's electricity consumption. Operating experiences are extremely good from all Finnish nuclear power plants. The Finns' attitude towards nuclear power has changed into a positive direction in recent times. This can probably be noted as an international trend now that the Chernobyl accident is becoming an incident of the past. The Finnish citizens and politicians are facing two questions; first, what is their attitude towards nuclear power as a source of energy, in other words, do they approve of the plants currently in operation. The second question is how they stand on the building of new plants. It is probably another universal phenomenon that the attitudes of people living in the vicinity of nuclear power plants are less critical than the attitudes of those living farther away. This does not, by any means, result in local information activity being easier or less important than nationwide information activity. On the contrary, local decision-makers, local media and inhabitants are those who can, and through whom we can, influence also wider circles. The Nuclear Energy Act, which became effective in Finland last year, defines that the final decision on whether nuclear power plants can be built inside a municipality, is made at local level. As far as TVO is concerned one factor making local information activity easier is the small size of the locality. The difficulty TVO has to face is the people's suspicion of information activity. All information is considered propaganda, regardless of its form, and only negative news are considered information. Also, a large proportion of people are passive

  10. Atomic power in space: A history

    International Nuclear Information System (INIS)

    1987-03-01

    ''Atomic Power in Space,'' a history of the Space Isotope Power Program of the United States, covers the period from the program's inception in the mid-1950s through 1982. Written in non-technical language, the history is addressed to both the general public and those more specialized in nuclear and space technologies. 19 figs., 3 tabs

  11. Atomic power or windmills. [Denmark

    Energy Technology Data Exchange (ETDEWEB)

    Korsbech, U [Danmarks Tekniske Hoejskole, Lyngby

    1976-01-01

    It is argued that if the Danish Ministry of Trade's plans for nuclear power in the nineties are changed to windpower, the price will be 5 times as high. A thorough estimation of the economy of a big Danish windpower program is given.

  12. Chapter 3. The economical power of the company

    International Nuclear Information System (INIS)

    1998-01-01

    In the third chapter of this CD ROM the economic power of the Slovak Electric, Plc. (Slovenske elektrarne, a.s.), is presented. It consist of next paragraphs (1) Property of Slovak Electric, Plc, the company; (2) Position of the Company; (3) Business performance of the Company (Economic results, Installed capacity, Generation of electricity and heat; Electricity trade, Distribution of electricity and heat trade are reviewed); (4) Shareholdings in other companies and international co-operation

  13. Embrittlement and annealing of reactor pressure vessel steels: comparison of BR3 surveillance and vessel plates to the surrogate plates representative of the Yankee Rowe vessel

    Energy Technology Data Exchange (ETDEWEB)

    Fabry, A.; Chaouadi, T.; Puzzolante, J.L.; Van de Velde, J. [Centre de l``Etude de l``Energie Nucleaire, Mol (Belgium); Biemiller, E.C. [Yankee Atomic Electric Company, Bolton (United States); Rossinski, S.T.; Carter, R.G. [Electric Power Research Institute, Charlotte (United States)

    1996-07-01

    The sister pressure vessels at the BR3 and Rowe Yankee PWR plants were operated at a lower-than-usual temperature (260 degrees Celsius) and their plates were austenitized at higher-than-usual temperature (970 degrees Celsius). A heat tratemement leading to a coarser microstructure than typical for the fine grain plates that are considered in development of USNRC Regulatory guide 1.99. This material displayed outlier behaviour charackterized by a 41J CVN-shift significantly larger than predicted by Regulatory Guide 1.99. Because lower radiation temperature and nickell alloying are generally considered detrimental to irradiation sensitivity, there was a major concern that the nickel-modified lower Rowe plate and the nickel-modified BR3 plate may become too embrittled to satisfy the toughness requirements enbodied in the PTS screening criterion. This paper compares three complementary studies undertaken to clarify these uncertainties: 1) the accelerated irradiation and test program launched in 1990 by Yankee Atomic Electric Company using typical vessel plate materials containing 0.24% copper at two nickel levels: YA1, 0.63% (A533-B) and YA9, 0.19% (A302-B). These were heat-treated to produce the coarse and fine grain microstructures representative of the Yankee/BR3 and the Regulatory Guide plates, respectively, 2) the BR3 surveillance and vessel testing program: this vessel was wet-annealed in 1984, relicensed for operation till the plant shutdown in 1987, ANCL was trepanned in early 1995, 3) the accelerated irradiations in the Belgian BR2 test reactor of the Yankee coarse grain plates YA1 and YA9 together with BR3 vessel specimens extracted at nozzle elevation, a location with negligible radiation exposure. It is shown that the PTS screening criterion was never attained by the BR3 and Rowe plates, and that the BR3 vessel anneal was neither necessary nor sufficient. Finally, the sensitivity of embrittlement, annealing and post-annealing reembrittlement to irradiation

  14. Embrittlement and annealing of reactor pressure vessel steels: comparison of BR3 surveillance and vessel plates to the surrogate plates representative of the Yankee Rowe vessel

    International Nuclear Information System (INIS)

    Fabry, A.; Chaouadi, T.; Puzzolante, J.L.; Van de Velde, J.; Biemiller, E.C.; Rossinski, S.T.; Carter, R.G.

    1996-07-01

    The sister pressure vessels at the BR3 and Rowe Yankee PWR plants were operated at a lower-than-usual temperature (260 degrees Celsius) and their plates were austenitized at higher-than-usual temperature (970 degrees Celsius). A heat tratemement leading to a coarser microstructure than typical for the fine grain plates that are considered in development of USNRC Regulatory guide 1.99. This material displayed outlier behaviour charackterized by a 41J CVN-shift significantly larger than predicted by Regulatory Guide 1.99. Because lower radiation temperature and nickell alloying are generally considered detrimental to irradiation sensitivity, there was a major concern that the nickel-modified lower Rowe plate and the nickel-modified BR3 plate may become too embrittled to satisfy the toughness requirements enbodied in the PTS screening criterion. This paper compares three complementary studies undertaken to clarify these uncertainties: 1) the accelerated irradiation and test program launched in 1990 by Yankee Atomic Electric Company using typical vessel plate materials containing 0.24% copper at two nickel levels: YA1, 0.63% (A533-B) and YA9, 0.19% (A302-B). These were heat-treated to produce the coarse and fine grain microstructures representative of the Yankee/BR3 and the Regulatory Guide plates, respectively, 2) the BR3 surveillance and vessel testing program: this vessel was wet-annealed in 1984, relicensed for operation till the plant shutdown in 1987, ANCL was trepanned in early 1995, 3) the accelerated irradiations in the Belgian BR2 test reactor of the Yankee coarse grain plates YA1 and YA9 together with BR3 vessel specimens extracted at nozzle elevation, a location with negligible radiation exposure. It is shown that the PTS screening criterion was never attained by the BR3 and Rowe plates, and that the BR3 vessel anneal was neither necessary nor sufficient. Finally, the sensitivity of embrittlement, annealing and post-annealing reembrittlement to irradiation

  15. The AGS Booster main ring power supply system

    International Nuclear Information System (INIS)

    Soukas, A.; Hughes, K.; Sandberg, J.; Toldo, F.; Zhang, S.Y.

    1989-01-01

    The AGS Booster is being designed as a very versatile particle accelerator. Its primary function is to be a high quality injector to the currently operating Alternating Gradient Synchrotron (AGS). The Booster/AGS combination will produce proton intensities greater than 5 x 10 13 protons per pulse (ppp), and accelerate heavy ions, with mass up to 200, to a maximum energy of 15 GeV per atomic mass unit (GeV/amu). The power supply for the Booster Main Ring (BMRPS) has to accommodate a wide range of cycles and a wide range of operating parameters. The cycles range from storage for several seconds to rapid cycling at 7.5 Hz. The peak output power is 18 MW. This paper will describe the AGS Booster machine powering requirements, the choice of power supply, the a.c. circuit tie-in and its associated problems and some of the details of the design of the BMRPS. 9 refs., 2 figs

  16. Consideration of the opinions and others in the public hearing on the alteration in reactor installation (addition of Unit 2) in the Tsuruga Power Station of the Japan Atomic Power Company

    International Nuclear Information System (INIS)

    1982-01-01

    A public hearing was held in Tsuruga City, Fukui Prefecture, on the alteration in reactor installation, i.e., the addition of Unit 2 in the Tsuruga Power Station, JAPC, on November 20, 1980, by the Nuclear Safety Commission. The opinions and others stated by the local people were taken into consideration in the governmental examinations on the installation, etc. The considerations of such opinions principally in the examinations by NSC are explained in the form of questions (i.e. opinion, etc.) and answers (i.e. consideration) as follows: site conditions (site, earthquakes, ground, meteorology, siting situation, etc.), the safety design of the reactor facilities (overall plant, aseismic design, the teaching by the TMI accident in U.S., ECCS, pre-stressed concrete containment vessel, radioactive waste release, etc.), radioactive waste management, radiation exposure relation, the technical capabilities of personnel (operation, etc.). (J.P.N.)

  17. Radwaste minimization successes at Duke Power Company

    International Nuclear Information System (INIS)

    Lan, C.D.; Johnson, G.T.; Groves, D.C.; Smith, T.A.

    1996-01-01

    At Duke Power Company, open-quotes Culture Changeclose quotes is a common term that we have used to describe the incredible transformation. We are becoming a cost conscious, customer driven, highly competitive business. Nowhere has this change been more evident then in the way we process and dispose 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' 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. In June, 1994, we invited EPRI to conduct assessments of our waste minimization programs at Oconee and Catawba nuclear stations. Included in the assessments were in-depth looks at contamination control, an inventory of items in the plant, the volume of waste generated in the plant and how it was processed, laundry reject data, site waste-handling operations, and plant open-quotes housekeepingclose quotes routines and process. One of the most important aspects of the assessment is the open-quotes dumpster dive,close quotes which is an evaluation of site dry active waste composition by sorting through approximately fifteen bags of radioactive waste. Finally, there was an evaluation of consumable used at each site in order to gain knowledge of items that could be standardized at all stations. With EPRI recommendations, we made several changes and standardized the items used. We have made significant progress in waste reduction. We realize, however, that we are aiming at a moving target and we still have room for improvement. As the price of processing and disposal (or storage) increases, we will continue to evaluate our waste minimization programs

  18. Atomic Power in Space: A History

    Science.gov (United States)

    1987-03-01

    "Atomic Power in Space," a history of the Space Isotope Power Program of the United States, covers the period from the program's inception in the mid-1950s through 1982. Written in non-technical language, the history is addressed to both the general public and those more specialized in nuclear and space technologies. Interplanetary space exploration successes and achievements have been made possible by this technology, for which there is no known substitue.

  19. Atomic power in space: A history

    Energy Technology Data Exchange (ETDEWEB)

    1987-03-01

    ''Atomic Power in Space,'' a history of the Space Isotope Power Program of the United States, covers the period from the program's inception in the mid-1950s through 1982. Written in non-technical language, the history is addressed to both the general public and those more specialized in nuclear and space technologies. 19 figs., 3 tabs.

  20. Externalities of energy and atomic power

    International Nuclear Information System (INIS)

    2006-09-01

    Energy technology ensures not only energy supply but also has great impacts on society and environments. Economical value and effect evaluation alone doesn't mean appropriate so the evaluation of 'externalities' should be appreciated. In order to assess atomic power in this context, the Atomic Energy Society of Japan set up a research committee on 'externalities of energy and atomic power' from April 2002 to March 2006, whose activities were described in this report. In addition to environmental effects and environmental externalities, four areas were newly studied as follows: (1) biological effects of low dose rate exposure and externalities, (2) externalities as social/economical effects including stable supply and security, (3) energy technologies evaluation and (4) social choice and decision-making. (T. Tanaka)

  1. Evaluation of efficiency in Japan electric power companies

    International Nuclear Information System (INIS)

    Ghaderi, F.; Muyajima, M.

    2001-01-01

    efficiencies drastic. with taking into account some operational non operational parameters as inputs and outputs in the Electric Power Companies in Japan, some insight in the extent of operation could be achieved with which it could be argued on the companies efficiency. Then with comparing them with each other the most efficient company with considering the particular parameter could be introduce. The main focus of the paper will be to evaluate the implementation of the electric companies which could be leaded later to promote efficiency. decreasing the price for the end users and energy-saving opportunities in the operating

  2. 78 FR 43197 - Duke Energy Florida, Inc.; Florida Power & Light Company; Tampa Electric Company; Orlando...

    Science.gov (United States)

    2013-07-19

    ... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [ER13-1922-000; ER13-1929-000; ER13-1932-000; NJ13-11-000] Duke Energy Florida, Inc.; Florida Power & Light Company; Tampa Electric Company; Orlando Utilities Commission; Notice of Compliance Filings Take notice that on July 10, 2013, Duke Energy...

  3. Rotary-Atomizer Electric Power Generator

    Science.gov (United States)

    Nguyen, Trieu; Tran, Tuan; de Boer, Hans; van den Berg, Albert; Eijkel, Jan C. T.

    2015-03-01

    We report experimental and theoretical results on a ballistic energy-conversion method based on a rotary atomizer working with a droplet acceleration-deceleration cycle. In a rotary atomizer, liquid is fed onto the center of a rotating flat surface, where it spreads out under the action of the centrifugal force and creates "atomized" droplets at its edge. The advantage of using a rotary atomizer is that the centrifugal force exerted on the fluid on a smooth, large surface is not only a robust form of acceleration, as it avoids clogging, but also easily allows high throughput, and produces high electrical power. We successfully demonstrate an output power of 4.9 mW and a high voltage up to 3120 V. At present, the efficiency of the system is still low (0.14%). However, the conversion mechanism of the system is fully interpreted in this paper, permitting a conceptual understanding of system operation and providing a roadmap for system optimization. This observation will open up a road for building power-generation systems in the near future.

  4. Northeast Empire Limited Partnership No. 2 Alternative Energy, Inc. and Maine Public Service Company (Docket No. EA-95): Environmental Assessment

    International Nuclear Information System (INIS)

    1992-05-01

    This environmental assessment (EA) has been prepared in connection with the application (the Application) by Alternative Energy, Inc. (AEI), Northeast Empire Limited Partnership number-sign 2 (the Partnership) and Maine Public Service Company (MPS and, collectively with AEI and the Partnership, the Applicants), filed on January 6, 1992, for authorization to transmit electric energy to a foreign country. The electric energy to be exported would be produced by a 39-megawatt (MW), wood-fired powerplant (the Project) to be developed by AEI and to be built by the Partnership in Ashland, Maine, which is located in MPS' service territory. In the Application, the Applicants requested authorization for MPS to transmit electricity generated by the Project from Maine through New Brunswick, Canada, on route back to the US for domestic use by Central Maine Power Company (MP). The need to cross the US -Canadian border arises due to the geography of the area and to facilitate access to an existing transmission line. None of the power will be used in Canada. This EA addresses the environmental impacts associated with the export of electric energy and the connected actions which are expected to result from the authorization of those exports. The electricity would be exported over cross-border transmission facilities maintained between MPS and New Brunswick Power Corporation (NB Power). No new cross-border facilities, and no modification of any existing cross-border facilities, are required in connection with the proposed action

  5. The main challenges for manufacturing companies in implementing and utilizing configurators

    DEFF Research Database (Denmark)

    Kristjansdottir, Katrin; Shafiee, Sara; Hvam, Lars

    2018-01-01

    Companies providing customized products increasingly apply configurators in supporting sales and design activities, thus improving lead-times, quality, cost, benefits perceived by customers, and customer satisfaction. While configurator advantages have been substantially investigated....... Finally, it is investigated whether the importance of the main categories of challenges varies according to a number of potential context variables. The results of the survey, which studies manufacturing companies that use configurators in providing customized products, offer new insights......, the challenges of implementing and utilizing configurators have less often been considered. By reviewing relevant literature, the present study first categorizes the main challenges faced by manufacturing companies when implementing and utilizing configurators. Six main categories of challenges are identified...

  6. Carolina Power and Light Company's computerized Radiological Information Management System

    International Nuclear Information System (INIS)

    Meyer, B.A.

    1987-01-01

    Carolina Power and Lignt Company has recently implement a new version of their computerized Radiological Information management System. The new version was programmed in-house and is run on the Company's mainframe computers. In addition to providing radiation worker dose histories and current dose updates, the system provides real-time access control for all three of the Company's nuclear plants such as respirator and survey equipment control and inventory, TLD QC records, and many other functions

  7. Power of Companies in Supply Chains and Their Effect on Network Development

    Directory of Open Access Journals (Sweden)

    Tamás Brányi

    2015-01-01

    Full Text Available A general supply chain functions as a closed cluster and consists of at least three companies: supplier, producer and buyer. In an optimal case the companies within a supply chain are well integrated, partnership rests on trust which results in common strategic decisions. Business practices show that there is a stronger company within the chain that uses its power position to influence network development. The objective of the research is to measure how and what kind of power position is needed to influence the supply chain. The hypothesis states, that power and network development are opposite effects in a supply chain. Statistical examination of data gained from 221 companies state that the company with power position has advantages if the supply chain extends. SPSS analysis proves that the hypothesis is false and opens a new direction of research. Companies within the supply chain have to cope with power structures while cooperating with each other. They tend to look for solutions to ease dependency. Using or misusing power has several factors; mainly they are inherited from the strongest link of the supply chain. This is usually a problem but the results of the statistical analysis show that still a win-win situation is needed for the companies in order to deepen the cooperation. To conclude this research the data shows that the goal is to be more competitive as a chain, not just as a company.

  8. The adaptation of the electric power companies to the power market

    International Nuclear Information System (INIS)

    Otterstad, B.; Ottosen, R.

    1993-02-01

    This report describes the challenges met by the Norwegian electric power companies in adapting to a more market oriented business and their possibilities and strategies when facing the uncertainties on the market side. The main principles of adaptation to the market are described and various strategies are illustrated by means of simple calculations and figures. The theoretical basis for analyses of adaptation to the market and for pricing period contracts and options are discussed. The report concludes with a discussion of the de-regulation of the North American gas market and draws parallels to the Norwegian power market. 17 figs

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

    Energy Technology Data Exchange (ETDEWEB)

    Jones, T. D.

    1978-01-01

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

  10. [Preliminary study on main impacting factors on brand equity of listed traditional Chinese medicine companies].

    Science.gov (United States)

    Tan, Wei; Geng, Dong-Mei; Rong, Xue; Li, Zi; Liu, Wei; Yang, Li; Xu, Si-Qun; Jie, Xiao-Qian

    2013-05-01

    The brand equity is valuable intangible assets of traditional Chinese medicine companies, who are excellent representatives of traditional Chinese medicine enterprises and the most promising ones to good international medicine brands. However, there is still no systematic study on how to correctly evaluate the brand equity of listed traditional Chinese medicine companies at present. To make it clear, the main impacting factors on brand equity of listed traditional Chinese medicine companies, both structured open outline pre-research and closed questionnaire research were adopted for the field survey, and some suggestions for how to protect and enhance the brand equity were also presented on the basis of survey and analysis, in the hope of improving the brand management level of listed traditional Chinese medicine companies, and making a beneficial exploration for the development of brand theory of the traditional Chinese medicine industry.

  11. Electric utility companies and geothermal power

    Science.gov (United States)

    Pivirotto, D. S.

    1976-01-01

    The requirements of the electric utility industry as the primary potential market for geothermal energy are analyzed, based on a series of structured interviews with utility companies and financial institution executives. The interviews were designed to determine what information and technologies would be required before utilities would make investment decisions in favor of geothermal energy, the time frame in which the information and technologies would have to be available, and the influence of the governmental politics. The paper describes the geothermal resources, electric utility industry, its structure, the forces influencing utility companies, and their relationship to geothermal energy. A strategy for federal stimulation of utility investment in geothermal energy is suggested. Possibilities are discussed for stimulating utility investment through financial incentives, amelioration of institutional barriers, and technological improvements.

  12. 77 FR 2972 - Thunder Bay Power Company, Thunder Bay Power, LLC, et al.

    Science.gov (United States)

    2012-01-20

    ... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission Thunder Bay Power Company, Thunder Bay Power, LLC, et al.; Notice of Application for Transfer of Licenses, and Soliciting Comments and Motions To Intervene Thunder Bay Power Company Project No. 2404-095 Thunder Bay Power, LLC Midwest Hydro, Inc...

  13. Vermont Yankee advanced off-gas system (AOG)

    International Nuclear Information System (INIS)

    Littlefield, P.S.; Miller, S.R.; DerHagopian, H.

    1975-01-01

    Early in 1971 the Vermont Yankee Nuclear Power Corporation decided to modify the existing off-gas delay system to reduce the release of noble gas isotopes from its boiling water reactor. This modification included a subsystem for recombining the radiolytic hydrogen and oxygen from the reactor and a series of adsorber tanks filled with activated carbon to delay the noble gas isotopes from the condenser air ejectors. The off-gas system and its operating history from initial operation in November 1973 to the present time are described. Data are also presented on the measured dynamic adsorption coefficient of the ambient carbon subsystem. Laboratory adsorption tests were conducted on the carbon prior to AOG startup and the results are compared with the effective coefficients obtained under operating conditions. (U.S.)

  14. Nuclear power company activity based costing management analysis

    International Nuclear Information System (INIS)

    Xu Dan

    2012-01-01

    With Nuclear Energy Industry development, Nuclear Power Company has the continual promoting stress of inner management to the sustainable marketing operation development. In view of this, it is very imminence that Nuclear Power Company should promote the cost management levels and built the nuclear safety based lower cost competitive advantage. Activity based costing management (ABCM) transfer the cost management emphases from the 'product' to the 'activity' using the value chain analysis methods, cost driver analysis methods and so on. According to the analysis of the detail activities and the value chains, cancel the unnecessary activity, low down the resource consuming of the necessary activity, and manage the cost from the source, achieve the purpose of reducing cost, boosting efficiency and realizing the management value. It gets the conclusion from the detail analysis with the nuclear power company procedure and activity, and also with the selection to 'pieces analysis' of the important cost related project in the nuclear power company. The conclusion is that the activities of the nuclear power company has the obviously performance. It can use the management of ABC method. And with the management of the procedure and activity, it is helpful to realize the nuclear safety based low cost competitive advantage in the nuclear power company. (author)

  15. DESIGN, INNOVATION AND PERSONALIZATION – THE MAIN ASSET COMPANY “SIMPO”, VRANJE

    Directory of Open Access Journals (Sweden)

    Ljiljana Stošić Mihajlović

    2013-07-01

    Full Text Available The company "Simpo" – Vranje, is the largest exporter of Serbian furniture and more than four decades has been present on the international market, in almost every continent. And today in about 30 countries worldwide exports 65% of production. Its main advantages are a business emphasis on modern design, the constant innovation of products and materials, and personalization.

  16. 77 FR 43071 - MPS Customer Group v. Maine Public Service Company; Notice of Complaint

    Science.gov (United States)

    2012-07-23

    ..., MPS Customer Group (Complainant) filed a formal complaint against Maine Public Service Company (MPS or... document is added to a subscribed docket(s). For assistance with any FERC Online service, please email... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Docket No. EL12-84-000] MPS Customer...

  17. Hamaoka Atomic Energy Hall, Chubu Electric Power Co. , Inc

    Energy Technology Data Exchange (ETDEWEB)

    Kawasaki, Y [Chubu Electric Power Co. Inc., Nagoya (Japan)

    1979-10-01

    Hamaoka Nuclear Power Station was constructed in the very large site of about 1.6 million m/sup 2/ surrounded by sand dunes and pine forests at the southern tip of Shizuoka Prefecture. Hamaoka Atomic Energy Hall was built on the right side of this power station. This hall had been planned as a part of the works commemorating the 20th anniversary of the founding of the company, and was opened in August, 1972. The building is of steel frame type, and has two floors of 1135 m/sup 2/ total area. The first floor comprises cinema room, power generation corner and open gallery, and the second floor comprises meeting room, native land corner and observation room. Moreover, there is observation platform on the roof. The purpose of the hall is coexistence and coprosperity with the regional residents, and 13 persons make explanations to visitors having reached to 1.9 million as of the end of June, 1979. It is incorporated in the sightseeing route centering around the Omaezaki lighthouse. The cinema hall accommodates 120 men, and the films concerning nuclear power generation and the construction of a nuclear power plant are shown. In the power generation corner, the explanation on nuclear power generation is made with models and panels. The third hall is being built now as energy corner, and it will be completed in autumn, 1979.

  18. Hamaoka Atomic Energy Hall, Chubu Electric Power Co., Inc

    International Nuclear Information System (INIS)

    Kawasaki, Yukio

    1979-01-01

    Hamaoka Nuclear Power Station was constructed in the very large site of about 1.6 million m 2 surrounded by sand dunes and pine forests at the southern tip of Shizuoka Prefecture. Hamaoka Atomic Energy Hall was built on the right side of this power station. This hall had been planned as a part of the works commemorating the 20th anniversary of the founding of the company, and was opened in August, 1972. The building is of steel frame type, and has two floors of 1135 m 2 total area. The first floor comprises cinema room, power generation corner and open gallery, and the second floor comprises meeting room, native land corner and observation room. Moreover, there is observation platform on the roof. The purpose of the hall is coexistence and coprosperity with the regional residents, and 13 persons make explanations to visitors having reached to 1.9 million as of the end of June, 1979. It is incorporated in the sightseeing route centering around the Omaezaki lighthouse. The cinema hall accommodates 120 men, and the films concerning nuclear power generation and the construction of a nuclear power plant are shown. In the power generation corner, the explanation on nuclear power generation is made with models and panels. The third hall is being built now as energy corner, and it will be completed in autumn, 1979. (Kako, I.)

  19. Experience of electric power conservation in COELBA (Bahia Electric Company)

    International Nuclear Information System (INIS)

    Bastos, A.C.F.

    1990-01-01

    The electric power crisis of Brazilian north-east in 1987 imposes the Bahia Electric Company-COELBA to management a electric power conservation. The institutional, organizational and operational aspects are presented, including the tariff system, the market, the consumption and the relation with public. (author)

  20. Monitoring method of an atomic power plant

    International Nuclear Information System (INIS)

    Koba, Akitoshi; Goto, Seiichiro; Ohashi, Hideaki.

    1975-01-01

    Object: To make a monitoring vehicle, which is loaded with various detecting elements, go round along the monorail disposed so as to surround various devices to thereby early discover various abnormal conditions. Structure: The monitoring vehicle is travelled on the monorail disposed so as to surround the periphery of various devices in an atomic power plant so that detection signals from an ITV camera, temperature and radioactive rays and sound detecting elements, and the like are received through a slide contact between the wheel and transmitting and receiving line disposed in the wheel groove to transmit the signals to a central control panel. (Yoshihara, H.)

  1. Environmental impact assessment. Ajka Mining and Power Company

    International Nuclear Information System (INIS)

    Sipkema, Arjan; De Visser, Petra

    1994-01-01

    An Environmental Impact Assessment (EIA) is a public document which evaluates the impact of a new company or a new project on the environment and it also lays out the possible alternatives. The present EIA was worked out to get an insight into the polluting effects of the Ajka Mining and Power Company in Ajka, Hungary and to understand what hinders the abatement of the pollution. The Ajka coal has a high sulphur content and is slightly radioactive. The Power Plant is situated in the neighborhood of the town Ajka and the wind usually blows the releases in the direction of the town. The radioactive sludge is also stored at the border of the town and its radioactivity exceeds the limit set for the Paks Power Plant (in Hungary). Alternatives for the present technology are explored. Nil-condensation and/or energy conservation seem to be the best alternatives. Theoretically, the Regional Environmental Inspectorate is responsible for all survey of pollution, which they monitor with their own equipment, with data obtained from the company or from other monitoring companies. However, the pollution of the Ajka Mining and Power Company is not completely monitored. (authors)

  2. Company of the month: French EDF opts for nuclear power

    International Nuclear Information System (INIS)

    Jansen, Siw Linnea

    2006-01-01

    EDF is Europe's largest power company with 640 TWh produced in 2005 and 36,7 million customers in Europe. On a global scale the company has more than 40 million customers. EDF has significant positions in the four big energy markets in Europe: Germany, France, Great Britain and Italy. EDF has an ambitious investment program in the area of nuclear power, and holds that increased investments in this sector is the best and most beneficial way of keeping up with Europe's increasing energy demand (ml)

  3. Atomic power plant and its operation method

    International Nuclear Information System (INIS)

    Yamamoto, Fumiaki; Higashio, Satoru.

    1986-01-01

    Purpose: To improve operation performance by partially restraining local over power in the axial power distribution of the reactor core by properly controlling the reactor pressure and furthermore by smoothly and properly performing reactor start-up operation in a short time while maintaining fuel integrity. Method: With the reactor pressure input to the pressure controller from the pressure detector, the valve opening of the main steam adjusting valve is adjusted so that the pressure will decrease when the reactor is started up. Also the adjusting valve is controlled so that the pressure will be lower than the set value of rated pressure, thus changing the axial distribution of void. In the meantime, with the stored state of xenon stored along with the increase of reactor power taken into consideration, the reactor pressure is increased as high as the rated value until the reactor power reaches to the rated power, thereby alleviating the local increase of reactor power without changing the whole reactor power and also enabling substantial reduction of reactor start-up time while maintaining reactor integrity. (Horiuchi, T.)

  4. Final Technical Report. Upgrades to Alabama Power Company Hydroelectric Developments

    Energy Technology Data Exchange (ETDEWEB)

    Crew, James F. [Southern Company Generation, Birmingham, AL (United States). Hydro Services; Johnson, Herbie N. [Southern Company Generation, Birmingham, AL (United States). Hydro Services

    2015-03-31

    From 2010 to 2014, Alabama Power Company (“Alabama Power”) performed upgrades on four units at three of the hydropower developments it operates in east-central Alabama under licenses issued by the Federal Energy Regulatory Commission (“FERC”). These three hydropower developments are located on the Coosa River in Coosa, Chilton, and Elmore counties in east-central Alabama.

  5. 75 FR 80547 - Carolina Power & Light Company, Shearon Harris Nuclear Power Plant, Unit No. 1; Exemption

    Science.gov (United States)

    2010-12-22

    ..., Shearon Harris Nuclear Power Plant, Unit No. 1; Exemption 1.0 Background Carolina Power & Light Company... operation of the Shearon Harris Nuclear Power Plant (HNP), Unit 1. The license provides, among other things... request to generically extend the rule's compliance date for all operating nuclear power plants, but noted...

  6. Own power: Motives of having electricity without the energy company

    International Nuclear Information System (INIS)

    Leenheer, Jorna; Nooij, Michiel de; Sheikh, Omer

    2011-01-01

    New technologies will enable households to generate an increasing amount of their own electricity. Intentions to generate own power are a preliminary step towards actual behavior. Because own generation is still very limited and the behavior of early adopters may not be representative for the complete population, our study focuses on intentions rather than actual behavior. A consumer survey among 2047 Dutch households reveals that environmental concerns are the most important driver of a household's intention to generate its own power. Affinity with technology and energy and the reputation of electricity companies are also significant drivers, but financial factors and power outages are not. About 40% of Dutch households have an intention to generate their own power, with an overrepresentation of young households. This group falls apart in two sub segments; for the 'generating savers' (21%) a high intention to generate own power coincides with a high intention to save energy, whereas generating users (18%) combine a high intention to generate own power with a low intention to save energy. - Highlights: → A consumer survey studies household intentions to generate own power. → Environmental concerns are the most important motive for generating own power. → Other drivers are affinity with technology and reputation of electricity companies. → About 40% of Dutch households feel a need to generate their own electricity.

  7. Establishment of professional nuclear power architectural engineering company

    International Nuclear Information System (INIS)

    Guo Dongli; Chen Hua

    2006-01-01

    The rapid development of nuclear power industry in China requires specialized management for the nuclear power engineering projects. It is necessary to establish the nuclear power architectural engineering company to meet the increasing market needs by providing the owner with specialized nuclear engineering project management and overall contracting services. It is imperative that the purpose of establishing the corporation and enterprise core competitiveness should be clearly identified when it is established. Its organizational structure should be geared to the enterprise operation management and development to facilitate the intensified project management and control, and improve its risk-proof ability. (authors)

  8. Motor-Generator powering the PS (Proton Synchrotron) main magnets

    CERN Multimedia

    1983-01-01

    This motor-generator,30 MW peak, 1500 r.p.m.,pulsed power supply for the PS main magnet replaced in 1968 the initial 3000 r.p.m. motor-generator-flywheel set which had served from the PS start-up in 1959 until end 1967. See also photo 8302337 and its abstract.

  9. Main unit electrical protection at Sizewell 'B' power station

    International Nuclear Information System (INIS)

    Fischer, A.; Keates, T.

    1992-01-01

    For any power station, reliable electrical protection of the main generating units (generators plus generator transformers) has important commercial implications. Spurious trips cause loss of generation and consequent loss of revenue, while failure to rapidly isolate a fault leads to unnecessary damage and again, loss of generation and revenue. While these conditions apply equally to Sizewell B there are additional factors to be taken into consideration. A spurious trip of a main generating unit may lead to a trip of the reactor with an associated challenge to the shutdown and core cooling plant. The generator transformers, besides exporting power from the generators to the 400 kV National Grid, also import power from the Grid to the 11 kV Main Electrical System, which in turn is the preferred source of supply to the Essential Electrical System. The Main Unit Protection is designed to clear generator faults leaving this off-site power route intact. Hence failure to operate correctly could affect the integrity of the Essential Electrical Supplies. (Author)

  10. Main building of the Paks nuclear power plant, Hungary

    International Nuclear Information System (INIS)

    Fejes, A.

    1983-01-01

    The general layout of the main service building of the power plant, the applied building materials as well as the prefabricated structures are described. The conditions of planning and construction are discussed. Novel construction methods under the given conditions were utilized. (author)

  11. Prospects of Foreign Capital Raising for Russian Power Grid Companies

    Directory of Open Access Journals (Sweden)

    N. N. Shvets

    2015-01-01

    Full Text Available The power sector reform in Russia saw capital raising as one of the key objectives. Additional investments are necessary, in particular, for renovation of fixed assets which are ca. 70% worn out. The official Strategy for the development of the Russian power grid also provides for privatization of certain companies and foreign investors are considered among others as the target audience. Upon prospective privatization the sector is expected not only to experience a certain increase in capital expenditures, but also to benefit from foreign expertise and efficiency enhancement. At the moment, however, the privatization plans are hard to implement due to a number of obstacles. Prospective investors are mostly concerned about the lack of transparent regulation and clear development strategy of the industry. This is particularly relevant to the tariff system, which has been continuously altered in recent years. This might be explained by the need of the state support by other sectors, which is often provided at the expense of the power industry. Furthermore, the prospects of foreign capital raising are negatively influenced by the conflict in Ukraine and the corresponding negative perception of potential investors. The above factors result in the decrease in value of power grid companies as well as in the lack of visibility regarding the prospects of the sector development. Privatization thus becomes unreasonable both for the state and prospective investors. At the same time, despite the sector specifics, there are precedents of successful sale of power grid assets to private investors by international peers. Particularly, Vatenfall and Forum have recently closed relevant transactions, nothing to say about the power grid sector of Brazil, majorly controlled by private owners. Transparent regulation, clear pricing rules and well-balanced economic policy are, indeed, indispensable prerequisites for successful privatization. Those might back up a

  12. The development of multimedia communication system for electric power company

    Energy Technology Data Exchange (ETDEWEB)

    Woo, Hee Gon; Kim, Seong Bok [Korea Electric Power Corp. (KEPCO), Taejon (Korea, Republic of). Research Center

    1995-12-31

    It is a final report of the research project that is a development of PC-LAN based multimedia desktop conference system, which is research on the essential technologies and application and development of multimedia communication services for electric power company. This report is consisted of -Survey and study of the multimedia related technologies, -Multimedia communication protocols and network configurations, and -Design, developments of pilot model, evaluation, and applications of multimedia conference system. (author). 112 refs., 250 figs.

  13. The development of multimedia communication system for electric power company

    Energy Technology Data Exchange (ETDEWEB)

    Woo, Hee Gon; Kim, Seong Bok [Korea Electric Power Corp. (KEPCO), Taejon (Korea, Republic of). Research Center

    1996-12-31

    It is a final report of the research project that is a development of PC-LAN based multimedia desktop conference system, which is research on the essential technologies and application and development of multimedia communication services for electric power company. This report is consisted of -Survey and study of the multimedia related technologies, -Multimedia communication protocols and network configurations, and -Design, developments of pilot model, evaluation, and applications of multimedia conference system. (author). 112 refs., 250 figs.

  14. Seismic considerations in the design of atomic power plants

    International Nuclear Information System (INIS)

    Arya, A.S.; Chandrasekaran, A.R.; Thakkar, S.K.

    1975-01-01

    A seismic design is one of the most important factors for the safety of nuclear power plants constructed in seismic areas. The various considerations in the design of atomic power plant structures and components to achieve high degree (near absolute) of safety during future probable earthquakes is described as follows: (a) determination of design earthquake parameters for SSE and OBE (b) fixing time history accelerograms and acceleration response spectra (c) mathematical modelling of the reactor building considering soil-structure interaction (d) deciding allowable stresses, damping factors and serviceability limits like drift, displacements and crack widths (e) tests for determining stiffness and damping characteristics of components in-situ before commissioning of plant. The main questions that arise under various items requiring further research investigations or development work are pointed out for discussion. (author)

  15. VG-400 atomic power and technological installation. Possible core design

    International Nuclear Information System (INIS)

    Komarov, E.V.; Laptev, F.V.; Lyubivyj, A.G.; Mitenkov, F.M.; Samojlov, O.B.; Sukhachevskij, Yu.B.

    1979-01-01

    The main characteristics, basic circuit and configuration of equipment of the VG-400 atomic power and technological installation are considered. This installation is intended for supplying with highly-potential heat of thermal electrochemical hydrogen production and for power generation in the steam-turbine cycle. The main installation characteristics: HTGR reactor heat power 1100 MW, electric power 300 MW, helium coolant pressure 50 atm, output temperature 950 deg C, steam pressure in the second contour 175 atm, temperature 535 deg C, core diameter and height 6.4 m and 4 m, respectively, number of spherical fuel elements 8.5x10 5 . The installation can ensure hydrogen production of 10 5 Nxm 3 /h. For the VG-400 reactor block the integral arrangement of the first circuit equipment in the reinforced concrete is chosen. Two versions of the reactor core with prismatic and spherical fuel elements are compared. It is shown that taking into account great potentialities of the spherical zone in a case of further temperature increase and its positive qualities with respect to construction and processing of fuel elements and graphite blocks, the utilization of simplier units and mechanisms in the overloading system and in the process of profiling of energy distribution the choice of the spherical configuration for the VG-400 pilot plant installation seems to be valid

  16. 76 FR 36910 - Astoria Generating Company, L.P., NRG Power Marketing LLC, Arthur Kill Power LLC, Astoria Gas...

    Science.gov (United States)

    2011-06-23

    ... Generating Company, L.P., NRG Power Marketing LLC, Arthur Kill Power LLC, Astoria Gas Turbine Power LLC... Generating Company, L.P., NRG Power Marketing LLC, Arthur Kill Power LLC, Astoria Gas Turbine Power [[Page... subscribed docket(s). For assistance with any FERC Online service, please e-mail [email protected

  17. 76 FR 34692 - Astoria Generating Company, L.P., NRG Power Marketing LLC, Arthur Kill Power LLC, Astoria Gas...

    Science.gov (United States)

    2011-06-14

    ... Generating Company, L.P., NRG Power Marketing LLC, Arthur Kill Power LLC, Astoria Gas Turbine Power LLC... Generating Company, L.P., NRG Power Marketing LLC, Arthur Kill Power LLC, Astoria Gas Turbine Power LLC... notification when a document is added to a subscribed docket(s). For assistance with any FERC Online service...

  18. Rotary-atomizer electric power generator

    NARCIS (Netherlands)

    Nguyen, Trieu; Tran, Tuan; de Boer, Hans L.; van den Berg, Albert; Eijkel, Jan C.T.

    2015-01-01

    We report experimental and theoretical results on a ballistic energy-conversion method based on a rotary atomizer working with a droplet acceleration-deceleration cycle. In a rotary atomizer, liquid is fed onto the center of a rotating flat surface, where it spreads out under the action of the

  19. Analysis of main dynamic parameters of split power transmission

    Directory of Open Access Journals (Sweden)

    A. Janulevičius

    2008-06-01

    Full Text Available The review carried out had shown one basic approach of split power transmission to the organization of drive which is applied to stepless transmissions of tractors and parallel hybrid cars. In the split power transmission the power split device uses a planetary gear. Tractor engine power in the split power transmission is transmitted to the drive shaft via a mechanical and hydraulic path. The theoretical analysis of main parameters of the split power transmission of the tractor is presented. The angular velocity of sun and coronary gears of the differential set is estimated by solution of the system of equations in which one equation is made for planetary differential gear, and another – for hydrostatic drive. The analysis of the transmission gear-ratio dependencies on the ratio of hydraulic machines capacities is carried out. Dependence of the variation of angular velocity of the coronary and the sun gears on the ground speed of the tractor is presented. Dependence of sum shaft torque and its constituents, carried by mechanical and hydraulic lines, on sum shaft angular velocity and ground speed of tractor and engine speed is also presented.

  20. Main aspects of the planned reform of the Act on the Peaceful Uses of Atomic Energy and Protection against its Hazards (Atomic Energy Act)

    International Nuclear Information System (INIS)

    Lukes, R.

    1991-01-01

    There is no specific reason for planning a reform of the atomic energy law just now; the main idea is to keep the atomic energy law abreast with the developments made in the regime of protective laws pertaining to the sector of science and technology. A further aspect not to be neglected, however, is the nuclear power phase-out currently under debate, and a decision against the abandonment of nuclear power should be taken as an occasion to think about a nuclear law reform. The judiciary has been contributing to the development of nuclear law in the last years, and the decisions of the Federal Constitutional Court and of the Federal Administrative Court have not only set the corner flags for the future development of the nuclear law, but have given concrete shape by final settlement of cases of divergence of judicial decisions, to the protective intents of the law and to the subject-related purposes. Thus the judiciary has been taking into account the idea prevailing today, namely that the scope of duties of the Federal Government certainly includes the task of protecting the citizens against the hazards of technology in general, and of novel technologies in particular, and the task of avoiding hazards. So the main line of orientation to be pursued is to draw level with protective regulations established in other fields of law, and to make the Atomic Energy Act a modern instrument of protection by the law. (orig./HSCH) [de

  1. Thoughts on Documentation of Atomic Power Technology

    International Nuclear Information System (INIS)

    Oh, Jeong Hoon; Lee, Hee Won; Song, Ki Chan

    2012-01-01

    Korean Atomic Energy Research Institute (KAERI) has accumulated a number of technology development and research outcomes, including its representative achievements such as atomic energy technology independence and the first export of atomic energy system, since it was established in 1959. With its long history of over 50 years, KAERI has produced a large amount of information and explicit knowledge such as experiment data, database, design data, report, instructions, and operation data at each stage of its research and development process as it has performed various researches since its establishment. Also, a lot of tacit knowledge has been produced both knowingly and not unknowingly based on the experience of researchers who have participated in many projects. However, in the research environment in Korea where they focus overly on the output, tacit knowledge has not been managed properly compared to explicit knowledge. This tacit knowledge is as an important asset as explicit knowledge for an effective research and development. Moreover, as the first generation of atomic energy independence and research manpower retire, their accumulated experience and knowledge are in danger of disappearing. Therefore, in this study, we sought how to take a whole view and to document atomic energy technology researched and developed by KAERI, from the background to achievement of each field of the technology. Comprehensive and systematic documentation of atomic energy technology will establish a comprehensive management system of national atomic energy technology record to make a foundation of technical advancement and development of atomic energy technology. Also, it is expected to be used as an important knowledge and information resource of atomic energy knowledge management system

  2. 'Nuclearelectrica' Company messages for a broadly acceptable nuclear power program

    International Nuclear Information System (INIS)

    Stiopol, Mihaela; Bilegan, C. Iosif

    2001-01-01

    Romania started the nuclear power program about 20 years ago, by a high level Government decision. After 1989 the former Ministry of Electrical Power was transformed into a state owned company, RENEL, in which nuclear activities were also included. RENEL was a monopoly system responsible for production, transport and distribution of electricity in Romania. The deregulation process in the power sector was many times asked by the World Bank and International Monetary Fund, to split this monopoly system in separately activities: Production, Transport and Distribution. The first step occurred in July 1998, when the nuclear activities were externalized from RENEL. In nuclear sector two new entities were created: SN 'Nuclearelectrica' SA, a state own company that includes three branches: - Nuclear Power Production - Cernavoda NPP Unit 1; - Nuclear Fuel Plant-Pitesti; - Project Development Branch - Cernavoda Units 2-5. The second entity is the so-called Romanian Authority (Autonomous Reggie) for Nuclear Activities (RAAN), including as branches the heavy water fabrication plant 'ROMAG PROD', the Nuclear Research Institute (ICN) Pitesti and the Nuclear Engineering and Design Institute (CITON) Bucharest. The rest of conventional power sector was renamed, namely, CONEL. The organization process continued and in August 2000, by a Government Ordinance the CONEL was split into the following companies: - one for hydropower production 'HIDROELECTRICA'; - one for thermal power production 'TERMOELECTRICA'; - one for transport 'TRANSELECTRICA'; - one for distribution 'ELECTRICA'. The goal of a third step of restructuring process is the privatization in the power field. The steps of Romanian Power Sector Restructuring are presented. Since 1991 a Public Information program has been established. Depending on the evolution of the construction of the first Romanian nuclear power station, during the years, the messages changed. Everybody working in the nuclear field knows how difficult is

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

    International Nuclear Information System (INIS)

    2011-12-01

    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)

  4. Appreciation analysis for power supply companies; Wertsteigerungsanalyse fuer Energieversorgungsunternehmen

    Energy Technology Data Exchange (ETDEWEB)

    Muche, T. [Hochschule Zittau/Goerlitz (Germany)

    2007-08-15

    In view of the probable future consolidation in the energy economy with municipal undertakings increasingly becoming subject to takeovers and participations issues of shareholder value are a matter of growing interest for power supply companies. Amongst other advantages, having a high shareholder value guards against unwanted takeovers. However, it is not enough for companies merely to know their shareholder value; they must rather have their entire operative and strategic planning and control instruments geared to it. This forms the background to a pilot project at Goerlitz/Zittau University which was dedicated to an analysis of the shareholder value of municipal undertakings on the basis of year-end financial and capital market data.

  5. Results of the radiological survey at the Napp Chemical Company, 199 Main Street, Lodi, New Jersey (LJ076)

    International Nuclear Information System (INIS)

    Foley, R.D.; Floyd, L.M.; Carrier, R.F.

    1989-11-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally 232 Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, the Napp Chemical Company, 199 Main Street, Lodi, New Jersey (LJ076), was conducted during 1987. Results of the survey demonstrated no radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. The radionuclide distributions were not significantly different from normal background levels in the northern New Jersey area. 4 refs., 8 figs., 3 tabs

  6. The booster linac of the Sparkle Company 18 MeV Cyclotron: main design elements

    International Nuclear Information System (INIS)

    Picardi, L.; Ronsivalle, C.

    2009-01-01

    The Sparkle Company (Casarano, Le) that is setting up a centre for production and research on radioisotopes for medical use, has requested to the ENEA Accelerator Laboratory a specific design of a linear accelerator for boosting the energy of its commercial cyclotron from 18 to 24 MeV, with the aim of implementing a small proton irradiation facility for radiobiology studies. This is the first case of coupling a cyclotron beam to a linac, that, if successful, can give rise to a new class of accelerators for proton therapy. The linac can accelerate only a very small portion of the cyclotron beam, due to the intrinsic mismatching of the two kind of accelerators both in the vertical and in the longitudinal phase planes. A beam transport line has been studied that besides matching at best the beam to the linac in the transverse plane, is equipped with a chopping system to lower drastically the primary beam power in order to protect the linac structure. The linac is SCDTL type, and operates at 3 GHz. In the following the results of the design are presented. [it

  7. THE ANALYSIS OF STRUCTURAL RELIABILITY OF THE MAIN ELECTRIC CONNECTION CIRCUITS OF NUCLEAR POWER PLANTS

    Directory of Open Access Journals (Sweden)

    M. A. Korotkevich

    2017-01-01

    Full Text Available The reliability of the main circuit of electrical connections at a nuclear electric power plant that has two units with a capacity of 1,200 MW each has been determined. Reliability, economical, maneuverable properties of the atomic power plant under study are largely determined by its main circuit, so the choice of the circuit for the design and its status in the process of operation occur to be critical objectives. Main electrical connection circuits in nuclear electric power plants are selected on the basis of the schematic networks of the energy system and the land attached to the plant. The circuit of the connection of a nuclear power plant to the grid in the original normal operating modes at all stages of the construction of such a plant should provide the outcome of the full added capacity of a nuclear power plant and the preservation of its stability in the power system without the influence of the emergency system automatics when any outgoing transmission line is disabled. When selecting the main circuit the individual capacity of the installed units and their number are taken into account as well as the order of development of the plant and power supply system; the voltage on which the power of a plant is delivered; a shortcircuit current for switchgear high voltage and the need for their limitation by circuit means; the most power that can be lost when damage to any switch. A model of reliability of the main circuit of electrical connections is designed to detect all types of accidents that are possible at the coincidence of failures of elements with the repair and operational modes that differs in composition and damageability of the equipment, as well as under conditions of the development of accidents due to failure of operation of devices of relay protection and automation.

  8. DEVELOPMENT OF RUSSIAN FEDERATION POWER SELLING COMPANY STRATEGIC MANAGEMENT

    Directory of Open Access Journals (Sweden)

    S. V. Grishkevich

    2011-01-01

    Full Text Available Strategic for power selling companies (PSC are buying, selling and investment activities. Buying activities are to be planned, selling activities predicted and both optimized by PSC on the basis of price and consumer number dynamics with due account of other factors. Very important is to develop the market of derivative instruments (derivatives as part of the risk management mechanism at all levels including that of the state, to use up-to-date and ecologically favorable technologies as well as renewable energy sources with due account of ecology improvement measurement costs.

  9. Power demand operation - environment and potential. Proposals for main project

    International Nuclear Information System (INIS)

    Wathne, M.

    1995-01-01

    This report discusses proposals for a main project on environmental and other problems arising when hydroelectric power stations supply energy at gigawatt levels. The project aims in particular to identify environmental problems where too little is known today for proper planning of this type of operation. The proposals emphasize the consequences which cannot be adequately analysed in terms of current techniques. These techniques presuppose steady state conditions. One proposal concerns market terms for power sales. Other proposals deal with hydrological data and uncertainty, capacity of watercourses, ice and temperature, aquatic eco-systems, erosion, supersaturation of water with air, flooding and dam breaks, impact on climate, inflow of fresh water in fjords and impact on algae. 33 refs., 4 tabs

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

    Energy Technology Data Exchange (ETDEWEB)

    Zagorski, J. F.

    1980-01-01

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

  11. High power atomic iodine photodissociation lasers

    International Nuclear Information System (INIS)

    Palmer, R.E.; Padrick, T.D.; Jones, E.D.

    1976-01-01

    The atomic iodine photodissociation laser has developed into a system capable of producing nanosecond or shorter pulses of near infrared radiation with energies well in excess of a hundred J. Discussed are the operating characteristics, advantages, and potential problem areas associated with this laser

  12. Company Slogan and a Vivid Image of a Trademark - as Main Components of a Strong Brand

    Directory of Open Access Journals (Sweden)

    Igor BELOSTECINIC

    2015-12-01

    Full Text Available Among other methods, good brand managers always affect clients and strengthen their fidelity to the brand by means of company advertising slogans and vivid images associated with this brand. Slogans may function as useful “levers” or “hooks” helping clients to understand the essence of a trademark and its peculiarity, as well as to nail in clients' minds the established image of a strong brand. One of the “hooks” attracting attention to brand and helping to nail it in a common man's mind – is a company (advertising slogan - short message or motto, which actively presents the key theme of the brand in general or of a certain advertising campaign, and contains substantial information, reflecting the essence of campaign's or product's marketing offer. One must admit that it is nice to recall favorite philosopher's aphorisms or sayings while getting up in the morning, and to whistle an aria from a renowned opera on your way to work. However, more often people sing unsophisticated verses about the “sign of a good taste” and get annoyed by a trivial call to “have a break” going round in their heads. This means that the advertisement of popular chocolate bars and drinks has hit its target. The main lever for success in generation of a positive and recognizable brand image - is the slogan and its graphic image in consumer's mind. Together with other brand components (logo, corporate colors, sound or music image a slogan generates the system of constant elements which ensure the brand's internal unity and are aimed at creation of exposure effect. To some extent, we all are “ad eaters” and are always capable of estimating an ad, even if it is at the level of feelings: whether we like it or not. So why a certain advertisement can make us smile, elicit good feelings and cause an urge to buy product/service that is being advertised, and another one - evokes disappointment and annoyance? The answer is obvious: the first one was

  13. Nuclear Regulatory Commission Issuances, Volume 44, No. 5

    International Nuclear Information System (INIS)

    1996-11-01

    This report includes the issuances received in November 1996. Issuances are from the Commission, the Atomic Safety and Licensing Boards, and the Directors' Decisions. Seven issuances were received and are abstracted individually in the database: Emerick S. McDaniel, U.S. Enrichment Corporation, Sequoyah Fuels Corporation and General Atomics, all power reactor licensees, Florida Power and Light Company, Maine Yankee Atomic Power Company, and Northern States Power Company. No issuances were received from the the Administrative Law Judges or the Decisions on Petitions for Rulemaking

  14. Service life monitoring of the main components at the Temelin nuclear power plant

    International Nuclear Information System (INIS)

    Hahn, J.; Vincour, D.

    2007-01-01

    Knowledge and experience gained from the introduction and periodical implementation of life assessment of the major components of the Temelin nuclear power plant is summarized. The initial Soviet technical design of the plant did not incorporate lifetime monitoring and evaluation, therefore it was completed with demonstrative strength and lifetime calculations from Czech companies. Moreover, a Westinghouse primary circuit diagnosis and monitoring system, including the monitoring of temperature and pressure cycles for low-cycle fatigue evaluation, was installed at the plant. The DIALIFE code for the calculation of mainly the low-cycle fatigue of the key pressure components, was developed and installed subsequently as a superstructure to the monitoring system. (author)

  15. Tampa Electric Company Polk Power Station IGCC project: Project status

    Energy Technology Data Exchange (ETDEWEB)

    McDaniel, J.E.; Carlson, M.R.; Hurd, R.; Pless, D.E.; Grant, M.D. [Tampa Electric Co., FL (United States)

    1997-12-31

    The Tampa Electric Company Polk Power Station is a nominal 250 MW (net) Integrated Gasification Combined Cycle (IGCC) power plant located to the southeast of Tampa, Florida in Polk County, Florida. This project is being partially funded under the Department of Energy`s Clean Coal Technology Program pursuant to a Round II award. The Polk Power Station uses oxygen-blown, entrained-flow IGCC technology licensed from Texaco Development Corporation to demonstrate significant reductions of SO{sub 2} and NO{sub x} emissions when compared to existing and future conventional coal-fired power plants. In addition, this project demonstrates the technical feasibility of commercial scale IGCC and Hot Gas Clean Up (HGCU) technology. The Polk Power Station achieved ``first fire`` of the gasification system on schedule in mid-July, 1996. Since that time, significant advances have occurred in the operation of the entire IGCC train. This paper addresses the operating experiences which occurred in the start-up and shakedown phase of the plant. Also, with the plant being declared in commercial operation as of September 30, 1996, the paper discusses the challenges encountered in the early phases of commercial operation. Finally, the future plans for improving the reliability and efficiency of the Unit in the first quarter of 1997 and beyond, as well as plans for future alternate fuel test burns, are detailed. The presentation features an up-to-the-minute update on actual performance parameters achieved by the Polk Power Station. These parameters include overall Unit capacity, heat rate, and availability. In addition, the current status of the start-up activities for the HGCU portion of the plant is discussed.

  16. Decommissioning cost recovery in the United States: lessons learned from Connecticut Yankee NPP

    International Nuclear Information System (INIS)

    Joosten, J.

    1999-01-01

    The international audience at ICONE-7 is already familiar with the roles of the owner and the NRC in ensuring the technical and safety performance goals of nuclear plant decommissioning. This paper addresses the role of the economic regulator since the pursuit of technical and safety goals must necessarily carry with them -a price tag- and owners must be concerned with the recovery of those costs. Answers to questions about how to pay and who should pay for decommissioning can very often influence nuclear power plant owner's decision-making. In the United States, most nuclear power plants are privately owned. Nevertheless, their owners are not totally free to determine the plant's economics or profitability. Instead, plant owners must sell their electricity to consumers in a regulated market wherein the price of electricity and terms of sale are controlled by the government. Under this regulatory regime, utilities are generally allowed to recover their investment costs -including decommissioning costs- provided that such costs are prudently, incurred. However, when an owner retires the plant prematurely, the prudence of his actions -up to and including the shutdown- are likely to be challenged. In 1997, for example, the owners of the Connecticut Yankee reactor faced a stiff challenge to the recovery of decommissioning costs when they shut down the plant ten years before license expiration. The Connecticut Yankee case thus provides valuable insights into the role of economic regulation on a nuclear plant's decommissioning strategy. (author)

  17. The World Power Conference and atomic energy

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1962-01-15

    The possibility that emerged after the last World War that useful power could be produced from nuclear fission led to optimistic estimates that nuclear power would prove to be the solution to the world's energy problems. The possible advantages of nuclear methods of power production compared with conventional means are discussed at the World Power Conference. The 1962 Conference with its theme 'The Changing Pattern of Power' will undoubtedly attract great interest in a world where the change-over from conventional to nuclear fuels for power production has started in some countries and is being actively examined in others. It is generally being realized that even though a country may possess indigenous supplies of uranium or thorium minerals, the building up of a nuclear industry i s a long and expensive process and the alternative of depending on countries more advanced in nuclear technology for the supply of materials, skill and know-how is costly in foreign exchange and international prestige. Many of the industrialized countries, still possessing supplies of conventional fuels, are preparing for the day when their reserves will become depleted and are embarking on training schemes to ensure a continuing supply of engineers and scientists skilled in nuclear arts

  18. Design of investment management optimization system for power grid companies under new electricity reform

    Science.gov (United States)

    Yang, Chunhui; Su, Zhixiong; Wang, Xin; Liu, Yang; Qi, Yongwei

    2017-03-01

    The new normalization of the economic situation and the implementation of a new round of electric power system reform put forward higher requirements to the daily operation of power grid companies. As an important day-to-day operation of power grid companies, investment management is directly related to the promotion of the company's operating efficiency and management level. In this context, the establishment of power grid company investment management optimization system will help to improve the level of investment management and control the company, which is of great significance for power gird companies to adapt to market environment changing as soon as possible and meet the policy environment requirements. Therefore, the purpose of this paper is to construct the investment management optimization system of power grid companies, which includes investment management system, investment process control system, investment structure optimization system, and investment project evaluation system and investment management information platform support system.

  19. 76 FR 36914 - Astoria Generating Company, L.P., NRG Power Marketing LLC, Arthur Kill Power LLC, Astoria Gas...

    Science.gov (United States)

    2011-06-23

    ... Generating Company, L.P., NRG Power Marketing LLC, Arthur Kill Power LLC, Astoria Gas Turbine Power LLC... Power Marketing LLC, Arthur Kill Power LLC, Astoria Gas Turbine Power LLC, Dunkirk Power LLC, Huntley... when a document is added to a subscribed docket(s). For assistance with any FERC Online service, please...

  20. Emergency response facility technical data system of Taiwan Power Company

    International Nuclear Information System (INIS)

    Lin, E.; Liang, T.M.

    1987-01-01

    Taiwan Power Company (Taipower) has developed its emergency response facility program since 1981. This program is integrated with the following activities to enhance the emergency response capability of nuclear power plants: (1) survey of the plant instrumentation based on the requirements of R.G. 1.97; (2) improvement of plant specific emergency operating procedures based on the emergency response guidelines developed by the Owners group; (3) implementation of the detailed control room design review with the consideration of human engineering and task analysis; and (4) organization, staff and communication of emergency planning of nuclear power plant. The emergency response facility programs of Taipower are implemented in Chinshan (GE BWR4/MARK I), Kuosheng (GE BWR6/MARK III) and Maanshan (W PWR). The major items included in each program are: (1) to establish new buildings for On-Site Technical Support Center, Near-Site Emergency Operation Facility; (2) to establish an Emergency Executive Center at Taipower headquarters; (3) to establish the communication network between control room and emergency response facilities; and (4) to install a dedicated Emergency Response Facility Technical Data System (ERFTDS) for each plant. The ERFTDS provides the functions of data acquisition, data processing, data storage and display in meeting with the requirements of NUREG 0696. The ERFTDS is designed with plant specific requirements. These specific requirements are expected to be useful not only for the emergency condition but also for normal operation conditions

  1. TQC works in newly-built nuclear power plant and main electric power system plannings

    International Nuclear Information System (INIS)

    Akiyama, Yoshihisa; Kawakatsu, Tadashi; Hashimoto, Yasuo

    1985-01-01

    In the Kansai Electric Power Co., Inc., TQC has been introduced to solve such major problems in nuclear power generation as the securing of nuclear power reliability, the suppression of rises in the costs, the reduction in long periods of power failure and the promotion in siting of nuclear power plants. It is thus employed as a means of the ''creation of a slim and tough business constitution''. The state of activities in Kansai Electric are described in quality assurance of a newly-built nuclear power plant and in raising the reliability of the main electric power system to distribute the generated nuclear power and further the future prospects are explained. (Mori, K.)

  2. Health physics practices and experience at Duke Power Company

    International Nuclear Information System (INIS)

    Lewis, L.

    1986-01-01

    The history and development of the health physics and as-low-as-reasonably-achievable (ALARA) program at Duke Power Company's Oconee Nuclear Station is described as are the fundamental elements of the program and how the program works. The benefits of this health physics/ALARA program have been determined to be (a) improved quality of manpower planning and scheduling, (b) increased efficiency of shutdown activities, (c) reduced cost of shutdown, (d) immediate awareness of adverse job exposure trends, (e) better management information on exposure-related problems, (f) improved accuracy of personnel and job dose records, and (g) in general, improved outage performance and subsequent plant operation. Experience with the health physics/ALARA program is discussed in terms of (a) savings of critical path time, (b) maintaining ALARA personnel doses, and (c) record capacity factors

  3. The Northern States Power Company welding manual advisor

    International Nuclear Information System (INIS)

    Lu, Yi; Wood, R.M.

    1993-01-01

    The Welding Manual Advisor (WMA) is an object oriented expert system designed to assist Northern States Power (NSP) personnel in implementing the company's Welding Manual. The expert system captures the knowledge of welding experts, addresses important issues in welding activities and automates the use of the Welding Manual. It is estimated that use of the WMA will save $81,000 over the next six years at NSP, because of the reduction of labor and errors in the use of the Welding Manual, and facilitation of training of NSP personnel. The important features of the WMA include the accuracy and consistency in determining welding procedure and requirements, update capability, user friendly interface, on-line help function, back-up capability, and well-documented manuals

  4. Atom chief calls for decision on N-power

    International Nuclear Information System (INIS)

    Hughes, N.

    1982-01-01

    A decision must be made, on whether South Africa is going to build more nuclear power stations. The Atomic Energy Corporation and the Electricity Supply Commission should come together, to present a nuclear development plan to the Government. If the nuclear power industry is going to expand, everything must be co-ordinated and this should be done in the immediate future

  5. Operation and maintenance experience at the General Atomic Company's TRIGA reactor facility at San Diego, California

    International Nuclear Information System (INIS)

    Whittemore, W.L.; Stout, W.A.; Shoptaugh, J.R.; Chesworth, R.H.

    1982-01-01

    Since the startup of the original 250 kW TRIGA Mark I reactor in 1958, General Atomic Company has accumulated nearly 24 years of operation and maintenance experience with this type of reactor. In addition to the nearly 24 years of experience gained on the Mark I, GA has operated the 1.5 MW Advanced Prototype Test Reactor (Mark F) for 22 years and operated a 2 MW below-ground TRIGA Mark III for five years. Information obtained from normal and abnormal operation are presented. (author)

  6. Power grid, mains filtering and power line communications ... a root cause for incompatibilities

    NARCIS (Netherlands)

    Coenen, Mart

    2013-01-01

    The power grid is intentionally meant to distribute electrical energy at the mains frequency, as produced by the electricity generating plants, towards the end-users. The three-phase low-voltage distribution network can be utilized more efficiently when a power factor of 1 is achieved and no

  7. Tarapur Atomic Power Station - - an overview of experience

    International Nuclear Information System (INIS)

    Shah, J.C.

    1979-01-01

    A broad overview of the experience and performance of the Tarapur Atomic Power Station (TAPS) in its role as the developing world's first foray in commercial atomic power has been attempted. The prime objective was not just generation of power but assimilation of an advanced technology on an economically viable basis in the underdeveloped environment compounded with governmental organisational culture. Scientific and technical advances registered through the TAPS experience in the area of design, operation and maintenance are mentioned. Aspects of station performance, management and even economics are also covered. (auth.)

  8. Framatome advanced nuclear power-benefits for our clients from the new company

    International Nuclear Information System (INIS)

    Weber, P.

    2001-01-01

    Framatome ANP (Advanced Nuclear Power) merges the complementary strengths of two global nuclear industry leaders Framatome and Siemens - offering clients the best technological solutions for safe, reliable and economical plant performance. With a combined workforce of 13,300 skilled individuals, Framatome ANP is now the nuclear industry's leading supplier. Serving as Original Equipment Manufacturer (OEM) for more than 90 reactors that provide about 30% of the world's total installed nuclear power capacity, our experienced resources remain focused on the local needs of individual clients, wherever in the world they may be. The Company main business used to be turnkey construction of complete Nuclear Power plants, BWR and PWR capabilities, heavy equipment manufacturing, comprehensive I and C capabilities, and also expertise and knowledge of VVER. Framatome ANP will benefit in all of its fields of activity of the experience gained through Framatome and Siemens' collaboration on the next generation reactor, the EPR, as well as on steam generators replacements and or modernization of VVER. Framatome ANP nuclear fuel designs for both PWR and BWR plants provide innovative features and world-leading performance. Framatome ANP is organized according a matrix organization with: - 4 Business Groups (Project and Engineering, Service, Nuclear Fuel, Mechanical Equipment) - 3 Regional Divisions (Framatome Advanced Nuclear Power S.A.S., France; Framatome Advanced Nuclear Power GmbH, Germany; Framatome Advanced Nuclear Power Inc., USA). By 30th January 2001 Siemens Nuclear Power GmbH, founded in 2000 as successor of the Nuclear Division of Siemens Power Generation Group (KWU), was renamed to Framatome Advanced Nuclear Power GmbH forming the German part of the world wide acting company. Over the past 40 years 23 nuclear power plants all around the world - not only pressurized and boiling water reactors, but also two heavy-watermoderated reactors have been designed, constructed and

  9. Fire safety in atomic power plants

    International Nuclear Information System (INIS)

    Kench, R.L.; British Insurance

    1988-01-01

    The main reactor types are described briefly - Magnox, advanced gas cooled, pressurized water and fast reactors. Fire risks exist at fuel stores and spent fuel storage facilities. Simple fire prevention measures are suggested. Solid radioactive wastes can also be combustible. Various fire prevention measures for the different storage methods, eg compaction, are given. Gaseous and liquid wastes are also considered. The main types of reactor accident are described and the causes of four incidents - at Chernobyl, Windscale, Brownsferry and Three Mile Island, are examined. (U.K.)

  10. Beaver Valley Power Station and Shippingport Atomic Power Station. 1977 annual environmental report: radiological. Volume 2

    International Nuclear Information System (INIS)

    1978-01-01

    The environmental monitoring conducted during 1977 in the vicinity of the Beaver Valley Power Station and the Shippingport Atomic Power Station is described. The environmental monitoring program consists of onsite sampling of water, gaseous, and air effluents, as well as offsite monitoring of water, air, river sediments, and radiation levels in the vicinity of the site. The report discusses releases of small quantities of radioactivity to the Ohio River from the Beaver Valley Power Station and Shippingport Atomic Power Station during 1977

  11. Demonstration test for reliability of valves for atomic power plants

    International Nuclear Information System (INIS)

    Hosaka, Shiro

    1978-01-01

    The demonstration test on the reliability of valves for atomic power plants being carried out by the Nuclear Engineering Test Center is reported. This test series is conducted as six-year project from FY 1976 to FY 1981 at the Isogo Test Center. The demonstration test consists of (1) environmental test, (2) reaction force test, (3) vibration test, (4) stress measurement test, (5) operational characteristic test, (6) flow resistance coefficient measuring test, (7) leakage test and (8) safety valve and relief valve test. These contents are explained about the special requirements for nuclear use, for example, the enviornmental condition after the design base accident of PWRs and BWRs, the environmental test sequence for isolation valves of containment vessels under the emergency condition, the seismic test condition for valves of nuclear use, the various stress measurements under thermal transient conditions, the leak test after 500 cycles between the normal operating conditions for PWRs and BWRs and the start up conditions and so on. As for the testing facilities, the whole flow diagram is shown, in which the environmental test section, the vibration test section, the steam test section, the hot water test section, the safety valve test section and main components are included. The specifications of each test section and main components are presented. (Nakai, Y.)

  12. The power of PV: one US company shows the potential of solar energy

    International Nuclear Information System (INIS)

    Wood, L.

    2005-01-01

    A California-based company, PowerLight, has grown from a one-man shop in 1991 to a company with 100 employees, an annual turnover of $100 million and an impressive client list. The company is one of the USA's fastest growing companies and a leader in large-scale, grid-connected solar systems. Its patented PowerGuard offers a lightweight solar rooftop assembly, while its PowerTracker product is a ground-mounted PV system. Details of some of the company's large projects are given and its plans for new markets highlighted

  13. About connection between atomic and hydrogen energy power

    International Nuclear Information System (INIS)

    Avdeeva, M.Zh.; Vecher, A.A.; Pan'kov, V.V.

    2008-01-01

    Possible interaction between atomic and hydrogen energy power has been discussed. The analysis of the result held shows that the electrical energy produced by the atomic reactor during the of-load hours can be involved into the process of obtaining hydrogen by electrolysis. In order to optimize the transportation and storage of hydrogen it is proposed to convert it into ammonia. The direct uses of ammonia as a fuel into the internal combustion engine and fuel cells are examined. (authors)

  14. Environmental management in companies: an analysis of the scientific production on environmental management in companies published in the main journals on administration between 1996 and 2005

    Directory of Open Access Journals (Sweden)

    Fernando César Almada Santos

    2008-07-01

    Full Text Available The aim of this article is to analyse the scientific production on environmental management in companies published in the six main journals on administration in Brazil (RAE, RAEE, RAUSP, RAP, REAd and RAC, during the period between 1996 and 2005. The following aspects were used in order to examine this academic production: quantitative progress of production; source of authorship; methodological profile; publication content and breadth; and internationalization level of references. The main concerns of this diagnosis are: the academic production on environmental management in companies corresponds to only 2,30% of the total production in administration; a significant part of this production is stimulated by international studies, mainly Hunt and Auster (1990 and Porter and Linde (1995; Brazilian research is restricted to small group of researchers and institutions, as almost 60% of the analyzed articles were published by only five institutions. Thus, this article contributes to the systematization of the academic production on environmental management in companies, as well as it provides insights for this field of research in Brazil.

  15. Development of management systems for nuclear power plant of Hokuriku Electric Power Company

    International Nuclear Information System (INIS)

    Nakamura, Tatsuaki; Hasunuma, Junichi; Suzuki, Shintaro

    2009-01-01

    Hokuriku Electric Power Company has been operating the Shika Nuclear Power Station that it constructed in Shika city, Ishikawa prefecture, for over 15 years since bringing Unit 1 of this plant online in July 1993. In addition to electricity generation, maintenance and inspection tasks constitute a big part of operating a large-scale nuclear power plant, and in recent years, problems at power stations in the nuclear power industry have led to several revisions of nationally regulated maintenance and inspection systems. This paper describes the background, objectives, development method, and features of the Maintenance Management System and Maintenance History Management System that make effective use of information technology to promote safer and more efficient maintenance work at large-scale nuclear power plants. (author)

  16. Power law load dependence of atomic friction

    OpenAIRE

    Fusco, C.; Fasolino, A.

    2004-01-01

    We present a theoretical study of the dynamics of a tip scanning a graphite surface as a function of the applied load. From the analysis of the lateral forces, we extract the friction force and the corrugation of the effective tip-surface interaction potential. We find both the friction force and potential amplitude to have a power-law dependence on applied load with exponent similar to1.6. We interpret these results as characteristic of sharp undeformable tips in contrast to the case of macr...

  17. 75 FR 16524 - FirstEnergy Nuclear Operating Company, Perry Nuclear Power Plant; Exemption

    Science.gov (United States)

    2010-04-01

    ... Company, Perry Nuclear Power Plant; Exemption 1.0 Background FirstEnergy Nuclear Operating Company (FENOC... the Perry Nuclear Power Plant, Unit 1 (PNPP). The license provides, among other things, that the... date for all operating nuclear power plants, but noted that the Commission's regulations provide...

  18. DETERMINANTS AFFECTING THE SUCCESS OF DISTRIBUTION GRID PROJECTS IN BINH THUAN POWER COMPANY, VIETNAM

    OpenAIRE

    Pham Van Tai* & Le Duc Thu

    2017-01-01

    The research identified the critical factors affecting the success of the distribution grid project in Binh Thuan Power Company, clarify the mutual relationship between the critical factors affecting the success of the distribution grid project in Binh Thuan Power Company and recommended and rated the solution to enhance the success of the distribution grid project in Binh Thuan Power Company. The research had found fours critical factors: External factors of project, Controlling and coordina...

  19. Attitudes of the general public and electric power company employees toward nuclear power generation

    International Nuclear Information System (INIS)

    Komiyama, Hisashi

    1997-01-01

    We conducted an awareness survey targeted at members of the general public residing in urban areas and in areas scheduled for construction of nuclear power plants as well as employees of electric power company in order to determine the awareness and attitude structures of people residing near scheduled construction sites of nuclear power plants with respect to nuclear power generation, and to examine ways of making improvements in terms of promoting nuclear power plant construction sites. Analysis of those results revealed that there are no significant differences in the awareness and attitudes of people residing in urban areas and in areas near scheduled construction sites. On the contrary, a general sense of apprehension regarding the construction of nuclear power plants was observed common to both groups. In addition, significant differences in awareness and attitudes with respect to various factors were determined to exist between members of the general public residing in urban areas and scheduled construction sites and employees of electric power company. (author)

  20. Nuclear power and atomic weapons. Chapter 7

    International Nuclear Information System (INIS)

    1978-01-01

    Following a brief historical introduction the concept of proliferation, vertical horizontal and subnational, is presented, and its relationship to nuclear power discussed. The risk of nuclear weapon proliferation, based on political decision, motivation and costs, is related to access to enriched uranium, plutonium and uranium 233. The possibilities for diversion and theft from nuclear facilities are discussed. International measures to prevent proliferation, the Non-Proliferation Treaty (NPT)and the IAEA safeguards system, are described and discussed. Measures which may be enacted against countries which break the NPT are discussed. Restrictions on international nuclear trude, both multilateral and unilateral, are also discussed, especially those at present, or shortly to be, enforced by USA, Canada and Australia. The International Nuclear Feel Cycle Evaluation (INFCE) is briefly presented. The physical protection of nuclear materials is also discussed. Finally the basc principles of nuclear weapons are briefly presented. (JIW)

  1. Nuclear power and atomic weapons. Chapter 7

    International Nuclear Information System (INIS)

    1978-01-01

    Following a brief historical introduction the concept of proliferation, vertical and horizontal and subnational, is presented, and its relationship to nuclear power discussed. The risk of nuclear weapon proliferation, based on political decision motivation and costs, is related to access to enriched uranium, plutonium and uranium 233. The possibilities for diversion and theft from nuclear facilities are discussed. International measures to prevent proliferation, the Non-Proliferation Treaty (NPT) and the IAEA safeguards system, are described and discussed. Measures which may be enacted against countries which break the NPT are discussed. Restrictions on international nuclear trade, both multilateral and unilateral, are also discussed, especially those at present, or shortly to be, enforced by USA, Canada and Australia. The International Nuclear Fuel Cycle Evaluation (INFCE) is briefly presented. The physical protection of nuclear materials is also discussed. Finally the basic principles of nuclear weapons are briefly presented. (JIW)

  2. Are atomic power plants saver than nuclear power plants

    International Nuclear Information System (INIS)

    Roeglin, H.C.

    1977-01-01

    It is rather impossible to establish nuclear power plants against the resistance of the population. To prevail over this resistance, a clarification of the citizens-initiatives motives which led to it will be necessary. This is to say: It is quite impossible for our population to understand what really heappens in nuclear power plants. They cannot identify themselves with nuclear power plants and thus feel very uncomfortable. As the total population feels the same way it is prepared for solidarity with the citizens-initiatives even if they believe in the necessity of nuclear power plants. Only an information-policy making transparent the social-psychological reasons of the population for being against nuclear power plants could be able to prevail over the resistance. More information about the technical procedures is not sufficient at all. (orig.) [de

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

    International Nuclear Information System (INIS)

    Gozhenko, S.V.

    2007-01-01

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

  4. Annual report 2007 - CPFL Energy - Light and Power Company from Sao Paulo, SP, Brazil

    International Nuclear Information System (INIS)

    2008-01-01

    This document presents the balance of the economic, social, environmental performance of the Sao Paulo Light and Power Company (CPFL), during the year of 2007 as follows: highlights of 2007; profile of the CPFL Energy group; corporative performance; strategy of the company; performance in 2007 (the best year of the company); social responsibility

  5. Kemeny commission report. Comments by NPC (Nuclear Power Company)

    Energy Technology Data Exchange (ETDEWEB)

    1979-01-01

    Following the accident at Three Mile island in March 1979 the Nuclear Power Company (NPC) has made evaluations of the available information and carried out preliminary investigations of the implications of the accident for all UK AGR's and for the PWR design. The results are summarized. Recommendations of the President's Commission are discussed with especial reference to those under the following headings: (1) The utility and its suppliers. (2) Training of operating personnel. (3) Technical assessment. It is concluded that while many of the relevant recommendations in the report of the President's Commission are already satisfied by UK practices for nuclear safety, and are being applied by NPC in their current programmes of work on AGR's and PWR's it is realised that it is of the utmost importance that complacent attitudes to safety are not allowed to develop. The accident at TMI and report of the Commision have provided a sharp reminder of the necessity to maintain unremitting vigilance in all aspects of design, construction and operation which are involved with the safety of the public and operators.

  6. Internal structure of reactor building for Madras Atomic Power Project

    International Nuclear Information System (INIS)

    Pandit, D.P.

    1975-01-01

    The structural configuration and analysis of structural elements of the internal structure of reactor building for the Madras Atomic Power Project has been presented. Two methods of analysis of the internal structure, viz. Equivalent Plane Frame and Finite Element Method, are explained and compared with the use of bending moments obtained. (author)

  7. High Precision Current Control for the LHC Main Power Converters

    CERN Document Server

    Thiesen, H; Hudson, G; King, Q; Montabonnet, V; Nisbet, D; Page, S

    2010-01-01

    Since restarting at the end of 2009, the LHC has reached a new energy record in March 2010 with the two 3.5 TeV beams. To achieve the performance required for the good functioning of the accelerator, the currents in the main circuits (Main Bends and Main Quadrupoles) must be controlled with a higher precision than ever previously requested for a particle accelerator at CERN: a few parts per million (ppm) of nominal current. This paper describes the different challenges that were overcome to achieve the required precision for the current control of the main circuits. Precision tests performed during the hardware commissioning of the LHC illustrate this paper.

  8. 77 FR 108 - Lockhart Power Company, Inc.; Notice Soliciting Scoping Comments

    Science.gov (United States)

    2012-01-03

    ... affect any federal lands. g. Filed Pursuant to: Federal Power Act 16 U.S.C. 791 (a)-825(r). h. Applicant Contacts: Bryan D. Stone, Chief Operating Officer, Lockhart Power Company, Inc., 420 River Street, P.O. Box...

  9. Local election: does bureaucracy become one of main political power?

    Science.gov (United States)

    Amin, Muryanto; Musthafa Sembiring, Walid

    2018-03-01

    This writing aims to analyze the emergence of bureaucracy as one of political power in local level after the local election is held in Indonesia. Due to information authorization, media network, and stable structure, the bureaucracy soon transforms into political power which can compete with the other political power at the local level. In Medan local election in 2010 and 2015 has evidently proven the power of bureaucracy network in winning the bureaucrat-background candidates. As methods of the research, the researcher held a Focus-Group Discussion (FGD) and had an in-depth interview with ten bureaucracy elites in Medan and local political elites. The observation and Focus-Group Discussion (FGD) are analyzed using qualitative analysis technique typology. The result states that the bureaucracy network in Medan has been used in a massive way as the political power of winning. The structure of bureaucracy – from the top to the low – is involved in the winning. The most governmental programs were applied to attract the mass’ sympathy toward the candidates. The bureaucratic proximity to media network is also used to do a campaign in a massive way. The conclusion of the research is that bureaucracy emerges as a new, massive, effective local political power in the local election.

  10. Power of Companies in Supply Chains and Their Effect on Network Development

    OpenAIRE

    Tamás Brányi; László Józsa

    2015-01-01

    A general supply chain functions as a closed cluster and consists of at least three companies: supplier, producer and buyer. In an optimal case the companies within a supply chain are well integrated, partnership rests on trust which results in common strategic decisions. Business practices show that there is a stronger company within the chain that uses its power position to influence network development. The objective of the research is to measure how and what kind of power position is need...

  11. Increasing power distribution mains efficiency through new mains configurations; Effizienzsteigerung im Verteilnetz durch neue Netzkonfigurationen

    Energy Technology Data Exchange (ETDEWEB)

    Hoeckel, M.

    2005-07-01

    This final report for the Swiss Federal Office of Energy (SFOE) summarises the findings of a study that sought to find new approaches to minimise distribution losses in medium and low voltage power grids. Options examined included the optimisation of distribution-station density, increasing the nominal voltage of the low-voltage grid and the implementation of decentralised energy production. Data from real-life grids were used together with simulations to analyse possible solutions. The conclusions of these analyses are presented and discussed. In addition, qualitative and detailed examinations were made concerning grid quality factors such as availability and voltage stability.

  12. 75 FR 52523 - Bowersock Mills and Power Company; Notice of Availability of Environmental Assessment

    Science.gov (United States)

    2010-08-26

    ... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Project No. 13526-002-KS] Bowersock Mills and Power Company; Notice of Availability of Environmental Assessment August 19, 2010. In... reviewed the application for an original license for the Bowersock Mills and Power Company's Expanded...

  13. 75 FR 21286 - Bowersock Mills and Power Company; Notice of Application Accepted for Filing, Soliciting Motions...

    Science.gov (United States)

    2010-04-23

    ... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Project No. 13526-002] Bowersock Mills... License. b. Project No.: 13526-002. c. Date Filed: February 8, 2010. d. Applicant: Bowersock Mills Power Company (Bowersock). e. Name of Project: Bowersock Mills and Power Company Expanded Kansas River...

  14. 75 FR 22772 - Cargill Power Markets, LLC, Complainant v. Public Service Company of New Mexico, Respondent...

    Science.gov (United States)

    2010-04-30

    ... Markets, LLC, Complainant v. Public Service Company of New Mexico, Respondent; Notice of Complaint April... of the Federal Power Act (FPA), 16 U.S.C. 824e (2006), Cargill Power Markets, LLC (Complainant) filed a formal complaint against Public Service Company of New Mexico (Respondent) alleging that...

  15. 75 FR 44224 - Grant of Authority for Subzone Status; Yankee Candle Corporation (Candles and Gift Sets); Whately...

    Science.gov (United States)

    2010-07-28

    ... Status; Yankee Candle Corporation (Candles and Gift Sets); Whately and South Deerfield, MA Pursuant to... special-purpose subzone at the candle and gift set manufacturing and distribution facilities of Yankee... activity related to the manufacturing and distribution of candles and gift sets at the facilities of Yankee...

  16. Atomic power engineering as military and nuclear deterrence

    International Nuclear Information System (INIS)

    Koryakin, Yu.I.

    2000-01-01

    The legislative aspects of the nuclear power facilities protection during military actions are discussed. The IAEA position on this question is considered. Absence in the IAEA subject scope of the works on preparation of the treaty on prohibiting the destruction of nuclear power facilities means that the IAEA countries differently understand the necessity for introducing the legislative positions of the international atomic law. However, observation of the unwritten codex of mutual nuclear deterrence gives rise to the hope for the wise solution of the problem on the nuclear power objects protection during the military actions [ru

  17. Physical reason for quantum behaviour of the electron and stability of the main state of the hydrogen atom

    International Nuclear Information System (INIS)

    Rangelov, J.M.

    1986-01-01

    An electron model is proposed explaining the physical reasons for its nonrelativistic quantum-mechanical behaviour, the origin of its own mechanical and magnetic momentum and field energy. As an example the main electron state in hydrogen atom is obtained

  18. Taiwan Power Company's power distribution analysis and fuel thermal margin verification methods for pressurized water reactors

    International Nuclear Information System (INIS)

    Huang, P.H.

    1995-01-01

    Taiwan Power Company's (TPC's) power distribution analysis and fuel thermal margin verification methods for pressurized water reactors (PWRs) are examined. The TPC and the Institute of Nuclear Energy Research started a joint 5-yr project in 1989 to establish independent capabilities to perform reload design and transient analysis utilizing state-of-the-art computer programs. As part of the effort, these methods were developed to allow TPC to independently perform verifications of the local power density and departure from nucleate boiling design bases, which are required by the reload safety evaluation for the Maanshan PWR plant. The computer codes utilized were extensively validated for the intended applications. Sample calculations were performed for up to six reload cycles of the Maanshan plant, and the results were found to be quite consistent with the vendor's calculational results

  19. Taming the atom: facing the future with nuclear power

    International Nuclear Information System (INIS)

    Blair, I.M.

    1983-01-01

    The subject is discussed under the headings: the mythology of the atom; what is nuclear power (the atom and its nucleus; radioactivity; nuclear fission; breeding nuclear fuel; how a reactor works; the natural reactor at Oklo; the fast reactor; nuclear fusion); the nuclear industry in profile (uranium mining; isotope enrichment; reactor fuel fabrication; types of reactor; decommissioning redundant stations; transport of spent nuclear fuel; reprocessing the spent fuel; management of waste products); nuclear power in the energy scene (energy in man's development; the impending crisis; the need for energy conservation; the role of nuclear power; status of the fast reactor programme; atoms by wire; other possible sources; the question of economics; the next few decades); matters of public concern (biological effects of radiation; probability and consequences of accidents; worries about waste disposal; no free lunches; the technological imperative; the centralisation of power; fears about terrorism; threats to civil liberties; proliferation of nuclear weapons); the great nuclear debate (depth of public concern; lack of public knowledge; differing national techniques; put it somewhere else; a question of credibility). (U.K.)

  20. Stainless steel pool constructing technology and management of Fangjiashan Nuclear Power Company

    International Nuclear Information System (INIS)

    Wei Lianfeng; Wang Qun

    2013-01-01

    The construction of Fangjiashan nuclear power plant stainless steel cladding has been taken much attention. Based on the careful analysis of stainless steel cladding welding and construction main issues; Many measures have been taken such as welding technology, construction process, the stress control of welding deformation, the cleanliness control of construction process, install precision control, improvements of Non-destructive testing, product protection, etc. And installation methods and techniques have been improved and innovative, the installation quality of stainless steel cladding has been enhanced. At the same time, as owners of the plants, we explored the methods of quality supervision and control, together with the relevant units; and sense of quality management has been unified effectively, made stainless steel cladding quality getting better and better. Fangjiashan nuclear power stainless steel cladding construction quality and management experience has been highly recognized by every company. (authors)

  1. Activities of the EMAG Mine Automation Company in development of control systems for powered supports

    Energy Technology Data Exchange (ETDEWEB)

    Sikora, W; Sobczyk, J

    1986-10-01

    Research programs are evaluated of the EMAG Mine Automation Company on electrohydraulic control systems and remote control for powered supports manufactured in Poland. A control system for the FAZOS-12/28-Oz and FAZOS-15/31-Oz supports is characterized by: reduced length of hydraulic pipes (by 1/3), increased reliability, increased number of commands, less complicated design and lower maintenance and repair cost. A scheme of the system and its main elements (electrohydraulic executive units, control panels and their position, power supply system, and electric cables) is given. After operational tests in the Murcki mine, EMAG will start manufacturing the systems on a commercial scale (about 35 units per year). The research program for development of a remote control system for the 1990s is characterized (computerized control, microprocessors complementary MOS units, etc.).

  2. Inquiry relating to modification of reactor installation of Hamaoka No. 2 nuclear power plant of Chubu Electric Power Company, Inc

    International Nuclear Information System (INIS)

    1979-01-01

    Application was made to the Minister of International Trade and Industry for the license relating to the modification of reactor installation of the Hamaoka No. 2 nuclear power plant, Chubu Electric Power Company, Inc., on February 8, 1979, from the president of the company. After the safety evaluation in the Ministry of International Trade and Industry was finished, inquiry was conducted to the head of the Atomic Energy Safety Commission (AESC) on May 25, 1979, from the Minister of International Trade and Industry. The investigation and discussion were commenced by the AESC on May 28, 1979. The modification of the reactor installation is the increase of spent fuel storage capacity from about 220% of in-core fuel at present to about 325%. The fundamental philosophy of the safety evaluation includes the following items; 1) the storage capacity of spent fuel is adequate, 2) the design is such that the criticality is prevented under any assumed condition, 3) the sufficient cooling capacity is kept for decay heat removal, 4) and others required for the safety. The contents of the safety examination for each philosophical item written above are presented. The increased spent fuel storage capacity is equivalent to the quantity produced in about eight years. The prevention of criticality in the spent fuel storage is carefully practiced by putting fuel assemblies in the stainless steel racks with large neutron absorption cross section and locating spent fuel assemblies at the proper distances. The effective multiplication factor is less than 0.95 at the most severe arrangement in the fuel pool. The water temperature in the pool is less than 65 deg C at about 325% core storage by operating the spent fuel pool water cooling system. The spent fuel storage racks are designed as the A class aseismatic structure. (Nakai, Y.)

  3. Main Characteristics of Nuclear Power Plants in the European Union and Candidate Countries

    International Nuclear Information System (INIS)

    Lillington, J.N.; Turland, B.D.; Haste, T.J.; Seiler, J.M.; Tapia, J.; Carretero, A.; Perez, T.; Geutges, A.; Sehgal, B.R.; Mattila, L.; Holmstrom, H.; Karwat, H.; Maroti, L.; Husarcek, J.

    2001-10-01

    The main objective was to advise the EC on future challenges and opportunities in terms of enhanced co-operation in the area of nuclear safety and harmonization of safety requirements and practices in an enlarged European Union Part of this activity was to provide a summary of the plant characteristics of the operating civil nuclear power plants in the EU Member and Candidate Countries. The present report provides these data in three formats: A reference table which lists the main characteristics of nuclear power-producing reactors operating in the European Union (EU) and Candidate Countries, as at 31 December 1999. Also included, for the sake of completeness, are data for reactors in the former Soviet Union, such as Russia and the Ukraine. The format adopted follows that in the annual International Atomic Energy Agency (IAEA) reference data report ''Nuclear Power Reactors of the World'', from which much of the information was taken; A summary table indicating totals by reactor type covering Western and Eastern Europe separately, again from IAEA sources, giving number of plant, total generating capacity and total years in operation. A list of the abbreviations for different reactor types is also provided; A set of detailed data sheets giving main plant characteristics for different reactor types ordered by country. These data sheets cover reactors in EU Member and Candidate Countries only. Details are provided on the origin of the data where these are available, so that further information may be obtained if desired and where permitted by commercial and/or proprietary considerations. (author)

  4. MAIN CHARACTERISTICS OF COMPANIES USING SERVICE ORIENTED ARCHITECTURE (SOA AND OF THEIR OPERATION CONTEXT

    Directory of Open Access Journals (Sweden)

    Alfonso Duran Heras

    2008-12-01

    Full Text Available The aim of this article is to establish the main characteristics of the organizations that have successfully implemented information systems based on Service Oriented Architecture (SOA. Their environmental circumstances have also been studied. To achieve this objective, a SOA bibliographic review has been carried out, encompassing an analysis of 25 real cases in which different SOA applications were successfully implemented. All these cases were published between 2.001 and 2.007. The conclusions of this article can be briefly summarized as follows: SOA is well suited for organizations that rely on important legacy systems, whose performance is hindered by the lack of integration and flexibility of their computer architectures. These organizations therefore need to improve such architectures rather than replace them by new systems; SOA is being used by organizations that need to integrate their systems with those of their supply chain partners; SOA solutions provide support for the use of Web technologies.

  5. Transient behaviour of main coolant pump in nuclear power plants

    International Nuclear Information System (INIS)

    Delja, A.

    1986-01-01

    A basic concept of PWR reactor coolant pump thermo-hydraulic modelling in transient and accident operational condition is presented. The reactor coolant pump is a component of the nuclear steam supply system which forces the coolant through the reactor and steam generator, maintaining design heat transfer condition. The pump operating conditions have strong influence on the flow and thermal behaviour of NSSS, both in the stationary and nonstationary conditions. A mathematical model of the reactor coolant pump is formed by using dimensionless homologous relations in the four-quadrant regimes: normal pump, turbine, dissipation and reversed flow. Since in some operational regimes flow of mixture, liquid and steam may occur, the model has additional correction members for two-phase homologous relations. Modular concept has been used in developing computer program. The verification is performed on the simulation loss of offsite power transient and obtained results are presented. (author)

  6. Survey on the trends of atomic power development and utilization in 1973 fiscal year

    International Nuclear Information System (INIS)

    1975-01-01

    Japanese activities in the atomic power development and utilization during 1973 (FY) were investigated and compared with the previous year. The investigation was done for each type of organization; medical, educational, research institute, private company, and others. The results of the investigation can be summarized as follows. The total number of personnel being engaged in the field of atomic industry increased by 1.2%. About 52.8% of them belong to private companies. The number of trainees during 1973 increased by 7.9%. About 92.3% of them were trained in domestic organizations. The expenditure for research and development was 100 billion yen which is 12.1% larger than that in the previous year. About 73.4% was used by public research institutes including JAERI and PNC. Investment in equipments was 235.2 billion yen which was increase of 20%. Most of this money (215.4 billion yen) was invested for the construction of power plants by electric utilities. Total amount of production was 73 billion yen which was increase of 45.9%. (Aoki, K.)

  7. Owners of nuclear power plants: Percentage ownership of commercial nuclear power plants by utility companies

    International Nuclear Information System (INIS)

    Wood, R.S.

    1987-08-01

    The following list indicates percentage ownership of commercial nuclear power plants by utility companies as of June 1, 1987. The list includes all plants licensed to operate, under construction, docked for NRC safety and environmental reviews, or under NRC antitrust review. It does not include those plants announced but not yet under review or those plants formally canceled. In many cases, ownership may be in the process of changing as a result of altered financial conditions, changed power needs, and other reasons. However, this list reflects only those ownership percentages of which the NRC has been formally notified. Part I lists plants alphabetically with their associated applicants/licensees and percentage ownership. Part II lists applicants/licensees alphabetically with their associated plants and percentage ownership. Part I also indicates which plants have received operating licenses (OL's). Footnotes for both parts appear at the end of this document

  8. 78 FR 32385 - Exelon Generation Company, LLC; CER Generation II, LLC; Constellation Mystic Power, LLC...

    Science.gov (United States)

    2013-05-30

    ... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Docket No. EL13-64-000] Exelon Generation Company, LLC; CER Generation II, LLC; Constellation Mystic Power, LLC; Constellation NewEnergy...) Rules of Practice and Procedure, 18 CFR 385.207, Exelon Generation Company, LLC, CER Generation II, LLC...

  9. 77 FR 77073 - York Haven Power Company, LLC; Notice of Meeting

    Science.gov (United States)

    2012-12-31

    ... Company, LLC; Notice of Meeting On Wednesday, January 9, 2013, Commission staff will meet with York Haven Power Company, LLC (applicant) in Washington, DC. The purpose of the meeting is to discuss the required... begin at 10 a.m. at the Federal Energy Regulatory Commission headquarters building located at 888 First...

  10. The new generation of nuclear power stations. A new trend in atomic power?

    International Nuclear Information System (INIS)

    Hohlefelder, W.

    2006-01-01

    According to the author, all options for future power supply should be followed, including atomic power provided that it can be made technically safe and treated with a maximum safety culture. On the one hand, power supply is an elementary human need, deciding on public welfare, economic development and technical progress. On the other hand, there is an impending shortage of power owing to depletion of resources and the emergence of new industrialized nations especially in south east Asia. For this reason, all options should be considered, from renewable energy sources to coal and nuclear power. (orig.)

  11. 77 FR 38796 - Alabama Power Company; Holt Hydroelectric Project; Notice of Revised Restricted Service List for...

    Science.gov (United States)

    2012-06-29

    ... Power Company; Holt Hydroelectric Project; Notice of Revised Restricted Service List for a Programmatic... Hydroelectric Project No. 2203. The programmatic agreement, when executed by the Commission, the Alabama SHPO...

  12. 77 FR 42715 - Lockhart Power Company, Inc.; Notice of Application Ready for Environmental Analysis and...

    Science.gov (United States)

    2012-07-20

    ...(r). h. Applicant Contact: Bryan D. Stone, Chief Operating Officer, Lockhart Power Company, Inc., 420... paper-filed. To paper-file, mail an original and seven copies to: Kimberly D. Bose, Secretary, Federal...

  13. 75 FR 11149 - Bowersock Mills and Power Company; Notice of Application Tendered for Filing With the Commission...

    Science.gov (United States)

    2010-03-10

    ... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Project No. 13526-001] Bowersock Mills...: Bowersock Mills Power Company (Bowersock). e. Name of Project: Bowersock Mills and Power Company Expanded....S.C. 791(a)-825(r). h. Applicant Contact: Sarah Hill-Nelson, The Bowersock Mills and Power Company...

  14. Future challenges for the management of power supply companies; Zukuenftige Herausforderungen fuer das Management von EVU

    Energy Technology Data Exchange (ETDEWEB)

    Bausch, A. [Jena Univ. (Germany). Professur fuer Allgemeine Betriebswirtschaftslehre/Internationales Management; Jacobs Univ., Bremen (Germany). Professur fuer Strategisches Management und Controlling; Werthschulte, S.; Schumacher, T. [Accenture GmbH (Germany); Holst, A. [Jena Univ. (Germany). Professur fuer Allgemeine Betriebswirtschaftslehre/Internationales Management; Fritz, T. [Jacobs Univ., Bremen (Germany). Professur fuer Strategisches Management und Controlling

    2007-06-15

    Among the challenges on power supply companies seeking profitable growth are strategic corporate development in terms of product and process innovation and the management's and employees' capacity for change. This was the outcome of a survey conducted as part of the ''Value Creator III'' study performed among 130 executives of German, Austrian and Swiss companies operating in the energy sector. Based on a review of companies' past successes and expectations for the future the study presents business models for tomorrow's energy market and classifies companies within a past-and-future portfolio according to their market prospects.

  15. Environmental studies and clearance compliance of Kudankulam Atomic Power Project

    International Nuclear Information System (INIS)

    Agarwal, S.K.; Singh, Jitendra

    2002-01-01

    Full text: Nuclear industry has played a leading role in evolving proper and effective environmental management impact from development practices right form inception thus minimizing the environmental impact from developmental activities of man. In the engineering design of nuclear power plant, safety is further enhanced considerably by providing double back-upped engineered safety systems. Besides the engineered safety, the other factors considered for ensuring environmental impact minimization are siting criteria, conservative rad-waste management, effluent treatment, application of stringent environmental protection standards for limiting waste discharges, an elaborate environmental surveillance program and an on site and off site emergency preparedness plan. Recently, nuclear power industry has taken a drive to develop and implement Environmental Management System (EMS) to all its operating stations in line with ISO-14001 standards. For Kudankulam atomic power project, a number of studies specifically for environmental protection are carried out to meet the requirements of Russian Federation, new guidelines of Ministry of environment and Forests (MOEF) and Atomic Energy Regulatory Board (AERB). In the present paper an attempt has been made to present the environmental management plan and clearance compliance status of the project

  16. Beaver Valley Power Station and Shippingport Atomic Power Station. 1984 Annual environmental report, radiological. Volume 2

    International Nuclear Information System (INIS)

    1985-01-01

    This report describes the Radiological Environmental Monitoring Program conducted during 1984 in the vicinity of the Beaver Valley Power Station and the Shippingport Atomic Power Station. The Radiological Environmental Program consists of on-site sampling of water and gaseous effluents and off-site monitoring of water, air, river sediments, soils, food pathway samples, and radiation levels in the vicinity of the site. This report discusses the results of this monitoring during 1984. The environmental program outlined in the Beaver Valley Power Station Technical Specifications was followed throughout 1984. The results of this environmental monitoring program show that Shippingport Atomic Power Station and Beaver Valley Power Station operations have not adversely affected the surrounding environment. 23 figs., 18 tabs

  17. Hydroelectric power plants may influence profit of company

    International Nuclear Information System (INIS)

    Regula, E.

    2006-01-01

    In this interview with divisional manager of the Division of control of operation of hydroelectric power plants of the Slovenske elektrarne, a.s. Mr. Milan Chudy is published. The effectiveness and its optimisation in hydroelectric power plants of the Slovenske elektrarne, a.s. are discussed

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

    International Nuclear Information System (INIS)

    Tawara, Shigesuke

    1979-01-01

    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.)

  19. Development on power distribution technologies of four electric power companies in Japan. The Tokyo Electric Power Co. , Inc

    Energy Technology Data Exchange (ETDEWEB)

    1989-07-01

    Electric power companies have been needed to cope with various needs in accordance with the progress of highly information-oriented society, the improvement of industrial technology, and the advancement and diversification of the living environment. In such situation, the power distribution section of Tokyo Electric Power has promoted technical development, setting up following priority items to put into operation: to reduce power failure caused by works and accidents, to improve reliability in supply, to reduce costs of construction and all over business management, to serve customers to answer various needs, to develop new technology and new methods based on the medium- and long-term prospect, and so forth. Several examples of recent technical development are introduced here. They are as follows; compact equipment and materials for electric poles to match the circumstances of cities and to simplify the construction method for power distribution, a 750kVA large high-voltage power-generation truck to make provision against an emergency such as a disaster by a typhoon, a compact transformer used on the ground, a high-voltage automatic cabinet, and a detector to find the failure of indoor power distribution works in resistances in a short time. 8 figs.

  20. Metal cluster compounds - chemistry and importance; clusters containing isolated main group element atoms, large metal cluster compounds, cluster fluxionality

    International Nuclear Information System (INIS)

    Walther, B.

    1988-01-01

    This part of the review on metal cluster compounds deals with clusters containing isolated main group element atoms, with high nuclearity clusters and metal cluster fluxionality. It will be obvious that main group element atoms strongly influence the geometry, stability and reactivity of the clusters. High nuclearity clusters are of interest in there own due to the diversity of the structures adopted, but their intermediate position between molecules and the metallic state makes them a fascinating research object too. These both sites of the metal cluster chemistry as well as the frequently observed ligand and core fluxionality are related to the cluster metal and surface analogy. (author)

  1. Role of Dividend of Power to Buy Shares in Companies in Indonesia Stock Exchange

    Directory of Open Access Journals (Sweden)

    Iskandar Muda

    2017-06-01

    Full Text Available This study aims to determine the role of the Purchasing Power Shares on manufacturing companies in Indonesia Stock Exchange Period 2014-2015. The variables used in this study as an Independent Variable Dividend and Purchasing Power Shares as Dependent Variables. Power Buy Stocks in this study was measured by the volume of stock sales every year. This research was conducted in Manufacturing company listed on the Indonesia Stock Exchange. The population of this study were 144 companies with purposive sampling as many as 19 of the Company's Manufacturing Company listed on the Indonesia Stock Exchange with the study of the 2014-2015 period in order to obtain 38 units of analysis. Data of this research are secondary data from the financial statements of 19 companies published in the Indonesia Stock Exchange. This research data processing method using the Test Statistics Deskribtif, Classical Assumption Test, Test Linear Regression using SPSS. The results of this study demonstrate that the role of the Dividend has significant influence on the Purchasing Power Shares in Manufacturing Company in Indonesia Stock Exchange (BEI.

  2. Shippingport Atomic Power Station decommissioning program and applied technology

    Energy Technology Data Exchange (ETDEWEB)

    Crimi, F P; Skavdahl, R E

    1985-01-01

    The Shippingport Station decommissioning project is the first decommissioning of a large scale nuclear power plant, and also the first nuclear power plant to be decommissioned which has continued the power operation as long as 25 years. The nuclear facilities which have been decommissioned so far have operated for shorter period and were small as compared with commercial power reactors, but the experience gained by those decommissionings as well as that gained by nuclear plant maintenance and modification has helped to establish the technology and cost basis for Shippingport and future decommissioning projects. In this paper, the current status of the preparation being made by the General Electric Co., its subcontractor and the US Department of Energy for starting the decommissioning phase of the Shippingport Atomic Power Station is described. Also remote metal cutting, decontamination, concrete removal, the volume reduction of liquids and solids and robotics which will be applied to the project are discussed. The Shippingport Station is a 72 MWe PWR plant having started operation in 1957, and permanently shut down in 1982, after having generated over 7.4 billion kWh of electricity.

  3. The Gyllingnaes investigation - a survey of altitudes in the Gylling postal area towards atomic power

    International Nuclear Information System (INIS)

    Boldsen, N.; Buelow, W.

    1977-01-01

    An investigation of the altitudes of the local population towards the possible construction of an atomic power station at Gyllingnaes in Denmark. It is primarily based on questionnaries, secondarily on interviews. To put the results in better perspective, similar investigations from 1974-1976 are also dealt with. It is concluded that the majority of the population are against atomic power; not only do they oppose the erection of an atomic power station at Gyllingnaes but they oppose the building of atomic power stations in general. An attempt is made to characterize the ''typical'' opponent and the ''typical'' supporter of atomic power. (B.P.)

  4. European coal technology applied by the Danish power companies

    Energy Technology Data Exchange (ETDEWEB)

    Frydenberg, B. [Elsamprojekt A/S, Fredericia (Denmark)

    1996-12-31

    The development of coal-fired power plants has shown remarkable improvements with regard to efficiency and cleaner technology, and as coal remains the most important fuel for electric power production, it is important to make use of this technological development to reduce CO{sub 2} emissions. Of the three available technologies: Integrated Coal Gasification and Combined Cycle, Fluid Bed Combustion and Pulverised Coal with Ultra Supercritical Steam Data, the technology chosen by I/S ELSAM is the PC-USC with power production efficiencies growing from 45% to 50%. 5 figs., 1 tab.

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

    Energy Technology Data Exchange (ETDEWEB)

    1980-01-01

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

  6. Radioactive waste management at Narora atomic power station in India

    International Nuclear Information System (INIS)

    Prasad, P.N.; Gupta, J.P.; Mittal, S.

    2001-01-01

    Modern society creates waste material, which have to be disposed of in nature without disturbing the ecological equilibrium. Hence effective waste management in all industries is a major concern today. Narora Atomic Power Station (NAPS) generates low and intermediate level liquid, solid and gaseous wastes during its operation and maintenance. The generation of wastes is controlled at the source itself. The wastes are managed by adequate and appropriate treatment before being released into the environment. Different types of liquid wastes are treated by chemical co-precipitation, ion exchange, evaporation, filtration, and dilution techniques. For handling and conditioning of solid wastes, volume reduction techniques such as incineration and baling are employed. The treated wastes are immobilised by incorporation into cement and polymer matrices. Gaseous waste is cleaned by passing through pre-filters and high efficiency particulate (HEPA) filters and diluted with inactive air prior to release to the atmosphere through a 145 m high stack to get further atmospheric dilution. Regular monitoring up to 30 km radius is carried out by fully equipped Environmental Survey and Micrometeorological Laboratory which functions independently under the Directorate of Health and Safety, Bhabha Atomic Research Centre (BARC), Mumbai. So far, the annual maximum dose to the public around NAPS is reported to be 0.2 to 0.3% of limit of 1 mSv/year recommended by the International Commission on Radiological Protection (ICRP). A decade of experience has proved that present practices of nuclear waste management at Narora Atomic Power Station are quite safe and effective with respect to ecological equilibrium. (author)

  7. Quality assurance system in electric power companies in Japan, (2)

    International Nuclear Information System (INIS)

    Hamaguchi, Shun-ichi

    1980-01-01

    The organization for the quality assurance in nuclear power plants of Kansai Electric Power Co., Inc. is introduced. It is still in investigation stage what quality assurance (QA) organization and system is the best. The QA investigation project team was organized in the form directly supervised by the Office of President. The purpose of QA in operation is to maintain the functions of power plants in good condition over the lifetime of the power plants after starting the operation, and the QA is divided into the following five items: (1) running operation, (2) check-up and maintenance, (3) in-service testing and inspection, (4) regular inspection, (5) general application control. The purposes and works to be implemented for these items are listed in a table, and explained in detail. The quality control in regular inspection is described about 4 stages is purchase order and contract, design, construction, and adjusting operation. Also further improvement of QA in operating nuclear power plants by implementing the next items has been decided to make the most of the teachings in the accident of Three Mile Island plant. (1) Reinforcement of operation management system, (2) completion of the training for operators, (3) clarification of the command system for operational control, and (4) change of installations and review of application. As seen in the above description, the important tasks in QA activities are the matching to the existing installations and the adjustment of interfaces with the equipments in operation. (Wakatsuki, Y.)

  8. Program change management during nuclear power plant decommissioning

    International Nuclear Information System (INIS)

    Bushart, Sean; Kim, Karen; Naughton, Michael

    2011-01-01

    Decommissioning a nuclear power plant is a complex project. The project involves the coordination of several different departments and the management of changing plant conditions, programs, and regulations. As certain project Milestones are met, the evolution of such plant programs and regulations can help optimize project execution and cost. This paper will provide information about these Milestones and the plant departments and programs that change throughout a decommissioning project. The initial challenge in the decommissioning of a nuclear plant is the development of a definitive plan for such a complex project. EPRI has published several reports related to decommissioning planning. These earlier reports provided general guidance in formulating a Decommissioning Plan. This Change Management paper will draw from the experience gained in the last decade in decommissioning of nuclear plants. The paper discusses decommissioning in terms of a sequence of major Milestones. The plant programs, associated plans and actions, and staffing are discussed based upon experiences from the following power reactor facilities: Maine Yankee Atomic Power Plant, Yankee Nuclear Power Station, and the Haddam Neck Plant. Significant lessons learned from other sites are also discussed as appropriate. Planning is a crucial ingredient of successful decommissioning projects. The development of a definitive Decommissioning Plan can result in considerable project savings. The decommissioning plants in the U.S. have planned and executed their projects using different strategies based on their unique plant circumstances. However, experience has shown that similar project milestones and actions applied through all of these projects. This allows each plant to learn from the experiences of the preceding projects. As the plant transitions from an operating plant through decommissioning, the reduction and termination of defunct programs and regulations can help optimize all facets of

  9. Important consequences of atomic diffusion inside main-sequence stars: opacities, extra-mixing, oscillations

    Directory of Open Access Journals (Sweden)

    Deal M.

    2017-01-01

    Full Text Available Atomic diffusion, including the effects of radiative accelerations on individual elements, leads to important variations of the chemical composition inside stars. The accumulation of important elements in specific layers leads to a local increase of the average opacity and to hydrodynamic instabilities that modify the internal stellar structure. This can also have important consequences for asteroseismology.

  10. Inevitability of atomic energy in India's power programme

    International Nuclear Information System (INIS)

    Ramanna, R.

    1977-01-01

    The case for atomic energy as the inevitable answer to the energy problem of India has been emphatically put up and supported with data. Hydroelectric power is costly to develop and moreover its potential is not enough to meet India's growing energy requirements. On the grounds of economics and safety, nuclear power has been shown to be superior to power from coal-based power plants. India's proved reserves of coal are 21 billion tonnes out of which 80% has ash content more than 20% and in order to reach only half of the present per capita energy consumption in Europe, the present output of 90 million tonnes/year of coal will have to be increased by a factor of 10, which in addition raises the problem of its transportation to the plant sites. Secondly, total energy from the available coal is estimated at 160 x 10 12 kwh, while that from known reserves of 52,000 tonnes of uranium is 7.2 x 10 12 kwh if used in thermal reactors and 208 x 10 12 kwh if used in fast reactors. Thorium with its known reserves of 320,000 tonnes would give another 1280 x 10 12 kwh. As for safety and ecology, it has been pointed out that : (1) in U.S., the number of coal miners dying of black cancer is 1000 per 10 12 kwh of electricity generated, whereas the fatality rate of uranium miners due to lung cancer is 20 per 10 12 kwh of electricity generated and (2) safety has been the primary concern in all aspects of nuclear technology - mining, fuel production, reactor operation and radioactive waste processing. It has also been explained how the fear of any terrorist getting possession of plutonium for spreading it into atmosphere or making a nuclear bomb is highly improbable, because at any point throughout the fuel cycle plutonium is under strict security surveillance and it is impossible to make a nuclear device without the back-up of powerful laboratory facilities. Finally, India's three stage atomic power programme is described in brief. (M.G.B.)

  11. Nitrogen oxide control at power plants of the ENEL company (Italy)

    Energy Technology Data Exchange (ETDEWEB)

    Kotler, V.R. (Vserossiiskii Teplotekhnicheskii Institut (Russian Federation))

    1993-03-01

    Analyzes experiences of the ENEL electricity company in Italy in controlling pollutant emission from fossil-fuel power plants. In 1990, the company produced 87% of the country's electricity. Until the year 2000, ENEL plans to increase coal use for power generation by 23.5% and install 9,300 MW of new coal-fired power plant capacity. New European and Italian emission standards require ENEL to reduce NO[sub x] emissions by 30% from 1986 to 1998. NO[sub x] emission values from various fuel-oil and pulverized-coal fired steam generators operated by the company are given. Modifications to existing combustion technologies and equipment installed to lower NO[sub x] content in flue gases at various ENEL power plants are considered. The most promising coal combustion technologies and ongoing research programs are pointed out. 4 refs.

  12. An overview of training and technical communication of Chinese representative nuclear power engineering company of EPC mode

    International Nuclear Information System (INIS)

    Qi Ting; Zhang Xiangyu

    2015-01-01

    After the Fukushima severe accident, nuclear power development has been in stagnation in all over the world. The Chinese nuclear industry has a slowdown on new NPP construction. As a result, high level technique on safety and effective communication are required. For nuclear power engineering company with EPC mode, high quality on training and technical communication is the principal investment in order to achieve better service on engineering design, environmental impact assessment, environmental engineering design, and equipment supervision and so on. EPC mode requires wide range knowledge on almost every field related to nuclear on nuclear power engineering. In this paper, the author investigated the case of the only nuclear power engineering EPC company (CNPE) in China and present an overview on its training and technical communication both domestic and abroad. Basically, there are 4 main branches of training. The internal training focuses on specifically task (both management and technique), such as HSE training, QC training and quality and safety training. Long term education in the university is organized by cooperated mechanism. Code and platform training is partly carried out by international organization or company, and the experienced engineers coach makes up the other part. The communication is a large part since the EPC mode needs the information and requirements from the NPP entity, authority, and the other institutes, international organizations (like IAEA, NINE, IRSN, OECD, NRC and CEA etc.) and sometimes the public. The overview of the training and communication of the EPC company prevails the outline of its advantage on domestic communication and disadvantage on international technical communication. The paper can be a tool on the soft strength construction of company under EPC mode to broaden its business like consultation and training. Some advice is given by the author on the consultation and global communication in the future. (author)

  13. The Japanese power equipment market - potential for foreign companies

    International Nuclear Information System (INIS)

    Bell, G.D.; Matsumoto, Satoru

    1993-01-01

    The potential for foreign companies for sales of heavy electrical equipment in Japan is assessed. The Japanese heavy electrical equipment industry (HEI) has very close links with the electricity supply industry. Traditionally a small circle of domestic manufacturers have supplied all the electric utilities. However, there is criticism in Japan of the inefficiencies which have arisen as a result of the close relationship and the cost competitiveness of domestic products has been eroded by the appreciation of the yen. The chief driving force in the opening of the market to foreign products is political, though. Friction between Japan and the USA and European Community on the subject of trade imbalance, has led the Ministry of Internal Trade and Industry to encourage major utilities to increase their imports from abroad. Consequently, opportunities now exist for foreign suppliers to gain access to the Japanese HEI market but only if they are willing to make a long term investment. Market entry is still likely to be very difficult, however, and unlikely to produce quick returns. In the longer term, though, access to the Japanese market could open up even wider opportunities. (UK)

  14. Quality assurance at a German power station company

    International Nuclear Information System (INIS)

    Czychon, K.H.

    1992-01-01

    The Integrated Operational Management System of the Emsland nuclear power station is described, together with its aims and system architecture as well as the structure and modus operandi of the Integrated Operational Management System Manager. The completion of repair work and the processing of modification and maintenance reports are explained as examples. Experience gained in the introduction and use of the system is presented. figs., 6 refs

  15. The main pump motor remote visual check in the application of the domestic nuclear power plants

    International Nuclear Information System (INIS)

    Ge Lianwei; Yu Tao; Fang Jiang; Zhang Ting; Zhang Xingtian; Ding Youyuan

    2014-01-01

    In this paper, the Qinshan nuclear power station the first main pump motor to the successful implementation of remote visual inspection the main pump motor remote visual inspection applications. Qinshan Nuclear Power Plant Units 1 and 2 of the main pump motor inspection results show that the key components of the Qinshan Nuclear Power Plant Units 1 and 2 of the main pump rotor, stator end coils good condition, its problems for 10 years in the motor does not affect the normal use of the motor state disintegration overhaul problems tracking disintegration overhaul in 10 years. (authors)

  16. Operating experience and performance at Narora Atomic Power Station

    International Nuclear Information System (INIS)

    Mittal, Subhash; Gupta, J.P.

    1998-01-01

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

  17. Developing Outbound Logistics in International Power and Automation Technology Company

    OpenAIRE

    Köykkä, Päivikki

    2010-01-01

    ABSTRACT The purpose of this Master’s Thesis was to document and analyse what has been done in the outbound logistics development project that has not been finished yet and to define actions for completing the project. Another objective was to plan what could be done in the future to develop the outbound logistics further. The work was commissioned by ABB. In the theoretical part of the study the main issues were related to developing outbound logistics processes. Also basic concepts ...

  18. Knolls Atomic Power Laboratory environmental monitoring report, calendar year 1999

    Energy Technology Data Exchange (ETDEWEB)

    None

    2000-12-01

    The results of the effluent and environmental monitoring programs at the three Knolls Atomic Power Laboratory (KAPL) Sites are summarized and assessed in this report. Operations at the three KAPL Sites [Knolls Site, Niskayuna, New York; Kesselring Site, West Milton, New York; S1C Site, Windsor, Connecticut] during calendar year 1999 resulted in no significant release of hazardous substances or radioactivity to the environment. The effluent and environmental monitoring programs conducted by KAPL are designed to determine the effectiveness of treatment and control methods, to provide measurement of the concentrations in effluents for comparison with applicable standards, and to assess resultant concentrations in the environment. The monitoring programs include analyses of samples of liquid and gaseous effluents for chemical constituents and radioactivity as well as monitoring of environmental air, water, sediment, and fish. Radiation measurements are also made around the perimeter of each Site and at off-site background locations.

  19. Condensing and water supplying systems in an atomic power plant

    International Nuclear Information System (INIS)

    Shinmura, Akira.

    1975-01-01

    Object: To reduce heat loss and eliminate accumulation of drain in water supplying and heating units in an atomic power plant by providing a direct contact type drain cooler between a gland-exhauster vapor condenser and a condensing and de-salting means, the drain from each water supplying and heating unit being collected in said cooler for heating the condensed water. Structure: Condensed water from a condenser is fed by a low pressure condensing pump through an air ejector and gland-exhauster vapor condenser to the direct-contact type drain cooler and is condensed in each water supply heater. Next, it is heated by drain fed through a drain level adjuster valve and an orifice and then forced by a medium pressure condenser pump into the condensing and de-salting means. It is then supplied by a high pressure condensing pump into the successive water supply heater. (Kamimura, M.)

  20. Knolls Atomic Power Laboratory environmental monitoring report, calendar year 1999

    International Nuclear Information System (INIS)

    2000-01-01

    The results of the effluent and environmental monitoring programs at the three Knolls Atomic Power Laboratory (KAPL) Sites are summarized and assessed in this report. Operations at the three KAPL Sites [Knolls Site, Niskayuna, New York; Kesselring Site, West Milton, New York; S1C Site, Windsor, Connecticut] during calendar year 1999 resulted in no significant release of hazardous substances or radioactivity to the environment. The effluent and environmental monitoring programs conducted by KAPL are designed to determine the effectiveness of treatment and control methods, to provide measurement of the concentrations in effluents for comparison with applicable standards, and to assess resultant concentrations in the environment. The monitoring programs include analyses of samples of liquid and gaseous effluents for chemical constituents and radioactivity as well as monitoring of environmental air, water, sediment, and fish. Radiation measurements are also made around the perimeter of each Site and at off-site background locations

  1. An FAHP-TOPSIS framework for analysis of the employee productivity in the Serbian electrical power companies

    Directory of Open Access Journals (Sweden)

    Snezana Pavle Knezevic

    2017-09-01

    Full Text Available The aim of this paper is to apply an integrated model, which combines methods of classical and fuzzy Multi-criteria decision making (MCDM in selected six large equity companies from the Serbian energy sector. The data considered are retrieved from the official financial statements. Four main criteria were analyzed, identified by the previous researchers and pointing to the employees productivity: Operating income/Number of employees, Equity/Number of employees, Net income/Number of employees and Total assets/Number of employees. The contribution of this paper lies in the application of a hybrid model that integrates two MCDM methods: Fuzzy Analytic Hierarchy Process (FAHP and Technique for Order Performance by Similarity to Ideal Solution (TOPSIS to analyse the employee productivity in selected D-Electrical power supply companies operating in Serbia. The FAHP is an effective method for mathematical representation of uncertain and imprecise evaluations made by humans, while the TOPSIS method is an efficient way to rank the alternatives. Results show that operating income is of highest importance for estimating employee productivity and decision making, while equity is of the weakest. Furthermore, the most productive operations in large enterprises from selected companies of the sector D-Electrical power supply are found in the company PC EPS Beograd, and the lowest are in the ED Center llc Kragujevac.

  2. Measures associated with the dose limitation system at the TVO Power Company

    International Nuclear Information System (INIS)

    Ruuskanen, A.T.; Sundell, R.O.

    1982-01-01

    The paper discusses radiation protection practices at the TVO Power Company, which owns and operates two BWR units of Asea-Atom design at Olkiluoto, Finland. The installed electric power of each unit is 660MW. The full power operation of TVO I and TVO II began in 1979 and 1980, respectively. The dose limitation system calls for an organization which is responsible for radiation protection. This organization at the plant site is described. To limit doses a good knowledge of the work activities which cause doses is needed. There is a very up-to-date microprocessor-based work dosimetry system at the TVO power plant. The system provides a practicable means of measuring personal doses from various work activities. It also makes the allocation of radiation protection measures possible. The system and experience in applying it are discussed. The dose limitation system presupposes the realization of the optimization principle. The practice applied at TVO in order to limit internal contamination is presented. Owing to this practice, workers' internal doses have remained at a considerably low level. The paper discusses the ALARA values of different kinds of respiratory equipment. These values, which vary from 2x10 4 to 1x10 6 FIM/man.Sv (1 FIM=approx. US$ 0.22), can be used in the evaluation of different measures in avoiding internal doses. The operating policy of movable lead shields is presented. The ALARA value of this activity is evaluated to be about 5x10 4 FIM/man.Sv and on that basis it can be concluded that the use of movable lead shields is very efficient. The dose statistics for TVO's plant are presented. The doses have been less than 0.001 man.Sv/MW.a. Although the dose statistics for TVO are very good it is not realistic to consider solely the optimization aspect of radiation protection. The costs must also be kept in mind; these are presented in the paper. Problems in assessing the level of radiation protection practices on an annual basis are briefly discussed

  3. Stopping powers and ranges for the heaviest atoms

    International Nuclear Information System (INIS)

    Sagaidak, Roman N.; Utyonkov, Vladimir K.; Dmitriev, Sergey N.

    2015-01-01

    Slowing down and stopping of the heaviest atoms, products of the fusion–evaporation nuclear reactions, during their passage through the Dubna gas-filled recoil separator has been studied using TRIM simulations. The study is important for experiments on the synthesis of super-heavy elements (SHEs) with atomic numbers around Z_P = 114 produced with accelerated heavy ion (HI) beams and extracted with a separator for their detection. The average Mylar stopping power (SP) values obtained with the simulations for HIs with 82 ⩽ Z_P ⩽ 92 reveal almost the same magnitudes, allowing extrapolation to the region of Z_P > 92. Similar extrapolation of the ranges in an He + Ar gas mixture leads to rather small values for the heaviest atoms (Z_P ⩾ 102) as compared to the range for U. The extrapolated values have large uncertainties and should be verified with different approaches. Available SP data obtained for HIs with 18 ⩽ Z_P ⩽ 92 at energies E < 20 MeV/u have been analysed within various semi-empirical approaches. The analysis has shown that existing parameterizations give Mylar SP values for Z_P ⩾ 82 that are very different from each other at energies of interest (around 0.1 MeV/u). We propose to use a general approach based on the HI effective charge parameterization obtained with available SP data for HIs and the hydrogen SP and effective charge corresponding to the same velocity and stopping medium as those for HIs. In this manner, the SPs of the gases H_2, He, C_4H_1_0, and Ar as well as those of the solids Mylar, C, Al, and Ti have been obtained for any atoms with Z_P ⩾ 18 (including the heaviest ones) at their reduced velocities 0.03 ⩽ V_r_e_d ⩽ 5.0. The SP values derived in such a way seem to be more reliable compared to the existing semi-empirical calculations and can be used in the conditioning of experiments on the synthesis of SHEs.

  4. Least cost planning within the service concept of power supply companies

    International Nuclear Information System (INIS)

    Lueschen, H.; Sonntag, J.; Werner, R.

    1995-01-01

    In discussing the implementation of energy service concepts, German power supply companies are gradually adopting categories originating from the USA, namely integrated resources planning (IRP), least cost planning (LCP), and demand-side management (DSM). While the activities of German power supply companies are more encompassing than those of their US counterparts in the traditional features of DSM such as load management, information, and consulting, further-going measures such as direct investment and financial incentive programmes for exploiting energy-saving potentials play a less important role and are controversial in the energy-political debate. The article presents the concept of power supply companies for implementing IRP/LCP and makes a concrete assessment of the worth and efficiency of consulting compared with the newer type of financial incentive programmes. (orig.) [de

  5. Clean coal technology project to Polk Power Station, Tampa Electric Company, Florida, Volume 1: Report

    International Nuclear Information System (INIS)

    1994-06-01

    Tampa Electric Company proposes to construct and operate a 1,150-MW power station in southwestern Polk County, Florida. The proposed Polk Power Station would require an EPA NPDES permit for a new source and would include a 260-MW IGCC unit as a DOE Clean Coal Technology demonstration project. This EIS document assesses the proposed project and alternatives with respect to environmental impacts. Mitigative measures are also evaluated for the preferred alternative. Included in this Volume I are the following: alternatives including Tampa Electric Companies proposed project (preferred alternative with DOE financial assistance); affected environment; environmental consequences of the alternatives

  6. The correlation between management power and risk in the Italian companies

    Directory of Open Access Journals (Sweden)

    Raffaella Scarabino

    2013-03-01

    Full Text Available The shareholders can not directly manage the business but they have powers of pulse and control by voting right that is essential for the correct functioning of the company. In 1942 the Italian legislature, although with some exceptions, adopted One share – One vote rule. The legal framework changed significantly after the enactment of corporate law reform in 2003. The objective of this research is to examine the status of the principle of correlation between management power and risk in the context of the regulatory framework of Italian public companies, as it emerged after the enactment of above mentioned corporate law reform in 2003.

  7. Trends of personal dosimetry at atomic power plants

    International Nuclear Information System (INIS)

    Yamamura, Seini

    1998-01-01

    The individual dosimetry at the atomic power station is sorted for monthly dosimetry, daily dosimetry and special job dosimetry in high dose circumstance. Film badge (passive dosimeter) can measure gamma dose, beta dose and neutron dose respectively lower than about 0.1 mSv. While workers are in the radiation controlled area, they have to wear the dosimeters and the individual dose is accumulated for every one month. Recently the Silicon semiconductors detecting beta ray and neutron have been developed. With microcircuit technology and these new sensors, new multiple function dosimeter of the card size had been put to practical use. The result of dose measurement obtained by the electronic dosimeter is consistent well with the measurement of usual film badge and new dosimeter can determine the dose as low as 0.01 mSv. The result is stored in the non-volatile memory in the electronic personal dosimeter and held for more than one year without the power supply. The function to read data directly from the memory improves the reliability of the data protection. The realization of the unified radiation control system that uses the electronic personal dosimeter for monthly dosimetry is expected. (J.P.N.)

  8. Atomic Energy (Miscellaneous Provisions) Act 1981

    International Nuclear Information System (INIS)

    1981-01-01

    This Act extends the power of the United Kingdom Atomic Energy Authority to dispose of shares held by it in any company, and the power of the Secretary of State for Energy to dispose of shares held by him in companies engaged in activities in the field of atomic energy or radioactive substances. (NEA) [fr

  9. Engineering grouts - materials and applications with specific examples from Ra asthan Atomic Power Pro ect

    International Nuclear Information System (INIS)

    Singha Roy, P.K.; Sachchidanand; Sukhthankar, K.D.

    1978-01-01

    Grouting, though not very significant costwise, is an important aspect6 of construction in most of the major projects. According to modern construction technology, grouts have very stringent and diverse uses. The materials and practices generally found in India for grouting, mainly for structural grouts upto the middle of this decade are outlined along with details of specific grouts used in the construction of the twin reactor (440 MWe) of Rajasthan Atomic Power Station, one reactor of which is already operational. Some guidance and tables for selection of grout for a specific use have also been given. (auth.)

  10. Effect of laser power and specimen temperature on atom probe analyses of magnesium alloys

    International Nuclear Information System (INIS)

    Oh-ishi, K.; Mendis, C.L.; Ohkubo, T.; Hono, K.

    2011-01-01

    The influence of laser power, wave length, and specimen temperature on laser assisted atom probe analyses for Mg alloys was investigated. Higher laser power and lower specimen temperature led to improved mass and spatial resolutions. Background noise and mass resolutions were degraded with lower laser power and higher specimen temperature. By adjusting the conditions for laser assisted atom probe analyses, atom probe results with atomic layer resolutions were obtained from all the Mg alloys so far investigated. Laser assisted atom probe investigations revealed detailed chemical information on Guinier-Preston zones in Mg alloys. -- Research highlights: → We study performance of UV laser assisted atom probe analysis for Mg alloys. → There is an optimized range of laser power and specimen temperature. → Optimized UV laser enables atom probe data of Mg alloys with high special resolution.

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

    International Nuclear Information System (INIS)

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

    1963-01-01

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

  12. New maintenance strategy of Tokyo Electric Power Company and Fukushima Dai-ichi Nuclear Power Plant for effective ageing management and safe long-term operation

    International Nuclear Information System (INIS)

    Inagaki, Takeyuki; Yamashita, Norimichi

    2009-01-01

    Fukushima Dai-ichi Nuclear Power Plant is the oldest among three nuclear power plants owned and operated by Tokyo Electric Power Company, which consists of six boiling water reactor units. The commercial operation of Unit 1 was commenced in 1971 (37 years old) and Unit 6 in 1978 (29 years old). Currently ageing degradations of systems, structures and components are managed through maintenance programs, component replacement/refurbishment programs and long-term maintenance plans. The long-term maintenance plans are established through ageing management component replacement/refurbishment programs reviews performed before the 30th year of operation and they are for safe and reliable operation after 30 years (long-term operation). However the past maintenance actions and past component replacement/refurbishment programs were not always proactive and past operational experience and maintenance practices suggest that effective/proactive ageing management programs be introduced in earlier stage of the plant operation. In this circumstance, Tokyo Electric Power Company and Fukushima Dai-ichi Nuclear Power Plant are setting up a new maintenance strategy that includes 1) improving the normal maintenance programs by using ageing degradation data, 2) effective use of information on internal/external operational experience and maintenance practices related to ageing, and 3) proactive component/equipment refurbishment programs during a refreshment outage for safe and reliable long-term operation. To accomplish the goal of this strategy, strengthening engineering capability of plant staff members is a crucial required for the plant. The objective of this paper is to briefly explain main results ageing management reviews, past and current significant ageing issues and management programs against them, and the new maintenance strategy established by Tokyo Electric Power Company and Fukushima Dai-ichi Nuclear Power Plant. (author)

  13. The simulation of control system for the KEK main ring power supply, 1

    International Nuclear Information System (INIS)

    Sato, Hikaru; Shintomi, Takakazu; Kubo, Tadashi; Masuda, Masayoshi; Nakano, Michio.

    1975-09-01

    The simulation of control system for the KEK main ring power supply is performed. The inductance of the magnet is assumed to be linear against to the current. The results of the simulations are described. (auth.)

  14. Inquiry relating to modifications of reactor installation in Ikata No. 1 and 2 nuclear power plants of Shikoku Electric Power Company, Inc

    International Nuclear Information System (INIS)

    1979-01-01

    Application was made to the Minister of International Trade and Industry for the license relating to the modifications of reactor installation in the Ikata No. 1 and 2 nuclear power plants of the Shikoku Electric Power Company, Inc., on February 13, 1979, from the president of the company. After the safety evaluation was finished by the Ministry of International Trade and Industry, inquiry was conducted to the Atomic Energy Safety Commission (AESC) on June 15, 1979, from the Minister of International Trade and Industry. The investigation and discussion were commenced by the AESC on June 19, 1979. The modifications of the reactor installation are the increase of new fuel storage capacity from about 1/3 to about 2/3 of in-core fuel for No. 1 plant and the modification of driving mechanism from the roller nut type to the magnetic jack type for the control rod cluster for adjusting power distribution in the No. 2 plant. The contents of the safety examination for each item written above are presented. The prevention of criticality is carefully practiced for the new fuel storage by putting fuel assemblies in stainless steel can type racks and locating the fuel assemblies at the proper distance. Relating to the driving mechanism for the control rod cluster adjusting power distribution, the driving speed is not modified and the reliability is kept by carrying out the continuous operation test and the electric power black out test as the demonstration test. The magnetic jack type mechanism has the locking device to prevent reactor tripping at the time of electric power black out, and the cluster is held at the location where the cluster existed at the time of black out. (Nakai, Y.)

  15. MSR redesign and reconstruction at Indiana Michigan Power Company's Donald C. Cook Nuclear Power Plant, Unit 1

    International Nuclear Information System (INIS)

    Yarden, A.L.; Tam, C.W.; Benes, J.D.; Arnold, W.E.

    1993-01-01

    When Indiana Michigan Power Company's (I and M) 1089- MWe, PWR, Donald C. Cook Nuclear Plant, Unit 1, (Cook 1) in Bridgeman, Michigan went into commercial operation in late 1975, its turbine generator included two Moisture Separator Reheater (MSR) vessels. Each of these original MSRs contained, in addition to the moisture separation section, a single stage 2-pass reheater consisting of 5/8 inch O.D., finned CuNi tubes with main heating steam as an energy source. The enormous size of the tube bank, with a vertical orientation of its tubes' U-bends, led the designer to choose two separate headers for the inlet side and outlet side of the tube bank. Over the years, these 2-pass reheaters had deteriorated mechanically such that maintenance costs had increased considerably. Also, the MSR performance in terms of MWe gain, had fallen off as a result of a gradual reduction of both superheat and moisture separation efficiency. In 1990, these MSRs were totally reconstructed with inherently different 4-pass reheaters and upgraded moisture separation systems. The performance and other direct parameters of these newly retrofitted and improved MSRs have exceeded original design specifications, and their operational stability has improved markedly. This MSR reconstruction at Cook 1 is the first of its kind to include a 4-pass reheater in association with a nuclear turbine generator of this design. This paper highlights the problems and solutions associated respectively with the original reheaters in the Cook 1 MSRs and their recent redesign, reconstruction, and performance

  16. 20 kHz main inverter unit. [for space station power supplies

    Science.gov (United States)

    Hussey, S.

    1989-01-01

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

  17. 15 years of information and educational programme of Czech Power Company CEZ

    International Nuclear Information System (INIS)

    Dufkova, M.

    2007-01-01

    The education program is the most important long-term communication programme of CEZ. It was established in 1992 shortly after an establishment of Czech Power Company. The support of education and talented students is doubtless a positive activity bringing a benefit to the company, especially in the field of nuclear energy. Students, who have been currently addressed with this program, are future consumers of electricity and as voters and politicians they shall decide on further development of power industry and nuclear installations. We care for them to make qualified decisions. CEZ has so far been the only Czech industrial company, which offers such program to schools. Education is the most important activity in the gaining support for nuclear energy. (author)

  18. Report of fact finding survey on atomic energy industries in FY1989

    International Nuclear Information System (INIS)

    1991-01-01

    Japan Atomic Industrial Forum, Inc. summarized the results of 31st fact finding survey on atomic energy industries, which investigated and analyzed the actual status and future perspective of the expenditure, sales and personnel related to atomic energy in electric power, mining and manufacture and trading companies in FY1989. As to the state of activities of atomic energy industries, the expenditure related to atomic energy of electric power companies was 1633.7 billion yen, decrease by 7 % as compared with the previous fiscal year. The main factors are that the construction works of nuclear power stations came to temporary pause, and the operation and maintenance expenses for power stations turned to decrease due to the mechanization of inspection and the decrease of expendables. The sales related to atomic energy of mining and manufacturing companies was 1728.3 billion yen, which is the highest so far, and is increase by 18 % as compared with the previous fiscal year. Due to the diversification of atomic energy market, the manufacture for service field and others grew by 64 %, and the mechanization of production seemed to advance. The backlog of mining and manufacturing companies which is the index of future market trend was as high as 3526 billion yen. (K.I.)

  19. Booster main magnet power supply, present operation and potential future upgrades

    Energy Technology Data Exchange (ETDEWEB)

    Bajon, E.; Bannon, M.; Marneris, I.; Danowski, G.; Sandberg, J.; Savatteri, S.

    2011-03-28

    The Brookhaven Booster Main Magnet Power Supply (MMPS) is a 24 pulse thyristor control supply, rated at 5500 Amps, +/-2000 Volts, or 3000 Amps, +/-6000 Volts. The power supply is fed directly from the power utility and the peak magnet power is 18 MWatts. This peak power is seen directly at the incoming ac line. This power supply has been in operation for the last 18 years. This paper will describe the present topology and operation of the power supply, the feedback control system and the different modes of operation of the power supply. Since the power supply has been in operation for the last 18 years, upgrading this power supply is essential. A new power supply topology has been studied where energy is stored in capacitor banks. DC to DC converters are used to convert the dc voltage stored in the capacitor banks to pulsed DC voltage into the magnet load. This enables the average incoming power from the ac line to be constant while the peak magnet power is pulsed to +/- 18 MWatts. Simulations and waveforms of this power supply will be presented.

  20. 77 FR 14516 - Alabama Power Company, Martin Dam Hydroelectric Project; Notice of Proposed Revised Restricted...

    Science.gov (United States)

    2012-03-12

    ... Power Company, Martin Dam Hydroelectric Project; Notice of Proposed Revised Restricted Service List for... for inclusion in, the National Register of Historic Places at the Martin Dam Hydroelectric Project...)). The Commission's responsibilities pursuant to section 106 for the Martin Dam Hydroelectric Project...

  1. 77 FR 38796 - Georgia Power Company; Bartletts Ferry Hydroelectric Project; Notice of Revised Restricted...

    Science.gov (United States)

    2012-06-29

    ... Alabama] Georgia Power Company; Bartletts Ferry Hydroelectric Project; Notice of Revised Restricted... by issuance of a new license for the Bartletts Ferry Hydroelectric Project No. 485. The programmatic... Hydroelectric Project. On June 14, 2012, the Kialegee Tribal Town requested a revision to the restricted service...

  2. 75 FR 7471 - Chandra Coffee and Rabun Boatworks, Complainants v. Georgia Power Company, Respondent; Notice of...

    Science.gov (United States)

    2010-02-19

    ... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Project No. 2354-10] Chandra Coffee and Rabun Boatworks, Complainants v. Georgia Power Company, Respondent; Notice of Complaint February 3, 2010. Take notice that on December 14, 2009, as amended on January 8, 2010, Chandra Coffee and Rabun...

  3. 76 FR 28024 - Swan Falls Hydroelectric Project, Idaho Power Company; Notice of Teleconference

    Science.gov (United States)

    2011-05-13

    ... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Project No. 503-048-ID] Swan Falls Hydroelectric Project, Idaho Power Company; Notice of Teleconference a. Date and Time of Meeting: Tuesday, May 24, 2011 at 10 a.m. (Mountain Time). b. Place: By copy of this notice we are inviting all interested parties to attend a teleconference from...

  4. 76 FR 71014 - Idaho Power Company, IDACORP Energy, L.P., IDACORP, Inc.; Notice of Petition

    Science.gov (United States)

    2011-11-16

    ... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Docket No. IN03-9-000] Idaho Power Company, IDACORP Energy, L.P., IDACORP, Inc.; Notice of Petition Take notice that on September 9, 2011..., 2003,\\1\\ filed a petition to terminate Appendix B, Appendix C, and Appendix E to the Settlement...

  5. 75 FR 57746 - Lockhart Power Company; Notice of Application Tendered for Filing With the Commission, Soliciting...

    Science.gov (United States)

    2010-09-22

    .... Applicant Contact: Bryan D. Stone, Chief Operating Officer, Lockhart Power Company, Inc., 420 River Street... Support. Although the Commission strongly encourages electronic filing, documents may also be paper-filed. To paper-file, mail an original and seven copies to: Kimberly D. Bose, Secretary, Federal Energy...

  6. 76 FR 7840 - American Hydro Power Company; Notice of Termination of Exemption by Implied Surrender and...

    Science.gov (United States)

    2011-02-11

    ... Power Company; Notice of Termination of Exemption by Implied Surrender and Soliciting Comments, Protests... the Commission: a. Type of Proceeding: Termination of exemption by implied surrender. b. Project No... if any term or condition of the exemption is violated. The project has not operated since 2004, and...

  7. The influence of the political, economic and main force risk factors on the power system

    International Nuclear Information System (INIS)

    Barbu, C.; Ruxanda, G.

    1996-01-01

    This paper deals mainly with the economic aspects of the Romanian power development policy in the context of European Union integration. There are presented the gradual steps of regional interconnection which are currently undertaken under PHARE program. Special attention is given to the legislation, power production technology, costs, and environmental protection problems. (C.M.) 1 fig

  8. Modern technical diagnostic system for the main components of powerful turbine generator

    International Nuclear Information System (INIS)

    Ezovit, G.P.; Uglyarenko, V.P.; Burlaka, S.I.; Goroz, N.I.; Orinin, S.E.; Komaritsa, V.N.; Zav'yalov, D.N.; Mazurenko, O.A.

    2011-01-01

    The modern diagnostic system to monitor the technical state of a powerful turbine generator is considered. This system permits the detection of defects in its main components and cooling system at the early stage of their development, prevention of damage and, as a consequence, emergency shutdown of nuclear power units

  9. 76 FR 56242 - Duke Energy Carolinas, LLC; Southern Nuclear Operating Company; Establishment of Atomic Safety...

    Science.gov (United States)

    2011-09-12

    ... NUCLEAR REGULATORY COMMISSION [Docket Nos. 52-018-COL, 52-019-COL, 52-025-COL, 52-026-COL; ASLBP No. 11-913-01-COL-BD01] Duke Energy Carolinas, LLC; Southern Nuclear Operating Company; Establishment... following captioned cases: Duke Energy Carolinas, LLC, (William States Lee III Nuclear Station, Units 1 and...

  10. Experience of Minas Gerais Energetic Company (CEMIG) in feasibility studies from hydroelectric power plants: energetic-economic studies

    International Nuclear Information System (INIS)

    Ramos, O.C.; Bras, A.J.F.; Batista Neto, R.P.; Salles Filho, M.P.

    1989-01-01

    The experience of Minas Gerais Energetic Company (CEMIG) - Brazil, on the use of dimensioning methodology for hydroelectric power plant from the Coordinated Group of Planning System was described, showing the problems with its use and the solutions, mainly the reservoir and the dimension of installed potential. It was concluded that the calculation procedures of the marginal costs for dimensioning, so as to become these costs more representative in future structure of the Brazilian generator park and less dependent to the oscillation due to conjuncture problems, must be re-evaluated. (C.G.C.). 7 refs, 3 figs, 1 tab

  11. Effects of respirator use on worker performance

    Energy Technology Data Exchange (ETDEWEB)

    Cardarelli, R. [Yankee Atomic Electric Co., Bolton, MA (United States)

    1995-03-01

    In 1993, EPRI funded Yankee Atomic Electric Company to examine the effects of respirator use on worker efficiency. Phase I of Yankee`s effort was to develop a study design to determine respirator effects. Given success in Phase I, a larger population will be tested to determine if a stasitically significant respirator effect on performance can be measured. This paper summarizes the 1993 EPRI/Yankee Respirator Effects of Pilot Study, and describes the study design for the 1994 EPRI/Yankee Respirator Study to be conducted at the Oyster Creek Nuclear Power Plant. Also described is a summary of respirator effect studies that have been conducted during the last ten (10) years.

  12. Knolls Atomic Power Laboratory environmental monitoring report, calendar year 2001

    International Nuclear Information System (INIS)

    2002-01-01

    The results of the effluent and environmental monitoring programs at the three Knolls Atomic Power Laboratory (KAPL) Sites are summarized and assessed in this report. Operations at the Knolls and Kesselring Sites and Site closure activities at the S1C Site (also known as the KAPL Windsor Site) continue to have no adverse effect on human health and the quality of the environment. The effluent and environmental monitoring programs conducted by KAPL at the Knolls and Kesselring Sites are designed to determine the effectiveness of treatment and control methods, to provide measurement of the concentrations in effluents for comparison with applicable standards, and to assess resultant concentrations in the environment. The monitoring programs include analyses of samples of liquid and gaseous effluents for chemical constituents and radioactivity as well as environmental monitoring of air, water, sediment, and fish. Radiation measurements are also made around the perimeter of the Knolls and Kesselring Sites and at off-site background locations. The environmental monitoring program for the S1C Site continues to be reduced in scope from previous years due to the completion of Site dismantlement activities during 1999 and a return to green field conditions during 2000

  13. Knolls Atomic Power Laboratory environmental monitoring report, calendar year 2000

    International Nuclear Information System (INIS)

    2001-01-01

    The results of the effluent and environmental monitoring programs at the three Knolls Atomic Power Laboratory (KAPL) Sites are summarized and assessed in this report. Operations at the Knolls Site, Niskayuna, New York and the Kesselring Site, West Milton, New York and site closure activities at the S1C Site, Windsor, Connecticut, continued to have no adverse effect on human health and the quality of the environment during calendar year 2000. The effluent and environmental monitoring programs conducted by KAPL are designed to determine the effectiveness of treatment and control methods, to provide measurement of the concentrations in effluents for comparison with applicable standards, and to assess resultant concentrations in the environment. The monitoring programs include analyses of samples of liquid and gaseous effluents for chemical constituents and radioactivity as well as monitoring of environmental air, water, sediment, and fish. Radiation measurements are also made around the perimeter of each Site and at off-site background locations. Monitoring programs at the S1C Site were reduced in scope during calendar year 2000 due to completion of site dismantlement activities during 1999

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

    Energy Technology Data Exchange (ETDEWEB)

    Jones, T. D.

    1979-01-01

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

  15. Knolls Atomic Power Laboratory environmental monitoring report, calendar year 2000

    Energy Technology Data Exchange (ETDEWEB)

    None

    2001-12-01

    The results of the effluent and environmental monitoring programs at the three Knolls Atomic Power Laboratory (KAPL) Sites are summarized and assessed in this report. Operations at the Knolls Site, Niskayuna, New York and the Kesselring Site, West Milton, New York and site closure activities at the S1C Site, Windsor, Connecticut, continued to have no adverse effect on human health and the quality of the environment during calendar year 2000. The effluent and environmental monitoring programs conducted by KAPL are designed to determine the effectiveness of treatment and control methods, to provide measurement of the concentrations in effluents for comparison with applicable standards, and to assess resultant concentrations in the environment. The monitoring programs include analyses of samples of liquid and gaseous effluents for chemical constituents and radioactivity as well as monitoring of environmental air, water, sediment, and fish. Radiation measurements are also made around the perimeter of each Site and at off-site background locations. Monitoring programs at the S1C Site were reduced in scope during calendar year 2000 due to completion of site dismantlement activities during 1999.

  16. Knolls Atomic Power Laboratory environmental monitoring report, calendar year 2001

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-12-31

    The results of the effluent and environmental monitoring programs at the three Knolls Atomic Power Laboratory (KAPL) Sites are summarized and assessed in this report. Operations at the Knolls and Kesselring Sites and Site closure activities at the S1C Site (also known as the KAPL Windsor Site) continue to have no adverse effect on human health and the quality of the environment. The effluent and environmental monitoring programs conducted by KAPL at the Knolls and Kesselring Sites are designed to determine the effectiveness of treatment and control methods, to provide measurement of the concentrations in effluents for comparison with applicable standards, and to assess resultant concentrations in the environment. The monitoring programs include analyses of samples of liquid and gaseous effluents for chemical constituents and radioactivity as well as environmental monitoring of air, water, sediment, and fish. Radiation measurements are also made around the perimeter of the Knolls and Kesselring Sites and at off-site background locations. The environmental monitoring program for the S1C Site continues to be reduced in scope from previous years due to the completion of Site dismantlement activities during 1999 and a return to green field conditions during 2000.

  17. Monitoring of atmospheric 3H around Narora Atomic Power Station

    International Nuclear Information System (INIS)

    Gautam, Y.P.; Sharma, A.K.; Sharma, S.; Rao, K.S.; Kumar, J.; Kumar, V.; Singh, B.; Kumar, A.; Hedge, A.G.

    2010-01-01

    Atmospheric tritium activity is measured regularly around Narora Atomic Power Station (NAPS) since gaseous waste, which contains tritium, is being released through a 145 m high stack at NAPS site. Atmospheric data collected during 2004-2008 shows a large variation of 3 H concentration in air, fluctuating in the range of ≤0.2-91.6 Bq m -3 . Significantly, higher tritium levels were measured in samples near the site boundary (1.6 km) of NAPS compared to off-site locations. The atmospheric dilution factor was found to be in the range of 1.1 x 10 -7 -7.3 x 10 -7 s m -3 . The scavenging ratio of NAPS site was found to be varying from 0.2 x 10 4 to 14.1 x 10 4 (Bq m -3 rain water per Bq m -3 air). The inhalation dose to a member of general public at different distances (1.6-30 km) from NAPS site was found to be ranged from 0.08-0.21 μSv year -1 . (author)

  18. Knolls Atomic Power Laboratory environmental monitoring report, calendar year 1996

    International Nuclear Information System (INIS)

    1996-01-01

    The results of the effluent and environmental monitoring programs at the three Knolls Atomic Power Laboratory (KAPL) sites are summarized and assessed in this report. The principal function at KAPL sites (Knolls, Kesselring, and Windsor) is research and development in the design and operation of Naval nuclear propulsion plants. The Kesselring Site is also used for the training of personnel in the operation of these plants. The Naval nuclear propulsion plant at the Windsor Site is currently being dismantled. Operations at the three KAPL sites resulted in no significant release of hazardous substances or radioactivity to the environment. The effluent and environmental monitoring programs conducted by KAPL are designed to determine the effectiveness of treatment and control methods, to provide measurement of the concentrations in effluents for comparison with applicable standards, and to assess resultant concentrations in the environment. The monitoring programs include analyses of samples of liquid and gaseous effluents for chemical constituents and radioactivity as well as monitoring of environmental air, water, sediment, and fish. Radiation measurements are also made around the perimeter of each site and at off-site background locations

  19. Knolls Atomic Power Laboratory environmental monitoring report, calendar year 1996

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-12-31

    The results of the effluent and environmental monitoring programs at the three Knolls Atomic Power Laboratory (KAPL) sites are summarized and assessed in this report. The principal function at KAPL sites (Knolls, Kesselring, and Windsor) is research and development in the design and operation of Naval nuclear propulsion plants. The Kesselring Site is also used for the training of personnel in the operation of these plants. The Naval nuclear propulsion plant at the Windsor Site is currently being dismantled. Operations at the three KAPL sites resulted in no significant release of hazardous substances or radioactivity to the environment. The effluent and environmental monitoring programs conducted by KAPL are designed to determine the effectiveness of treatment and control methods, to provide measurement of the concentrations in effluents for comparison with applicable standards, and to assess resultant concentrations in the environment. The monitoring programs include analyses of samples of liquid and gaseous effluents for chemical constituents and radioactivity as well as monitoring of environmental air, water, sediment, and fish. Radiation measurements are also made around the perimeter of each site and at off-site background locations.

  20. Quality control of three main materials for civil construction of nuclear power plant

    International Nuclear Information System (INIS)

    Wang Feng

    2011-01-01

    The construction and operation of nuclear power plant is a systematic engineering. To ensure quality and safety of nuclear power plants, each work from design to operation can have certain impact on the quality and safety of the project. The quality of each related work shall be controlled. Starting from the quality control over raw materials for the civil construction of nuclear power plant, this article mainly analyzes how to control the quality and manage the three main materials of steel, concrete and modular parts in the civil construction. (author)

  1. Large screen mimic display design research for advanced main control room in nuclear power plant

    International Nuclear Information System (INIS)

    Zheng Mingguang; Yang Yanhua; Xu Jijun; Zhang Qinshun; Ning Zhonghe

    2002-01-01

    Firstly the evolution of mimic diagrams or displays used in the main control room of nuclear power plant was introduced. The active functions of mimic diagrams were analyzed on the release of operator psychological burden and pressure, the assistance of operator for the information searching, status understanding, manual actuation, correct decision making as well as the safe and reliable operation of the nuclear power plant. The importance and necessity to use the (large screen) mimic diagrams in advanced main control room of nuclear power plant, the design principle, design details and verification measures of large screen mimic display are also described

  2. Considerations for surviving the loss of a main feedwater pump at full power

    International Nuclear Information System (INIS)

    Gaydos, K.A.; Calvo, R.; Conroy, P.W.; Klein, C.M.; Mellers, J.E.

    1990-01-01

    Today's economics dictate that nuclear power operational costs be contained by addressing frequently-occurring trips that might be minimized or avoided via specific upgrades. Much recent attention has focused on the significant percentage of plant trips related to feedwater flow regulation; however, another frequent feedwater-related trip stems from the loss of a single main feedwater pump while operating at high power levels, causing a plant trip on low steam generator water-level. This paper summarizes the results of several plant-specific studies that evaluate a unit's capabilities to consistently survive the loss of a main feedwater pump from full power, and outlines a methodology for analyzing this capability

  3. Burning issue of energy problem after Fukushima disaster of TEPCO's atomic power stations

    International Nuclear Information System (INIS)

    Harada, Shoji

    2012-01-01

    Strikes of unanticipated enormous earthquake and subsequent tsunami brought unbelievable disaster in eastern Japan on March 11, 2012. In particular, collapse of cooling system of TEPCO's Fukushima atomic power stations resulted in IAEA-defined level7 accident including heavy radiation, hydrogen explosion -induced collapse of the building of power station No.2 and No.4 and melt through of nuclear pressure vessel No1.3.4 At an initial stage of the disaster, nobody knew precisely what happened at the power stations. According to the recent report of the national investigation committee, precise reason of the collapse of the cooling system whether it was induced by the strike of huge earthquake or tsunami is still unclear. Due to poor risk management of the government and TEPCO and closure of the precise disaster information, people became suspicious and nervous about the atomic power station. Fifty four atomic power stations have been constructed for these forty years in Japan. On last May 04, all the atomic power stations were shut down due to periodic inspection. However, restart of them became hot discussion. Although atomic power station was regarded as a powerful tool to reduce carbon dioxide several years ago, this situation after March 11 completely changed. In many countries which possess atomic power station, making a road map to develop recyclable energy is a burning issue. It should be noted that German spent about thirty years to declare atomic energy free society. Finally necessity of succession of technology of utilizing atomic power is emphasized. Politics on depending atomic power differs in each country. Therefore, study from Fukushima disaster should be widely used to prevent from unexpected accident of atomic power station.

  4. Optimization of the main control room habitability system in nuclear power plant

    International Nuclear Information System (INIS)

    Zheng Guanghui; Zhao Xinyan

    2013-01-01

    This article describes the optimization of main control room habitability system in nuclear power plant. It also describes the design shortage in terms of habitability in the main control room. Through modification and optimization, habitable conditions are met for personnel staying in the emergency area of the main control room for a period of time, with an aim to take accident intervention measures smoothly and reduce the accident loss and radioactive contamination as low as possible. (authors)

  5. Performance of on-power fuelling equipment at Rajasthan Atomic Power Station

    International Nuclear Information System (INIS)

    Jayabarathan, S.; Gopalakrishnan, S.

    1977-01-01

    Natural uranium reactors on account of their intrinsically low reactivity need frequent refuelling. The Rajasthan Atomic Power Station based on natural uranium reactors has, therefore, been provided with on-power fuel handling system which was installed in 1972. Its performance has met the design intent and operational objectives which are enumerated. However, continuous fuelling 7 to 10 days has not been possible because frequent maintenance of refuelling system is needed on account of certain deficiencies major of which is the heavy water leakage. For better performance, installation of a programmable logic controller is suggested. Mention has also been made of inadequate number of skilled man-power required for maintenance which leads to quick depletion of man-rem of all the available personnel trained for maintenance work. (M.G.B.)

  6. Atomic Information Technology Safety and Economy of Nuclear Power Plants

    CERN Document Server

    Woo, Taeho

    2012-01-01

    Atomic Information Technology revaluates current conceptions of the information technology aspects of the nuclear industry. Economic and safety research in the nuclear energy sector are explored, considering statistical methods which incorporate Monte-Carlo simulations for practical applications. Divided into three sections, Atomic Information Technology covers: • Atomic economics and management, • Atomic safety and reliability, and • Atomic safeguarding and security. Either as a standalone volume or as a companion to conventional nuclear safety and reliability books, Atomic Information Technology acts as a concise and thorough reference on statistical assessment technology in the nuclear industry. Students and industry professionals alike will find this a key tool in expanding and updating their understanding of this industry and the applications of information technology within it.

  7. IAEA activities and main achievements on human resource management and training of nuclear power plant personnel

    International Nuclear Information System (INIS)

    Kossilov, A.

    2002-01-01

    The Nuclear Power Engineering Section is responsible for implementation of the Agency's sub-programme on Engineering and Management Support for Competitive Nuclear Power. The objectives of the sub-programme is to increase Member State capabilities in utilizing the best engineering and management practices for improving NPP performance and competitiveness, optimizing plant service life and decommissioning and strengthening nuclear power infrastructure. NPES' main activities cover: Nuclear power infrastructure, Knowledge management, Personal training and qualification, Quality Management and QA, NPP life management including databases, Modern NPP control and instrumentation, and NPP performance management

  8. A proposal for human factors education in a power plant company

    International Nuclear Information System (INIS)

    Hikono, Masaru

    2004-01-01

    The author was asked by a power plant company to investigate how to change the actual education system concerning human factor education for the plant staff. First, the problems faced by actual education system were investigated based on the results of a large number of surveys conducted in educational fields, and various documents. In the present paper, the author describes the newly proposed educational program., using as illustration a case study. The findings of the present study suggests that, concerning the content of the educational program, it is indispensable for each company to develop a curriculum based on its specific needs. (author)

  9. Incentive mechanisms to promote energy efficiency programs in power distribution companies

    International Nuclear Information System (INIS)

    Osorio, Karim; Sauma, Enzo

    2015-01-01

    Power distribution companies (DISCOs) play an important role in promoting energy efficiency (hereafter EE), mainly due to the fact that they have detailed information regarding their clients' consumption patterns. However, under the traditional regulatory framework, DISCOs have disincentives to promote EE, due to the fact that a reduction in sales also means a reduction in their revenues and profits. Most regulatory policies encouraging EE have some embedded payment schemes that allow financing EE programs. In this paper, we focus on these EE-programs' payment schemes that are embedded into the regulatory policies. Specifically, this paper studies two models of the Principal–Agent bi-level type in order to analyze the economic effects of implementing different payment schemes to foster EE in DISCOs. The main difference between each model is that uncertainty in energy savings is considered by the electricity regulatory institution in only one of the models. In terms of the results, it is observed that, in general terms, it is more convenient for the regulator to adopt a performance-based incentive mechanism than a payment scheme financing only the fixed costs of implementing EE programs. However, if the electricity regulatory institution seeks a higher level of minimum expected utility, it is optimal to adopt a mixed system of compensation, which takes into account the fixed cost compensation and performance-based incentive payments. - Highlights: • We studied different payment schemes to promote energy efficiency in DISCOs. • We propose two bi-level models based on the Principal–Agent theory. • Uncertainty associated with energy savings is incorporated in one of the models. • A performance-based payment scheme is generally more convenient for the regulator. • A mixed payment scheme is optimal when a lower level of uncertainty is tolerated

  10. Statistical analysis on main cause of death among atomic bomb survivors

    International Nuclear Information System (INIS)

    Hamada, Tadao; Kuramoto, Kiyoshi

    1986-01-01

    The purpose of this report is to present the patho-statistical analysis in 2306 autopsied patients (1237 exposed patients and 1069 non-exposed patients), focusing on the difference in the main cause of death between the exposed and non-exposed groups. The most common cause of death was malignancy in both exposed and non-exposed groups. The incidence of cardiovascular, respiratory tract, and hematologic diseases was higher in the exposed group than the non-exposed group. The incidence of various types of malignancy varied in the following order: lung cancer > stomach cancer > leukemia > liver cancer in patients exposed at ≤ 2,000 m from ground zero; stomach cancer > lung cancer > liver cancer > leukemia in those exposed at > 2,000 m or who were not in city; and liver cancer > stomach cancer > lung cancer > leukemia in non-exposed patients. Cancers of the lung and stomach were more frequently observed in the exposed group than the non-exposed group. The incidence of stomach cancer tended to increase with aging in the exposed group, as opposed to that of leukemia, although still observed in younger patients, decreasing with time. Older women tended to have liver cancer more frequently in the exposed group than the non-exposed group; however, this tendency was not seen in men. (Namekawa, K.)

  11. 76 FR 66333 - Carolina Power & Light Company, H.B. Robinson Steam Electric Plant, Unit No. 2; Environmental...

    Science.gov (United States)

    2011-10-26

    ... NUCLEAR REGULATORY COMMISSION [Docket No. 50-261; NRC-2011-0247] Carolina Power & Light Company, H.B. Robinson Steam Electric Plant, Unit No. 2; Environmental Assessment and Finding of No Significant... Facility Operating License No. DPR-23, issued to Carolina Power & Light Company (the licensee), for...

  12. 78 FR 16490 - Jersey Central Power and Light Company, PSEG Fossil, LLC; Notice of Authorization for Continued...

    Science.gov (United States)

    2013-03-15

    ... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Project No. 2309-000] Jersey Central Power and Light Company, PSEG Fossil, LLC; Notice of Authorization for Continued Project Operation On February 18, 2011, the Jersey Central Power and Light Company and PSEG Fossil LLC, licensees for the Yards...

  13. 76 FR 13173 - Jersey Central Power & Light Company and PSEG Fossil, LLC; Notice of Application Tendered for...

    Science.gov (United States)

    2011-03-10

    ... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Project No. 2309-019] Jersey Central Power & Light Company and PSEG Fossil, LLC; Notice of Application Tendered for Filing With the.... Date Filed: February 18, 2011. d. Applicant: Jersey Central Power & Light Company and PSEG Fossil, LLC...

  14. 77 FR 16026 - Cargill Power Markets, LLC v. Public Service Company of New Mexico; Notice of Compliance Filing

    Science.gov (United States)

    2012-03-19

    ... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Docket No. EL10-61-002] Cargill Power Markets, LLC v. Public Service Company of New Mexico; Notice of Compliance Filing Take notice that on March 12, 2012, Public Service Company of New Mexico and Cargill Power Markets, LLC submitted a...

  15. 78 FR 28835 - Salton Sea Power Generation Company; Supplemental Notice That Initial Market-Based Rate Filing...

    Science.gov (United States)

    2013-05-16

    ... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Docket No. ER13-1271-000] Salton Sea Power Generation Company; Supplemental Notice That Initial Market-Based Rate Filing Includes Request for... Salton Sea Power Generation Company's application for market-based rate authority, with an accompanying...

  16. Release criteria for decommissioning of the Shippingport Atomic Power Station

    International Nuclear Information System (INIS)

    Eger, K.J.; Gardner, D.L.; Giordano, R.J.

    1986-01-01

    The United States Department of Energy (DOE) has established guidelines for allowable levels of residual radioactivity at remote sites in the Surplus Facilities Management Program (SFMP). These guidelines specify that doses to the public from this residual radioactivity must not exceed 500 mrem/year (for up to five years) or 100 mrem/year (for a lifetime), regardless of the use of the land. The guidelines also specify that exposures be further limited, depending on ALARA considerations. The decommissioning of the Shippingport Atomic Power Station, done under the auspices of SFMP, is being performed in accordance with these guidelines. It follows that, at the conclusion of the project, the concentrations of residual radioactivity, identified both by isotope and location (x,y,z), must be low enough so that the guidelines (500,100) are not exceeded. Furthermore, the concentrations must be low enough so that additional action which might be taken to reduce them cannot cost effectively decrease the dose to the public. A cost-benefit analysis, based on actual conditions at Shippingport, is being prepared to identify these ''low-enough'' concentrations. Once identified, these concentrations will comprise the release criteria for the site. The analysis will be developed by (1) performing an initial site characterization, (2) employing pathways analyses to compute the dose to a future occupant, (3) costing of proposed site modifications, and (4) repeating a pathways analysis based on each ''as-modified'' location on the site. The result will be a paired set of data relating the cost of modification to the reduction in the dose to the future occupant

  17. Orcas Power and Light Company [fourth quarterly] technical progress report, July--September 1992

    Energy Technology Data Exchange (ETDEWEB)

    1992-12-31

    After a year of operating the G-Van, OPALCO concluded that the company transportation needs were not being met by the G-Van. The previous quarterly report mentioned battery problems with the Solectria (No. 51). This problem is one of reduced range and power and has been determined to be caused by one or more individual monoblock failures. The local Solectria representative and Solectria headquarters personnel have been aware of this unsatisfactory condition and are continuing their attempt to solve it. The Solectria and G-Van continue to be used intermittently by company personnel for errands and engineering trips. Generally, the smaller, compact size of the Solectria make it the most preferred by company drivers. Clearly the G-Van is not selected for use because of its size and weight. It is important to note that the driver dissatisfaction is not related to the fact that it is an electric van, but more its lack of maneuverability.

  18. Orcas Power and Light Company [fourth quarterly] technical progress report, July--September 1992

    Energy Technology Data Exchange (ETDEWEB)

    1992-01-01

    After a year of operating the G-Van, OPALCO concluded that the company transportation needs were not being met by the G-Van. The previous quarterly report mentioned battery problems with the Solectria (No. 51). This problem is one of reduced range and power and has been determined to be caused by one or more individual monoblock failures. The local Solectria representative and Solectria headquarters personnel have been aware of this unsatisfactory condition and are continuing their attempt to solve it. The Solectria and G-Van continue to be used intermittently by company personnel for errands and engineering trips. Generally, the smaller, compact size of the Solectria make it the most preferred by company drivers. Clearly the G-Van is not selected for use because of its size and weight. It is important to note that the driver dissatisfaction is not related to the fact that it is an electric van, but more its lack of maneuverability.

  19. Harmonic and power balance tools for tapping-mode atomic force microscope

    International Nuclear Information System (INIS)

    Sebastian, A.; Salapaka, M. V.; Chen, D. J.; Cleveland, J. P.

    2001-01-01

    The atomic force microscope (AFM) is a powerful tool for investigating surfaces at atomic scales. Harmonic balance and power balance techniques are introduced to analyze the tapping-mode dynamics of the atomic force microscope. The harmonic balance perspective explains observations hitherto unexplained in the AFM literature. A nonconservative model for the cantilever - sample interaction is developed. The energy dissipation in the sample is studied and the resulting power balance equations combined with the harmonic balance equations are used to estimate the model parameters. Experimental results confirm that the harmonic and power balance tools can be used effectively to predict the behavior of the tapping cantilever. [copyright] 2001 American Institute of Physics

  20. Forecasted electric power demands for the Delmarva Power and Light Company. Volume 1 and Volume 2. Documentation manual

    International Nuclear Information System (INIS)

    Estomin, S.L.; Beach, J.E.

    1990-10-01

    The two-volume report presents the results of an econometric forecast of peak load and electric power demands for the Delmarva Power and Light Company (DP ampersand L) through the year 2008. Separate sets of models were estimated for the three jurisdictions served by DP ampersand L: Delaware, Maryland and Virginia. For both Delaware and Maryland, econometric equations were estimated for residential, commercial, industrial, and streetlighting sales. For Virginia, equations were estimated for residential, commercial plus industrial, and streetlighting sales; separate industrial and commercial equations were not estimated for Virginia due to the relatively small size of DP ampersand L's Virginia Industrial load. Wholesale sales were econometrically estimated for the DP ampersand L system as a whole. In addition to the energy sales models, an econometric model of annual (summer) peak demand was estimated for the Company

  1. Atomic Energy of Canada Limited-Chemical Company Annual review of operations, 1980-81

    International Nuclear Information System (INIS)

    1981-01-01

    Record production of heavy water was achieved: the plants at Glace Bay and Port Hawkesbury, Nova Scotia, produced a total of 560 megagrams. A shipment of 500 Mg was delivered on time to the Wolsung CANDU reactor in Korea. Energy conservation and waste heat utilization programs included the construction of a greenhouse at the Glace Bay site. Long-term protection of the La Prade site is essentially complete. The company has reorganized its marketing and engineering division and assumed a greater international role

  2. Prediction of the Main Engine Power of a New Container Ship at the Preliminary Design Stage

    Science.gov (United States)

    Cepowski, Tomasz

    2017-06-01

    The paper presents mathematical relationships that allow us to forecast the estimated main engine power of new container ships, based on data concerning vessels built in 2005-2015. The presented approximations allow us to estimate the engine power based on the length between perpendiculars and the number of containers the ship will carry. The approximations were developed using simple linear regression and multivariate linear regression analysis. The presented relations have practical application for estimation of container ship engine power needed in preliminary parametric design of the ship. It follows from the above that the use of multiple linear regression to predict the main engine power of a container ship brings more accurate solutions than simple linear regression.

  3. Centralized vs. decentralized thermal IR inspection policy: experience from a major Brazilian electric power company

    Science.gov (United States)

    dos Santos, Laerte; da Costa Bortoni, Edson; Barbosa, Luiz C.; Araujo, Reyler A.

    2005-03-01

    Furnas Centrais Elétricas S.A is one of the greatest companies of the Brazilian electric power sector and a pioneer in using infrared thermography. In the early 70s, the maintenance policy used was a centralized approach, with only one inspection team to cover all the company"s facilities. In the early 90s, FURNAS decided to decentralize the thermography inspections creating several inspection teams. This new maintenance policy presented several advantages when compared to the previous one. However the credibility of the results obtained with the thermal inspection was frequently being questioned, in part due to the lack of a detailed planning to carry out the transition from the centralized inspection to the decentralized one. In some areas of the company it was suggested the inactivation of the thermography. This paper presents the experience of FURNAS with these different maintenance policies and details the procedures which have been taken that nowadays the infrared thermal inspection has become one of the most important techniques of predictive maintenance in the company.

  4. Environmental Disclosure of Electric Power Companies Listed in the Corporate Sustainability Index (CSI

    Directory of Open Access Journals (Sweden)

    Clésia Ana Gubiani

    2012-12-01

    Full Text Available The study aimed to verify the level of disclosure of environmental information in the administration reports of the energy companies listed in the Corporate Sustainability Index (CSI. A descriptive and quantitative research was done, using the content analysis technique on the administration reports from 2006 to 2008. The sample consisted of 11 electric power companies listed in the CSI. For quantitative analysis of the disclosure index, the data collection instrument was based on the study of Rover, Murcia and Borba (2008, which proposes eight environmental categories and 36 subcategories. For the whole analysis of the data were elaborated networks of the items disclosed in each company, using the software UNICET ®. The survey results showed that there is satisfactory disclosure in the categories of environmental policies and education, training and research environment. However, it was found that there is need for greater disclosure of categories of products impacts and processes in the environment, power polices and financial environmental information. It was concluded that the information disclosed in the administration reports of the companies surveyed about the environmental information do not respect the principle of full disclosure.

  5. Research on cognitive reliability model for main control room considering human factors in nuclear power plants

    International Nuclear Information System (INIS)

    Jiang Jianjun; Zhang Li; Wang Yiqun; Zhang Kun; Peng Yuyuan; Zhou Cheng

    2012-01-01

    Facing the shortcomings of the traditional cognitive factors and cognitive model, this paper presents a Bayesian networks cognitive reliability model by taking the main control room as a reference background and human factors as the key points. The model mainly analyzes the cognitive reliability affected by the human factors, and for the cognitive node and influence factors corresponding to cognitive node, a series of methods and function formulas to compute the node cognitive reliability is proposed. The model and corresponding methods can be applied to the evaluation of cognitive process for the nuclear power plant operators and have a certain significance for the prevention of safety accidents in nuclear power plants. (authors)

  6. Status of the maintenance for the KEK 12GEV-PS main ring and power supply

    International Nuclear Information System (INIS)

    Sato, Hikaru; Igarashi, Susumu; Marutsuka, Katsumi; Mikawa, Katsuhiko; Shirakata, Masashi; Sueno, Tsuyoshi; Tokuda, Noboru

    2004-01-01

    More than 30 years passed since the KEK 12GeV-PS construction, some of accelerator equipments are highly radiated, especially the injection and the extraction equipments. In recent years, the higher intensity beam has been required for such as the long baseline neutrino oscillation experiment and rare decay experiments. Then, the circumference of the maintenance work has become severe. Further, almost equipments of main ring and power supply have deteriorated. Status of the Maintenance for the KEK 12GeV-PS main ring and power supply are presented. (author)

  7. 76 FR 54259 - Virginia Electric and Power Company, Docket Nos. 50-338 and 50-339, North Anna Power Station...

    Science.gov (United States)

    2011-08-31

    ... NUCLEAR REGULATORY COMMISSION [NRC-2011-0185] Virginia Electric and Power Company, Docket Nos. 50.... NPF-4 and NPF-7, issued to Virginia Electric Power Company (the licensee), for operation of the North...) and (d) during declarations of severe weather conditions involving tropical storm or hurricane force...

  8. Simulation of the control system for the KEK main ring power supply-II

    International Nuclear Information System (INIS)

    Kabe, Atsushi; Sato, Hikaru; Masuda, Masayoshi; Takeda, Masahiro; Nakano, Michio

    1977-05-01

    The tracking error between the magnetic field of the bending magnets and that of the quadrupole magnets is a very important problem of the KEK main ring power supply. Tacking performance is simulated using DDS (Digital Dynamics Simulator) in cases of 8 GeV and 12 GeV operation of the KEK main ring. The results of simulation coincide with the data of actual system. (auth.)

  9. The effect of electric transmission constraints on how power generation companies bid in the Colombian electrical power market

    Directory of Open Access Journals (Sweden)

    Luis Eduardo Gallego Vega

    2010-05-01

    Full Text Available This paper presents the results of research about the effect of transmission constraints on both expected electrical energy to be dispatched and power generation companies’ bidding strategies in the Colombian electrical power market. The proposed model simulates the national transmission grid and economic dispatch by means of optimal power flows. The proposed methodology allows structural problems in the power market to be analyzed due to the exclusive effect of trans- mission constraints and the mixed effect of bidding strategies and transmission networks. A new set of variables is proposed for quantifying the impact of each generation company on system operating costs and the change in expected dispatched energy. A correlation analysis of these new variables is presented, revealing some interesting linearities in some generation companies’ bidding patterns.

  10. Sale of electric energy: the case of Electric Power Company of Santa Catarina State (CELESC)

    International Nuclear Information System (INIS)

    Aurich, D.S.

    1990-01-01

    An electric power system assuring the electric supply to the investor client was developed by CELESC, linking the sale resources to one generation construction. It was related the cost of enlargement work from Pery plant, with the participation of Manville Forest Products in the investments. The economic aspects of this contract are presented, including the supply assure, the costs and the advantage each company will receive. (C.G.C.)

  11. Marketing strategic choice for wind power technology in China : case: Chinese domestic wind technology companies

    OpenAIRE

    Shi, Yi

    2011-01-01

    There are almost 80 wind turbine manufacturers in China. However, the supportive government policies are the fact behind the rapid growth of those case companies. In reality, there are less than 10 Chinese wind turbine manufacturers with actual production capacity. Most of them lack core technology and depend in many ways on state patronage. The current situation is worrisome. Therefore, the correct comprehension of wind power market conditions and the consequent adoption of right marketing s...

  12. The MISO Wiretap Channel with Noisy Main Channel Estimation in the High Power Regime

    KAUST Repository

    Rezki, Zouheir

    2017-02-07

    We improve upon our previous upper bound on the secrecy capacity of the wiretap channel with multiple transmit antennas and single-antenna receivers, with noisy main channel state information (CSI) at the transmitter (CSI-T). Specifically, we show that if the main CSI error does not scale with the power budget at the transmitter P̅, then the secrecy capacity is )bounded above essentially by log log (P̅ yielding a secure degree of freedom (sdof) equal to zero. However, if the main CSI error scales as O(P̅-β), for β ∈ [0,1], then the sdof is equal to β.

  13. The MISO Wiretap Channel with Noisy Main Channel Estimation in the High Power Regime

    KAUST Repository

    Rezki, Zouheir; Chaaban, Anas; Alomair, Basel; Alouini, Mohamed-Slim

    2017-01-01

    We improve upon our previous upper bound on the secrecy capacity of the wiretap channel with multiple transmit antennas and single-antenna receivers, with noisy main channel state information (CSI) at the transmitter (CSI-T). Specifically, we show that if the main CSI error does not scale with the power budget at the transmitter P̅, then the secrecy capacity is )bounded above essentially by log log (P̅ yielding a secure degree of freedom (sdof) equal to zero. However, if the main CSI error scales as O(P̅-β), for β ∈ [0,1], then the sdof is equal to β.

  14. Power law of distribution of emergency situations on main gas pipeline

    Science.gov (United States)

    Voronin, K. S.; Akulov, K. A.

    2018-05-01

    The article presents the results of the analysis of emergency situations on a main gas pipeline. A power law of distribution of emergency situations is revealed. The possibility of conducting further scientific research to ensure the predictability of emergency situations on pipelines is justified.

  15. High resolution ADC interface to main magnet power supply at the NSLS

    Energy Technology Data Exchange (ETDEWEB)

    Bordoley, M.

    1993-07-01

    Previous readings of DCCT were limited to 11 bits of resolution with large offsets and drifts, providing inaccurate data. The current design overcomes this limitation by using Analog Device`s AD7703 20 bit serial output ADC to digitize the main magnet DCCT at the power supply, and transmit the data serially at 2KHz over to the VME controller.

  16. High resolution ADC interface to main magnet power supply at the NSLS

    Energy Technology Data Exchange (ETDEWEB)

    Bordoley, M.

    1993-01-01

    Previous readings of DCCT were limited to 11 bits of resolution with large offsets and drifts, providing inaccurate data. The current design overcomes this limitation by using Analog Device's AD7703 20 bit serial output ADC to digitize the main magnet DCCT at the power supply, and transmit the data serially at 2KHz over to the VME controller.

  17. High resolution ADC interface to main magnet power supply at the NSLS

    International Nuclear Information System (INIS)

    Bordoley, M.

    1993-01-01

    Previous readings of DCCT were limited to 11 bits of resolution with large offsets and drifts, providing inaccurate data. The current design overcomes this limitation by using Analog Device's AD7703 20 bit serial output ADC to digitize the main magnet DCCT at the power supply, and transmit the data serially at 2KHz over to the VME controller

  18. Atoms

    International Nuclear Information System (INIS)

    Fuchs, Alain; Villani, Cedric; Guthleben, Denis; Leduc, Michele; Brenner, Anastasios; Pouthas, Joel; Perrin, Jean

    2014-01-01

    Completed by recent contributions on various topics (atoms and the Brownian motion, the career of Jean Perrin, the evolution of atomic physics since Jean Perrin, relationship between scientific atomism and philosophical atomism), this book is a reprint of a book published at the beginning of the twentieth century in which the author addressed the relationship between atomic theory and chemistry (molecules, atoms, the Avogadro hypothesis, molecule structures, solutes, upper limits of molecular quantities), molecular agitation (molecule velocity, molecule rotation or vibration, molecular free range), the Brownian motion and emulsions (history and general features, statistical equilibrium of emulsions), the laws of the Brownian motion (Einstein's theory, experimental control), fluctuations (the theory of Smoluchowski), light and quanta (black body, extension of quantum theory), the electricity atom, the atom genesis and destruction (transmutations, atom counting)

  19. Advance of technological innovations of electric power in 2012

    International Nuclear Information System (INIS)

    Mayumi, Akihiko; Tanaka, Masanori; Takebe, Toshiro

    2013-01-01

    Twelve companies in Japan reported on the technological innovations in 2012. The Japan Atomic Power Company mainly studied five projects; (1) control of wall thinning of the secondary system in PWR by injection of molybdic acid, (2) application of pipe test method using electromagnetic acoustic resonance to existing equipment, (3) developed high performance Co-60 crud removal resin for Tsuruga Power Station Unit 2, (4) improvement of technology for safety of core in FBR, and (5) improvement of technology for coolant of FBR by dispersing nano-particles in liquid sodium metal. Tokyo Electric Power Company developed mainly three projects; (1) the support for the mental health care activities by industry protection staff at the Fukushima Daiichi and Daini Nuclear Power Plant, (2) laboratory test method using non-radioactive cesium for performance of decontamination reagent, and (3) decontamination effects estimation code (DeConEP). Hokuriku Electric Power Company reported the operations management measures in accordance with the safety enhancement measures to Shika nuclear power station. Other nine reports are published by Hokkaido Electric Power Co., Inc. Tohoku Electric Power Co., Inc. Chubu Electric Power Co., Inc., The Kansai Electric Power Co., Inc., The Chugoku Electric Power Co., Inc., Shikoku Electric Power Co., Inc., Kyushu Electric Power Co., Inc., Okinawa Electric Power Company Inc. and J-Power. (S.Y.)

  20. The law governing power generation and the atomic energy law in Japan, with special regard to the current situation in the energy sector

    International Nuclear Information System (INIS)

    Fujiwara, J.

    1984-01-01

    This contribution characterises Japanese legislation on power generation and supply, goes into detail with regard to the current Atomic Energy Law within the framework of the overall legal concept governing power supply, and presents an outlook on future developments. A table summarizes the main problems in this field. (orig./HSCH) [de

  1. Sandia high-power atomic iodine photodissociation laser

    International Nuclear Information System (INIS)

    Palmer, R.E.; Padrick, T.D.

    1975-01-01

    One of the more promising candidates for a laser to demonstrate the feasibility of laser fusion is the 1.315 μ atomic iodine laser. In a relatively short time it has been developed into a viable subnanosecond, high energy laser. Although at present the iodine laser cannot equal the output capabilities of a large Nd:glass laser system, there are no foreseeable obstacles in the construction of a 100 psec, 10 KJ or greater atomic iodine laser system. A 100 joule system being constructed at Sandia to investigate many of the scaling parameters essential to the design of a 10 KJ or greater system is described. (U.S.)

  2. Nuclear Reactors for Space Power, Understanding the Atom Series.

    Science.gov (United States)

    Corliss, William R.

    The historical development of rocketry and nuclear technology includes a specific description of Systems for Nuclear Auxiliary Power (SNAP) programs. Solar cells and fuel cells are considered as alternative power supplies for space use. Construction and operation of space power plants must include considerations of the transfer of heat energy to…

  3. Main Power Distribution Unit for the Jupiter Icy Moons Orbiter (JIMO)

    Science.gov (United States)

    Papa, Melissa R.

    2004-01-01

    Around the year 2011, the Jupiter Icy Moons Orbiter (JIMO) will be launched and on its way to orbit three of Jupiter s planet-sized moons. The mission goals for the JIMO project revolve heavily around gathering scientific data concerning ingredients we, as humans, consider essential: water, energy and necessary chemical elements. The JIM0 is an ambitious mission which will implore propulsion from an ION thruster powered by a nuclear fission reactor. Glenn Research Center is responsible for the development of the dynamic power conversion, power management and distribution, heat rejection and ION thrusters. The first test phase for the JIM0 program concerns the High Power AC Power Management and Distribution (PMAD) Test Bed. The goal of this testing is to support electrical performance verification of the power systems. The test bed will incorporate a 2kW Brayton Rotating Unit (BRU) to simulate the nuclear reactor as well as two ION thrusters. The first module of the PMAD Test Bed to be designed is the Main Power Distribution Unit (MPDU) which relays the power input to the various propulsion systems and scientific instruments. The MPDU involves circuitry design as well as mechanical design to determine the placement of the components. The MPDU consists of fourteen relays of four different variations used to convert the input power into the appropriate power output. The three phase system uses 400 Vo1ts(sub L-L) rms at 1000 Hertz. The power is relayed through the circuit and distributed to the scientific instruments, the ION thrusters and other controlled systems. The mechanical design requires the components to be positioned for easy electrical wiring as well as allowing adequate room for the main buss bars, individual circuit boards connected to each component and power supplies. To accomplish creating a suitable design, AutoCAD was used as a drafting tool. By showing a visual layout of the components, it is easy to see where there is extra room or where the

  4. Evaluating perceived quality of CELPE service: A Brazilian power company case study

    International Nuclear Information System (INIS)

    Paes de Barros Filho, Joao; Fritsch Damasio da Silva, Cleriston; Nascimento Melo, Maria Auxiliadora do; Dumke de Medeiros, Denise

    2009-01-01

    This paper presents an application of a methodology for the diagnosis and analysis of the service quality perceived by a Particular Group of CELPE Corporate Customers, a Brazilian power company at Pernambuco State. Concepts, on the power sector, of Quality in Services, Performance Objectives and Critical Factors of Success have been used to develop the analysis. Next, the Critical Factors for a power company were determined and classified in accordance with the performance objectives: Quality, Dependability, Speed and Flexibility. From the factors established, a questionnaire was created to collect data. The case studied involves quantitative research on CELPE's private corporate principal customers using statistical tests to measure internal consistency reliability of the questionnaire scales and to identify underlying concepts, in the four groups analyzed, through which the private corporate customers perceive quality in the given services. Among the goals of this study are to improve the relationship with principal Private Corporate Clients, to create customer loyalty, and to maximize efforts in providing the power supply service, all of them with a view to improving and determining the Global Satisfaction Index

  5. Evaluating perceived quality of CELPE service: A Brazilian power company case study

    Energy Technology Data Exchange (ETDEWEB)

    Paes de Barros Filho, Joao [Federal University of Pernambuco (UFPE), Center of Technology and Geosciences, 5th floor, Academico Helio Ramos av., Cidade Universitaria, Recife, PE 50.670-901 (Brazil)], E-mail: joaopaes@celpe.com.br; Fritsch Damasio da Silva, Cleriston [Federal University of Pernambuco (UFPE), Center of Technology and Geosciences, 5th floor, Academico Helio Ramos av., Cidade Universitaria, Recife, PE 50.670-901 (Brazil)], E-mail: cleriston_silva@yahoo.com.br; Nascimento Melo, Maria Auxiliadora do [Federal University of Pernambuco (UFPE), Center of Technology and Geosciences, 5th floor, Academico Helio Ramos av., Cidade Universitaria, Recife, PE 50.670-901 (Brazil)], E-mail: manmelo@ufpe.br; Dumke de Medeiros, Denise [Federal University of Pernambuco (UFPE), Center of Technology and Geosciences, 5th floor, Academico Helio Ramos av., Cidade Universitaria, Recife, PE 50.670-901 (Brazil)], E-mail: ddm@ufpe.br

    2009-04-15

    This paper presents an application of a methodology for the diagnosis and analysis of the service quality perceived by a Particular Group of CELPE Corporate Customers, a Brazilian power company at Pernambuco State. Concepts, on the power sector, of Quality in Services, Performance Objectives and Critical Factors of Success have been used to develop the analysis. Next, the Critical Factors for a power company were determined and classified in accordance with the performance objectives: Quality, Dependability, Speed and Flexibility. From the factors established, a questionnaire was created to collect data. The case studied involves quantitative research on CELPE's private corporate principal customers using statistical tests to measure internal consistency reliability of the questionnaire scales and to identify underlying concepts, in the four groups analyzed, through which the private corporate customers perceive quality in the given services. Among the goals of this study are to improve the relationship with principal Private Corporate Clients, to create customer loyalty, and to maximize efforts in providing the power supply service, all of them with a view to improving and determining the Global Satisfaction Index.

  6. Evaluating perceived quality of CELPE service. A Brazilian power company case study

    Energy Technology Data Exchange (ETDEWEB)

    De Barros Filho, Joao Paes; Da Silva, Cleriston Fritsch Damasio; Do Nascimento Melo, Maria Auxiliadora; De Medeiros, Denise Dumke [Federal University of Pernambuco (UFPE), Center of Technology and Geosciences, 5th floor, Academico Helio Ramos av., Cidade Universitaria, Recife, PE 50.670-901 (Brazil)

    2009-04-15

    This paper presents an application of a methodology for the diagnosis and analysis of the service quality perceived by a Particular Group of CELPE Corporate Customers, a Brazilian power company at Pernambuco State. Concepts, on the power sector, of Quality in Services, Performance Objectives and Critical Factors of Success have been used to develop the analysis. Next, the Critical Factors for a power company were determined and classified in accordance with the performance objectives: Quality, Dependability, Speed and Flexibility. From the factors established, a questionnaire was created to collect data. The case studied involves quantitative research on CELPE's private corporate principal customers using statistical tests to measure internal consistency reliability of the questionnaire scales and to identify underlying concepts, in the four groups analyzed, through which the private corporate customers perceive quality in the given services. Among the goals of this study are to improve the relationship with principal Private Corporate Clients, to create customer loyalty, and to maximize efforts in providing the power supply service, all of them with a view to improving and determining the Global Satisfaction Index. (author)

  7. Concept of electric power output control system for atomic power generation plant utilizing cool energy of stored snow

    International Nuclear Information System (INIS)

    Kamimura, Seiji; Toita, Takayuki

    2003-01-01

    A concept of the SEAGUL system (Snow Enhancing Atomic-power Generation UtiLity) is proposed in this paper. Lowering the temperature of sea water for cooling of atomic-power plant will make a efficiency of power generation better and bring several ten MW additional electric power for 1356 MW class plant. The system concept stands an idea to use huge amount of seasonal storage snow for cooling water temperature control. In a case study for the Kashiwazaki-Kariwa Nuclear Power Station, it is estimated to cool down the sea water of 29degC to 20degC by 80 kt snow for 3 hours in a day would brought 60 MWh electric power per a day. Annually 38.4 Mt of stored snow will bring 1800 MWh electric power. (author)

  8. Compact, Low-Power Atomic Time and Frequency Standards

    Science.gov (United States)

    2008-12-01

    2007). This is consistent with other reports of survival of CSAC devices with thin polymide tethers to 500g ( Lutwak et al., 2007). • Humidity...InterPACK 󈧋 , July 8-12, 2007, Vancouver, British Columbia, CANADA Lutwak , R., et al., “The chip-scale atomic clock – prototype evaluation

  9. The low-temperature water-water reactor for district heating atomic power plant (DHPP)

    International Nuclear Information System (INIS)

    Skvortsov, S.A.; Sokolov, I.N.; Krauze, L.V.; Nikiporetz, Yu.G.; Philimonov, Yu.V.

    1977-01-01

    The district heating atomic power plant in the article is distinguished by the increased reliability and safety of operation that was provided by the use of following main principles: relatively low parameters of the coolant; the intergral arrangement of equipment and accordingly the minimum branching of the reactor circuit; the natural circulation of coolant of the primary circuit in the steady-state, transient and emergency regimes of reactor operation; the considerable reserves of cold water of the primary circuit in the reactor vessel, providing the emergency cooling; the application of two shells each of which is designed for the total working pressure, the second shell is made of prestressed reinforced concrete that eliminates its brittle failure. (M.S.)

  10. Purification of ammonia-containing trap waters from atomic power plant by ozone treatment

    International Nuclear Information System (INIS)

    Grachok, M.A.; Prokudina, S.A.; Shulyat'ev, M.I.

    1990-01-01

    The aim of research was to study the process of ozonation of ammonia-containing trap waters from the Kursk Atomic Power Plant both on the model solutions and on real ones. Different factors (pH of the medium, temperature, concentration of the initial substances) have been studied for their effect on ozonation of aqueous ammonia solutions, model solutions of trap waters from the Kursk Atomic Power Plant as well as ammonia-containing trap waters and liquid radioactive wastes delivered to special water treatment at the Kursk Atomic Power Plant. It is shown that in all the cases the highest rate of ammonia oxidation by ozone is observed in the alkaline medium (pH 1.4-11.0) and at 55 deg C. The obtained results have shown that a method of ozonation followed by evaporation of water to be purified can be used to treat ammonia-containing waters from atomic power plant

  11. Audible Noise Measurement and Analysis of the Main Power Apparatus in UHV GIS Substations

    Directory of Open Access Journals (Sweden)

    Zhou Nian Guang

    2016-01-01

    Full Text Available Investigation of audible noise characteristics of the main power apparatus in UHV GIS substations provides essential statistics for the noise prediction and control. Noise pressure level, spectrum and attenuation characteristics of the main transformers and high voltage (HV reactors are measured and analyzed in this paper. The result shows that the main transformer and HV reactor have identical A-weighted equivalent sound pressure level. The medium- and low-frequency noises are the primary components in the spectral. More attention should be paid to the low-frequency bands in the noise control process. The noise of cooling fan has a large influence on that of the main transformer. Without the consideration of corona noise, the average A-weighted sound pressure level shows an overall decreasing trend with the increase of the propagation distance. Obvious interference phenomenon of the noises at 100 and 200Hz exists in the noise propagation process.

  12. The main features of control and operation of steam turbines at nuclear power plants

    International Nuclear Information System (INIS)

    Czinkoczky, B.

    1981-01-01

    The output and speed control of steam turbines at nuclear power plants as well as the combination of both controls are reviewed and evaluated. At the same time the tasks of unit control at nuclear power plants, the control of steady main steam pressure and medium pressure of primary circuit, further the connection of reactor and turbine controls and the self-controlling properties of pressurized water reactor are dealt with. Hydraulic and electro-hydraulic speed control, the connection of cach-up dampers and speed control and the application of electro-hydraulic signal converters are discussed. The accomplishment of protection is also described. (author)

  13. Examination of turbine discs from nuclear power plants

    International Nuclear Information System (INIS)

    Czajkowski, C.J.; Weeks, J.R.

    1982-01-01

    Investigations were performed on a cracked turbine disc from the Cooper Nuclear Power Station, and on two failed turbine discs (governor and generator ends) from the Yankee-Rowe Nuclear Power Station. Cooper is a boiling water reactor (BWR) which went into commercial operation in July 1974, and Yankee-Rowe is a pressurized water reactor (PWR) which went into commercial operation in June 1961. Cracks were identified in the bore of the Cooper disc after 41,913 hours of operation, and the disc removed for repair. At Yankee-Rowe two discs failed after 100,000 hours of operation. Samples of the Cooper disc and both Yankee-Rowe disc (one from the governor and one from the generator end of the LP turbine) were sent to Brookhaven National Laboratory (BNL) for failure analysis

  14. Modification of reactor installation in the Genkai nuclear power plant No. 1 of Kyushu Electric Power Company, Inc

    International Nuclear Information System (INIS)

    1979-01-01

    The Nuclear Safety Commission recognized the adequacy concerning the inquiry which was offered from the Minister of International Trade and Industry on July 25, 1979, following the safety evaluation in the Ministry of International Trade and Industry, and decided to submit a report to the Minister of International Trade and Industry on July 26, 1979, about the modification of reactor installation in the Genkai nuclear power plant No. 1 of the Kyushu Electric Power Company, Inc. This is concerned to the application which was made from the president of the Kyushu Electric Power Company, Inc., to the Minister of International Trade and Industry on July 24, 1979. The content of the modification is to add a control circuit which is actuated by the signal of abnormal low pressure in a reactor to the circuit of actuating the emergency core cooling system of the plant. The influences on the safety protection system by the addition of the circuit transmitting safety injection signal and by the additions of an interlock circuit preventing the misoperation of pressurizer spray and of a block circuit of safety injection signal in case of the abnormal low pressure in a reactor were evaluated. The effects on the function and characteristics of the emergency core cooling system due to the addition of the control circuit were investigated, and it was recognized by the analysis that there is no effect in the pipe ruptures of both small and large scales. (Nakai, Y.)

  15. Policy planning for nuclear power: an overview of the main issues and requirements

    International Nuclear Information System (INIS)

    1995-05-01

    The report contains information on the political, governmental, economic, financial and technical issues and requirements associated with planning and implementing a safe, economic and reliable nuclear power programme. It highlights the main areas in which policies must be developed and decisions taken, as well as the role and responsibilities of government, the plant owner and national industry. Also presented are the main criteria to assist policy planners in defining options and strategies which can achieve a balance among such objectives as cost effective and efficient electricity production, realistic and acceptable financing arrangements, national development requirements, safety and environmental protection. (NHA)

  16. Validation study on reliability analysis of main safety system in Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Nam Jin; Cho, Chang Keun; Kim, Yong Hui; Kim, Tae Hyeong; Hong, Seo Kee; Park, Keon Woo; Park, Chang Jea [Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of); Cheong, Woo Sik [Institute for Advanced Engineering, Yongin (Korea, Republic of); Park, Moon Kyu [KEPRI, Taejon (Korea, Republic of)

    1993-12-15

    The scope and contents of this validation study are to review the design changes of the four main safety systems in Wolsong 2/3/4 Nuclear Power Plants, to review the consideration of the above design changes in the AECL reports, the structure of fault trees, and the data base used in the quantification of the fault trees, to quantify the unavailabilities of main safety systems and check them if they meet the requirements, and to recommend desirable design changes in the emergency core cooling system to reduce the unavailability.

  17. In-service diagnostics of main circulating circuit pipes of WWER nuclear power plants

    International Nuclear Information System (INIS)

    Svoboda, V.; Merta, J.; Merta, V.

    1982-01-01

    The application is discussed of the acoustic emission method for testing the integrity of the components of the main circulating circuit of the WWER 440 nuclear power plant. A description is given of the main circulating circuit and a stress analysis on the basis of strength computations considering operating modes is presented. An analysis is also presented of the possible damage of the pipe material as related to the application of the acoustic emission method for in-service inspection of the pipes. Certain practical problems of application are discussed. (author)

  18. Education of engineers at the Atomic Power Institute in Obninsk

    International Nuclear Information System (INIS)

    Korolev, V.V.; Sereda, G.A.

    1982-01-01

    The curriculum development for specific specializations proceeds from the operating functions of the specialist in the power plant, the tasks which he will have to fulfil and their linkage with the final objective of power plant operation, namely to secure reliable power production. The curricula for each year of study are specified. It appears that a specialized institution of higher education and its material and technical equipment and a method of instruction which maximally meets the demands of practice, form the basic preconditions for training skilled personnel for nuclear power production. (J.P.)

  19. Inquiry relating to modifications of reactor installation in Genkai No. 1 and 2 nuclear power plants of Kyushu Electric Power Company, Inc

    International Nuclear Information System (INIS)

    1979-01-01

    Application was made to the Minister of International Trade and Industry for the license relating to the modifications of reactor installation in the Genkai No. 1 and 2 nuclear power plants, Kyushu Electric Power Company, Inc., on February 27, 1979, from the president of the company. After the safety evaluation was finished by the Ministry of International Trade and Industry, inquiry was conducted to the head of the Atomic Energy Safety Commission (AESC) on June 15, 1979 from the Minister of International Trade and Industry. The investigation and discussion were commenced by the AESC on June 19, 1979. The modifications of the reactor installation are the increase of new fuel storage capacity from about 1/3 to about 2/3 of in-core fuel for each plant, the new establishment of a miscellaneous solid waste incinerator which is common to both plants, and the enlargement of a solid waste storage which is also common to both plants. The contents of the safety examination for each item written above are presented. The prevention of criticality is carefully practiced for the new fuel storage by putting fuel assemblies in stainless steel can type racks and locating the fuel assemblies at the proper distance. The miscellaneous solid waste incinerator building is designed as the B class aseismatic structure and also as the controlled area with adequate shielding and ventilating facilities. The decontamination factor of the incinerator facility is more than 10 5 , and the necessary monitoring system is provided in the building. Concerning the solid waste storage, the additional storage area is about 1600 m 2 , and the storage capacity is about ten years quantity. This building is designed as the B class aseismatic structure. (Nakai, Y.)

  20. A study of public acceptance of construction of atomic power plant

    International Nuclear Information System (INIS)

    Harada, Kazunori; Matsuhashi, Ryuji; Yoshida, Yoshikuni

    2011-01-01

    In June 2010, Basic Energy Plan was approved in a Cabinet meeting. It says that Japan aims to construct more than 14 atomic power plants by 2030. Today, there are 12 plans of construction of atomic power plant, but it is hard to say that their plans easily come off. That's because public acceptance of atomic power plant is low in Japan, for example local residents wage opposition campaigns. This study conducts a survey in the form of a questionnaire and analyzes it by Analytical Hierarchical Process (AHP). Analytic Hierarchy Process is a structured technique for dealing with complex decisions. A questionnaire using AHP is very easy to answer and analyze. This survey was conducted in 2 areas. First area is Hohoku-cho, Yamaguchi Pref. that had a plan of construction of atomic power plant and the plan was demolished by opposition campaigns. Second area is Kaminoseki-cho, Yamaguchi Pref. that has a plan of construction of atomic power plant now and the plan is working order. Public acceptance can be calculated from survey data of 2 areas, and it helps to understand why first area disapproved a plan of atomic power plant and second area approves it. We consider a model to analyze public acceptance. (author)

  1. Digitized operator evaluation system for main control room of nuclear power plant

    International Nuclear Information System (INIS)

    Chen Yu; Yan Shengyuan; Chen Wenlong

    2014-01-01

    In order to evaluate the human-machine system matching relation of main control room in nuclear power plant accurately and efficiently, the expression and parameters of operator human body model were analyzed, and the evaluation required function of digital operator was determined. Based on the secondary development technology, the digital operator evaluation body model was developed. It could choose generation, gender, operation posture, single/eyes horizon, and left/right hand up to the domain according to the needs of specific evaluation, it was used to evaluate whether display information can be visible and equipment can be touch, and it also has key evaluation functions such as workspace and character visibility at the same time. The examples show that this method can complete the evaluation work of human-machine matching relation for main control room of nuclear power plant accurately, efficiently and quickly, and achieve the most optimal human-machine coordination relationship. (authors)

  2. The New Control and Interlock System for the SPS Main Power Converters

    CERN Document Server

    Denis, B; Mugnier, C; Varas, J

    1999-01-01

    The Control and Interlock System (CIS) of the SPS main power converters was designed in the mid-70s and became increasingly difficult to maintain. A new system based on Programmable Logic Controllers has been developed by an external contractor in close collaboration with CERN. The system is now operational and fully integrated in the SPS/LEP control infrastructure. The CIS is the first major contracted industrial solution used to control accelerator equipment directly involved in the production of particle beams at CERN. This paper gives an overview of the SPS main power converter installation and describes both the contractual and technical solution adopted for the CIS. It first explains how the system was specified and how the contractual relationship was defined to respect CERN’s purchasing rules and the operational requirements of the SPS accelerator. The architectural design of the new system is presented with special emphasis on how the conflict between safety and availability has been addressed.

  3. The main steps of the Romanian nuclear power program development - Accumulated experience

    International Nuclear Information System (INIS)

    Chirica, T.; Popescu, D.; Condu, M.; Vatamanu, M.

    1998-01-01

    The paper presents a historical summary of the Romanian Nuclear Power Program development, providing details for the main criteria and principles the Program was based upon, the contracts signed with the foreign partners to implement it, and the national participation (site contractors, suppliers and design organizations). The effect of the equipment assimilation program on the NPP Cernavoda (5x700 MWe) and especially on Unit 1 schedule and performance is analyzed. Further on the impact of the transition from centralized to a market economy over the Romanian Nuclear Power Program development is analyzed, providing information's on its actual status and perspectives for the next 20 years. A description of the NPP Cernavoda Unit 1 actual progress and of the main steps performed by RENEL to get finance to complete NPP Cernavoda Unit 2 is included. Finally there is summarized the accumulated experience, and its feed back on RENEL strategy to complete NPP Cernavoda Unit 2. (author)

  4. Re-Examining first principles of regulation: NRG power marketing, LLC v. Maine public utilities Commission

    Energy Technology Data Exchange (ETDEWEB)

    Haskell, Mark R.

    2010-03-15

    Maine PUC and Morgan Stanley have resolved some of the key issues facing the energy industry. The Supreme Court has plainly and directly in both cases reaffirmed the central role that private contracts play in the energy industry and set terms to balance the need to secure long-term investment with the public interest that lies at the heart of the Federal Power Act. (author)

  5. Main lessons based on the Chernobyl nuclear power plant accident liquidation experience

    International Nuclear Information System (INIS)

    Vasil'chenko, V.N.; Nosovskij, A.V.

    2006-01-01

    The authors review the main lessons of the Chernobyl nuclear power plant accident and the liquidation of its consequences in the area of the nuclear reactors safety operation, any major accident management, liquidation accident consequences criteria, emergency procedures, preventative measures and treatment irradiated victims, the monitoring methods etc. The special emphasis is put on the questions of the emergency response and the antiaccidental measures planning in frame of international cooperation program

  6. The active filter voltage ripple correction system of the Brookhaven AGS main magnet power supply

    International Nuclear Information System (INIS)

    Marneris, I.; Bonati, R.; Geller, J.; Sandberg, J.N.; Soukas, A.

    1995-01-01

    This paper, and a companion paper, describe the improvements to the Main Magnet Power Supply (MMPS) so that it enables a more flexible operation of the AGS, enhances its reliability, and also improves the MMPS's ultimate performance specifications. One of the major areas for the latter is the fixed target program operating off the AGS slow extracted beam lines. The active filter, by improving the MMPS output ripple, is instrumental in the improvement of the ultimate duty factor of the extraction beam spill

  7. OVERVIEW OF A RECONFIGURABLE SIMULATOR FOR MAIN CONTROL ROOM UPGRADES IN NUCLEAR POWER PLANTS

    Energy Technology Data Exchange (ETDEWEB)

    Ronald L. Boring

    2012-10-01

    This paper provides background on a reconfigurable control room simulator for nuclear power plants. The main control rooms in current nuclear power plants feature analog technology that is growing obsolete. The need to upgrade control rooms serves the practical need of maintainability as well as the opportunity to implement newer digital technologies with added functionality. There currently exists no dedicated research simulator for use in human factors design and evaluation activities for nuclear power plant modernization in the U.S. The new research simulator discussed in this paper provides a test bed in which operator performance on new control room concepts can be benchmarked against existing control rooms and in which new technologies can be validated for safety and usability prior to deployment.

  8. 77 FR 13156 - Carolina Power & Light Company; Shearon Harris Nuclear Power Plant, Unit 1; Exemption

    Science.gov (United States)

    2012-03-05

    ... generation, and cladding oxidation from the metal/water reaction shall be calculated using the Baker-Just... boiling or pressurized light-water nuclear power reactor fueled with uranium oxide pellets within... spring 2012. The AREVA fuel design consists of low enriched uranium oxide fuel within M5 \\TM\\ zirconium...

  9. Policy planning for nuclear power: An overview of the main issues and requirements

    International Nuclear Information System (INIS)

    1993-08-01

    This special report, Policy Planning for Nuclear Power: An Overview of the Main Issues and Requirements, has been prepared in response to the express request of a number of IAEA Member States for a document to assist makers in developing countries on the introduction of nuclear power. The report contains information on the political, governmental, economic, financial and technical issues and requirements associated with planning and implementing a safe, economic and reliable nuclear power programme. It highlights the main areas in which policies must be developed and decisions taken, as well as the role and responsibilities of government, the plant owner and national industry. Also presented are the main criteria to assist policy planners in defining options and strategies which can achieve a balance among such objectives as cost effective and efficient electricity production, realistic and acceptable financing arrangements, national development requirements, safety and environmental protection. Further information and details on the technical and other issues presented in this report are given in the list of related IAEA publications and documents at the end of this report

  10. 76 FR 25330 - Georgia Power Company; Project No. 485-063-Georgia and Alabama, Bartletts Ferry Hydroelectric...

    Science.gov (United States)

    2011-05-04

    ... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission Georgia Power Company; Project No. 485-063--Georgia and Alabama, Bartletts Ferry Hydroelectric Project; Notice of Proposed Restricted Service... Ferry Hydroelectric Project. The Programmatic Agreement, when executed by the Commission, the Georgia...

  11. Atom for peace, code for war. The technology policy of the atomic power solution in Finland between 1955-1970

    International Nuclear Information System (INIS)

    Sarkikoski, T.

    2011-01-01

    This dissertation investigates the atomic power solution in Finland between 1955 - 1970. During these years a national arrangement for atomic energy technology evolved. The foundations of the Finnish atomic energy policy; the creation of basic legislation and the first governmental bodies, were laid between 1955 - 1965. In the late 1960's, the necessary technological and political decisions were made in order to purchase the first commercial nuclear reactor. A historical narration of this process is seen in the international context of 'atoms for peace' policies and Cold War history in general. The geopolitical position of Finland made it necessary to become involved in the balanced participation in international scientific-technical exchange and assistive nuclear programs. The Paris Peace Treaty of 1947 categorically denied Finland acquisition of nuclear weapons. Accordingly, from the 'Geneva year' of 1955, the emphasis was placed on peaceful purposes for atomic energy as well as on the education of national professionals in Finland. An initiative for the governmental atomic energy commission came from academia but the ultimate motive behind it was an anticipated structural change in the supply of national energy. Economically exploitable hydro power resources were expected to be built within ten years and atomic power was seen as a promising and complementing new energy technology. While importing fuels like coal was out of the question, because of scarce foreign currency, domestic uranium mineral deposits were considered as a potential source of nuclear fuel. Nevertheless, even then nuclear energy was regarded as just one of the possible future energy options. In the mid-1960 s a bandwagon effect of light water reactor orders was witnessed in the United States and soon elsewhere in the world. In Finland, two separate invitations for bids for nuclear reactors were initiated. This study explores at length both their preceding grounds and later phases. An

  12. Advance in technologies of electric power in 2008

    International Nuclear Information System (INIS)

    Hamada, Kenichi; Maekawa, Fumiaki; Nakamura, Akio

    2008-01-01

    Ten electric power companies and two related companies reported their advance in technologies. The technologies of nuclear power plants were stated by ten companies, which consisted of introduction of new main control board to Tomari-3 in Hokkaido Electric Power Co., Inc., reduction methods of exposure dose of Higashidori-1 in Tohoku Electric Power, hot water based two-phase flow testing device for pipe thinning test by Tokyo Electric Power Company, Guideline for prevention of piping damage caused by combustion of mixture gases in BWR (the second edition) published by Thermal and Nuclear Power Engineering Society, setting up distributor in the low-pressure turbine of Shika-2 in Hokuriku Electric Power Company, development of rapid estimation method of release radioactivity and application of high density neutron source to nuclear transmutation of nuclear fuel cycle and introduction of new core monitor system by The Kansai Electric Power Co., Inc., upgrade of investigation of the effects of hot waste water and development of detector for dropout parts of cooling system in reactor by Shikoku Electric Power Co., Inc., change of transformer in Sendai-1 by Kyushu Electric Power Co., Inc., and reactor core design for Oma ABWR by J-Power. The Japan Atomic Power Company reported four articles such as development of technologies for established nuclear power plants, promotion of Tsuruga-3 and Tsuruga-4, application of clearance system in Japan and development of future reactors. (S.Y.)

  13. Analysis and application of advanced fuel management strategies at Florida Power and Light Company

    International Nuclear Information System (INIS)

    Knuckles, E.R.; Mantyh, J.D.; Hoskins, K.C.

    1986-01-01

    Reload design flexibility is the degree of freedom that the fuel management engineer has in utilizing various options to achieve and maintain an optimal core design. The major factors affecting flexibility are the basic design constraints, fuel design, and operational and regulatory uncertainty. The degree of flexibility available to the engineer can be improved through an understanding of the inter-relationship of these factors. Specific examples are used to demonstrate how the concept of flexibility has been implemented at Florida Power and Light Company

  14. Value of solar thermal and photovoltaic power plants to Arizona Public Service Company

    International Nuclear Information System (INIS)

    Smith, P.A.

    1994-01-01

    Arizona Public Service Company has performed a study using historical solar radiation and system load data to (1) estimate the effects of six types of solar generation on system reliability, (2) estimate the central station value of each to its system, (3) and to assess the potential of each of those technologies to provide bulk power to its system in the 2000 time frame. Technologies included three solar thermal (central receiver, dish Stirling, and parabolic trough) and three flat plate photovoltaic plants (fixed position, one axis, and two axis tracking)

  15. Derivation of main drivers affecting the possibility of human errors during low power and shutdown operation

    International Nuclear Information System (INIS)

    Kim, Ar Ryum; Seong, Poong Hyun; Park, Jin Kyun; Kim, Jae Whan

    2016-01-01

    In order to estimate the possibility of human error and identify its nature, human reliability analysis (HRA) methods have been implemented. For this, various HRA methods have been developed so far: techniques for human error rate prediction (THERP), cause based decision tree (CBDT), the cognitive reliability and error analysis method (CREAM) and so on. Most HRA methods have been developed with a focus on full power operation of NPPs even though human performance may more largely affect the safety of the system during low power and shutdown (LPSD) operation than it would when the system is in full power operation. In this regard, it is necessary to conduct a research for developing HRA method to be used in LPSD operation. For the first step of the study, main drivers which affect the possibility of human error have been developed. Drivers which are commonly called as performance shaping factors (PSFs) are aspects of the human's individual characteristics, environment, organization, or task that specifically decrements or improves human performance, thus respectively increasing or decreasing the likelihood of human errors. In order to estimate the possibility of human error and identify its nature, human reliability analysis (HRA) methods have been implemented. For this, various HRA methods have been developed so far: techniques for human error rate prediction (THERP), cause based decision tree (CBDT), the cognitive reliability and error analysis method (CREAM) and so on. Most HRA methods have been developed with a focus on full power operation of NPPs even though human performance may more largely affect the safety of the system during low power and shutdown (LPSD) operation than it would when the system is in full power operation. In this regard, it is necessary to conduct a research for developing HRA method to be used in LPSD operation. For the first step of the study, main drivers which affect the possibility of human error have been developed. Drivers which

  16. Derivation of main drivers affecting the possibility of human errors during low power and shutdown operation

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Ar Ryum; Seong, Poong Hyun [KAIST, Daejeon (Korea, Republic of); Park, Jin Kyun; Kim, Jae Whan [KAERI, Daejeon (Korea, Republic of)

    2016-05-15

    In order to estimate the possibility of human error and identify its nature, human reliability analysis (HRA) methods have been implemented. For this, various HRA methods have been developed so far: techniques for human error rate prediction (THERP), cause based decision tree (CBDT), the cognitive reliability and error analysis method (CREAM) and so on. Most HRA methods have been developed with a focus on full power operation of NPPs even though human performance may more largely affect the safety of the system during low power and shutdown (LPSD) operation than it would when the system is in full power operation. In this regard, it is necessary to conduct a research for developing HRA method to be used in LPSD operation. For the first step of the study, main drivers which affect the possibility of human error have been developed. Drivers which are commonly called as performance shaping factors (PSFs) are aspects of the human's individual characteristics, environment, organization, or task that specifically decrements or improves human performance, thus respectively increasing or decreasing the likelihood of human errors. In order to estimate the possibility of human error and identify its nature, human reliability analysis (HRA) methods have been implemented. For this, various HRA methods have been developed so far: techniques for human error rate prediction (THERP), cause based decision tree (CBDT), the cognitive reliability and error analysis method (CREAM) and so on. Most HRA methods have been developed with a focus on full power operation of NPPs even though human performance may more largely affect the safety of the system during low power and shutdown (LPSD) operation than it would when the system is in full power operation. In this regard, it is necessary to conduct a research for developing HRA method to be used in LPSD operation. For the first step of the study, main drivers which affect the possibility of human error have been developed. Drivers

  17. High-inertia hermetically sealed main coolant pump for next generation passive nuclear power plants

    International Nuclear Information System (INIS)

    Kujawski, Joseph M.; Nair, Bala R.; Vijuk, Ronald P.

    2003-01-01

    The main coolant pump for the Westinghouse AP1000 advanced passive nuclear power plant represents a significant scale-up in power, flow capacity, and physical size from its predecessor designed for the smaller AP600 power plant. More importantly, the AP1000 pump incorporates several innovative features that contribute to improved efficiency, operational reliability, and plant safety. The features include an internals design which provides the highest hydraulic efficiency achieved in commercial nuclear power plant applications. Another feature is the use of a distributed inertial mass system in the rotating assembly to develop the high rotational inertia to meet the extended system flow coastdown requirement for core heat removal in the event of loss of power to the pumps. This advanced canned motor pump also incorporates the latest development in higher operating voltage, providing plant designers with the ability to eliminate plant transformers and operate directly on the site electrical bus in many cases. The salient features of the pump design and performance data are presented in this paper. (author)

  18. Ripple characteristic of the main ring magnet power supply for the KEK 12 GeV PS

    International Nuclear Information System (INIS)

    Sato, Hikaru; Sueno, Tuyosi; Mikawa, Katsuhiko

    1995-01-01

    First of all, general description of the main ring magnet power supply for the KEK 12 GeV PS will be described. The main power supply consists of thyristor rectifiers, DC filters, reactive power compensators, AC harmonic filters and control systems. Devices and control systems for suppressing ripple component of magnet field will be described. (author)

  19. Atom

    International Nuclear Information System (INIS)

    Auffray, J.P.

    1997-01-01

    The atom through centuries, has been imagined, described, explored, then accelerated, combined...But what happens truly inside the atom? And what are mechanisms who allow its stability? Physicist and historian of sciences, Jean-Paul Auffray explains that these questions are to the heart of the modern physics and it brings them a new lighting. (N.C.)

  20. Westinghouse Electric Company experiences in chemistry on-line monitoring in Eastern European nuclear power plants

    International Nuclear Information System (INIS)

    Balavage, J.

    2001-01-01

    Westinghouse Electric Company has provided a number of Chemistry On-Line Monitoring (OLM) Systems to Nuclear Power Plants in Eastern Europe. Eleven systems were provided to the Temelin Nuclear Power Plant in the south of the Czech Republic. Four systems were provided to the Russian NPP at Novovoronezh. In addition, a system design was developed for primary side chemistry monitoring for units 5 and 6 of another eastern European VVER. The status of the Temelin OLM systems is discussed including updates to the Temelin designs, and the other Eastern European installations and designs are also described briefly. Some of the problems encountered and lessons learned from these projects are also discussed. (R.P.)

  1. Study of 1 MW neutron source synchrotron dual frequency power circuit for the main ring magnets

    International Nuclear Information System (INIS)

    McGhee, D.G.

    1993-01-01

    This paper describes the proposed design of the resonant power circuits for the 1-MW neutron source synchrotron's main ring magnets. The synchrotron is to have a duty cycle of 30 Hz with a maximum upper limit of operation corresponding to 2.0 GeV and a maximum design value of 2.2 GeV. A stability of 30 ppM is the design goal for the main bending and focusing magnets (dipoles and quadruples), in order to achieve an overall stabffity of 100 ppm when random field and position errors of the magnets are included. The power circuits of this design are similar to those used in Argonne's Intense Pulsed Neutron Source (IPNS) where the energy losses during each cycle are supplied by continuous excitation from modulated multiphase DC power supplies. Since only 50% of the 30-Hz sinewave is used for acceleration, a dual-frequency resonant magnet circuit is used in this design. The 30-Hz repetition rate is maintained with a 20-Hz magnet guide field during acceleration and a 60-Hz reset field when no beam is present. This lengthens the guide-field rise time and shortens the fall time, improving the duty factor for acceleration. The maximum B dot is reduced by 33% during acceleration and hence, the maximum rf voltage/turn is reduced by 56%

  2. An approach for obtaining high availability at Madras Atomic Power Station

    International Nuclear Information System (INIS)

    Subramanian, K.S.; Murthy, K.S.N.; Hariharan, K.

    1977-01-01

    Causes of unavailability of nuclear power plants are described, with special reference to the Madras Atomic Power Plant (MAPP). Design inadequacies, component failures, installation errors, etc. encountered at the MAPP are enumerated. Systems testing followed as well as recruitment and training efforts resorted to are also reported. (K.B.)

  3. Northern States Power Company's open transmission tariff from a customer's perspective

    International Nuclear Information System (INIS)

    Marietta, K.E.; Achinger, S.K.

    1993-01-01

    In October of 1990, Northern States Power Company (NSP or Company), filed a unique open transmission tariff for both captive customers and through-system transactions. This is an important step towards expanding transmission services in the United States. Many individuals in the utility industry, who may be considering Imposing generation costs on transmission services, have been closely monitoring NSP's case which is currently before the Federal Energy Regulatory Commission (FERC). NSP's innovative generation costs include charges for reactive power production, frequency control, load dispatching, and load following. The results of this case may also have an important impact on the future of open transmission tariffs. Rates for these services depend on the customer's classification as either a captive or through-system consumer. The proposed tariff raises critical issues related to the costing of these transmission services. NSP's methodology has caused serious concern because the proposed tariff would increase transmission costs by an average of 53%. This paper will discuss the benefits of transmission, proposed rates, contract terms, and costing methodologies of NSP's plan

  4. Probabilistic safety assessment support for the maintenance rule at Duke Power Company

    International Nuclear Information System (INIS)

    Brewer, H. Duncan; Canady, Ken S.

    1999-01-01

    The Nuclear Regulatory Commission (NRC) published the Maintenance Rule on July 10, 1991 with an implementation date of July 10, 1996 . Maintenance rule implementation at the Duke Power Company has used probabilistic safety assessment (PSA) insights to help focus the monitoring of structures, systems and components (SSC) performance and to ensure that maintenance is effectively performed. This paper describes how the probabilistic risk assessment (PRA) group at the Duke Power Company provides support for the maintenance rule by performing the following tasks: (1) providing a member of the expert panel; (2) determining the risk-significant SSCs; (3) establishing SSC performance criteria for availability and reliability; (4) evaluating past performance and its impact on core damage risk as part of the periodic assessment; (5) providing input to the PRA matrix; (6) providing risk analyses of combinations of SSCs out of service; (7) providing support for the SENTINEL program; and (8) providing support for PSA training. These tasks are not simply tied to the initial implementation of the rule. The maintenance rule must be kept consistent with the current design and operation of the plant. This will require that the PRA models and the many PSA calculations performed to support the maintenance rule are kept up-to-date. Therefore, support of the maintenance rule will be one of the primary roles of the PSA group for the remainder of the life of the plant

  5. Report from investigation committee on the accident at the Fukushima Nuclear Power Stations of Tokyo Electric Power Company

    International Nuclear Information System (INIS)

    Koshizuka, Seiichi

    2012-01-01

    Government's Investigation Committee on the Accident at Fukushima Nuclear Power Stations of Tokyo Electric Power Company published its final report on July 23, 2012. Results of investigation combined final report and interim report published on December 26, 2011. The author was head of accident accuse investigation team mostly in charge of site response, prior measure and plant behavior. This article reported author related technical investigation results focusing on site response and prior measures against tsunamis of units 1-3 of Fukushima Nuclear Power Stations. Misunderstanding of working state of isolation condenser of unit 1, unsuitability of alternative water injection at manual stop of high-pressure coolant injection (HPCI) system of unit 3 and improper prior measure against tsunami and severe accident were pointed out in interim report. Improper monitoring of suppression chamber of unit 2 and again unsuitable work for HPCI system of unit 3 were reported in final report. Thorough technical investigation was more encouraged to update safety measures of nuclear power stations. (T. Tanaka)

  6. Fire fighting precautions at Bohunice Atomic Power Plants

    International Nuclear Information System (INIS)

    Anon.

    1984-01-01

    Some shortcomings are discussed of the project design of fire protection at the V-1 and V-2 nuclear power plants. The basic shortcoming of the system is insufficient division of the units for fire protection. Fire fighting measures are described for cable areas, switch houses and outside transformers, primary and secondary circuits and auxiliary units. Measures are presented for increasing fire safety in Jaslovske Bohunice proceedi.ng from experience gained with a fire which had occurred at a nuclear power plant in Armenia. (E.S.)

  7. A proposal to pulse the Bevatron/Bevalac main guide field magnet with SCR power supplies

    International Nuclear Information System (INIS)

    Frias, B.; Alonso, J.; Dwinell, R.; Lothrop, F.

    1989-01-01

    The Bevatron/Bevalac Main Guide Field Power Supply was originally designed to provide a 15,250 Volt DC. at sign 8400 Ampere peak magnet pulse. Protons were accelerated to 6.2 Gev. The 128 Megawatt (MW) pulse required two large motor-generator (MG) sets with 67 ton flywheels to store 680 Megajoules of energy. Ignitron rectifiers are used to rectify the generator outputs. Acceleration of heavy ions results in an operating schedule with a broad range of peak fields. The maximum field of 12.5 kilogauss requires a peak pulse of 80 MW. Acceleration of ions to 1.0 kilogauss requires an 8 MW peak pulse. One MG set can provide pulses below 45 MW. Peak pulses of less than 15 MW are now a large block of the operating schedule. A proposal has been made to replace the existing MG system with eight SCR power supplies for low field operation. The SCR supplies will be powered directly from the Lawrence Berkeley Laboratory's 12.3 KV. power distribution system. This paper describes the many advantages of the plan. 4 refs., 3 figs., 3 tabs

  8. Study on quality control measures of static casting main pipe in PWR nuclear power plant

    International Nuclear Information System (INIS)

    Jiang Zhenbiao; Li Guanying; Liu Zhicheng

    2013-01-01

    This study analyzes the main reasons which impact the quality of primary pipe static casting elbows in PWR-M310 nuclear power plant. The quality control measures are developed from the election and inspection of material, improving sand production and casting process, improving lean management of personnel. The static casting defects of primary pipe elbows for Fuqing Unit 1 and 2 were down to less than 50% of the former project. The quality of static casting for the primary pipe elbows was significantly improved. Moreover, the implementation saves human resources and financing to repair casting defects, and also helps to win the delivery schedule. The quality control measures are good reference for improving primary pipe casting process. This study provides valuable experience for further study of improving the quality of static casting for the primary pipe of PWR nuclear power plant. (authors)

  9. The truth about atomic power plants. 2. ed.

    International Nuclear Information System (INIS)

    Hoell, K.

    1978-01-01

    The book discusses - the risk of nuclear power, - the dangers of population exposure, - hushed-up or belittled accidents and catastrophes, - the increasing radioactive pollution of our environment, - the hazard of nuclear cooling water to our rivers - blue algare toxins in our rivers. The strongest of all known poisons, - dangers to our drinking water, - necessary measures to protect the population. (orig./HP) [de

  10. All welded titanium condenser adopted in atomic power plants

    International Nuclear Information System (INIS)

    Iwai, Nagao; Itabashi, Yukihiko

    1980-01-01

    Condensers in power plants are shell-and-tube type heat exchangers. Most condensers use seawater as a coolant. Their tube and tube Sheets have usually been made of brass, which resists corrosion but cannot completely prevent it; as a result, tubes sometimes corrode or erode, allowing seawater to leak into the turbine cycle. As is well known, titanium has almost complete corrosion resistance against seawater; for this reason titanium tubes have replaced brass ones in some condensers operating in Europe and the USA. Even in such condensers, though, the tube plates have still been made of brass, tightly fitted to the titanium tubes, and it has proved impossible to eliminate seawater leakage at the junctions between tubes and tube Sheets. In order to eliminate such leakage completely, the tube Sheets must be made of titanium too, and the tubes and plates must be welded together. However, the welding of titanium requires an extremely celan atmosphere, a condition very difficult to fulfill at power plant construction sites, and the use of whole welded titanium tube condensers has long been considered a practical impossibility. Such all-titanium welded condensers have now been successfully constructed and installed in two 600 MW fossil power plants and one 1100 MW nuclear power plant. This paper describes the techniques used, add in addition reviews the various materials that have been used in condenser tubes. (author)

  11. Plug the socket of the main closing valve in a nuclear power plant

    International Nuclear Information System (INIS)

    Neupauer, J.; Bednar, B.

    1988-01-01

    The plug is designed for closing the main closing valve socket during a refuelling shutdown of a nuclear power plant. The plug is fixed in the using jaws forced against the socket ring part. The socket is sealed by expanding a ring between two cone trays. A valve provided in the plug allows draining the pipe. The plug is inserted in the socket using a jib suspended on a rail. Following sealing both sockets the inner surfaces of the closing valve can be decontaminated. Following decontamination, a water-proof cover is slid over the plug protecting the plug moving mechanism from damage. (J.B.). 1 fig

  12. Performance Evaluation and Quality Assurance Management during the Series Power Tests of LHC Main Lattice Magnets

    CERN Document Server

    Siemko, A

    2008-01-01

    Within the LHC magnet program a series production of superconducting dipoles and quadrupoles has recently been completed in industry and all magnets were cold tested at CERN. The main features of these magnets are: two-in-one structure, 56 mm aperture, two layer coils wound from 15.1 mm wide Nb-Ti cables, and all-polyimide insulation. This paper reviews the process of the power test quality assurance and performance evaluation, which was applied during the LHC magnet series tests. The main test results of magnets tested in both supercritical and superfluid helium, including the quench training, the conductor performance, the magnet protection efficiency and the electrical integrity are presented and discussed in terms of the design parameters and the requirements of the LHC project.

  13. Influence of laser power on atom probe tomographic analysis of boron distribution in silicon

    Energy Technology Data Exchange (ETDEWEB)

    Tu, Y., E-mail: ytu@imr.tohoku.ac.jp [The Oarai Center, Institute for Materials Research, Tohoku University, Oarai, Ibaraki 311-1313 (Japan); Takamizawa, H.; Han, B.; Shimizu, Y.; Inoue, K.; Toyama, T. [The Oarai Center, Institute for Materials Research, Tohoku University, Oarai, Ibaraki 311-1313 (Japan); Yano, F. [The Oarai Center, Institute for Materials Research, Tohoku University, Oarai, Ibaraki 311-1313 (Japan); Tokyo City University, Setagaya, Tokyo 158-8557 (Japan); Nishida, A. [Renesas Electronics Corporation, Hitachinaka, Ibaraki 312-8504 (Japan); Nagai, Y. [The Oarai Center, Institute for Materials Research, Tohoku University, Oarai, Ibaraki 311-1313 (Japan)

    2017-02-15

    The relationship between the laser power and the three-dimensional distribution of boron (B) in silicon (Si) measured by laser-assisted atom probe tomography (APT) is investigated. The ultraviolet laser employed in this study has a fixed wavelength of 355 nm. The measured distributions are almost uniform and homogeneous when using low laser power, while clear B accumulation at the low-index pole of single-crystalline Si and segregation along the grain boundaries in polycrystalline Si are observed when using high laser power (100 pJ). These effects are thought to be caused by the surface migration of atoms, which is promoted by high laser power. Therefore, for ensuring a high-fidelity APT measurement of the B distribution in Si, high laser power is not recommended. - Highlights: • Influence of laser power on atom probe tomographic analysis of B distribution in Si is investigated. • When using high laser power, inhomogeneous distributions of B in single-crystalline and polycrystalline Si are observed. • Laser promoted migration of B atoms over the specimen is proposed to explain these effects.

  14. Measures taken by electric power companies for the accident at JCO

    International Nuclear Information System (INIS)

    Taniguchi, Kazufumi

    2000-01-01

    Activities for the JCO accident were done by 700 electric company personnel/day at the maximum, who were mainly the experts of radiation management and were from the whole Japanese regions. The major activities were as follows. Monitoring of body surface contamination of people at the refuge, which was done on request from Tokaimura, showed no radioactive contamination over detection limit. Activities based on the request from the national counter-planning headquarters involved environmental monitoring, which only showed the higher ambient dose rate than usual at the boundary of JCO site. Monitoring of toy equipments in kindergartens and primary and junior schools showed no contamination over detection limit. Measurement of dose equivalent of the personnel showed 0.0 mSv exposure by γ-, β-ray and neutron. In summary, questions and requests raised by people mainly concerned the influence of radiation exposure. (K.H.)

  15. A survey on the application of robot techniques to an atomic power plant

    International Nuclear Information System (INIS)

    Hasegawa, Tsutomu; Sato, Tomomasa; Hirai, Shigeoki; Suehiro, Takashi; Okada, Tokuji

    1982-01-01

    Tasks of workers in atomic power plants have been surveyed from the viewpoint of necessity and possibility of their robotization. The daily tasks are classified into the following: (1) plant operation; (2) periodical examination; (3) patrol and inspection; (4) in-service inspection; (5) maintenance and repaire; (6) examination and production of the fuel; (7) waste disposal; (8) decommission of the plant. The necessity and present status of the robotization in atomic power plants are investigated according to the following classification: (1) inspection robots; (2) patrol inspection/maintenance robots; (3) hot cell robots; (4) plant decommission robots. The following have been made clear through the survey: (1) Various kinds of tasks are necessary for an atomic power plant: (2) Because of most of the tasks taking place in intense radiation environments, it is necessary to introduce robots into atomic power plants: (3) In application of robots in atomic power plant systems, it is necessary to take account of various severe conditions concerning spatial restrictions, radioactive endurance and reliability. Lastly wide applicability of the techniques of knowledge robots, which operate interactively with men, has been confirmed as a result of the survey. (author)

  16. Thermal expansion measurement of turbine and main steam piping by using strain gages in power plants

    International Nuclear Information System (INIS)

    Na, Sang Soo; Chung, Jae Won; Bong, Suk Kun; Jun, Dong Ki; Kim, Yun Suk

    2000-01-01

    One of the domestic co-generation plants have undergone excessive vibration problems of turbine attributed to external force for years. The root cause of turbine vibration may be shaft alignment problem which sometimes is changed by thermal expansion and external force, even if turbine technicians perfectly performed it. To evaluate the alignment condition from plant start-up to full load, a strain measurement of turbine and main steam piping subjected to thermal loading is monitored by using strain gages. The strain gages are bonded on both bearing housing adjusting bolts and pipe stoppers which installed in the x-direction of left-side main steam piping near the turbine inlet in order to monitor closely the effect of turbine under thermal deformation of turbine casing and main steam piping during plant full load. Also in situ load of constant support hangers in main steam piping system is measured by strain gages and its results are used to rebalance the hanger rod load. Consequently, the experimental stress analysis by using strain gages turns out to be very useful tool to diagnose the trouble and failures of not only to stationary components but to rotating machinery in power plants

  17. The liberalization of the European energy market from the perspective of the Austrian regional power company

    International Nuclear Information System (INIS)

    Sander, H.

    1999-01-01

    This dissertation addresses the liberalization of the European energy sector from an Austrian perspective, emphasizing its effect on a regional power company (KELAG). The energy market's changing conditions are creating new opportunities for consumers that allow them to optimize their ability to fulfill their power requirements. Decentralized solutions are now just as viable for large industrial customers as the ability to have all energy supplied through the utility network. In addition, partnerships with independent power producers (IPP's) or cooperation between the large customers in energy production can be considered. From a regional perspective, the central management concept of KELAG is the answer to an altered market situation, since this concept created tremendous potential for streamlining the management of energy production and operation of the network. The liberalization of the energy market for large industrial customers in Carinthia's electricity sector was preceded by a series of important decisions. The Verbundgesellschaft combine their generating facilities. In the future the power plants of Draukraft in Carinthia will be supervised and controlled remotely from KELAG's central control unit in Klagenfurt, as a result of which the central control unit becomes the primary energy control for Carinthia. (author)

  18. Good practices in radiological protection at Narora Atomic Power Station

    International Nuclear Information System (INIS)

    Singh, V.P.; Kumar, Sanjeev; Agrawal, Mitesh; Tiwari, S.K.; Kulhari, Praveen; Gupta, Ashok

    2016-01-01

    Radiological protection performance of nuclear power plant is assessed by collective exposure, individual average exposure, external/external exposure, personnel/surface contamination and reduction of radioactive wastes. Collective exposure is reduced by integrated comprehensive ALARA program in all aspects of nuclear plant operation and maintenance has reduced collective dose many folds. In the present paper, implementation of new good practices in Radiological Protection is presented

  19. Development on power distribution technologies of four electric power companies in Japan. The Kansai Electric Power Co. , Inc

    Energy Technology Data Exchange (ETDEWEB)

    1989-07-01

    Since dependency upon electric power has been rising yearly with the development of industry and the progress of information-oriented society, various kinds of technical development are needed to supply electricity. Furthermore, amenity of people's living has been highly intended, and life style has varied. Consequently, customers' needs for energy including related services have varied remarkably, and each customer has selected energy more subjectively from the wide range of viewpoint such as reliability, handiness, cleanliness, safety, and economic efficiency. In such situation, the power distribution section of Kansai Electric Power settled four themes for major technical development and has been promoting them. Four themes are as follows; to develop a total automation system for power distribution, to promote 20kV/400V-class power distribution, to develop techniques to form facilities harmonizing with local amenity, and to make business management efficient with the advanced NC system. 3 figs., 4 tabs.

  20. Analysis of relationship between the local governments and the power companies through the changes of safety agreements

    International Nuclear Information System (INIS)

    Sugawara, Shin-etsu; Inamura, Tomoaki; Kimura, Hiroshi; Madarame, Haruki

    2009-01-01

    In Japan, safety of nuclear facilities is regulated by the central government and local governments are responsible for protecting the local public. To operate nuclear facilities in local communities, local governments would conclude safety agreements with power companies. In recent years, local governments have used the safety agreements as excuse for delaying the operations of nuclear facilities. The legal basis of the safety agreements was questioned by some who considered that this was the cause of the stranded relationship between local governments and power companies, and in some cases, the interrupted nature of electricity supply. To understand the sources of this difficult relationship, safety agreements must be analyzed, although these documents may have undergone revisions, and various regulations may have changed. By analyzing the safety agreements and revisions, we found that the relationship between local governments and power companies gradually changed over time, which can be divided into the following 3 stages: (1) in the early 70s, the dawn stage when local governments groped with the situation of nuclear facilities built in their communities; (2) from late 70s to 90s, the stage when local governments demanded information, and (3) from late 90s to present, the stage when local governments demand information and trustworthiness. This paper shows the results of analyzing the relationship changes between local governments and power companies. We conclude that viewpoints of local governments on nuclear power evolve, as social responsibilities of power companies stipulated in safety agreements also evolve over time. (author)

  1. Maintenance experience on reactor recirculation pumps at Tarapur Atomic Power Station

    International Nuclear Information System (INIS)

    Singh, A.K.

    1995-01-01

    Reactor recirculation pumps at Tarapur Atomic Power Station (TAPS) are vertical, single stage centrifugal pumps having mechanical shaft seals and are driven by vertical mounted 3.3 kV, 3 phase, 1500 h.p. electric motors. During these years of operation TAPS has gained enough experience and expertise on the maintenance of reactor recirculation pumps which are dealt in this article. Failure of mechanical shaft seals, damage on pump carbon bearings, motor winding insulation failures and motor shaft damage have been the main areas of concern on recirculation pump. A detailed procedure step by step with component sketches has helped in eliminating errors during shaft seal assembly and installation. Pressure breakdown devices in seal assembly were rebuilt. Additional coolant water injection for shaft seal cooling was provided. These measures have helped in extending the reactor recirculation pump seal life. Pump bearing problems were mainly due to failure of anti-rotation pins and dowel pins of bearing assembly. These pins were redesigned and strengthened. Motor stator winding insulation failures were detected. Stator winding replacement program has been taken up on regular basis to avoid winding insulation failure due to aging. 3 refs., 2 tabs., 7 figs

  2. Radiotoxicity of Actinides During Transmutation in Final Stage of Atomic Power

    International Nuclear Information System (INIS)

    Gerasimov, Aleksander S.; Bergelson, Boris R.; Myrtsymova, Lidia A.; Tikhomirov, Georgy V.

    2002-01-01

    Characteristics of a transmutation mode in final stage of atomic power are analyzed. In this stage, transmutation of actinides accumulated in transmutation reactors is performed without feed by actinides from other reactors. The radiotoxicity during first 20 years of transmutation is caused mainly by 244 Cm. During following period of time, 252 Cf is main nuclide. Contribution of 246 Cm and 250 Cf is 5-7 times less than that of 252 Cf. During 50 years of a transmutation, the total radiotoxicity falls by 50 times. Long-lived radiotoxicity decreases slowly. During the period between T=50 years and T=100 years, long-lived radiotoxicity falls by 3.7 times. For each following 50 years after this period, long-lived radiotoxicity falls by 3.2 times. These results corresponding to neutron flux density 10 14 neutr/(cm 2 s) in transmutation reactor demonstrate that the final stage of a transmutation should be performed with use of high flux transmutation facilities which provide shorter time of transmutation. (authors)

  3. Evaluation of Risks Related To Russian Power Grid Companies by Foreign Investors

    Directory of Open Access Journals (Sweden)

    Daria L. Val'kova

    2016-01-01

    Full Text Available The article focuses on the impact of the current crisis on evaluation of risks related to Russian power grid companies by foreign investors as well as on prospects of raising foreign capital. The current situation resulted in a considerable deterioration of investment climate in Russia as well as in aggravation of industry-specific problems. Inflation growth, devaluation of the national currency, GDP decrease, drop in electricity consumption and the crisis in the banking sector negatively impact the investment profile of the country. This leads to increased risk premium for foreign capital investments in any type of Russian assets. At the same time industry-specific problems augmented as well. Those are primarily lack of transparency in regulation, which is subject to constant changes, growth in overdue receivables, limited access to modern technologies. All of the above had a considerable impact on the perception of Russian risks by international investors. A comprehensive approach is needed to improve the investment climate in the country and this would be largely defined by the general macroeconomic development of the Russian Federation and relations with other states. Consistent strategy and integrated actions of the Government and respective Ministries are of particular importance. As for the industry-specific factors, transparent and well-balanced long-term tariff system is the key condition for sustainable improvement of the situation in the sector, according to the major industry participants and leading experts. Thus, the article highlights changes in investor perception of the Russian power grid sector as well as relative impact on the industry development prospects. This analysis is the basis for further elaboration of recommendations regarding easing off of the crisis impact on the power grid companies as well as for assessment of prospects of meeting strategic industry development objectives.

  4. 78 FR 49305 - Luminant Generation Company LLC, Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 2...

    Science.gov (United States)

    2013-08-13

    ... NUCLEAR REGULATORY COMMISSION [Docket Nos. 50-445 and 50-446; NRC-2013-0182] Luminant Generation Company LLC, Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 2; Application for Amendment to Facility... Operating License Nos. NPF-87 and NPF-89 for the Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 2...

  5. 78 FR 14361 - In the Matter of Luminant Generation Company LLC, Comanche Peak Nuclear Power Plant, Units 1 and...

    Science.gov (United States)

    2013-03-05

    ... NUCLEAR REGULATORY COMMISSION [NRC-2012-0310; Docket Nos. 50-445 and 50-446; License Nos. NPF-87 and NPF-89] In the Matter of Luminant Generation Company LLC, Comanche Peak Nuclear Power Plant, Units... Nuclear Power Plant, Units 1 and 2 (CPNPP), and its Independent Spent Fuel Storage Installation Facility...

  6. 75 FR 82414 - Carolina Power & Light Company; H. B. Robinson Steam Electric Plant, Unit No. 2; Exemption

    Science.gov (United States)

    2010-12-30

    ... NUCLEAR REGULATORY COMMISSION [Docket No. 50-261; NRC-2010-0062] Carolina Power & Light Company; H. B. Robinson Steam Electric Plant, Unit No. 2; Exemption 1.0 Background Carolina Power & Light... authorizes operation of the H.B. Robinson Steam Electric Plant, Unit 2 (HBRSEP). The license provides, among...

  7. 75 FR 11579 - Carolina Power & Light Company H. B. Robinson Steam Electric Plant, Unit No. 2; Exemption

    Science.gov (United States)

    2010-03-11

    ... NUCLEAR REGULATORY COMMISSION [Docket No. 50-261; NRC-2010-0062] Carolina Power & Light Company H. B. Robinson Steam Electric Plant, Unit No. 2; Exemption 1.0 Background Carolina Power & Light... of the H. B. Robinson Steam Electric Plant, Unit 2 (HBRSEP). The license provides, among other things...

  8. Cost structure analysis of commercial nuclear power plants in Japan based on corporate financial statements of electric utility companies

    International Nuclear Information System (INIS)

    Kunitake, Norifumi; Nagano, Koji; Suzuki, Tatsujiro

    1998-01-01

    In this paper, we analyze past and current cost structure of commercial nuclear power plants in Japan based on annual corporate financial statements published by the Japanese electric utility companies, instead of employing the conventional methodology of evaluating the generation cost for a newly constructed model plant. The result of our study on existing commercial nuclear plants reveals the increasing significance of O and M and fuel cycle costs in total generation cost. Thus, it is suggested that electric power companies should take more efforts to reduce these costs in order to maintain the competitiveness of nuclear power in Japan. (author)

  9. Output control system in a boiling water atomic power plant

    International Nuclear Information System (INIS)

    Sadakane, Ken-ichiro.

    1975-01-01

    Object: To provide a line in bypass relation with a water heater, a flow rate of said bypass being adjusted to thereby perform quick responsive sub-cool control of a core inlet. Structure: A steam line and a water line are disposed so as to feed water from the reactor core to the water heater via turbine and thence to the core. A line disposed in bypass relation with the water heater arranged in the water line includes a control valve for controlling water passing through the bypass line and a main control for sending a signal to said control valve, said main control receiving loads from the outside, whereby a control signal is transmitted to the control valve, causing water passing through the water heater and water line to the core to be bypassed, a period of time for supplying time to be reduced, and quick response to be enhanced. (Kamimura, M.)

  10. FINAL–REPORT NO. 2: INDEPENDENT CONFIRMATORY SURVEY SUMMARY AND RESULTS FOR THE ENRICO FERMI ATOMIC POWER PLANT, UNIT 1, NEWPORT, MICHIGAN (DOCKET NO. 50 16; RFTA 10-004)

    Energy Technology Data Exchange (ETDEWEB)

    Erika Bailey

    2011-07-07

    The Enrico Fermi Atomic Power Plant, Unit 1 (Fermi 1) was a fast breeder reactor design that was cooled by sodium and operated at essentially atmospheric pressure. On May 10, 1963, the Atomic Energy Commission (AEC) granted an operating license, DPR-9, to the Power Reactor Development Company (PRDC), a consortium specifically formed to own and operate a nuclear reactor at the Fermi 1 site. The reactor was designed for a maximum capability of 430 megawatts (MW); however, the maximum reactor power with the first core loading (Core A) was 200 MW. The primary system was filled with sodium in December 1960 and criticality was achieved in August 1963.

  11. Final-Report No. 2: Independent Confirmatory Survey Summary And Results For The Enrico Fermi Atomic Power Plant, Unit 1, Newport, Michigan (Docket No. 50 16; RFTA 10-004) DCN 2018-SR-02-0

    International Nuclear Information System (INIS)

    Bailey, Erika

    2011-01-01

    The Enrico Fermi Atomic Power Plant, Unit 1 (Fermi 1) was a fast breeder reactor design that was cooled by sodium and operated at essentially atmospheric pressure. On May 10, 1963, the Atomic Energy Commission (AEC) granted an operating license, DPR-9, to the Power Reactor Development Company (PRDC), a consortium specifically formed to own and operate a nuclear reactor at the Fermi 1 site. The reactor was designed for a maximum capability of 430 megawatts (MW); however, the maximum reactor power with the first core loading (Core A) was 200 MW. The primary system was filled with sodium in December 1960 and criticality was achieved in August 1963.

  12. Atomic power engineering as military and nuclear deterrence

    International Nuclear Information System (INIS)

    Koryakin, Yu.I.

    2000-01-01

    The consequences of the NPP destruction in the course of the military actions, which are related to the powerful release of radioactivity, are analyzed. The ways of protection of the NPPs and other industrial objects during the war are considered. Special attention is paid to the advisability of the NPPs underground location. The data on the costs of the NPP units underground construction in the USA, Canada, Norway and Sweden are presented. The conclusion is made, that the NPPs underground location by itself does not increase their failure-proof operation and does not solve all safety problems during the military actions [ru

  13. Main characteristics of the radioactive enrichment in ashes produced in coal-fired power stations

    International Nuclear Information System (INIS)

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

    2008-01-01

    Under contract with the Spain's 'Nuclear Safety Council', a study is being conducted of the nation's largest nominal output coal-fired power stations. Its purpose is to assess the radiological impact on workers and local populations due to this source of NORM activity. One of the aspects of particular interest is the study of the radioactive enrichment in the combustion wastes relative to the different coals used as fuel (usually local bituminous coal or lignite, or imported coal). These wastes consist of fly ash (mostly fine particles collected in electrostatic precipitators), and bottom ash (larger in size, and collected wet or dry in hoppers below the boilers). In general terms, the enrichment factors measured were between 2 and 18 for the radionuclides 40 K, 226 Ra, 232 Th, and 210 Po. The magnitude of this enrichment factor depended mainly on the ash content of each coal, and hence on the type of coal used as fuel and the specific operation cycle in the different power stations. For the radionuclides 40 K, 226 Ra, and 232 Th, the enrichment was relatively similar in value in the fly and bottom ashes produced by the different types of coal used in the power stations studied. For 210 Po, however, as was expected, the enrichment was much greater in the fly ash than in the bottom ash for each coal analyzed. (author)

  14. Studies for aseismatic design of atomic power equipment

    International Nuclear Information System (INIS)

    Uchiyama, Yuichi; Takayanagi, Masaaki; Moriyama, Takeo; Mizuno, Sadao

    1976-01-01

    The social requirements for the safety of nuclear power stations are very severe, and especially in Japan where earthquakes occur frequently, the safety against earthquakes is regarded as an important matter. The numerous machinery and equipments composing nuclear power plants have largely different roles in the safety, accordingly it is important to maintain effectively the safety as a whole. The design is carried out by classifying buildings, machinery and equipments, pipings and electric appliances according to the importance, and so that the aseismatic property corresponding to the importance is given to each. In most cases, the aseismatic design is carried out with computing codes, but it is necessary to forward the design by proving the propriety of analysis models and calculated results. Efforts are exerted in Hitachi Ltd. to improve the accuracy of the aseismatic analysis by carrying out basic experiment, the demonstration test in actual plants and the study on analytical method as many as possible. The measurement of the vibration of actual pipings in order to confirm the supporting conditions, the comparison of multi-input analysis and SRSS method for piping analysis, and the vibration tests of a model containment vessel and a fuel assembly were carried out, and the results are reported in this paper. It is important to improve the accuracy of earthquake response analysis further. (Kako, I.)

  15. Advertising the atom: federal promotion of nuclear power, 1953-1984

    Energy Technology Data Exchange (ETDEWEB)

    Smith, M.

    1984-01-01

    The public relations strategies of the Atomic Energy Commission (AEC) and the nuclear power industry reveal both public and official perceptions of nuclear power and the social uses of technology in general during the first 15 years after passage of the Atomic Energy Act of 1954. The relation between nuclear promotion and regulation also helps explain the environmental crisis of the 1969-1984 years. Project Plowshare coincides roughly with the early promotional years, and provides a case study of the relation of regulatory standards to promotion in AEC policymaking. The author examines the environmentalists challenge to nuclear power that emerged in 1969 alongside government and industry response. He concludes with an assessment of the present state of federal nuclear power policy and of the nuclear power industry.

  16. Advertising the atom: federal promotion of nuclear power, 1953-1984

    International Nuclear Information System (INIS)

    Smith, M.

    1984-01-01

    The public relations strategies of the Atomic Energy Commission (AEC) and the nuclear power industry reveal both public and official perceptions of nuclear power and the social uses of technology in general during the first 15 years after passage of the Atomic Energy Act of 1954. The relation between nuclear promotion and regulation also helps explain the environmental crisis of the 1969-1984 years. Project Plowshare coincides roughly with the early promotional years, and provides a case study of the relation of regulatory standards to promotion in AEC policymaking. The author examines the environmentalists challenge to nuclear power that emerged in 1969 alongside government and industry response. He concludes with an assessment of the present state of federal nuclear power policy and of the nuclear power industry

  17. Factors analysis of water hammer in FLOWMASTER for main feedwater systems of PWR nuclear power plants

    International Nuclear Information System (INIS)

    Wang Xin; Han Weishi

    2010-01-01

    The main feedwater system of a nuclear power plant (NPP) is an important part in ensuring the cooling of a steam generator. It is the main pipe section where water hammers frequently occur. Studying the regulator patterns of water hammers in the main feedwater systems is significant to the stable operation of the system. This article focuses on a parametric study to avoid the consequences of water hammer effect in PWR by employing a general purpose fluid dynamic simulation software-FLOWMASTER. Through FLOWMASTER's transient calculating functions, a mathematical model is established with boundary conditions such as feedwater pumps, control valves, etc., calculations of water hammer pressure when feedwater pumps and control valves shut down, and simulations during instantaneous changes in water hammer pressure. Combining a plethora of engineering practical examples, this research verified the viability of calculating water hammer pressure through FLOWMASTER's transient functions and we found out that, increasing the periods of closure of control valves and feedwater pumps control water hammers effectively. We also found out that changing the intervals of closing signals to feedwater pumps and control valves aid to relieve hydraulic impact. This could be a guideline for practical engineering design and system optimization. (author)

  18. Water hammer calculation and analysis in main feedwater system of PWR nuclear power plants

    International Nuclear Information System (INIS)

    Wang Xin; Han Weishi

    2010-01-01

    The main feedwater system of a nuclear power plant is an important part in ensuring the cooling of the steam generator. Moreover, it is the main pipe section where water hammers frequently occur. Studying the regular patterns of water hammers to the main feedwater system is significant to the stable operation of the system. The paper focuses on the study of water hammers through Flowmaster's transient calculating function to establish a mathematical model with boundary conditions such as a feedwater pump, control valves, etc.; calculation of the water hammers pressure when feedwater pumps and control valves shut down; exporting the instantaneous change in solution of pressure. Combined with engineering practical examples, the conclusions verify the viability of calculating the water hammers pressure through Flowmaster's transient function, increasing the periods of closure of control valves and feedwater pumps control water hammers effectively, changing the intervals of closing signals to feedwater pumps and control valves to relieve hydraulic impact. This could be a guideline for practical engineering design and system optimization. (authors)

  19. Design and construction of solidification and dewatering facility at Alabama Power Company's Farley Nuclear Plant

    International Nuclear Information System (INIS)

    Farnsworth, P.

    1988-01-01

    The approximate total cost of the structure and supporting piping systems is estimated to be 4.1 million dollars. Total dose savings per year could be as high as 70 man Rem for resin processing alone. The ability to store refueling equipment, process contaminated oils, load and unload trucks and containers regardless of weather conditions and support repair work on equipment greatly enhances the cost effectiveness of the project. It will take at least one year of operation of the facility to accurately assess the true cost savings to Alabama Power Company. The morale factor for the Waste and Decon Group has escalated measurably due to the dose reduction to our personnel. Plant and company management are well pleased due to the possibility of a spill or release to the environment has been eliminated which was on intangible cost. Facility construction has been completed as of this date and resin transfer anticipated within the next few days. Some of the problems encountered in planning and constructing this solidification and dewatering facility are presented. A safety evaluation for the facility is included in the appendix

  20. Poison pills: A defensive measure against a hostile takeover or a demonstration of power of the target company

    Directory of Open Access Journals (Sweden)

    Jovanović-Zattila Milena

    2014-01-01

    Full Text Available The balance of power is particularly at stake in hostile takeovers, which makes the issue of establishing the balance of power one of the most controversial issues in the contemporary company law. In the circumstances of direct market competition and the need to have a dominant market position, companies are necessarily forced to constantly upgrade and advance their offensive and defensive methods, techniques and strategies. In order to prevent a hostile takeover, the target company may resort to an array of defence mechanisms, the most prominent of which are 'poison pills'. In spite of being perceived as the most powerful tool for obstructing hostile takeovers (and commonly designated as the 'Holy Grail' among the defensive mechanisms, there are many pros and cons underlying their application. One of the positive effects of using the poison pills is that the fear of takeovers makes the target company management more disciplined and efficient in business operations. The negative consequences are reflected in the relationship between the company board of directors and the shareholders. The target company management makes a unilateral decision on using a poison pill and this decision does not have to be approved by the shareholders in the General Meeting; however, this is highly inconsistent with the basic principles of corporate governance. The asymmetry of information, where the management (an agent has disproportionately more relevant information at its disposal than the shareholders (principals, generates a conflict between the management and the shareholders. In company law, this agency problem is generally known as the principal-agent problem, which is most prominent in a takeover. Poison pills are often associated with the discrimination of the target company shareholders, but not necessarily. The controversial nature of this defensive measure which can be applied by the target company has given rise to numerous debates on the need to

  1. Atom and the fault: experts, earthquakes, and nuclear power

    International Nuclear Information System (INIS)

    Meehan, R.L.

    1984-01-01

    A narrative account of the geology expert's role in an environmental controversy focuses on the problem of siting nuclear power plants near geologic faults and the conflicting testimony delivered by equally sincere consultants. The author examines the problem of faults and their significance to reactor safety, and concludes that part of the controversy and regulatory indecision are due to the lack of an accepted scientific standard for risk. He explores the historical and social role of the principal professional groups (geologists and engineers) in the debate, and concludes that concerns at some sites were warranted. Scientific advocacy, he feels, serves a useful function in the hearing process, and that the representation for intervenors has been generally good. 18 references, 10 figures

  2. Spent-fuel management strategies at Carolina Power ampersand Light Company

    International Nuclear Information System (INIS)

    Thompson, M.F. Jr.; Kunita, R.K.

    1990-01-01

    Carolina Power ampersand Light (CP ampersand L) Company serves customers in portions of both North and South Carolina, and operates the Robinson 2, Brunswick 1 and 2, and Harris nuclear units. Due first to licensing delays in the Allied General Nuclear Service reprocessing plant and then to actions and inactions by the federal government, CP ampersand L like other utilities, is concerned with the storage of spent fuel. Despite pool reracking to the maximum practical, further actions have been necessary; hence, CP ampersand L undertook efforts to make both dry storage and transshipment viable alternatives. Based on experience, it is found that while both dry storage and transshipment are viable options, transshipment is the better strategy for CP ampersand L. Dry storage will be maintained as an alternative strategy

  3. Fault diagnosis of main coolant pump in the nuclear power station based on the principal component analysis

    International Nuclear Information System (INIS)

    Feng Junting; Xu Mi; Wang Guizeng

    2003-01-01

    The fault diagnosis method based on principal component analysis is studied. The fault character direction storeroom of fifteen parameters abnormity is built in the simulation for the main coolant pump of nuclear power station. The measuring data are analyzed, and the results show that it is feasible for the fault diagnosis system of main coolant pump in the nuclear power station

  4. Cost efficiency of Japanese steam power generation companies: A Bayesian comparison of random and fixed frontier models

    Energy Technology Data Exchange (ETDEWEB)

    Assaf, A. George [Isenberg School of Management, University of Massachusetts-Amherst, 90 Campus Center Way, Amherst 01002 (United States); Barros, Carlos Pestana [Instituto Superior de Economia e Gestao, Technical University of Lisbon, Rua Miguel Lupi, 20, 1249-078 Lisbon (Portugal); Managi, Shunsuke [Graduate School of Environmental Studies, Tohoku University, 6-6-20 Aramaki-Aza Aoba, Aoba-Ku, Sendai 980-8579 (Japan)

    2011-04-15

    This study analyses and compares the cost efficiency of Japanese steam power generation companies using the fixed and random Bayesian frontier models. We show that it is essential to account for heterogeneity in modelling the performance of energy companies. Results from the model estimation also indicate that restricting CO{sub 2} emissions can lead to a decrease in total cost. The study finally discusses the efficiency variations between the energy companies under analysis, and elaborates on the managerial and policy implications of the results. (author)

  5. Observations of Crassostrea virginica cultured in the heated effluent and discharged radionuclides of a nuclear power reactor

    International Nuclear Information System (INIS)

    Price, A.H.; Hess, C.T.; Smith, C.W.

    1976-06-01

    American oysters (Crassostrea virginica) were rafted for 26 months at four sites in the effluent waters near Maine Yankee Nuclear Power Reactor in Montsweag Bay and at a control site in the adjacent Damariscotta River. In an evaluation of the thermal effluent for aquaculture, comparisons are made among the sites of the effects of heated effluent on oyster growth and condition, and the uptake and retention of gamma-ray emitting radionuclides. Growth and uptake of radionuclides were observed to be accelerated at the warmer water sites. Both experimental results and calculations for 58 Co and 54 Mn are presented

  6. Site Environmental Report for Calendar Year 2000. DOE Operations at The Boeing Company, Rocketdyne Propulsion & Power

    Energy Technology Data Exchange (ETDEWEB)

    Rutherford, Phil [The Boeing Company, Canoga Park, CA (United States); Samuels, Sandy [The Boeing Company, Canoga Park, CA (United States); Lee, Majelle [The Boeing Company, Canoga Park, CA (United States)

    2001-09-01

    This Annual Site Environmental Report (ASER) for 2000 describes the environmental conditions related to work performed for the Department of Energy (DOE) at Area IV of the Rocketdyne Santa Susana Field Laboratory (SSFL). In the past, these operations included development, fabrication, and disassembly of nuclear reactors, reactor fuel, and other radioactive materials, under the former Atomics International (AI) Division. Other activities included the operation of large-scale liquid metal facilities for testing of liquid metal fast breeder components at the Energy Technology Engineering Center (ETEC), a government-owned company-operated, test facility within Area IV. All nuclear work was terminated in 1988, and subsequently, all radiological work has been directed toward decontamination and decommissioning (D&D) of the previously used nuclear facilities and associated site areas. Large-scale D&D activities of the sodium test facilities began in 1996. Results of the radiological monitoring program for the calendar year of 2000 continue to indicate no significant releases of radioactive material from Rocketdyne sites. All potential exposure pathways are sampled and/or monitored, including air, soil, surface water, groundwater, direct radiation, transfer of property (land, structures, waste), and recycling. All radioactive wastes are processed for disposal at DOE disposal sites and other sites approved by DOE and licensed for radioactive waste. Liquid radioactive wastes are not released into the environment and do not constitute an exposure pathway.

  7. Crud separation from equipment drain of BWR atomic power station

    International Nuclear Information System (INIS)

    Hayashi, Masaru; Yamaguchi, Hisashi; Moriya, Yasuhiro; Koshiba, Yukihiko; Ota, Yoshiharu.

    1977-01-01

    In the primary cooling systems of BWR nuclear power stations, radioactive crud is generated and accumulates in reactors and circulating systems, which causes the radiation exposure of workers at the time of the inspection and maintenance of reactors. The chemical composition and grain size distribution of crud differ largely according to the construction of primary systems, the operational conditions of reactors, and the process of operation. The study on the application of nuclear pore membrane filter NPMF to the separation of crud in the waste water from equipment drain systems has been carried out. With the NPMF, clarified filtrate can be obtained without any filter aid, therefore the secondary waste of filter sludge is not generated. When the filter is clogged, the filtration capability can be regenerated by reverse flow washing, and continuous filtration is possible actually because the regeneration takes only short time. The NPMF is the polycarbonate membrane of about 10 μm thick, to which charged particles are irradiated vertically, and the flight tracks are etched with alkali solution, thus the required pore treatment is applied. The basic investigation of waste liquid, the endurance test of actual filters, the filtration test with the pilot apparatus, the demonstration test with an actual equipment, and the design of the actual equipment have been carried out for three years. (Kako, I.)

  8. The problem of ensuring the seismic stability of atomic electric power plant equipment and ways of solving it

    International Nuclear Information System (INIS)

    Kaznovskii; Filippov, G.A.

    1983-01-01

    By seismic stability the authors mean the ability of the equipment and buildings to retain certain properties when subjected to seismic loads: leakproofness, strength, the absence of any residual changes of shape, which interfere with normal operation, ability to be repaired, nuclear and radiation safety. The latter requirement is the main thing which differentiates atomic electric power plants from other constructions, including other power-generation plants. Whereas, for example, an accident in the event of an earthquake in a thermal electric power plant can be regarded as a local accident, and the measures to ensure seismic stability are determined by economic factors and safety requirements for the operating staff, to ensure the seismic stability of an AES it is essential to take account in the first instance of the possibility of dangerous radiation effects both in the AES and in the vast area around it

  9. Establishment of land model at the Shika Nuclear Power Plant. Mainly, on rock board classification

    International Nuclear Information System (INIS)

    Katagawa, Hideki; Hashimoto, Toru; Hirano, Shuji

    1999-01-01

    In order to grasp engineering properties of basic land of constructions, there is rock board classification as a method to classify whole of rock board to some groups considerable to be nearly equal on its properties. Among the method, various methods in response to its aim and characteristics are devised, and for a classification to hard rock board, the Denken type rock board classification considering degree of weathering to its main element and so forth are well known. The basic rock board of the Shika Nuclear Power Plant is composed of middle and hard types of rock, and its weathering is limited to its shallow portion, most of which are held at fresh condition. For such land, a new classification standard in response to characteristics of land was established. Here were introduced on a progress to establish a new classification standard, its application results and rock board properties. (G.K.)

  10. Main phases of siting for nuclear power plants with review of required investigations

    International Nuclear Information System (INIS)

    Malbasa, N.

    1984-01-01

    The purpose of the article is a short description of the main phases in the process of siting for nuclear power plants as interpreted and applied by the Institut za elektroprivredu, Zagreb in the screening, comparison and evaluation of the sites for NPPs in the SR of Croatia. The scope and purpose, as well as review of required data and investigations for each particular phase are given. Common used methods for the comparison of sites are described and example of rejection criteria applicable for early phases of the siting is proposed. It is given a list of the most important activities which detailed analysis id indispensable for ending of the evaluation and getting a site permit from the regulatory body. A legal and regulatory basis for carrying out the siting process is also described. (author)

  11. Feasibility study for biomass power plants in Thailand. Volume 1. Main report. Export trade information

    International Nuclear Information System (INIS)

    1997-01-01

    This study, conducted by Black and Veatch, was funded by the U.S. Trade and Development Agency. The report presents a technical and commercial analysis for the development of three nearly identical electricity generating facilities (biomass steam power plants) in the towns of Chachoengsao, Suphan Buri, and Pichit in Thailand. The Main Report is divided into the following sections: (1.0) Executive Study; (2.0) Project Objectives; (3.0) Review of Combustion Technology for Biomass Fueled Steam Generator Units; (4.0) Conceptual Design; (5.0) Plant Descriptions; (6.0) Plant Operations Staffing; (7.0) Project Schedule; (8.0) Project Cost Estimate; (9.0) Financial Analysis; Appendix - Financial Analysis

  12. Probabilistic safety assessment of Narora Atomic Power Project

    International Nuclear Information System (INIS)

    Babar, A.K.; Saraf, R.K.; Kakodkar, A.; Sanyasi Rao, V.V.S.

    1989-01-01

    Various safety studies on Pressurised Water and Boiling Water reactors have been conducted. However, a detailed report on probabilistic safety assessment (PSA) of PHWRs is not available. PSA level I results of the standardised 235 MWe PHWR under construction at Narora are presented herein. Fault Tree analysis of various initiating events (IEs), safety systems has been completed. Event Tree analysis has been performed for all the dominating IEs to identify the accident sequences and a list of the dominating accident sequences is included. Analysis has been carried out using Monte Carlo simulation to propagate the uncertanities in failure rate data. Further uncertainty analysis is extended to obtain distributions for the accident sequences and core damage frequency. Some noteworthy results of the study apart from the various design modifications incorporated during the design phase are: (i) The accident sequences resulting from station blackout are dominant contributors to the core damage frequency. (ii) Class-IV transients, small break LOCA are significant IEs. Main steam line break is likely to induce steam generator tube ruptures. (iii) Moderator circulation, fire fighting system, secondary steam relief are relatively important in core damage frequency reductions. (iv) Under accidental situations human errors are likely to be asociated with valving in shutdown cooling and fire fighting systems. (author). 14 tabs., 14 figs., 15 refs

  13. Operational status of the AGS Booster Main Ring Magnet Power Supply

    International Nuclear Information System (INIS)

    Soukas, A.; Bannon, M.; Geller, J.; McNerney, A.J.; Sandberg, J.; Toldo, F.; Zhang, S.Y.

    1992-01-01

    The Booster is a multipurpose accelerator interposed between a 200 MeV linac, a pair of 15 MV Tandem Van deGraaf accelerators, and the AGS. It can operate on slow cycles of 0.3 Hertz pulse repetition frequency up to a maximum of 7.5 Hertz. The different cycles, from long front porches for long injection or accumulation periods or flattops for slow extraction, to normal fast extraction cycles, accommodate protons, heavy ions (h.i.) and polarized protons. One of the systems enabling the flexible Booster operation is the Main Ring Magnet Power Supply (MRPS) system. It consist of a series connection of six, 1000 volt, multiphase rectifiers together with by pass switches. Two of the six operate at currents up to 6 kA and the rest up to 3 kA. All bypass switches are rated for 6 kA. The system is equipped with passive, damped LCRC filters as well as an active transformer coupled correction system. The MRPS is connected directly to the Long Island 69 Kv bus via a dedicated 20 MVA transformer. The choice of a series of modules enables the very flexible cycle generation and at the same time minimizes the deleterious effects of power factor and harmonics on the ac lines

  14. Psychological factors of professional success of nuclear power plant main control room operators

    Directory of Open Access Journals (Sweden)

    Kosenkov A.A.

    2014-12-01

    Full Text Available Aim: to conduct a comparative analysis of the psychological characteristics of the most and least successful main control room operators. Material and Methods. Two NPP staff groups: the most and least successful main control room operators, who worked in routine operating conditions, were surveyed. Expert evaluation method has been applied to identify the groups. The subjects were administered the Minnesota Multiphasic Personality Inventory (MMPI, Cattell's Sixteen Personality Factor Questionnaire (16PF form A and Raven's Progressive Matrices test. Results. Numerous significant psychological differences between the groups of most and least successful control room operators were obtained: the best operators were significantly more introverted and correctly solved more logical tasks with smaller percentage of mistakes under time pressure than worst ones. Conclusions: 1. The psychodiagnostic methods used in the study were adequate to meet research objective 2. Tendency to introversion, as well as developed the ability to solve logic problems undertime pressure, apparently, are important professional qualities for control room operators. These indicators should be considered in the process of psychological selection and professional guidance of nuclear power plant operators.

  15. POSSIBILITIES OF APPLYING THE DEA METHOD IN THE ASSESSMENT OF EFFICIENCY OF COMPANIES IN THE ELECTRIC POWER INDUSTRY: REVIEW OF WIND ENERGY COMPANIES

    Directory of Open Access Journals (Sweden)

    Dario Maradin

    2014-07-01

    Full Text Available One of the fundamental tasks of modern power system is finding ways to produce stable and continuous electricity from scarce energy resources. One of the possible solutions is introduction, implementation and improvement of alternative forms of energy such as renewable energy sources, particularly wind energy as an increasingly important energy source which is expected to further increase its share in total electricity production. Numerous methods can be used in assessing the efficiency of wind energy companies, and in the focus of this research is the Data Envelopment Analysis method (DEA, a widely accepted methodology given its interdisciplinary approach and flexibility. This method represents a step forward in the field of renewable energy management, because it provides the possibility to compare the selected companies with the best in the industry (the most efficient and the possibility of determining sources of inefficiency and, consequently, the possibilities of their elimination.

  16. Hurricane Andrew causes major oil spill at Florida Power ampersand Light Company's Turkey Point Power Plant, Homestead, Florida

    International Nuclear Information System (INIS)

    Jones, M.A.; Butts, R.L.; Lindsay, J.R.; McCully, B.S.; Pickering, T.H.

    1993-01-01

    On August 24, 1992, Hurricane Andrew slammed into South Florida with wind gusts in excess of 160 mph. At 4:00 a.m. that day, the eye of this category four storm passed over Florida Power ampersand Light Company's Turkey Point power plant, south of Miami. Although the plant's two nuclear units escaped any significant damage, the storm caused extensive destruction to buildings and transmission facilities, and damaged two 400 foot tall emission stacks associated with the site's two fossil fuel generating units. In addition, a 90,000 to 110,000 gallon spill of No. 6 fuel oil resulted when a piece of wind-blown debris punctured the steel of the unit One 12,000 barrel fuel oil metering tank approximately 30 feet up from the tank bottom. Despite the presence of a secondary containment structure around the tank, the intense wind blew oil throughout the plant site. The damage to the metering tank apparently occurred during the first half hour of the hurricane. As the tank's oil level fell due to the puncture, transfer pumps from the bulk oil storage tanks received a low level alarm which automatically began transferring oil to the damaged metering tank. To prevent the further discharge of oil, plant personnel entered the power block and secured the pumps during the passage of the hurricane eye. Immediately following the storm, facility personnel deployed booms across the barge canal and the Units 1 and 2 intake canal to contain the oil which had entered the water. The response strategy and implementation is described in detail. The remediation costs were approximately $14/gallon spilled, including 54,000 gallons recovered for electricity generation

  17. The contract of design of an atomic reactor system in Yonggwang - 5, 6 nuclear power plant

    International Nuclear Information System (INIS)

    1995-05-01

    This is a contract of design of an atomic reactor system in Yonggwang 5, 6 nuclear power plant. It has the general contract condition. In the appendix, it indicates the detail regulations between two parties which are the coverage of division on the responsibility, schedule of the delivery, standard of the technology, guarantee, drawing and paper support of the Korea Electric Power Corporation, support of technology drill, test, regulations of code and standard and list of items and prices.

  18. Photoionization of atoms encapsulated by cages using the power-exponential potential

    International Nuclear Information System (INIS)

    Lin, C Y; Ho, Y K

    2012-01-01

    The systems of confined atoms in cages have received considerable attention for decades due to interesting phenomena arising from the effect of cage environment on the atom. For early theoretical work based on empirical model potentials, the Dirac δ-potential, i.e. the so-called bubble potential, and the attractive short-range spherical shell potential are conventionally used for the description of interaction between the valence electron of confined atom and the cage. In this work, the power-exponential potential with a flexible confining shape is proposed to model the cages. The methods of complex scaling in the finite-element discrete variable representation are implemented to investigate the hydrogen, hydrogen-like ions and alkali metals encapsulated by the cages. The energy spectrum varying with the confining well depth exhibits avoided crossings. The influence of cage on atomic photoionization leading to the oscillation behaviour or the so-called confinement resonances in cross sections is demonstrated in a variety of confined atomic systems. In comparisons with existing predictions using the Dirac δ-potential and the attractive short-range spherical shell potentials, our results show the significant influence of cage thickness and smooth shell boundary on the photoionization. The drastic changes of cross sections due to the character of cage are presented and discussed for the encaged lithium and sodium atoms. The present model is useful for clarifying the boundary effect of confining shell on the endohedral atoms. (paper)

  19. Application of wind power systems to the Service Area of the Minnesota Power and Light Company. Final report, July 1975--August 1976

    Energy Technology Data Exchange (ETDEWEB)

    Lindquist, O.H.; Malver, F.S.

    1976-01-01

    Honeywell, in a joint effort with Minnesota Power and Light Company (MP and L), Boeing Vertol Company, and Dr. C.G. Justus, Georgia Institute of Technology, has conducted a regional application study of wind energy systems. Minnesota Power and Light Company, an investor-owned company with 853-MW owned capacity, has served as the case study subject utility. An initial system definition was developed based on available wind information and near-term wind turbine generator (WTG) technology. The system was tailored to fit MP and L's forecasted generation needs and the company's existing transmission and distribution system. Honeywell developed a WECS simulation to convert wind data to wind energy available for input to the utility's grid. The simulation was used to evaluate the performance of preliminary design wind turbine generators developed for ERDA/NASA by the General Electric Company and Kaman Aerospace Corporation, and to evaluate the performance of a wind turbine optimized for the Northern Minnesota wind regime and developed by the Boeing Vertol Company under subcontract to Honeywell.

  20. Study of the dynamic operational characteristics of the Taiwan Power Company system - a nuclear majority system

    International Nuclear Information System (INIS)

    Yu, I.H.

    1982-01-01

    All conclusions drawn in this dissertation are based on the results of about six hundred study cases. The dynamic characteristics of the present Taiwan Power Company system are very different not only from the characteristics of any other power system in the world but also from Taipower's own history characteristics. Based on the engineers' knowledge, this dissertation takes a calculation risk approach to deal with the problems in the energy systems. Chapter I introduces the information related with the stability of the present Taipower system. Taipower operating engineers are facing the problem of committing a large amount of nuclear generation at a low base load level. The general introduction of the stability program developed for this study is described in Chapter II. In Chapter III, the processes of performing the transient stability study are explained to show how this study was performed. Critical tie flows were suggested in Chapter IV, which might help balance the nuclear generation and thermal generation at the base load level and plan the unit maintenance schedule. Several operation modes which may increase the degree of stability or minimize the number unit trippings were discussed in Chapter V. In Chapter VI, how to adjust the load shedding policy to improve the stability are discussed. The remote tripping scheme which is effective in preventing massive system blackout was studied in Chapter VII. Some broader concepts in load management are presented in Chapter VII for Taipower's management decision

  1. Prospects and constraints in biofouling control at Madras Atomic Power Plant: a historical perspective

    International Nuclear Information System (INIS)

    Azariah, Jayapaul; Nair, K.V.K.

    1995-01-01

    The paper describes the various aspects of Madras Atomic Power Station -its prospects and constraints in biofouling control. It reviews the achievements in biofouling control. It also includes current studies on barnacles and mussels, suspended particulate matter as an antifoulant, flow conditions and larval settlement and biofilm and larval adhesion along with recommendations. (V.R.). 21 refs

  2. Genetic effects of prolonged combined irradiation of laboratory animals in Chernobyl Atomic Power Plant alienation zone

    International Nuclear Information System (INIS)

    Savtsova, Z.D.; Vojejkova, Yi.M.; Dzhaman, N.Yi.; Yudyina, O.Yu.; Yindik, V.M.; Kovbasyuk, S.A.

    2000-01-01

    Prolonged combined (external and internal) irradiation of mice in the r zone of the Chernobyl Atomic Power Plant caused hereditary disturbances physiological defects in the posterity irrespective of the fact if one or both parents were irradiated. The most favourable indices were observed in F2 posterity of the both exposed parents

  3. Biofouling in the condenser cooling conduits of Madras Atomic Power Station

    International Nuclear Information System (INIS)

    Thiyagarajan, V.; Subramoniam, T.; Venugopalan, V.P.; Nair, K.V.K.

    1995-01-01

    The present paper deals with various aspects fouling organisms collected from the condenser cooling water circuit of Madras Atomic Power Station (MAPS II) their biomass, thickness, composition and length frequency distribution of one of the major species namely, B. reticulatus. (author). 8 refs., 1 tab., 2 figs

  4. Design of calandria-end shield support diaphragm of Narora Atomic Power Project

    Energy Technology Data Exchange (ETDEWEB)

    Srivastava, S K; Nanda Kumar, S; Kakodkar, A

    1975-01-01

    The calandria-end shield diaphragm is one of the important components in Narora Atomic Power Plant. The support diaphragm is designed against elastic and plastic instability failures. Method of analysis for elastic and plastic instability is discussed for normal loading, pipe rupture loading, and earthquake loading.

  5. Nuclear power. Nuclear fuel cycle and waste management. 1990-2002. International Atomic Energy Agency publications

    International Nuclear Information System (INIS)

    2002-02-01

    This document lists all sales publications of the International Atomic Energy Agency dealing with Nuclear Power, Nuclear Fuel Cycle and Waste Management, issued during the period 1990-2002. It gives a short abstract of these publications along with contents and their costs

  6. Design of calandria-end shield support diaphragm of Narora Atomic Power Project

    International Nuclear Information System (INIS)

    Srivastava, S.K.; Nanda Kumar, S.; Kakodkar, A.

    1975-01-01

    The calandria-end shield diaphragm is one of the important components in Narora Atomic Power Plant. The support diaphragm is designed against elastic and plastic instability failures. Method of analysis for elastic and plastic instability is discussed for normal loading, pipe rupture loading and earthquake loading. (author)

  7. Nuclear Regulatory Commission issuances. Volume 44, Number 3

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-09-01

    This report includes issuances received during September 1996. After reviewing in detail each of the claims made in this informal proceeding the presiding officer sustained the staff of the USNRC in its determination that the applicant did not pass the written portion of his examination to become a licensed operator of a nuclear power plant. In the proceeding concerning citizen group challenges to the decommissioning plan for the Rowe Yankee power station, the licensing board grants licensee Yankee Atomic Electric Company`s motion for summary disposition.

  8. DYNAMICS OF MAIN PROFITABILITY INDICATORS IN DISTRIBUTION OF FOOD AND AGRICULTURAL PRODUCTS OF THE COMPANY EL CASIO COM SRL-SLOBOZIA

    Directory of Open Access Journals (Sweden)

    Laurentiu MUNTEANU

    2013-01-01

    Full Text Available The return of distribution companies is related to the performance of activity based management, which can be expressed through a system of indicators reflecting their activity. This paper aims to analyse the company EL CASIO COM SRL Slobozia, active in the distribution field of food and agricultural products in Ialomita and Calarasi counties. We analysed the economic indicators between 1999-2009 from which resulted the main elements influencing the company’s revenue and profitability. The analysed period revealed that the break-even was achieved in 2003 with 5 employees, a revenue of 1899, 16 thousand lei whereas the expenses amounted 1732 thousand lei and labour productivity was set at 379, 8 thousand lei/ worker. The resulted trend after presenting and interpreting the exponential function Y=3,862·X10,5480866·X 21,239971is given based on the changes of income level (Y, from the factors of influence, represented by the amount of equity (x 1 and labour used (x 2. The multiple correlation ratios (rx 1x 2 = 0, 9505, confirm the influence intensity of the two factors upon the trends in revenue growth. As result we can see trends in revenue growth with amplification factors of influence

  9. Measuring efficiency and productivity change in power electric generation management companies by using data envelopment analysis: A case study

    International Nuclear Information System (INIS)

    Fallahi, Alireza; Ebrahimi, Reza; Ghaderi, S.F.

    2011-01-01

    This paper provides an empirical analysis of the determinants of energy efficiency in 32 power electric generation management companies over the period 2005–2009. The study uses non-parametric Data Envelopment Analysis (DEA) to estimate the relative technical efficiency and productivity change of these companies. In order to verify the stability of our DEA model and the importance of each input variable, a stability test is also conducted. The results of the study indicate that average technical efficiency of companies decreased during the study period. Nearly half of the companies (14) are below this average level of 88.7% for five years. Moreover, it is shown that the low increase of productivity changes is more related to low efficiency rather than technology changes. -- Highlights: ► DEA was applied on the 32 power electric generation management companies. ► A stability test is applied to verify the stability of DEA model. ► Average technical efficiency of companies decreased during the study period. ► The low increase of productivity changes is more related to low efficiency changes.

  10. Surge currents and voltages at the low voltage power mains during lightning strike to a GSM tower

    Energy Technology Data Exchange (ETDEWEB)

    Markowska, Renata [Bialystok Technical University (Poland)], E-mail: remark@pb.edu.pl

    2007-07-01

    The paper presents the results of numerical calculations of lightning surge currents and voltages in the low voltage power mains system connected to a free standing GSM base station. Direct lightning strike to GSM tower was studied. The analysis concerned the current that flows to the transformer station through AC power mains, the potential difference between the grounding systems of the GSM and the transformer stations and the voltage differences between phase and PE conductors of the power mains underground cable at both the GSM and the transformer sides. The calculations were performed using a numerical program based on the electromagnetic field theory and the method of moments. (author)

  11. Migration of Older to New Digital Control Systems in Nuclear Power Plant Main Control Rooms

    Energy Technology Data Exchange (ETDEWEB)

    Kovesdi, Casey Robert [Idaho National Lab. (INL), Idaho Falls, ID (United States); Joe, Jeffrey Clark [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2016-04-01

    The United States (U.S.) Department of Energy (DOE) Office of Nuclear Energy (NE) has the primary mission to advance nuclear power by resolving socio-technical issues through research and development (R&D). One DOE-NE activity supporting this mission is the Light Water Reactor Sustainability (LWRS) program. LWRS has the overall objective to sustain the operation of existing commercial nuclear power plants (NPPs) through conducting R&D across multiple “pathways,” or R&D focus areas. The Advanced Instrumentation, Information, and Control (II&C) Systems Technologies pathway conducts targeted R&D to address aging and reliability concerns with the legacy instrumentation and control (I&C) and related information systems in operating U.S. NPPs. This work involves (1) ensuring that legacy analog II&C systems are not life-limiting issues for the LWR fleet, and (2) implementing digital II&C technology in a manner that enables broad innovation and business improvement in the NPP operating model. Under the LWRS Advanced II&C pathway, Human Factors experts at Idaho National Laboratory (INL) have been conducting R&D in support of NPP main control room (MCR) modernization activities. Work in prior years has focused on migrating analog I&C systems to new digital I&C systems (). In fiscal year 2016 (FY16), one new focus area for this research is migrating older digital I&C systems to new and advanced digital I&C systems. This report summarizes a plan for conducting a digital-to-digital migration of a legacy digital I&C system to a new digital I&C system in support of control room modernization activities.

  12. Migration of Older to New Digital Control Systems in Nuclear Power Plant Main Control Rooms

    International Nuclear Information System (INIS)

    Kovesdi, Casey Robert; Joe, Jeffrey Clark

    2016-01-01

    The United States (U.S.) Department of Energy (DOE) Office of Nuclear Energy (NE) has the primary mission to advance nuclear power by resolving socio-technical issues through research and development (R&D). One DOE-NE activity supporting this mission is the Light Water Reactor Sustainability (LWRS) program. LWRS has the overall objective to sustain the operation of existing commercial nuclear power plants (NPPs) through conducting R&D across multiple ''pathways,'' or R&D focus areas. The Advanced Instrumentation, Information, and Control (II&C) Systems Technologies pathway conducts targeted R&D to address aging and reliability concerns with the legacy instrumentation and control (I&C) and related information systems in operating U.S. NPPs. This work involves (1) ensuring that legacy analog II&C systems are not life-limiting issues for the LWR fleet, and (2) implementing digital II&C technology in a manner that enables broad innovation and business improvement in the NPP operating model. Under the LWRS Advanced II&C pathway, Human Factors experts at Idaho National Laboratory (INL) have been conducting R&D in support of NPP main control room (MCR) modernization activities. Work in prior years has focused on migrating analog I&C systems to new digital I&C systems (). In fiscal year 2016 (FY16), one new focus area for this research is migrating older digital I&C systems to new and advanced digital I&C systems. This report summarizes a plan for conducting a digital-to-digital migration of a legacy digital I&C system to a new digital I&C system in support of control room modernization activities.

  13. Electricity, nuclear power and fuel cycle in OECD countries, main data 1987

    International Nuclear Information System (INIS)

    1987-01-01

    A questionnaire on Electricity Generation. Nuclear Power and Fuel Cycle Data is distributed annually to OECD Member Countries. In the questionnaire of January 1987, countries were asked to provide historical data for 1985 and 1986 and most likely projections up to the year 2005. The replies to the questionnaire or the results of the discussions between national correspondents and the Secretariat are presented in this Booklet. The Secretariat has, in some cases, referred to IEA's electricity-related data and IAEA's nuclear plant data. Where data were still unavailable the Secretariat made estimates based on information from other sources. Data for 1986 are provisional for several countries. The data on electricity generation and electric capacity are presented to the year 2005, and the data on fuel cycle services to the year 2000. The installed nuclear capacity of the OECD countries for the year 2000 is estimated at 340 GWe, a 25 GWe reduction from the estimate in the 1986 Booklet. This reduction is mainly due to revised lower projections of electricity demand. The Addendum contains an analysis of the present and past projections for installed nuclear capacity to 2000. It shows the total capacity of those plants connected to the grid, under construction and firmly planned to be in operation in 2000 as 294 GWe. The new projection of 340 GWe is well above this estimate, indicating that some countries are still planning to expand their nuclear capacities. In only one country does it appear that planned expansion has been affected specifically by the Chernobyl accident. The electricity generation and production data for fuel cycle services refer to those facilities located within the country, and thus exclude imports. The fuel cycle requirements, however, refer to the amounts of fuel cycle materials and services necessary for national nuclear power programmes

  14. Simulation of main steam and feedwater system of full scope simulator for Qinshan 300 MW Nuclear Power Unit

    International Nuclear Information System (INIS)

    Zhao Xiaoyu

    1996-01-01

    The simulation of main steam and feedwater system is the most important and maximal part in secondary circuit model, including all of main steam and feedwater's thermal-hydraulic properties, except heat-exchange of secondary side of steam generator. It simulates main steam header, steam power in each stage of turbine, moisture separator-reheater, deaerator, condenser, high pressure and low pressure heater, auxiliary feedwater and main steam bypass in full scope

  15. Installation modification of the reactor No.2 of Ikata nuclear power plant of Shikoku Electric Power Company, Inc

    International Nuclear Information System (INIS)

    1980-01-01

    The application was made on August 25, 1979, from the president of the Shikoku Electric Power Company, Inc., to the Minister of International Trade and Industry, relating to the installation modification of the reactor No. 2 in the Ikata nuclear power plant. The inquiry was submitted on September 28, 1979, from the Minister of International Trade and Industry to the Nuclear Safety Commission, after the safety evaluation in the Ministry of International Trade and Industry, and the investigation and deliberation were started on October 1, 1979, in the Nuclear Safety Commission. The content of the modification is to add the circuit actuated by the abnormal low pressure signal of the reactor to the actuating circuit of the emergency core cooling system (ECCS) and to increase the new fuel storage capacity from about 1/3 core to about 2/3 core. The additional signal circuit is composed of the logic circuit of ''2 out of 4'' and is multichannel design. The circuit is independent from the reactor control system and the conventional signal circuit of the concurrence of low pressure in the reactor and low level in the pressurizer. With the addition of the circuit of abnormal low pressure signal of the reactor, the countermeasures for preventing ECCS start by mistake are also added. These modifications give no influence to the functions of the reactor control system and reactor protection system. The function and the performance of ECCS were analyzed and evaluated accompanying these modifications assuming the loss of coolant accident. Concerning the new fuel storage capacity, the type of racks is modified from angle type to can type, and the subcriticality is kept even at the time of water flood. (Nakai, Y.)

  16. Application study of the project management on the nuclear power projects in China Institute of Atomic Energy

    International Nuclear Information System (INIS)

    Ji Cunxing

    2012-01-01

    The article introduced the actions of foreign and domestic nuclear power technical services in China Institute of Atomic Energy, the project management theory is applied to the organization, implementation and control of the nuclear power projects. It is analyzed the quality, schedule , investment etc of nuclear power projects, the improving measures and suggestions are bring forward on the project management organization, quality assurance, reduce cost etc. It will raise its nuclear power project management level in China Institute of Atomic Energy. (author)

  17. A study on the characteristics, predictions and policies of China’s eight main power grids

    International Nuclear Information System (INIS)

    Wang, Jianzhou; Dong, Yao; Jiang, He

    2014-01-01

    Highlights: • Indian blackout is analyzed as a warning for China’s power system. • Issues and recommendations of China’s eight power grids are presented. • Five models are employed for scenario analysis on power generation and consumption. • The optimized combined model outperforms other models. • Methods towards balancing power generation and environmental impacts are proposed. - Abstract: Electricity is an indispensable energy source for modern social and economic development. However, large-scale blackouts can cause incalculable loss to society. In 2012, three major Indian power grids collapsed, resulting in the interruption of the electricity supply to over 600 million people. To avoid an event like that, China needs to forecast the power generation and consumption of eight power grids effectively. This paper first analyzes the characteristics of eight power grids and then proposes a combined model based on three improved grey models optimized by a differential evolution algorithm to predict electricity production and consumption of each power grid. The optimized combined forecasting model provides a better prediction than other models, and it is also the most workable and satisfactory model. Experiment results show electricity production and consumption would increase. In consideration of the real situation and existing problems, some suggestions are proposed. The government could decrease thermal power and exploit renewable energy power, like hydroelectric power, wind power and solar power, to ensure the safe and reliable operation of China’s major power grids and protect environment

  18. Performance of the Electric power companies of Burkina Faso, the Ivory Coast, Mali and Senegal, and their organizational models

    International Nuclear Information System (INIS)

    Girod, J.

    1993-01-01

    The history of the technical, economic, and financial performances of these four countries' power companies over the past two decades is recounted, and then interpreted as the result of the existing organizational models. The changes that have occurred can be understood in long-term perspective by comparing the performance of these companies to the characteristics, rules, and objectives used to define the models, which also helps explain the history of performance indicator variations. Two models are defined: one for the physical plant and one for the management. These correspond to two successive phases in the organization and operation of the electrical sector. Rural electrification and regional interconnection will be important factors in any new model or models developed for the future, because the forms they take is likely to modify the characteristics of these national power companies. 26 refs., 1 fig., 3 tabs

  19. Measuring Situation Awareness of Operating Team in Different Main Control Room Environments of Nuclear Power Plants

    Directory of Open Access Journals (Sweden)

    Seung Woo Lee

    2016-02-01

    Full Text Available Environments in nuclear power plants (NPPs are changing as the design of instrumentation and control systems for NPPs is rapidly moving toward fully digital instrumentation and control, and modern computer techniques are gradually introduced into main control rooms (MCRs. Within the context of these environmental changes, the level of performance of operators in a digital MCR is a major concern. Situation awareness (SA, which is used within human factors research to explain to what extent operators of safety-critical systems know what is transpiring in the system and the environment, is considered a prerequisite factor to guarantee the safe operation of NPPs. However, the safe operation of NPPs can be guaranteed through a team effort. In this regard, the operating team's SA in a conventional and digital MCR should be measured in order to assess whether the new design features implemented in a digital MCR affect this parameter. This paper explains the team SA measurement method used in this study and the results of applying this measurement method to operating teams in different MCR environments. The paper also discusses several empirical lessons learned from the results.

  20. Atomic Power

    African Journals Online (AJOL)

    controls the electrons around it, and like a strong spring pushes other nuclei away. Later experiments performed, notably by Cahd- wick, one of Rutherford's associates during his. Cambridge University days (when Rutherford was. Head of the famous Cavendish Laboratories, Cam- bridge, England), showed that the nucleus ...

  1. Atomic Power

    African Journals Online (AJOL)

    carbon can also exist as 6Cl J, i.e. a heavier species, because its mass .... mium or boron, which have the property of absorb- ing neutrons ... When a reactor plant is in operation, it is neces- ... are replaced by uranium dioxide, the higher gas.

  2. Wastes power generation introduction manual. Main edition; Haikibutsu hatsuden donyu manual. Honpen

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-03-01

    A practical and specific working manual was prepared that satisfies the standards and criteria defined in the relevant law such as the Sanitation and Environment Ordinance No. 249, the guideline for generation of dioxins caused by refuse disposal, and that enables the reports evaluating the wastes quantitatively to be submitted to heads of the local governments when persons in charge of planning the introduction of wastes power generation at local governments discuss the wastes power generation systems. Taking general combustible wastes and sewage sludge treatments as the object, this paper details from the economic performance to size of wastes treatment at the priority limit for the power generation facility introduction. The subject power generation systems include the following: the stoker furnace/separation type ash melting furnace power generation system, the fluidized bed/separation type ash melting furnace power generation system, and the direct type gasification melting furnace power generation system, whose establishment of safety, reliability and stability have been verified by full-size system operation record available at the local governments, the gas turbine re-powering composite type power generation system (gas turbine power plants are installed beside the incineration furnaces) that makes high-efficiency power generation possible, and the RDF power generation system (power generation by mixed combustion with general refuses, and power generation using RDF (refuse derived fuel) exclusive combustion). Other important discussion and assessment items include environment and resource utilization performances. (NEDO)

  3. Sierra Pacific Power Company Alturas Transmission Line Project, Final Environmental Impact Report/Environmental Impact Statement. Volume 3: Appendices

    International Nuclear Information System (INIS)

    1995-11-01

    Sierra Pacific Power Company has proposed the construction and operation of a 345,000 volt overhead electric power transmission line from Alturas, California to Reno, Nevada. This Environmental Impact Report/Environmental Impact Statement will assess the potential environmental impacts of the proposed project and alternatives. This report contains Appendices A--I which contain the following: glossary/abbreviations; scoping report; structure coordinate summary; air quality; biological resources; geology; noise; visual contrast rating forms; and cultural resources

  4. The Chip-Scale Atomic Clock - Low-Power Physics Package

    Science.gov (United States)

    2004-12-01

    36th Annual Precise Time and Time Interval (PTTI) Meeting 339 THE CHIP-SCALE ATOMIC CLOCK – LOW-POWER PHYSICS PACKAGE R. Lutwak ...pdf/documents/ds-x72.pdf [2] R. Lutwak , D. Emmons, W. Riley, and R. M. Garvey, 2003, “The Chip-Scale Atomic Clock – Coherent Population Trapping vs...2002, Reston, Virginia, USA (U.S. Naval Observatory, Washington, D.C.), pp. 539-550. [3] R. Lutwak , D. Emmons, T. English, and W. Riley, 2004

  5. Overview of electric power industry of main countries in the world

    International Nuclear Information System (INIS)

    2013-01-01

    The electric power supply system, power producer, regulation system, electricity liberalization, power demand and supply, electricity rate, development of electric power sources, nuclear power generation and renewable energy of six countries such as USA, England, German, France, Russia and China are reported. On USA, 3,754 x 10 9 kWh of total electric energy, 104 of nuclear reactors are running and giving careful consideration to safety of the plant. Shale gas production is increasing, and new technology of electric car, smart grid and demand response is developing. On England, 368 x 10 9 kWh of total electric energy, which consisted of 70.4% thermal power, 18.8% nuclear power and 10.8% renewable energy, 18 nuclear reactors are running, but almost nuclear power plants will be closed until 2023. Biomass and wind power have been developed. On German, 609 x 10 9 kWh of total electric energy, 9 nuclear reactors are running but closed till 2022, the renewable energy such as wind power and photovoltaic is introduced. On France, 542 x 10 9 kWh total electric energy, which consisted of 9% hydroelectricity, 9% thermal power, 78% nuclear power and 4% renewable energy. The renewable energy plan is formulated. On Russia, 1,052 x 10 9 kWh total electric energy consisted of 67.8% thermal power, 15.7% hydroelectricity and 16.4% nuclear power, 32 nuclear power plants are running and 9 nuclear reactors building. On China, 4,693 x 10 9 kWh power consumption, 6 nuclear power plants are running to generate 1.85% electric energy, the objects of nuclear power generation and renewable energy were announced. (S.Y.)

  6. 75 FR 62531 - Alabama Power Company; Project No. 349-150-Alabama Martin Dam Hydroelectric Project; Notice of...

    Science.gov (United States)

    2010-10-12

    ... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission Alabama Power Company; Project No. 349-150--Alabama Martin Dam Hydroelectric Project; Notice of Proposed Restricted Service List for a... the Martin Dam Hydroelectric Project. The Programmatic Agreement, when executed by the Commission, the...

  7. 75 FR 44292 - Northern States Power Company; Prairie Island Nuclear Generating Plant, Units 1 and 2; Notice of...

    Science.gov (United States)

    2010-07-28

    ... and DPR-60] Northern States Power Company; Prairie Island Nuclear Generating Plant, Units 1 and 2... assessment, and behavioral observation) of the unescorted access authorization program when making the... under consideration to determine whether it met the criteria established in NRC Management Directive (MD...

  8. 75 FR 75704 - Pacific Gas and Electric Company (Diablo Canyon Nuclear Power Plant, Units 1 And 2); Notice of...

    Science.gov (United States)

    2010-12-06

    ... NUCLEAR REGULATORY COMMISSION [Docket Nos. 50-275-LR; 50-323-LR] Pacific Gas and Electric Company (Diablo Canyon Nuclear Power Plant, Units 1 And 2); Notice of Appointment of Adjudicatory Employee... Seismologist, Office of Nuclear Material Safety and Safeguards, has been appointed as a Commission adjudicatory...

  9. 77 FR 7142 - Jersey Central Power and Light Company, PSEG Fossil, LLC; Notice of Availability of Environmental...

    Science.gov (United States)

    2012-02-10

    ... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Project No. 2309-019] Jersey Central Power and Light Company, PSEG Fossil, LLC; Notice of Availability of Environmental Assessment In accordance with the National Environmental Policy Act of 1969 and the Federal Energy Regulatory Commission's...

  10. The Tokai-mura JCO criticality accident and the activities of the accident countermeasure support team of Electric Power Companies, Japan

    International Nuclear Information System (INIS)

    Ogawa, Junko

    2000-01-01

    A criticality accident occurred at the JCO Tokai-mura nuclear fuel processing plant on September 30, 1999. This accident brought the damages which were unrivaled in the history of atomic energy development in Japan, seriously influencing the citizen life to such an extent as requesting for 320,000 inhabitants within 10 kilometers radius to stay indoors for as long as 18 hours. However, it could be said that though three workers suffered fatal injuries, no substantial hazards were made upon the regional inhabitants due to little release of radioactive substances. This video recorded the activities of the Accident Countermeasure Support Team of the Electric Power Companies immediately after the accident occurred, showing the chronological overview of the particulars of the accident. (author)

  11. De minimis applications for alternative disposal of very low level radioactive waste at Duke Power Company

    International Nuclear Information System (INIS)

    Lan, C.

    1986-01-01

    Existing NRC regulations provide no minimum level of radioactivity in waste from a licensee's facility that may be disposed of in a manner other than as radioactive waste. With one exception, in 10CFRsection20.306, licensees may dispose of certain levels of tritium and carbon-14 in liquid-scintillation and animal-carcass waste without regard to its radioactivity. In the interim, before specific or generic provisions for disposing of very low level radioactive wastes are adopted through rule making, licensees have another alternative for obtaining approval to dispose of large volumes of materials contaminated with very low levels of radioactivity under provision 10CFRsection20.302(a) ''Method for obtaining approval of proposed disposal procedures.'' This paper provides the experiences of obtaining both NRC and states (North Carolina and South Carolina) approval for disposing of very low-level radioactive wastes from Duke Power Company's nuclear stations. The approved disposal procedures include landfarming of water treatment residues, on-site disposal (burial) of sand and feedwater heaters, and include offsite release for treatment and disposal of sanitary sewage sludge. In summary, users of radioactive materials should not exclude this approach in their quest to reduce the volume of radioactive waste. It is expected that such submittals could provide a data base for further development of generic limits for radioactive wastes

  12. Vogtle Unit 1 readiness review: Assessment of Georgia Power Company readiness review pilot program

    International Nuclear Information System (INIS)

    Lewis, G.

    1987-09-01

    Georgia Power Company (GPC) performed a readiness review at Vogtle Unit 1 as a pilot program. The pilot program was a new and innovative approach for the systematic and disciplined review, with senior management involvement, of GPC's implementation of design, construction, and operational readiness processes. The program's principal objective was to increase the level of assurance that quality programs at Vogtle Unit 1 have been accomplished in accordance with regulatory requirements. This report assesses the effectiveness of the GPC's readiness review pilot program (RRPP) at Vogtle Unit 1. It includes (1) an overview of what was experienced during the program's implementation, (2) an assessment of how well program objectives were met, and (3) lessons learned on the future use of the readiness review concept. Overall, GPC and the NRC staff believe that the RRPP at Vogtle Unit 1 was a success and that the program provided significant added assurance that Vogtle Unit 1 licensing commitments and NRC regulations have been adequately implemented. Although altering the NRC licensing review process for the few plants still in the construction pipeline may not be appropriate, licensees may benefit significantly by performing readiness reviews on their own initiative as GPC did for Vogtle. (7 refs.)

  13. Applying wind turbines and battery storage to defer Orcas Power and Light Company distribution circuit upgrades

    International Nuclear Information System (INIS)

    Zaininger, H.W.; Barnes, P.R.

    1997-03-01

    The purpose of this study is to conduct a detailed assessment of the Orcas Power and Light Company (OPALCO) system to determine the potential for deferring the costly upgrade of the 25-kV Lopez- Eastsound circuit, by the application of a MW-scale wind farm and battery storage facilities as appropriate. Local wind resource data has been collected over the past year and used to determine MW-scale wind farm performance. This hourly wind farm performance data is used with measured hourly Eastsound load data, and recent OPALCO distribution system expansion plans and cost projections in performing this detailed benefit-cost assessment. The OPALCO distribution circuit expansion project and assumptions are described. MW-scale wind farm performance results are given. The economic benefit-cost results for the wind farm and battery storage applications on the OPALCO system using OPALCO system design criteria and cost assumptions are reported. A recalculation is presented of the benefit-cost results for similar potential wind farm and battery storage applications on other utility systems with higher marginal energy and demand costs. Conclusions and recommendations are presented. costs. Conclusions and recommendations are presented

  14. Study on the identification of main drivers affecting the performance of human operators during low power and shutdown operation

    International Nuclear Information System (INIS)

    Kim, Ar Ryum; Park, Jinkyun; Kim, Ji Tae; Kim, Jaewhan; Seong, Poong Hyun

    2016-01-01

    Highlights: • The performance of human operator during LPSD operation is significantly important. • Human performance is affected by drivers such as procedure, training, and etc. • Main drivers during LPSD operation at domestic NPPs were suggested. • It is expected that it will be used for estimating human reliability during LPSD operation. - Abstract: In the past, many researchers believed that a reactor during low power and shutdown operation was sufficiently safe. This belief has been changed by the number of accidents during such types of operation, which is significantly high. Also, it was pointed out that one of the main differences between low power and shutdown operation and full power operation is the significance of human action because there are huge amounts of human actions due to extensive maintenance and testing while automatic control and safety functions may be disabled and procedures are insufficient or incomplete. This paper suggests the main drivers in performing human reliability analysis. For this study, we reviewed eight reports relating to human performance during low power and shutdown operation and applied a root cause analysis method for 53 human or human-related events at domestic nuclear power plants to derive the main drivers that affect the occurrence of those events. As a result, several main drivers were derived, such as procedures, training, experience of personnel, and workload/stress. It is expected that these main drivers will be used to perform human reliability analysis for low power and shutdown operation.

  15. The recent activities of nuclear power globalization. Our provision against global warming by global deployment of our own technologies as integrated nuclear power plant supply company'

    International Nuclear Information System (INIS)

    Yamauchi, Kiyoshi; Suzuki, Shigemitsu

    2008-01-01

    Mitsubishi Heavy Industries, Ltd. (MHI) is striving to expand and spread nuclear power plants as an 'Integrated Nuclear Power Plant Supply Company' based on its engineering, manufacturing, and technological support capabilities. The company also has ample experience in the export of major components. MHI is accelerating its global deployment through the market introduction of large-sized strategic reactor US-APWR, the joint development of a mid-sized strategic reactor ATMEA1 with AREVA, and a small strategic reactor PBMR. The company also plans to internationally deploy technologies for the nuclear fuel cycle. We present here the leading-edge trends in the global deployment of these nuclear businesses, all of which help to solve the energy and environmental issues in the world. (author)

  16. Scenarios for the popular initiatives 'Strom ohne Atom' (Electricity without nuclear power) and 'Moratorium Plus'

    International Nuclear Information System (INIS)

    Eckerle, K.; Haker, K.; Hofer, P.

    2001-01-01

    This report for the Swiss Federal Office of Energy (SFOE) presents the results of a study made on the possible effects of two Swiss Popular Initiatives which called for the shutdown of nuclear power stations in Switzerland ('Strom ohne Atom'), the restriction of their operating life and the abstention from building new atomic power stations ('Moratorium Plus'). The report examines the energetic and financial consequences of the initiatives. The approaches used for the analysis are described and the energy policy actions required to avoid gaps in the supply of power after the possible closure of the power stations are discussed. Apart from a reference scenario (long-term utilisation of nuclear energy), scenarios for power generation using co-generation are presented. The problems posed by the resulting CO 2 and NO x emissions are discussed. Further scenarios review the contribution to be made by renewable sources of energy and increasing energy-conservation efforts. The costs of the shutdown of nuclear power stations are discussed and the results of a sensitivity analysis are presented

  17. Research on characteristics of communication content of operation crew in digital main control room of nuclear power plant

    International Nuclear Information System (INIS)

    Zhang Li; Ye Haifeng; Qing Tao; Li Pengcheng

    2015-01-01

    Communication content, communication mode and timeliness of communication are the main three factors that influence the effectiveness of the communication between team members. Based on the work domain analysis to execution of state-oriented procedures (SOP), the assumptions for operation crews' characteristics of the communication content in executing SOP were proposed, which supposed that the power plant status and parameters, power plant system functions and equipment, and SOP as well were the main communication contents. On a full-scope simulator of nuclear power plant, three operation crews performed experiments simulating accident scenarios. The results show that the assumptions of characteristics of the communication content are valid. (authors)

  18. Leading Players of the European Power and Gas Industry Overview of Groups - SWOTs - Benchmarking - Company Profiles and Financials

    International Nuclear Information System (INIS)

    2017-09-01

    This study presents: The medium-term and mega trends of the industry market developments and geographical segments; The competitive landscape and the main corporate rankings; The main conclusions of the report, summarised in 10 analytical slides. Content: 1. Overview: The Sector, Ranking, Performance Analysis; 2. Company Profiles: EDF, Enel, Engie, RWE, E.ON, SSE, Iberdrola, Gas Natural Fenosa, Vattenfall, EDP; 3. Sources; 4. Annexes

  19. The Industrial Photography and the Steel Company Archive of Puerto de Sagunto: Representation, Power and Identity (1944-1976

    Directory of Open Access Journals (Sweden)

    Esteban Torres

    2015-01-01

    Full Text Available This article makes a contribution on photo - documentary archives in the steel industry as a source of knowledge and sociological tool. It deals with the case of documentary photo archive Altos Hornos de Vizcaya and Altos Hornos del Mediterráneo in Sagunto (Puerto between 1944 and 1976. The article discusses the need to analyze the role of company photographers and his role as "rapporteurs" of labor and social discourse of the company. We analyze the photographic archive as "artifact of power" with a narrative structure and autonomous with functionality within the industrial process related to the generation of a structure of symbolic and identity discourses.

  20. Solid cancer mortality associated with chronic external radiation exposure at the French atomic energy commission and nuclear fuel company.

    Science.gov (United States)

    Metz-Flamant, C; Samson, E; Caër-Lorho, S; Acker, A; Laurier, D

    2011-07-01

    Studies of nuclear workers make it possible to directly quantify the risks associated with ionizing radiation exposure at low doses and low dose rates. Studies of the CEA (Commissariat à l'Energie Atomique) and AREVA Nuclear Cycle (AREVA NC) cohort, currently the most informative such group in France, describe the long-term risk to nuclear workers associated with external exposure. Our aim is to assess the risk of mortality from solid cancers among CEA and AREVA NC nuclear workers and its association with external radiation exposure. Standardized mortality ratios (SMRs) were calculated and internal Poisson regressions were conducted, controlling for the main confounding factors [sex, attained age, calendar period, company and socioeconomic status (SES)]. During the period 1968-2004, there were 2,035 solid cancers among the 36,769 CEA-AREVA NC workers. Cumulative external radiation exposure was assessed for the period 1950-2004, and the mean cumulative dose was 12.1 mSv. Mortality rates for all causes and all solid cancers were both significantly lower in this cohort than in the general population. A significant excess of deaths from pleural cancer, not associated with cumulative external dose, was observed, probably due to past asbestos exposure. We observed a significant excess of melanoma, also unassociated with dose. Although cumulative external dose was not associated with mortality from all solid cancers, the central estimated excess relative risk (ERR) per Sv of 0.46 for solid cancer mortality was higher than the 0.26 calculated for male Hiroshima and Nagasaki A-bomb survivors 50 years or older and exposed at the age of 30 years or older. The modification of our results after stratification for SES demonstrates the importance of this characteristic in occupational studies, because it makes it possible to take class-based lifestyle differences into account, at least partly. These results show the great potential of a further joint international study of

  1. Spatio-temporal distribution of 3H in air moisture around Kakrapar Atomic Power Station

    International Nuclear Information System (INIS)

    Joshi, C.P.; Patra, A.K.; Jain, A.K.; Ravi, P.M.; Sarkar, P.K.; Gadhia, M.

    2012-01-01

    Tritium ( 3 H) is the only radioactive isotope of hydrogen. It decays to helium by emission of beta particle with a maximum energy of 18.6 keV. 3 H is most environmentally mobile radionuclide. To accomplish the task of estimating human exposure to tritium, it is necessary to know the tritium concentration in the atmosphere. Environmental Survey Laboratory (ESL) of Health Physics Division (HPD) of Bhabha Atomic Power Station (BARC) located at Kakrapar Atomic Power Station (KAPS) site is regularly monitoring the activity of tritium in the environment to ensure the safety of the public. This paper presents the result of analysis of tritium in atmospheric environment covering an area up to 30 km radius around KAPS site

  2. Development, Dedication and Application of an Automatic Seismic Trip System for Nuclear Power Plants of Taiwan Power Company

    International Nuclear Information System (INIS)

    Liao, Hsin-kai; Lee, Chung-lin; Chen, Chang-kuo; Hsu, Yao-tung; Shyu, Shian-shing

    2011-01-01

    This paper describes the setups of Automatic Seismic Trip System (ASTS), including development, dedication and implementation, for Nuclear Power Plants (NPPs) of Taiwan Power Company (TPC). The purposed ASTS was designed to trip the reactor when big earthquake occurs. These ASTS were classified as class 1E equipment. They were developed and dedicated for safety applications in accordance with IEEE 323-1983, IEEE 344-1987, IEEE 383-1974 and Reg. Guide 1.180 R1. In order to meet the technical specification required by TPC, three sub-units in the ASTS were developed: Earthquake sensors: Kinemetrices FBA-23 triaxial accelerometers are selected since they were successfully used in Taiwan for seismic monitoring for more than 10 years. Signal conditioning module: It is designed to reduce noise from motion accelerometer (FBA-23) and then transmit seismic signal to the set-point and trip unit via instrument amplify circuit, 0.1 to 10Hz band pass filter circuit, absolute-value converter and voltage to current converter. Trip control module: after comparing the seismic signal level and set-point, the result will decide whether to drive the output relay or not. The output relay is used as the interface between ASTS and the reactor protection system in NPP. For the commercial grade item dedication for safety application, five processes were conducted. Those processes are Seismic test: to use plant specific required response spectrum (RRS), the test required spectrum should envelop RRS: Seismic auto-trip accuracy test: must not trip when filtered PA below set point minus 0.05g, and must trip when filtered PA exceeds set point over 0.05g. Trip signals occurred within 10 second interval are considered as same events: NEMA4 water proof test for sensor box: Anti-radiation test: 8.76x100 rads over 40 years: EMI/EMC test: follow RG 1.180 requirement. The ASTS were installed in three NPPs, six units in total, without connection to RPS in 2006. After one year reliable operation, the

  3. Nuclear power, nuclear fuel cycle and waste management, 1986-1999. International Atomic Energy Agency publications

    International Nuclear Information System (INIS)

    2000-04-01

    This catalogue lists all sales publications of the International Atomic Energy Agency dealing with nuclear power and nuclear fuel cycle and waste management and issued during the period of 1986-1999. Some earlier titles which form part of an established series or are still considered of importance have been included. Most publications are in English. Proceedings of conferences, symposia and panels of experts may contain papers in languages other than English, but all of these papers have abstracts in English

  4. Partial thorium loading in the initial core of Kakrapar atomic power reactor

    International Nuclear Information System (INIS)

    Balakrishnan, M.R.

    1993-01-01

    The first unit of Kakrapar nuclear power station has gone critical with some thorium oxide fuel bundles loaded in its core. The thorium helps to flatten the power by reducing neutron flux in the centre of the reactor. However, the placing of the thorium had to be planned with care, because if the neutron flux at a point where a safety rod is located is depressed, the reactivity worth of the safety rod gets reduced. Using a dynamic programing approach, the Reactor Engineering Division of Bhabha Atomic Research Centre worked out a satisfactory configuration for loading the thorium bundles

  5. Regulation for delivery of subsidies for urgent safety measures for atomic power generating facilities

    International Nuclear Information System (INIS)

    1981-01-01

    This rule is established under the provisions of the law for the proper enforcement of subsidy budgets and the ordinance for the execution of this law and to practice these provisions. It is applied to the delivery of subsidies for the expenses of the measures taken beforehand for the security of inhabitants in the surrounding areas of atomic power generating facilities in the emergency time of hazard or the danger of the occurrence of hazard by such facilities. Basic terms are defined, such as atomic power generating facilities and others, prefecture concerned, cities, towns and villages concerned, emergency communication network arrangement business, emergency medical facility arrangement business, business of holding hazard prevention course and expected date of beginning operation. Directors of ministries and agencies concerned deliver, if necessary, to prefectures concerned subsidies for all or a part of the expenses needed for the businesses of emergency communication network arrangement, emergency medical facility arrangement and holding hazard prevention course. The terms of delivery and the amounts of subsidies vary according to the kinds of businesses. Prefectures which intend to apply for the delivery of subsidies shall file to the director of the ministry or agency concerned the specified application attaching the operation plans of businesses and the general explanation of atomic power generating facilities, etc. The decision and conditions of delivery, reports on the situations and results of businesses and other related matters are defined, respectively. (Okada, K.)

  6. 76 FR 77022 - In the Matter of Carolina Power & Light Company, H.B. Robinson Steam Electric Plant, Unit No. 2...

    Science.gov (United States)

    2011-12-09

    ... and 72-3] In the Matter of Carolina Power & Light Company, H.B. Robinson Steam Electric Plant, Unit No. 2, H. B. Robinson Steam Electric Plant, Unit 2, Independent Spent Fuel Storage Installation; Order Approving Indirect Transfer of Control of Licenses I. Carolina Power & Light Company (CP&L, the licensee) is...

  7. A three-stage short-term electric power planning procedure for a generation company in a liberalized market

    International Nuclear Information System (INIS)

    Nabona, Narcis; Pages, Adela

    2007-01-01

    In liberalized electricity markets, generation companies bid their hourly generation in order to maximize their profit. The optimization of the generation bids over a short-term weekly period must take into account the action of the competing generation companies and the market-price formation rules and must be coordinated with long-term planning results. This paper presents a three stage optimization process with a data analysis and parameter calculation, a linearized unit commitment, and a nonlinear generation scheduling refinement. Although the procedure has been developed from the experience with the Spanish power market, with minor adaptations it is also applicable to any generation company participating in a competitive market system. (author)

  8. Nuclear Regulatory Commission issuances, Volume 44, No. 4

    International Nuclear Information System (INIS)

    1996-10-01

    This report includes the issuances received in October 1996. Issuances are from the Commission, the Atomic Safety and Licensing Boards, and the Directors' Decisions. 15 issuances were received and are abstracted individually in the database: Louisiana Energy Services, U.S. Enrichment Corporation, Yankee Atomic Electric Company, General Public Utilities Nuclear Corporation, James L. Shelton, Juan Guzman, Northern States Power Company, TESTCO Inc., Washington Public Power Supply System, all nuclear plants, Cleveland Electric Illuminating Company, Duke Power Company, Florida Power Corporation, and Northeast Nuclear Energy Company (2 issuances). No issuances were received from the the Administrative Law Judges or the Decisions on Petitions for Rulemaking

  9. Nuclear Regulatory Commission issuances, Volume 44, No. 4

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-10-01

    This report includes the issuances received in October 1996. Issuances are from the Commission, the Atomic Safety and Licensing Boards, and the Directors` Decisions. 15 issuances were received and are abstracted individually in the database: Louisiana Energy Services, U.S. Enrichment Corporation, Yankee Atomic Electric Company, General Public Utilities Nuclear Corporation, James L. Shelton, Juan Guzman, Northern States Power Company, TESTCO Inc., Washington Public Power Supply System, all nuclear plants, Cleveland Electric Illuminating Company, Duke Power Company, Florida Power Corporation, and Northeast Nuclear Energy Company (2 issuances). No issuances were received from the the Administrative Law Judges or the Decisions on Petitions for Rulemaking.

  10. Evaluation of low flow characteristics of the Vermont Yankee plant

    International Nuclear Information System (INIS)

    Ganther, S.; LeFrancoi, M.; Bergeron, P.

    1997-01-01

    Boiling water reactor (BWR) core flow instrumentation inaccuracies under low-flow conditions have been the subject of both reactor vendor and regulatory communications in response to incidents of the reported core flow being less than the flow corresponding to the natural-circulation line on the power flow map. During single recirculation loop operation, low-flow conditions exist in the idle recirculation loop, and these flow inaccuracies can affect the usefulness of the reported core flow. Accurate core flow indications are needed above 25% power to administer fuel thermal limits and comply with restrictions associated with the potential for thermal-hydraulic instability. While the natural-circulation line on the power flow map is recognized to be a nominal estimate of the flow expected at and near natural-circulation conditions, the boundaries of the stability regions are associated with conditions assumed in safety analyses performed to demonstrate compliance with general design criteria 10 and 12

  11. Perspectives at the East European engineering companies in the field of power industry in the power-plant construction globalization conditions

    International Nuclear Information System (INIS)

    Ganchev, R.

    2001-01-01

    A large group of companies, institutes, boiler and power engineering work ect. from East European countries, currently in process of reorganization or already transformed into new-established private companies and corporations possess significant intellectual property in the field of thermal power technologies and equipment and broad experience in the design and the erection of thermal power plants. In many cases this know-how is not only competitive to that of the large companies of the West and of the Far East, but frequently it also proves to have a number of advantages. However, in the years of transition in these countries and simultaneous globalization, the owners of this potentials meet with difficulties and restrictions to realize it fully. Large investment projects - for new or replacement capacities or comprehensive rehabilitation or refurbishment of TPPs - are accessible only for the financially powerful EPC-contractors and key equipment suppliers, for which large bank credits are accessible. The near future perspective, for the scientists and experts that have accumulated this capital, is in the opportunity to employ the extensive experience and know-how of this firms in the forthcoming large-scale rehabilitation projects in these countries, and primarily, in the solution of specific problems, that have not been solved so far, provided that the projects are awarded not on the basis of the financial power of the contractors but on the basis of the efficiency of the proposed original solutions

  12. Interaction of antiprotons with Rb atoms and a comparison of antiproton stopping powers of the atoms H, Li, Na, K, and Rb

    DEFF Research Database (Denmark)

    Lühr, Armin Christian; Fischer, Nicolas; Saenz, Alejandro

    2009-01-01

    Ionization and excitation cross sections as well as electron-energy spectra and stopping powers of the alkali metal atoms Li, Na, K, and Rb colliding with antiprotons were calculated using a time-dependent channel-coupling approach. An impact-energy range from 0.25 to 4000 keV was considered....... The target atoms are treated as effective one-electron systems using a model potential. The results are compared with calculated cross sections for antiproton-hydrogen atom collisions....

  13. The main safety problems encountered at Creys-Malville power station

    International Nuclear Information System (INIS)

    Saitcevsky, Boris

    1980-01-01

    The 1200 MW. Creys-Malville nuclear power station, situated on the upper Rhone river, in the Isere department, is the largest unit in construction of the fast neutrons sodium-cooled reactor channel. Realized within a European framework, this power station of a specific character, requires special safety dispositions, owing to the utilization of sodium. Safety rests on a thorough preventive system, particularly at the level of the sodium circuits, the shut-down system and the devices for the evacuation of residual power [fr

  14. Mains power synchronous conducted noise measurement in the 2 to 150 kHz band

    NARCIS (Netherlands)

    Keyer, Cornelis H.A.; Buesink, Frederik Johannes Karel; Leferink, Frank Bernardus Johannes

    2016-01-01

    When testing large stationary equipment for EMC compliance, on-site testing is often the only option. In case of a fixed mains connection, use of an artificial mains network is problematic. Within In the framework of an European Research project on EMI testing of large installations, research has

  15. Measuring sustainability by Energy Efficiency Analysis for Korean Power Companies: A Sequential Slacks-Based Efficiency Measure

    Directory of Open Access Journals (Sweden)

    Ning Zhang

    2014-03-01

    Full Text Available Improving energy efficiency has been widely regarded as one of the most cost-effective ways to improve sustainability and mitigate climate change. This paper presents a sequential slack-based efficiency measure (SSBM application to model total-factor energy efficiency with undesirable outputs. This approach simultaneously takes into account the sequential environmental technology, total input slacks, and undesirable outputs for energy efficiency analysis. We conduct an empirical analysis of energy efficiency incorporating greenhouse gas emissions of Korean power companies during 2007–2011. The results indicate that most of the power companies are not performing at high energy efficiency. Sequential technology has a significant effect on the energy efficiency measurements. Some policy suggestions based on the empirical results are also presented.

  16. Pressurized thermal shock probabilistic fracture mechanics sensitivity analysis for Yankee Rowe reactor pressure vessel

    International Nuclear Information System (INIS)

    Dickson, T.L.; Cheverton, R.D.; Bryson, J.W.; Bass, B.R.; Shum, D.K.M.; Keeney, J.A.

    1993-08-01

    The Nuclear Regulatory Commission (NRC) requested Oak Ridge National Laboratory (ORNL) to perform a pressurized-thermal-shock (PTS) probabilistic fracture mechanics (PFM) sensitivity analysis for the Yankee Rowe reactor pressure vessel, for the fluences corresponding to the end of operating cycle 22, using a specific small-break-loss- of-coolant transient as the loading condition. Regions of the vessel with distinguishing features were to be treated individually -- upper axial weld, lower axial weld, circumferential weld, upper plate spot welds, upper plate regions between the spot welds, lower plate spot welds, and the lower plate regions between the spot welds. The fracture analysis methods used in the analysis of through-clad surface flaws were those contained in the established OCA-P computer code, which was developed during the Integrated Pressurized Thermal Shock (IPTS) Program. The NRC request specified that the OCA-P code be enhanced for this study to also calculate the conditional probabilities of failure for subclad flaws and embedded flaws. The results of this sensitivity analysis provide the NRC with (1) data that could be used to assess the relative influence of a number of key input parameters in the Yankee Rowe PTS analysis and (2) data that can be used for readily determining the probability of vessel failure once a more accurate indication of vessel embrittlement becomes available. This report is designated as HSST report No. 117

  17. Water electrolysis plants for hydrogen and oxygen production. Shipped to Tsuruga Power Station Unit No.1, and Tokai No.2 power station, the Japan Atomic Power Co

    International Nuclear Information System (INIS)

    Ueno, Syuichi; Sato, Takao; Ishikawa, Nobuhide

    1997-01-01

    Ebara's water electrolysis plants have been shipped to Tsuruga Power Station Unit No.1, (H 2 generation rate: 11 Nm 3 /h), and Tokai No.2 Power Station (H 2 generation rate: 36 Nm 3 /h), Japan Atomic Power Co. An outcome of a business agreement between Nissho Iwai Corporation and Norsk Hydro Electrolysers (Norway), this was the first time that such water electrolysis plants were equipped in Japanese boiling water reactor power stations. Each plant included an electrolyser (for generating hydrogen and oxygen), an electric power supply, a gas compression system, a dehumidifier system, an instrumentation and control system, and an auxiliary system. The plant has been operating almost continuously, with excellent feedback, since March 1997. (author)

  18. 76 FR 17712 - In the Matter of Entergy Nuclear Vermont Yankee, LLC and Entergy Nuclear Operations, Inc...

    Science.gov (United States)

    2011-03-30

    ... referred to as tritiated water. The detection of tritiated water in the monitoring well indicated abnormal... leakage to the environment had been stopped by isolating the piping and containing the water leaking from... to the NRC that water samples taken from groundwater monitoring well GZ-3 on site at Vermont Yankee...

  19. Nuclear power and the energy crisis. Politics and the atomic industry. [United Kingdom

    Energy Technology Data Exchange (ETDEWEB)

    Burn, D

    1978-01-01

    An analysis is presented of the politics and economics of the decisions made during the past decade on the development and supply of nuclear power. The subject is treated under the following headings: first competitive reactor - the light water reactor (the paradox of LWR development, competitiveness accepted, the rise of costs - extent and sources, safety of the LWR, peak and collapse 1974 to 76, the LWR outside the United States); AGR to SGHWR (the course of AGR development, sources of the AGR disaster, response to failure - two governments decide, single D and C company, LWR versus SGHWR).

  20. The future of nuclear power: An IAEA perspective. Address at the German atomic forum, Berlin, 27 January 2000

    International Nuclear Information System (INIS)

    ElBaradei, M.

    2000-01-01

    In his address at the German Atomic Forum (Berlin, 27 January 2000), the Director General of the IAEA presented a survey of the prospects for nuclear power as seen from the perspective of the IAEA. The speech focussed on the following aspects: nuclear power and world energy requirements, nuclear and radiation safety, competitiveness of nuclear power, and public support