Safety Evaluation Report related to the operation of Comanche Peak Steam Electric Station, Units 1 and 2 (Docket Nos. 50-445 and 50-446). Supplement No. 8

International Nuclear Information System (INIS)

1985-02-01

Supplement 8 to the Safety Evaluation Report for the Texas Utilities Electric Company application for a license to operate Comanche Peak Steam Electric Station, Units 1 and 2 (Docket Nos. 50-445, 50-446), located in Somervell County, Texas, has been jointly prepared by the Office of Nuclear Reactor Regulation and the Comanche Peak Technical Review Team of the US Nuclear Regulatory Commission. This Supplement provides the results of the staff's evaluation and resolution of approximately 80 technical concerns and allegations relating to civil and structural and miscellaneous issues regarding construction and plant readiness testing practices at the Comanche Peak facility. Issues raised during recent Atomic Safety and Licensing Board hearings will be dealt with in future supplements to the Safety Evaluation Report

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

International Nuclear Information System (INIS)

1983-06-01

Supplement 5 to the Safety Evaluation Report for the application filed by Louisiana Power and Light Company for a license to operate the Waterford Steam Electric Station, Unit 3 (Docket No. 50-382), located in St. Charles Parish, Louisiana has been prepared by the Office of Nuclear Reactor Regulation of the Nuclear Regulatory Commission. The purpose of this supplement is to update the Safety Evaluation Report by providing the staff's evaluation of information submitted by the applicant since the Safety Evaluation Report and its four previous Supplements were issued

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

International Nuclear Information System (INIS)

1985-03-01

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

Safety Evaluation Report related to the operation of Waterford Steam Electric Station, Unit No. 3 (Docket No. 50-382). Supplement 9

International Nuclear Information System (INIS)

1984-12-01

Supplement 9 to the Safety Evaluation Report for Louisiana Power and Light's application for a license to operate Waterford Steam Electric Station, Unit 3 (Docket No. 50-382), located in St. Charles Parish, Louisiana, has been jointly prepared by the Office of Nuclear Reactor Regulation and the Region IV Office of the US Nuclear Regulatory Commission. This supplement provides the results of the staff's completion of its evaluation of approximately 350 allegations and concerns of poor construction practices at the Waterford 3 facility

75 FR 15462 - PPL Susquehanna, LLC; Susquehanna Steam Electric Station, Units 1 and 2; Exemption

Science.gov (United States)

2010-03-29

... section through its Commission-approved Physical Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Cyber Security Plan referred to collectively hereafter as `security plans...

Safety Evaluation Report related to the operation of Comanche Peak Steam Electric Station, Units 1 and 2. Docket Nos. 50-445 and 50-446

International Nuclear Information System (INIS)

1983-03-01

Supplement No. 3 to the Safety Evaluation Report (SER) related to the operation of the Comanche Peak Steam electric Station, Units 1 and 2, has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. the facility is located in Somervell County, Texas. Subject to favorable resolution of the items identified in this supplement, the staff concludes that the facility can be operated by the applicatn without endangering the health and safety of the public. This document provides the NRC staff's evaluation of the outstanding and confirmatory issues that have been resolved since Supplement No. 2 was issued in January 1982, and addresses changes to the SER and its earlier supplements which have resulted from the receipt of additonal information from the applicant during the period of January throught October 1982

Safety evaluation report related to the operation of Comanche Peak Steam Electric Station, Units 1 and 2 (Docket Nos. 50-445 and 50-446): Supplement No. 21

International Nuclear Information System (INIS)

1989-04-01

Supplement 21 to the Safety Evaluation Report related to the operation of the Comanche Peak Steam Electric Station (CPSES), Units 1 and 2 (NUREG-0797), has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission (NRC). The facility is located in Somervell County, Texas, approximately 40 miles southwest of Fort Worth, Texas. This supplement reports the status of certain issues that had not been resolved when the Safety Evaluation Report and Supplements 1, 2, 3, 4, 6, and 12 to that report were published. This supplement also lists the new issues that have been identified since Supplement 12 was issued and includes the evaluations for licensing items resolved in this interim period. 21 refs

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

International Nuclear Information System (INIS)

1984-09-01

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

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

International Nuclear Information System (INIS)

1984-06-01

Supplement 6 to the Safety Evaluation Report for the application filed by Louisiana Power and Light Company for a license to operate the Waterford Steam Electric Station, Unit 3 (Docket No. 50-382), located in St. Charles Parish, Louisiana, has been prepared by the Office of Nuclear Reactor Regulation of the Nuclear Regulatory Commission. The purpose of this supplement is to update the Safety Evaluation Report by providing the staff's evaluation of information submitted by the applicant since the Safety Evaluation Report and its five previous supplements were issued

Safety Evaluation Report related to the operation of Waterford Steam Electric Station, Unit No. 3 (Docket No. 50-382). Supplement No. 8

International Nuclear Information System (INIS)

1984-12-01

Supplement 8 to the Safety Evaluation Report for the application filed by Louisiana Power and Light Company for a license to operate the Waterford Steam Electric Station, Unit 3 (Docket No. 50-382), located in St. Charles Parish, Louisiana, has been prepared by the Office of Nuclear Reactor Regulation of the Nuclear Regulatory Commission. The purpose of this supplement is to update the Safety Evaluation Report by providing the staff's evaluation of information submitted by the applicant since the Safety Evaluation Report and its seven previous supplements were issued

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

Science.gov (United States)

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

2018-05-01

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

75 FR 13322 - PPL Susquehanna, LLC.: Susquehanna Steam Electric Station, Units 1 and 2 Environmental Assessment...

Science.gov (United States)

2010-03-19

... workers and members of the public. Therefore, no changes or different types of radiological impacts are... to historical and cultural resources. There would be no impact to socioeconomic resources. Therefore...

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

International Nuclear Information System (INIS)

1985-05-01

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

Safety evaluation report related to the operation of Comanche Peak Steam Electric Station, Units 1 and 2 (Docket Nos. 50-445 and 50-446)

International Nuclear Information System (INIS)

1988-11-01

Supplement 19 to the Safety Evaluation Report related to the operation of the Comanche Peak Steam Electric Station (CPSES), Units 1 and 2 (NUREG-0797), has been prepared by the Office of Special Projects of the US Nuclear Regulatory Commission (NRC). The facility is located in Somervell County, Texas, approximately 40 miles southwest of Fort Worth, Texas. This supplement presents the staff's evaluation of the Texas Utilities Electric Company's (lead applicant's) corrective action program (CAP) related to equipment qualification. The scope and methodology for the CAP workscope, as summarized in Revision 0 to the Equipment Qualification Project Status Report and as detailed in related documents, were developed to resolve various issues raised by the Comanche Peak Response Team (CPRT) and the NRC staff to ensure that plant equipment is appropriately environmentally and/or seismically and dynamically qualified and documented in accordance with the validated plant design resulting from other CAP scopes of work for Unit 1 and areas common to Units 1 and 2. The staff concludes that the CAP workscope for equipment qualification provides a comprehensive program for resolving the concerns identified by the CPRT and the NRC staff, including issues raised in the Comanche Peak Safety Evaluation Report and its supplements, and its implementation will ensure that the environmental and/or seismic and dynamic qualification of equipment at CPSES satisfies the validated plant design and the applicable requirements of 10 CFR Part 50. As is routine staff practice, the NRC staff will verify the adequacy of implementation of the environmental and seismic and dynamic equipment qualification program at CPSES during inspections that will take place before fuel loading. 97 refs

75 FR 8753 - Carolina Power & Light Company, Brunswick Steam Electric Plant, Units 1 and 2; Environmental...

Science.gov (United States)

2010-02-25

... Dusenbury of the North Carolina Department of Environment and Natural Resources regarding the environmental... & Light Company, Brunswick Steam Electric Plant, Units 1 and 2; Environmental Assessment and Finding of No... identification of licensing and regulatory actions requiring environmental assessments,'' the NRC prepared an...

Use of mock-up training to reduce personnel exposure at the North Anna Unit 1 Steam Generator Replacement Project

Energy Technology Data Exchange (ETDEWEB)

Henry, H.G. [Virginia Power, Mineral, VA (United States); Reilly, B.P. [Bechtel Power Corp., Gaithersburg, MD (United States)

1995-03-01

The North Anna Power Station is located on the southern shore of Lake Anna in Louisa County, approximately forty miles northwest of Richmond, Virginia. The two 910 Mw nuclear units located on this site are owned by Virginia Electric and Power Company (Virginia Power) and Old Dominion Electric Cooperative and operated by Virginia Power. Fuel was loaded into Unit 1 in December 1977, and it began commercial operation in June 1978. Fuel was loaded into Unit 2 in April 1980 and began commercial operation in December 1980. Each nuclear unit includes a three-coolant-loop pressurized light water reactor nuclear steam supply system that was furnished by Westinghouse Electric Corporation. Included within each system were three Westinghouse Model 51 steam generators with alloy 600, mill-annealed tubing material. Over the years of operation of Unit 1, various corrosion-related phenomena had occurred that affected the steam generators tubing and degraded their ability to fulfill their heat transfer function. Advanced inspection and repair techniques helped extend the useful life of the steam generators, but projections based on the results of the inspections indicated that the existing steam generators tubing and degraded their ability to fullfill their heat transfer function. Advanced inspection and repair techniques helped extend the useful life of the steam generators, but projections based on the results of the inspections indicated that the existing steam generators would not last their design life and must be repaired. To this end Virginia Power determined that a steam generator replacement (SGR) program was necessary to remove the old steam generator tube bundles and lower shell sections, including the channel heads (collectively called the lower assemblies), and replace them with new lower assemblies incorporating design features that will prevent the degradation problems that the old steam generators had experienced.

Steam turbines for nuclear power stations in Czechoslovakia and their use for district heating

International Nuclear Information System (INIS)

Drahy, J.

1989-01-01

The first generation of nuclear power stations in Czechoslavakia is equipped with 440 MW e pressurized water reactors. Each reactor supplies two 220 MW, 3000 rpm condensing type turbosets operating with saturated steam. After the completion of heating water piping systems, all of the 24 units of 220 MW in Czechoslovak nuclear power stations will be operated as dual purpose units, delivering both electricity and heat. At the present time, second-generation nuclear power stations, with 1000 MW e PWRs, are being built. Each such plant is equipped with one 1000 MW full-speed saturated steam turbine. The turbine is so designed as to permit the extraction of steam corresponding to the following quantities of heat: 893 MJ/s with three-stage water heating (150/60 0 C); and 570 MJ/s with two-stage water heating (120/60 0 C). The steam is taken from uncontrolled steam extraction points. (author)

Safety evaluation report related to the operation of Comanche Peak Steam Electric Station, Units 1 and 2: Docket No. 50-445 and 50-446

International Nuclear Information System (INIS)

1988-11-01

Supplement 20 to the Safety Evaluation Report related to the operation of the Comanche Peak Steam Electric Station (CPSES), Units 1 and 2 (NUREG-0797), has been prepared by the Office of Special Projects of the US Nuclear Regulatory Commission (NRC). The facility is located in Somervell County, Texas, approximately 40 miles southwest of Fort Worth, Texas. This supplement presents the staff's evaluation of CPRT implementation of the Comanche Peak Response Team (CPRT) Program Plan and the issue-specific action plans (ISAPs), as well as the CPRT's investigations to determine the adequacy of various types of programs and hardware at CPSES. The results and conclusions of the CPRT activities are documented in a results report for each ISAP, a Collective Evaluation Report (CER), and a Collective Significance Report (CSR). This supplement also presents the staff's safety evaluation of TU Electric's root cause assessment of past CPSES design deficiencies and weaknesses. The NRC staff concludes that the CPRT has adequately implemented its investigative activities related to the design, construction, construction quality assurance/quality control, and testing at CPSES. The NRC staff further concludes that the CPRT evaluation of the results of its investigation is thorough and complete and its recommendations for corrective actions are sufficient to resolve identified deficiencies

Safety evaluation report related to the operation of Comanche Peak Steam Electric Station, Units 1 and 2 (Docket Nos. 50-445 and 50-446)

International Nuclear Information System (INIS)

1988-11-01

Supplement 18 to the Safety Evaluation Report related to the operation of the Comanche Peak Steam Electric Station (CPSES), Units 1 and 2 (NUREG-0797), has been prepared by the Office of Special Projects of the US Nuclear Regulatory Commission (NRC). The facility is located in Somervell County, Texas, approximately 40 miles southwest of Fort Worth, Texas. This supplement presents the staff's evaluation of the applicant's Corrective Action Program (CAP) related to the structural design of the heating, ventilation, and air conditioning (HVAC) systems. The scope and methodologies for the CAP workscope as summarized in Revision 0 to the HVAC project status report and as detailed in related documents referenced in this evaluation were developed to resolve the technical concerns identified in the HVAC area. The NRC staff concludes that the CAP workscope for the HVAC structural design provides a comprehensive program for resolving the associated technical concerns and its implementation ensures that the structural design of the HVAC systems at CPSES satisfies the applicable requirements of 10 CFR Part 50. 32 refs

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...

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...

Safety Evaluation Report related to the operation of Comanche Peak Steam Electric Station, Units 1 and 2 (Docket Nos. 50-445 and 50-446)

International Nuclear Information System (INIS)

1990-02-01

Supplement 23 to the Safety Evaluation Report related to the operation of the Comanche Peak Steam Electric Station (CPSES), Units 1 and 2 (NUREG-0797), has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission (NRC). The facility is located in Somervell County, Texas, approximately 40 miles southwest of Fort Worth, Texas. This supplement reports the status of certain issues that had not been resolved when the Safety Evaluation Report and supplements 1, 2, 3, 4, 6, 12, 21, and 22 to that report were published. This supplement also includes the evaluations for licensing items resolved since Supplement 22 was issued. Supplement 5 has not been issued. Supplements 7, 8, 9, 10, and 11 were limited to the staff evaluation of allegations investigated by the NRC Technical Review Team. Supplement 13 presented the staff's evaluation of the Comanche Peak Response Team (CPRT) Program Plan, which was formulated by the applicant to resolve various construction and design issues raised by sources external to TU Electric. Supplements 14 through 19 presented the staff's evaluation of the CPSES Corrective Action Program: large- and small-bore piping and pipe supports (Supplement 14); cable trays and cable tray hangers (Supplement 15); conduit supports (Supplement 16); mechanical, civil/structural, electrical, instrumentation and controls, and systems portions of the heating, ventilation, and air conditioning (HVAC) system workscopes (Supplement 17); HVAC structural design (Supplement 18); and equipment qualification (Supplement 19). Supplement 20 presented the staff's evaluation of the Comanche Peak Response Team implementation of the CPRT Program

Manufacture of steam generator units and components for the AGR power stations at Heysham II and Torness

International Nuclear Information System (INIS)

Glasgow, J.R.; Parkin, K.

1984-01-01

The current AGR Steam Generator is a development of the successful once-through units supplied for the Oldbury Magnox and Hinkley B/Hunterston B AGR power stations. In this paper a brief outline of the evolution of the steam generator design from the earlier gas cooled reactor stations is presented. A description of the main items of fabrication development is given. The production facilities for the manufacture of the units are described. Reference is also made to some of the work on associated components. The early experience on the construction site of installation of the steam generators is briefly outlined. (author)

Manufacture of steam generator units and components for the AGR power stations at Heysham II and Torness

Energy Technology Data Exchange (ETDEWEB)

Glasgow, J R; Parkin, K [N.E.I. Nuclear Systems Ltd., Gateshead, Tyne and Wear (United Kingdom)

1984-07-01

The current AGR Steam Generator is a development of the successful once-through units supplied for the Oldbury Magnox and Hinkley B/Hunterston B AGR power stations. In this paper a brief outline of the evolution of the steam generator design from the earlier gas cooled reactor stations is presented. A description of the main items of fabrication development is given. The production facilities for the manufacture of the units are described. Reference is also made to some of the work on associated components. The early experience on the construction site of installation of the steam generators is briefly outlined. (author)

Safety evaluation report related to the operation of Comanche Peak Steam Electric Station, Units 1 and 2 (Docket Nos. 50-445 and 50-446)

International Nuclear Information System (INIS)

1990-04-01

Supplement 24 to the Safety Evaluation Report related to the operation of the Comanche Peak Steam Electric Station (CPSES), Units 1 and 2 (NUREG-0797), has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission (NRC). The facility is located in Somervell County, Texas, approximately 40 miles southwest of Fort Worth, Texas. This supplement reports the status of certain issues that had not been resolved when the Safety Evaluation Report and Supplements 1, 2, 3, 4, 6, 12, 21, 22, and 23 to that report were published. This supplement also includes the evaluations for licensing items resolved since Supplement 23 was issued. Supplement 5 has not been issued. Supplements 7, 8, 9, 10, and 11 were limited to the staff evaluation of allegations investigated by the NRC Technical Review Team. Supplement 13 represented the staff's evaluation of the Comanche Peak Response Team (CPRT) Program Plan, which was formulated by the applicant to resolve various construction and design issues raised by sources external to TU Electric. Supplements 14 through 19 presented the staff's evaluation of the CPSES Corrective Action Program: large- and small-bore piping and pipe supports (Supplement 14); cable trays and cable tray hangers (Supplement 15); conduit supports (Supplement 16); mechanical, civil/structural, electrical, instrumentation and controls, and systems portions of the heating, ventilation, and air conditioning (HVAC) system workscopes (Supplement 17); HVAC structural design (Supplement 18); and equipment qualification (Supplement 19). Supplement 20 presented the staff's evaluation of the CPRT implementation of its Program Plan and the issue-specific action plans, as well as the CPRT's investigations to determine the adequacy of various types of programs and hardware at CPSES

Safety evaluation report related to the operation of Comanche Peak Steam Electric Station, Units 1 and 2: Docket Nos. 50-445 and 50-446

International Nuclear Information System (INIS)

1988-07-01

Supplement 15 to the Safety Evaluation Report related to the operation of the Comanche Peak Steam Electric Station (CPSES), Units 1 and 2 (NUREG-0797), has been prepared by the Office of Special Projects of the US Nuclear Regulatory Commission (NRC). The facility is located in Somervell County, Texas, approximately 40 miles southwest of Fort Worth, Texas. This supplement presents the staff's evaluation of the applicant's Corrective Action Program (CAP) related to the design of cable trays and cable tray hangers. The scope and methodologies for the CAP workscope as summarized in Revision O to the cable tray and cable tray hanger project status report and as detailed in related documents referenced in this evaluation were developed to resolve various design issues raised by the Atomic Safety and Licensing Board (ASLB) the intervenor, Citizens Association for Sound Energy (CASE); the Comanche Peak Response Team (CPRT); CYGNA Energy Services (CYGNA); and the NRC staff. The NRC staff concludes that the CAP workscope for cable trays and cable tray hangers provides a comprehensive program for resolving the associated technical concerns identified by the ASLB, CASE, CPRT, CYGNA, and the NRC staff and its implementation ensures that the design of cable trays and cable tray hangers at CPSES satisfies the applicable requirements of 10 CFR Part 50

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

International Nuclear Information System (INIS)

1986-05-01

Supplement 13 to the Safety Evaluation Report related to the operation of Comanche Peak Steam Electric Station (CPSES), Units 1 and 2 (NUREG-0797), has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission (NRC). The facility is located in Somervell County, Texas, approximately 40 miles southwest of Fort Worth, Texas. This supplement presents the staff's evaluation of the Comanche Peak Response Team (CPRT) Program Plan which was formulated by the applicant to resolve various construction and design issues raised by the Atomic Safety and Licensing Board, allegers, intervenor Citizens Association for Sound Energy (CASE), NRC inspections of various types, and Cygna Energy Services while conducting its independent design assessment. The NRC staff concludes that the CPRT Program Plan provides an overall structure for addressing all existing issues and any future issues which may be identified from further evaluations, and if properly implemented will provide important evidence of the design and construction quality of CPSES, and will identify any needed corrective action. The report identifies items to be addressed by the NRC staff during the implementation phase

Steam generator replacement at Surry Power Station

International Nuclear Information System (INIS)

McKay, H.S.

1982-01-01

The purposes of the steam generator repair program at Surry Power Station were to repair the tube degradation caused by corrosion-related phenomena and to restore the integrity of the steam generators to a level equivalent to new equipment. The repair program consisted of (1) replacing the existing lower-shell assemblies with new ones and (2) adding new moisture separation equipment to the upper-shell assemblies. These tasks required that several pieces of reactor coolant piping, feedwater piping, main steam piping, and the steam generator be cut and refurbished for reinstallation after the new lower shell was in place. The safety implications and other potential effects of the repair program both during the repair work and after the unit was returned to power were part of the design basis of the repair program. The repair program has been completed on Unit 2 without any adverse effects on the health and safety of the general public or to the personnel engaged in the repair work. Before the Unit 1 repair program began, a review of work procedures and field changes for the Unit 2 repair was conducted. Several major changes were made to avoid recurrence of problems and to streamline procedures. Steam generator replacements was completed on June 1, 1981, and the unit is presently in the startup phase of the outrage

Safety Evaluation Report related to the operation of Comanche Peak Steam Electric Station, Units 1 and 2 (Docket Nos. 50-445 and 50-446)

International Nuclear Information System (INIS)

1990-01-01

Supplement 22 to the Safety Evaluation Report related to the operation of the Comanche Peak Steam Electric Station, Units 1 and 2 (NUREG-0797), has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located in Somervell County, Texas, approximately 40 miles southwest of Fort Worth, Texas. This supplement reports the status of certain issues that had not been resolved at the time of publication of the Safety Evaluation Report and Supplements 1, 2, 3, 4, 6, 12, and 21 to that report. This supplement also includes the evaluations for licensing items resolved since Supplement 21 was issued. Supplement 5 has been cancelled. Supplements 7 through 11 were limited to the staff evaluation of allegations investigated by the NRC Technical Review Team. Supplement 13 presented the staff's evaluation of the Comanche Peak Response Team (CPRT) Program Plan, which was formulated by the applicant to resolve various construction and design issues raised by sources external to the applicant. Supplements 14 through 20 presented the staff's evaluation of the applicant's Corrective Action Program and CPRT activities. Items identified in Supplements 7, 8, 9, 10, 11, 13, 14, and 15 through 20 are not included in this supplement, except to the extent that they affect the applicant's Final Safety Analysis Report. 154 refs., 24 figs., 8 tabs

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

International Nuclear Information System (INIS)

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

1980-01-01

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

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

Science.gov (United States)

2010-07-01

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

Recruiting, Training, Retaining, and Promoting the Workforce of the Future at Comanche Peak Steam Electric Station

International Nuclear Information System (INIS)

Sunseri, M.

1999-01-01

TXU Electric expects to encounter a relatively high turnover in the workforce in the coming years. To prepare for this challenge and to maintain a high level of performance, a number of approaches are being implemented. These approaches involve recruiting experienced personnel, recruiting and developing local nonexperienced personnel, and developing current employees. Through these approaches, TXU Electric expects to maintain a high-quality workforce for the continued support of Comanche Peak Steam Electric Station

Environmental codes of practice for steam electric power generation

International Nuclear Information System (INIS)

1985-03-01

The Design Phase Code is one of a series of documents being developed for the steam electric power generation industry. This industry includes fossil-fuelled stations (gas, oil and coal-fired boilers), and nuclear-powered stations (CANDU heavy water reactors). In this document, environmental concerns associated with water-related and solid waste activities of steam electric plants are discussed. Design recommendations are presented that will minimize the detrimental environmental effects of once-through cooling water systems, of wastewaters discharged to surface waters and groundwaters, and of solid waste disposal sites. Recommendations are also presented for the design of water-related monitoring systems and programs. Cost estimates associated with the implementation of these recommendations are included. These technical guides for new or modified steam electric stations are the result to consultation with a federal-provincial-industry task force

A drier unit for steam separators

International Nuclear Information System (INIS)

Peyrelongue, J.-P.

1973-01-01

Description is given of a drier unit adapted to equip a water separator mounted in a unit for treating a wet steam fed from a high pressure enclosure, so as to dry and contingently superheat said steam prior to injecting same into a turbine low pressure stage. This drier unit is constituted by at least a stack of separating sheets maintained in parallel relationship and at a slight angle with respect to the horizontal so as to allow the water provided by wet steam to flow toward a channel communicating with a manifold, and by means for guiding the steam between the sheets and evenly distributing it. This can be applied to steam turbines in nuclear power stations [fr

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

International Nuclear Information System (INIS)

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

1980-01-01

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

Safety evaluation report related to steam generator repair at H.B. Robinson Steam Electric Plant, Unit No. 2. Docket No. 50-261

International Nuclear Information System (INIS)

1983-11-01

A Safety Evaluation Report was prepared for the H.B. Robinson Steam Electric Plant Unit No. 2 by the Office of Nuclear Reactor Regulation. This report considers the safety aspects of the proposed steam generator repair at H.B. Robinson Steam Electric Plant Unit No. 2. The report focuses on the occupational radiation exposure associated with the proposed repair program. It concludes that there is reasonable assurance that the health and safety on the public will not be endangered by the conduct of the proposed action, such activities will be conducted in compliance with the Commission's regulations, and the issuance of this amendment will not be inimical to the common defense and security or the health and safety of the public

Technical evaluation report on the monitoring of electric power to the reactor-protection system for the Brunswick Steam Electric Plant, Units 1 and 2

International Nuclear Information System (INIS)

Selan, J.C.

1982-01-01

This report documents the technical evaluation of the monitoring of electric power to the reactor protection system (RPS) at the Brunswick Steam Electric Plant, Units 1 and 2. The evaluation is to determine if the proposed design modification will protect the RPS from abnormal voltage and frequency conditions which could be supplied from the power supplies and will meet certain requirements set forth by the Nuclear Regulatory Commission. The proposed design modifications with time delays verified by GE, will protect the RPS from sustained abnormal voltage and frequency conditions from the supplying sources

Fuqing nuclear power of nuclear steam turbine generating unit No.1 at the implementation and feedback

International Nuclear Information System (INIS)

Cao Yuhua; Xiao Bo; He Liu; Huang Min

2014-01-01

The article introduces the Fuqing nuclear power of nuclear steam turbine generating unit no.l purpose, range of experience, experiment preparation, implementation, feedback and response. Turn of nuclear steam turbo-generator set flush, using the main reactor coolant pump and regulator of the heat generated by the electric heating element and the total heat capacity in secondary circuit of reactor coolant system (steam generator secondary side) of saturated steam turbine rushed to 1500 RPM, Fuqing nuclear power of nuclear steam turbine generating unit no.1 implementation of the performance of the inspection of steam turbine and its auxiliary system, through the test problems found in the clean up in time, the nuclear steam sweep turn smooth realization has accumulated experience. At the same time, Fuqing nuclear power of nuclear steam turbine generating unit no.1 at turn is half speed steam turbine generator non-nuclear turn at the first, with its smooth realization of other nuclear power steam turbine generator set in the field of non-nuclear turn play a reference role. (authors)

Nuclear Regulatory Commission Issuances, May 81

International Nuclear Information System (INIS)

1981-05-01

Contents: Issuances of the Nuclear Regulatory Commission--Consolidated Edison Company of New York, Inc. (Indian Point, Unit No. 2), Power Authority of the State of New York (Indian Point, No. 3 Nuclear Power Plant), Pacific Gas and Electric Company (Diablo Canyon Nuclear Power Plant, Units 1 and 2), Statement of Policy on Conduct of Licensing Proceedings, Uranium Mill Licensing Requirements; Issuances of Atomic Safety and Licensing Appeal Boards--Houston Lighting and Power Company, et al. (South Texas Project, Units 1 and 2), Metropolitan Edison Company, et al. (Three Mile Island Nuclear Station, Unit No. 2), Pennsylvania Power and Light Company and Allegheny Electric Cooperative, Inc. (Susquehanna Steam Electric Station, Units 1 and 2), Philadelphia Electric Company et al. (Peach Bottom Atomic Power Station, Units 2 and 3), Public Service Electric and Gas Company (Hope Creek Generating Station, Units 1 and 2); Issuances of the Atomic Safety and Licensing Boards--Duke Power Company (William B. McGuire Nuclear Station, Units 1 and 2), Florida Light and Power Company (Turkey Point Nuclear Generating, Units 3 and 4), Illinois Power Company, et al. (Clinton Power Station, Units 1 and 2), Sacramento Municipal Utility District (Rancho Seco Nuclear Generating Station); Issuances of the Directors Denial--Commonwealth Edison Company (Byron Station, Units 1 and 2), Consolidated Edison Company of New York, Inc. (Indian Point Unit No. 2), Gulf States Utilities Company (River Bend Station Units 1 and 2), Petition to Suspend All Operating Licenses for Pressurized Water Reactors (River Bend Station Units 1 and 2), Portland General Electric Company (Trojan Nuclear

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...

Improvements in steam cycle electric power generating plants

International Nuclear Information System (INIS)

Bienvenu, Claude.

1973-01-01

The invention relates to a steam cycle electric energy generating plants of the type comprising a fossil or nuclear fuel boiler for generating steam and a turbo alternator group, the turbine of which is fed by the boiler steam. The improvement is characterized in that use is made of a second energy generating group in which a fluid (e.g. ammoniac) undergoes a condensation cycle the heat source of said cycle being obtained through a direct or indirect heat exchange with a portion of the boiler generated steam whereby it is possible without overloading the turbo-alternator group, to accomodate any increase of the boiler power resulting from the use of another fuel while maintaining a maximum energy output. This can be applied to electric power stations [fr

Characterization and dissolution studies of Bruce Unit 3 steam generator secondary side deposits

International Nuclear Information System (INIS)

Semmler, J.

1998-01-01

The physical and chemical properties of secondary side steam generator deposits in the form of powder and flake obtained from Bruce Nuclear Generating Station A (BNGS A) Unit 3 were studied. The chemical phases present in both types of deposits, collected prior to the 1994 chemical cleaning during the pre-clean water lancing campaign, were magnetite (Fe 3 O 4 ), metallic copper (Cu), hematite (Fe 2 O 3 ) and cuprous oxide (Cu 2 O). The major difference between the chemical composition of the powder and the flake was the presence of zinc silicate (Zn 2 SiO 4 ) and several unidentified silicate phases containing Ca, Al, Mn, and Mg in the flake. The flake deposit had high hardness values, high electrical resistivity, low porosity and a lower dissolution rate in the EPRI-SGOG (Electric Power Research Institute-Steam Generator Owner's Group) chemical cleaning solvents compared to the powder deposit. Differences in the deposit properties after chemical cleaning of the Unit 3 steam generators and after laboratory cleaning were noted. The presence of silicates in the deposit inhibit magnetite dissolution

Steam generator replacement at Kansai Electric Power Co., Inc

International Nuclear Information System (INIS)

Kimura, S.; Dodo, Takashi; Negishi, Kazuo

1995-01-01

Eleven nuclear units are in operation at the Kansai Electric Power Co., Inc.. In seven of them, Mihama-1·2·3, Takahama-1·2, and Ohi-1·2, comparatively long duration for tube inspection and repair have been required during late annual outages. KEPCO decided to replace all steam generators in these 7 units with the latest model which was improved upon the past degradation experiences, as a result of comprehensive considerations including public confidence in nuclear power generation, maintenability, and economic efficiency. This report presents the design improvements in new steam generators, replacement techniques, and so on. (author)

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

International Nuclear Information System (INIS)

Anon.

1980-01-01

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

Draft environmental statement related to steam generator repair at H.B. Robinson Steam Electric Plant Unit No. 2, (Docket No. 50-261)

International Nuclear Information System (INIS)

1983-09-01

The staff has considered the environmental impacts and economic costs of the proposed steam generator repair at the H.B. Robinson Steam Electric Plant Unit No. 2 along with reasonable alternatives to the proposed action. The staff has concluded that the proposed repair will not significantly affect the quality of the human environment and that there are no preferable alternatives to the proposed action. Furthermore, any impacts from the repair program are outweighted by its benefits

Strategic elements of steam cycle chemistry control practices at TXU's Comanche Peak steam electric station

International Nuclear Information System (INIS)

Fellers, B.; Stevens, J.; Nichols, G.

2002-01-01

Early industry experience defined the critical importance of Chemistry Control Practices to maintaining long-term performance of PWR steam generators. These lessons provided the impetus for a number of innovations and alternate practices at Comanche Peak. For example, advanced amine investigations and implementation of results provided record low iron transport and deposition. The benefits of the surface-active properties of dimethyl-amine exceeded initial expectations. Operation of pre-coat polishers and steam generator blowdown demineralizers in the amine cycle enabled optimization of amine concentrations and stable pH control. The strategy for coordinated control of oxygen and hydrazine dosing complemented the advanced amine program for protective oxide stabilization. Additionally, a proactive chemical cleaning was performed on Unit 1 to prevent degradations from general fouling of steam generator tube-tube support plate (TSP) and top-of-tubesheet (TTS) crevices. This paper shares the results of these innovations and practices. Also, the bases, theory, and philosophy supporting the strategic elements of program will be presented. (authors)

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

International Nuclear Information System (INIS)

1977-09-01

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

Elevated-constant pH control assessment at TXU's Comanche peak steam electric station

International Nuclear Information System (INIS)

Fellers, B.; Perkins, D.; Bosma, J.; Deshon, J.

2002-01-01

Industry experience with axial offset anomaly (AOA) has raised the importance of crud management strategies. Elevated-constant pH control is recognized as one potential solution. Additionally, minimizing radiation fields remains a high industry goal which is supported by this strategy. An investigation of industry experience and experimental data has supported a strategy of constant at-temperature pH of 7.4, requiring as much as 6-ppm lithium at the beginning-of-cycle (BOC). This approach, in a modern high temperature plant with high boron requirements, necessitated a careful assessment of potential risk for increased susceptibility to corrosion for both fuel cladding and RCS structural materials. This paper presents results of the assessment for Comanche peak steam electric station (CPSES) and plans for a demonstration of this practice. (author)

Periodical inspection in nuclear power stations

International Nuclear Information System (INIS)

1986-01-01

Periodical inspection is presently being made of eight nuclear power plants in nuclear power stations. Up to the present time, in three of them, failures as follows have been observed. (1) Unit 3 (PWR) of the Mihama Power Station in The Kansai Electric Power Co., Inc. Nineteen heat-transfer tubes of the steam generators were plugged up due to failure. A fuel assembly with a failed spring fixture and in another the control-rod cluster with a failed control rod fixture were replaced. (2) Unit 2 (PWR) of the Oi Power Station in The Kansai Electric Power Co., Inc. Eight heat-transfer tubes of the heat exchangers were plugged up due to failure. (3) Unit 6 (BWR) of the Fukushima Nuclear Power Station I in The Tokyo Electric Power Co., Inc. A fuel assembly with leakage was replaced. (Mori, K.)

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)

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

International Nuclear Information System (INIS)

Ito, Yoshinori

2013-01-01

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

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

International Nuclear Information System (INIS)

Moore, M.M.

1975-12-01

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

Review of the research proposal for the steam generator retired from Kori unit 1

Energy Technology Data Exchange (ETDEWEB)

Kim, Joung Soo; Han, Joung Ho; Kim, Hong Pyo; Lim, Yun Soo; Lee, Deok Hyun; Hwang, Seong Sik; Hur, Do Haeng [Korea Atomic Energy Research Institute, Taejeon (Korea)

2002-03-01

The tubes of the steam generator retired form Kori unit 1 have many different kinds of failures, such as denting pitting, wastage, ODSCC, PWSCC.Korea Electric Power Research Institute (KEPRI) submitted a research proposal for the steam generator to the Korea Institute S and T Evaluation and Planning (KSITEP). The KISTEP requested Korea Atomic Energy Research Institute to review the proposal by organizing a committee which should be composed of the specialists of the related domestic research institutes. Opinions of the committee on the objectives, research fields, economic benefit and validity in the research proposal were reviewed and suggested optimal research fields to be fulfilled successfully for the retired steam generator. Also, the rolls for the participants in the research works were allocated, which is critical in order to do the project effectively. 6 figs., 5 tabs. (Author)

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

International Nuclear Information System (INIS)

Selan, J.C.

1983-01-01

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

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...

Alteration in reactor installation (addition of Unit 2) in Shimane Nuclear Power Station, Chugoku Electric Power Co., Inc. (inquiry)

International Nuclear Information System (INIS)

1983-01-01

An inquiry was made by the Ministry of International Trade and Industry to Nuclear Safety Commission on the addition of Unit 2 in Shimane Nuclear Power Station of The Chugoku Electric Power Co., Inc., concerning the technical capability of Chugoku Electric Power Co., Inc., and the plant safety. The NSC requested the Committee on Examination of Reactor Safety to make a deliberation on this subject. Both the technical capability and the safety of Unit 1 were already confirmed by MITI. Unit 2 to be newly added in the Shimane Nuclear Power Station is a BWR power plant with electric output of 820 MW. The examination made by MITI is described: the technical capability of Chugoku Electric Power Co., Inc., the safety of Unit 2 about its siting, reactor proper, reactor cooling system, radioactive waste management, etc. (J.P.N.)

Steam-treated wood pellets: Environmental and financial implications relative to fossil fuels and conventional pellets for electricity generation

International Nuclear Information System (INIS)

McKechnie, Jon; Saville, Brad; MacLean, Heather L.

2016-01-01

Highlights: • Steam-treated pellets can greatly reduce greenhouse gas emissions relative to coal. • Cost advantage is seen relative to conventional pellets. • Higher pellet cost is more than balanced by reduced retrofit capital requirements. • Low capacity factors further favour steam-treated pellets over conventional pellets. - Abstract: Steam-treated pellets can help to address technical barriers that limit the uptake of pellets as a fuel for electricity generation, but there is limited understanding of the cost and environmental impacts of their production and use. This study investigates life cycle environmental (greenhouse gas (GHG) and air pollutant emissions) and financial implications of electricity generation from steam-treated pellets, including fuel cycle activities (biomass supply, pellet production, and combustion) and retrofit infrastructure to enable 100% pellet firing at a generating station that previously used coal. Models are informed by operating experience of pellet manufacturers and generating stations utilising coal, steam-treated and conventional pellets. Results are compared with conventional pellets and fossil fuels in a case study of electricity generation in northwestern Ontario, Canada. Steam-treated pellet production has similar GHG impacts to conventional pellets as their higher biomass feedstock requirement is balanced by reduced process electricity consumption. GHG reductions of more than 90% relative to coal and ∼85% relative to natural gas (excluding retrofit infrastructure) could be obtained with both pellet options. Pellets can also reduce fuel cycle air pollutant emissions relative to coal by 30% (NOx), 97% (SOx), and 75% (PM 10 ). Lesser retrofit requirements for steam-treated pellets more than compensate for marginally higher pellet production costs, resulting in lower electricity production cost compared to conventional pellets ($0.14/kW h vs. $0.16/kW h). Impacts of retrofit infrastructure become increasingly

Steam generator replacement at the Obrigheim nuclear power station

International Nuclear Information System (INIS)

Pickel, E.; Schenk, H.; Huemmler, A.

1984-01-01

The Obrigheim Nuclear Power Station (KWO) is equipped with a dual-loop pressurized water reactor of 345 MW electric power; it was built by Siemens in the period 1965 to 1968. By the end of 1983, KWO had produced some 35 billion kWh in 109,000 hours of operation. Repeated leaks in the heater tubes of the two steam generators had occurred since 1971. Both steam generators were replaced in the course of the 1983 annual revision. Kraftwerk Union AG (KWU) was commissioned to plant and carry out the replacement work. Despite the leakages the steam generators had been run safely and reliably over a period of 14 years until their replacement. Replacing the steam generators was completed within twelve weeks. In addition to the KWO staff and the supervising crew of KWU, some 400 external fitters were employed on the job at peak work-load periods. For the revision of the whole plant, work on the emergency systems and replacement of the steam generators a maximum number of approx. 900 external fitters were employed in the plant in addition to some 250 members of the plant crew. The exposure dose of the personnel sustained in the course of the steam generator replacement was 690 man-rem, which was clearly below previous estimates. (orig.) [de

Automation of steam generator services at public service electric & gas

Energy Technology Data Exchange (ETDEWEB)

Cruickshank, H.; Wray, J.; Scull, D. [Public Service Electric & Gas, Hancock`s Bridge, NJ (United States)

1995-03-01

Public Service Electric & Gas takes an aggressive approach to pursuing new exposure reduction techniques. Evaluation of historic outage exposure shows that over the last eight refueling outages, primary steam generator work has averaged sixty-six (66) person-rem, or, approximately tewenty-five percent (25%) of the general outage exposure at Salem Station. This maintenance evolution represents the largest percentage of exposure for any single activity. Because of this, primary steam generator work represents an excellent opportunity for the development of significant exposure reduction techniques. A study of primary steam generator maintenance activities demonstrated that seventy-five percent (75%) of radiation exposure was due to work activities of the primary steam generator platform, and that development of automated methods for performing these activities was worth pursuing. Existing robotics systems were examined and it was found that a new approach would have to be developed. This resulted in a joint research and development project between Westinghouse and Public Service Electric & Gas to develop an automated system of accomplishing the Health Physics functions on the primary steam generator platform. R.O.M.M.R.S. (Remotely Operated Managed Maintenance Robotics System) was the result of this venture.

Recent technology for BWR nuclear steam turbine unit

International Nuclear Information System (INIS)

Moriya, Shin-ichi; Masuda, Toyohiko; Kashiwabara, Katsuto; Oshima, Yoshikuni

1990-01-01

As to the ABWR plants which is the third improvement standard boiling water reactor type plants, already the construction of a plant of 1356 MWe class for 50 Hz is planned. Hitachi Ltd. has accumulated the technology for the home manufacture of a whole ABWR plant including a turbine. As the results, the application of a butterfly type combination intermediate valve to No.5 plant in Kashiwazaki Kariwa Nuclear Power Station, Tokyo Electric Power Co., Inc., which began the commercial operation recently and later plants, the application of a moisture separating heater to No.4 plant in Hamaoka Nuclear Power Station, Chubu Electric Power Co., Inc., which is manufactured at present and later plants and so on were carried out. As to the steam turbine facilities for nuclear power generation manufactured by Hitachi Ltd., three turbines of 1100 MWe class for 50 Hz and one turbine for 60 Hz are in operation. As the new technologies for the steam turbines, the development of 52 in long last stage blades, the new design techniques for the rotor system, the moisture separating heater, the butterfly type combination intermediate valve, cross-around pipes and condensate and feedwater system are reported. (K.I.)

Tube structural integrity evaluation of Palo Verde Unit 1 steam generators for axial upper-bundle cracking

International Nuclear Information System (INIS)

Woodman, B.W.; Begley, J.A.; Brown, S.D.; Sweeney, K.; Radspinner, M.; Melton, M.

1995-01-01

The analysis of the issue of upper bundle axial ODSCC as it apples to steam generator tube structural integrity in Unit 1 at the Palo Verde Nuclear generating Station is presented in this study. Based on past inspection results for Units 2 and 3 at Palo Verde, the detection of secondary side stress corrosion cracks in the upper bundle region of Unit 1 may occur at some future date. The following discussion provides a description and analysis of the probability of axial ODSCC in Unit 1 leading to the exceedance of Regulatory Guide 1.121 structural limits. The probabilities of structural limit exceedance are estimated as function of run time using a conservative approach. The chosen approach models the historical development of cracks, crack growth, detection of cracks and subsequent removal from service and the initiation and growth of new cracks during a given cycle of operation. Past performance of all Palo Verde Units as well as the historical performance of other steam generators was considered in the development of cracking statistics for application to Unit 1. Data in the literature and Unit 2 pulled tube examination results were used to construct probability of detection curves for the detection of axial IGSCC/IGA using an MRPC (multi-frequency rotating panake coil) eddy current probe. Crack growth rates were estimated from Unit 2 eddy current inspection data combined with pulled tube examination results and data in the literature. A Monte-Carlo probabilistic model is developed to provide an overall assessment of the risk of Regulatory Guide exceedance during plant operation

Steam turbines for PWR stations

International Nuclear Information System (INIS)

Muscroft, J.

1989-01-01

The thermodynamic cycle requirements and mechanical design features applying to modern GEC 3000 rev/min steam turbines for pressurised water reactor power stations are reviewed. The most recent developments include machines of 630 MW and 985 MW output which are currently under construction. The importance of service experience with nuclear wet steam turbines associated with a variety of types of water cooled reactor and its relevance to the design of modern 3000 rev/min turbines for pressurised water reactor applications is emphasised. (author)

Brunswick Steam Electric Plant, Units 1 and 2. Annual operating report for 1976

International Nuclear Information System (INIS)

1977-01-01

Net electrical energy generated by Unit 1 was 30,399 MWH with the generator on line 334.5 hrs. Unit 2 generated 2,481,014 MWH with the generator on line 4,915.53 hrs. Information is presented concerning operations, shutdowns and power reductions, maintenance, power generation, modifications, changes to operational procedures, radiation exposures, and leak rate testing

Surry Power Station secondary water chemistry improvement since steam generator replacement and the unit two feedwater pipe rupture

International Nuclear Information System (INIS)

Swindell, E.T.

1988-01-01

Surry Power Station has two Westinghouse-designed three-loop PWRs of 811 MWe design rating. The start of commercial operation was in July, 1972 in No.1 plant, and May, 1973 in No.2 plant. Both plants began the operation using controlled phosphate chemistry for the steam generators. In 1975, both plants were converted to all volatile treatment on the secondary side due to the tube wall thinning corrosion in the steam generators, which was associated with the phosphate sludge that was building up on the tube sheets and created acidic condition. Thereafter, condenser and air leakage and steam generator denting occurred, and after the operation of 8 years 2 month of No.1 plant and 5 years 9 months of No.2 plant, the steam generators were replaced. A major plant improvement program was designed and implemented from 1979 to 1980. The improvement in new steam generators, the modification for preventing corrosion, the addition of a steam generator blowdown recovery system, the reconstruction of condensers, the installation of full flow, deep bed condensate polishers, the addition of Dionex 8,000 on-line ion chromatograph, a long term maintenance agreement with Westinghouse and so on are reported. (Kako, I.)

Lessons learned while implementing a safety parameter display system at the Comanche Peak steam electric station

International Nuclear Information System (INIS)

Hagar, B.

1987-01-01

With the completion of site Verification and Validation tests, the Safety Parameter Display System (SPDS) will be fully operational at the Comanche Peak Steam Electric Station. Implementation of the SPDS, which began in 1982, included: modifying generic Safety Assessment System Software; developing site-specific displays and features; installing and integrating system equipment into the plant; modifying station heating, ventilation, and air conditioning systems to provide necessary cooling; installing an additional uninterruptible power supply system to provide necessary power; and training station personnel in the operation and use of the system. Lessons learned during this project can be discussed in terms of an ideal SPDS implementation project. Such a project would design and implement an SPDS for a plant that is already under construction or operating, and would progress through a sequence of activities that includes: (1) developing and documenting the system design bases, and including all major design influences; (2) developing a database description and system functional specifications to clarify specific system requirements; (3) developing detailed system hardware and software design specifications to fully describe the system, and to enable identification of necessary site design changes early in the project; (4) implementing the system design; (5) configuring and extensively testing the system prior to routine system operation; and (6) tuning the system after the completion of system installation. The ideal project would include future system users in design development and system testing, and would use Verification and Validation techniques throughout the project to ensure that each sequential step is appropriate and correct

77 FR 74548 - North Shore Railroad Company-Acquisition and Operation Exemption-PPL Susquehanna, LLC

Science.gov (United States)

2012-12-14

... Railroad Company--Acquisition and Operation Exemption--PPL Susquehanna, LLC North Shore Railroad Company...., that PPL Susquehanna, LLC (PPLS), and Allegheny Electric Cooperative, Inc. (AEC), the owners of the... extends to an interchange with Norfolk Southern Railway. North Shore states that it provides the only...

Technical Feasible Study for Future Solar Thermal Steam Power Station in Malaysia

Science.gov (United States)

Bohari, Z. H.; Atira, N. N.; Jali, M. H.; Sulaima, M. F.; Izzuddin, T. A.; Baharom, M. F.

2017-10-01

This paper proposed renewable energy which is potential to be used in Malaysia in generating electricity to innovate and improve current operating systems. Thermal and water act as the resources to replace limited fossil fuels such as coal which is still widely used in energy production nowadays. Thermal is also known as the heat energy while the water absorbs energy from the thermal to produce steam energy. By combining both of the sources, it is known as thermal steam renewable energy. The targeted area to build this power station has constant high temperature and low humidity which can maximize the efficiency of generating power.

Design and performance of BWC replacement steam generators for PWR systems

International Nuclear Information System (INIS)

Klarner, R.; Steinmoeller, F.; Millman, J.; Schneider, W.

1998-01-01

In recent years, Babcock and Wilcox Canada (BWC) has provided a number of PWR Replacement Steam Generators (RSGS) to replace units that had experienced extensive Alloy 600 tube degradation. BWC RSG units are in operation at Northeast Utilities' Millstone Unit 2, Rochester Gas and Electric's Ginna Station, Duke Energy's Catawba Unit 1, McGuire Unit 1 and 2, Florida Power and Light's St. Lucie Unit 1 and Commonwealth Edison's Byron 1 Station. Extensive start-up performance characteristics have been obtained for Millstone 2, Ginna, McGuire 1, and Catawba 1 RSGS. The Millstone 2, Ginna and Catawba 1 RSGs have also undergone extensive inspections following their first cycle of operation. The design and start-up performance characteristics of these RSGs are presented. The BWC Replacement Steam generators were designed to fit the existing envelope of pressure boundary dimensions to ensure licensability and integration into the Nuclear Steam Supply System. The RSGs were provided with a tube bundle of Alloy 690TT tubing, sized to match or exceed the original steam generator (OSG) thermal performance including provision for the reduced thermal conductivity of Alloy 690 relative to Alloy 600. The RSG tube bundle configurations provide a higher circulation design relative to the OSG, and feature corrosion resistant lattice grid and U-bend tube supports which provide effective anti-vibration support. The tube bundle supports accommodate relatively unobstructed flow and allow unrestrained structural interactions during thermal transients. Efficient steam separators assure low moisture carryover as well as high circulation. Performance measurements obtained during start-up verify that the BWC RSGs meet or exceed the specified thermal and moisture carryover performance requirements. RSG water level stability results at nor-mal operation and during plant transients have been excellent. Visual and ECT inspections have confirmed minimal deposition and 100% tube integrity following

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

Science.gov (United States)

2011-07-11

... NUCLEAR REGULATORY COMMISSION [NRC-2011-0100; Docket Nos. 50-413 and 50-414; Docket Nos. 50-369 and 50-370; Docket Nos. 50-269, 50-270, And 50-287] Duke Energy Carolinas, LLC Catawba Nuclear Station, Units 1 and 2; McGuire Nuclear Station, Units 1 and 2; Oconee Nuclear Station, Units 1, 2, and 3; Notice...

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

International Nuclear Information System (INIS)

1974-01-01

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

Safety evaluation report related to the operation of Comanche Peak Steam Electric Station, Units 1 and 2 (Docket Nos. 50-445 and 50-446)

International Nuclear Information System (INIS)

1988-03-01

Supplement 14 to the Safety Evaluation Report related to the operation of the Comanche Peak Stam Electric Station (CPSES), Units 1 and 2 (NUREG-0797), has been prepared by the Office of Special Projects of the US Nuclear Regulatory Commission (NRC). The facility is located in Somerville County, Texas, approximately 40 miles southwest of Fort Worth, Texas. This supplement presents the staff's evaluation of the applicants' Corrective Action Program (CAP0 related to large ans small bore piping and pipe supports. The scope and methodologies for CAP workshop as summarized in revision O to the large and small bore piping project status reports and as detailed in related documents referenced in this evaluation were developed to resolve various design issues raised by the Atomic Safety and Licensing Board (ASLB);the intervenor, Citizens Association for Sound Energy (CASE);the Camanche Peak Response Team (CPRT);SYGNA Energy Services (CYGNA);and the NRC staff. The NRC staff concludes that the CAP workscopes for large and small bore piping provide a comprehensive program for resolving the associated technical concerns identified by the ASLB, CASE, CPRT, CYGNA, and the NRC staff and their implementation ensures that the design of large and small bore piping and pipe supports at CPSES satisfies the applicable requirements of 10 CFR 50

Research on simulation of supercritical steam turbine system in large thermal power station

Science.gov (United States)

Zhou, Qiongyang

2018-04-01

In order to improve the stability and safety of supercritical steam turbine system operation in large thermal power station, the body of the steam turbine is modeled in this paper. And in accordance with the hierarchical modeling idea, the steam turbine body model, condensing system model, deaeration system model and regenerative system model are combined to build a simulation model of steam turbine system according to the connection relationship of each subsystem of steam turbine. Finally, the correctness of the model is verified by design and operation data of the 600MW supercritical unit. The results show that the maximum simulation error of the model is 2.15%, which meets the requirements of the engineering. This research provides a platform for the research on the variable operating conditions of the turbine system, and lays a foundation for the construction of the whole plant model of the thermal power plant.

Replacement of steam generators at arkansas nuclear one, unit-2 (ano-2)

International Nuclear Information System (INIS)

Wilson, R.M.; Buford, A.

2001-01-01

The Arkansas Nuclear One, Unit-2 steam generators, originally supplied by Combustion Engineering, began commercial operation in 1980 producing a gross electrical output of 958 MW. After several years of successful operation, the owner decided that the tube degradation rates of the original steam generators were too high for the plant to meet the performance requirements for the full 40-year license period. The contract to supply replacement steam generators (RSGs) was awarded to Westinghouse Electric Company in 1996. Installation of these RSGs took place in the last months of 2000. This paper compares the design features of the original and re-placement steam generators with emphasis on design and reliability enhancements achieved. (author)

Three Mile Island Nuclear Station steam generator chemical cleaning

International Nuclear Information System (INIS)

Hansen, C.A.

1992-01-01

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

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

International Nuclear Information System (INIS)

1982-06-01

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

Steam-generator replacement sets new marks

International Nuclear Information System (INIS)

Beck, R.L.

1995-01-01

This article describes how, in one of the most successful steam-generator replacement experiences at PWRs worldwide, the V C Summer retrofit exceeded plant goals for critical-path duration, radiation, exposure, and radwaste generation. Intensive planning and teamwork, combined with the firm support of station management and the use of mockups to prepare the work crews for activity in a radiological environment, were key factors in the record performance achieved by South Carolina Electric and Gas Co (SCE and G) in replacing three steam generators at V C Summer nuclear station. The 97-day, two-hour breaker-to-breaker replacement outage -- including an eight-day delay for repair of leak in a small-bore seal-injection line of a reactor coolant pump (unrelated to the replacement activities) -- surpassed the project goal by over one day. Moreover, the outage was only 13 hours shy of the world record held by Virginia Power Co's North Anna Unit 1

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

Kawasaki steam power plant of Tokyo Electric Power Co. and an example of geothermal power generation

Energy Technology Data Exchange (ETDEWEB)

1961-01-01

The first part of this discussion is devoted to a description of the Kawasaki steam power plant, installed by Tokyo Electric Co. to supply electricity to the Keihin industrial area. The output is 700 MW and it possesses a thermal efficiency of 36.9%. The plant is operated automatically by remote control. The latter section describes the status of a geothermal power station in Hakone. It outlines the steam distribution piping, the steam itself, the turbine and vapor/water separation equipment. With regard to technical problems, it is suggested that old wells having weak pressure can be restored by self-cleaning and that further improvement can be brought about by dynamiting the base of the borehole.

Design and development of steam generators for the AGR power stations at Heysham II/Torness

Energy Technology Data Exchange (ETDEWEB)

Charcharos, A N; Jones, A G [National Nuclear Corp. Ltd., Cheshire (United Kingdom)

1984-07-01

The current AGR steam generator design is a development of the successful once-through units supplied for the Oldbury Magnox and Hinkley/Hunterston AGR power stations. These units have demonstrated proven control and reliability in service. In this paper the factors which have dictated the design and layout of the latest AGR steam generators are described and reference made to the latest high temperature design techniques that have been employed. Details of development work to support the design and establish the performance characteristics over the range of plant operating conditions are also given. To comply with current UK safety standards, the AGR steam generators and associated plant are designed to accommodate seismic loadings. In addition, provision is made for an independent heat removal system for post reactor trip operations. (author)

Design and development of steam generators for the AGR power stations at Heysham II/Torness

International Nuclear Information System (INIS)

Charcharos, A.N.; Jones, A.G.

1984-01-01

The current AGR steam generator design is a development of the successful once-through units supplied for the Oldbury Magnox and Hinkley/Hunterston AGR power stations. These units have demonstrated proven control and reliability in service. In this paper the factors which have dictated the design and layout of the latest AGR steam generators are described and reference made to the latest high temperature design techniques that have been employed. Details of development work to support the design and establish the performance characteristics over the range of plant operating conditions are also given. To comply with current UK safety standards, the AGR steam generators and associated plant are designed to accommodate seismic loadings. In addition, provision is made for an independent heat removal system for post reactor trip operations. (author)

Electricity Generation Through the Koeberg Nuclear Power Station of Eskom in South Africa

International Nuclear Information System (INIS)

Dladla, G.; Joubert, J.

2015-01-01

The poster provides information on the process of nuclear energy generation in a nuclear power plant in order to produce electricity. Nuclear energy currently provides approximately 11% of the world’s electricity needs, with Koeberg Nuclear Power Station situated in the Western Cape providing 4.4% of South Africa’s electricity needs. As Africa’s first nuclear power station, Koeberg has an installed capacity of 1910 MW of power. Koeberg’ s total net output is 1860 MW. While there are significant differences, there are many similarities between nuclear power plants and other electrical generating facilities. Uranium is used for fuel in nuclear power plants to make electricity. With the exception of solar, wind, and hydroelectric plants, all others including nuclear plants convert water to steam that spins the propeller-like blades of a turbine that spins the shaft of a generator. Inside the generator coils of wire and magnetic fields interact to create electricity. The energy needed to boil water into steam is produced in one of two ways: by burning coal, oil, or gas (fossil fuels) in a furnace or by splitting certain atoms of uranium in a nuclear energy plant. The uranium fuel generates heat through a controlled fission process fission, which is described in this poster presentation. The Koeberg Nuclear Power Station is a Pressurised water reactor (PWR). The operating method and the components of the Koeberg Power Station are also described. The nuclear waste generated at a nuclear power station is described under three headings— low-level waste, intermediate-level waste and used or spent fuel, which can be solid, liquid or gaseous. (author)

Search and Retrieval of Foreign Objects for the Steam Generator of Wolsung NPP Unit 1

Energy Technology Data Exchange (ETDEWEB)

Jeong, Woo-Tae; Lee, Kyung-Ho [KHNP CRI, Daejeon (Korea, Republic of)

2016-10-15

We developed a foreign object search and retrieval (FOSAR) system for Wolsung NPP unit 1 steam generators. The steam generators of Wolsung NPP unit 1 have one 2.5 inch hand hole and two 4 inch hand holes. The FOSAR system was designed to be installed through 4 inch hand holes. Using permanent magnet, the FOSAR system was firmly attached to the vertical annulus wall of the steam generator. We successfully developed the FOSAR system for Wolsung NPP unit 1. Using the developed FOSAR system, technicians successfully found and removed various foreign objects. Most of the foreign objects, we found, were made of carbon steel sheet, therefore magnet tool was the most useful to remove it. Alligator tool was sometimes used. Based on the experience during the FOSAR activities, we are developing a lancing system for Wolsung NPP unit 1. It will be designed and manufactured until November 2016.

Search and Retrieval of Foreign Objects for the Steam Generator of Wolsung NPP Unit 1

International Nuclear Information System (INIS)

Jeong, Woo-Tae; Lee, Kyung-Ho

2016-01-01

We developed a foreign object search and retrieval (FOSAR) system for Wolsung NPP unit 1 steam generators. The steam generators of Wolsung NPP unit 1 have one 2.5 inch hand hole and two 4 inch hand holes. The FOSAR system was designed to be installed through 4 inch hand holes. Using permanent magnet, the FOSAR system was firmly attached to the vertical annulus wall of the steam generator. We successfully developed the FOSAR system for Wolsung NPP unit 1. Using the developed FOSAR system, technicians successfully found and removed various foreign objects. Most of the foreign objects, we found, were made of carbon steel sheet, therefore magnet tool was the most useful to remove it. Alligator tool was sometimes used. Based on the experience during the FOSAR activities, we are developing a lancing system for Wolsung NPP unit 1. It will be designed and manufactured until November 2016

Design and performance of BWC replacement steam generators for PWR systems

Energy Technology Data Exchange (ETDEWEB)

Klarner, R.; Steinmoeller, F.; Millman, J.; Schneider, W. [Babcock and Wilcox Canada, Cambridge, Ontario (Canada)

1998-07-01

In recent years, Babcock and Wilcox Canada (BWC) has provided a number of PWR Replacement Steam Generators (RSGS) to replace units that had experienced extensive Alloy 600 tube degradation. BWC RSG units are in operation at Northeast Utilities' Millstone Unit 2, Rochester Gas and Electric's Ginna Station, Duke Energy's Catawba Unit 1, McGuire Unit 1 and 2, Florida Power and Light's St. Lucie Unit 1 and Commonwealth Edison's Byron 1 Station. Extensive start-up performance characteristics have been obtained for Millstone 2, Ginna, McGuire 1, and Catawba 1 RSGS. The Millstone 2, Ginna and Catawba 1 RSGs have also undergone extensive inspections following their first cycle of operation. The design and start-up performance characteristics of these RSGs are presented. The BWC Replacement Steam generators were designed to fit the existing envelope of pressure boundary dimensions to ensure licensability and integration into the Nuclear Steam Supply System. The RSGs were provided with a tube bundle of Alloy 690TT tubing, sized to match or exceed the original steam generator (OSG) thermal performance including provision for the reduced thermal conductivity of Alloy 690 relative to Alloy 600. The RSG tube bundle configurations provide a higher circulation design relative to the OSG, and feature corrosion resistant lattice grid and U-bend tube supports which provide effective anti-vibration support. The tube bundle supports accommodate relatively unobstructed flow and allow unrestrained structural interactions during thermal transients. Efficient steam separators assure low moisture carryover as well as high circulation. Performance measurements obtained during start-up verify that the BWC RSGs meet or exceed the specified thermal and moisture carryover performance requirements. RSG water level stability results at nor-mal operation and during plant transients have been excellent. Visual and ECT inspections have confirmed minimal deposition and 100

Duke Power Company - McGuire Nuclear Station: steam-generator hideout return and cleanup

International Nuclear Information System (INIS)

Anon.

1986-01-01

McGuire Nuclear Station steam generator hideout return and cleanup are discussed. Hideout return data are presented for Unit 1 shutdowns that occurred on November 23, 1984, and April 19, 1985, and a Unit 2 shutdown on January 25, 1985. The data are presented as the concentrations of various species as a function of time after power reduction and primary water temperature. The steam generator blowdown as a function of time after power reduction is also presented. The concentrations of sodium, potassium, calcium, magnesium, aluminum, iron, and copper cations, and chloride, fluoride, sulfate, phosphate and nitrite anions were monitored during the each shutdown. Silica was also measured in the two 1985 shutdowns. The return of sulfate, phosphate, calcium and magnesium showed retrograde solubility. Silica concentrations showed an increase as the temperature decreased to about 450 to 500 0 F and then they decreased as the temperature decreased. McGuire has a holf point at 300 at 350 0 F to clean up the steam generator secondary water. The return of sulfates should occur within 4 to 6 hours. The blowdown is maximized to reduce the secondary water impurity concentrations. Cleanup continues until the sulfate concentration is reduced to below 100 ppb. At that point cooldown is continued

Evaluation of material integrity on electricity generator water steam cycles component (Main Steam Pipe)

International Nuclear Information System (INIS)

Sudardjo; Histori; Triyadi, Ari

1998-01-01

The evaluation of material integrity on electricity generator component has been done. That component was main steam pipe of Unit II Suralaya Coal Fired Power Plant. evaluation was done by replication technique. The damage was found are two porosity's, from two point samples of six points sample population. Based on cavity evaluation in steels, which proposed by Neubauer and Wedel that porosity's still at class A damage. For class A damage, its means no remedial action would be required until next major scheduled maintenance outage. That porosity's was grouped on isolated cavities and not need ti repair that main steam pipe component less than three year after replication test

Technical specifications for the provision of heat and steam sources for INPP and Visaginas. Final report

International Nuclear Information System (INIS)

2003-01-01

In October 1999, the National Energy Strategy was approved by the Lithuanian Parliament. The National Energy Strategy included the decision to close Unit-1 of INPP before 2005. Later is has been decided to close Unit 2 before the end of 2009 as well. The closure and decommissioning will have heavy impact on the heat supply for the city of Visaginas. Unit 1 and Unit 2 of INPP supplies hot water and steam to INPP for process purposes and for space heating of residential and commercial buildings. When Unit 1 is permanently shut down, reliable heat and steam sources independent of the power plants own heat and steam generation facilities are required for safety reasons in the event of shutdown of the remaining unit for maintenance or in an emergency. These steam and heat sources must be operational before single unit operation is envisaged. Provision of a reliable independent heat and steam source is therefore urgent. After both reactors are shut down permanently, a steam source will be needed at the plant for radioactive waste storage and disposal. INPP and DEA has performed a feasibility study for the provision of a reliable heat source for Ignalina Nuclear Power Plant and Visaginas, and the modernisation of Visaginas district heating system. The objective of this project is to prepare technical specifications for the provision of new heat and steam sources for INPP and Visaginas, and for rehabilitation of the heat transmission pipeline between INPP, the back-up boiler station and Visaginas City. The results of the study are presented in detail in the reports and technical specifications: 1. Transient analysis for Visaginas DH system, 2. Non-destructive testing of boiler stations, pump stations and transmission lines, 3. Conceptual design, 4. Technical specifications, Package 1 to 6. The study has suggested: 1. Construction of new steam boiler station, 2. Construction of new heat only boiler station, 3. Renovation of existing back-up heat only boiler station, 4

Safety evaluation report related to the operation of Susquehanna Steam Electric Station, Units 1 and 2. Docket Nos. 50-387 and 50-388, Pennsylvania Power and Light Company, Allegheny Electric Cooperative, Inc

International Nuclear Information System (INIS)

1982-07-01

Information is presented concerning site characteristics; design criteria for systems and components; reactor thermal and hydraulic characteristics; reactor coolant pressure boundary; engineered safety features; instrumentation and control; electrical power systems; auxiliary systems; conduct of operations; quality assurance; and TMI-2 requirements

Trouble found in regular inspection of No.1 plant in Ikata Power Station, Shikoku Electric Power Co., Inc

International Nuclear Information System (INIS)

1989-01-01

Since May 2, 1989, the regular inspection of No.1 plant which is a PWR plant with the rated output of 566 MW in Ikata Power Station, Shikoku Electric Power Co., Inc. has been carried out, and eddy current flaw detection inspection was conducted on the total 6585 heating tubes of steam generators except already plugged tubes. As the result, significant indication was observed in 12 heating tubes at the expanded part of the high temperature side tube plates. As to the cause, similarly to those observed in the same plant in the past, it is considered that the residual stress caused by expanding at the time of the manufacture and the internal pressure stress during the operation were superposed, and stress corrosion cracking occurred. It was decided that these 12 defective tubes are plugged. State of plugging in steam generators. Number of total heating tubes: 6776=3388 tubes x 2 steam generators. Number of plugged tubes: 203 including the increase of 12 this time. Ratio of plugging: 3.0 %. Heating tubes: Inconel 600 tubes of φ22.7 mm x 1.27 mm thickness. (K.I.)

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

International Nuclear Information System (INIS)

White, R.L.

1983-01-01

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

Results of the 5th regular inspection of Unit 1 in the Hamaoka Nuclear Power Station

International Nuclear Information System (INIS)

1983-01-01

The 5th regular inspection of Unit 1 in the Hamaoka Nuclear Power Station was carried out from March 27 to July 27, 1982. Inspection was made on the reactor proper, reactor cooling system, instrumentation/control system, radiation control facility, etc. By the examinations of external appearance, leakage, performance, etc., no abnormality was observed. In the regular inspection, personnel exposure dose was all below the permissible level. The works done during the inspection were the following: the replacement of control rod drives, the replacement of core support-plate plugs, the repair of steam piping, steam extraction pipes and feed water heaters, the repair of a waste-liquid concentrator, the installation of barriers and leak detectors, the installation of drain sump monitors in a containment vessel, the replacement of concentrated liquid waste pumps, the employment of type B fuel. (Mori, K.)

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

International Nuclear Information System (INIS)

1981-01-01

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

Experience and development of on-line BWR surveillance system at Onagawa nuclear power station unit-1

International Nuclear Information System (INIS)

Kishi, A.; Chiba, K.; Kato, K.; Ebata, S.; Ando, Y.; Sakamoto, H.

1986-01-01

ONAGAWA nuclear power station Unit-1 (Tohoku Electric Power Co.) is a BWR-4 nuclear power station of 524 MW electric power which started commercial operation in June 1984. To attain high reliability and applicability for ONAGAWA-1, Tohoku Electric Power Co. and Toshiba started a Research and Development project on plant surveillance and diagnosis from April 1982. Main purposes of this project are to: (1) Develop an on-line surveillance system and acquire its operating experience at a commercial BWR, (2) Assist in plant operation and maintenance by data acquisition and analysis, (3) Develop a new technique for plant surveillance and diagnosis. An outline of the project, operating experience gained from the on-line surveillance system and an introduction to new diagnosis techniques are reported in this paper. (author)

Development of a steam generator lancing system

International Nuclear Information System (INIS)

Jeong, Woo-Tae; Kim, Seok-Tae; Hong, Sung-Yull

2006-01-01

It is recommended to clean steam generators of nuclear power plants during plant outages. Under normal operations, sludge is created and constantly accumulates in the steam generators. The constituents of this sludge are different depending on each power plant characteristics. The sludge of the Kori Unit 1 steam generator, for example, was found to be composed of 93% ferrous oxide, 3% carbon and 1% of silica oxide and nickel oxide each. The research to develop a lancing system that would remove sludge deposits from the tubesheet of a steam generator was started in 1998 by the Korea Electric Power Research Institute (KEPRI) of the Korea Electric Power Corporation (KEPCO). The first commercial domestic lancing system in Korea, and KALANS-I Lancing System, was completed in 2000 for Kori Unit 1 for cleaning the tubesheet of its Westinghouse Delta-60 steam generator. Thereafter, the success of the development and site implementation of the KALANS-I lancing system for YGN Units 1 and 2 and Ulchin Units 3 and 4 was also realized in 2004 for sludge removal at those sites. The upper bundle cleaning system for Westinghouse model F steam generators is now under development

Vibration Spectrum Analysis for Indicating Damage on Turbine and Steam Generator Amurang Unit 1

Directory of Open Access Journals (Sweden)

Beny Cahyono

2017-12-01

Full Text Available Maintenance on machines is a mandatory asset management activity to maintain asset reliability in order to reduce losses due to failure. 89% of defects have random failure mode, the proper maintenance method is predictive maintenance. Predictive maintenance object in this research is Steam Generator Amurang Unit 1, which is predictive maintenance is done through condition monitoring in the form of vibration analysis. The conducting vibration analysis on Amurang Unit 1 Steam Generator is because vibration analysis is very effective on rotating objects. Vibration analysis is predicting the damage based on the vibration spectrum, where the vibration spectrum is the result of separating time-based vibrations and simplifying them into vibrations based on their frequency domain. The transformation of time-domain-wave into frequency-domain-wave is using the application of FFT, namely AMS Machinery. The measurement of vibration value is done on turbine bearings and steam generator of Unit 1 Amurang using Turbine Supervisory Instrument and CSI 2600 instrument. The result of this research indicates that vibration spectrum from Unit 1 Amurang Power Plant indicating that there is rotating looseness, even though the vibration value does not require the Unit 1 Amurang Power Plant to stop operating (shut down. This rotating looseness, at some point, can produce some indications that similar with the unbalance. In order to avoid more severe vibrations, it is necessary to do inspection on the bearings in the Amurang Unit 1 Power Plant.

Preoperation of Hamaoka Nuclear Power Station Unit No. 4

International Nuclear Information System (INIS)

Fukuyo, Tadashi; Kurata, Satoshi

1994-01-01

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

Reconstruction of steam generators super emergency feadwater supply system (SHNC) and steam dump stations to the atmosphere system PSA

International Nuclear Information System (INIS)

Kuzma, J.

2001-01-01

Steam Generators Super Emergency Feadwater Supply System (SHNC) and Steam Dump Stations to the Atmosphere System (PSA) are two systems which cooperate to remove residual heat from reactor core after seismic event. SHNC assure feeding of the secondary site of steam generator (Feed) where after heat removal.from primary loops, is relieved to the atmosphere by PSA (Bleed) in form of steam. (author)

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

Energy Technology Data Exchange (ETDEWEB)

1984-07-01

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

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

International Nuclear Information System (INIS)

1984-07-01

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

Power stations

International Nuclear Information System (INIS)

Cawte, H.; Philpott, E.F.

1980-01-01

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

Alternatives to electrical cogeneration: The direct application of steam engines

International Nuclear Information System (INIS)

Phillips, W.C.

1993-01-01

Although small to medium sized industrial facilities are aware of electrical cogeneration, often they are too small for it to be economically justifiable. The direct application of steam turbine power to equipment formerly powered by electric motors, can allow them to use steam capacity to reduce electrical demand and consumption, bypassing cogeneration. Cogeneration converts the heat energy of steam into circular mechanical motion and then converts the circular mechanical motion into electricity. Each conversion entails a loss of energy due to friction and other conversion losses. A substantial amount of the generated electricity is then converted back into circular motion with electric motors, again incurring energy losses. Directly applying the mechanical motion of turbines eliminates both the motion-to-electricity (generator) and the electricity-to-motion (motor) conversion losses. Excess steam capacity during the summer is not unusual for facilities that use steam to provide winter heating. Similarly, most of these facilities experience a large electrical demand peak during the cooling season due to the electricity needed to operate centrifugal chillers. Steam capacity via a turbine to power the chillers can allow the boilers to operate at a higher loading while reducing electrical consumption and demand precisely those periods when demand reduction is most needed. In facilities where the steam generating capacity is sufficient, air compressors provide an appropriate year-round application for turbine power. This paper is the result of an on-going project by the Energy Division, State of North Carolina, Department of Economic and Community Development, in conjunction with the University of North Carolina at Charlotte. The objective of this project is to educate the operating engineers and managers of small to medium sized manufacturing facilities on the technical application and economic justification of steam turbine power

Aerial radiological survey of the Comanche Peak Steam Electric Station and surrounding area, Glen Rose, Texas. Date of Survey: March 1982

International Nuclear Information System (INIS)

1982-12-01

An aerial radiological survey was performed from 1 to 9 March 1982 over a 260-square-kilometer area centered on the Comanche Peak Steam Electric Station located in Somervell County, Texas. The survey was conducted by the Energy Measurements Group of EG and G for the US Nuclear Regulatory Commission. All gamma ray data were collected by flying parallel lines spaced 152 meters (500 feet) apart at an altitude of 91 meters (300 feet) above ground level. Count rates obtained from the aerial platform were converted to total exposure rates at 1 meter above the ground and are presented in the form of an isoradiation contour map. The observed exposure rates ranged from 6 to 12 microroentgens per hour (μR/h), with the average background ranging from 6 to 8 μR/h. These values include an estimated cosmic ray contribution of 3.8 μR/h. The exposure rates obtained from ground-based measurements taken in typical background locations within the survey area displayed positive agreement with the aerial data

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

Science.gov (United States)

2011-05-02

... NUCLEAR REGULATORY COMMISSION [Docket Nos. 50-413 and 50-414; NRC-2011-0100; Docket Nos. 50-369 and 50-370; Docket Nos. 50-269, 50-270, and 50-287] Duke Energy Carolinas, LLC; Catawba Nuclear Station, Units 1 and 2; McGuire Nuclear Station, Units 1 and 2; Oconee Nuclear Station, Units 1, 2, and 3...

The steam generator repair project of the Donald C. Cook Nuclear Plant, Unit 2

International Nuclear Information System (INIS)

White, J.D.

1993-01-01

Donald C. Cook Nuclear Plant Unit 2 is part of a two unit nuclear complex located in southwestern Michigan and owned and operated by the Indiana Michigan Power Company. The Cook Nuclear Plant is a pressurized water reactor (PWR) plant with four Westinghouse Series 51 steam generators housed in an ice condenser containment. This paper describes the program undertaken by Indiana Michigan Power and the American Electric Power Service Corporation (AEPSC) to repair the Unit 2 steam generators. (Both Indiana Michigan Power and AEPSC arc subsidiaries of American Electric Power Company, Incorporated (AEP). AEPSC provides management and technical support services to Indiana Michigan Power and the other AEP operating companies.) Eddy current examinations, in a series of refueling and forced outages between November 1983 and July 1986 resulted in 763 (5.6%) plugged tubes. In order to maintain adequate reactor core cooling, a limit of 10% is placed on the allowable percentage of steam generator tubes that can be removed from service by plugging. Additionally, sections of tubes were removed for metallurgical analysis and confirmed that the degradation was due to intergranular stress corrosion cracking. In developing the decision on how to repair the steam generators, four alternative actions were considered for addressing these problems: retubing in place, sleeving, operating at 80% reactor power to lower temperature and thus reduce the rate of corrosion, replacing steam generator lower assemblies

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

International Nuclear Information System (INIS)

Nassersharif, B.

1986-01-01

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

Electric motorcycle charging station powered by solar energy

Science.gov (United States)

Siriwattanapong, Akarawat; Chantharasenawong, Chawin

2018-01-01

This research proposes a design and verification of an off-grid photovoltaic system (PVS) for electric motorcycle charging station to be located in King’s Mongkut’s University of Technology Thonburi, Bangkok, Thailand. The system is designed to work independently (off-grid) and it must be able to fully charge the batteries of a typical passenger electric motorcycle every evening. A 1,000W Toyotron electric motorcycle is chosen for this study. It carries five units of 12.8V 20Ah batteries in series; hence its maximum energy requirement per day is 1,200Wh. An assessment of solar irradiation data and the Generation Factor in Bangkok, Thailand suggests that the charging system consists of one 500W PV panel, an MPPT charge controller, 48V 150Ah battery, a 1,000W DC to AC inverter and other safety devices such as fuses and breakers. An experiment is conducted to verify the viability of the off-grid PVS charging station by collecting the total daily energy generation data in the raining season and winter. The data suggests that the designed off-grid solar power charging station for electric motorcycle is able to supply sufficient energy for daily charging requirements.

Analysis of electrical systems from Cernavoda NPP - Unit 1 based on commissioning activity

International Nuclear Information System (INIS)

Goia, M.L.; Manolescu, I.

1996-01-01

Several design solutions regarding the electrical part of Cernavoda NPP Unit 1 station auxiliaries are discussed in this paper. The solutions mentioned may have different variants which should be taken into consideration in the design of Units U2 - U5. This work offers an ample debate on such matters as the supply source connection of the station auxiliaries, the use of two different voltages for the mean voltage (MV) supply, the consequence of the lack of breakers on the 24 kV part of station auxiliary transformers T03 - T04, the protection devices non correlated with the breakers to which they react, as well as the consequences of low subtransient reactance of the new stand-by Diesel generators. Besides these design solutions that can influence the station auxiliaries reliability, matters as malfunctioning of the dry type MV/LV transformers and unreliable behaviour of some MV composite insulators are also discussed. For some of the above mentioned problems the authors proposed several solutions. (authors). 1 fig., 1 tab

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

International Nuclear Information System (INIS)

1975-01-01

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

High level waste (HLW) steam reducing station evaluation

International Nuclear Information System (INIS)

Gannon, R.E.

1993-01-01

Existing pressure equipment in High Level Waste does not have a documented technical baseline. Based on preliminary reviews, the existing equipment seems to be based on system required capacity instead of system capability. A planned approach to establish a technical baseline began September 1992 and used the Works Management System preventive maintenance schedule. Several issues with relief valves being undersized on steam reducing stations created a need to determine the risk of maintaining the steam in service. An Action Plan was developed to evaluate relief valves that did not have technical baselines and provided a path forward for continued operation. Based on Action Plan WER-HLE-931042, the steam systems will remain in service while the designs are being developed and implemented

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

International Nuclear Information System (INIS)

1976-10-01

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

Sourcing of Steam and Electricity for Carbon Capture Retrofits.

Science.gov (United States)

Supekar, Sarang D; Skerlos, Steven J

2017-11-07

This paper compares different steam and electricity sources for carbon capture and sequestration (CCS) retrofits of pulverized coal (PC) and natural gas combined cycle (NGCC) power plants. Analytical expressions for the thermal efficiency of these power plants are derived under 16 different CCS retrofit scenarios for the purpose of illustrating their environmental and economic characteristics. The scenarios emerge from combinations of steam and electricity sources, fuel used in each source, steam generation equipment and process details, and the extent of CO 2 capture. Comparing these scenarios reveals distinct trade-offs between thermal efficiency, net power output, levelized cost, profit, and net CO 2 reduction. Despite causing the highest loss in useful power output, bleeding steam and extracting electric power from the main power plant to meet the CCS plant's electricity and steam demand maximizes plant efficiency and profit while minimizing emissions and levelized cost when wholesale electricity prices are below 4.5 and 5.2 US¢/kWh for PC-CCS and NGCC-CCS plants, respectively. At prices higher than these higher profits for operating CCS retrofits can be obtained by meeting 100% of the CCS plant's electric power demand using an auxiliary natural gas turbine-based combined heat and power plant.

Steam turbines of large output especially for nuclear power stations. Part 1

International Nuclear Information System (INIS)

Drahny, J.; Stasny, M.

1986-01-01

At the international conference, 53 papers were presented in 3 sessions dealing with the design of large output steam turbines, with problems of flow in steam turbines, and with the reliability and service life of steam turbines. Part 1 of the conference proceedings contains two introductory papers, one reviewing the 100 years history of steam turbines (not included in INIS), the other giving an overview of the development of steam turbines in the eighties; and the 13 papers heard in the session on steam turbine design, all inputted in INIS. (A.K.)

Some causes of vibrations recorded by in-service diagnostic systems in steam generators of units 1 and 2 of Dukovany nuclear power plant

International Nuclear Information System (INIS)

Sadilek, J.; Matal, O.

1989-01-01

A brief description is presented of the design of the steam generators of the first and second units of the Dukovany nuclear power plant. Attention is also given to the feed water systems and the diagnostic systems. The causes are analyzed of the irregularly occurring vibrations in the steam generators in service. It is demonstrated that the source of the vibrations transmitted to the steam generators are the valves in the feeding tract. The vibrations are induced by dynamic forces from the feed water. Reducing the water pressure at the delivery of the electric feed pumps by reducing the size of the rotor, etc., does not remove all vibrations. It is therefore recommended that valves be ins+alled with better regulating characteristics. (Z.M.). 6 figs., 1 tab., 3 refs

Alteration in reactor installations (Unit 1 and 2 reactor facilities) in the Hamaoka Nuclear Power Station of The Chubu Electric Power Co., Inc. (report)

International Nuclear Information System (INIS)

1982-01-01

A report by the Nuclear Safety Commission to the Ministry of International Trade and Industry concerning the alteration in Unit 1 and 2 reactor facilities in the Hamaoka Nuclear Power Station, Chubu Electric Power Co., Inc., was presented. The technical capabilities for the alteration of reactor facilities in Chubu Electric Power Co., Inc., were confirmed to be adequate. The safety of the reactor facilities after the alteration was confirmed to be adequate. The items of examination made for the confirmation of the safety are as follows: reactor core design (nuclear design, mechanical design, mixed reactor core), the analysis of abnormal transients in operation, the analysis of various accidents, the analysis of credible accidents for site evaluation. (Mori, K.)

Burst protection device for largely cylindrical steam raising units, preferably of pressurized water nuclear power stations

International Nuclear Information System (INIS)

Mutzl, J.

1978-01-01

This burst protection device controls forces to be expected in an accident by resolving them into axial (vertical) and radial (horizontal) components, which are taken by a large number of elements stressed in tension. The steam raising unit is surrounded by a containment, but remains easily accessible. The containment consists of a steel jacket, lid and floor. Several cylindrical sections above one another form the steel jacket, which surrounds the steam raising unit with an intermediate insulating layer of concrete. The insulating concrete cylinder is of several times the thickness of the steel jacket, and also consists of cylindrical sections. An outer supporting ring for the lid and floor of the containment have outside diameters which project beyond the jacket. Prestressed circumferential vertical tension ropes between the supporting ring and floor take any additional tensional forces. The lid is domed with downward curvature towards the upper boiler dome. Internal bursting forces produce compressive stresses in the lid, which thus pass along its outside diameter into the surrounding ring. The lid, which is devided along one diameter, makes dismantling and access to the boiler easy even with a central steam pipe going upwards. The floor of the burst protection is also the floor of the steam raising unit. It is of several times the thickness of the tube floor, which, with its spacing above the floor forms the usual inlet and outlet space for the reactor cooling water. The main coolant pump installed there is driven by an external motor through a floor penetration. (HP) [de

Passive system with steam-water injector for emergency supply of NPP steam generators

International Nuclear Information System (INIS)

Il'chenko, A.G.; Strakhov, A.N.; Magnitskij, D.N.

2009-01-01

The calculation results of reliability indicators of emergency power supply system and emergency feed-water supply system of serial WWER-1000 unit are presented. To ensure safe water supply to steam generators during station blackout it was suggested using additional passive emergency feed-water system with a steam-water injector working on steam generators dump steam. Calculated analysis of steam-water injector operating capacity was conducted at variable parameters of steam at the entrance to injector, corresponding to various moments of time from the beginning of steam-and-water damping [ru

Troubles detected during regular inspection of No.1 plant in Oi Power Station, Kansai Electric Power Co., Inc

International Nuclear Information System (INIS)

1990-01-01

No. 1 plant in Oi Power Station, Kansai Electric Power Co., Inc. is a PWR plant with rated output of 1175 MW, and its regular inspection is carried out since August 14, 1989. When eddy current flaw detection inspection was carried out on the total number (11426 except already plugged tubes) of the heating tubes of steam generators, significant indication was observed in tube supporting plate part of 279 tubes, at the boundary of tube plate expanded part of 34 tubes, and in the tube plate expanded part of 99 tubes, 411 heating tubes in total (all on high temperature side). Consequently, it was decided to repair 367 tubes using sleeves, and to plug other 44 tubes. Besides, among the heating tubes plugged in the past, it was decided to remove plugs from 161 tubes, and by repairing them with sleeves, to use them again. Total number of heating tubes 13552 (3388 tubes x 4 steam generators), Number of plugged tubes 2009 (decrease by 117 this time), Ratio of plugging 14.8%. (K.I.)

Soviet steam generator technology: fossil fuel and nuclear power plants

International Nuclear Information System (INIS)

Rosengaus, J.

1987-01-01

In the Soviet Union, particular operational requirements, coupled with a centralized planning system adopted in the 1920s, have led to a current technology which differs in significant ways from its counterparts elsewhere in the would and particularly in the United States. However, the monograph has a broader value in that it traces the development of steam generators in response to the industrial requirements of a major nation dealing with the global energy situation. Specifically, it shows how Soviet steam generator technology evolved as a result of changing industrial requirements, fuel availability, and national fuel utilization policy. The monograph begins with a brief technical introduction focusing on steam-turbine power plants, and includes a discussion of the Soviet Union's regional power supply (GRES) networks and heat and power plant (TETs) systems. TETs may be described as large central co-generating stations which, in addition to electricity, provide heat in the form of steam and hot water. Plants of this type are a common feature of the USSR today. The adoption of these cogeneration units as a matter of national policy has had a central influence on Soviet steam generator technology which can be traced throughout the monograph. The six chapters contain: a short history of steam generators in the USSR; steam generator design and manufacture in the USSR; boiler and furnace assemblies for fossil fuel-fired power stations; auxiliary components; steam generators in nuclear power plants; and the current status of the Soviet steam generator industry. Chapters have been abstracted separately. A glossary is included containing abbreviations and acronyms of USSR organizations. 26 references

Steam Oxidation Testing in the Severe Accident Test Station

Energy Technology Data Exchange (ETDEWEB)

Pint, Bruce A. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

2017-08-01

After the March 2011 accident at Fukushima Daiichi, Oak Ridge National Laboratory (ORNL) began conducting high temperature steam oxidation testing of candidate materials for accident tolerant fuel (ATF) cladding in August 2011 [1-11]. The ATF concept is to enhance safety margins in light water reactors (LWR) during severe accident scenarios by identifying materials with 100× slower steam oxidation rates compared to current Zr-based alloys. In 2012, the ORNL laboratory equipment was expanded and made available to the entire ATF community as the Severe Accident Test Station (SATS) [4,12]. Compared to the current UO2/Zr-based alloy fuel system, an ATF alternative would significantly reduce the rate of heat and hydrogen generation in the core during a coolant-limited severe accident [13-14]. The steam oxidation behavior of candidate materials is a key metric in the evaluation of ATF concepts and also an important input into models [15-17]. However, initial modeling work of FeCrAl cladding has used incomplete information on the physical properties of FeCrAl. Also, the steam oxidation data being collected at 1200°-1700°C is unique as no prior work has considered steam oxidation of alloys at such high temperatures. Also, because many accident scenarios include steadily increasing temperatures, the required data are not traditional isothermal exposures but exposures with varying “ramp” rates. In some cases, the steam oxidation behavior has been surprising and difficult to interpret. Thus, more fundamental information continues to be collected. In addition, more work continues to focus on commercially-manufactured tube material. This report summarizes recent work to characterize the behavior of candidate alloys exposed to high temperature steam, evaluate steam oxidation behavior in various ramp scenarios and continue to collect integral data on FeCrAl compared to conventional Zr-based cladding.

Final environmental statement related to the operation of H.B. Robinson Nuclear Steam-Electric Plant, Unit 2: (Docket No. 50-261)

International Nuclear Information System (INIS)

1975-04-01

The proposed action is the continuation of Facility Operating License DPR-23 to Carolina Power and Light Company for H.B. Robinson Unit 2. Unit 2, located adjacent to Lake Robinson in Darlington County, near Hartsville, South Carolina, employs a pressurized water reactor to produce up to 2200 megawatts thermal (MWt). A steam turbine-generator uses this heat to provide 700 megawatts electric (MWe) of net electrical power capacity. A design power level of 2300 MWt (730 MWe) has been requested and is considered in the assessments contained in this statement. The exhaust steam is cooled by a flow of water obtained from the discharged to a 2250-acre cooling lake, Lake Robinson. Land areas disturbed during construction of the plant, but not used, have been seeded to native grasses, trees, and shrubs. Construction of a cooling water discharge canal extension resulted in alteration of about 100 acres of wildlife habitat. Subsequently, the canal banks were seeded with pines and legumes. Some erosion has taken place in the pine-seeded areas. Some small fish are killed by impingement on the water intake screens. Organisms passing through the screens very likely do not survive their passage through the circulating water system. Operation of the plant will cause an increase in the temperature of Black Creek below Lake Robinson. A small impact exists due to production and, after processing, disposal or release of sanitary and chemical wastes. Unit 2 may discharge up to 500 pounds/day of chemicals (primarily sulfates). Under conditions of low flow into and out of the lake, this increases the sulfate concentration in the lake by less than 1 ppM over the normal 7.7 ppM

Upgrading the SPP-500-1 moisture separators-steam reheaters used in the Leningrad NPP turbine units

Science.gov (United States)

Legkostupova, V. V.; Sudakov, A. V.

2015-03-01

The specific features of existing designs of moisture separators-steam reheaters (MSRs) and experience gained with using them at nuclear power plants are considered. Main factors causing damage to and failures of MSRs are described: nonuniform distribution of wet steam flow among the separation modules, breakthrough of moisture through the separator (and sometimes also through the steam reheater), which may lead to the occurrence of additional thermal stresses and, hence, to thermal-fatigue damage to or stress corrosion cracking of metal. MSR failure results in a less efficient operation of the turbine unit as a whole and have an adverse effect on the reliability of the low-pressure cylinder's last-stage blades. By the time the design service life of the SPP-500-1 MSRs had been exhausted in power units equipped with RBMK-1000 reactors, the number of damages inflicted to both the separation part and to the pipework and heating surface tubes was so large, that a considerable drop of MSR effectiveness and turbine unit efficiency as a whole occurred. The design of the upgraded separation part used in the SPP-500-1 MSR at the Leningrad NPP is described and its effectiveness is shown, which was confirmed by tests. First, efforts taken to achieve more uniform distribution of moisture content over the perimeter and height of steam space downstream of the separation modules and to bring it to values close to the design ones were met with success. Second, no noticeable effect of the individual specific features of separation modules on the moisture content was revealed. Recommendations on elaborating advanced designs of moisture separators-steam reheaters are given: an MSR arrangement in which the separator is placed under or on the side from the steam reheater; axial admission of wet steam for ensuring its uniform distribution among the separation modules; inlet chambers with an extended preliminary separation system and devices for uniformly distributing steam flows in the

Electricity from geothermal steam

Energy Technology Data Exchange (ETDEWEB)

Wheatcroft, E L.E.

1959-01-01

The development of the power station at Wairakei geothermal field is described. Wairakei is located at the center of New Zealand's volcanic belt, which lies within a major graben which is still undergoing some degree of downfaulting. A considerable number of wells, some exceeding 610 m, have been drilled. Steam and hot water are produced from both deep and shallow wells, which produce at gauge pressures of 1.5 MPa and 0.6 MPa, respectively. The turbines are fed by low, intermediate, and high pressure mains. The intermediate pressure turbine bank was installed as a replacement for a heavy water production facility which had originally been planned for the development. Stage 1 includes a 69 MW plant, and stage 2 will bring the capacity to 150 MW. A third stage, which would bring the output up to 250 MW had been proposed. The second stage involves the installation of more high pressure steam turbines, while the third stage would be powered primarily by hot water flashing. Generation is at 11 kV fed to a two-section 500 MVA board. Each section of the board feeds through a 40 MVA transformer to a pair of 220 V transmission lines which splice into the North Island grid. Other transformers feed 400 V auxiliaries and provide local supply.

Steam generator leak detection at Bruce A Unit 1

International Nuclear Information System (INIS)

Maynard, K.J.; McInnes, D.E.; Singh, V.P.

1997-01-01

A new steam generator leak detection system was recently developed and utilized at Bruce A. The equipment is based on standard helium leak detection, with the addition of moisture detection and several other capability improvements. All but 1% of the Unit 1 Boiler 03 tubesheet was inspected, using a sniffer probe which inspected tubes seven at a time and followed by individual tube inspections. The leak search period was completed in approximately 24 hours, following a prerequisite period of several days. No helium leak indications were found anywhere on the boiler. A single water leak indication was found, which was subsequently confirmed as a through-wall defect by eddy current inspection. (author)

Mini hydro electric power stations Lukar 1,2,3,4: Public enterprise (JP) Komunalec

International Nuclear Information System (INIS)

Stojanova, Blagica

2004-01-01

The role of the Public enterprises in improving entire living conditions of the citizens, not only by its services towards the citizenship such as: water supplying and public hygiene but the opportunity to produce the electric power by the Mini hydro electric-power stations built on the main city water supply pipes. The paper presents experiences of building the mini hydro electric power stations Lukar 1,2,3,4. The successful completion of this project should be a motivation for building more electric power stations because there are great water potential in the Republic of Macedonia i.e. there have been recorded more than a hundred places suitable for construction of power electric stations. This will contribute not only for clean ecological energy but will have a direct influence on the total economic development of the Republic of Macedonia. (Author)

Device for inspection and/or repair of a pipe of a steam raising unit of a nuclear power station

International Nuclear Information System (INIS)

Vermaat, H.P.

1986-01-01

Eddy current sensors are introduced into the pipe from the steam raising unit chamber. The two-part device on the supporting pillar is used to support the sensors and to position them, and so is an arm connected to it via a clutch. It is accommodated inside the steam raising chamber, but can be operated remotely from outside the steam raising chamber. This reduces the radiation loading of the operating staff. (DG) [de

Final environmental statement related to the operation of Byron Station, Units 1 and 2 (Docket Nos. STN 50-454 and STN 50-455)

International Nuclear Information System (INIS)

1982-04-01

The proposed action is the issuance of an operating license to Commonwealth Edison Company (CECo) of Chicago, Illinois, for startup and operation of the Byron Station, Units 1 and 2 on a 710-ha (1754-acre) site in Ogle County 6 km (4 miles) south-southwest of Byron, Illinois, and 3 km (2 miles) east of the Rock River. Each of the two generating units consists of a pressurized-water reactor, four steam generators, one steam turbine generator, a heat-dissipation system, and associated auxiliary and engineered safeguards. Information is presented under the following topics: purpose and need for the action; alternatives to the proposed action; project description and affected environment; environmental consequences and mitigating actions; evaluation of the proposed action; list of contributors; list of agencies and organizations requested to comment on the draft environmental statement; and responses to comments on the Draft Environmental Statement

Susquehanna SES maintenance supervisor training and certification

International Nuclear Information System (INIS)

Deckman, M.

1991-01-01

Susquehanna's program targets all Supervisors, Supervisor Candidates, and Temporary Supervisors that are responsible for in-plant maintenance or maintenance support activities, including: mechanical maintenance; electrical maintenance; maintenance support (labor support, radwaste, etc.); mobile construction support (mechanical and electrical); chemistry; health physics; maintenance planning; and instrument and controls. The program integrates the three major areas of direct Supervisory responsibilities: (1) Leadership and Management - Skills that require interpersonal activities that are typically humanistic and subjective; such as coaching, motivating, communications, etc. (2) Technical and Administrative - Knowledge that is directly related to the job of Supervising from the production, regulatory, accountability perspective. These topics are very objective and include training on topics such as workpackages, plant chemistry parameters, radiological concerns, etc. (3) Technical Skills - Ensure each Supervisor is technically competent in the plant systems, components, or equipment he/she is tasked with maintaining or overseeing. Typical skills found in this area are, circuit breaker maintenance, primary system sampling, or overhauling pumps

Draft environmental impact statement. New England Power Units 1 and 2 (NEP 1 and 2)

International Nuclear Information System (INIS)

Anon.

1979-01-01

Construction of New England Power Company Units 1 and 2 on 120 acres of 604-acre site near Block Island South in Charlestown, Rhode Island is proposed. Each unit would employ a pressurized water reactor to drive a steam turbine generator with a power rating of 1194 megawatts (MWe) of electric power capacity and a net output of 1150 MWe. A once-through flow of water obtained from and discharged into Block Island South at a rate of 1907 cubic feet per second would cool the units' exhaust steam. The station would transmit power through a 6700-foot, 345-kilovolt (kV) transmission line extending underground to the planned Charlestown substation, thence through a total of 70.5 miles of aboveground 345-kV line to the applicant's transmission system. The station would provide area consumers with a 2300-MWe base-load capacity and supply 14 billion kilowatt-hours annually during a 30-year operating life. Construction of the units would generate a total of $640 million in wages, plant operation would employ 250 persons with total wages of $8.4 million annually, and the applicant would contribute 90% of the Charlestown local tax base. Construction activities would cover 350 acres of land, and transmission line rights-of-way would require 1754 acres, including 1300 acres of forestland. Plant structures would mar the landscape, and the cooling system would contribute thermal pollution and some chemical pollutants to the Block Island Sound. Intermittent use of explosives would occur during an eight-to-ten-month period. Entrainment of fish in the cooling system could significantly reduce populations of tautog and cunner in the Block Island Sound

Nuclear Regulatory Commission Issuances, September 1981

International Nuclear Information System (INIS)

1981-01-01

Contents include: Issuances of the Nuclear Regulatory Commission--Commonwealth Edison Company (Dresden Nuclear Power Station, Unit 1), Consolidated Edison Company of New York (Indian Point, Unit 2), Metropolitan Edison Company, et al. (Three Mile Island Nuclear Station, Unit 1), Pacific Gas and Electric Company (Diablo Canyon Nuclear Power Plant, Units 1 and 2), Pacific Gas and Electric Company (Diablo Canyon Nuclear Power Plant, Units 1 and 2), Power Authority of the State of New York (Indian Point, Unit 3), Texas Utilities Generating Company, et al. (Comanche Peak Steam Electric Station, Units 1 and 2); Issuances of Atomic Safety and Licensing Appeal Boards--Pacific Gas and Electric Company (Diablo Canyon Nuclear Power Plant, Units 1 and 2), Philadelphia Electric Company, et al. (Peach Bottom Atomic Power Statin, Units 2 and 3), Metropolitan Edison Company, et al. (Three Mile Island Nuclear Statin, Unit No. 2), Public Service Electric and Gas Company (Hope Creek Generating Station, Units 1 and 2), The Toledo Edison Company, et al. (Davis-Besse Nuclear Power Station, Units 2 and 3); Issuances of the Atomic Safety Licensing Boards--Cleveland Electric Illuminating Company, et al. (Perry Nuclear Power Plant, Units 1 and 2), Commonwealth Edison Company (Dresden Station, Units 2 and 3), Houston Lighting and Power Company (Allens Creek Nuclear Generating Station, Unit 1), Southern California Edison Company, et al. (San Onofre Nuclear Generating Station, Units 2 and 3), Texas Utilities Generating Company, et al. (Comanche Peak Steam Electric Station, Units 1 and 2), Texas Utilities Generating Company, et al

A unique manual method for emergency offsite dose calculations

International Nuclear Information System (INIS)

Wildner, T.E.; Carson, B.H.; Shank, K.E.

1987-01-01

This paper describes a manual method developed for performance of emergency offsite dose calculations for PP and L's Susquehanna Steam Electric Station. The method is based on a three-part carbonless form. The front page guides the user through selection of the appropriate accident case and inclusion of meteorological and effluent data data. By circling the applicable accident descriptors, the user circles the dose factors on pages 2 and 3 which are then simply multiplied to yield the whole body and thyroid dose rates at the plant boundary, two, five, and ten miles. The process used to generate the worksheet is discussed, including the method used to incorporate the observed terrain effects on airflow patterns caused by the Susquehanna River Valley topography

Corrective action program reengineering project

International Nuclear Information System (INIS)

Vernick, H.R.

1996-01-01

A series of similar refueling floor events that occurred during the early 1990s prompted Susquehanna steam electric station (SSES) management to launch a broad-based review of how the Nuclear Department conducts business. This was accomplished through the formation of several improvement initiative teams. Clearly, one of the key areas that benefited from this management initiative was the corrective action program. The corrective action improvement team was charged with taking a comprehensive look at how the Nuclear Department identified and resolved problems. The 10-member team included management and bargaining unit personnel as well as an external management consultant. This paper provides a summary of this self-assessment initiative, including a discussion of the issues identified, opportunities for improvement, and subsequent completed or planned actions

Analysis of flood-magnitude and flood-frequency data for streamflow-gaging stations in the Delaware and North Branch Susquehanna River Basins in Pennsylvania

Science.gov (United States)

Roland, Mark A.; Stuckey, Marla H.

2007-01-01

The Delaware and North Branch Susquehanna River Basins in Pennsylvania experienced severe flooding as a result of intense rainfall during June 2006. The height of the flood waters on the rivers and tributaries approached or exceeded the peak of record at many locations. Updated flood-magnitude and flood-frequency data for streamflow-gaging stations on tributaries in the Delaware and North Branch Susquehanna River Basins were analyzed using data through the 2006 water year to determine if there were any major differences in the flood-discharge data. Flood frequencies for return intervals of 2, 5, 10, 50, 100, and 500 years (Q2, Q5, Q10, Q50, Q100, and Q500) were determined from annual maximum series (AMS) data from continuous-record gaging stations (stations) and were compared to flood discharges obtained from previously published Flood Insurance Studies (FIS) and to flood frequencies using partial-duration series (PDS) data. A Wilcoxon signed-rank test was performed to determine any statistically significant differences between flood frequencies computed from updated AMS station data and those obtained from FIS. Percentage differences between flood frequencies computed from updated AMS station data and those obtained from FIS also were determined for the 10, 50, 100, and 500 return intervals. A Mann-Kendall trend test was performed to determine statistically significant trends in the updated AMS peak-flow data for the period of record at the 41 stations. In addition to AMS station data, PDS data were used to determine flood-frequency discharges. The AMS and PDS flood-frequency data were compared to determine any differences between the two data sets. An analysis also was performed on AMS-derived flood frequencies for four stations to evaluate the possible effects of flood-control reservoirs on peak flows. Additionally, flood frequencies for three stations were evaluated to determine possible effects of urbanization on peak flows. The results of the Wilcoxon signed

Station power supply by residual steam of Fugen

Energy Technology Data Exchange (ETDEWEB)

Kamiya, Y.; Kato, H.; Hattori, S. (Power Reactor and Nuclear Fuel Development Corp., Tokyo (Japan))

1981-09-01

In the advanced thermal reactor ''Fugen'', when the sudden decrease of load more than 40% occurs due to the failure of power system, the turbine regulating valve is rapidly shut, and the reactor is brought to scrum. However, the operation of turbo-generators is continued with the residual steam in the reactor, and the power for inside the station is supplied for 30 sec by the limiting timer, then the power-generating plant is automatically stopped. The reasons why such design was adopted are to reduce manual operation at the time of emergency, to continue water supply for cooling the reactor and to maintain the water level in the steam drum, and to reduce steam release from the safety valve and the turbine bypass valve. The output-load unbalance relay prevents the everspeed of the turbo-generator when load decreased suddenly, but when the failure of power system is such that recovers automatically in course of time, it does not work. The calculation for estimating the dynamic characteristics at the time of the sole operation within the station is carried out by the analysis code FATRAC. The input conditions for the calculation and the results are reported. Also the dynamic characteristics were actually tested to confirm the set value of the limiting timer and the safe working of turbine and generator trips. The estimated and tested results were almost in agreement.

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

Science.gov (United States)

2010-06-28

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

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

Science.gov (United States)

2013-12-24

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

Assessment of MTI Water Temperature Retrievals with Ground Truth from the Comanche Peak Steam Electric Station Cooling Lake

International Nuclear Information System (INIS)

Kurzeja, R.J.

2002-01-01

Surface water temperatures calculated from Multispectral Thermal Imager (MTI) brightness temperatures and the robust retrieval algorithm, developed by the Los Alamos National Laboratory (LANL), are compared with ground truth measurements at the Squaw Creek reservoir at the Comanche Peak Steam Electric Station near Granbury Texas. Temperatures calculated for thirty-four images covering the period May 2000 to March 2002 are compared with water temperatures measured at 10 instrumented buoy locations supplied by the Savannah River Technology Center. The data set was used to examine the effect of image quality on temperature retrieval as well as to document any bias between the sensor chip arrays (SCA's). A portion of the data set was used to evaluate the influence of proximity to shoreline on the water temperature retrievals. This study found errors in daytime water temperature retrievals of 1.8 C for SCA 2 and 4.0 C for SCA 1. The errors in nighttime water temperature retrievals were 3.8 C for SCA 1. Water temperature retrievals for nighttime appear to be related to image quality with the largest positive bias for the highest quality images and the largest negative bias for the lowest quality images. The daytime data show no apparent relationship between water temperature retrieval error and image quality. The average temperature retrieval error near open water buoys was less than corresponding values for the near-shore buoys. After subtraction of the estimated error in the ground truth data, the water temperature retrieval error was 1.2 C for the open-water buoys compared to 1.8 C for the near-shore buoys. The open-water error is comparable to that found at Nauru

Steam Pressure-Reducing Station Safety and Energy Efficiency Improvement Project

Energy Technology Data Exchange (ETDEWEB)

Lower, Mark D [ORNL; Christopher, Timothy W [ORNL; Oland, C Barry [ORNL

2011-06-01

The Facilities and Operations (F&O) Directorate is sponsoring a continuous process improvement (CPI) program. Its purpose is to stimulate, promote, and sustain a culture of improvement throughout all levels of the organization. The CPI program ensures that a scientific and repeatable process exists for improving the delivery of F&O products and services in support of Oak Ridge National Laboratory (ORNL) Management Systems. Strategic objectives of the CPI program include achieving excellence in laboratory operations in the areas of safety, health, and the environment. Identifying and promoting opportunities for achieving the following critical outcomes are important business goals of the CPI program: improved safety performance; process focused on consumer needs; modern and secure campus; flexibility to respond to changing laboratory needs; bench strength for the future; and elimination of legacy issues. The Steam Pressure-Reducing Station (SPRS) Safety and Energy Efficiency Improvement Project, which is under the CPI program, focuses on maintaining and upgrading SPRSs that are part of the ORNL steam distribution network. This steam pipe network transports steam produced at the ORNL steam plant to many buildings in the main campus site. The SPRS Safety and Energy Efficiency Improvement Project promotes excellence in laboratory operations by (1) improving personnel safety, (2) decreasing fuel consumption through improved steam system energy efficiency, and (3) achieving compliance with applicable worker health and safety requirements. The SPRS Safety and Energy Efficiency Improvement Project being performed by F&O is helping ORNL improve both energy efficiency and worker safety by modifying, maintaining, and repairing SPRSs. Since work began in 2006, numerous energy-wasting steam leaks have been eliminated, heat losses from uninsulated steam pipe surfaces have been reduced, and deficient pressure retaining components have been replaced. These improvements helped ORNL

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

International Nuclear Information System (INIS)

Talbot, K.H.

1994-01-01

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

Amazing & extraordinary facts the steam age

CERN Document Server

Holland, Julian

2012-01-01

Respected transport author Julian Holland delves into the intriguing world of steam in his latest book, which is full of absorbing facts and figures on subjects ranging from Cornish beam engines, steam railway locomotives, road vehicles and ships through to traction engines, steam rollers and electricity generating stations and the people who designed and built them. Helped along the way by the inventive minds of James Watt, Richard Trevithick and George Stephenson, steam became the powerhouse that drove the Industrial Revolution in Britain in the late 18th and 19th centuries.

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

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-02-01

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

Evaluation of River Bend Station Unit 1 Technical Specifications

International Nuclear Information System (INIS)

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

1985-08-01

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

Construction of Shika Nuclear Power Station Unit No.2 of the Hokuriku Electric Power Co., Inc

International Nuclear Information System (INIS)

Yamanari, Shozo; Miyahara, Ryohei; Umezawa, Takeshi; Teshiba, Ichiro

2006-01-01

Construction of the Shika Nuclear Power Station Unit No.2 of the Hokuriku Electric Power Co., Inc. (advanced boiling-water reactor; output: 1.358 mega watts) was begun in August 1999 and it will resume commercial operation in March 2006 as scheduled. Hitachi contributed effectually toward realizing the project with supply of a complete set of the advanced nuclear reactor and turbine-generator system with the latest design and construction technology in harmony. Large-scale modular structures for installation and a computer-aided engineering system for work procedure and schedule management were applied with the utmost priority placed on work efficiency, safety and quality assurance. (T.Tanaka)

Non-radiological consequences to the aquatic biota and fisheries of the Susquehanna River from the 1979 accident at Three Mile Island Nuclear Station

International Nuclear Information System (INIS)

Hickey, C.R. Jr.; Samworth, R.B.

1979-11-01

The non-radiological consequences to the aquatic biota and fishes of the Susquehanna River from the March 28, 1979 accident at Three Mile Island Nuclear Station were assessed through the post-accident period of July 1979. Thermal and chemical discharges during the period did not exceed required effluent limitations. Several million gallons of treated industrial waste effluents were released into the river which were not of unusual volumes compared with normal operation and were a very small proportion of the seasonally high river flows. The extent and relative location of the effluent plume were defined and the fisheries known to have been under its immediate influence were identified, including rough, forage, and predator/sport fishery species

Eddy Currents Inspection of CANDU Steam Generator Tubes using Zetec's ZR-1 Robot. Experience in Romania

International Nuclear Information System (INIS)

Scott Hower; Luiza Vladu; Adrian Nichisov; Mihai Cretu

2006-01-01

Full text of publication follows: The commercial operation of Unit 1 of Cernavoda NPP started on 2 December, 1996. The unit's reactor type is PHWR-CANDU 6 (electrical capacity 706 MWe), using natural uranium. The nuclear fuel is manufactured in Romania. The Cernavoda nuclear power plant has four CANDU - design steam generators that have been in service since 1996. The paper introduces the new ZR-1 Robot System for Inspection and Maintenance/Repair from Zetec that combines the newest state-of-the-art robotics technology with Zetec experience - based innovation to address the needs for inspection and repair of steam generators. The multipurpose ZR-1 can be easily installed to perform the necessary eddy current inspection and remain installed ready for follow-up maintenance and repair. It has superior technical performances and a modular three axis motion of arm that enables 100% coverage of tube sheet. Automated, repeatable, and precise positioning of tool heads ensures accurate delivery and reducing costly rework and reduces inspection time by 30%. The modular, light weight, and portable design permits easy assembly and disassembly through small openings and it reduces setup/tear down time by 30%. The first deployment of the new ZR-1 Robot was made in September 2004 at the Cernavoda NPP inspection outage. The unit's reactor type is PHWR-CANDU 6 (electrical capacity 706 MWe), using natural uranium; the nuclear fuel is manufactured in Romania. The Cernavoda nuclear power plant Unit 1 has four CANDU - design steam generators that have been in service since 1996. The paper presents also the Zetec's field experience and customer experience with this system. It describes the equipment setup in Cernavoda's steam generators mock-up, functional tests and calibration. Finally, provides details on the execution of the inspection, options for standardizing the inspection techniques and conclusions. (authors)

Evaluation of a main steam line break with induced, multiple tube ruptures: A comparison of NUREG 1477 (Draft) and transient methodologies Palo Verde Nuclear Generating Station

Energy Technology Data Exchange (ETDEWEB)

Parrish, K.R.

1995-09-01

This paper presents the approach taken to analyze the radiological consequences of a postulated main steam line break event, with one or more tube ruptures, for the Palo Verde Nuclear Generating Station. The analysis was required to support the restart of PVNGS Unit 2 following the steam generator tube rupture event on March 14, 1993 and to justify continued operation of Units 1 and 3. During the post-event evaluation, the NRC expressed concern that Unit 2 could have been operating with degraded tubes and that similar conditions could exist in Units 1 and 3. The NRC therefore directed that a safety assessment be performed to evaluate a worst case scenario in which a non-isolable main steam line break occurs inducing one or more tube failures in the faulted steam generator. This assessment was to use the generic approach described in NUREG 1477, Voltage-Based Interim Plugging Criteria for Steam Generator Tubes - Task Group Report. An analysis based on the NUREG approach was performed but produced unacceptable results for off-site and control room thyroid doses. The NUREG methodology, however, does not account for plant thermal-hydraulic transient effects, system performance, or operator actions which could be credited to mitigate dose consequences. To deal with these issues, a more detailed analysis methodology was developed using a modified version of the Combustion Engineering Plant Analysis Code, which examines the dose consequences for a main steam line break transient with induced tube failures for a spectrum equivalent to 1 to 4 double ended guillotine U-tube breaks. By incorporating transient plant system responses and operator actions, the analysis demonstrates that the off-site and control room does consequences for a MSLBGTR can be reduced to acceptable limits. This analysis, in combination with other corrective and recovery actions, provided sufficient justification for continued operation of PVNGS Units 1 and 3, and for the subsequent restart of Unit 2.

Evaluation of a main steam line break with induced, multiple tube ruptures: A comparison of NUREG 1477 (Draft) and transient methodologies Palo Verde Nuclear Generating Station

International Nuclear Information System (INIS)

Parrish, K.R.

1995-01-01

This paper presents the approach taken to analyze the radiological consequences of a postulated main steam line break event, with one or more tube ruptures, for the Palo Verde Nuclear Generating Station. The analysis was required to support the restart of PVNGS Unit 2 following the steam generator tube rupture event on March 14, 1993 and to justify continued operation of Units 1 and 3. During the post-event evaluation, the NRC expressed concern that Unit 2 could have been operating with degraded tubes and that similar conditions could exist in Units 1 and 3. The NRC therefore directed that a safety assessment be performed to evaluate a worst case scenario in which a non-isolable main steam line break occurs inducing one or more tube failures in the faulted steam generator. This assessment was to use the generic approach described in NUREG 1477, Voltage-Based Interim Plugging Criteria for Steam Generator Tubes - Task Group Report. An analysis based on the NUREG approach was performed but produced unacceptable results for off-site and control room thyroid doses. The NUREG methodology, however, does not account for plant thermal-hydraulic transient effects, system performance, or operator actions which could be credited to mitigate dose consequences. To deal with these issues, a more detailed analysis methodology was developed using a modified version of the Combustion Engineering Plant Analysis Code, which examines the dose consequences for a main steam line break transient with induced tube failures for a spectrum equivalent to 1 to 4 double ended guillotine U-tube breaks. By incorporating transient plant system responses and operator actions, the analysis demonstrates that the off-site and control room does consequences for a MSLBGTR can be reduced to acceptable limits. This analysis, in combination with other corrective and recovery actions, provided sufficient justification for continued operation of PVNGS Units 1 and 3, and for the subsequent restart of Unit 2

Identification of leaky steam generators by iodine mapping technique and development of tools for cutting of tubes of steam generators of Indian PHWRS

International Nuclear Information System (INIS)

Subba Rao, D.

2006-01-01

Kakrapar Atomic Power Station (2X220 MWe) located in Mandvi Taluka of Surat District in the state of Gujarat is the fifth Nuclear Power Station of the country. It has got an excellent record in the field of operation, safety, public awareness and emergency preparedness. KAPS Unit -1 achieved first criticality in Sep-1992 and was declared for commercial operation in may-1993. KAPS Unit -2 achieved first criticality in Jan-1995 and was declared for commercial operation in Sep-1995. So far station has generated about 30 billion units.Unit-1 achieved 98.4% and was graded as a world's No.1 in year 2002 amongst all CANDU type reactors. KAPS Unit -1 has made another record of operating continuously for more than 300 days in Indian PHWR s operating history. This paper mainly deals with the Indian PHWRs Steam Generators (SG) tube leaks, leaky steam generator identification by Iodine mapping, and development of special tool for cutting, removal and plugging of leaky tubes. These Steam Generators are designed by M/s Kraft Werke Union (KWU) of Siemens Group, West Germany, and Manufactured by M/s ENSA, SPAIN for Unit- 1 and by M/s MAN-GHH, Germany for Unit- 2. First time in October-2002 one of the Steam Generators of Unit-1 developed tube leak. To identify leaky Steam Generator, KAPS has established a method of Iodine mapping. With that the leaky SG was identified in very short time and corrective actions were taken immediately. Total three tube leaks (two in SG-4 of Unit-1 and one in SG-1 of unit-2) were experienced in both Units'. Following observations were made on SG tubes failure: All failures were in cold leg side; All Failures / deterioration locations were in front of main feed water nozzle; All Failures / deterioration locations were observed to be just above tube support plate (TSP) number 4 or 5; Deterioration ( i.e. wall thinning) observed from OD side and these tubes were adjacent to failed tubes; In all the three incidents, failed / deteriorated tubes were

New steam generators slated for nuclear units

International Nuclear Information System (INIS)

Anon.

1992-01-01

This article is a brief discussion of Duke Power's plans to replace steam generators at its McGuire and Catawba nuclear units. A letter of intent to purchase (from Babcock and Wilcox) the 12 Westinghouse steam generators has been signed, but no constructor has been selected at this time. This action is brought about by the failures of more than 3000 tubes in these units

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

International Nuclear Information System (INIS)

Selan, J.C.

1984-01-01

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

The expected environmental consequences and hazards of laser-fusion electric generating stations

International Nuclear Information System (INIS)

Devaney, J.J.; Pendergrass, J.H.

The operation of an expected early form of a laser-fusion electric power plant is described and the hazards and the environmental effects of such a station are estimated. Possible environmental impacts and hazards to mankind can occur from nuclear excursions or explosions, nuclear weapon proliferation, loss of coolant accident (LOCA), tritium releases, chemical fires and accompanying releases of radioactivity or chemicals, induced radioactivity releases (other than tritium), radioactive waste disposal, lasers, normal electrical generation and steam plant effects, external intrusions, natural disasters, land use, resource and transportation use, thermal pollution, and air and water pollution. We find the principle environmental effects to be those of a medium size chemical plant. Electric, magnetic, steam, and radioactive hazards are of a lower order. Indeed in the event of extraordinary success in getting high temperatures and densities so that more difficult nuclear species can be reacted, such as protons with boron-11, there will be no radioactivity at all and also enormously lower hazardous chemical inventories. In our plant designs, for any fusion fuels, nuclear explosions (or even excursions beyond design limits) are not possible. (author)

Postfact phenomena of the wet-steam flow electrization in turbines

Science.gov (United States)

Tarelin, A. A.

2017-11-01

Physical processes occurring in a turbine with natural electrization of a humidity-steam flow and their effect on efficiency and reliability of the turbine operation has been considered. Causes of the electrical potential occurrence on a rotor shaft are analyzed. The wet steam's electrization exposure on the electrical potential that is one of the major factors of bearings' electroerosion has been demonstrated on the full-scale installation. Hydrogen formation in wheelspace of the turbine as a result of electrochemical processes and electric field exposure of the space charge has been considered. Hydrogen concentration dependence on a volume charge density in the steam flow has been determined. It is stated that the processes occurring behind the final stage of wet-steam turbines are similar to the ones in elaerosol ectrostatic generators. It has been demonstrated that this phenomenon causes the flow's temporal inhibition and starts pulsations. These factors' impact on power loss of the turbine has been evaluated and recommendations for their elimination have been offered. It has been determined that motions of charged drops can cause self-maintained discharges inside of the flow and between the flow and grounded surfaces that are accompanied by electromagnetic radiation of the wide spectrum. The integrated studies have shown that physical phenomena occurring due to natural electrization negatively affect efficiency and reliability of the turbine operation. Practical recommendations allowing one to minimize the negative effects of the flow natural electrization process have been offered.

Cleaning device for steam units in a nuclear power plant

International Nuclear Information System (INIS)

Sasamuro, Takemi.

1978-01-01

Purpose: To prevent radioactive contamination upon dismantling and inspection of steam units such as a turbine to a building containing such units and the peripheral area. Constitution: A steam generator indirectly heated by steam supplied from steam generating source in a separate system containing no radioactivity is provided to produce cleaning steam. A cleaning steam pipe is connected by way of a stop valve between separation valve of a nuclear power plant steam pipe and a high pressure turbine. Upon cleaning, the separation valve is closed, and steam supplied from the cleaning steam pipe is flown into a condenser. The water thus condensated is returned by way of a feed water heater and a condenser to a water storage tank. (Nakamura, S.)

Eddy current magnetic bias x-probe qualification and inspection of steam generator Monel 400 tubing in Pickering Nuclear Generating Station

International Nuclear Information System (INIS)

Lepine, B.A.; Van Langen, J.; Obrutsky, L.

2006-01-01

This paper presents an overview of the x-probe MB 350 eddy current inspection array probe, for detection of open OD axial crack-like flaws in Monel 400 tubes at Pickering Nuclear Generating Station. This report contains a selection of inspection results from the field inspections performed with this probe during the 2003 and 2004 period at Pickering Nuclear Generating Station A and B. During the 2003 in-service eddy current inspection results of Pickering Nuclear Generating Station A (PNGS-A) Unit 2, a 13 mm (0.5 inch) long axial indication was detected by the CTR1 bobbin and CTR2-C4 array probes in Tube R25-C52 of Steam Generator (SG) 11 in the hot leg sludge pile region. An experimental magnetic bias X-probe, specially designed by Zetec for inspection of Monel 400 tubing, was deployed and the indication was characterized as a potential out diameter (OD) axially oriented crack. Post-inspection tube pulling and destructive examination confirmed the presence of an Environmentally Assisted Crack (EAC), approximately 80% deep and 13mm long. Due to the significance of this discovery, Ontario Power Generation (OPG) requested AECL to initiate a program for qualification of the X-probe MB 350 for the detection of OD axial cracks in medium to high magnetic permeability μ r Monel 400 PNGS-A and B steam generator tubing at different locations. The X-probe MB 350 subsequently has been deployed as a primary inspection probe for crack detection for PNGS steam generators. (author)

Steam generation unit in a simple version of biomass based small cogeneration unit

Directory of Open Access Journals (Sweden)

Sornek Krzysztof

2014-01-01

Full Text Available The organic Rankine cycle (ORC is a very promising process for the conversion of low or medium temperature heat to electricity in small and micro scale biomass powered systems. Classic ORC is analogous to Clausius–Rankine cycle in a steam power plant, but instead of water it uses low boiling, organic working fluids. Seeking energy and economical optimization of biomass-based ORC systems, we have proposed some modifications e.g. in low boiling fluid circuit construction. Due to the fact that the operation of a micro steam turbine is rather inefficient from the technical and economic point of view, a specially modified air compressor can be used as a steam piston engine. Such engine should be designed to work at low pressure of the working medium. Studies regarding the first version of the prototype installation were focused on the confirmation of applicability of a straw boiler in the prototype ORC power system. The results of the previous studies and the studies described in the paper (on the new cogeneration unit confirmed the high potential of the developed solution. Of course, many further studies have to be carried out.

76 FR 19148 - PSEG Nuclear, LLC, Hope Creek Generating Station and Salem Nuclear Generating Station, Units 1...

Science.gov (United States)

2011-04-06

... NUCLEAR REGULATORY COMMISSION [Docket Nos. 50-272, 50-311, 50-354; NRC-2009-0390 and NRC-2009-0391] PSEG Nuclear, LLC, Hope Creek Generating Station and Salem Nuclear Generating Station, Units 1 and 2..., DPR-70, and DPR-75 for an additional 20 years of operation for the Hope Creek Generating Station (HCGS...

Fast-Valving of Large Steam Turbine Units as a Means of Power System Security Enhancement

Directory of Open Access Journals (Sweden)

Bogdan Sobczak

2014-03-01

Full Text Available Fast-valving assists in maintaining system stability following a severe transmission system fault by reducing the turbine mechanical power. Fast-valving consists in rapid closing and opening of steam valves in an adequate manner to reduce the generator accelerating power following the recognition of a severe fault. FV can be an effective and economical method of meeting the performance requirements of a power system in the presence of an increase in wind and solar generation in the power system, newly connected large thermal units and delaying of building new transmission lines. The principle of fast-valving and advantages of applying this technique in large steam turbine units was presented in the paper. Effectiveness of fast-valving in enhancing the stability of the Polish Power Grid was analyzed. The feasibility study of fast-valving application in the 560 MW unit in Kozienice Power Station (EW SA was discussed.

Technical and economic studies of small reactors for supply of electricity and steam

International Nuclear Information System (INIS)

Spiewak, I.; Klepper, O.H.; Fuller, L.C.

1977-01-01

Several years ago conventional opinion held that nuclear power plants must be very large to be competitive with fossil fuels. This situation has changed markedly in most countries within recent years, as oil and gas supplies have become more scarce and costly. Studies have been carried out of several nuclear steam supply systems in the small and intermediate size range. Detail studies are reported of the Consolidated Nuclear Steam Generator (CNSG), a 313 MW(t) pressurized water reactor being developed by Babcock and Wilcox, as applied to industrial energy needs. Both conventional and barge-mounted nuclear steam supply systems are considered. Conceptual studies have been started of pressurized and boiling water reactors in the range of 1000 MW(t), which are envisioned for utility operation for supply of electric power and steam. Design studies of a 500 MW(t) high temperature reactor are also reported. The small reactors are expected to have higher unit costs than the large commercial plants, but to have compensating advantages in higher plant availability, shorter construction schedule and greater siting flexibility. Studies are also reported of power cycle parameters and cost allocations for extraction of steam from steam turbine plants. This steam could be used for industrial energy, district heating or desalination

Technical and economic studies of small reactors for supply of electricity and steam

International Nuclear Information System (INIS)

Spiewak, I.; Klepper, O.H.; Fuller, L.C.

1977-02-01

Several years ago conventional opinion held that nuclear power plants must be very large to be competitive with fossil fuels. This situation has changed markedly in most countries within recent years, as oil and gas supplies have become more scarce and costly. Studies have been carried out for several nuclear steam supply systems in the small and intermediate size range. Detail studies are reported of the Consolidated Nuclear Steam Generator (CNSG), a 365 MW(th) pressurized water reactor being developed by Babcock and Wilcox, as applied to industrial energy needs. Both conventional and barge-mounted nuclear steam supply systems are considered. Conceptual studies have been started of pressurized and boiling water reactors in the range of 1000 MW(th), which are envisioned for utility operation for supply of electric power and steam. Design studies of a 500 MW(th) high temperature reactor are also reported. The small reactors are expected to have higher unit costs than the large commercial plants, but to have compensating advantages in higher plant availability, shorter construction schedule, and greater siting flexibility. Studies are also reported of power cycle parameters and cost allocations for extraction of steam from steam turbine plants. This steam could be used for industrial energy, district heating, or desalination

Technical and economic studies of small reactors for supply of electricity and steam

International Nuclear Information System (INIS)

Spiewak, I.; Klepper, O.H.; Fuller, L.C.

1977-01-01

Several years ago conventional opinion held that nuclear power plants must be very large to be competitive with fossil fuels. This situation has changed markedly in most countries within recent years, as oil and gas supplies have become more scarce and costly. Studies have been carried out of several nuclear steam supply systems in the small and intermediate size range. Detail studies are reported of the Consolidated Nuclear Steam Generator (CNSG), a 313MW(th) pressurized water reactor being developed by Babcock and Wilcox, as applied to industrial energy needs. Both conventional and barge-mounted nuclear steam supply systems are considered. Conceptual studies have been started of pressurized and boiling water reactors in the range of 1000MW(th), which are envisioned for utility operation for supply of electric power and steam. Design studies of a 500MW(th) high temperature reactor are also reported. The small reactors are expected to have higher unit costs than the large commercial plants, but to have compensating advantages in higher plant availability, shorter construction schedule and greater siting flexibility. Studies are also reported of power cycle parameters and cost allocations for extraction of steam from steam turbine plants. This steam could be used for industrial energy, district heating or desalination. (author)

Trouble found during regular inspection of No.1 plant in Takahama Power Station, Kansai Electric Power Co., Inc

International Nuclear Information System (INIS)

1990-01-01

No.1 plant in Takahama Power Station, Kansai Electric Power Co., Inc. is a PWR plant with the rated output of 826 MWe. Its regular inspection has been carried out since August 10, 1989, and eddy current flaw detection inspection was performed on the total number of steam generator heating tubes (9619 tubes except already plugged tubes). As the result, significant indication was observed in 6 tubes in the U-bend part, in 6 tubes in the tube-supporting plate part, in 4 tubes in the crevice part in the tube plate, in 9 tubes in the expanded part in the tube plate and in 11 tubes at the boundary of the expanded part, in total in 36 heating tubes, all of them on high temperature side. Consequently, it was decided to plug these 36 defective heating tubes. The heating tubes are those made of Inconel 600, having 22.2 mm outside diameter and 1.27 mm wall thickness. (K.I.)

Chemistry, materials and related problems in steam generators of power stations

International Nuclear Information System (INIS)

Mathur, P.K.

2000-01-01

The operational reliability and availability of power plants are considerably influenced by chemical factors. Researches all over the world indicate that several difficulties in power plants can be traced to off-normal or abnormal water chemistry conditions. Whatever the source of energy, be it fossil fuel or nuclear fuel, the ultimate aim is steam generation to drive a turbine. It is, therefore, natural that problems of water chemistry and material compatibility are similar in thermal and nuclear power stations. The present paper discusses various types of problems in the form of corrosion damages, taking place in the boiler-turbine cycles and describes different types of boiler feed water/boiler water treatments that have been in use both in nuclear and thermal power stations. Current positions in relation to requirements of boiler feed water, boiler water and steam quality have been described

Steam generator waterlancing at DNGS

International Nuclear Information System (INIS)

Seppala, D.; Malaugh, J.

1995-01-01

Darlington Nuclear Generating Station (DNGS) is a four 900 MW Unit nuclear station forming part of the Ontario Hydro East System. There are four identical steam generators(SGs) per reactor unit. The Darlington SGs are vertical heat exchangers with an inverted U-tube bundle in a cylindrical shell. The DNGS Nuclear Plant Life Assurance Group , a department of DNGS Engineering Services have taken a Proactive Approach to ensure long term SG integrity. Instead of waiting until the tubesheets are covered by a substantial and established hard deposit; DNGS plan to clean each steam generator's tubesheet, first half lattice tube support assembly and bottom of the thermal plate every four years. The ten year business plan provides for cleaning and inspection to be conducted on all four SGs in each unit during maintenance outages (currently scheduled for every four years)

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

Development of radiation protection technology for application of the retired steam generator, Kori Unit no. 1

Energy Technology Data Exchange (ETDEWEB)

Kim, J. H.; Jang, D. C.; Song, K. S.; Lee, S. J.; Ahn, C. S.; Kim, D. H.; Im, Y. K.; Kim, H. D. [Hanil Nuclear Co., Ltd., Anyang (Korea, Republic of)

2005-04-15

It is a field study to develop and verify maintenance technologies such as verification and technology development of ECT (Eddy current test) using failure, heat tube excavation and field pressure test regarding the utilization of retired steam generator using 2 units of Retired Steam Generator in Kori 1 that was replaced for the first time in Korea in 1998. Since May, 2003, our team has investigated Retired Steam Generator which was stored in Radioactive waste warehouse in Korea Hydro and Nuclear Power Kori unit no.1 Branch, in order to study natural fault ECT signal acquisition, maintenance technology verification, small tubes/samples abstraction. A temporal task zone was made focusing on 'Man Way at the bottom of Chamber 'A'.' The purpose of the study is to establish Radiological Protection and Radioactive Waste Treatment Plan by setting ALARA (As Low As Reasonably Achievable) goal systematically, which is the basic concept of Radiological Protection and reduction in exposure of radiological workers to radioactive materials with proper Radiological Protection countermeasures according to the changes in radioactivity, to prevent expansion from contamination and to manage 'Radioactive Waste Reduction Activities' effectively.

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)

Evaluation of Shoreham Nuclear Power Station, Unit 1 technical specifications

International Nuclear Information System (INIS)

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

1985-08-01

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

Eddy Currents Inspection of CANDU Steam Generator Tubes using Zetec's ZR-1 Robot. Experience in Romania

Energy Technology Data Exchange (ETDEWEB)

Scott Hower [Zetec Inc. (Romania); Luiza Vladu; Adrian Nichisov; Mihai Cretu [COMPCONTROL ING. (Romania)

2006-07-01

Full text of publication follows: The commercial operation of Unit 1 of Cernavoda NPP started on 2 December, 1996. The unit's reactor type is PHWR-CANDU 6 (electrical capacity 706 MWe), using natural uranium. The nuclear fuel is manufactured in Romania. The Cernavoda nuclear power plant has four CANDU - design steam generators that have been in service since 1996. The paper introduces the new ZR-1 Robot System for Inspection and Maintenance/Repair from Zetec that combines the newest state-of-the-art robotics technology with Zetec experience - based innovation to address the needs for inspection and repair of steam generators. The multipurpose ZR-1 can be easily installed to perform the necessary eddy current inspection and remain installed ready for follow-up maintenance and repair. It has superior technical performances and a modular three axis motion of arm that enables 100% coverage of tube sheet. Automated, repeatable, and precise positioning of tool heads ensures accurate delivery and reducing costly rework and reduces inspection time by 30%. The modular, light weight, and portable design permits easy assembly and disassembly through small openings and it reduces setup/tear down time by 30%. The first deployment of the new ZR-1 Robot was made in September 2004 at the Cernavoda NPP inspection outage. The unit's reactor type is PHWR-CANDU 6 (electrical capacity 706 MWe), using natural uranium; the nuclear fuel is manufactured in Romania. The Cernavoda nuclear power plant Unit 1 has four CANDU - design steam generators that have been in service since 1996. The paper presents also the Zetec's field experience and customer experience with this system. It describes the equipment setup in Cernavoda's steam generators mock-up, functional tests and calibration. Finally, provides details on the execution of the inspection, options for standardizing the inspection techniques and conclusions. (authors)

75 FR 8757 - Nebraska Public Power District, Cooper Nuclear Station, Unit 1; Notice of Availability of the...

Science.gov (United States)

2010-02-25

..., Cooper Nuclear Station, Unit 1; Notice of Availability of the Draft Supplement 41 to the Generic... Renewal of Cooper Nuclear Station, Unit 1 Notice is hereby given that the U.S. Nuclear Regulatory... operating license DPR-46 for an additional 20 years of operation for Cooper Nuclear Station, Unit 1 (CNS-1...

Primary separator replacement for Bruce Unit 8 steam generators

International Nuclear Information System (INIS)

Roy, S.B.; Mewdell, C.G.; Schneider, W.G.

2000-01-01

During a scheduled maintenance outage of Bruce Unit 8 in 1998, it was discovered that the majority of the original primary steam separators were damaged in two steam generators. The Bruce B steam generators are equipped with GXP type primary cyclone separators of B and W supply. There were localized perforations in the upper part of the separators and large areas of generalized wall thinning. The degradation was indicative of a flow related erosion corrosion mechanism. Although the unit- restart was justified, it was obvious that corrective actions would be necessary because of the number of separators affected and the extent of the degradation. Repair was not considered to be a practical option and it was decided to replace the separators, as required, in Unit 8 steam generators during an advanced scheduled outage. GXP separators were selected for replacement to minimize the impact on steam generator operating characteristics and analysis. The material of construction was upgraded from the original carbon steel to stainless steel to maximize the assurance of full life. The replacement of the separators was a first of a kind operation not only for Ontario Power Generation and B and W but also for all CANDU plants. The paper describes the degradations observed and the assessments, the operating experience, manufacture and installation of the replacement separators. During routine inspection in 1998, many of the primary steam separators in two of steam generators at Bruce Nuclear Division B Unit 8 were observed to have through wall perforations. This paper describes assessment of this condition. It also discusses the manufacture and testing of replacement primary steam separators and the development and execution of the replacement separator installation program. (author)

Particle-borne radionuclides as tracers for sediment in the Susquehanna River and Chesapeake Bay

Energy Technology Data Exchange (ETDEWEB)

Donoghue, J F [Florida State Univ., Tallahassee, FL (USA). Dept. of Geology; Bricker, O P [Geological Survey, Reston, VA (USA). Water Resources Div.; Olsen, C R [Oak Ridge National Lab., TN (USA)

1989-10-01

The Chesapeake Bay receives nearly 1,000,000 tonnes of sediment annually from its major tributary, the Susquehanna River. The pattern of deposition of this sediment affects the lifetime of the estuarine resource and the fate of any sediment-borne contaminants. Previous estimates of the extent to which Susquehanna River sediment is transported down the Chesapeake have differed considerably. By use of reactor-generated radionuclides adsorbed on the river sediment, a sediment budget has been compiled for the upper Chesapeake Bay and the reservoirs on the lower Susquehanna. Reservoirs impound nearly 1,400,000 tonnes of sediment annually behind the power dams on the lower Susquehanna River. Without the dams, sediment delivery to the upper bay would more than double. The uppermost Chesapeake Bay, within and above the turbidity maximum, retains virtually all of the fluvial sediment delivered to it. The result is an annual sedimentation rate of approximately 3 mm yr{sup -1} in the upper bay, an infilling rate that is nearly equal to the regional rate of sea level rise. (author).

Particle-borne radionuclides as tracers for sediment in the Susquehanna River and Chesapeake Bay

International Nuclear Information System (INIS)

Donoghue, J.F.

1989-01-01

The Chesapeake Bay receives nearly 1,000,000 tonnes of sediment annually from its major tributary, the Susquehanna River. The pattern of deposition of this sediment affects the lifetime of the estuarine resource and the fate of any sediment-borne contaminants. Previous estimates of the extent to which Susquehanna River sediment is transported down the Chesapeake have differed considerably. By use of reactor-generated radionuclides adsorbed on the river sediment, a sediment budget has been compiled for the upper Chesapeake Bay and the reservoirs on the lower Susquehanna. Reservoirs impound nearly 1,400,000 tonnes of sediment annually behind the power dams on the lower Susquehanna River. Without the dams, sediment delivery to the upper bay would more than double. The uppermost Chesapeake Bay, within and above the turbidity maximum, retains virtually all of the fluvial sediment delivered to it. The result is an annual sedimentation rate of approximately 3 mm yr -1 in the upper bay, an infilling rate that is nearly equal to the regional rate of sea level rise. (author)

Accurate calibration of steam turbine speed control system and its influence on primary regulation at electric grid

Energy Technology Data Exchange (ETDEWEB)

Irrazabal Bohorquez, Washington Orlando; Barbosa, Joao Roberto [Technological Institute of Aeronautics (ITA/CTA), Sao Jose dos Campos, SP (Brazil). Center for Reference on Gas Turbine and Energy], E-mail: barbosa@ita.br

2010-07-01

In an interconnected electric system there are two very important parameters: the field voltage and the frequency system. The frequency system is very important for the primary regulation of the electric grid. Each turbomachine actuating as generator interconnected to the grid has an automatic speed regulator to keep the rotational speed and mechanical power of the prime machine operating at the set conditions and stable frequency. The electric grid is a dynamical system and in every moment the power units are exposed to several types of disturbances, which cause unbalance of the mechanical power developed by prime machine and the consumed electric power at the grid. The steam turbine speed control system controls the turbine speed to support the electric grid primary frequency at the same time it controls the frequency of the prime machine. Using a mathematical model for the speed control system, the transfer functions were calculated, as well as the proportionality constants of each element of the steam turbine automatic speed regulator. Among other parameters, the droop characteristic of steam turbine and the dynamic characteristics of the automatic speed regulator elements were calculated. Another important result was the determination of the behavior of the speed control when disturbances occur with the improvement of the calibration precision of the control system. (author)

Importance of deposit information in the design and execution of steam generator chemical cleaning

International Nuclear Information System (INIS)

Flores, O.; Remark, J.

1997-01-01

During the planning stages of the chemical cleaning of the San Onofre Nuclear Generating Station (SONGS) units 2 and 3 steam generators, it was determined that an understanding of the steam generator deposit loading and composition was essential to the design and success of the project. It was also determined that qualification testing, preferably with actual deposits from the SONGS steam generators, was also essential. SONGS units 2 and 3 have Combustion Engineering (CE)-designed pressurized water reactors. Each unit has two CE model 3410 steam generators. Each steam generator has 9350 alloy 600 tubes with 1.9-cm (3/4 in.) outside diameter. Unit 2 began commercial operation in 1983, and unit 3, in 1984. The purpose of this technical paper is to explain the effort and methodology for deposit composition, characterization, and quantification. In addition, the deposit qualification testing and design of the cleaning are discussed

Long-term security of electrical and control engineering equipment in nuclear power stations to withstand a loss of coolant accident

International Nuclear Information System (INIS)

Mueller, H.

1996-01-01

Electrical and control engineering equipment, which has to function even after many years of operation in the event of a fault in a saturated steam atmosphere of 160 C maximum, is essential in nuclear power stations in order to control a loss of coolant accident. The nuclear power station operators have, for this purpose, developed verification strategies for groups of components, by means of which it is ensured that the electrical and control engineering components are capable of dealing with a loss of coolant accident even at the end of their planned operating life. (orig.) [de

LMFBR steam generators in the United Kingdom

International Nuclear Information System (INIS)

Anderson, R.; Hayden, O.

2002-01-01

Experience has been gained in the UK on the operation of LMFBR Steam Generator Units (SGU) over a period of 20 years from the Dounreay Fast Reactor (DFR) and the Prototype Fast Reactor (PFR). The DFR steam generator featured a double barrier and therefore did not represent a commercial design. PFR, however, faced the challenge of a single wall design and it is experience from this which is most valuable. The PFR reactor went critical in March 1974 and the plant operating history since then has been dominated by experience with leaks in the tube to tube plate welds of the high performance U-tubes SGU's. Operation at high power using the full complement of three secondary sodium circuits was delayed until July 1976 by the occurrence of leaks in the tube to tube plate welds of the superheater and reheater units which are fabricated in stainless steel. Repairs were carried out to the two superheaters and they were returned to service. The reheater tube bundle was removed from circuit after sodium was found to have entered the steam side. When the sodium had been removed and inspection carried out it was decided not to recover the unit. Since 1976 the remaining five stainless steel units have operated satisfactorily. This year a replacement reheater unit has been installed. This is of a new design in 9-Cr-Mo ferritic steel using a sleeve through which the steam tube passes to eliminate the tube to tube plate weld. Despite a few early leaks in evaporator tube to tube plate welds up to 1979, these failures did not initially present a major problem. However, in 1980 the rate of evaporator weld failures increased and despite the successful application of a shot peening process to eliminate stress corrosion failures from the water side of the weld, failures traced to the sodium side continued. A sleeving process was developed for application to complete evaporator units on a production basis with the objective of bypassing the welds at each end of the 500 tubes. The decision

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

International Nuclear Information System (INIS)

1977-02-01

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

Electric machinery and drives in thermal power stations

International Nuclear Information System (INIS)

1974-01-01

The following subjects were dealt with during the VDE meeting: 1) Requirements made by the electric network on the generators and their excitation equipment, and the influence thereof on their design; 2) requirements made by the power station process on the electric drives and the influence thereof on type and design; 3) requirements made on protective measures from the point of the electric power station machinery. (TK) [de

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

International Nuclear Information System (INIS)

1982-05-01

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

A probabilistic evaluation of temporarily extending the diesel generator limiting condition for operation

International Nuclear Information System (INIS)

Kukielka, C.A.; Detamore, M.B.

1986-01-01

Pennsylvania Power and Light Company is installing a fifth diesel generator at its Susquehanna Steam Electric Station. This new diesel generator will serve as a ''swing'' diesel generator, i.e., perform the function of any of the existing diesel generators. The addition of this diesel generator avoids a dual unit shutdown should a diesel generator outage for maintenance or repair exceed the three day Technical Specification Limiting Condition for Operation (LCO). It is estimated that up to fifteen days per diesel generator will be required to complete the tie-in. In accordance with the existing three day LCO, a dual unit shutdown would then result. To preclude such a shutdown, a one time temporary extension to the three day LCO was requested of the Nuclear Regulatory Commission (NRC). This paper presents a probabilistic evaluation that was used to estimate the increased risk due to extending the LCO to a cumulative sixty days to allow the tie-in of the fifth diesel generator

Improving nuclear generating station response for electrical grid islanding

International Nuclear Information System (INIS)

Chou, Q.B.; Kundur, P.; Acchione, P.N.; Lautsch, B.

1989-01-01

This paper describes problems associated with the performance characteristics of nuclear generating stations which do not have their overall plant control design functions co-ordinated with the other grid controls. The paper presents some design changes to typical nuclear plant controls which result in a significant improvement in both the performance of the grid island and the chances of the nuclear units staying on-line following the disturbance. This paper focuses on four areas of the overall unit controls and turbine governor controls which could be modified to better co-ordinate the control functions of the nuclear units with the electrical grid. Some simulation results are presented to show the performance of a typical electrical grid island containing a nuclear unit with and without the changes

Turbine steam path replacement at the Grafenrheinfeld Nuclear Power Station

International Nuclear Information System (INIS)

Weschenfelder, K.D.; Oeynhausen, H.; Bergmann, D.; Hosbein, P.; Termuehlen, H.

1994-01-01

In the last few years, replacement of old vintage steam turbine flow path components has been well established as a valid approach to improve thermal performance of aged turbines. In nuclear power plants, performance improvement is generally achieved only by design improvements since performance deterioration of old units is minor or nonexistent. With fossil units operating over decades loss in performance is an additional factor which can be taken into account. Such loss of performance can be caused by deposits, solid particle erosion, loss of shaft and inter-stage seal strips, etc. Improvement of performance is typically guaranteed as output increases for operation at full load. This value can be evaluated as a direct gain in unit capacity without fuel or steam supply increase. Since fuel intake does not change, the relative improvement of the net plant heat rate or efficiency is equal to the relative increase in output. The heat rate improvement is achieved not only at full load but for the entire load range. Such heat rate improvement not only moves a plant up on the load dispatch list increasing its capacity factor, but also extensive fuel savings can pay off for the investment cost of new steam path components. Another important factor is that quite often older turbine designs show a deterioration of their reliability and need costly repairs. With new flow path components an aged steam turbine starts a new useful life

Operating experiences with 1 MW steam generator

Energy Technology Data Exchange (ETDEWEB)

Sano, A; Kanamori, A; Tsuchiya, T

1975-07-01

1 MW steam generator, which was planned as the first stage of steam generator development in Power Reactor and Nuclear Fuel Corp. (PNC) in Japan, is a single-unit, once-through, integrated shell and tube type with multi-helical coil tubes. It was completed in Oarai Engineering Center of PNC in March of 1971, and the various performance tests were carried out up to April, 1972. After the dismantle of the steam generator for structural inspection and material test, it was restored with some improvements. In this second 1 MW steam generator, small leak occurred twice during normal operation. After repairing the failure, the same kind of performance tests as the first steam generator were conducted in order to verify the thermal insulation effect of argon gas in downcomer zone from March to June, 1974. In this paper the above operating experiences were presented including the outline of some performance test results. (author)

Life extension and replacement management for RAPS type steam generators

International Nuclear Information System (INIS)

Arya, R.C.; Rastogi, A.K.

1996-01-01

The steam generating equipment in first four units of Indian PHWRs Rajasthan Atomic Power Station (RAPS) 1-2 and Madras Atomic Power Station (MAPS) 1-2 are hairpin type and comprise of eight boiler assemblies. Each assembly consists of identical, single pass, inverted and vertical hairpin heat exchangers (10 for RAPS and 11 for MAPS) containing 195 monel-400 U tubes of 12.7 mm dia x 1.242 mm thick. The hot heavy water flows through these tubes and imparts heat to feed, light demineralized water entering the shell at the bottom of preheat leg. The heat is generated on the outer surface of the tubes. Details of studies carried out for life extension and replacement management for RAPS type steam generators are given. 1 fig., 5 tabs

75 FR 6223 - PSEG Nuclear LLC; Hope Creek Generating Station and Salem Nuclear Generating Station, Unit Nos. 1...

Science.gov (United States)

2010-02-08

... NUCLEAR REGULATORY COMMISSION [Docket Nos. 50-272, 50-311 and 50-354; NRC-2010-0043] PSEG Nuclear LLC; Hope Creek Generating Station and Salem Nuclear Generating Station, Unit Nos. 1 and 2...-70, and DPR-75, issued to PSEG Nuclear LLC (PSEG, the licensee), for operation of the Hope Creek...

1000 MW steam turbine for Temelin nuclear power station

International Nuclear Information System (INIS)

Drahy, J.

1992-01-01

Before the end 1991 the delivery was completed of the main parts (3 low-pressure sections and 1 high-pressure section, all of double-flow design) of the first full-speed (3000 r.p.m.) 1000 MW steam turbine for saturated admission steam for the Temelin nuclear power plant. Description of the turbine design and of new technologies and tools used in the manufacture are given. Basic technical parameters of the steam turbine are as follows: maximum output of steam generators 6060 th -1 ; maximum steam flow into turbine 5494.7 th -1 ; output of turbo-set 1024 MW; steam conditions before the turbine inlet: pressure 5.8 MPa, temperature 273.3 degC, steam wetness 0.5%; nominal temperature of cooling water 21 degC; temperature of feed water 220.8 degC; maximum consumption of heat from turbine for heating at 3-stage heating of heating water 60/150 degC. (Z.S.) 7 figs., 2 refs

Quad-Cities Station, Units 1 and 2. Annual report, 1975

International Nuclear Information System (INIS)

1976-01-01

Net electrical power generated by Unit 1 was 2,246,757 MWh(e) with the generator on line 4,287.5 hrs while Unit 2 generated 1,729,147 MWh(e) with the generator on line 3,056.21 hrs. Information is presented concerning operations, power generation, shutdowns, maintenance, changes, tests, and experiments

Method for heating of the primary circuit of WWER electric power units at cold start-up

International Nuclear Information System (INIS)

Ivanov, I.N.; Dimitrov, B.D.; Korkinova, M.I.

1982-01-01

The method increases the heating rate and shorten the start-up time of the electric power units. It comprises a primary stopping of the reactor core heating and provides a forced circulation of the heat-carrier through the circulation cycles of the primary circuit. The thermal energy is supplied in one or several steam generators in the secondary circuit of an NPP operating unit. 1 cl., 3 figs

Snubber reduction program at the Byron Station, Unit 1

International Nuclear Information System (INIS)

Arterburn, J.; Bakhtiari, S.

1987-01-01

Commonwealth Edison Company's (CECo's) Byron Station, unit 1, was originally designed with approximately 1200 snubbers supporting the plant's large- and small-bore piping systems. This relatively large number of snubbers is attributed to excessive conservatism in nuclear piping codes and regulations effective during the original piping design. A recent pilot program at CECo's LaSalle County Station, a boiling water reactor plant, demonstrated that a 50% or greater reduction in total snubber population is achievable in plants of this design vintage. Based on the successful results of the pilot program, CECo initiated a full scale snubber reduction program at Byron, a pressurized water reactor plant of the same vintage at the LaSalle County Station. The benefits from a reduced snubber population are described. To realize the maximum potential benefits, all snubbers in the plant were prioritized in order of desirability for removal. The priority designations are discussed. The major results from phase 1 of the Byron program are summarized. The NRC inspection of the project addressed a variety of issues and is discussed. The conclusions that can be drawn from the phase 1 program are summarized

Comparison of food habits of white perch (Morone americana) in the heated effluent canal of a steam electric station and in an adjacent river system

International Nuclear Information System (INIS)

Moore, C.J.; Fuller, S.L.H.; Burton, D.T.

1975-01-01

Analysis of the stomach contents of 97 white perch, Morone americana, taken from the effluent canal of a steam electric station (S.E.S.) and 106 white perch from adjacent Patuxent River waters indicated similar food habits from September 1970 through August 1971. However, 35 percent of all white perch taken from the heated effluent canal contained small pieces of coal and cinders, whereas only 3 percent of the river specimens contained such items in their stomachs. Fly ash and coal dust are present on the bottom of the S.E.S. canal, whereas little such material, if any, can be found on the river bottom in the study area. This suggests the canal fish were actively feeding in the heated effluent and not simply moving into the canal after feeding in the river. No significant difference (P greater than 0.05) was found between the average wet weight stomach contents of the river and canal fish within the same month

Electric power generating plant having direct-coupled steam and compressed-air cycles

Science.gov (United States)

Drost, M.K.

1981-01-07

An electric power generating plant is provided with a Compressed Air Energy Storage (CAES) system which is directly coupled to the steam cycle of the generating plant. The CAES system is charged by the steam boiler during off peak hours, and drives a separate generator during peak load hours. The steam boiler load is thereby levelized throughout an operating day.

Electric power generating plant having direct coupled steam and compressed air cycles

Science.gov (United States)

Drost, Monte K.

1982-01-01

An electric power generating plant is provided with a Compressed Air Energy Storage (CAES) system which is directly coupled to the steam cycle of the generating plant. The CAES system is charged by the steam boiler during off peak hours, and drives a separate generator during peak load hours. The steam boiler load is thereby levelized throughout an operating day.

Analysis of steam generator tube sections removed from Gentilly-2 nuclear generating station

International Nuclear Information System (INIS)

Semmler, J.; Lockley, A.J.; Doyon, D.

2010-01-01

deposition rate in the steam generators from 2001 to 2009 were estimated and compared to the estimated values from 1983 (station commissioning) to 2001. This paper presents a summary of steam generator tube characterization results and describes how the data on the oxide deposition rate were correlated to the changes in station operating practices. These data demonstrate the benefits that resulted from recent changes to station chemistry and operational practices. (author)

Electrical system design and reliability at Ontario Hydro nuclear generating stations

Energy Technology Data Exchange (ETDEWEB)

Royce, C. J. [Ontario Hydro, 700 University Avenue, Toronto, Ontario M5G 1X6 (Canada)

1986-02-15

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

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

International Nuclear Information System (INIS)

1977-01-01

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

Peach Bottom Atomic Power Station recirc pipe dose rates with zinc injection and condenser replacement

International Nuclear Information System (INIS)

DiCello, D.C.; Odell, A.D.; Jackson, T.J.

1995-01-01

Peach Bottom Atomic Power Station (PBAPS) is located near the town of Delta, Pennsylvania, on the west bank of the Susquehanna River. It is situated approximately 20 miles south of Lancaster, Pennsylvania. The site contains two boiling water reactors of General Electric design and each rated at 3,293 megawatts thermal. The units are BWR 4s and went commercial in 1977. There is also a decommissioned high temperature gas-cooled reactor on site, Unit 1. PBAPS Unit 2 recirc pipe was replaced in 1985 and Unit 3 recirc pipes replaced in 1988 with 326 NGSS. The Unit 2 replacement pipe was electropolished, and the Unit 3 pipe was electropolished and passivated. The Unit 2 brass condenser was replaced with a Titanium condenser in the first quarter of 1991, and the Unit 3 condenser was replaced in the fourth quarter of 1991. The admiralty brass condensers were the source of natural zinc in both units. Zinc injection was initiated in Unit 2 in May 1991, and in Unit 3 in May 1992. Contact dose rate measurements were made in standard locations on the 28-inch recirc suction and discharge lines to determine the effectiveness of zinc injection and to monitor radiation build-up in the pipe. Additionally, HPGe gamma scans were performed to determine the isotopic composition of the oxide layer inside the pipe. In particular, the specific (μCi/cm 2 ) of Co-60 and Zn-65 were analyzed

Peach Bottom Atomic Power Station recirc pipe dose rates with zinc injection and condenser replacement

Energy Technology Data Exchange (ETDEWEB)

DiCello, D.C.; Odell, A.D.; Jackson, T.J. [PECO Energy Co., Delta, PA (United States)

1995-03-01

Peach Bottom Atomic Power Station (PBAPS) is located near the town of Delta, Pennsylvania, on the west bank of the Susquehanna River. It is situated approximately 20 miles south of Lancaster, Pennsylvania. The site contains two boiling water reactors of General Electric design and each rated at 3,293 megawatts thermal. The units are BWR 4s and went commercial in 1977. There is also a decommissioned high temperature gas-cooled reactor on site, Unit 1. PBAPS Unit 2 recirc pipe was replaced in 1985 and Unit 3 recirc pipes replaced in 1988 with 326 NGSS. The Unit 2 replacement pipe was electropolished, and the Unit 3 pipe was electropolished and passivated. The Unit 2 brass condenser was replaced with a Titanium condenser in the first quarter of 1991, and the Unit 3 condenser was replaced in the fourth quarter of 1991. The admiralty brass condensers were the source of natural zinc in both units. Zinc injection was initiated in Unit 2 in May 1991, and in Unit 3 in May 1992. Contact dose rate measurements were made in standard locations on the 28-inch recirc suction and discharge lines to determine the effectiveness of zinc injection and to monitor radiation build-up in the pipe. Additionally, HPGe gamma scans were performed to determine the isotopic composition of the oxide layer inside the pipe. In particular, the specific ({mu}Ci/cm{sup 2}) of Co-60 and Zn-65 were analyzed.

Darlington steam generator life assurance program

International Nuclear Information System (INIS)

Jelinski, E.; Dymarski, M.; Maruska, C.; Cartar, E.

1995-01-01

The Darlington Nuclear Generating Station belonging to Ontario Hydro is one of the most modern and advanced nuclear generating stations in the world. Four reactor units each generate 881 net MW, enough to provide power to a major city, and representing approximately 20% of the Ontario grid. The nuclear generating capacity in Ontario represents approximately 60% of the grid. In order to look after this major asset, many proactive preventative and predictive maintenance programs are being put in place. The steam generators are a major component in any power plant. World wide experience shows that nuclear steam generators require specialized attention to ensure reliable operation over the station life. This paper describes the Darlington steam generator life assurance program in terms of degradation identification, monitoring and management. The requirements for chemistry control, surveillance of process parameters, surveillance of inspection parameters, and the integration of preventative and predictive maintenance programs such as water lancing, chemical cleaning, RIHT monitoring, and other diagnostics to enhance our understanding of life management issues are identified and discussed. We conclude that we have advanced proactive activities to avoid and to minimize many of the problems affecting other steam generators. An effective steam generator maintenance program must expand the knowledge horizon to understand life limiting processes and to analyze and synthesize observations with theory. (author)

A study on the evaluation of vibration effect and the development of vibration reduction method for Wolsung unit 1 main steam piping

Energy Technology Data Exchange (ETDEWEB)

Lee, Hyun; Kim, Yeon Whan [Korea Electric Power Corp. (KEPCO), Taejon (Korea, Republic of). Research Center; Kim, Tae Ryong; Park, Jin Ho [Korea Atomic Energy Research Inst., Daeduk (Korea, Republic of)

1996-08-01

The main steam piping of nuclear power plant which runs between steam generator and high pressure turbine has been experienced to have a severe effect on the safe operation of the plant due to the vibration induced by the steam flowing inside the piping. The imposed cyclic loads by the vibration could result in the degradation of the related structures such as connection parts between main instruments, valves, pipe supports and building. The objective of the study is to reduce the vibration level of Wolsung nuclear power plant unit 1 main steam pipeline by analyzing vibration characteristics of the piping, identifying sources of the vibration and developing a vibration reduction method .The location of the maximum vibration is piping between the main steam header and steam chest .The stress level was found to be within the allowable limit .The main vibration frequency was found to be 4{approx}6 Hz which is the same as the natural frequency from model test .A vibration reduction method using pipe supports of energy absorbing type(WEAR)is selected .The measured vibration level after WEAR installation was reduced about 36{approx}77% in displacement unit (author). 36 refs., 188 figs.

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

International Nuclear Information System (INIS)

1983-12-01

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

Nuclear process steam for industry

International Nuclear Information System (INIS)

Seddon, W.A.

1981-11-01

A joint industrial survey funded by the Bruce County Council, the Ontario Energy Corporation and Atomic Energy of Canada Limited was carried out with the cooperation of Ontario Hydro and the Ontario Ministry of Industry and Tourism. Its objective was to identify and assess the future needs and interest of energy-intensive industries in an Industrial Energy Park adjacent to the Bruce Nuclear Power Development. The Energy Park would capitalize on the infrastructure of the existing CANDU reactors and Ontario Hydro's proven and unique capability to produce steam, as well as electricity, at a cost currently about half that from a comparable coal-fired station. Four industries with an integrated steam demand of some 1 x 10 6 lb/h were found to be prepared to consider seriously the use of nuclear steam. Their combined plants would involve a capital investment of over $200 million and provide jobs for 350-400 people. The high costs of transportation and the lack of docking facilities were considered to be the major drawbacks of the Bruce location. An indication of steam prices would be required for an over-all economic assessment

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

Science.gov (United States)

2011-04-29

... Service Company, Palo Verde Nuclear Generating Station, Units 1, 2, and 3, Notice of Issuance of Renewed... Company (licensee), the operator of the Palo Verde Nuclear Generating Station, Units 1, 2, and 3 (PVNGS... Plants: Supplement 43, Regarding Palo Verde Nuclear Generating Station,'' issued January 2011, discusses...

Susquehanna River Basin Hydrologic Observing System (SRBHOS)

Science.gov (United States)

Reed, P. M.; Duffy, C. J.; Dressler, K. A.

2004-12-01

In response to the NSF-CUAHSI initiative for a national network of Hydrologic Observatories, we propose to initiate the Susquehanna River Basin Hydrologic Observing System (SRBHOS), as the northeast node. The Susquehanna has a drainage area of 71, 410 km2. From the headwaters near Cooperstown, NY, the river is formed within the glaciated Appalachian Plateau physiographic province, crossing the Valley and Ridge, then the Piedmont, before finishing its' 444 mile journey in the Coastal Plain of the Chesapeake Bay. The Susquehanna is the major source of water and nutrients to the Chesapeake. It has a rich history in resource development (logging, mining, coal, agriculture, urban and heavy industry), with an unusual resilience to environmental degradation, which continues today. The shallow Susquehanna is one of the most flood-ravaged rivers in the US with a decadal regularity of major damage from hurricane floods and rain-on-snow events. As a result of this history, it has an enormous infrastructure for climate, surface water and groundwater monitoring already in place, including the nations only regional groundwater monitoring system for drought detection. Thirty-six research institutions have formed the SRBHOS partnership to collaborate on a basin-wide network design for a new scientific observing system. Researchers at the partner universities have conducted major NSF research projects within the basin, setting the stage and showing the need for a new terrestrial hydrologic observing system. The ultimate goal of SRBHOS is to close water, energy and solute budgets from the boundary layer to the water table, extending across plot, hillslope, watershed, and river basin scales. SRBHOS is organized around an existing network of testbeds (legacy watershed sites) run by the partner universities, and research institutions. The design of the observing system, when complete, will address fundamental science questions within major physiographic regions of the basin. A nested

Composite electric generator equipped with steam generator for heating reactor coolant

International Nuclear Information System (INIS)

Watabe, Masaharu; Soman, Yoshindo; Kawanishi, Kohei; Ota, Masato.

1997-01-01

The present invention concerns a composite electric generator having coolants, as a heating source, of a PWR type reactor or a thermonuclear reactor. An electric generator driving gas turbine is disposed, and a superheater using a high temperature exhaust gas of the gas turbine as a heating source is disposed, and main steams are superheated by the superheater to elevate the temperature at the inlet of the turbine. This can increase the electric generation capacity as well as increase the electric generation efficiency. In addition, since the humidity in the vicinity of the exit of the steam turbine is reduced, occurrence of loss and erosion can be suppressed. When cooling water of the thermonuclear reactor is used, the electric power generated by the electric generator driven by the gas turbine can be used upon start of the thermonuclear reactor, and it is not necessary to dispose a large scaled special power source in the vicinity, which is efficient. (N.H.)

Energy Conversion Alternatives Study (ECAS), Westinghouse phase 1. Volume 5: Combined gas-steam turbine cycles. [energy conversion efficiency in electric power plants

Science.gov (United States)

Amos, D. J.; Foster-Pegg, R. W.; Lee, R. M.

1976-01-01

The energy conversion efficiency of gas-steam turbine cycles was investigated for selected combined cycle power plants. Results indicate that it is possible for combined cycle gas-steam turbine power plants to have efficiencies several point higher than conventional steam plants. Induction of low pressure steam into the steam turbine is shown to improve the plant efficiency. Post firing of the boiler of a high temperature combined cycle plant is found to increase net power but to worsen efficiency. A gas turbine pressure ratio of 12 to 1 was found to be close to optimum at all gas turbine inlet temperatures that were studied. The coal using combined cycle plant with an integrated low-Btu gasifier was calculated to have a plant efficiency of 43.6%, a capitalization of $497/kW, and a cost of electricity of 6.75 mills/MJ (24.3 mills/kwh). This combined cycle plant should be considered for base load power generation.

Capturing interactions between nitrogen and hydrological cycles under historical climate and land use: Susquehanna watershed analysis with the GFDL land model LM3-TAN

Science.gov (United States)

Lee, M.; Malyshev, S.; Shevliakova, E.; Milly, Paul C. D.; Jaffé, P. R.

2014-01-01

We developed a process model LM3-TAN to assess the combined effects of direct human influences and climate change on terrestrial and aquatic nitrogen (TAN) cycling. The model was developed by expanding NOAA's Geophysical Fluid Dynamics Laboratory land model LM3V-N of coupled terrestrial carbon and nitrogen (C-N) cycling and including new N cycling processes and inputs such as a soil denitrification, point N sources to streams (i.e., sewage), and stream transport and microbial processes. Because the model integrates ecological, hydrological, and biogeochemical processes, it captures key controls of the transport and fate of N in the vegetation–soil–river system in a comprehensive and consistent framework which is responsive to climatic variations and land-use changes. We applied the model at 1/8° resolution for a study of the Susquehanna River Basin. We simulated with LM3-TAN stream dissolved organic-N, ammonium-N, and nitrate-N loads throughout the river network, and we evaluated the modeled loads for 1986–2005 using data from 16 monitoring stations as well as a reported budget for the entire basin. By accounting for interannual hydrologic variability, the model was able to capture interannual variations of stream N loadings. While the model was calibrated with the stream N loads only at the last downstream Susquehanna River Basin Commission station Marietta (40°02' N, 76°32' W), it captured the N loads well at multiple locations within the basin with different climate regimes, land-use types, and associated N sources and transformations in the sub-basins. Furthermore, the calculated and previously reported N budgets agreed well at the level of the whole Susquehanna watershed. Here we illustrate how point and non-point N sources contributing to the various ecosystems are stored, lost, and exported via the river. Local analysis of six sub-basins showed combined effects of land use and climate on soil denitrification rates, with the highest rates in the

Mathematical modeling of control system for the experimental steam generator

Science.gov (United States)

Podlasek, Szymon; Lalik, Krzysztof; Filipowicz, Mariusz; Sornek, Krzysztof; Kupski, Robert; Raś, Anita

2016-03-01

A steam generator is an essential unit of each cogeneration system using steam machines. Currently one of the cheapest ways of the steam generation can be application of old steam generators came from army surplus store. They have relatively simple construction and in case of not so exploited units - quite good general conditions, and functionality of mechanical components. By contrast, electrical components and control systems (mostly based on relay automatics) are definitely obsolete. It is not possible to use such units with cooperation of steam bus or with steam engines. In particular, there is no possibility for automatically adjustment of the pressure and the temperature of the generated steam supplying steam engines. Such adjustment is necessary in case of variation of a generator load. The paper is devoted to description of improvement of an exemplary unit together with construction of the measurement-control system based on a PLC. The aim was to enable for communication between the steam generator and controllers of the steam bus and steam engines in order to construction of a complete, fully autonomic and maintenance-free microcogeneration system.

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

International Nuclear Information System (INIS)

1990-03-01

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

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

Science.gov (United States)

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

1989-01-01

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

The Japanese and Italian power station markets: prospects for steam coal

Energy Technology Data Exchange (ETDEWEB)

Thomas, S D

1989-02-01

The world market for steam coal seems likely to fall far short of the expectations of 1980. Two markets which appeared to offer considerable scope for expansion, the Italian and Japanese power station markets, are examined and the factors behind their disappointing performance analysed. The reasons behind the lack of investments in new power stations differ. Difficulties in obtaining sites and financial problems are most important in Italy, whilst environmental restrictions and the attractions of competing technologies dominate in Japan. It is concluded that these factors will not weaken significantly in the next decade and coal's prospects in these two markets are correspondingly restricted. 20 refs., 20 tabs.

Steam supply and power cogeneration at Yanshan Petrochemical Co., Ltd.

Energy Technology Data Exchange (ETDEWEB)

NONE

2000-03-01

For the purpose of reducing greenhouse effect gas emissions, a project was studied for the improvement of cogeneration facilities with steam supply of 600t/h and electric output of 55MW at Beijing Yanshan Petrochemical Co., China. In Plan A, fuel is changed from heavy oil to natural gas, and two heavy oil boilers are replaced with two gas turbines and two exhaust heat recovery steam generators for steam supply of 241t/h per unit and electric output of 136.9MW per unit. In Plan B, the boilers are replaced with three gas turbines and three exhaust heat recovery steam generators for steam supply of 210t/h per unit and electric output of 79.5MW per unit. The initial investment is 700 million yuan {+-} 100 million yuan in Plan A, and 500 million yuan {+-} 100 million yuan in Plan B. The generating cost is 0.403 yuan/kWh in Plan A, and 0.455 yuan/kWh in Plan B. It was concluded that without Plan A, the project will not be economically successful. In Plan A, the energy conservation will be 887,847 toe/y heavy oil equivalent, which increases productivity. Further, the amount of greenhouse effect gas emissions will be 2,747,187 t-CO2/y. (NEDO)

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

International Nuclear Information System (INIS)

Ueyama, Koreyasu

1982-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

Ueyama, Koreyasu [Tokyo Electric Power Co., Inc. (Japan)

1982-09-01

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

Quad Cities Unit 2 Main Steam Line Acoustic Source Identification and Load Reduction

International Nuclear Information System (INIS)

DeBoo, Guy; Ramsden, Kevin; Gesior, Roman

2006-01-01

The Quad Cities Units 1 and 2 have a history of steam line vibration issues. The implementation of an Extended Power Up-rate resulted in significant increases in steam line vibration as well as acoustic loading of the steam dryers, which led to equipment failures and fatigue cracking of the dryers. This paper discusses the results of extensive data collection on the Quad Cities Unit 2 replacement dryer and the Main Steam Lines. This data was taken with the intent of identifying acoustic sources in the steam system. Review of the data confirmed that vortex shedding coupled column resonance in the relief and safety valve stub pipes were the principal sources of large magnitude acoustic loads in the main steam system. Modifications were developed in sub-scale testing to alter the acoustic properties of the valve standpipes and add acoustic damping to the system. The modifications developed and installed consisted of acoustic side branches that were attached to the Electromatic Relief Valve (ERV) and Main Steam Safety Valve (MSSV) attachment pipes. Subsequent post-modification testing was performed in plant to confirm the effectiveness of the modifications. The modifications have been demonstrated to reduce vibration loads at full Extended Power Up-rate (EPU) conditions to levels below those at Original Licensed Thermal Power (OLTP). (authors)

76 FR 3517 - Standards of Performance for Fossil-Fuel-Fired, Electric Utility, Industrial-Commercial...

Science.gov (United States)

2011-01-20

... Standards of Performance for Fossil-Fuel-Fired, Electric Utility, Industrial-Commercial-Institutional, and... following: Category NAICS \\1\\ Examples of regulated entities Industry 221112 Fossil fuel-fired electric utility steam generating units. Federal Government 22112 Fossil fuel-fired electric utility steam...

Steam generator life cycle management: Ontario Power Generation (OPG) experience

International Nuclear Information System (INIS)

Maruska, C.C.

2002-01-01

A systematic managed process for steam generators has been implemented at Ontario Power Generation (OPG) nuclear stations for the past several years. One of the key requirements of this managed process is to have in place long range Steam Generator Life Cycle Management (SG LCM) plans for each unit. The primary goal of these plans is to maximize the value of the nuclear facility through safe and reliable steam generator operation over the expected life of the units. The SG LCM plans integrate and schedule all steam generator actions such as inspection, operation, maintenance, modifications, repairs, assessments, R and D, performance monitoring and feedback. This paper discusses OPG steam generator life cycle management experience to date, including successes, failures and how lessons learned have been re-applied. The discussion includes relevant examples from each of the operating stations: Pickering B and Darlington. It also includes some of the experience and lessons learned from the activities carried out to refurbish the steam generators at Pickering A after several years in long term lay-up. The paper is structured along the various degradation modes that have been observed to date at these sites, including monitoring and mitigating actions taken and future plans. (author)

75 FR 43571 - Duke Energy Carolinas, LLC; Catawba Nuclear Station, Units 1 and 2; Environmental Assessment And...

Science.gov (United States)

2010-07-26

... NUCLEAR REGULATORY COMMISSION [Docket Nos. 50-413 and 50-414; NRC-2010-0260] Duke Energy Carolinas, LLC; Catawba Nuclear Station, Units 1 and 2; Environmental Assessment And Finding of No Significant... Energy Carolinas, LLC (the licensee), for operation of the Catawba Nuclear Station, Units 1 and 2...

Retrofit flue gas desulfurization system at Indianapolis Power and Light Co. Petersburg Station Units 1 and 2

International Nuclear Information System (INIS)

Watson, W.K.; Wolsiffer, S.R.; Youmans, J.; Martin, J.E.; Wedig, C.P.

1992-01-01

This paper briefly describes the status of the retrofit wet limestone flue gas desulfurization system (FGDS) project at Indianapolis Power and Light Company (IPL), Petersburg Units 1 and 2. This project was initiated by IPL in response to the Clean Air Act of 1990 and is intended to treat the flue gas from two base load units with a combined capacity of approximately 700 MW gross electrical output. IPL is the owner and operator of the Petersburg Station located in southwestern Indiana. Stone and Webster Engineering Corporation (Stone and Webster) is the Engineer and Constructor for the project. Radian Corporation is a subcontractor to Stone and Webster in the area of flue gas desulfurization (FGD) process. General Electric Environmental Systems, Inc. (GEESI) is the supplier of the FGDS. The project is organized as a team with each company providing services. The supplier of the new stack is scheduled to be selected and join the team in early 1992. Other material suppliers and field contractors will be selected in 1992

Mechanical problems in turbomachines, steam and gas turbines. Large steam turbine manufacturing requirements to fulfill customer needs for electric power

International Nuclear Information System (INIS)

Brazzini, R.

1975-01-01

The needs of the customers in large steam turbines for electric power are examined. The choices and decisions made by the utility about the equipments are dealt with after considering the evolution of power demand on the French network. These decisions and choices mainly result from a technical and economic optimization of production equipments: choice of field-proven solutions, trend to lower steam characteristics, trend to higher output of the units (i.e. size effect), spreading out standardization of machines and components (policy of technical as well as technological levels, i.e. mass production effect). Standardization of external characteristics of units of same level of output and even standardization of some main components. The requirements turbine manufacturers have to meet may fall in two categories: on one side: gaining experience and know-how, capability of making high quality experiments, out put capacity, will to hold a high efficiency level; on the other side: meeting the technical requirements related to the contracts. Among these requirements, one can differentiate those dealing with the service expected from the turbine and that resulting in the responsibility limits of the manufacturer and those tending to gain interchangeability, to improve availability of the equipment, to increase safety, and to make operation and maintenance easier [fr

Studies and solutions of steam turbines for nuclear heating power stations

International Nuclear Information System (INIS)

Drahy, J.

1979-01-01

The possibilities of combined generation of heat and electric power and special features of the corresponding equipment for WWER type reactors are considered. Condensing steam turbines with bled steam points and the constructional solution of bled points are presented for heating the network water to 110 0 C, 120 0 C, and 160 0 C, respectively. The dimensions of the low pressure final stage of the turbine are given. Problems concerning condensing and bleeding turbines and combination types of back-pressure and condensing turbines as well as solutions to the design of 250 MW and 500 MW turbines are discussed

78 FR 41907 - Effluent Limitations Guidelines and Standards for the Steam Electric Power Generating Point...

Science.gov (United States)

2013-07-12

... ENVIRONMENTAL PROTECTION AGENCY 40 CFR Part 423 [EPA-HQ-OW-2009-0819. FRL-9832-7; EPA-HQ-RCRA-2013-0209] RIN 2040-AF14 Effluent Limitations Guidelines and Standards for the Steam Electric Power... proposed rule entitled, ``Effluent Limitations Guidelines and Standards for the Steam Electric Power...

Development, implementation and operational experience with 900 mm R1T pocket-type bearings at Oskarshamn unit 3 nuclear steam turbine generator

International Nuclear Information System (INIS)

Peel, P.; Roos, A.

2015-01-01

The Oskarshamn unit 3 nuclear steam turbine generator in Sweden is operated by OKG and, following the extensive PULS upgrade project, delivers an increased rated output of 1450 MW making it the most powerful BWR unit worldwide. Several turbine bearing incidents occurred in 2009 and 2010, which initiated a detailed root cause analysis to determine the reasons and propose appropriate mitigation measures to ensure reliable unit operation. Together with OKG, ALSTOM Power implemented a short-term solution to operate the unit over the winter period of 2010-11. Subsequently, during the annual outage in June 2011, a permanent solution involving a R1T pocket-type bearing design was installed at three shaft-line positions. Since the 1980's, R1T bearings with diameters from 250 to 670 mm have been operating in numerous full-speed (3000/3600 rpm) steam turbine generators. However, this was the first application of a R1T bearing developed at a diameter of 900 mm and for half-speed operation. This paper presents an overview of the bearing development and details the successful operational feedback gathered to date on the three installed bearings. In comparison with the three tilting pad bearing design, which has typically been used on large half-speed ALSTOM Power steam turbine generators to date, it confirms the R1T bearing design as a viable alternative. (authors)

Trouble found during regular inspection of No.3 plant in Mihama Power Station, Kansai Electric Power Co., Inc

International Nuclear Information System (INIS)

1990-01-01

No.3 plant in Mihama Power Station, Kansai Electric Power Co., Inc. is a PWR type plant with the rated output of 826 MWe. Its regular inspection has been carried out since September 11, 1989, and eddy current flaw detection inspection was carried out on the total number of steam generator heating tubes (9997 tubes except already plugged tubes). As the result, significant indication was observed in 24 tubes in the expanded parts in tube plates, and in 36 tubes at the boundary of the expanded parts (all on high temperature side), in total in 60 tubes. Consequently, it was decided to plug these 60 defective heating tubes. The heating tubes are those made of Inconel 600, having 22.2 mm outside diameter and 1.27 mm wall thickness. The total number of heating tubes in 10164 (3388 tubes x 3 steam generators), the number of plugged tubes is 227, and the ratio of plugging is 2.2 %. (K.I.)

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

International Nuclear Information System (INIS)

1975-01-01

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

Motor-pump unit provided with a lifting appliance of the motor

International Nuclear Information System (INIS)

Veronesi, Luciano; Francis, W.R.

1978-01-01

This invention relates to lifting appliances and particularly concerns a 'pump and motor set' or motor-pump unit fitted with a lifting appliance enabling the motor to be separated from the pump. In nuclear power stations the reactor discharges heat that is carried by the coolant to a distant point away from the reactor to generate steam and electricity conventionally. In order to cause the reactor coolant to flow through the system, coolant motor-pump units are provided in the cooling system. These units are generally of the vertical type with an electric motor fitted vertically on the pump by means of a cylindrical or conical structure called motor support [fr

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)

Evolutionary growth for Space Station Freedom electrical power system

Science.gov (United States)

Marshall, Matthew Fisk; Mclallin, Kerry; Zernic, Mike

1989-01-01

Over an operational lifetime of at least 30 yr, Space Station Freedom will encounter increased Space Station user requirements and advancing technologies. The Space Station electrical power system is designed with the flexibility to accommodate these emerging technologies and expert systems and is being designed with the necessary software hooks and hardware scars to accommodate increased growth demand. The electrical power system is planned to grow from the initial 75 kW up to 300 kW. The Phase 1 station will utilize photovoltaic arrays to produce the electrical power; however, for growth to 300 kW, solar dynamic power modules will be utilized. Pairs of 25 kW solar dynamic power modules will be added to the station to reach the power growth level. The addition of solar dynamic power in the growth phase places constraints in the initial Space Station systems such as guidance, navigation, and control, external thermal, truss structural stiffness, computational capabilities and storage, which must be planned-in, in order to facilitate the addition of the solar dynamic modules.

Electric utility engineer`s FGD manual -- Volume 1: FGD process design. Final report

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-03-04

Part 1 of the Electric Utility Engineer`s Flue Gas Desulfurization (FGD) Manual emphasizes the chemical and physical processes that form the basis for design and operation of lime- and limestone-based FGD systems applied to coal- or oil-fired steam electric generating stations. The objectives of Part 1 are: to provide a description of the chemical and physical design basis for lime- and limestone-based wet FGD systems; to identify and discuss the various process design parameters and process options that must be considered in developing a specification for a new FGD system; and to provide utility engineers with process knowledge useful for operating and optimizing a lime- or limestone-based wet FGD system.

Process for improving the load factor of an electricity generating power station

International Nuclear Information System (INIS)

Rostaing, Michel.

1974-01-01

A description is given of a process for improving the load factor of an electricity generating power station feeding a supply network in which all or part of the power not required by the network during off-peak hours is used for producing hydrogen which is then stored. The stored hydrogen is then burned and the heat generated is employed for superheating the steam generated by the nuclear reactor of the power plant. This combustion is carried out permanently. The hydrogen is produced by water electrolysis. The oxygen also produced in this manner is used as a comburent in the combustion of the hydrogen. The reactor is of the pressurized water type [fr

Mathematical modeling of control system for the experimental steam generator

Directory of Open Access Journals (Sweden)

Podlasek Szymon

2016-01-01

Full Text Available A steam generator is an essential unit of each cogeneration system using steam machines. Currently one of the cheapest ways of the steam generation can be application of old steam generators came from army surplus store. They have relatively simple construction and in case of not so exploited units – quite good general conditions, and functionality of mechanical components. By contrast, electrical components and control systems (mostly based on relay automatics are definitely obsolete. It is not possible to use such units with cooperation of steam bus or with steam engines. In particular, there is no possibility for automatically adjustment of the pressure and the temperature of the generated steam supplying steam engines. Such adjustment is necessary in case of variation of a generator load. The paper is devoted to description of improvement of an exemplary unit together with construction of the measurement-control system based on a PLC. The aim was to enable for communication between the steam generator and controllers of the steam bus and steam engines in order to construction of a complete, fully autonomic and maintenance-free microcogeneration system.

Steam turbines for the future

International Nuclear Information System (INIS)

Trassl, W.

1988-01-01

Approximately 75% of the electrical energy produced in the world is generated in power plants with steam turbines (fossil and nuclear). Although gas turbines are increasingly applied in combined cycle power plants, not much will change in this matter in the future. As far as the steam parameters and the maximum unit output are concerned, a certain consolidation was noted during the past decades. The standard of development and mathematical penetration of the various steam turbine components is very high today and is applied in the entire field: For saturated steam turbines in nuclear power plants and for steam turbines without reheat, with reheat and with double reheat in fossil-fired power plants and for steam turbines with and without reheat in combined cycle power plants. (orig.) [de

Kajian Efisiensi Termal Dari Boiler Di Pembangkit Listrik Tenaga Uap Amurang Unit 1

OpenAIRE

Kurniawan, Hanzen Yauri; Gunawan, Hardi; Maluegha, Benny

2015-01-01

Indonesia has a considerably high potential resources that can be harnessed to generate electricity through power plants. At Amurang Steam Power Plant (PLTU Amurang), coal is used for the fuel and boiler is the equipment to burn the coal producing heat. Boiler is one of the equipments in the thermodynamics cycle which aims to turn the water into steam. This study was conducted to determine the thermal efficiency of the boiler in PLTU Amurang Unit 1 based on operational data. The data collecte...

Experiences of operation for Ikata Nuclear Power Station

International Nuclear Information System (INIS)

Kashimoto, Shigeyuki

1979-01-01

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

Economic analysis of process steam and electricity generation by a 200 MW NHR

International Nuclear Information System (INIS)

Tian Li; Wang Yongqing

2000-01-01

New applications for low temperature nuclear heating reactors should be developed using economic analysis. This paper compares and analyzes the economics of the generation 1.5 MPa process steam and electricity by a 200 MW nuclear heating reactor (NHR-200) for industrial development. The project is very attractive economically with an internal rate of return of 19.61%, a net present worth (discount rate 10%) of 765 million yuan RMB and a capital recovery or payback period of about 5 years after construction is completed. Compared with only using the NHR-200 for in winter heating, the economic of process steam and electricity generation by NHR-200 are much better. In addition, the NHR-200 will significantly improve environmental pollution in cities and reduce the transport of coal from north to south in China

Assessment of Extremely Low Frequency (ELF Electric and Magnetic Fields in Hamedan High Electrical Power Stations and their Effects on Workers

Directory of Open Access Journals (Sweden)

Farshid Ghorbani Shahna

2011-09-01

Full Text Available Introduction: Public and occupational exposure to extremely low frequency (ELF electric and magnetic fields induced by electrical equipment is a significant issue in the environment and at the workplace due to their potential health effects on public health. The purpose of this study was assessment of the electric and magnetic fields intensities and determination of mental and psychological effects of occupational exposure in the high voltage electric power stations in the city of Hamadan, Iran. Material and Methods: The intensities of the magnetic and electric fields were measured at eight high voltage electric power stations at three different intervals of sources using an HI-3604 instrument. A two-part questionnaire was used to assess mental and psychological effects of the exposure to these fields. Two groups of control and case workers including 30 samples were selected to determine the exposure effects. Results: The results of field measurements showed the highest average electric field intensity was related to the CVT unit with 3110 V/m at a 2 m distance from the source and the lowest average was related to the control room with 1.35 V/m next to the source. Also, the highest and lowest magnetic field intensities were close to the transformator 2 and the battery room (50.42 and 1.31 mG, respectively. Discussion and Conclusion: The intensities of electric and magnetic fields in the selected stations are lower than the ACGIH and ICNIRP standard levels for occupational exposures. The results obtained indicate that the distribution of these fields was nonlinear around the sources and the effects observed on exposed workers were non-thermal.

1000 MW steam turbine for nuclear power station

International Nuclear Information System (INIS)

Drahy, J.

1987-01-01

Skoda Works started the manufacture of the 1000 MW steam turbine for the Temelin nuclear power plant. The turbine will use saturated steam at 3,000 r.p.m. It will allow steam supply to heat water for district heating, this of an output of 893 MW for a three-stage water heating at a temperature of 150/60 degC or of 570 MW for a two-stage heating at a temperature of 120/60 degC. The turbine features one high-pressure and three identical low-pressure stages. The pressure gradient between the high-pressure and the low-pressure parts was optimized as concerns the thermal efficiency of the cycle and the thermodynamic efficiency of the low-pressure part. A value of 0.79 MPa was selected corresponding to the maximum flow rate of the steam entering the turbine. This is 5,495 t/h, the admission steam parameters are 273.3 degC and 5.8 MPa. The feed water temperature is 220.9 degC. It is expected that throughout the life of the turbine, there will be 300 cold starts, 1,000 starts following shutdown for 55 to 88 hours, and 600 starts following shutdown for 8 hours. (Z.M.). 8 figs., 1 ref

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

Science.gov (United States)

2011-11-21

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

Outline of Noto Nuclear Power Station, Hokuriku Electric Power Co., Inc

International Nuclear Information System (INIS)

1988-01-01

The location of the power station is in Shiga-cho, Hakui-gun, Ishikawa-ken. One BWR of about 1,600 MWt (540 MWe) capacity is installed. The area of the site is about 1.6 million m 2 , which is on the gentle slope of hilly land at the elevation of about 50 m, and faces Japan Sea. The nuclear reactor proper is installed at the position about 400 m eastward from the coastline. The height of the exhaust stack is about 100 m above the ground. The shortest distance from the center of the reactor core to the boundary of the site is about 450 m in the direction of south and southwest. The objective of use in commercial electric power generation. The start of operation is scheduled in March, 1993. The total cost of construction is about 235 billion yen, which is equivalent to about 435,000 yen-kW. The fuel assemblies are 8 x 8 type, the fuel material is uranium dioxide sintered pellets, and the average degree of enrichment of the initially charged fuel is about 1.6 wt.% in type 1, 2.4 wt.% in type 2 and 3.0 wt.% in type 3 (about 2.3 wt.% on the average). The highest burnup of fuel assemblies is 40,000 MWd-t. The total amount of fuel charged in the core is about 64 t of uranium. The main steam temperature at the reactor exit is 286 deg C, and the feedwater pressure at the reactor entrance is 72 kg-cm 2 g. The steam turbine is a tandem four-flow exhaust condensing turbine of 540 MW output. (Kako, I.)

Assessment of the once-through cooling alternative for central steam-electric generating stations

Energy Technology Data Exchange (ETDEWEB)

Paddock, R. A.; Ditmars, J. D.

1978-12-01

The efficacy of the disposal of waste heat from steam-electric power generation by means of once-through cooling systems was examined in the context of the physical aspects of water quality standards and guidelines for thermal discharges. Typical thermal standards for each of the four classes of water bodies (rivers, lakes, estuaries, and coastal waters) were identified. The mixing and dilution characteristics of various discharge modes ranging from simple, shoreline surface discharges to long, submerged multiport diffusers were examined in terms of the results of prototype measurements, analytical model predictions, and physical model studies. General guidelines were produced that indicate, for a given plant capacity, a given type of receiving water body, and a given discharge mode, the likelihood that once-through cooling can be effected within the restrictions of typical thermal standards. In general, it was found that shoreline surface discharges would not be adequate for large power plants (greater than or equal to 500 MW) at estuarine and marine coastal sites, would be marginally adequate at lake sites, and would be acceptable only at river sites with large currents and river discharges. Submerged multiport diffusers were found to provide the greatest likelihood of meeting thermal standards in all receiving water environments.

Assessment of the once-through cooling alternative for central steam-electric generating stations

International Nuclear Information System (INIS)

Paddock, R.A.; Ditmars, J.D.

1978-12-01

The efficacy of the disposal of waste heat from steam-electric power generation by means of once-through cooling systems was examined in the context of the physical aspects of water quality standards and guidelines for thermal discharges. Typical thermal standards for each of the four classes of water bodies (rivers, lakes, estuaries, and coastal waters) were identified. The mixing and dilution characteristics of various discharge modes ranging from simple, shoreline surface discharges to long, submerged multiport diffusers were examined in terms of the results of prototype measurements, analytical model predictions, and physical model studies. General guidelines were produced that indicate, for a given plant capacity, a given type of receiving water body, and a given discharge mode, the likelihood that once-through cooling can be effected within the restrictions of typical thermal standards. In general, it was found that shoreline surface discharges would not be adequate for large power plants (greater than or equal to 500 MW) at estuarine and marine coastal sites, would be marginally adequate at lake sites, and would be acceptable only at river sites with large currents and river discharges. Submerged multiport diffusers were found to provide the greatest likelihood of meeting thermal standards in all receiving water environments

Flood-inundation maps for the Susquehanna River near Harrisburg, Pennsylvania, 2013

Science.gov (United States)

Roland, Mark A.; Underwood, Stacey M.; Thomas, Craig M.; Miller, Jason F.; Pratt, Benjamin A.; Hogan, Laurie G.; Wnek, Patricia A.

2014-01-01

A series of 28 digital flood-inundation maps was developed for an approximate 25-mile reach of the Susquehanna River in the vicinity of Harrisburg, Pennsylvania. The study was selected by the U.S. Army Corps of Engineers (USACE) national Silver Jackets program, which supports interagency teams at the state level to coordinate and collaborate on flood-risk management. This study to produce flood-inundation maps was the result of a collaborative effort between the USACE, National Weather Service (NWS), Susquehanna River Basin Commission (SRBC), The Harrisburg Authority, and the U.S. Geological Survey (USGS). These maps are accessible through Web-mapping applications associated with the NWS, SRBC, and USGS. The maps can be used in conjunction with the real-time stage data from the USGS streamgage 01570500, Susquehanna River at Harrisburg, Pa., and NWS flood-stage forecasts to help guide the general public in taking individual safety precautions and will provide local municipal officials with a tool to efficiently manage emergency flood operations and flood mitigation efforts. The maps were developed using the USACE HEC–RAS and HEC–GeoRAS programs to compute water-surface profiles and to delineate estimated flood-inundation areas for selected stream stages. The maps show estimated flood-inundation areas overlaid on high-resolution, georeferenced, aerial photographs of the study area for stream stages at 1-foot intervals between 11 feet and 37 feet (which include NWS flood categories Action, Flood, Moderate, and Major) and the June 24, 1972, peak-of-record flood event at a stage of 33.27 feet at the Susquehanna River at Harrisburg, Pa., streamgage.

Type test of Class 1E electric cables, field splices, and connections for nuclear power generating stations - 1975

International Nuclear Information System (INIS)

Anon.

1976-01-01

This Standard provides direction for establishing type tests which may be used in qualifying Class 1E electric cables, field splices, and other connections for service in nuclear power generating stations. General guidelines for qualifications are given in IEEE Std 323-1974, Standard for Qualifying Class 1E Electric Equipment for Nuclear Power Generating Stations. Categories of cables covered are those used for power control and instrumentation services. Though intended primarily to pertain to cable for field installation, this guide may also be used for the qualification of internal wiring of manufactured devices

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

International Nuclear Information System (INIS)

1984-10-01

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

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

International Nuclear Information System (INIS)

1984-07-01

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

75 FR 43572 - Duke Energy Carolinas, LLC, McGuire Nuclear Station, Units 1 and 2; Environmental Assessment and...

Science.gov (United States)

2010-07-26

... NUCLEAR REGULATORY COMMISSION [Docket Nos. 50-369 and 50-370; NRC-2010-0259] Duke Energy Carolinas, LLC, McGuire Nuclear Station, Units 1 and 2; Environmental Assessment and Finding of No Significant... Energy Carolinas, LLC (the licensee), for operation of the McGuire Nuclear Station, Units 1 and 2...

Steam generator tube integrity requirements and operating experience in the United States

International Nuclear Information System (INIS)

Karwoski, K.J.

2009-01-01

Steam generator tube integrity is important to the safe operation of pressurized-water reactors. For ensuring tube integrity, the U.S. Nuclear Regulatory Commission uses a regulatory framework that is largely performance based. This performance-based framework is supplemented with some prescriptive requirements. The framework recognizes that there are three combinations of tube materials and heat treatments currently used in the United States and that the operating experience depends, in part, on the type of material used. This paper summarizes the regulatory framework for ensuring steam generator tube integrity, it highlights the current status of steam generators, and it highlights some of the steam generator issues and challenges that exist in the United States. (author)

The System of Fast Charging Station for Electric Vehicles with Minimal Impact on the Electrical Grid

Directory of Open Access Journals (Sweden)

Petr Chlebis

2016-01-01

Full Text Available The searching and utilization of new energy sources and technologies is a current trend. The effort to increase the share of electricity production from renewable energy sources is characteristic for economically developed countries. The use of accumulation of electrical energy with a large number of decentralized storage units is most preferred, as well as the focus on the production of energy at the point of its consumption. Modern cogeneration units are a good example. This paper describes the accumulation of electrical energy for equalizing the power balance of electric charging stations with high instantaneous power. The possibility of re-utilization of electrical energy from the charged vehicle in the case of lack of electricity in the power grid is solved at the same time. This paper also deals with the selection of appropriate concept of accumulation system and its cooperation with both renewable and distribution networks. Details of the main power components including the results obtained from the system implementation are also described in this paper.

CDIO – The steam engine powering the electric grid

DEFF Research Database (Denmark)

Træholt, Chresten; Holbøll, Joachim; Thomsen, Ole Cornelius

2011-01-01

In building the new DTU B.Eng programme [1] one of the pilots on the 4’th semester is the Design-build project course in Electric Energy Systems. In this course, which is the last Designbuild course many of the CDIO Syllabus bullets [2] are addressed starting with problem identification and formu......In building the new DTU B.Eng programme [1] one of the pilots on the 4’th semester is the Design-build project course in Electric Energy Systems. In this course, which is the last Designbuild course many of the CDIO Syllabus bullets [2] are addressed starting with problem identification...... and formulation, experimental inquiry and modelling, finally leading to planning and solution. The goal is to acquire the skills that are needed for an engineer within electric power engineering to analyse a given task, define the necessary steps to solve the task, organize him/her self and others and finally...... solve the task with success. The concrete work is built up around a miniaturized electric energy system powered by a steam engine. The system mimics an essential sub-section of a real electric power system. The process is realised with a combination of optional lectures, optional exercises, 3 set...

Dynamic underground stripping: steam and electric heating for in situ decontamination of soils and groundwater

Science.gov (United States)

Daily, William D.; Ramirez, Abelardo L.; Newmark, Robin L.; Udell, Kent; Buetnner, Harley M.; Aines, Roger D.

1995-01-01

A dynamic underground stripping process removes localized underground volatile organic compounds from heterogeneous soils and rock in a relatively short time. This method uses steam injection and electrical resistance heating to heat the contaminated underground area to increase the vapor pressure of the contaminants, thus speeding the process of contaminant removal and making the removal more complete. The injected steam passes through the more permeable sediments, distilling the organic contaminants, which are pumped to the surface. Large electrical currents are also applied to the contaminated area, which heat the impermeable subsurface layers that the steam has not penetrated. The condensed and vaporized contaminants are withdrawn by liquid pumping and vacuum extraction. The steam injection and electrical heating steps are repeated as necessary. Geophysical imaging methods can be used to map the boundary between the hot, dry, contamination-free underground zone and the cool, damp surrounding areas to help monitor the dynamic stripping process.

Conformance to Regulatory Guide 1.97, River Bend Station, Unit No. 1 (Docket No. 50-458)

International Nuclear Information System (INIS)

Udy, A.C.

1985-08-01

This EG and G, Inc., report reviews the submittals for Regulatory Guide 1.97, Revision 3, for the River Bend Station, Unit No. 1. Any exception to Regulatory Guide 1.97 is evaluated and those areas where sufficient basis for acceptability is not provided are identified. 8 refs

US central station nuclear electric generating units: significant milestones (status as of January 1, 1979)

International Nuclear Information System (INIS)

1979-03-01

Construction and operational milestones are tabulated for US nuclear power plants. Data are presented on nuclear steam supply system orders. A schedule of commercial operation and projected capital costs through 1990 is given

Experiences from Loviisa Nuclear Power Station concerning the decontamination of steam generators and primary system components

International Nuclear Information System (INIS)

Jaernstroem, R.

1989-01-01

Loviisa 1 and 2 are 465 MWe PWR units of the Soviet type VVER-440. Loviisa 1 has been in commercial operation since spring 1977 and Loviisa 2 from the beginning of 1980. Decontamination of primary circuit components - even big ones as steam generators - can be performed in an efficient and quick way with good results and resonable expences. Total costs for decontamination of the two steam generators including planning, construction, documentation, operation, chemicals etc. did not rise above 100,000.00 dollars. (author) 6 figs., 2 tabs

On the possibility of generation of cold and additional electric energy at thermal power stations

Science.gov (United States)

Klimenko, A. V.; Agababov, V. S.; Borisova, P. N.

2017-06-01

A layout of a cogeneration plant for centralized supply of the users with electricity and cold (ECCG plant) is presented. The basic components of the plant are an expander-generator unit (EGU) and a vapor-compression thermotransformer (VCTT). At the natural-gas-pressure-reducing stations, viz., gas-distribution stations and gas-control units, the plant is connected in parallel to a throttler and replaces the latter completely or partially. The plant operates using only the energy of the natural gas flow without burning the gas; therefore, it can be classified as a fuelless installation. The authors compare the thermodynamic efficiencies of a centralized cold supply system based on the proposed plant integrated into the thermal power station scheme and a decentralized cold supply system in which the cold is generated by electrically driven vapor-compression thermotransformers installed on the user's premises. To perform comparative analysis, the exergy efficiency was taken as the criterion since in one of the systems under investigation the electricity and the cold are generated, which are energies of different kinds. It is shown that the thermodynamic efficiency of the power supply using the proposed plant proves to be higher within the entire range of the parameters under consideration. The article presents the results of investigating the impact of the gas heating temperature upstream from the expander on the electric power of the plant, its total cooling capacity, and the cooling capacities of the heat exchangers installed downstream from the EGU and the evaporator of the VCTT. The results of calculations are discussed that show that the cold generated at the gas-control unit of a powerful thermal power station can be used for the centralized supply of the cold to the ventilation and conditioning systems of both the buildings of the power station and the neighboring dwelling houses, schools, and public facilities during the summer season.

Summary of erosion-corrosion observations made in power stations on damp-steam circuits

International Nuclear Information System (INIS)

Lacaille, L.

1981-01-01

The development of the light-water system has profoundly modified the operating conditions of the turbines, in which expansion now takes place from the first saturated-steam stages. In addition to the traditional phenomena of mechanical erosion there are now problems of a chemical nature, linked to the temperatures of the liquid phase, which cause destruction in the HP stages of the turbines, the drier-feed heaters, and the linking piping. Systematic observations have been made in the PWR stations at Chooz, Doel, Tihange, Fessenheim, and Le Bugey, followed by trials of materials, improvements in the flow, chemical treatment of the secondary circuit, and reduction of the liquid phase in the steam emerging from the HP turbine [fr

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

International Nuclear Information System (INIS)

1989-08-01

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

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

Science.gov (United States)

2010-03-30

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

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

Science.gov (United States)

2013-05-29

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

Safety Evaluation Report related to the full-term operating license for Millstone Nuclear Power Station, Unit No. 1 (Docket No. 50-245)

International Nuclear Information System (INIS)

1985-10-01

The Safety Evaluation Report for the full-term operating license application filed by the Connecticut Light and Power Company, the Hartford Electric Light Company, Western Massachusetts Electric Company and the Millstone Point Company [(now known as Connecticut Light and Power Company (CL and P) and Western Massachusetts Electric Company (WMECO) having authority to possess Millstone-1, 2, and 3, and the Northeast Nuclear Energy Company (NNECO) as the responsible entity for operation of the facilities)] for Millstone Nuclear Power Station Unit 1 has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located in the town of Waterford, Connecticut. Subject to favorable resolution of the items discussed in this report, the staff concludes that the facility can continue to be operated without endangering the health and safety of the public

Flood-inundation maps for the West Branch Susquehanna River near the Boroughs of Lewisburg and Milton, Pennsylvania

Science.gov (United States)

Roland, Mark A.; Hoffman, Scott A.

2014-01-01

Digital flood-inundation maps for an approximate 8-mile reach of the West Branch Susquehanna River from approximately 2 miles downstream from the Borough of Lewisburg, extending upstream to approximately 1 mile upstream from the Borough of Milton, Pennsylvania, were created by the U.S. Geological Survey (USGS) in cooperation with the Susquehanna River Basin Commission (SRBC). The inundation maps, which can be accessed through the USGS Flood Inundation Mapping Science Web site at http://water.usgs.gov/osw/flood_inundation/, depict the estimated areal extent and depth of flooding corresponding to selected water levels (stages) at the USGS streamgage 01553500, West Branch Susquehanna River at Lewisburg, Pa. In addition, the information has been provided to the Susquehanna River Basin Commission (SRBC) for incorporation into their Susquehanna Inundation Map Viewer (SIMV) flood warning system (http://maps.srbc.net/simv/). The National Weather Service (NWS) forecasted peak-stage information (http://water.weather.gov/ahps) for USGS streamgage 01553500, West Branch Susquehanna River at Lewisburg, Pa., may be used in conjunction with the maps developed in this study to show predicted areas of flood inundation. In this study, flood profiles were computed for the stream reach by means of a one-dimensional step-backwater model. Calibration of the model was achieved using the most current stage-discharge relations (rating number 11.1) at USGS streamgage 01553500, West Branch Susquehanna River at Lewisburg, Pa., a documented water-surface profile from the December 2, 2010, flood, and recorded peak stage data. The hydraulic model was then used to determine 26 water-surface profiles for flood stages at 1-foot intervals referenced to the streamgage datum ranging from 14 feet (ft) to 39 ft. Modeled flood stages, as defined by NWS, include Action Stage, 14 ft; Flood Stage, 18 ft; Moderate Flood Stage, 23 ft; and Major Flood Stage, 28 ft. Geographic information system (GIS) technology

Evaluation of Steam Generator Level behavior for Determination of Turbine Runback rate on COPs trip for Yonggwang 1 and 2 Power Uprating Units

International Nuclear Information System (INIS)

Lee, Kyung Jin; Hwang, Su Hyun; Yoo, Tae Geun; Chung, Soon Il; An, Byung Chang; Park, Jung Gu

2010-01-01

4.5% power uprate project has been progressing for the first time in Yonggwang 1 and 2(YGN1 and 2). Reviews for design change due to the power uprate were accomplished. Steam generator level behavior was one of the most important parameters because it could be cause of reactor trip or turbine trip. As the results of the reviews, YGN1 and 2 had to reassess it for change of turbine runback rate when turbine runback occurs due to the condensate operating pumps (COP) trip. This study has been carried out for evaluating the steam generator level behavior for determination of turbine runback rate on COPs trip for Yonggwang 1 and 2 Power Uprating Units. The steam generator water level evaluation program for YGN1 and 2 (SLEP-Y1) has been developed for it. The program includes models for the steam generator water level response. SLEP-Y1 is programmed with advanced continuous system simulation language (ACSL). The language has been used to simulate physical systems as a commercial tool used to evaluate system designs

The economic aspect of transition to power units with supercritical steam parameters

Energy Technology Data Exchange (ETDEWEB)

V.R. Kotler

2007-09-15

Information on the development and use of power units for supercritical and ultrasupercritical steam parameters in the United States, as well as in Europe and Japan, is presented. It is shown that increasing the parameters of steam reduces not only the fuel consumption, but also the specific emissions of toxic and greenhouse gases. Results of a calculation carried out at the EPRI (the United States) are presented, which show that it is advisable to construct power units for supercritical parameters only at certain (sufficiently high) price of the fuel being fired.

Steam coal trade: demand, supply and prices to 2020

Energy Technology Data Exchange (ETDEWEB)

1993-04-01

This report on the international seaborne steam coal market was prepared using an electricity generation model developed for each coal-importing country, with the aid of WEFA Energy's power station database. The report contains chapters on: import demand forecasting methodology; orimulsion (environmental considerations and market potential); Scandinavia; North West Europe; British Isles; South West Europe; Eastern Europe; Eastern Mediterranean and North Africa; Asia; Latin America; North America; world steam coal demand summary; trade and price forecasting methodology; base case forecast; shipping rates; import demand; export supply and foreign exchange rates.

Calculation Method of Steam Generator Level for swelling and shrinking effects in YGN 1/2 Simulator

International Nuclear Information System (INIS)

Hwang, Do Hyun; Seo, In Yong; Park, Weon Seo; Suh, Jae Seung

2007-01-01

In August 2006, the development of new simulator for YGN 1/2 Simulator was completed. The NSSS (Nuclear Steam Supply System) T/H(Thermal- Hydraulic) module in this simulator was developed with ARTS code based on RETRAN, which is a best estimate thermal-hydraulic code designed to analyze several operational transients by EPRI(Electric Power Research Institute). RETRAN, however, has some limitations in real-time calculation capability and its robustness to be used in the simulator for some transient conditions. To overcome these limitations, its robustness and real-time calculation capability have been improved with simplifications and removing of discontinuities of the physical correlations of the RETRAN code. And some supplements are also developed to extend its simulation scope of the ARTS code. In comparison to KNPEC(Kori Nuclear Power Education Center) no.2 simulator, the simulator based on Younggwang Unit 1 developed in the year 2001, the ARTS code was upgraded that it extended its calculating region to the steam line and common header before turbine while it had calculated to the steam generator exit before steam line in KNPEC no.2 simulator. Consequently, the number of volume and fill/normal junction in ARTS nodalization increased to 109 and 174 from 62 and 125, respectively

Synergetic mechanism of methanol–steam reforming reaction in a catalytic reactor with electric discharges

International Nuclear Information System (INIS)

Kim, Taegyu; Jo, Sungkwon; Song, Young-Hoon; Lee, Dae Hoon

2014-01-01

Highlights: • Methanol–steam reforming was performed on Cu catalysts under an electric discharge. • Discharge had a synergetic effect on the catalytic reaction for methanol conversion. • Discharge lowered the temperature for catalyst activation or light off. • Discharge controlled the yield and selectivity of species in a reforming process. • Adsorption triggered by a discharge was a possible mechanism for a synergetic effect. - Abstract: Methanol–steam reforming was performed on Cu/ZnO/Al 2 O 3 catalysts under an electric discharge. The discharge occurred between the electrodes where the catalysts were packed. The electric discharge was characterized by the discharge voltage and electric power to generate the discharge. The existence of a discharge had a synergetic effect on the catalytic reaction for methanol conversion. The electric discharge provided modified reaction paths resulting in a lower temperature for catalyst activation or light off. The discharge partially controlled the yield and selectivity of species in a reforming process. The aspect of control was examined in view of the reaction kinetics. The possible mechanisms for the synergetic effect between the catalytic reaction and electric discharge on methanol–steam reforming were addressed. A discrete reaction path, particularly adsorption triggered by an electric discharge, was suggested to be the most likely mechanism for the synergetic effect. These results are expected to provide a guide for understanding the plasma–catalyst hybrid reaction

Energy Conversion Alternatives Study (ECAS), Westinghouse phase 1. Volume 11: Advanced steam systems. [energy conversion efficiency for electric power plants using steam

Science.gov (United States)

Wolfe, R. W.

1976-01-01

A parametric analysis was made of three types of advanced steam power plants that use coal in order to have a comparison of the cost of electricity produced by them a wide range of primary performance variables. Increasing the temperature and pressure of the steam above current industry levels resulted in increased energy costs because the cost of capital increased more than the fuel cost decreased. While the three plant types produced comparable energy cost levels, the pressurized fluidized bed boiler plant produced the lowest energy cost by the small margin of 0.69 mills/MJ (2.5 mills/kWh). It is recommended that this plant be designed in greater detail to determine its cost and performance more accurately than was possible in a broad parametric study and to ascertain problem areas which will require development effort. Also considered are pollution control measures such as scrubbers and separates for particulate emissions from stack gases.

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

International Nuclear Information System (INIS)

1984-12-01

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

Procedure for estimating nonfuel operation and maintenance costs for large steam-electric power plants

International Nuclear Information System (INIS)

Myers, M.L.; Fuller, L.C.

1979-01-01

Revised guidelines are presented for estimating annual nonfuel operation and maintenance costs for large steam-electric power plants, specifically light-water-reactor plants and coal-fired plants. Previous guidelines were published in October 1975 in ERDA 76-37, a Procedure for Estimating Nonfuel Operating and Maintenance Costs for Large Steam-Electric Power Plants. Estimates for coal-fired plants include the option of limestone slurry scrubbing for flue gas desulfurization. A computer program, OMCOST, is also presented which covers all plant options

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

International Nuclear Information System (INIS)

1975-01-01

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

Analysis of a station blackout transient at the Kori units 3/4

International Nuclear Information System (INIS)

Bang, Young Seok; Kim, Hho Jung

1992-01-01

A transient analysis of station blackout accident is performed to evaluate the plant specific capability to cope with the accident at the Kori Units 3/4. The RELAP5/MOD3/5m5 code and full three loop modelling scheme are used in the calculation. The leak flow from reactor coolant system due to a failure of reactor coolant pump seal following the accident is assumed to be 25 gpm and the turbine driven aux feedwater unavailable. As a result, it is found that no core uncovery occurs in the plant until 7100 sec following a station blackout, the steam generator has a decay heat removal capability until 3100 sec, and the natural circulation over the reactor coolant loop until the complete loop seal voiding are observed. And the Nuclear Plant Analyzer is used and found to be effective in improving the phenomenological understanding on the accident

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

Science.gov (United States)

2010-02-23

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

Ontario Hydro's operating experience with steam generators with specifics on Bruce A and Bruce B problems

Energy Technology Data Exchange (ETDEWEB)

Eatock, J W; Patterson, R W [Ontario Hydro, Toronto, ON (Canada); Dyck, R W [Ontario Hydro, Central Production Services Division, Toronto, ON (Canada)

1991-04-01

The performance of the steam generators in Ontario Hydro nuclear power stations is reviewed. This performance has generally been outstanding compared to world averages, with very low tube failure and plugging rates. Steam generator problems have made only minor contributions to Ontario Hydro nuclear station incapability factors. The mechanisms responsible for the the observed tube degradation and failures are described. The majority of the leaks have been due fatigue in the U-bend of the Bruce 'A' steam generators. There have been very few failures attributed to corrosion of the three tube materials used in Ontario Hydro steam generators. Recent performance has been deteriorating primarily due to deposit accumulation in the steam generators. Plugging of the broached holes in the upper support plates at Bruce 'A' has caused some derating of two units. Increases have been observed in the primary heat transport system reactor inlet temperature of several units. These increases may be attributed to steam generator tube surface fouling. In addition, several units have accumulated deep, hard sludge piles on the tube sheet, although little damage been observed. Recently some fretting of tubes has been observed at BNGSB in the U-bend support region. Remedial measures are being taken to address the current problems. Solutions are being evaluated to reduce the generation of corrosion products in the feedtrain and their subsequent transport to the steam generators. (author)

Ontario Hydro's operating experience with steam generators with specifics on Bruce A and Bruce B problems

International Nuclear Information System (INIS)

Eatock, J.W.; Patterson, R.W.; Dyck, R.W.

1991-01-01

The performance of the steam generators in Ontario Hydro nuclear power stations is reviewed. This performance has generally been outstanding compared to world averages, with very low tube failure and plugging rates. Steam generator problems have made only minor contributions to Ontario Hydro nuclear station incapability factors. The mechanisms responsible for the the observed tube degradation and failures are described. The majority of the leaks have been due fatigue in the U-bend of the Bruce 'A' steam generators. There have been very few failures attributed to corrosion of the three tube materials used in Ontario Hydro steam generators. Recent performance has been deteriorating primarily due to deposit accumulation in the steam generators. Plugging of the broached holes in the upper support plates at Bruce 'A' has caused some derating of two units. Increases have been observed in the primary heat transport system reactor inlet temperature of several units. These increases may be attributed to steam generator tube surface fouling. In addition, several units have accumulated deep, hard sludge piles on the tube sheet, although little damage been observed. Recently some fretting of tubes has been observed at BNGSB in the U-bend support region. Remedial measures are being taken to address the current problems. Solutions are being evaluated to reduce the generation of corrosion products in the feedtrain and their subsequent transport to the steam generators. (author)

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

International Nuclear Information System (INIS)

1989-08-01

In August 1983 the staff of the Nuclear Regulatory commission issued its Safety Evaluation Report (NUREG-0991) regarding the application of the Philadelphia Electric Company (the licensee) for the licenses to operate the Limerick Generating Station, Units 1 and 2, located on a site in Montgomery and Chester Counties, Pennsylvania. Supplement 1 was issued in December 1983. Supplement 2 was issued in October 1984. Supplement 3 was issued in October 1984. Supplement 4 was issued in May 1985. Supplement 5 was issued in July 1985. Supplement 6 was issued in August 1985 and Supplement 7 was issued in April 1989. Supplement 7 addresses the major design differences between Units 1 and 2, the resolution of all issues that remained open when the Unit 1 full-power license was issued, the staff's assessment regarding the application by the licensee to operate Unit 2 and issues that require resolution before issuance of an operating license for Unit 2. Supplements 8 and 9 address further issues that require resolution prior to issuance of an operating license. 1 tab

The Paks Nuclear Power Station

International Nuclear Information System (INIS)

Erdosi, N.; Szabo, L.

1978-01-01

As the first stage in the construction of the Paks Nuclear Power Station, two units of 440 MW(e) each will be built. They are operated with two coolant loops each. The reactor units are VVER 440 type water-moderated PWR type heterogeneous power reactors designed in the Soviet Union and manufactured in Czechoslovakia. Each unit operates two Soviet-made K-220-44 steam turbines and Hungarian-made generators of an effective output of 220 MW. The output of the transformer units - also of Hungarian made - is 270 MVA. The radiation protection system of the nuclear power station is described. Protection against system failures is accomplished by specially designed equipment and security measures especially within the primary circuit. Some data on the power station under construction are given. (R.P.)

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

International Nuclear Information System (INIS)

1983-03-01

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

Innovation of blow-down system in steam generators of a VVER 440 unit

International Nuclear Information System (INIS)

Matal, O.; Simo, T.; Mancev, M.D.

1997-01-01

The impurities getting into the steam generator with the feedwater are continually removed by the blowdown and unit sludge system. The mostly non-symmetrical type of pipe branches under steam generators at WWER-440 units causes nonuniform blowdown flow rates at the halves of the steam generator; this often leads to a blocking of the pipe with the lower flow rate. The most simple way of hydraulically equalizing the blowdown pipes is to implement symmetric blowdown pipes and to install efficient throttling elements in the pipe. The proposed innovation will make it possible to re-distribute the blowdown flow rates and to reduce more effectively the concentrations of impurities in steam generators. (M.D.)

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

International Nuclear Information System (INIS)

1976-01-01

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

Safety Evaluation Report related to the operation of Limerick Generating Station, Units 1 and 2 (Docket Nos. 50-352 and 50-353). Supplement 3

International Nuclear Information System (INIS)

1984-10-01

In August 1983 the staff of the Nuclear Regulatory Commission issued its Safety Evaluation Report (NUREG-0991) regarding the application of the Philadelphia Electric Company (the applicant) for licenses to operate the Limerick Generating Station, Units 1 and 2. Supplement 1 was issued in December 1983 and addressed several outstanding issues. Supplement 1 also contains the comments made by the Advisory Committee on Reactor Safeguards in its report dated October 18, 1983. Supplement 2 was issued in October 1984 and addressed fourteen outstanding and fifty-three confirmatory issues and closed them put. This Supplement 3 addresses the remaining issues that require resolution before issuance of the operating license for Unit 1 and closes them out

900 MW CP1 nuclear steam turbine retrofit thermal effects on low pressure diaphragms

International Nuclear Information System (INIS)

Buguin, A.; Gruau, P.; Lamarque, F.; Huggett, J.

2015-01-01

The steam turbines of the Koeberg units 1 and 2 operated by ESKOM in South Africa have been retrofitted in order to mitigate the generic problems of stress corrosion cracking of the original shrunk-on disk rotor design. As already done in Belgium and France, the implementation of welded rotors improves the turbine reliability and availability. Moreover, the new technology implemented associated with a new steam path allows a significant performance improvement. With a wealth of experience in CP1 retrofit, ALSTOM has put in place new technical features in the steam path in order to further improve the heat rate. Among them, steam balance holes drilled in the rotor disks have exacerbated the thermal sensitivity of the LP diaphragms. During the commissioning of the Unit 1 LP turbines following the retrofit, the load increase led to unacceptable vibrations. An investigation program was launched to determine the root causes of the problem. This paper presents the findings following the turbine inspection, as well as the recommendations and modifications to allow a smooth return to service of the unit. In addition, the results of the root cause analysis of the vibration incident are explained. Based on finite element calculations and site measurements, ALSTOM has established that the diaphragm thermal behavior, intensified by the steam balance holes, has led to radial rubbing. It was also established that the phenomena had no effect on the diaphragms mechanical integrity. Design changes have been proposed to ensure a safe and reliable long term operation of the units. These modifications have been successfully implemented onto the Koeberg Unit 2 Nuclear Steam Turbine commissioned in November 2012. (authors)

Space Station Freedom electrical power system hardware commonality with the United States Polar Platform

Science.gov (United States)

Rieker, Lorra L.; Haraburda, Francis M.

1989-01-01

Information is presented on how the concept of commonality is being implemented with respect to electric power system hardware for the Space Station Freedom and the U.S. Polar Platform. Included is a historical account of the candidate common items which have the potential to serve the same power system functions on both Freedom and the Polar Platform. The Space Station program and objectives are described, focusing on the test and development responsibilities. The program definition and preliminary design phase and the design and development phase are discussed. The goal of this work is to reduce the program cost.

Steam turbine of WWER-1000 unit

International Nuclear Information System (INIS)

Drahy, J.

1986-01-01

The manufacture was started by Skoda of a saturated steam, 1,000 MW, 3,000 rpm turbine designed for the Temelin nuclear power plant. The turbine provides steam for heating water for district heating, this either with an output of 893 MW for a three-stage water heating at 150/60 degC, or of 570 MW for a two-stage water heating at 120/60 degC. The turbine features one high-pressure and three identical low-pressure stages. The pressure gradient between the high-pressure and the low-pressure parts was optimized with respect to the thermal efficiency of the cycle and to the thermodynamic efficiency of the low-pressure part. A value of 0.79 MPa was selected corresponding to the maximum through-flow of steam entering the turbine. This makes 5,495 t/h, the admission steam parameters are 273.3 degC and 5.8 MPa. The feed water temperature is 220.9 degC. 300 cold starts, 1,000 starts after shutdowns for 55 to 88 hours and 600 starts after shutdown for 8 hours are envisaged for the entire turbine service life. (Z.M.). 5 figs., 1 tab., 6 refs

Development and application of the lancing system of delta-60 steam generator-Kori nuclear power plant unit 1

International Nuclear Information System (INIS)

Jeong, W. T.; Han, D. Y.; Ahn, N. S.; Jo, B. H.; Hong, Y. W.

2001-01-01

A lancing system for removing the deposits on the tube sheet of a nuclear steam generator using high pressure water was developed and applied to Kori Nuclear Power Plant( NPP) Unit 1. As the place where the lancing system is to be installed is relatively high radioactive area, every part consisting the equipment is carefully selected to be radiation resistant. The lancing robot was designed to be water proof to aviod possible malfunction of the lancing robot because of high pressure water. To minimize radiation exposure to operators, the system was designed considering easy installation and maintenance in mind. Water ejection nozzle are designed to have high strength with special material and heat treatment so as to lessen abrasion caused by high pressure ejection. The lancing system showed good performance during the on-site lancing using the system for Delta-60 steam generator of Kori NPP No. 1 in October 2000

Technical Specifications, Byron Station, Unit Nos. 1 and 2 (Docket Nos. STN 50-454 and STN 50-455). Appendix A to license No. NPF-37

International Nuclear Information System (INIS)

1985-02-01

The Byron Station, Unit No. 1 and Unit No. 2 Technical Specifications were prepared by the US Nuclear Regulatory Commission to set forth the limits, operating conditions, and other requirements applicable to a nuclear reactor facility as set forth in Section 50.36 of 10 CFR Part 50 for the protection of the health and safety of the public. Specifications are presented for limiting conditions for operation for the reactor control system, power distribution limits, instrumentation, primary coolant circuit, ECCS, containment systems, plant systems, electrical power systems, refueling operations, radioactive effluents, and radiological environmental monitoring

Electricity pricing model in thermal generating stations under deregulation

International Nuclear Information System (INIS)

Reji, P.; Ashok, S.; Moideenkutty, K.M.

2007-01-01

In regulated public utilities with competitive power markets, deregulation has replaced the monopoly. Under the deregulated power market, the electricity price primarily depends on market mechanism and power demand. In this market, generators generally follow marginal pricing. Each generator fixes the electricity price based on their pricing strategy and it leads to more price volatility. This paper proposed a model to determine the electricity price considering all operational constraints of the plant and economic variables that influenced the price, for a thermal generating station under deregulation. The purpose of the model was to assist existing stations, investors in the power sector, regulatory authorities, transmission utilities, and new power generators in decision-making. The model could accommodate price volatility in the market and was based on performance incentive/penalty considering plant load factor, availability of the plant and peak/ off peak demand. The model was applied as a case study to a typical thermal utility in India to determine the electricity price. It was concluded that the case study of a thermal generating station in a deregulated environment showed that the electricity price mainly depended on the gross calorific value (GCV) of fuel, mode of operation, price of the fuel, and operating charges. 11 refs., 2 tabs., 1 fig

Experience of Ko-Ri Unit 1 water chemistry

International Nuclear Information System (INIS)

Tae Il Lee

1983-01-01

The main focus is placed on operational experience in secondary system water chemistry (especially the steam generator) of the Ko-Ri nuclear power plant Unit 1, Republic of Korea, but primary side chemistry is also discussed. The major concern of secondary water chemistry in a PWR is that the condition of the steam generator be well maintained. Full flow deep bed condensate polishers have recently been installed and operation started in July 1982. Boric acid treatment of the steam generator was stopped and only the all volatile treatment method was used thereafter. A review of steam generator integrity, the chemistry control programme, secondary water quality, etc. is considered to be of great value regarding the operation of Unit 1 and future units now under startup testing or construction in the Republic of Korea. (author)

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

International Nuclear Information System (INIS)

1977-01-01

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

VT Data - Electric Charging Stations

Data.gov (United States)

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

Type GQS-1 high pressure steam manifold water level monitoring system

International Nuclear Information System (INIS)

Li Nianzu; Li Beicheng; Jia Shengming

1993-10-01

The GQS-1 high pressure steam manifold water level monitoring system is an advanced nuclear gauge that is suitable for on-line detecting and monitor in high pressure steam manifold water level. The physical variable of water level is transformed into electrical pulses by the nuclear sensor. A computer is equipped for data acquisition, analysis and processing and the results are displayed on a 14 inch color monitor. In addition, a 4 ∼ 20 mA output current is used for the recording and regulation of water level. The main application of this gauge is for on-line measurement of high pressure steam manifold water level in fossil-fired power plant and other industries

Upgraded Steam Generator Lancing System for Uljin NPP no.2

International Nuclear Information System (INIS)

Kim, Seok Tae; Jeong, Woo Tae; Hong, Sung Yull

2005-01-01

KEPRI(Korea Electric Power Research Institute) has developed various types of steam generator lancing systems since 1998. In this paper, we introduce a new lancing system with new improvements from the previous steam generator lancing system for Uljin NPP #2(nuclear power plant) constructed by KEPRI. The previous lancing system is registered as KALANS R -II and was developed for System-80 type steam generators. The previous lancing system was applied to Uljin unit #3 and it lowered radiation exposure of operators in comparison to manually operated lancing systems. And it effectively removed sludge accumulated around kidney bean zone in the Uljin unit #3 steam generators. But the previous lancing system could only clean partially the steam generators of Uljin unit #4. This was because the rail of the previous lancing system interfered with a part of the steam generator. Therefore we developed a new lancing system that can solve the interference problem. This new lancing system was upgraded from the previous lancing system. Also, a new lancing system for System-80 S/G will be introduced in this paper

Mitigation of organically bound sulphate from water treatment plants at Bruce NGS and impact on steam generator secondary side chemistry control

Energy Technology Data Exchange (ETDEWEB)

Nashiem, R.; Davloor, R.; Harper, B.; Smith, K. [Bruce Power, Tiverton, Ontario (Canada); Gauthier, C. [CTGIX Services Inc., Burlington, Ontario (Canada); Schexnailder, S. [GE Water and Process Technologies, Dallas, Texas (United States)

2010-07-01

Bruce Power is the source of more than 20 per cent of Ontario's electricity and currently operates six reactor units at the Bruce Nuclear Generating Station A (two units) and B (four units) stations located on Lake Huron. This paper discusses the challenges faced and operating experience (OPEX) gained in meeting WANO 1.0 chemistry performance objectives for steam generator secondary side chemistry control, particularly with control of steam generator sulphates. A detailed sampling and analysis program conducted as part of this study concluded that a major contributor to steam generator (SG) elevated sulphates is Organically Bound Sulphate (OBS) in Water Treatment Plants (WTP) effluent. The Bruce A and B WTPs consist of clarification with downstream sand and carbon filtration for Lake Water pre-treatment, which are followed by conventional Ion Exchange (IX) demineralization. Samples taken from various locations in the process stream were analyzed for a variety of parameters including both organic bound and inorganic forms of sulphate. The results are inconclusive with respect to finding the definitive source of OBS. This is primarily due to the condition that the OBS in the samples, which are in relatively low levels, are masked during chemical analysis by the considerably higher inorganic sulphate background. Additionally, it was also determined that on-line Total Organic Carbon (TOC) levels at different WTP locations did not always correlate well with OBS levels in the effluent, such that TOC could not be effectively used as a control parameter to improve OBS performance of the WTP operation. Improvement efforts at both plants focused on a number of areas including optimization of clarifier operation, replacement of IX resins, addition of downstream mobile polishing trailers, testing of new resins and adsorbents, pilot-scale testing with a Reverse Osmosis (RO) rig, review of resin regeneration and backwashing practices, and operating procedure improvements

Mitigation of organically bound sulphate from water treatment plants at Bruce NGS and impact on steam generator secondary side chemistry control

International Nuclear Information System (INIS)

Nashiem, R.; Davloor, R.; Harper, B.; Smith, K.; Gauthier, C.; Schexnailder, S.

2010-01-01

Bruce Power is the source of more than 20 per cent of Ontario's electricity and currently operates six reactor units at the Bruce Nuclear Generating Station A (two units) and B (four units) stations located on Lake Huron. This paper discusses the challenges faced and operating experience (OPEX) gained in meeting WANO 1.0 chemistry performance objectives for steam generator secondary side chemistry control, particularly with control of steam generator sulphates. A detailed sampling and analysis program conducted as part of this study concluded that a major contributor to steam generator (SG) elevated sulphates is Organically Bound Sulphate (OBS) in Water Treatment Plants (WTP) effluent. The Bruce A and B WTPs consist of clarification with downstream sand and carbon filtration for Lake Water pre-treatment, which are followed by conventional Ion Exchange (IX) demineralization. Samples taken from various locations in the process stream were analyzed for a variety of parameters including both organic bound and inorganic forms of sulphate. The results are inconclusive with respect to finding the definitive source of OBS. This is primarily due to the condition that the OBS in the samples, which are in relatively low levels, are masked during chemical analysis by the considerably higher inorganic sulphate background. Additionally, it was also determined that on-line Total Organic Carbon (TOC) levels at different WTP locations did not always correlate well with OBS levels in the effluent, such that TOC could not be effectively used as a control parameter to improve OBS performance of the WTP operation. Improvement efforts at both plants focused on a number of areas including optimization of clarifier operation, replacement of IX resins, addition of downstream mobile polishing trailers, testing of new resins and adsorbents, pilot-scale testing with a Reverse Osmosis (RO) rig, review of resin regeneration and backwashing practices, and operating procedure improvements

Integrated gasification and Cu-Cl cycle for trigeneration of hydrogen, steam and electricity

Energy Technology Data Exchange (ETDEWEB)

Aghahosseini, S; Dincer, I; Naterer, G F [University of Ontario, Oshawa, ON (Canada). Institute of Technology

2011-02-15

This paper develops and analyzes an integrated process model of an Integrated Gasification Combined Cycle (IGCC) and a thermochemical copper-chlorine (Cu-Cl) cycle for trigeneration of hydrogen, steam and electricity. The process model is developed with Aspen HYSYS software. By using oxygen instead of air for the gasification process, where oxygen is provided by the integrated Cu-Cl cycle, it is found that the hydrogen content of produced syngas increases by about 20%, due to improvement of the gasification combustion efficiency and reduction of syngas NOx emissions. Moreover, about 60% of external heat required for the integrated Cu-Cl cycle can be provided by the IGCC plant, with minor modifications of the steam cycle, and a slight decrease of IGCC overall efficiency. Integration of gasification and thermochemical hydrogen production can provide significant improvements in the overall hydrogen, steam and electricity output, when compared against the processes each operating separately and independently of each other.

Autonomous Electrical Vehicles’ Charging Station

OpenAIRE

Józef Paska; Mariusz Kłos; Łukasz Rosłaniec; Rafał Bielas; Magdalena Błędzińska

2016-01-01

This paper presents a model of an autonomous electrical vehicles’ charging station. It consists of renewable energy sources: wind turbine system, photovoltaic cells, as well as an energy storage, load, and EV charging station. In order to optimise the operating conditions, power electronic converters were added to the system. The model was implemented in the Homer Energy programme. The first part of the paper presents the design assumptions and technological solutions. Further in the paper...

Steam drums

International Nuclear Information System (INIS)

Crowder, R.

1978-01-01

Steam drums are described that are suitable for use in steam generating heavy water reactor power stations. They receive a steam/water mixture via riser headers from the reactor core and provide by means of separators and driers steam with typically 0.5% moisture content for driving turbines. The drums are constructed as prestressed concrete pressure vessels in which the failure of one or a few of the prestressing elements does not significantly affect the overall strength of the structure. The concrete also acts as a radiation shield. (U.K.)

US central station nuclear electric generating units: significant milestones (status as of July 1, 1980)

International Nuclear Information System (INIS)

1980-09-01

The status of 189 US nuclear power plants is reported in a table which gives the name, owner, capacity, type, NSSS architect and contractor and data of public announcement, NSSS order, licensing, and initial operation. The plants are also indexed according to state, region, utility, and alphabetical name. The utility nuclear steam supply system orders are also listed

Aluminum-Enhanced Underwater Electrical Discharges for Steam Explosion Triggering

International Nuclear Information System (INIS)

HOGELAND, STEVE R.; NELSON, LLOYD S.; ROTH, THOMAS CHRISTOPHER

1999-01-01

For a number of years, we have been initiating steam explosions of single drops of molten materials with pressure and flow (bubble growth) transients generated by discharging a capacitor bank through gold bridgewires placed underwater. Recent experimental and theoretical advances in the field of steam explosions, however, have made it important to substantially increase these relatively mild transients in water without using high explosives, if possible. To do this with the same capacitor bank, we have discharged similar energies through tiny strips of aluminum foil submerged in water. By replacing the gold wires with the aluminum strips, we were able to add the energy of the aluminum-water combustion to that normally deposited electrically by the bridgewire explosion in water. The chemical enhancement of the explosive characteristics of the discharges was substantial: when the same electrical energies were discharged through the aluminum strips, peak pressures increased as much as 12-fold and maximum bubble volumes as much as 5-fold above those generated with the gold wires. For given weights of aluminum, the magnitudes of both parameters appeared to exceed those produced by the underwater explosion of equivalent weights of high explosives

Audit of Wolf Creek Generating Station, Unit 1 technical specifications. Final technical evaluation report

International Nuclear Information System (INIS)

Stromberg, H.M.

1985-07-01

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

Transmutor demo unit and thermal into electrical energy transformation problems

International Nuclear Information System (INIS)

Matal, O.; Fiedler, J.

1999-01-01

In the three circuits layout of the transmutor the heat is transferred from the primary through the secondary circuits by a favourable heat carrier into the tertiary circuit where the thermal into electrical energy transformation in turbo-generator comes into force. Properties as well as parameters of the heat carrier in the secondary circuit affect basically both the conceptual layout of the tertiary circuit and consequently investments costs for its realization and the effectiveness of the transformation of thermal into electrical energy. For several heat carriers considered for the transmutor secondary circuit particular tertiary circuit concepts for the demonstration transmutor unit of approx. 15 W thermal power rate are analyzed, layout features and possibilities of turbogenerator selection are commented and investment costs as well as effectiveness of thermal into electrical energy transformation are estimated. Some of the results are as follows: (i) Heat carrier properties influence thermodynamics of the TDU water/steam cycle substantially. One of the dominant parameters is the melting (freezing) temperature of the heat carrier. (ii) Heat carrier properties influence investment costs of components of the TDU tertiary circuit substantially. Dominantly influenced are costs of the steam generator, steam turbine and high pressure regeneration system. (iii) If the heat carrier has to be a molten salt than a salt with a low melting temperature is recommended to be selected, for example KHF2. (iv) Eutectic alloy Pb-Bi as the heat carrier serves changes to design the TDU with efficient thermodynamics, with acceptable low investment costs of the tertiary as well as secondary circuit components and with an acceptable level of the nuclear safety

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

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

International Nuclear Information System (INIS)

Sueyoshi, Toshiyuki; Goto, Mika

2014-01-01

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

Design and performance of General Electric boiling water reactor main steam line isolation valves

International Nuclear Information System (INIS)

Rockwell, D.A.; van Zylstra, E.H.

1976-08-01

An extensive test program has been completed by the General Electric Company in cooperation with the Commonwealth Edison Company on the basic design type of large main steam line isolation valves used on General Electric Boiling Water Reactors. Based on a total of 40 tests under simulated accident conditions covering a wide range of mass flows, mixture qualities, and closing times, it was concluded that the commercially available valves of this basic type will close completely and reliably as required. Analytical methods to predict transient effects in the steam line and valve after postulated breaks were refined and confirmed by the test program

Results of 7th regular inspection of No.1 plant in Oi Power Station, Kansai Electric Power Co., Inc

International Nuclear Information System (INIS)

1989-01-01

The 7th regular inspection of No.1 plant in Oi Power Station was carried out from December 25, 1987 to July 15, 1988. The parallel operation was resumed on June 23, 1988, 182 days after the start of the inspection. The facilities to be inspected were the reactor proper, reactor cooling system, measurement and control system, fuel facilities, radiation control facilities, waste facilities, reactor containment installation and emergency power generation system. On these facilities to be inspected, the appearance, disassembling, leak, function, performance and other inspections were carried out, and as the results, a part of the fitting of a water chamber partition cover for a steam generator broke off, significant signals were observed in 936 heating tubes of steam generators, 72 bolts for fixing the blade of a primary coolant pump were damaged, and leak was found in two fuel assemblies. The works related to this regular inspection were accomplished within the range of allowable radiation dose based on the relevant laws. The main reconstruction works carried out during the period of this regular inspection were the use of the fuel containing gadolinia, the removal of a thermometer bypass piping and the repair of defective steam generator tubes. (K.I.)

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

International Nuclear Information System (INIS)

1983-08-01

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

Safety evaluation report related to steam generator tube repair and return to operation Three Mile Island Nuclear Station, Unit No. 1 (Docket No. 50-289)

International Nuclear Information System (INIS)

Silver, H.

1983-11-01

Based on our evaluation of the steam generator tube repair method and of subsequent operation using the repaired steam generators, we conclude that the steam generator tube kinetic expansion process is acceptable, that applicable GDC have been met, and that there is reasonable assurance that the health and safety of the public will not be endangered by subsequent operation of the plant

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

International Nuclear Information System (INIS)

1989-06-01

In August 1983 the staff of the Nuclear Regulatory Commission issued its Safety Evaluation Report (NUREG-0991) regarding the application of the Philadelphia Electric Company (the licensee) for licenses to operate the Limerick Generating Station, Units 1 and 2, located on site in Montgomery and Chester Counties, Pennsylvania. Supplement 1 to NUREG-0991 was issued in December 1983. Supplements 2 and 3 were issued in October 1984. License NPF-27 for the low-power operation of Limerick Unit 1 was issued on October 26, 1984. Supplement 4 was issued in May, 1985, Supplement 5 was issued in July 1985, and Supplement 6 was issued in August 1985. These supplements addressed further issues that required resolution before Unit 1 proceeded beyond the 5-percent power level. The full-power operating license for Limerick Unit 1 (NPF-39) was issued August 8, 1985, and the unit has completed two cycles of operation. Supplement 7 was issued April 1989 to address some of the few significant design differences between Units 1 and 2, the resolution of issues that remained open when the Unit 1 full-power license was issued and an assessment of some of the issues that required resolution before issuance of an operating license for Unit 2. This supplement addresses the remaining issues that required resolution before issuance of and operating license for Unit 2

Start up and commercial operation of Laguna Verde nuclear power plant. Unit 1

International Nuclear Information System (INIS)

Torres Ramirez, J.F.

1991-01-01

Prior to start up of Laguna Verde nuclear power plant preoperational tests and start tests were performed and they are described in its more eminent aspects. In relation to commercial operation of nuclear station a series of indicator were set to which allow the measurement of performance in unit 1, in areas of plant efficiency and personal safety. Antecedents. Laguna Verde station is located in Alto Lucero municipality in Veracruz state, 70 kilometers north-northeast from port of Veracruz and a 290 kilometers east-northeast from Mexico city. The station consist of two units manufactured by General Electric, with a nuclear system of vapor supply also called boiling water (BWR/5), and with a system turbine-generator manufactured by Mitsubishi. Each unit has a nominal power of 1931 MWt and a level design power of 675 Mwe and a net power of 654 Electric Megawatts

Analysis of induced steam generator tube rupture using MAAP 4.0

International Nuclear Information System (INIS)

Kenton, M.; Epstein, M.; Henry, R.E.; Paik, C.; Fuller, E.

1996-01-01

The nuclear industry has initiated a program of Steam Generator Degradation Specific Management (SGDSM) to cope with the various types of corrosion that have been observed in pressurized water reactor (PWR) steam generators. In parallel, the U.S. Nuclear Regulatory Commission is promulgating revised rules on steam generator tube integrity. To support these efforts, the Electric Power Research Institute has sponsored calculations with the MAAP 4 code. The principal objective of these calculations is to estimate the peak temperatures experienced by the steam generator tubes during high-pressure severe accidents. These results are used to evaluate the potential for degraded tubes to leak or rupture. Attention was focused on station blackout (SBO) accidents with loss of turbine-driven auxiliary feedwater because these generally result in the greatest threat to the tubes

Manufacture of the 300 MW steam generator and pressure stabilizer for Qinshan Nuclear Power Station

International Nuclear Information System (INIS)

Qian Yi; Miao Deming.

1989-01-01

A brief description of the manufacturing process of the steam generator and pressure stabilizer for 300 MWe Qinshan Nuclear Power Station in Shanghai Boiler Works is presented, with special emphasis on fabrication facilities, test procedures and technological evaluations during the manufaturing process-imcluding deep driling of tubesheets, welding of tubes to tube-sheets and tube rolling tests

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

International Nuclear Information System (INIS)

Onishi, Akiyoshi

1983-01-01

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

General Analysis of System Efficiency in Application of Combined Power Plants for Gas-Distribution Station

Directory of Open Access Journals (Sweden)

A. D. Kachan

2004-01-01

Full Text Available The paper proposes utilization of discharged heat of gas-piston engine (GPE or contact steam-gas plants (SGP with the purpose to heat up gas at gas-distribution stations (GDS of combined power plants with turbine and gas-expansion units. Calculations prove significant economic efficiency of the proposed variant in comparison with the application of ordinary gas- turbine units. Technical and economic calculation is used to determine gas-piston engine or contact steam-gas plant power for specific operational conditions of gas-distribution stations and utilization rate of discharged heat.

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

International Nuclear Information System (INIS)

1980-08-01

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

Development of the APR1400 model for countercurrent natural circulation in hot leg and steam generator under station blackout

International Nuclear Information System (INIS)

Park, Sang Gil; Kim, Han Chul

2012-01-01

In order to analyze severe accident phenomena, Korea Institute of Nuclear Safety (KINS) made a MELCOR model for APR1400 to examine natural circulation and creep rupture failure in the Reactor Coolant System (RCS) under station blackout (SBO). In this study, we are trying to advance the former model to describe natural circulation more accurately. After Fukushima accident, the concerns of severe accident management, assuring the heat removal capability, has risen for the case when the SBO is happened and there are no more electric powers to cool down decay heat. Under SBO there are three kinds of natural circulation which can delay the core heatup. One is in vessel natural circulation in the upper plenum of reactor vessel and the second is countercurrent natural circulation in hot leg through steam generator tubes and the last is full loop natural circulation when the reactor coolant pump loop seal is cleared and reactor coolant pump sealing is damaged by high temperature and high pressure. Among them this study focuses on the countercurrent natural circulation model using MELCOR1.8.6

Completion of latest ABWR 'SHIKA Unit 2' construction

International Nuclear Information System (INIS)

Yamazaki, Tatsuhiro; Yoshimoto, Yuichiro

2007-01-01

The Shika Nuclear Power Station Unit No.2 of the Hokuriku Electric Power Company, Inc. is the first Advanced BWR unit built in Japan by a single contractor and it is among the largest nuclear power stations in Japan. Its construction started in August 1999 when the first construction permit was issued. The design and construction of the plant was carried out with utmost care for betterment of operational safety, reliability and economy. The construction advanced on schedule and the plant entered its commercial operation in March 2006 as planned. Hitachi, Ltd. supplied the entire plant from design, fabrication and construction including the reactor and steam turbine generation system. In the design and construction of the plant, the most advanced technology has been applied in order to match the civil construction process and aim to supply safest, reliable and economical power plant. (author)

Operation of Grand Gulf Nuclear Station, Units 1 and 2, Dockets Nos. 50-416 and 50-417: Mississippi Power and Light Company, Middle South Energy, Inc., South Mississippi Electric Power Association. Final environmental statement

International Nuclear Information System (INIS)

1981-09-01

The information in this Final Environmental Statement is the second assessment of the environmental impacts associated with the construction and operation of the Grand Gulf Nuclear Station, Units 1 and 2, located on the Mississippi River in Claiborne County, Mississippi. The Draft Environmental Statement was issued in May 1981. The first assessment was the Final Environmental Statement related to construction, which was issued in August 1973 prior to issuance of the Grand Gulf Nuclear Station construction permits. In September 1981 Grand Gulf Unit 1 was 92% complete and Unit 2 was 22% complete. Fuel loading for Unit 1 is scheduled for December 1981. The present assessment is the result of the NRC staff review of the activities associated with the proposed operation of the Station, and includes the staff responses to comments on the Draft Environmental Statement

Electric utilities deregulation and its impact on nuclear power generating stations

International Nuclear Information System (INIS)

Trehan, N.K.

1998-01-01

Under restructuring and deregulation, it is not clear as to who would have the responsibility, and what obligations the market participants would have to ensure that the electrical system reliability (stability) is maintained. Due to the dynamic nature of the electrical grid, especially with the implementation of restructuring and deregulation, vulnerabilities exist which may impact the reliability (stability) of the offsite electrical power system. In a nuclear power generating unit, an offsite electric power system and an onsite electric power system are required to permit the functioning of structures, systems, and components which are important to safety. The safety function for each system is to provide sufficient capacity and capability to assure that the containment integrity is maintained during power operation or in the event of a postulated accident. Analyses performed by the applicants must verify that the electrical grid remains stable in the event of a loss of the nuclear unit generator, the largest other unit on the grid or the most critical transmission line. The stability of the electric grid is assumed in the safety analyses and a change in it would impact those analyses. However, it may impact the availability of a stable electric power to the safety buses because of the limited number of available transmission lines. This paper discusses electrical power generation and demand, reserve margins, power transfer capability, development of new innovative technologies to compensate for lack of the construction of transmission lines, legislation for the formulation of a self regulation organization (SRO), grid disturbances that may lead to a voltage collapse, and the vulnerabilities which may impact the availability of a stable power to the nuclear power generating stations

Nuclear Regulatory Commission issuances. Volume 17, No. 3

International Nuclear Information System (INIS)

1983-03-01

This report contains the Issuances received during March 1983 from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors Decisions (DD), and the Denials of Petition for Rulemaking (DPRM). The Issuances concerned the following facilities: Three Mile Island Nuclear Station, Unit No. 1; Comanche Peak Steam Electric Station, Units 1 and 2; Vallecitos Nuclear Center; Floating Nuclear Power Plants; San Onofre Nuclear Generating Station, Units 2 and 3; Point Beach Nuclear Plant, Unit 1; Perry Nuclear Power Plant, Units 1 and 2; Shoreham Nuclear Power Station, Unit 1; Western New York Nuclear Service Center; Limerick Generating Station, Units 1 and 2; Seabrook Station, Units 1 and 2; Black Fox Station, Units 1 and 2; WmH Zimmer Nuclear Power Station, Unit 1; WPPSS Nuclear Project No. 1; Zion Nuclear Plant, Units 1 and 2; and South Texas Project, Units 1 and 2

Ecotaxes and their impact in the cost of steam and electric energy generated by a steam turbine system

International Nuclear Information System (INIS)

Montero, Gisela

2006-01-01

Ecotaxes allow the internalization of costs that are considered externalities associated with polluting industrial process emissions to the atmosphere. In this paper, ecotaxes internalize polluting emissions negative impacts that are added to electricity and steam generated costs of a steam turbine and heat recovery systems from a utilities refinery plant. Steam costs were calculated by means of an exergy analysis tool and Aspen Plus simulation models. Ecotaxes were calculated for specific substances emitted in the refinery flue gases, based on a toxicity and pollution scale. Ecotaxes were generated from a model that includes damages produced to biotic and abiotic resources and considers the relative position of those substances in a toxicity and pollution scale. These ecotaxes were internalized by an exergoeconomic analysis resulting in an increase in the cost per kWh produced. This kind of ecotax is not applied in Mexico. The values of ecotaxes used in the cost determination are referred to the values currently applied by some European countries to nitrogen oxides emissions. (author)

Newman Unit 1 advanced solar repowering advanced conceptual design. Final report

Energy Technology Data Exchange (ETDEWEB)

None

1982-04-01

The Newman Unit 1 solar repowering design is a water/steam central receiver concept supplying superheated steam. The work reported is to develop a refined baseline conceptual design that has potential for construction and operation by 1986, makes use of existing solar thermal technology, and provides the best economics for this application. Trade studies performed in the design effort are described, both for the conceptual design of the overall system and for the subsystem conceptual design. System-level functional requirements, design, operation, performance, cost, safety, environmental, institutional, and regulatory considerations are described. Subsystems described include the collector, receiver, fossil energy, electrical power generating, and master control subsystems, site and site facilities. The conceptual design, cost, and performance of each subsystem is discussed at length. A detailed economic analysis of the repowered unit is made to realistically assess the economics of the first repowered unit using present cost data for a limited production level for solar hardware. Finally, a development plan is given, including the design, procurement, construction, checkout, startup, performance validation, and commercial operation. (LEW)

Electrical engineer's reference book

CERN Document Server

Laughton, M A

1985-01-01

Electrical Engineer's Reference Book, Fourteenth Edition focuses on electrical engineering. The book first discusses units, mathematics, and physical quantities, including the international unit system, physical properties, and electricity. The text also looks at network and control systems analysis. The book examines materials used in electrical engineering. Topics include conducting materials, superconductors, silicon, insulating materials, electrical steels, and soft irons and relay steels. The text underscores electrical metrology and instrumentation, steam-generating plants, turbines

Antenna unit and radio base station therewith

Science.gov (United States)

Kuwahara, Mikio; Doi, Nobukazu; Suzuki, Toshiro; Ishida, Yuji; Inoue, Takashi; Niida, Sumaru

2007-04-10

Phase and amplitude deviations, which are generated, for example, by cables connecting an array antenna of a CDMA base station and the base station, are calibrated in the baseband. The base station comprises: an antenna apparatus 1; couplers 2; an RF unit 3 that converts a receive signal to a baseband signal, converts a transmit signal to a radio frequency, and performs power control; an A/D converter 4 for converting a receive signal to a digital signal; a receive beam form unit 6 that multiplies the receive signal by semi-fixed weight; a despreader 7 for this signal input; a time-space demodulator 8 for demodulating user data; a despreader 9 for probe signal; a space modulator 14 for user data; a spreader 13 for user signal; a channel combiner 12; a Tx calibrater 11 for controlling calibration of a signal; a D/A converter 10; a unit 16 for calculation of correlation matrix for generating a probe signal used for controlling an Rx calibration system and a TX calibration system; a spreader 17 for probe signal; a power control unit 18; a D/A converter 19; an RF unit 20 for probe signal; an A/D converter 21 for signal from the couplers 2; and a despreader 22.

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

DEFF Research Database (Denmark)

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

2017-01-01

Electric vehicles (EVs) are becoming a key feature of smart grids. EVs will be embedded in the smart grids as a mobile load-storage with probabilistic behavior. In order to manage EVs as flexible loads, charging stations (CSs) have essential roles. In this paper, a new method for optimal sitting...... are considered based on time-of-use (TOU) demand response programs (DRPs). In order to solve the optimization problem considering uncertainty of load growth, electricity price, initial state of charge of batteries and solar power generation, genetic algorithm method using Monte-Carlo simulation is used...

A process for superheating steam in a nuclear power station circuit and device for putting in operation this process

International Nuclear Information System (INIS)

Monteil, Marcel; Forestier, Jean; Leblanc, Bernard; Monteil, Pierre

1975-01-01

A process is described for superheating steam in a nuclear power station circuit, comprising a turbine with a high pressure chamber and a low pressure chamber. It consists in superheating the steam between the high and low pressure chambers of the turbine by using as heating fluid water under pressure at vaporisation temperature, directly taken from the recirculation or circulation flow water of the reactor or of the steam generators. The process is adapted to a pressurised water reactor using a once-through steam generator comprising in succession an economiser, a vaporiser and a superheater, the superheating water being taken at the vaporiser intake. It is also adapted for a boiling water reactor, in that the water is taken directly from the reactor vessel and at a suitable level in the recirculation water [fr

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

International Nuclear Information System (INIS)

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

1989-01-01

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

Drying system for steam generators, particularly for steam generators of nuclear power stations

International Nuclear Information System (INIS)

Lavalerie, Claude; Borrel, Christian.

1982-01-01

A drying system is described which allows for modular construction and which provides a significant available exchange area in a reduced volume. All the drying elements are identical and are distributed according to a ternay circular symmetry and are placed radially and associated to steam guiding facilities which alternately provide around the axis of revolution an output volume of dry steam from one element and an input volume of wet steam in the following element [fr

Technical specifications: McGuire Nuclear Station, Unit Nos. 1 and 2. Docket Nos. 50-369 and 50-370

International Nuclear Information System (INIS)

Anderson, F.

1983-03-01

Information is presented concerning safety limits for operation; control systems; power distribution limits; instrumentation; primary coolant circuit; emergency core cooling systems; containment systems; steam turbines and secondary coolant circuits; electrical equipment; refueling operations; radioactive effluents; and reactor site

Twenty-five-year study of radionuclides in the Susquehanna river via periphyton biomonitors.

Science.gov (United States)

Patrick, Ruth; Palms, John; Kreeger, Danielle; Harris, Charles

2007-01-01

This 25-y study monitored aquatic and terrestrial gamma-ray-emitting radionuclide levels near a nuclear power plant. It is the only known, long-term environmental survey of its kind. It was conducted neither by a utility owner, nor by a government agency, but rather by a private, environmental research institution. Compared to dozens of other flora and fauna, periphyton was found to be the best indicator to biomonitor the Susquehanna River, which runs near PPL Susquehanna's nuclear plant. Sampling began in 1979 before the first plant start-up and continued for the next 24 years. Monitoring began two months after the Three Mile Island accident of 28 March 1979 and includes Three Mile Island area measurements. Ongoing measurements detected fallout from Chernobyl in 1986, as well as I not released from PPL Susquehanna. Although this paper concentrates on radionuclides found in periphyton, the scope of the entire environmental program includes a wide variety of aquatic and land-based plants, animals, and inorganic matter. Other species and matter studied were fish, mussels, snails, crayfish, insects, humus, mushrooms, lichens, squirrels, deer, cabbage, tomatoes, coarse and flocculated sediment, and more. Results show periphyton works well for detection of radionuclide activity, even in concentrations less than 100 Bq kg (picocuries per gram amounts). Data indicate that PPL Susquehanna's radionuclide releases have had no known environmental or human health impact.

Cost management in a nuclear operating environment

International Nuclear Information System (INIS)

Steckel, J.K.; Gruber, C.O.

1985-01-01

This paper presents an integrated philosophy and program for managing costs in a nuclear operating environment. The ideas presented here are being used by Pennsyvania Power and Light Company (PPandL) at the Susquehanna Steam Electric Station. Three basic ideas necessary to successful cost management are listed and include: recognize the framework that is needed to ''manage'': treat cost as part of an integrated plan; and apply different techniques to different types of work activities. It is the author's opinion that the technical framework of a successful cost management system must include all work activities but recognize types. Project activities should be managed to a defined scope and authorized cost using a well communicated estimating program, aggressive trending and forecasting, and a change identification process

Heat balance calculation and feasibility analysis for initial startup of Fuqing nuclear turbine unit with non-nuclear steam

International Nuclear Information System (INIS)

He Liu; Xiao Bo; Song Yumeng

2014-01-01

Non-nuclear steam run up compared with nuclear steam run up, can verify the design, manufacture, installation quality of the unit, at the same time shorten the follow-up duration of the entire group ready to start debugging time. In this paper, starting from the first law of thermodynamics, Analyzed Heat balance Calculation and Feasibility analysis for Initial startup of Fuqing nuclear Turbine unit with Non-nuclear steam, By the above calculation, to the system requirements and device status on the basis of technical specifications, confirmed the feasibility of Non-nuclear steam running up in theory. After the implementation of the Non-nuclear turn of Fuqing unit, confirmed the results fit with the actual process. In summary, the Initial startup of Fuqing turbine unit with Non-nuclear steam is feasible. (authors)

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

International Nuclear Information System (INIS)

1975-01-01

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

Poultry litter power station in the United Kingdom

International Nuclear Information System (INIS)

Anon.

1995-01-01

Poultry litter has presented a waste disposal problem to the poultry industry in many parts of the United Kingdom. The plant at Eye is a small to medium scale power station, fired using poultry litter. The 12.7 MW of electricity generated is supplied, through the local utility, to the National Grid. The spent litter that constitutes the fuel is made up of excrement and animal bedding (usually 90% excrement and 10% straw or wood shavings). It comes from large climate-controlled buildings (broiler houses) where birds, reared for meat production, are allowed to roam freely. (UK)

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

Energy Technology Data Exchange (ETDEWEB)

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

2015-07-01

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

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

International Nuclear Information System (INIS)

Martins, Carlos F.O.; Crepaldi, Roberto; Freire, Enio M.; Campello, Sergio A.

2015-01-01

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

Design and development of electric vehicle charging station equipped with RFID

Science.gov (United States)

Panatarani, C.; Murtaddo, D.; Maulana, D. W.; Irawan, S.; Joni, I. M.

2016-02-01

This paper reports the development of electric charging station from distributed renewable for electric vehicle (EV). This designed refer to the input voltage standard of IEC 61851, plugs features of IEC 62196 and standard communication of ISO 15118. The developed electric charging station used microcontroller ATMEGA8535 and RFID as controller and identifier of the EV users, respectively. The charging station successfully developed as desired features for electric vehicle from renewable energy resources grid with solar panel, wind power and batteries storage.

A Cryogenic Test Station for the Pre-series 2400 W @ 1.8 K Refrigeration Units for the LHC

CERN Document Server

Claudet, S; Gully, P; Jäger, B; Millet, F; Roussel, P; Tavian, L

2002-01-01

The cooling capacity below 2 K for the superconducting magnets in the Large Hadron Collider (LHC), at CERN, will be provided by eight refrigeration units at 1.8 K, each of them coupled to a 4.5 K refrigerator. The supply of the series units is linked to successful testing and acceptance of the pre-series delivered by the two selected vendors. To properly assess the performance of specific components such as cold compressors and some process specificities a dedicated test station is necessary. The test station is able to process up to 130 g/s between 4.5 & 20 K and aims at simulating the steady and transient operational modes foreseen for the LHC. After recalling the basic characteristics of the 1.8 K refrigeration units and the content of the acceptance tests of the pre-series, the principle of the test cryostat is detailed. The components of the test station and corresponding layout are described. The first testing experience is presented as well as preliminary results of the pre-series units.

Probabilistic fire risk assessment for Koeberg Nuclear Power Station Unit 1

International Nuclear Information System (INIS)

Grobbelaar, J.F.; Foster, N.A.S.; Luesse, L.J.

1995-01-01

A probabilistic fire risk assessment was done for Koeberg Nuclear Power Station Unit 1. Areas where fires are likely to start were identified. Equipment important to safety, as well as their power and/or control cable routes were identified in each fire confinement sector. Fire confinement sectors where internal initiating events could be caused by fire were identified. Detection failure and suppression failure fault trees and event trees were constructed. The core damage frequency associated with each fire confinement sector was calculated, and important fire confinement sectors were identified. (author)

Reducing lighting electricity use in underground metro stations

International Nuclear Information System (INIS)

Casals, Miquel; Gangolells, Marta; Forcada, Núria; Macarulla, Marcel

2016-01-01

Highlights: • Lighting systems are big energy consumers in underground metro stations. • An adaptive lighting system strategy is developed for underground stations. • Dimming controls are based on station occupancy levels and maintenance cycles. • The k-means clustering technique is used to identify stations’ occupancy patterns. • Savings were found to amount to 255.47 MW h in 2 years for a case study metro network. - Abstract: Lighting systems are usually one of the largest electrical end-uses in underground metro stations. Taking into account that budget restrictions in publicly owned companies hinder energy efficiency retrofit projects that require high initial investments, affordable energy saving strategies are needed. This paper presents a low-cost approach for reducing lighting electricity use in underground stations, without affecting passengers’ comfort or the metro operator’s service. For this purpose, an adaptive lighting strategy of dimming the illuminance levels of artificial light sources has been developed. Dimming controls are based on the occupancy of the station, and the preventive maintenance and cleaning cycles of the luminaires. The stations’ monthly occupancy patterns are defined through the k-means clustering technique. To illustrate its effectiveness, the method was applied to 115 underground stations of the Barcelona metro network. The results revealed overall electricity savings of 255.47 MW h on a biannual basis, which represents 36.22% of the stations’ baseline lighting consumption. Individual energy savings were found to range from 25 to 87.5 MW h/year in the stations of the Barcelona metro network, depending on the number and profile of station users. The research findings will undoubtedly be useful for the future energy efficiency project plans of worldwide metro operators and managers of other underground spaces.

Steam turbine cycle

International Nuclear Information System (INIS)

Okuzumi, Naoaki.

1994-01-01

In a steam turbine cycle, steams exhausted from the turbine are extracted, and they are connected to a steam sucking pipe of a steam injector, and a discharge pipe of the steam injector is connected to an inlet of a water turbine. High pressure discharge water is obtained from low pressure steams by utilizing a pressurizing performance of the steam injector and the water turbine is rotated by the high pressure water to generate electric power. This recover and reutilize discharged heat of the steam turbine effectively, thereby enabling to improve heat efficiency of the steam turbine cycle. (T.M.)

Graphite-water steam-generating reactor in the USSR

Energy Technology Data Exchange (ETDEWEB)

Dollezhal, N A [AN SSSR, Moscow

1981-10-01

One of the types of power reactor used in the USSR is the graphite-water steam-generating reactor RBMK. This produces saturated steam at a pressure of 7MPa. Reactors giving 1GWe each have been installed at the Leningrad, Kursk, Chernobyl and other power stations. Further stations using reactors of this type are being built. A description is given of the fuel element design, and of the layout of the plant. The main characteristics of RBMK reactors using fuel of rated and higher enrichment are listed.

LPGC, Levelized Steam Electric Power Generator Cost

International Nuclear Information System (INIS)

Coen, J.J.; Delene, J.G.

1994-01-01

1 - Description of program or function: LPGC is a set of nine microcomputer programs for estimating power generation costs for large steam-electric power plants. These programs permit rapid evaluation using various sets of economic and technical ground rules. The levelized power generation costs calculated may be used to compare the relative economics of nuclear and coal-fired plants based on life-cycle costs. Cost calculations include capital investment cost, operation and maintenance cost, fuel cycle cost, decommissioning cost, and total levelized power generation cost. These programs can be used for quick analyses of power generation costs using alternative economic parameters, such as interest rate, escalation rate, inflation rate, plant lead times, capacity factor, fuel prices, etc. The two major types of electric generating plants considered are pressurized-water reactor (PWR) and pulverized coal-fired plants. Data are also provided for the Large Scale Prototype Breeder (LSPB) type liquid metal reactor. Costs for plant having either one or two units may be obtained. 2 - Method of solution: LPGC consists of nine individual menu-driven programs controlled by a driver program, MAINPWR. The individual programs are PLANTCAP, for calculating capital investment costs; NUCLOM, for determining operation and maintenance (O and M) costs for nuclear plants; COALOM, for computing O and M costs for coal-fired plants; NFUEL, for calculating levelized fuel costs for nuclear plants; COALCOST, for determining levelized fuel costs for coal-fired plants; FCRATE, for computing the fixed charge rate on the capital investment; LEVEL, for calculating levelized power generation costs; CAPITAL, for determining capitalized cost from overnight cost; and MASSGEN, for generating, deleting, or changing fuel cycle mass balance data for use with NFUEL. LPGC has three modes of operation. In the first, each individual code can be executed independently to determine one aspect of the total

Application of a steam injector for passive emergency core cooling during a station blackout

International Nuclear Information System (INIS)

Heinze, D.; Behnke, L.; Schulenberg, T.

2012-01-01

One of the basic protection targets of reactor safety is the safe heat removal during normal operation but also following shut-down. Since the reactor accident in Fukushima an optimization of the plant robustness in case of beyond-design accident is performed. Special attention is given to the increase of time available for starting appropriate measures for emergency core cooling in case of a station blackout. The state-of the art in engineering and research is presented. Investigations on the applicability of a steam injector for passive emergency core cooling during a station blackout in BWR-type reactors have progressed, experiments on dynamic behavior of the injector are described. A precise design with respect to the thermal hydraulic boundary conditions has been performed.

Station blackout transient at the Browns Ferry Unit 1 Plant: a severe accident sequence analysis (SASA) program study

International Nuclear Information System (INIS)

Schultz, R.R.

1982-01-01

Operating plant transients are of great interest for many reasons, not the least of which is the potential for a mild transient to degenerate to a severe transient yielding core damage. Using the Browns Ferry (BF) Unit-1 plant as a basis of study, the station blackout sequence was investigated by the Severe Accident Sequence Analysis (SASA) Program in support of the Nuclear Regulatory Commission's Unresolved Safety Issue A-44: Station Blackout. A station blackout transient occurs when the plant's AC power from a comemrcial power grid is lost and cannot be restored by the diesel generators. Under normal operating conditions, f a loss of offsite power (LOSP) occurs [i.e., a complete severance of the BF plants from the Tennessee Valley Authority (TVA) power grid], the eight diesel generators at the three BF units would quickly start and power the emergency AC buses. Of the eight diesel generators, only six are needed to safely shut down all three units. Examination of BF-specific data show that LOSP frequency is low at Unit 1. The station blackout frequency is even lower (5.7 x 10 - 4 events per year) and hinges on whether the diesel generators start. The frequency of diesel generator failure is dictated in large measure by the emergency equipment cooling water (EECW) system that cools the diesel generators

The Trencin water power station

International Nuclear Information System (INIS)

2005-01-01

This leaflet describes the Trencin water power station. The Trencin water power station was built seven years after the Dubnica nad Vahom water power station started its operation and was the last stage of the first and the oldest derived cascade of water power stations on the Vah River. After completing water power stations at Ladce (1936), Ilava (1946) and Dubnica nad Vahom (1949) and before constructing the Trencin water power station, the whole second derived cascade of water power stations including water power stations at Kostolna, Nove Mesto nad Vahom and Horna Streda was built as soon as possible mainly because the need to get compensation for discontinued electricity supplies as well as energetic coal from the Czech Republic. Hereby, experiences from the construction of previous grades were used, mainly as far as the dimensioning was concerned, as the fi rst installed power stations had, in comparison with the growing requirements on the electricity supplies, very low absorption capacity - only 150 m 3 .s -1 . Thus the Trencin power station (original name was the Skalka power station) was already dimensioned for the same absorption capacity as the cascade located downstream the river, that is 180 m 3 .s -1 . That was related also to growing demands on electricity supplies during the peaks in the daily electric system load diagram, and thus to the transfer from continuous operation of the water power station to semi-peak or even peak performance. According to the standards of power station classification, the Trencin water power station is a medium size, low pressure, channel power station with two units equipped by Kaplan turbines and synchronous hydro-alternators. The water power station installed capacity is 16.1 MW in total and its designed annual production of electrical energy for medium water year is 85,000 MWh, while the average annual production during the last 30 years is 86,252 MWh. Installed unit has a four-blade Kaplan turbine with the diameter

Power station instrumentation

International Nuclear Information System (INIS)

Jervis, M.W.

1993-01-01

Power stations are characterized by a wide variety of mechanical and electrical plant operating with structures, liquids and gases working at high pressures and temperatures and with large mass flows. The voltages and currents are also the highest that occur in most industries. In order to achieve maximum economy, the plant is operated with relatively small margins from conditions that can cause rapid plant damage, safety implications, and very high financial penalties. In common with other process industries, power stations depend heavily on control and instrumentation. These systems have become particularly significant, in the cost-conscious privatized environment, for providing the means to implement the automation implicit in maintaining safety standards, improving generation efficiency and reducing operating manpower costs. This book is for professional instrumentation engineers who need to known about their use in power stations and power station engineers requiring information about the principles and choice of instrumentation available. There are 8 chapters; chapter 4 on instrumentation for nuclear steam supply systems is indexed separately. (Author)

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

International Nuclear Information System (INIS)

1986-02-01

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

Electric Vehicle Charging Stations as a Climate Change Mitigation Strategy

Science.gov (United States)

Cave, Bridget; DeYoung, Russell J.

2014-01-01

In order to facilitate the use of electric vehicles at NASA Langley Research Center (LaRC), charging stations should be made available to LaRC employees. The implementation of charging stations would decrease the need for gasoline thus decreasing CO2 emissions improving local air quality and providing a cost savings for LaRC employees. A charging station pilot program is described that would install stations as the need increased and also presents a business model that pays for the electricity used and installation at no cost to the government.

Draft Environmental Statement related to the operation of Vogtle Electric Generating Plant, Units 1 and 2 (Docket Nos. 50-424 and 50-425)

International Nuclear Information System (INIS)

1984-10-01

This Draft Environmental Statement contains an assessment of the environmental impact associated with the operation of the Vogtle Electric Generating Plant, Units 1 and 2, pursuant to the National Environmental Policy Act of 1969 (NEPA) and Title 10 of the Code of Federal Regulations, part 51 (10 CFR 51), as amended, of the Nuclear Regulatory Commission regulations. This statement examines the environmental impacts, environmental consequences and mitigating actions, and environmental and economic benefits and costs associated with station operation

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

International Nuclear Information System (INIS)

1977-10-01

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

Experimental research of variable rotation speed ICE-based electric power station

Directory of Open Access Journals (Sweden)

Dar’enkov Andrey

2017-01-01

Full Text Available Developing variable rotation speed ICE-based stand-alone electric power stations which can supply distant regions and autonomous objects with electricity are of scientific interest due to the insufficient study. The relevance of developing such electric power stations is determined by their usage is to provide a significant fuel saving as well as increase ICE motor service life. The article describes the electric station of autonomous objects with improved fuel economy. The article describes multivariate characteristic. Multivariate characteristic shows the optimal frequency of rotation of the internal combustion engine. At this rotational speed there is the greatest fuel economy.

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

International Nuclear Information System (INIS)

1987-01-01

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

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

International Nuclear Information System (INIS)

1983-07-01

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

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

International Nuclear Information System (INIS)

1983-09-01

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

Electric machinery and drives in thermal power stations. Elektrische Maschinen und Antriebe in thermischen Kraftwerken

Energy Technology Data Exchange (ETDEWEB)

1974-01-01

The following subjects were dealt with during the VDE meeting: 1) Requirements made by the electric network on the generators and their excitation equipment, and the influence thereof on their design; 2) requirements made by the power station process on the electric drives and the influence thereof on type and design; 3) requirements made on protective measures from the point of the electric power station machinery.

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

International Nuclear Information System (INIS)

Ellis, R.J.

2000-01-01

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

Environmental management at the Grand Rapids Generating Station following the Unit No.1 headcover failure

International Nuclear Information System (INIS)

Windsor, D.C.

1993-01-01

Failure of the headcover of Unit 1 in the Grand Rapids generating station in March, 1992 caused the station to flood, releasing several thousand gallons of oil and removing the station from service for several weeks. Environmental considerations were a considerable part of the station restoration activities, reservoir and flow management programs and responses to public concerns arising from the accident. A major oil spill containment and cleanup program was undertaken, with station cleanup and debris disposal carried out in a manner acceptable to environmental authorities. Reservoir spillage was necessitated by the station shutdown. The spill recreated fish habitat in the spillway and walleye spawning were documented. A compensation program was developed to respond to problems caused by debris flushed from the spillway channel. On spill termination, a fish salvage program removed fish from a scour hole in the spillway channel. A proactive program of public information provided local residents with the facts about the incident and response program, and allayed concerns about public safety. 4 refs., 2 figs