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Sample records for docket nos 50-352

  1. 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

  2. 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

  3. 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

  4. 76 FR 54259 - Virginia Electric and Power Company, Docket Nos. 50-338 and 50-339, North Anna Power Station...

    Science.gov (United States)

    2011-08-31

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

  5. 76 FR 52992 - Notice of Acceptance for Docketing of the Application and Notice of Opportunity for Hearing...

    Science.gov (United States)

    2011-08-24

    ... NUCLEAR REGULATORY COMMISSION [NRC-2011-0166; Docket Numbers 50-352 and 50-353] Notice of Acceptance for Docketing of the Application and Notice of Opportunity for Hearing Regarding Renewal of Facility Operating License Nos. NPF-39 and NPF-85 for an Additional 20-Year Period, Exelon Generation Company, LLC, Limerick Generating Station The U.S....

  6. Safety Evaluation Report related to the operation of Diablo Canyon Nuclear Power Plant, Units 1 and 2 (Docket Nos. 50-275 and 50-323)

    International Nuclear Information System (INIS)

    1991-06-01

    Supplement 34 to the Safety Evaluation Report for the application by Pacific Gas and Electric Company (PG ampersand E) for licenses to operate Diablo Canyon Nuclear Power Plant, Unit Nos. 1 and 2 (Docket Nos. 50-275 and 50-323, respectively) has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement documents the NRC staff review of the Long-Term Seismic Program conducted by PG ampersand E in response to License Condition 2.C.(7) of Facility Operating License DPR-80, the Diablo Canyon Unit 1 operating license. 111 refs., 20 figs., 31 tabs

  7. Safety evaluation report related to the operation of Braidwood Station, Units 1 and 2 (Docket Nos. 50-456 and 50-457)

    International Nuclear Information System (INIS)

    1983-11-01

    The Safety Evaluation Report for the application filed by the Commonwealth Edison Company, as applicant and owner, for a license to operate Braidwood Station, Units 1 and 2 (Docket Nos. STN 50-456 and STN 50-457), has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located in Reed Township, Will County, Illinois. Subject to favorable resolution of the items discussed in this report, the staff concludes that the facility can be operated by the applicant without endangering the health and safety of the public

  8. Safety evaluation report related to the operation of Midland Plant, Units 1 and 2. Docket Nos. 50-329 and 50-330. Consumers Power Company

    International Nuclear Information System (INIS)

    1982-06-01

    This report supplements the Safety Evaluation Report, NUREG-0793, issued with respect to the application filed for licenses to operate the Midland Plant, Units 1 and 2 (Docket Nos. 50-329 and 50-330). This supplement provides recent information regarding resolution of some of the open items identified in the Safety Evaluation Report and discusses recommendations of the Advisory Committee on Reactor Safeguards in its interim report dated June 8, 1982

  9. Safety evaluation report related to the operation of Diablo Canyon Nuclear Power Plant, Units 1 and 2 (Docket Nos. 50-275 and 50-323)

    International Nuclear Information System (INIS)

    1984-06-01

    Supplement 23 to the Safety Evaluation Report for Pacific Gas and Electric Company's application for licenses to operate Diablo Canyon Nuclear Power Plants, Units 1 and 2 (Docket Nos. 50-275 and 50-323) has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement addresses the applicant's requests for approval of 22 deviations from the requirements of Section III.G of Appendix R of Title 10 of the Code of Federal Regulations Part 50

  10. Safety Evaluation Report related to the operation of Braidwood Station, Units 1 and 2 (Docket Nos. 50-456 and 50-457)

    International Nuclear Information System (INIS)

    1987-05-01

    In November 1983, the staff of the Nuclear Regulatory Commission issued its Safety Evaluation Report (NUREG-1002) regarding the application filed by the Commonwealth Edison Company, as applicant and owner, for a license to operate Braidwood Station, Units 1 and 2 (Docket Nos. 50-456 and 50-457). The first supplement to NUREG-1002 was issued in September 1986; the second supplement to NUREG-1002 was issued in October 1986. This third supplement to NUREG-1002 reports the status of certain items that remained unresolved at the time Supplement 2 was published. The facility is located in Reed Township, Will County, Illinois

  11. Safety Evaluation Report related to the operation of Diablo Canyon Nuclear Power Plant, Units 1 and 2 (Docket Nos. 50-275 and 50-323)

    International Nuclear Information System (INIS)

    1984-02-01

    Supplement 17 to the Safety Evaluation Report for Pacific Gas and Electric Company's application for licenses to operate Diablo Canyon Nuclear Power Plants, Units 1 and 2 (Docket Nos. 50-275 and 50-323) has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement reports the status of certain items that had not been resolved at the time of publication of the Safety Evaluation Report and the previous supplements

  12. Safety Evaluation Report related to the operation of Perry Nuclear Power Plant, Units 1 and 2, (Docket Nos. 50-440 and 50-441)

    International Nuclear Information System (INIS)

    1984-02-01

    Supplement No. 4 to the Safety Evaluation Report on the application filed by the Cleveland Electric Illuminating Company on behalf of itself and as agent for the Duquesne Light Company, the Ohio Edison Company, the Pennsylvania Power Company, and the Toledo Edison Company (the Central Area Power Coordination Group or CAPCO), as applicants and owners, for a license to operate the Perry Nuclear Power Plant, Units 1 and 2 (Docket Nos. 50-440 and 50-441), has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located in Lake County, Ohio. This supplement reports the status of certain issues that had not been resolved at the time of publication of the Safety Evaluation Report and Supplement Nos. 1, 2 and 3 to that report

  13. Safety Evaluation Report related to the operation of Braidwood Station, Units 1 and 2 (Docket Nos. 50-456 and 50-457). Supplement No. 1

    International Nuclear Information System (INIS)

    1986-09-01

    In November 1983 the staff of the Nuclear Regulatory Commission issued its Safety Evaluation Report (NUREG-1002) regarding the application filed by the Commonwealth Edison Company, as applicant and owner, for a license to operate Braidwood Station, Units 1 and 2 (Docket Nos. STN 50-456 and STN 50-457). The facility is located in Reed Township, Will County, Illinois. This first supplement to NUREG-1002 reports the status of certain items that remained unresolved at the time the Safety Evaluation Report was published

  14. Safety evaluation report related to the operation of Seabrook Station, Units 1 and 2 (Docket Nos. 50-443 and 50-444)

    International Nuclear Information System (INIS)

    1986-05-01

    This report is Supplement 4 to the Safety Evaluation Report (SER, NUREG-0896, March 1983) for the application filed by the Public Service Company of New Hampshire, et al., for licenses to operate Seabrook Station, Units 1 and 2 (Docket Nos. STN 50-443 and STN 50-444). It has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission and provides recent information on open items identified in the SER. The facility is located in Seabrook, New Hamphsire. Subject to favorable resolution of the items discussed in this report, the staff concludes that the facility can be operated by the applicant without endangering the health and safety of the public

  15. Safety evaluation report related to the operation of Seabrook Station, Units 1 and 2 (Docket Nos. 50-443 and 50-444)

    International Nuclear Information System (INIS)

    1987-10-01

    This report is Supplement No. 7 to the Safety Evaluation Report (NUREG-0896, March 1983) for the application filed by the Public Service Company of New Hampshire, et al. for licenses to operate Seabrook Station, Units 1 and 2 (Docket Nos. STN 50-443 and STN 50-444). It has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission and provides recent information on open items identified in the SER. The facility is located in Seabrook, New Hampshire. Subject to favorable resolution of the items discussed in this report, the staff concludes that the facility can be operated by the applicant without endangering the health and safety of the public

  16. Safety-evaluation report related to the operation of Seabrook Station, Units 1 and 2. Docket Nos. 50-443 and 50-444

    International Nuclear Information System (INIS)

    1983-06-01

    This report is Supplement 2 to the Safety Evaluation Report (NUREG-0896, March 1983) for the application filed by the Public Service Company of New Hampshire, et al., for licenses to operate Seabrook Station, Units 1 and 2 (Docket Nos. STN 50-443 and STN 50-444). It has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission and provides recent information on open items identified in the SER. The facility is located in Seabrook, New Hampshire. Subject to favorable resolution of the items discussed in this report, the staff concludes that the facility can be operated by the applicant without endangering the health and safety of the public

  17. Safety evaluation report related to the operation of Watts Bar Nuclear Plant, Units 1 and 2, Docket Nos. 50-390 and 50-391

    International Nuclear Information System (INIS)

    1992-01-01

    Supplement No. 8 to the Safety Evaluation Report for the application filed by the Tennessee Valley Authority for license to operate Watts Bar Nuclear plant, Units 1 and 2, Docket Nos. 50-390 and 50-391, located in Rhea County, Tennessee, 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 of (1) additional information submitted by the applicant since Supplement No. 7 was issued, and (2) matters that the staff had under review when Supplement No. 7 was issued

  18. Safety Evaluation Report related to the operation of Braidwood Station, Units 1 and 2 (Docket Nos. 50-456 and 50-457). Supplement No. 2

    International Nuclear Information System (INIS)

    1986-10-01

    In November 1983, the staff of the Nuclear Regulatory Commission issued its Safety Evaluation Report (NUREG-1002) regarding the application filed by the Commonwealth Edison Company, as applicant and owner, for a license to operate Braidwood Station, Units 1 and 2 (Docket Nos. 50-456 and 50-457). The first supplement to NUREG-1002 was issued in September 1986. This second supplement to NUREG-1002 reports the status of certain items that remained unresolved at the time Supplement 1 was published. The facility is located in Reed Township, Will County, Illinois

  19. Safety Evaluation Report related to the operation of Seabrook Station, Units 1 and 2 (Docket Nos. 50-443 and 50-444)

    International Nuclear Information System (INIS)

    1989-05-01

    This report is Supplement No. 8 to the Safety Evaluation Report (SER) (NUREG-0896, March 1983) for the application filed by the Public Service Company of New Hampshire, et al., for licenses to operate Seabrook Station, Units 1 and 2 (Docket Nos. STN 50-443 and STN 50-444). It has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission and provides recent information on open items identified in the SER. The facility is located in Seabrook, New Hampshire. Subject to favorable resolution of the items discussed in this report, the staff concludes that the facility can be operated by the applicant without endangering the health and safety of the public. 2 figs., 1 tab

  20. 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

  1. Safety evaluation report related to the operation of South Texas Project, Units 1 and 2 (Docket Nos. 50-498 and 50-499)

    International Nuclear Information System (INIS)

    1987-01-01

    In April 1986 staff of the Nuclear Regulatory Commission issued its Safety Evaluation Report (NUREG-0781) regarding the application of Houston Lighting and Power Company (applicant and agent for the owners) for a license to operate South Texas Project, Units 1 and 2 (Docket Nos. 50-498 and 50-499). The facility is located in Matagorda County, Texas, west of the Colorado River, 8 miles north-northwest of the town of Matagorda and about 89 miles southwest of Houston. The first supplement to NUREG-0781 was issued in September 1986. This second supplement reports on the status of unresolved items in the Safety Evaluation Report and identifies certain additional items that have since been reviewed by the staff

  2. Safety Evaluation Report 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)

    1987-03-01

    In June 1985, the staff of the Nuclear Regulatory Commission issued its Safety Evaluation Report (NUREG-1137) regarding the application of Georgia Power Company, Municipal Electric Authority of Georgia, Oglethorpe Power Corporation, and the City of Dalton, Georgia, for licenses to operate the Vogtle Electric Generating Plant, Units 1 and 2 (Docket Nos. 50-424 and 50-425). This sixth supplement of NUREG-1137 provides recent information regarding resolution of some of the open and confirmatory items that remained unresolved at the time the Safety Evaluation Report was issued. These areas are performance testing, reactor cooling hydraulics, loose parts monitoring, and electric power systems

  3. Safety evaluation report related to the operation of Midland Plant, Units 1 and 2. Docket Nos. 50-329 and 50-330, Consumers Power Company

    International Nuclear Information System (INIS)

    1982-05-01

    The Safety Evaluation Report for the application filed by the Consumers Power Company, as applicant and owner, for a license to operate the Midland Plant Units 1 and 2 (Docket Nos. 50-329 and 50-330), has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located near the city of Midland in Midland County, Michigan. Subject to favorable resolution of the items discussed in this report, the staff concludes that the facility can be operated by the applicant without endangering the health and safety of the public

  4. Safety evaluation report related to the operation of Perry Nuclear Power Plant, Units 1 and 2. Docket Nos. 50-440 and 50-441

    International Nuclear Information System (INIS)

    1983-04-01

    Supplement No. 3 to the Safety Evaluation Report on the application filed by the Cleveland Electric Illuminating Company on behalf of itself and as agent for the Duquesne Light Company, the Ohio Edison Company, the Pennsylvania Power Company, and the Toledo Edison Company (the Central Area Power Coordination Group or CAPCO), as applicants and owners, for a license to operate the Perry Nuclear Power Plant, Units 1 and 2 (Docket Nos. 50-440/441), has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located in Lake County, Ohio. This supplement reports the status of certain issues that had not been resolved at the time of publication of the Safety Evaluation Report and Supplement Nos. 1 and 2 to that report

  5. 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

  6. Safety Evaluation Report 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)

    1985-06-01

    The Safety Evaluation Report for the application filed by Georgia Power Company, Municipal Electric Authority of Georgia, Oglethorpe Power Corporation, and City of Dalton, Georgia, as applicants and owners, for licenses to operate the Vogtle Electric Generating Plant, Units 1 and 2 (Docket Nos. 50-424 and 50-425), has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located in Burke County, Georgia, approximately 41.5 km (26 mi) south-southeast of Augusta, and on the Savannah River. Subject to favorable resolution of the items discussed in this report, the staff concludes that the applicant can operate the facility without endangering the health and safety of the public

  7. Safety evaluation report related to the operation of Seabrook Station, Units 1 and 2. Docket Nos. 50-443 and 50-444. Suppl. 1

    International Nuclear Information System (INIS)

    1983-04-01

    This report supplements the Safety Evaluation Report (NUREG-0896, March 1983) for the application filed by the Public Service Company of New Hampshire, et. al., for licenses to operate Seabrook Station, Units 1 and 2 (Docket Nos. STN 50-443 and STN 50-444). It has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission and provides recent information on open items identified in the SER. The facility is located in Seabrook, New Hampshire. Subject to favorable resolution of the items discussed in this report, the staff concludes that the facility can be operated by the applicant without endangering the health and safety of the public

  8. Safety evaluation report related to the operation of Vogtle Electric Generating Plant, Units 1 and 2 (Docket Nos. 50-424 and 50-425)

    International Nuclear Information System (INIS)

    1988-01-01

    In June 1985, the staff of the Nuclear Regulatory Commission issued its Safety Evaluation Report (NUREG-1137) regarding the application of Georgia Power Company, Municipal Electric Authority of Georgia, Oglethorpe Power Corporation, and the City of Dalton, Georgia, for licenses to operate Vogtle Electric Generating Plant, Units 1 and 2 (Docket Nos. 50-424 and 50-425). The facility is located in Burke County, Georgia, approximately 26 miles south-southeast of Augusta, Georgia, and on the Savannah River. This seventh supplement to NUREG-1137 provides recent information regarding resolution of some of the open and confirmatory items that remained unresolved following issuance of Supplement 6, and documents completion of several Unit 1 license conditions

  9. Safety Evaluation report related to the operation of Braidwood Station, Units 1 and 2 (Docket Nos. STN 50-456 and STN 50-457)

    International Nuclear Information System (INIS)

    1987-07-01

    In November 1983, the staff of the Nuclear Regulatory Commission issued its Safety Evaluation Report (NUREG-1002) regarding the application filed by the Commonwealth Edison Company, as applicant and owner, for a license to operate Braidwood Station, Units 1 and 2 (Docket Nos. 50-456 and 50-457). The first supplement to NUREG-1002 was issued in September 1986; the second supplement to NUREG-1002 was issued in October 1986; the third supplement to NUREG-1002 was issued in May 1987. This fourth supplement to NUREG-1002 reports the status of certain items that remained unresolved at the time Supplement 3 was published. The facility is located in Reed Township, Will County, Illinois

  10. Safety evaluation report related to the operation of Watts Bar Nuclear Plant, Units 1 and 2 (Docket Nos. 50-390 and 50-391). Supplement No. 14

    Energy Technology Data Exchange (ETDEWEB)

    Tam, P.S.

    1994-12-01

    Supplement No. 14 to the Safety Evaluation Report for the application filed by the Tennessee Valley Authority for license to operate Watts Bar Nuclear Plant, Units 1 and 2, Docket Nos. 50-390 and 50-391, located in Rhea County, Tennessee, 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 with additional information submitted by the applicant since Supplement No. 13 was issued, and matters that the staff had under review when Supplement No. 13 was issued.

  11. Safety Evaluation Report related to the operation of Diablo Canyon Nuclear Power Plant, Units 1 and 2 (Docket Nos. 50-275 and 50-323). Supplement No. 28

    International Nuclear Information System (INIS)

    1985-04-01

    Supplement 28 to the Safety Evaluation Report for the Pacific Gas and Electric Company's application for licenses to operate Diablo Canyon Nuclear Power Plant, Units 1 and 2 (Docket Nos. 50-275 and 50-323) has been prepared jointly by the Office of Nuclear Reactor Regulation and the Region V Office of the US Nuclear Regulatory Commission. The supplement reports on the status of the staff's investigation, inspection, and evaluation of those allegations or concerns that have been identified to the NRC as of March 1, 1985

  12. Safety-evaluation report related to the operation of Diablo Canyon Nuclear Power Plants, Units 1 and 2. Docket Nos. 50-275 and 50-323. Supplement No. 18

    International Nuclear Information System (INIS)

    1983-08-01

    Supplement 18 to the Safety Evaluation Report for Pacific Gas and Electric Company's application for licenses to operate Diablo Canyon Nuclear Power Plants, Units 1 and 2 (Docket Nos. 50-275 and 50-323), has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement reports on the verification effort for Diablo Canyon Unit 1 that was performed between November 1981 and the present in response to Commission Order CLI-81-30 and an NRC letter to the licensee

  13. Safety evaluation report related to the operation of South Texas Project, Units 1 and 2 (Docket Nos. 50-498 and 50-499)

    International Nuclear Information System (INIS)

    1987-07-01

    In April 1986 the staff of the Nuclear Regulatory Commission issued its Safety Evaluation Report (NUREG-0781) regarding the application of Houston Lighting and Power Company (applicant and agent for the owners) for a license to operate South Texas Project, Units 1 and 2 (Docket Nos. 50-498 and 50-499). The facility is located in Matagorda County, Texas, west of the Colorado River, 8 miles north-northwest of the town of Matagorda and about 89 miles southwest of Houston. The first supplement to NUREG-0781 was issued in September 1986, the second supplement in January 1987, and the third supplement in May 1987. This fourth supplement reports on the status of unresolved items in the Safety Evaluation Report and resolves all the issues necessary to support the issuance of a low-power license

  14. Safety-evaluation report related to operation of McGuire Nuclear Station, Units 1 and 2. Docket Nos. 50-369 and 50-370

    International Nuclear Information System (INIS)

    1983-05-01

    This report supplements the Safety Evaluation Report Related to the Operation of McGuire Nuclear Station, Units 1 and 2 (SER (NUREG-0422)) issued in March 1978 by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission with respect to the application filed by Duke Power Company, as applicant and owner, for licenses to operate the McGuire Nuclear Station, Units 1 and 2 (Docket Nos. 50-369 and 50-370). The facility is located in Mecklenburg County, North Carolina, about 17 mi north-northwest of Charlotte, North Carolina. This supplement provides information related to issuance of a full-power authorization for Unit 2. The staff concludes that the McGuire Nuclear Station can be operated by the licensee without endangering the health and safety of the public

  15. Safety Evaluation Report related to the operation of South Texas Project, Units 1 and 2 (Docket Nos. 50-498 and 50-499)

    International Nuclear Information System (INIS)

    1986-04-01

    The Safety Evaluation Report for the application filed by Houston Lighting and Power Company, City Public Service Board of San Antonio, Central Power and Light Company, and the City of Austin, as applicants and owners, for licenses to operate the South Texas Project Units 1 and 2 (Docket Nos. 50-498 and 50-499) has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located in Matagorda County, Texas, west of the Colorado River, 8 miles north-northwest of the town of Matagorda and about 89 miles southwest of Houston. Subject to resolution of the items discussed in this report, the staff concludes that the applicant can operate the facility without endangering the health and safety of the public

  16. Safety Evaluation Report related to the operation of Perry Nuclear Power Plant, Units 1 and 2 (Docket Nos. 50-440 and 50-441). Supplement No. 6

    International Nuclear Information System (INIS)

    1985-04-01

    Supplement No. 6 to the Safety Evaluation Report (NUREG-0887) on the application filed by the Cleveland Electric Illuminating Company on behalf of itself and as agent for the Duquesne Light Company, the Ohio Edison Company, the Pennsylvania Power Company, and the Toledo Edison Company (the Central Area Power Coordination Group or CAPCO), as applicants and owners, for a license to operate the Perry Nuclear Power Plant, Units 1 and 2 (Docket Nos. 50-540 and 50-441), has been prepared by the Office of the Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located in Lake County, Ohio, approximately 35 miles northeast of Cleveland, Ohio. This supplement reports the status of certain issues that had not been resolved at the time of publication of the Safety Evaluation Report and Supplement Nos. 1 through 5 to that report

  17. Safety Evaluation Report related to the operation of Perry Nuclear Power Plant, Units 1 and 2 (Docket Nos. 50-440 and 50-441). Supplement No. 8

    International Nuclear Information System (INIS)

    1986-01-01

    Supplement No. 8 to the Safety Evaluation Report (NUREG-0887) on the application filed by the Cleveland Electric Illuminating Company on behalf of itself and as agent for the Duquesne Light Company, the Ohio Edison Company, the Pennsylvania Power Company, and the Toledo Edison Company (the Central Area Power Coordination Group or CAPCO), as applicants and owners, for a license to operate the Perry Nuclear Power Plant, Units and 1 and 2 (Docket Nos. 50-440 and 50-441), has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located in Lake County, Ohio, approximately 35 miles northeast of Cleveland, Ohio. This supplement reports the status of certain issues that has not been resolved at the time of publication of the Safety Evaluation Report and Supplement Nos. 1 through 7 to that report

  18. Safety Evaluation Report related to the operation of Perry Nuclear Power Plant, Units 1 and 2 (Docket Nos. 50-440 and 50-441). Supplement No. 5

    International Nuclear Information System (INIS)

    1985-02-01

    Supplement No. 5 to the Safety Evaluation Report (NUREG-0887) on the application filed by the Cleveland Electric Illuminating Company on behalf of itself and as agent for the Duquesne Light Company, the Ohio Edison Company, The Pennsylvania Power Company, and the Toledo Edison Company (the Central Area Power Coordination Group or CAPCO), as applicants and owners, for a license to operate the Perry Nuclear Power Plant, Units 1 and 2 (Docket Nos. 50-440 and 50-441), has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located in Lake County, Ohio, approximately 35 miles northeast of Cleveland, Ohio. This supplement reports the status of certain issues that had not been resolved at the time of publication of the Safety Evaluation Report and Supplement Nos. 1 through 4 to that report

  19. Safety Evaluation Report related to the operation of Grand Gulf Nuclear Station, Units 1 and 2 (Docket Nos. 50-416 and 50-417)

    International Nuclear Information System (INIS)

    1984-10-01

    This report supplements the Safety Evaluation Report (NUREG-0831) issued in September 1981 by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission with respect to the application filed by Mississippi Power and Light (MP and L) Company, Middle South Energy, Inc., and South Mississippi Electric Power Association as applicants and owners, for licenses to operate the Grand Gulf Nuclear Station, Units 1 and 2 (Docket Nos. 50-416 and 50-417, respectively). The facility is located on the east bank of the Mississippi River near Port Gibson in Claiborne County, Mississippi. This supplement provides information on the NRC staff's evaluation of requests for exemptions to NRC regulations pursuant to the Commission's direction in CLI-84-19, dated October 25, 1984

  20. Safety evaluation report related to the operation of Watts Bar Nuclear Plant, Units 1 and 2 (Docket Nos. 50--390 and 50--391)

    International Nuclear Information System (INIS)

    1990-11-01

    This report supplements the Safety Evaluation Report (SER), NUREG-0847 (June 1982), Supplement No. 1 (September 1982), Supplement No. 2 (January 1984), Supplement No. 3 (January 1985), and Supplement No. 4 (March 1985), issued by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission with respect to the application filed by the Tennessee Valley Authority, as applicant and owner, for licenses to operate the Watts Bar Nuclear Plant, Units 1 and 2 (Docket Nos. 50-390 and 50-391). The facility is located in Rhea County, Tennessee, near the Watts Bar Dam on the Tennessee River. This supplement provides recent information regarding resolution of some of the outstanding and confirmatory items and proposed license conditions identified in the SER

  1. Safety Evaluation Report related to the operation of Watts Bar Nuclear Plant, Units 1 and 2 (Docket Nos. 50-390 and 50-391)

    International Nuclear Information System (INIS)

    Tam, P.S.

    1991-04-01

    This report supplements the Safety Evaluation Report (SER), NUREG- 0847 (June 1982), Supplement No. 1' (September 1982), Supplement No. 2 (January 1984), Supplement No. 3 (January 1985), Supplement No. 4 (March 1985), and Supplement No. 5 (November 1990) issued by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory commission with respect to the application filed by the Tennessee Valley Authority, as applicant and owner, for licenses to operate the Watts Bar Nuclear Plant, Units 1 and 2 (Docket Nos. 50--390 and 50--391). The facility is located in Rhea County, Tennessee, near the Watts Bar Dam on the Tennessee River. This supplement provides recent information regarding resolution of some of the outstanding and confirmatory items, and proposed license conditions identified in the SER

  2. Safety evaluation report related to the operation of Diablo Canyon Nuclear Power Plant, Units 1 and 2 (Docket Nos. 50-275 and 50-323). Supplement No. 25

    International Nuclear Information System (INIS)

    1984-07-01

    Supplement 25 to the Safety Evaluation Report for Pacific Gas and Electric Company's application for licenses to operate Diablo Canyon Nuclear Power Plants, Unit 1 and Unit 2 (Docket Nos. 50-275 and 50-323) has been prepared by the Office of Nuclear Reactor Regulation (NRR) of the US Nuclear Regulatory Commission. This supplement reports on the staff's inspection and evaluation efforts on the matter of piping and piping supports as related to the seven technical license conditions in an Order Modifying License issued by NRR on April 18, 1984

  3. Safety evaluation report related to the operation of Midland Plant, Units 1 and 2. Docket Nos. 50-329 and 50-330, Consumers Power Company

    International Nuclear Information System (INIS)

    1982-10-01

    This report supplements the Safety Evaluation Report related to the Operation of Midland Plant, Units 1 and 2 (SER) (NUREG-0793) issued in May 1982 by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission with respect to the application filed by Consumers Power Company, as applicant and owner, for licenses to operate the Midland Plant, Units 1 and 2 (Docket Nos. 50-329 and 50-330). The facility is located in the city of Midland in Midland County, Michigan. This supplement provides recent information regarding resolution of the soils settlement issue, one of the open items identified in the SER. Certain confirmatory issues identified in the SER also are addressed

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

    International Nuclear Information System (INIS)

    1984-06-01

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

  5. Safety Evaluation Report related to the operation of Seabrook Station, Units 1 and 2 (Docket Nos. 50-443 and 50-444). Supplement No. 5

    International Nuclear Information System (INIS)

    1986-07-01

    This report is Supplement No. 5 to the Safety Evaluation Report (NUREG-0896, March 1983) for the application filed by the Public Service Company of New Hampshire, et al., for licenses to operate Seabrook Station, Units 1 and 2 Docket Nos. STN 50-443 and STN 50-444). It has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission and provides recent information on open items identified in the SER. The facility is located in Seabrook, New Hampshire. Subject to favorable resolution of the items discussed in this report, the staff concludes that the facility can be operated by the applicant without endangering the health and safety of the public

  6. Safety evaluation report related to the operation of Watts Bar Nuclear Plant, Units 1 and 2 (Docket Nos. 50-390 and 50-391): Supplement No. 19

    International Nuclear Information System (INIS)

    1995-11-01

    Supplement No. 19 to the Safety Evaluation Report for the application filed by the Tennessee Valley Authority for license to operate Watts Bar Nuclear Plant, Units 1 and 2, Docket Nos. 50-390 and 50-391, located in Rhea County Tennessee, 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 with (1) additional information submitted by the applicant since Supplement No. 18 was issued, and (2) matters that the staff had under review when Supplement No. 18 was issued

  7. Safety evaluation report related to the operation of Shearon Harris Nuclear Power Plant, Units 1 and 2. Docket Nos. STN 50-400 and STN 50-401

    International Nuclear Information System (INIS)

    1983-11-01

    The Safety Evaluation Report for the application filed by the Carolina Power and Light Company, as applicant and owner, for licenses to operate the Shearon Harris Nuclear Power Plant Units 1 and 2 (Docket Nos. 50-400 and 50-401) has been prepared by the Office of Nuclear Reactor Regulation of US Nuclear Regulatory Commission. The facility is located near Raleigh, North Carolina. Subject to favorable resolution of the items discussed in this report, the NRC staff concludes that the facility can be operated by the applicant without endangering the health and safety of the public

  8. Safety Evaluation Report related to the operation of South Texas Project, Units 1 and 2 (Docket Nos. 50-498 and 50-499). Supplement No. 1

    International Nuclear Information System (INIS)

    1986-09-01

    In April 1986 the staff of the Nuclear Regulatory Commission issued its Safety Evaluation Report (NUREG-0781) regarding the application of Houston Lighting and Power Company (applicant and agent for the owners) for a license to operate South Texas Project, Units 1 and 2 (Docket Nos. 50-498 and 50-499). The facility is located in Matagorda County, Texas, west of the Colorado River, 8 miles north-northwest of the town of Matagorda and about 89 miles southwest of Houston. This first supplement to NUREG-0781 reports the status of certain items that remained unresolved at the time the Safety Evaluation Report was published

  9. Safety evaluation report related to the operation of Perry Nuclear Power Plant, Units 1 and 2 (Docket Nos. 50-440 and 50-441). Supplement No. 10

    International Nuclear Information System (INIS)

    1986-09-01

    Supplement No. 10 to the Safety Evaluation Report (NUREG-0887) on the application filed by the Cleveland Electric Illuminating Company on behalf of itself and as agent for the Duquesne Light Company, the Ohio Edison Company, the Pennsylvania Power Company, and the Toledo Edison Company (the Central Area Power Coordination Group or CAPCO), as applicants and owners for a license to operate the Perry Nuclear Power Plant, Units 1 and 2 (Docket Nos. 50-440 and 50-441), has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located in Lake County, Ohio, approximately 35 miles northeast of Cleveland, Ohio. This supplement reports the status of certain issues and action items that had not been resolved or completed at the time of publication of the Safety Evaluation Report and Supplements Nos. 1 through 9 to that report

  10. Safety evaluation report related to the operation of Perry Nuclear Power Plant, Units 1 and 2: Docket Nos. 50-440 and 50-441

    International Nuclear Information System (INIS)

    1983-01-01

    Supplement No. 2 to the Safety Evaluation Report on the application filed by the Cleveland Electric Illuminating Company on behalf of itself and as agent for the Duquesne Light Company, the Ohio Edison Company, the Pennsylvania Power Company, and the Toledo Edison Company (the Central Area Power Coordination Group (CAPCO)), as applicants and owners, for a license to operate the Perry Nuclear Power Plant, Units 1 and 2 (Docket Nos. 50-440 and 50-441), has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located in Lake County, Ohio. This supplement reports the status of certain issues that had not been resolved at the time of publication of the Safety Evaluation Report and Supplement No. 1 to that report

  11. Final Environmental Statement related to the operation of Comanche Peak Steam Electric Station, Units 1 and 2 (Docket Nos. 50-445 and 50-446)

    International Nuclear Information System (INIS)

    1989-10-01

    In September 1981, the staff of the Nuclear Regulatory Commission (NRC) issued its Final Environmental Statement (NUREG-0775) related to the operation of Comanche Peak Steam Electric Station, Units 1 and 2 (Docket Nos. 50-445 and 50-446), located in Somervell County, Texas, approximately 40 miles southwest of Fort Worth, Texas. The NRC has prepared this supplement to NUREG-0775 to present its evaluation of the alternative of operating Comanche Peak with the installation of further severe-accident-mitigation design features. The NRC has discovered no substantial changes in the proposed action as previously evaluated in the Final Environmental Statement that are relevant to environmental concerns and bearing on the licensing of Comanche Peak Steam Electric Station, Units 1 and 2. 6 refs., 3 tabs

  12. Safety evaluation report: related to the operation of Seabrook Station, Units 1 and 2, Docket Nos. 50-443 and 50-444, Public Service Company of New Hampshire, et al

    International Nuclear Information System (INIS)

    1983-03-01

    The Safety Evaluation Report for the application filed by the Public Service Company of New Hampshire, et al., for licenses to operate Seabrook Station, Units 1 and 2 (Docket Nos. STN 50-443 and STN 50-444), has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located in Seabrook, New Hampshire. Subject to favorable resolution of the items discussed in this report, the staff concludes that the facility can be operated by the applicant without endangering the health and safety of the public

  13. 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

  14. Safety evaluation report related to the operation of Diablo Canyon Nuclear Power Plant, Units 1 and 2 (Docket Nos. 50-275 and 50-323). Supplement No. 26

    International Nuclear Information System (INIS)

    1984-07-01

    Supplement 26 to the Safety Evaluation Report for Pacific Gas and Electric Company's application for licenses to operate Diablo Canyon Nuclear Power Plants, Units 1 and 2 (Docket Nos. 50-275 and 50-323), has been prepared jointly by the Office of Nuclear Reactor Regulation and the Region V Office of the US Nuclear Regulatory Commission. The supplement reports on the status of the staff's investigation, inspection and evaluation of those allegations or concerns that have been identified to the NRC as of July 8, 1984. The report specifically addresses those allegations which the staff determined must be satisfactorily resolved prior to full power operation of Diablo Canyon Unit 1

  15. Safety Evaluation Report related to the operation of Watts Bar Nuclear Plant, Units 1 and 2 (Docket Nos. 50-390 and 50-391). Supplement No. 4

    International Nuclear Information System (INIS)

    1985-03-01

    This report supplements the Safety Evaluation Report, NUREG-0847 (June 1982), Supplement No. 1 (September 1982), Supplement No. 2 (January 1984), and Supplement No. 3 (January 1985) issued by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission with respect to the application filed by the Tennessee Valley Authority, as applicant and owner, for licenses to operate the Watts Bar Nuclear Plant, Units 1 and 2 (Docket Nos. 50-390 and 50-391). The facility is located in Rhea County, Tennessee, near the Watts Bar Dam on the Tennessee River. This supplement provides recent information regarding resolution of some of the open and confirmatory items and license conditions identified in the Safety Evaluation Report

  16. Safety Evaluation Report related to the operation of Watts Bar Nuclear Plant, Units 1 and 2 (Docket Nos. 50-390 and 50-391). Supplement No. 3

    International Nuclear Information System (INIS)

    1985-01-01

    This report supplements the Safety Evaluation Report, NUREG-0847 (June 1982), Supplement No. 1 (September 1982), and Supplement No. 2 (January 1984) issued by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission with respect to the application filed by the Tennessee Valley Authority, as applicant and owner, for licenses to operate the Watts Bar Nuclear Plant, Units 1 and 2 (Docket Nos. 50-390 and 50-391). The facility is located in Rhea County, Tennessee, near the Watts Bar Dam on the Tennessee River. This supplement provides recent information regarding resolution of some of the open and confirmatory items and license conditions identified in the Safety Evaluation Report

  17. Safety Evaluation Report related to the operation of South Texas Project, Units 1 and 2 (Docket Nos. 50-498 and 50-499)

    International Nuclear Information System (INIS)

    1988-03-01

    In April 1986 the staff of the US Nuclear Regulartory Commission issued its Safety Evaluation Report (NURED-0781) regarding the application of Houston Lighting and Power Companany (applicant and agent for the owners) for a license to operate South Texas Project, Units 1 and 2 (Docket Nos. 50-498 and 50-499). The facililty is located in Matagorda County, Texas, west of the Colorado River, 8 miles north-northwest of the town of Matagorda and about 89 miles southwest of Houston. The first supplement to NUREG-0781 was issued in September 1986, the second supplement in January 1987, the third supplement in May 1987, and the fourth supplement in July 1987. This fifth supplement provides updated information on the issues that had been considered previously as well as the evaluation of issues that have arisen since the fourth supplement was issued. The evaluation resolves all the issues necessary to support the issuance of a full-power license for Unit 1

  18. Safety Evaluation Report related to the operation of Watts Bar Nuclear Plant, Units 1 and 2 (Docket Nos. 50-390 and 50-391)

    International Nuclear Information System (INIS)

    Tam, P.S.

    1992-10-01

    This report supplements the Safety Evaluation Report (SER), NUREG-0847 (June 1982), Supplement No. 1 (September 1982), Supplement No. 2 (January 1984), Supplement No. 3 (January 1985), Supplement No. 4 (March 1985), Supplement No. 5 (November 1990), Supplement No. 6 (April 1991), Supplement No. 7 (September 1991), Supplement No. 8 (January 1992), and Supplement No. 9 (June 1992) issued by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission with respect to the application filed by the Tennessee Valley Authority, as applicant and owner, for licenses to operate the Watts Bar Nuclear Plant, Units I and 2 (Docket Nos. 50-390 and 50-391). The facility is located in Rhea County, Tennessee, near the Watts Bar Dam on the Tennessee River. This supplement provides recent information regarding resolution of some of the outstanding and confirmatory items, and proposed license conditions identified in the SER

  19. Safety evaluation report 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)

    1986-12-01

    In June 1985, the staff of the Nuclear Regulatory Commission issued its Safety Evaluation Report (NUREG-1137) regarding the application of Georgia Power Company, Municipal Electric Authority of Georgia, Oglethorpe Power Corporation, and City of Dalton, Georgia, for licenses to operate the Vogtle Electric Generating Plant, Units 1 and 2 (Docket Nos. 50-424 and 50-425). Supplement 1 to NUREG-0737 was issued by the staff in October 1985, Supplement 2 was issued in May 1986, and Supplement 3 was issued in August 1986. The facility is located in Burke County, Georgia, approximately 26 miles south-southeast of Augusta, Georgia, and on the Savannah River. This fourth supplement to NUREG-1137 provides recent information regarding resolution of some of the open and confirmatory items that remained unresolved at the time the Safety Evaluation Report was issued. This supplement also discusses some new items

  20. Safety evaluation report 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)

    1987-01-01

    In June 1985, the staff of the Nuclear Regulatory Commission issued its Safety Evaluation Report (NUREG-1137) regarding the application of Georgia Power Company, Municipal Electric Authority of Georgia, Oglethorpe Power Corporation, and the City of Dalton, Georgia, for licenses to operate the Vogtle Electric Generating Plant, Units 1 and 2 (Docket Nos. 50-424 and 50-425). Supplement 1 to NUREG-1137 was issued by the staff in October 1985, Supplement 2 was issued in May 1986, Supplement 3 was issued in August 1986, and Supplement 4 was issued in December 1986. The facility is located in Burke County, Georgia, approximately 26 miles south-southeast of Augusta, Georgia, and on the Savannah River. This fifth supplement to NUREG-1137 provides recent information regarding resolution of some of the open and confirmatory items that remained unresolved at the time the Safety Evaluation Report was issued

  1. Safety evaluation report related to the operation of Diablo Canyon Nuclear Power Plant, Units 1 and 2 (Docket Nos. 50-275 and 50-323)

    International Nuclear Information System (INIS)

    1983-12-01

    Supplement 20 to the Safety Evaluation Report for Pacific Gas and Electric Company's application for licenses to operate Diablo Canyon Nuclear Power Plant, Unit 1 and Unit 2 (Docket Nos. 50-275 and 50-323), has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement reports on the verification effort for Diablo Canyon Unit 1 that was performed between November 1981 and the present in response to Commission Order CLI-81-30 and an NRC letter of November 19, 1981 to the licensee. Specifically, Supplement 20 addresses those issues and other matters identified in Supplements 18 and 19 that must be resolved prior to Unit 1 achieving criticality and operating at power levels up to 5% of rated full power. This SER Supplement applies only to Diablo Canyon Unit 1

  2. Safety Evaluation Report related to the operation of Catawba Nuclear Station, Units 1 and 2 (Docket Nos. 50-413 and 50-414). Supplement No. 6

    International Nuclear Information System (INIS)

    1986-05-01

    This report supplements the Safety Evaluation Report (NUREG-0954) issued in February 1983 by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission with respect to the application filed by Duke Power Company, North Carolina Municipal Power Agency Number 1, North Carolina Membership Corporation, Saluda River Electric Cooperative, Inc., and Piedmont Municipal Power Agency, as applicants and owners, for licenses to operate the Catawba Nuclear Station, Units 1 and 2 (Docket Nos. 50-413 and 50-414, respectively). The facility is located in York County, South Carolina, approximately 9.6 km (6 miles) north of Rock Hill and adjacent to Lake Wylie. This supplement provides additional information supporting the license for operation above 5% power and power ascension to full-power operation for Unit 2

  3. Safety Evaluation Report related to the operation of Vogtle Electric Generating Plant, Units 1 and 2 (Docket Nos. 50-424 and 50-425). Supplement No. 1

    International Nuclear Information System (INIS)

    1985-10-01

    In June 1985, the staff of the Nuclear Regulatory Commission issued its Safety Evaluation Report (NUREG-1137) regarding the application of Georgia Power Company, Municipal Electric Authority of Georgia, Oglethorpe Power Corporation, and City of Dalton, Georgia, for a license to operate the Vogtle Electric Generating Plant, Units 1 and 2 (Docket Nos. 50-424 and 50-425). The facility is located in Burke County, Georgia, approximately 26 miles south-southeast of Augusta, Georgia, and on the Savannah River. This first supplement to NUREG-1137 provides recent information regarding resolution of some of the open and confirmatory items that remained unresolved at the time the Safety Evaluation Report was issued and provides the Advisory Committee on Reactor Safeguards letter dated August 13, 1985

  4. Safety evaluation report 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)

    1989-03-01

    In June 1985, the staff of the Nuclear Regulatory Commission issued its Safety Evaluation Report (NUREG-1137) regarding the application of Georgia Power Company, Municipal Electric Authority of Georgia, Oglethorpe Power Corporation, and the City of Dalton, Georgia, for licenses to operate the Vogtle Electric Generating Plant, Units 1 and 2 (Docket Nos. 50-424 and 50-425). Supplement 1 to NUREG-1137 was issued by the staff in October 1985, Supplement 2 was issued in May 1986, Supplement 3 was issued in August 1986, Supplement 4 was issued in December 1986, Supplement 5 was issued in January 1987, Supplement 6 was issued in March 1987, Supplement 7 was issued in January 1988, and Supplement 8 was issued in February 1989. The facility is located in Burke County, Georgia, approximately 26 miles south-southeast of Augusta, Georgia, and on the Savannah River. This ninth supplement to NUREG-1137 provides recent information regarding resolution of conditional items following issuance of Supplement 8

  5. Safety Evaluation Report related to the operation of Braidwood Station, Units 1 and 2 (Docket Nos. STN 50-456 and STN 50-457)

    International Nuclear Information System (INIS)

    1988-06-01

    In November 1983, the staff of the Nuclear Regulatory Commission issued its Safety Evaluation Report (NUREG-1002) regarding the application filed by the Commonwealth Edison Company, as applicant and owner, for a license to operate Braidwood Station, Units 1 and 2 (Docket Nos. 50-456 and 50-457). The first supplement to NUREG-1002 was issued in September 1986; the second supplement was issued in October 1986; the third supplement was issued in May 1987; the fourth supplement was issued in July 1987 in support of the full power license for Unit 1; the fifth supplement was issued in December 1987 in support of the low power license for Unit 2. This sixth supplement to NUREG-1002 is in support of the full-power license for Unit 2 and provides the status of items that remained unresolved at the time Supplement 5 was published. The facility is located in Reed Township, Will County, Illinois

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

    International Nuclear Information System (INIS)

    1983-04-01

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

  7. Safety Evaluation Report related to the operation of Vogtle Electric Generating Plant, Units 1 and 2 (Docket Nos. 50-424 and 50-425). Supplement No. 2

    International Nuclear Information System (INIS)

    1986-05-01

    In June 1985, the staff of the Nuclear Regulatory Commission issued its Safety Evaluation Report (NUREG-1137) regarding the application of Georgia Power Company, Municipal Electric Authority of Georgia, Oglethorpe Power Corporation, and City of Dalton, Georgia, for a license to operate the Vogtle Electric Generating Plant, Units 1 and 2 (Docket Nos. 50-424 and 50-425). Supplement 1 to NUREG-1137 was issued by the staff in October 1985. The facility is located in Burke County, Georgia, approximately 26 miles south-southeast of Augusta, Georgia, and on the Savannah River. This second supplement to NUREG-1137 provides recent information regarding resolution of some of the open and confirmatory items that remained unresolved at the time the Safety Evaluation Report was issued. This supplement also discusses some new open and confirmatory items

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

    International Nuclear Information System (INIS)

    1985-01-01

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

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

    International Nuclear Information System (INIS)

    1983-02-01

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

  10. 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

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

    International Nuclear Information System (INIS)

    1984-10-01

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

  12. Safety Evaluation Report related to the operation of Perry Nuclear Power Plant, Units 1 and 2 (Docket Nos. 50-440 and 50-441). Supplement No. 7

    International Nuclear Information System (INIS)

    1985-11-01

    Supplement No. 7 to the Safety Evaluation Report (NUREG-0887) on the application filed by the Cleveland Electric Illuminating Company on behalf of itself and as agent for the Duquesne Light Company, the Ohio Edison Company, the Pennsylvania Power Company, and the Toledo Edison Company (the Central Area Power Coordination Group or CAPCO), as applicants and owners, for a license to operate the Perry Nuclear Power Plant, Units 1 and 2 (Docket No. 50-440 and 50-441) has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located in Lake County, Ohio, approximately 35 miles northeast of Cleveland, Ohio. This supplement reports the status of certain issues that had not been resolved at the time of publication of the Safety Evaluation Report and Supplement Nos. 1 through 6 to that report

  13. Safety evaluation report related to the operation of Watts Bar Nuclear Plant, Units 1 and 2, (Docket Nos. 50-390 and 50-391), Tennessee Valley Authority

    International Nuclear Information System (INIS)

    1992-06-01

    This report supplements the Safety Evaluation Report (SER), NUREG- 0847 (June 1982), Supplement No. 1 (September 1982), Supplement No. 2 (January 1984), Supplement No. 3 (January 1985), Supplement No. 4 (March 1985), Supplement No. 5 (November 1990), Supplement No. 6 (April 1991), Supplement No. 7 (September 1991), and Supplement No. 8 (January 1992) issued by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission with respect to the application filed by the Tennessee Valley Authority, as applicant and owner, for licenses to operate the Watts Bar Nuclear Plant, Units 1 and 2 (Docket Nos. 50-390 and 50-391). The facility is located in Rhea County, Tennessee near the Watts Bar Dam on the Tennessee River. This supplement provides recent information regarding resolution of some of the outstanding and confirmatory items, and proposed license conditions identified in the SER

  14. Safety Evaluation Report related to the operation of Vogtle Electric Generating Plant, Units 1 and 2 (Docket Nos. 50-424 and 50-425). Supplement No. 3

    International Nuclear Information System (INIS)

    1986-08-01

    In June 1985, the staff of the Nuclear Regulatory Commission issued its Safety Evaluation Report (NUREG-1137) regarding the application of Georgia Power Company, Municipal Electric Authority of Georgia, Oglethorpe Power Corporation, and City of Dalton, Georgia, for a license to operate the Vogtle Electric Generating Plant, Units 1 and 2 (Docket Nos. 50-424 and 50-425). Supplement 1 to NUREG-1137 was issued by the staff in October 1985, and Supplement 2 was issued in May 1986. The facility is located in Burke County, Georgia, approximately 26 miles south-southeast of Augusta, Georgia, and on the Savannah River. This third supplement to NUREG-1137 provides recent information regarding resolution of some of the open and confirmatory items that remained unresolved at the time the Safety Evaluation Report was issued. This supplement also discusses some new open items

  15. Safety Evaluation Report related to the operation of Diablo Canyon Nuclear Power Plant, Units 1 and 2 (Docket Nos. 50-275 and 50-323). Supplement No. 33

    International Nuclear Information System (INIS)

    1986-05-01

    Supplement 33 to the Safety Evaluation Report for the Pacific Gas and Electric Company's Diablo Canyon Nuclear Power Plant, Units 1 and 2 (Docket Nos. 50-275 and 50-323) has been prepared jointly by the Office of Nuclear Reactor Regulation and the Region V Office of the US Nuclear Regulatory Commission. The supplement reports on the status of the staff's investigation, inspection, and evaluation of allegations and concerns that have been identified to the NRC through March 1986. The report includes a complete listing of all allegations and concerns, indicating the status of their resolution. The NRC staff concludes that the technical issues raised in the allegations with regard to the design, construction, and safe operation of Diablo Canyon Units 1 and 2 have been satisfactorily resolved and no further action is required

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

    International Nuclear Information System (INIS)

    1987-03-01

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

  17. Safety evaluation report related to the operation of Vogtle Electric Generating Plant, Units 1 and 2 (Docket Nos. 50-424 and 50-425): Supplement 8

    International Nuclear Information System (INIS)

    1989-02-01

    In June 1985, the staff of the Nuclear Regulatory Commission issued its Safety Evaluation Report (NUREG-1137) regarding the application of Georgia Power Corporation, and the City of Dalton, Georgia, for licenses to operate the Vogtle Electric Generating Plant, Units 1 and 2 (Docket Nos. 50-424 and 50-425). Supplement 1 to NUREG-1137 was issued by the Staff in October 1985, Supplement 2 was issued in May 1986, Supplement 3 was issued in August 1986, Supplement 4 was issued in December 1986, Supplement 5 was issued in January 1987, Supplement 6 was issued in March 1987, and Supplement 7 was issued in January 1988. The facility is located in Burke County, Georgia, approximately 26 miles south-southeast of Augusta, Georgia, and on the Savannah River. This eighth supplement to NUREG-1137 provides recent information regarding resolution of some of the open and confirmatory items that remained unresolved following issuance of Supplement 7. 5 figs., 3 tabs

  18. Safety evaluation report related to the operation of Diablo Canyon Nuclear Power Plant, Units 1 and 2 (Docket Nos. 50-275 and 50-323). Suppl. 22

    International Nuclear Information System (INIS)

    1984-03-01

    Supplement 22 to the Safety Evaluation Report for Pacific Gas and Electric Company's application for licenses to operate Diablo Canyon Nuclear Power Plants, Unit 1 and 2 (Docket Nos. 50-275 and 50-323), has been prepared jointly by the Office of Nuclear Reactor Regulation and the Region V Office of the US Nuclear Regulatory Commission. This supplement provides the criteria that were used by the staff to determine which of the allegations that have been evaluated and must be resolved prior to Unit 1 achieving criticality and operating at power level up to 5 percent of rated power (i.e., low power operation). The supplement also reports on the status of the staff's investigation, inspection and evaluation of 219 allegations or concerns that have been identified to the NRC as of March 9, 1984, excluding those recently received under 10 CFR 2.206 petitions

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

    International Nuclear Information System (INIS)

    1984-12-01

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

  20. Safety Evaluation Report related to the operation of Perry Nuclear Power Plant, Units 1 and 2 (Docket Nos. 50-440 and 50-441). Supplement No. 9

    International Nuclear Information System (INIS)

    1986-03-01

    Supplement No. 9 to the Safety Evaluation Report (NUREG-0887) on the application filed by the Cleveland Electric Illuminating Company on behalf of itself and as agent for the Duquesne Light Company, the Ohio Edison Company, the Pennsylvania Power Company, and the Toledo Edison Company (the Central Area Power Coordination Group or CAPCO) for a license to operate the Perry Nuclear Power Plant, Units 1 and 2 (Docket Nos. 50-440 and 50-441), has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located in Lake County, Ohio, approximately 35 miles northeast of Cleveland, Ohio. This supplement reports the staff's evaluation findings pertaining to the earthquake event that occurred in the vicinity of the Perry Nuclear Power Plant site on January 31, 1986, and is limited to that evaluation. Future supplemental reports will continue reporting on the status of new or unresolved issues since Supplement No. 8 was issued in January 1986

  1. Safety evaluation report: related to the operation of Perry Nuclear Power Plant, Units 1 and 2, Docket Nos. 50-440 and 50-441, Cleveland Electric Illuminating Company

    International Nuclear Information System (INIS)

    1982-08-01

    Supplement No. 1 to the Safety Evaluation Report on the application filed by the Cleveland Electric Illuminating Company on behalf of itself and as agent for the Duquesne Light Company, the Ohio Edison Company, the Pennsylvania Power Company, and the Toledo Edison Company (the Central Area Power Coordination Group, CAPCO), as applicants and owners, for a license to operate the Perry Nuclear Power Plant, Units 1 and 2 (Docket Nos. 50-440 and 441). The facility is located near Lake Erie in Lake County, Ohio. This supplement has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission and reports the status of certain items that had not been resolved at the time of publication of the Safety Evaluation Report

  2. Technical Specifications, South Texas Project, Unit Nos. 1 and 2 (Docket Nos. 50-498 and 50-499): Appendix ''A'' to License Nos. NPF-76 and NPF-80

    International Nuclear Information System (INIS)

    1989-03-01

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

  3. Technical specifications, South Texas Project, Unit Nos. 1 and 2 (Docket Nos. 50-498 and 50-499): Appendix ''A'' to License Nos. NPF-76 and NPF-78

    International Nuclear Information System (INIS)

    1989-01-01

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

  4. Safety evaluation report related to the operation of Watts Bar Nuclear Plant, Units 1 and 2 (Docket Nos. 50-390 and 50-391). Supplement No. 15

    International Nuclear Information System (INIS)

    Tam, P.S.

    1995-06-01

    This report supplements the Safety Evaluation Report (SER), NUREG-0847 (June 1982), Supplement No. 1 (September 1982), Supplement No. 2 (January 1984), Supplement No. 3 (January 1985), Supplement No. 4 (March 1985), Supplement No. 5 (November 1990), Supplement No. 6 (April 1991), Supplement No. 7 (September 1991), Supplement No. 8 (January 1992), Supplement No. 9 (June 1992), Supplement No. 10 (October 1992), Supplement No. 11 (April 1993), Supplement No. 12 (October 1993), Supplement No. 13 (April 1994), and Supplement No. 14 (December 1994) issued by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission with respect to the application filed by the Tennessee Valley Authority, as applicant and owner, for licenses to operate the Watts Bar Nuclear Plant, Units 1 and 2 (Docket Nos. 50-390 and 50-391). The facility is located in Rhea County, Tennessee, near the Watts Bar Dam on the Tennessee River. This supplement provides recent information regarding resolution of some of the outstanding and confirmatory items, and proposed license conditions identified in the SER

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

    International Nuclear Information System (INIS)

    1985-12-01

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

  6. Technical Specifications: Vogtle Electric Generating Plant, Unit Nos. 1 and 2 (Docket Nos. 50-424 and 50-425): Appendix ''A'' to License Nos. NPF-68 and NPF-79

    International Nuclear Information System (INIS)

    1989-02-01

    The Vogtle Electric Generating Plant, Unit Nos. 1 and 2, Technical Specifications were prepared by the US Nuclear Regulatory Commission to set forth the limits, operating conditions, and other requirements applicable to a nuclear facility as set forth in Section 50.36 of 10 CFR 50 for the protection of the health and safety of the public

  7. Technical Specifications, Vogtle Electric Generating Plant, Unit Nos. 1 and 2 (Docket Nos. 50-424 and 50-425): Appendix ''A'' to License Nos. NPF-68 and NPF-81

    International Nuclear Information System (INIS)

    1989-03-01

    The Vogtle Electric Generating Plant, Unit Nos. 1 and 2, Technical Specifications were prepared by the US Nuclear Regulatory Commission to set forth the limits, operating conditions, and other requirements applicable to a nuclear facility as set forth in Section 50.36 of 10 CFR 50 for the protection of the health and safety of the public

  8. Final environmental statement related to construction of Skagit Nuclear Power Project Units 1 and 2: (Docket Nos. 50-522 and 50-523)

    International Nuclear Information System (INIS)

    1975-05-01

    The proposed action is the issuance of construction permits to the Pudget Sound Power and Light Company, Pacific Power and Light Company, Washington Water Power Company and the Washington Public Power Supply System, for the construction of Skagit Nuclear Power Projects Units 1 and 2 (Docket Nos. 50-522 and 50-523) in Skagit County, Washington (about 64 miles north of Seattle and 6 miles ENE of Sedro Woolley). These units are scheduled for commercial service in 1982 and 1985, respectively. Each unit will employ a boiling-water nuclear reactor with a maximum expected thermal power level of 4100 MWt, which is considered in the assessments contained in this statement. At the 3800 MWt power level initially to be licensed, the net electrical capacity of each unit will be 1288 MWe. The exhaust steam from the turbine-generators will be cooled in condensers which will utilize one hyperbolic-type natural-draft cooling tower per unit to dissipate heat to the atmosphere. Water (106 cfs max.) for the cooling tower makeup (82.4 cfs) and other plant uses will be withdrawn from the Skagit River through Ranney Collectors embedded in the north bank of the river and pumped to the plant through a pipeline about 35,000 ft. long. Cooling tower blowdown (7 cfs max.) from the project and dilution water (20 cfs max.) will flow through a pipeline back to the river where it will be discharged through a diffuser

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

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

    International Nuclear Information System (INIS)

    1987-05-01

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

  11. Safety evaluation report related to the operation of Watts Bar Nuclear Plant, Units 1 and 2, Docket Nos. 50-390 and 50-391, Tennessee Valley Authority. Supplement number 20

    International Nuclear Information System (INIS)

    1996-02-01

    This report supplements the Safety Evaluation Report (SER), NUREG-0847 (June 1982), Supplement No. 1 (September 1982), Supplement No. 2 (January 1984), Supplement No. 3 (January 1985), Supplement No. 4 (March 1985), Supplement No. 5 (November 1990), Supplement No. 6 (April 1991), Supplement No. 7 (September 1991), Supplement No. 8 (January 1992), Supplement No. 9 (June 1992), Supplement No. 10 (October 1992), Supplement No. 11 (April 1993), Supplement No. 12 (October 1993), Supplement No. 13 (April 1994), Supplement No. 14 (December 1994), Supplement No. 15 (June 1995), Supplement No. 16 (September 1995), Supplement No. 17 (October 1995), Supplement No. 18 (October 1995), and Supplement No. 19 (November 1995) issued by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission with respect to the application filed by the Tennessee Valley Authority, as applicant and owner, for licenses to operate the Watts Bar Nuclear Plant, Units 1 and 2 (Docket Nos. 50-390 and 50-391). The facility is located in Rhea County, Tennessee, near the Watts Bar Dam on the Tennessee River. This supplement provides recent information regarding resolution of some of the issues identified in the SER

  12. Safety evaluation report related to the operation of Watts Bar Nuclear Plant, Units 1 and 2 (Docket Nos. 50-390 and 50-391). Supplement No. 17

    International Nuclear Information System (INIS)

    Tam, P.S.

    1995-10-01

    This report supplements the Safety Evaluation Report (SER), NUREG-0847 (June 1982), Supplement No. 1 (September 1982), Supplement No. 2 (January 1984), Supplement No. 3 (January 1985), Supplement No. 4 (March 1985), Supplement No. 5 (November 1990), Supplement No. 6 (April 1991), Supplement No. 7 (September 1991), 1991), Supplement No. 8 (January 1992), Supplement No. 9 (June 1992), Supplement No. 10 (October 1992), Supplement No. 11 (April.1993), Supplement No. 12 (October 1993), Supplement No. 13 (April 1994), Supplement No. 14 (December 1994), Supplement No. 15 (June 1995), and Supplement No. 16 (September 1995) issued by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission with respect to the application filed by the Tennessee Valley Authority, as applicant and owner, for licenses to operate the Watts Bar Nuclear Plant, Units 1 and 2 (Docket Nos. 50--390 and 50--391). The facility is located in Rhea county, Tennessee, near the Watts Bar Dam on the Tennessee River. In this supplement, NRC examines the significant problems of construction quality and quality assurance effectiveness that led TVA to withdraw its certification in 1985 that Watts Bar Unit I was ready to load fuel. Also discussed are the extensive corrective actions performed by TVA according to its nuclear performance plans and other supplemental programs, and NRC's extensive oversight to determine whether the Watts Bar Unit 1 construction quality and TVA's operational readiness and quality assurance effectiveness are adequate for a low-power operating license to be issued. SSER 17 does not address Watts Bar Unit 2, except for the systems which are necessary to support Unit 1 operation

  13. Safety Evaluation Report related to the operation of Diablo Canyon Nuclear Power Plant, Units 1 and 2 (Docket Nos. 50-275 and 50-323)

    International Nuclear Information System (INIS)

    1984-07-01

    Supplement 27 to the Safety Evaluation Report for Pacific Gas and Electric Company's application for a license to operate Diablo Canyon Nuclear Power Plant, Unit 1 (Docket No. 50-275), has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement addresses the revisions to the license conditions and to the Technical Specifications as they relate to Amendment 10 to Diablo Canyon, Unit 1 Facility Operating License, DPR-76

  14. 78 FR 49305 - Luminant Generation Company LLC, Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 2...

    Science.gov (United States)

    2013-08-13

    ... NUCLEAR REGULATORY COMMISSION [Docket Nos. 50-445 and 50-446; NRC-2013-0182] Luminant Generation Company LLC, Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 2; Application for Amendment to Facility... Operating License Nos. NPF-87 and NPF-89 for the Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 2...

  15. Conformance to Regulatory Guide 1.97 Slurry Power Station, Unit Nos. 1 and 2 (Docket Nos. 50-280 and 50-281)

    International Nuclear Information System (INIS)

    Stoffel, J.W.

    1985-09-01

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

  16. Conformance to Regulatory Guide 1.97, Perry Nuclear Power Plant, Unit Nos. 1 and 2 (Docket Nos. 50-440 and 50-441)

    International Nuclear Information System (INIS)

    Udy, A.C.

    1985-03-01

    This EG and G Idaho, Inc., report provides a review of the submittals for Regulatory Guide 1.97, Revision 2, for the Perry Nuclear Power Plant, Unit Nos. 1 and 2. Any exception to the guidelines of Regulatory Guide 1.97 are evaluated

  17. Safety Evaluation Report related to the operation of South Texas Project, Unit 2 (Docket No. 50-499)

    International Nuclear Information System (INIS)

    1989-01-01

    In April 1986 the staff of the US Nuclear Regulatory Commission issued its Safety Evaluation Report (NUREG-0781) regarding the application of Houston Lighting and Power Company (applicant and agent for the owners) for a license to operate South Texas Project, Units 1 and 2 (Docket Nos. 50-498 and 50-499). The facility is located in Matagorda County, Texas, west of the Colorado River, 8 miles north-northwest of the town of Matagorda and about 89 miles southwest of Houston. The first supplement to NUREG-0781 was issued in September 1986, the second supplement in January 1987, the third supplement in May 1987, the fourth supplement in July 1987 and the fifth supplement in March 1988. This sixth supplement provides updated information on the issues that had been considered previously as well as the evaluation of issues that have arisen since the fifth supplement was issued. The evaluation resolves all the issues necessary to support the issuance of a low-power license for Unit 2

  18. Conformance to Regulatory Guide 1.97 Browns Ferry Nuclear Plant, Unit Nos. 1, 2 and 3 (Docket Nos. 50-259, 50-260, and 50-296)

    International Nuclear Information System (INIS)

    Udy, A.C.

    1985-07-01

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

  19. Safety Evaluation Report related to the operation of Shearon Harris Nuclear Power Plant, Unit No. 1 (Docket No. STN 50-400). Supplement No. 4

    International Nuclear Information System (INIS)

    1986-10-01

    This report, Supplement No. 4 to the Safety Evaluation Report for the application filed by the Carolina Power and Light Company and North Carolina Eastern Municipal Power Agency (the applicants) for a license to operate the Shearon Harris Nuclear Power Plant Unit 1 (Docket No. 50-400), has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement reports the status of certain items that had not been resolved at the time of publication of the Safety Evaluation Report and Supplement Nos. 1, 2, and 3

  20. Safety Evaluation Report related to the operation of Shearon Harris Nuclear Power Plant, Unit No. 1 (Docket No. STN 50-400). Supplement No. 3

    International Nuclear Information System (INIS)

    1986-05-01

    This report, Supplement No. 3 to the Safety Evaluation Report for the application filed by the Carolina Power and Light Company and North Carolina Eastern Municipal Power Agency (the applicants) for a license to operate the Shearon Harris Nuclear Power Plant Unit 1 (Docket No. 50-400), has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement reports the status of certain items that had not been resolved at the time of publication of the Safety Evaluation Report and Supplement Nos. 1 and 2

  1. 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...

  2. Safety Evaluation Report related to the operation of Watts Bar Nuclear Plant, Units 1 and 2 (Docket Numbers 50-390 and 50-391)

    International Nuclear Information System (INIS)

    1994-04-01

    This report supplements the Safety Evaluation Report (SER), NUREG-0847 (June 1982), Supplement No. 1 (September 1982), Supplement No. 2 (January 1984), Supplement No. 3 (January 1985), Supplement No. 4 (March 1985), Supplement No. 5 (November 1990), Supplement No. 6 (April 1991), Supplement No. 7 (September 1991), Supplement No. 8 (January 1992), Supplement No. 9 (June 1992), Supplement No. 10 (October 1992), Supplement No. 11 (April 1993), and Supplement No. 12 (October 1993), issued by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission with respect to the application filed by the Tennessee Valley Authority, as applicant and owner, for licenses to operate the Watts Bar Nuclear Plant, Units 1 and 2 (Docket Nos. 50-390 and 50-391). The facility is located in Rhea County, Tennessee, near the Watts Bar Dam on the Tennessee River. This supplement provides recent information regarding resolution of some of the outstanding and confirmatory items, and proposed license conditions identified in the SER. These issues relate to: Design criteria -- structures, components, equipment, and systems; Reactor; Instrumentation and controls; Electrical power systems; Auxiliary systems; Conduct of operations; Accident analysis; and Quality assurance

  3. Conformance to Regulatory Guide 1.97, Shearon Harris Nuclear Power Plant, Unit Nos. 1 and 2 (Docket Nos. 50-400 and 50-401)

    International Nuclear Information System (INIS)

    Stoffel, J.W.

    1985-09-01

    This EG and G Idaho, Inc. report reviews the submittals for Regulatory Guide 1.97, Revision 3, for Unit Nos. 1 and 2 of the Shearon Harris Nuclear Power Plant and identifies areas of nonconformance to the regulatory guide. Exceptions to Regulatory Guide 1.97 are evaluated and those areas where sufficient basis for acceptability is not provided are identified. 7 refs

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

    International Nuclear Information System (INIS)

    1986-10-01

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

  5. Conformance to Generic Letter 83-28, Items 3.1.3 and 3.2.3, Beaver Valley, Unit No. 1, North Anna, Unit Nos. 1 and 2, Surry Unit Nos. 1 and 2 (Docket Nos. 50-334, 50-338, 50-339, 50-280, and 50-281)

    International Nuclear Information System (INIS)

    Haroldsen, R.

    1985-09-01

    This report provides a review of the submittals for Beaver Valley, Unit No. 1, North Anna, Unit Nos. 1 and 2, and Surry, Unit Nos. 1 and 2, for conformance to Generic Letter 83-28, Items 3.1.3 and 3.2.3. The specific plants selected were reviewed as a group because of similarity in type and applicability of review items

  6. Safety evaluation report related to the operation of South Texas Project, Unit 2 (Docket No. 50-499)

    International Nuclear Information System (INIS)

    1989-03-01

    In April 1986 the staff of the US Nuclear Regulatory Commission issued its Safety Evaluation Report (NUREG-0781) regarding the application of Houston Lighting and Power Company (applicant and agent for the owners) for a license to operate South Texas Project, Units 1 and 2 (Docket Nos. 50-498 and 50-499). The facility is located in Matagorda County, Texas, west of the Colorado River, 8 miles north-northwest of the town of Matagorda and about 89 miles southwest of Houston. The first supplement to NUREG-0781 was issued in September 1986, the second supplement in January 1987, the third supplement in May 1987, the fourth supplement in July 1987, the fifth supplement in March 1988, and the sixth supplement in January 1989. This seventh supplement, which supports the issuance of a full-power license for Unit 2, provides updated information on the issues that had been considered previously as well as the evaluation of issues that have arisen since the sixth supplement was issued. The evaluation resolves all the issues necessary to support the issuance of a full-power license for Unit 2. 2 refs., 2 figs., 1 tab

  7. Safety Evaluation Report related to the operation of Diablo Canyon Nuclear Power Plant, Units 1 and 2 (Docket Nos. 50-275 and 50-323). Supplement No. 30

    International Nuclear Information System (INIS)

    1985-04-01

    Supplement 30 to the Safety Evaluation Report for the application by the Pacific Gas and Electric Company (PG and E) to operate the Diablo Canyon Nuclear Power Plant - Unit 2 (Docket No. 50-323) has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. SSER 30 reports on the staff's technical review and evaluation of the design and analysis of Unit 2 piping systems and pipe supports. The staff effort includes an evaluation of PG and E's treatment of issues raised during the Unit 1 design verification, actions resulting from low power License Condition 2.C.(11) in the Unit 1 low power license DPR-76 and the Unit 2 applicability and resolution of certain allegations related to piping and supports

  8. Design data and safety features of commercial nuclear power plants. Vol. IV. Dockets 50-452 through 50-503

    International Nuclear Information System (INIS)

    Heddleson, F.A.

    1975-03-01

    Design data, safety features, and site characteristics are summarized for 36 nuclear power units in 18 power stations in the United States. Six pages of data are presented for each plant consisting of thermal-hydraulic and nuclear factors, containment features, emergency-core-cooling systems, site features, circulating water system data, and miscellaneous factors. An aerial perspective is also presented for each plant. The volume covers reactors with dockets 50-452 through 50-503. (U.S.)

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

    International Nuclear Information System (INIS)

    1979-01-01

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

  10. South Texas project, Units 1 and 2: Final environmental statement (Docket Nos. 50-498 and 50-499)

    International Nuclear Information System (INIS)

    1975-03-01

    The proposed action is the issuance of a construction permit to the Houston Lighting and the Power Company, acting as Project manager on behalf of itself, the City Public Service Board of San Antonio, Central Power and Light Company, and the City of Austin, for the construction of the South Texas Project (STP) Units 1 and 2, located in Matagorda County, Texas. A total of 12,352 acres will be utilized for the STP site. Construction-related activities on the site will disturb about 610 acres not including the 7310 acres of inundated by the STP cooling lake and embankments, which will be constructed in conjunction with the project. Approximately 400 miles of transmission-line corridors will require about 5685 acres of land for the right-of-way. An access road and a railroad spur will affect about 60 acres. Farm to Market Road 521 will be rerouted north around the STP exclusion area. Plant construction will involve extensive community impacts. Two families will be displaced from the site. Traffic on local roads will increase due to construction and commuting activities. The influx of construction workers' families (2100 peak work force) is expected to cause no major housing or school problems. There will be a demand for increased services in Matagorda County. The proposed plan to alter Little Robbins Slough and the resultant 65% reduction in the watershed supplying freshwater inflow to the upper marsh may cause the displacement of numerous freshwater species and reduce its desirability as a nursery for estuarine-dependent organisms. Studies to determine the need for freshwater makeup will be required. 39 figs., 76 tabs

  11. Draft environmental statement related to the operation of Limerick Generating Station, Units 1 and 2. Docket Nos. 50-352 and 50-353

    International Nuclear Information System (INIS)

    1983-06-01

    This Draft Environmental Statement contains the second assessment of the environmental impact associated with the operation of the Limerick Generating Station, Units 1 and 2, pursuant to the National Environment Policy Act of 1969 (NEPA) and Title 10 of the Code of Federal Regulations, Part 51, as amended, of the Nuclear Regulatory Commission regulations. This statement examines the environment, environmental consequences and mitigating actions, and environmental and economic benefits and costs. Land use and terrestrial and aquatic ecological impacts will be small. Operational impacts to historic and archeological sites will be negligible. The effects of routine operations, energy transmission, and periodic maintenance of rights of way and transmission facilities should not jeopardize any populations of endangered or threatened species. No significant impacts are anticipated from normal operational releases of radioactivity

  12. 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

  13. 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

  14. Title list of documents made publicly available. Documents from October-December 1978 for Dockets 50-334 through STN 50-597

    International Nuclear Information System (INIS)

    1978-01-01

    This special edition of the Title List contains Docket 50 material from 1978 that has not appeared in previous issues of the Title List. The documents in this supplement are indexed by personal author, corporate source, and report number. The listings of this material on the domestic licensing of production and utilization facilities, divided into the categories used for filing and searching in the NRC Public Document Room, are presented

  15. 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...

  16. 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...

  17. Conformance to Regulatory Guide 1.97, Joseph M. Farley Nuclear Plant, Unit Nos. 1 and 2 (Docket No. 50-348 and 50-364)

    International Nuclear Information System (INIS)

    Stoffel, J.W.

    1985-05-01

    This EG and G Idaho, Inc., report reviews the submittals for Regulatory Guide 1.97 for Unit Nos. 1 and 2 of the Joseph M. Farley Nuclear Plant and identifies areas of nonconformance to the regulatory guide. Exceptions to Regulatory Guide 1.97 are evaluated and those areas where sufficient basis for acceptability is not provided are identified

  18. Safety evaluation report related to the operation of River Bend Station (Docket No. 50-458)

    International Nuclear Information System (INIS)

    1984-05-01

    The Safety Evaluation Report for the application filed by the Gulf States Utilities Company, as applicant and owner, for a license to operate the River Bend Station (Docket No. 50-458) has been prepared by the Office of Nuclear Reactor Regulation of US Nuclear Regulatory Commission. The facility is located near St. Francisville, Louisiana. 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

  19. 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

  20. 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

  1. 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

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

    International Nuclear Information System (INIS)

    1979-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    1979-01-01

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

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

    International Nuclear Information System (INIS)

    1979-01-01

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

  5. The NF-κB p65 and p50 homodimer cooperate with IRF8 to activate iNOS transcription

    International Nuclear Information System (INIS)

    Simon, Priscilla S.; Sharman, Sarah K.; Lu, Chunwan; Yang, Dafeng; Paschall, Amy V.; Tulachan, Sidhartha S.; Liu, Kebin

    2015-01-01

    observed that the p65/p65 and p50/p50 homodimers, not the canonical p65/p50 heterodimer, directly binds to the nos2 promoter to regulate iNOS expression in myeloid cells. IFNγ-induced IRF8 acts in concert with NF-κB to regulate iNOS expression in both colon carcinoma and myeloid cells. In myeloid cells, the NF-κB complexes that bind to the nos2 promoter are p65/p65 and p50/p50 homodimers

  6. Safety Evaluation Report related to the operation of Hope Creek Generating Station (Docket No. 50-354)

    International Nuclear Information System (INIS)

    1984-10-01

    The Safety Evaluation Report for the application filed by Public Service Electric and Gas Company, as applicant, for a license to operate the Hope Creek Generating Station (Docket No. 50-354), has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located in Salem County, New Jersey. 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

  7. Safety Evaluation Report related to the operation of Limerick Generating Station, Units 1 and 2 (Docket Nos. 50-352 and 50-353). Supplement No. 5

    International Nuclear Information System (INIS)

    1985-07-01

    In August 1983 the NRC issues its Safety Evaluation Report regarding the application for 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 and addressed several outstanding issues. SSER 1 also contains the comments made by the Advisory Committee on Reactor Safeguards in its interim report dated October 18, 1983. Supplement 2 was issued in October 1984. Supplement 3 was issued in October 1984 and addressed the remaining issues that required resolution before issuance of the operating licence for Unit 1. On October 26, 1984 a license (NPF-27) for Unit 1 was issued which was restricted to a five percent power level and contained conditions which required resolution prior to proceeding beyond the five percent power level. Supplement 4 issued in May 1985 addressed some of the technical issues and their associated license conditions, which required resolution prior to proceeding beyond the five percent power level. SSER 4 also contained the comments made by the Advisory Committee on Reactor Safeguards in its report dated November 6, 1984. This Supplement 5 to the SER addresses further issues that require resolution prior to proceeding beyond the five percent power level

  8. Safety Evaluation Report related to the operation of Limerick Generating Station, Units 1 and 2 (Docket Nos. 50-352 and 50-353). Supplement No. 4

    International Nuclear Information System (INIS)

    1985-05-01

    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. A license (NPF-27) for the operation of Limerick Unit 1 was issued on October 26, 1984. The license, which was restricted to a five percent power level, contained conditions which required resolution prior to proceeding beyond the five percent power level. This Supplement 4 to the SER addresses some of those technical issues and their associated license conditions which require resolution prior to proceeding beyond the five percent power level. The remaining issues to be addressed prior to proceeding beyond the five percent power level will be addressed in a later supplement to this report. This Supplement 4 to the SER also contains the comments made by the Advisory Committee on Reactor Safeguards in its report dated November 6, 1984, regarding full power operation of Limerick Unit 1

  9. Safety Evaluation Report related to the operation of Limerick Generating Station, Units 1 and 2 (Docket Nos. 50-352 and 50-353). Supplement No. 6

    International Nuclear Information System (INIS)

    1985-08-01

    In August 1983 the staff of the Nuclear Regulatory Commission issued its Safety Evaluation Report (NUREG-0991) regarding the application of the Philadelphia Electric Company (the licensee) for licenses to operate the Limerick Generating Station, Units 1 and 2, located on a site in Montgomery and Chester Counties, Pennsylvania. A license for the operation of Limerick Unit 1 was issued on October 26, 1984. The license, which was restricted to a five percent power level, contained conditions which required resolution prior to proceeding beyond the five percent power level. Supplement 4, issued in May 1985, addressed some of these issues. Supplement 4 also contained the comments made by the Advisory Committee on Reactor Safeguards in its report dated November 6, 1984, regarding full power operation of Limerick Unit 1. Supplement 5, issued in July 1985, and this Supplement 6 address further issues, principally the status of offsite emergency planning, that require resolution prior to proceeding beyond the five percent power level

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

    International Nuclear Information System (INIS)

    1986-05-01

    This report, Supplement No. 1 to the Safety Evaluation Report for the application filed by the Duquesne Light Company et al. (the applicant) for a license to operate the Beaver valley Power Station, Unit 2 (Docket No. 50-412), has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement reports the status of certain items that had not been resolved at the time the Safety Evaluation Report was published

  11. Safety Evaluation Report related to the operation of WPPSS Nuclear Project No. 2 (Docket No. 50-397)

    International Nuclear Information System (INIS)

    1984-04-01

    This report, Supplement No. 5 to the Safety Evaluation Report (SSER 5) on the Washington Public Power Supply System application for a license to operate WNP-2 (Docket No. 50-397), located in Benton County, Washington, approximately 12 miles north of Richland, Washington, has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement reports the status of certain items that had not been resolved at the time of publication of the Safety Evaluation Report and Supplements No. 1, 2, 3, and 4

  12. Safety Evaluation Report related to the operation of Beaver Valley Power Station, Unit 2 (Docket No. 50-412)

    International Nuclear Information System (INIS)

    1987-05-01

    This report, Supplement No. 5 to the Safety Evaluation Report for the application filed by the Duquesne Light Company et al. (the applicant) for a license to operate the Beaver Valley Power Station, Unit 2 (Docket No. 50-412), has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement reports the status of certain items that had not been resolved when the Safety Evaluation Report and its Supplements 1, 2, 3, and 4 were published

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

    International Nuclear Information System (INIS)

    1987-03-01

    This report, Supplement No. 4 to the Safety Evaluation Report for the application filed by the Duquesne Light Company et al. (the applicant) for a license to operate the Beaver Valley Power Station, Unit 2 (Docket No. 50-412), has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement reports the status of certain items that had not been resolved when the Safety Evaluation Report and its Supplements 1, 2, and 3 were published

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

    International Nuclear Information System (INIS)

    1987-08-01

    This report, Supplement No. 6 to the Safety Evaluation Report for the application filed by the Duquesne Light Company et al. (the licensee) for a license to operate the Beaver Valley Power Station, Unit 2 (Docket No. 50-412), has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement reports the status of certain items that had not been resolved when the Safety Evaluation Report and its Supplements 1, 2, 3, 4, and 5 were published

  15. 44 CFR 352.1 - Definitions.

    Science.gov (United States)

    2010-10-01

    ... 44 Emergency Management and Assistance 1 2010-10-01 2010-10-01 false Definitions. 352.1 Section 352.1 Emergency Management and Assistance FEDERAL EMERGENCY MANAGEMENT AGENCY, DEPARTMENT OF HOMELAND SECURITY PREPAREDNESS COMMERCIAL NUCLEAR POWER PLANTS: EMERGENCY PREPAREDNESS PLANNING § 352.1 Definitions...

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

    International Nuclear Information System (INIS)

    1987-07-01

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

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

    International Nuclear Information System (INIS)

    1982-02-01

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

  18. 9 CFR 352.17 - Transportation.

    Science.gov (United States)

    2010-01-01

    ... 9 Animals and Animal Products 2 2010-01-01 2010-01-01 false Transportation. 352.17 Section 352.17 Animals and Animal Products FOOD SAFETY AND INSPECTION SERVICE, DEPARTMENT OF AGRICULTURE AGENCY... CERTIFICATION EXOTIC ANIMALS AND HORSES; VOLUNTARY INSPECTION Exotic Animals § 352.17 Transportation. This shall...

  19. 7 CFR 352.14 - Costs.

    Science.gov (United States)

    2010-01-01

    ... 7 Agriculture 5 2010-01-01 2010-01-01 false Costs. 352.14 Section 352.14 Agriculture Regulations... OF AGRICULTURE PLANT QUARANTINE SAFEGUARD REGULATIONS § 352.14 Costs. All costs incident to the... assigned hours of duty at the usual places of duty shall be furnished without cost to the person requesting...

  20. 7 CFR 1250.352 - Reports.

    Science.gov (United States)

    2010-01-01

    ... 7 Agriculture 10 2010-01-01 2010-01-01 false Reports. 1250.352 Section 1250.352 Agriculture... Research and Promotion Order Reports, Books, and Records § 1250.352 Reports. Each handler subject to this subpart and other persons subject to section 7(c) of the act may be required to report to the Board...

  1. 22 CFR 35.2 - Definitions.

    Science.gov (United States)

    2010-04-01

    ... 22 Foreign Relations 1 2010-04-01 2010-04-01 false Definitions. 35.2 Section 35.2 Foreign Relations DEPARTMENT OF STATE CLAIMS AND STOLEN PROPERTY PROGRAM FRAUD CIVIL REMEDIES § 35.2 Definitions. (a..., record, or accounting or bookkeeping entry made— (1) With respect to a claim or to obtain the approval or...

  2. 12 CFR 352.6 - Employment.

    Science.gov (United States)

    2010-01-01

    ... 12 Banks and Banking 4 2010-01-01 2010-01-01 false Employment. 352.6 Section 352.6 Banks and... NONDISCRIMINATION ON THE BASIS OF DISABILITY § 352.6 Employment. No qualified individual with a disability shall, on the basis of that disability, be subjected to discrimination in employment in any program or activity...

  3. Safety Evaluation Report related to the operation of Beaver Valley Power Station, Unit 2 (Docket No. 50-412)

    International Nuclear Information System (INIS)

    1985-10-01

    This Safety Evaluation Report on the application filed by Duquesne Light Company, as applicant and agent for the owners, for a license to operate the Beaver Valley Power Station Unit 2 (Docket No. 50-412) has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located in Shippingport Borough, Beaver County, Pennsylvania, on the south bank of the Ohio River. Subject to the favorable resolution of the items discussed in this report, the staff concludes that the facility can be operated by the applicant without endangering the health and safety of the public

  4. 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

  5. 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

  6. 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

  7. 7 CFR 1207.352 - Confidential treatment.

    Science.gov (United States)

    2010-01-01

    ... 7 Agriculture 10 2010-01-01 2010-01-01 false Confidential treatment. 1207.352 Section 1207.352 Agriculture Regulations of the Department of Agriculture (Continued) AGRICULTURAL MARKETING SERVICE (MARKETING... PLAN Potato Research and Promotion Plan Reports, Books, and Records § 1207.352 Confidential treatment...

  8. Safety-Evaluation Report related to the construction of the Clinch River Breeder Reactor Plant. Docket No. 50-537

    International Nuclear Information System (INIS)

    1983-03-01

    The Safety-Evaluation Report for the application by the United States Department of Energy, Tennessee Valley Authority, and the Project Management Corporation, as applicants and owners, for a license to construct the Clinch River Breeder Reactor Plant (docket No. 50-537) has been prepared by the Office of Nuclear Reactor Regulation of the United States Nuclear Regulatory Commission. The facility will be located on the Clinch River approximately 12 miles southwest of downtown Oak Ridge and 25 miles west of Knoxville, Tennessee. Subject to resolution of the items discussed in this report, the staff concludes that the construction permit requested by the applicants should be issued

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

    International Nuclear Information System (INIS)

    1987-07-01

    This report supplements the Safety Evaluation Report (NUREG-1047, February 1985) for the application filed by Niagara Mohawk Power Corporation, as applicant and co-owner, for the license to operate Nine Mile Point Nuclear Station, Unit 2 (Docket No. 50-410). It has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located near Oswego, New York. This report supports the issuance of the full-power license for Nine Mile Point Nuclear Station, Unit No. 2

  10. Safety Evaluation Report related to the operation of Beaver Valley Power Station, Unit 2 (Docket No. 50-412). Supplement No. 2

    International Nuclear Information System (INIS)

    1986-08-01

    This report, Supplement No. 2 to the the Safety Evaluation Report for the application filed by the Duquesne Light Company, et al. (the applicant) for a license to operate the Beaver Valley Power Station Unit 2 (Docket No. 50-412), has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement reports the status of certain items that had not been resolved at the time the Safety Evaluation Report was published

  11. 32 CFR 352a.5 - Relationships.

    Science.gov (United States)

    2010-07-01

    ... 32 National Defense 2 2010-07-01 2010-07-01 false Relationships. 352a.5 Section 352a.5 National Defense Department of Defense (Continued) OFFICE OF THE SECRETARY OF DEFENSE (CONTINUED) ORGANIZATIONAL CHARTERS DEFENSE FINANCE AND ACCOUNTING SERVICE (DFAS) § 352a.5 Relationships. (a) In the performance of...

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

    International Nuclear Information System (INIS)

    1985-02-01

    The Safety Evaluation Report for the application filed by the Niagara Mohawk Power Corporation, as applicant and co-owner, for a license to operate the Nine Mile Point Nuclear Station, Unit 2 (Docket No. 50-410), has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located near Oswego, New York. Subject to favorable resolution of the items discussed in this report, the NRC staff concludes that the facility can be operated by the applicant without endangering the health and safety of the public

  13. 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

  14. EPA Administrative Enforcement Dockets

    Data.gov (United States)

    U.S. Environmental Protection Agency — The EPA Administrative Enforcement Dockets database contains the electronic dockets for administrative penalty cases filed by EPA Regions and Headquarters. Visitors...

  15. Safety evaluation report related to the operation of WPPSS Nuclear Project No. 2, Docket No. 50-397, Washington Public Power Supply System

    International Nuclear Information System (INIS)

    1982-12-01

    Supplement 2 to the Safety Evaluation Report for Washington Public Power Supply System's application for a license to operate WNP-2 (Docket No. 50-397), located in Benton County, Washington, approximately 12 miles north of Richland, Washington, has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement reports the status of certain items that had not been resolved at the time of publication of the Safety Evaluation Report and Supplement 1

  16. Safety evaluation report related to the operation of Millstone Nuclear Power Station, Unit No. 3 (Docket No. 50-423)

    International Nuclear Information System (INIS)

    1984-07-01

    The Safety Evaluation Report for the application filed by Northeast Nuclear Energy Company, as applicant and agent for the owners, for a license to operate the Millstone Nuclear Power Station Unit 3 (Docket No. 50-423), has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located in the town of Waterford, New London County, Connecticut, on the north shore of Long Island Sound. Subject to favorable resolution of the items discussed in this report, the NRC staff concludes that the facility can be operated by the applicant without endangering the health and safety of the public

  17. 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

  18. 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

  19. 42 CFR 412.352 - Budget neutrality adjustment.

    Science.gov (United States)

    2010-10-01

    ... 42 Public Health 2 2010-10-01 2010-10-01 false Budget neutrality adjustment. 412.352 Section 412.352 Public Health CENTERS FOR MEDICARE & MEDICAID SERVICES, DEPARTMENT OF HEALTH AND HUMAN SERVICES... § 412.352 Budget neutrality adjustment. For FY 1992 through FY 1995, CMS will determine an adjustment to...

  20. 21 CFR 352.10 - Sunscreen active ingredients.

    Science.gov (United States)

    2010-04-01

    ... 21 Food and Drugs 5 2010-04-01 2010-04-01 false Sunscreen active ingredients. 352.10 Section 352.10 Food and Drugs FOOD AND DRUG ADMINISTRATION, DEPARTMENT OF HEALTH AND HUMAN SERVICES (CONTINUED... until further notice. For the convenience of the user, the revised text is set forth as follows: § 352...

  1. 44 CFR 352.28 - Reimbursement.

    Science.gov (United States)

    2010-10-01

    ... 44 Emergency Management and Assistance 1 2010-10-01 2010-10-01 false Reimbursement. 352.28 Section... Participation § 352.28 Reimbursement. In accordance with Executive Order 12657, Section 6(d), and to the extent permitted by law, FEMA will coordinate full reimbursement, either jointly or severally, to the agencies...

  2. 21 CFR 352.3 - Definitions.

    Science.gov (United States)

    2010-04-01

    ...) and desired response to ultraviolet (UV) radiation. (1) Minimal sun protection product. A sunscreen... 21 Food and Drugs 5 2010-04-01 2010-04-01 false Definitions. 352.3 Section 352.3 Food and Drugs FOOD AND DRUG ADMINISTRATION, DEPARTMENT OF HEALTH AND HUMAN SERVICES (CONTINUED) DRUGS FOR HUMAN USE...

  3. 31 CFR 352.10 - Taxation.

    Science.gov (United States)

    2010-07-01

    ... 31 Money and Finance: Treasury 2 2010-07-01 2010-07-01 false Taxation. 352.10 Section 352.10 Money... Taxation. The interest paid on Series HH bonds is subject to all taxes imposed under the Internal Revenue..., whether Federal or State, but are exempt from all taxation now or hereafter imposed on the principal or...

  4. 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

  5. Safety Evaluation Report related to the operation of Millstone Nuclear Power Station Unit No. 3 (Docket No. 50-4423). Supplement No. 1

    International Nuclear Information System (INIS)

    1985-03-01

    In July 1984 staff of the Nuclear Regulatory Commission issued its Safety Evaluation Report regarding the application of Northeast Nuclear Energy Company (applicant and agent for the owners) for a license to operate Millstone Nuclear Power Station, Unit No. 3 (Docket 50-423). The facility is located in the town of Waterford, New London County, Connecticut, on the north shore of Long Island Sound. This first supplement to NUREG-1031 reports the status of certain items that remained unresolved at the time the Safety Evaluation Report was published

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

    International Nuclear Information System (INIS)

    1975-10-01

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

  7. 44 CFR 352.29 - Appeal process.

    Science.gov (United States)

    2010-10-01

    ... 44 Emergency Management and Assistance 1 2010-10-01 2010-10-01 false Appeal process. 352.29 Section 352.29 Emergency Management and Assistance FEDERAL EMERGENCY MANAGEMENT AGENCY, DEPARTMENT OF HOMELAND SECURITY PREPAREDNESS COMMERCIAL NUCLEAR POWER PLANTS: EMERGENCY PREPAREDNESS PLANNING Federal...

  8. 7 CFR 1210.352 - Confidential treatment.

    Science.gov (United States)

    2010-01-01

    ... 7 Agriculture 10 2010-01-01 2010-01-01 false Confidential treatment. 1210.352 Section 1210.352 Agriculture Regulations of the Department of Agriculture (Continued) AGRICULTURAL MARKETING SERVICE (MARKETING... treatment. (a) All information obtained from the books, records, or reports required to be maintained under...

  9. 24 CFR 92.352 - Environmental review.

    Science.gov (United States)

    2010-04-01

    ... 24 Housing and Urban Development 1 2010-04-01 2010-04-01 false Environmental review. 92.352... Development HOME INVESTMENT PARTNERSHIPS PROGRAM Other Federal Requirements § 92.352 Environmental review. (a) General. The environmental effects of each activity carried out with HOME funds must be assessed in...

  10. 24 CFR 982.352 - Eligible housing.

    Science.gov (United States)

    2010-04-01

    ... 24 Housing and Urban Development 4 2010-04-01 2010-04-01 false Eligible housing. 982.352 Section 982.352 Housing and Urban Development Regulations Relating to Housing and Urban Development (Continued) OFFICE OF ASSISTANT SECRETARY FOR PUBLIC AND INDIAN HOUSING, DEPARTMENT OF HOUSING AND URBAN DEVELOPMENT...

  11. 42 CFR 35.2 - Compliance with hospital rules.

    Science.gov (United States)

    2010-10-01

    ... EXAMINATIONS HOSPITAL AND STATION MANAGEMENT General § 35.2 Compliance with hospital rules. All patients and visitors in stations and hospitals of the Service are expected to comply with the rules and instructions... 42 Public Health 1 2010-10-01 2010-10-01 false Compliance with hospital rules. 35.2 Section 35.2...

  12. 40 CFR 52.352 - Interstate transport.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 3 2010-07-01 2010-07-01 false Interstate transport. 52.352 Section 52...) APPROVAL AND PROMULGATION OF IMPLEMENTATION PLANS Colorado § 52.352 Interstate transport. Addition to the Colorado State Implementation Plan of the Colorado Interstate Transport SIP regarding the 1997 8-Hour Ozone...

  13. 42 CFR 441.352 - State assurances.

    Science.gov (United States)

    2010-10-01

    ... expended for home and community-based services. The State must provide for an independent audit f its... 42 Public Health 4 2010-10-01 2010-10-01 false State assurances. 441.352 Section 441.352 Public Health CENTERS FOR MEDICARE & MEDICAID SERVICES, DEPARTMENT OF HEALTH AND HUMAN SERVICES (CONTINUED...

  14. 21 CFR 352.73 - Determination of SPF value.

    Science.gov (United States)

    2010-04-01

    ... 21 Food and Drugs 5 2010-04-01 2010-04-01 false Determination of SPF value. 352.73 Section 352.73... Procedures § 352.73 Determination of SPF value. (a)(1) The following erythema action spectrum shall be used... used in calculating the SPF. (c) Determination of individual SPF values. A series of UV radiation...

  15. 31 CFR 352.13 - Fiscal agents.

    Science.gov (United States)

    2010-07-01

    ... 31 Money and Finance: Treasury 2 2010-07-01 2010-07-01 false Fiscal agents. 352.13 Section 352.13 Money and Finance: Treasury Regulations Relating to Money and Finance (Continued) FISCAL SERVICE... Reserve Bank of Kansas City, 925 Grand Avenue, Kansas City, MO 64198 Dallas, San Francisco, Kansas City...

  16. 9 CFR 3.52 - Facilities, outdoor.

    Science.gov (United States)

    2010-01-01

    ... 9 Animals and Animal Products 1 2010-01-01 2010-01-01 false Facilities, outdoor. 3.52 Section 3.52 Animals and Animal Products ANIMAL AND PLANT HEALTH INSPECTION SERVICE, DEPARTMENT OF AGRICULTURE ANIMAL... outdoors when the atmospheric temperature falls below 40 °F. (d) Protection from predators. Outdoor housing...

  17. Procedure for Electronic Management of Rulemaking and Other Docketed Records in the Federal Docket Management System

    Science.gov (United States)

    This procedure identifies the specific requirements, processes and supporting documents EPA uses to electronically manage rulemaking and other docketed records in the Federal Docket Management System (FDMS).

  18. Draft environmental statement related to the proposed manufacture of floating nuclear power plants (Docket No. STN 50-437)

    International Nuclear Information System (INIS)

    1976-10-01

    The proposed action is the issuance of a manufacturing license to Offshore Power Systems for the startup and operation of a proposed manufacturing facility located at Blount Island, Jacksonville, Florida (Docket No. STN 50-436). No nuclear fuel will be handled or stored at the manufacturing site. The plants will be fueled after they have been towed to and moored within breadwaters at specific offshore locations designated by the purchaser and after an operating license has been issued by the Nuclear Regulatory Commision. Each nuclear generating plant, mounted on a floating platform, has a net capacity of 1150 MWe. This energy is provided by a pressurized water reactor steam supply system consisting of a Westinghouse four-loop 3425 MWt unit with an ice-condenser containment system. When one or more of these units is located within a single breakwater, the installation is designated an offshore power station. 3 figs., 1 tab

  19. 24 CFR 983.352 - Vacancy payment.

    Science.gov (United States)

    2010-04-01

    ... PROJECT-BASED VOUCHER (PBV) PROGRAM Payment to Owner § 983.352 Vacancy payment. (a) Payment for move-out month. If an assisted family moves out of the unit, the owner may keep the housing assistance payment... 24 Housing and Urban Development 4 2010-04-01 2010-04-01 false Vacancy payment. 983.352 Section...

  20. Safety evaluation report related to the operation of Shearon Harris Nuclear Power Plant, Unit No. 1 (Docket No. STN 50-400). Supplement No. 1

    International Nuclear Information System (INIS)

    1984-06-01

    This report, Supplement No. 1 to the Safety Evaluation Report for the application filed by the Carolina Power and Light Company and North Carolina Eastern Municipal Power Agency (the applicant) for license to operate the Shearon Harris Nuclear Power Plant Unit 1 (Docket No. 50-400), has been prepared by the Office of Nuclear Reactor Regulation of the U.S. Nuclear Regulatory Commission. This supplement reports the status of certain items that had not been resolved at the time of publication of the Safety Evaluation Report

  1. 5 CFR 352.304 - International organizations covered.

    Science.gov (United States)

    2010-01-01

    ... REEMPLOYMENT RIGHTS Detail and Transfer of Federal Employees to International Organizations § 352.304... public international organization or international organization preparatory commission only when the... 5 Administrative Personnel 1 2010-01-01 2010-01-01 false International organizations covered. 352...

  2. Safety Evaluation Report related to the operation of Shearon Harris Nuclear Power Plant, Unit No. 1 (Docket No. STN 50-400). Supplement No. 2

    International Nuclear Information System (INIS)

    1985-06-01

    This report, Supplement No. 2 to the Safety Evaluation Report for the application filed by the Carolina Power and Light Company and North Carolina Eastern Municipal Power Agency (the applicants) for a license to operate the Shearon Harris Nuclear Power Plant Unit 1 (Docket No. 50-400), has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement reports the status of certain items that had not been resolved at the time of publication of the Safety Evaluation Report and Supplement No. 1

  3. 7 CFR 1781.17 - Docket preparation and processing.

    Science.gov (United States)

    2010-01-01

    ... preparation, with a list of documents to be included in the docket. (3) Objectives of the docket. The docket.... (b) Loan processing by State Office—(1) Review of the docket. The processing office will check the... for authorized purposes. (v) Actions are in compliance with requirements of applicable Federal and...

  4. 22 CFR 102.27 - Docket.

    Science.gov (United States)

    2010-04-01

    ... 22 Foreign Relations 1 2010-04-01 2010-04-01 false Docket. 102.27 Section 102.27 Foreign Relations... other than the Director of the Office of Aviation and summaries of oral communications prepared in...) All comments submitted under this subpart and placed in the docket, are available for public...

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

    International Nuclear Information System (INIS)

    1976-10-01

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

  6. Draft environmental statement related to construction of Erie Nuclear Plant, Units 1 and 2: (Docket Nos. STN 50-580 and STN 50-581)

    International Nuclear Information System (INIS)

    1977-11-01

    The proposed action is the issuance of construction permits to the Ohio Edison Company, acting on behalf of itself, the Cleveland Electric Illuminating Company, Duquesne Light Company, Pennsylvania Power Company, and the Toledo Edison Company, for the construction of the Erie Nuclear Plant Units 1 and 2, located in Erie County, Ohio. A total of 704 hectares (ha) (1740 acres) will be used for the Erie plant site. Construction-related activities on the primary site will disturb about 223 ha (551 acres). Approximately 641 ha (1584 acres) will be required for transmission line rights-of-way. The 3.86-km (2.4-mile) intake and discharge pipeline land corridor will involve alteration of approximately 13 ha (32 acres) of corridor and 1 ha (2.5 acres) for shore facilities. Also, 3.9 ha (9.6 acres) of lake bottom will be disturbed to provide 15-m-wide (50-ft-wide) trenches and an additional 15-m-wide (50-ft-wide) area for storage of excavated material for subsequent backfill for the 701-m (2300-ft) intake and 579-m (1900-ft) discharge lines. Plant construction will involve some community impacts. No residents will be displaced from the site property. Traffic on local roads will increase due to construction and commuting activities. The influx of construction workers' families (a peak work force of about 2700) is expected to cause no major housing or school problems. It is assumed that aquatic organisms entrained in the circulating water system will be killed due to thermal and mechanical shock. The maximum impact based on the population densities of phytoplankton and zooplankton organisms in the adjacent lake area will be the destruction of 0.1% of the entrainable organisms from the lake water. The entrainment of fish larvae will not constitute a significant impact on the lake fishery. 62 figs., 32 tabs

  7. 48 CFR 352.231-70 - Precontract costs.

    Science.gov (United States)

    2010-10-01

    ... 48 Federal Acquisition Regulations System 5 2010-10-01 2010-10-01 false Precontract costs. 352.231... SOLICITATION PROVISIONS AND CONTRACT CLAUSES Text of Provisions and Clauses 352.231-70 Precontract costs. As prescribed in 48 CFR 1331.205-32, insert the following clause: Precontract Costs (APR 2010) The contractor is...

  8. 31 CFR 352.0 - Offering of bonds.

    Science.gov (United States)

    2010-07-01

    ... 31 Money and Finance: Treasury 2 2010-07-01 2010-07-01 false Offering of bonds. 352.0 Section 352.0 Money and Finance: Treasury Regulations Relating to Money and Finance (Continued) FISCAL SERVICE... terminate at the close of business on August 31, 2004. [69 FR 40318, July 2, 2004] ...

  9. 48 CFR 352.224-70 - Privacy Act.

    Science.gov (United States)

    2010-10-01

    ... 48 Federal Acquisition Regulations System 4 2010-10-01 2010-10-01 false Privacy Act. 352.224-70... SOLICITATION PROVISIONS AND CONTRACT CLAUSES Texts of Provisions and Clauses 352.224-70 Privacy Act. As prescribed in 324.103(b)(2), the Contracting Officer shall insert the following clause: Privacy Act (January...

  10. 76 FR 40945 - Entergy Nuclear Indian Point 2, LLC, Entergy Nuclear Indian Point 3, LLC, Entergy Nuclear...

    Science.gov (United States)

    2011-07-12

    ... NUCLEAR REGULATORY COMMISSION [NRC-2011-0150; Docket Nos. 50-003, 50-247, and 50-286; License Nos. DPR-5, DPR-26, and DPR-64] Entergy Nuclear Indian Point 2, LLC, Entergy Nuclear Indian Point 3, LLC, Entergy Nuclear Operations, Inc.; Receipt of Request for Action Notice is hereby given that by petition...

  11. Safety Evaluation Report related to the operation of Millstone Nuclear Power Station, Unit No. 3 (Docket No. 50-423). Supplement No. 3

    International Nuclear Information System (INIS)

    1985-11-01

    This report supplements the Safety Evaluation Report (NUREG-1031) issued in July 1984, Supplement 1 issued in March 1985, and Supplement 2 issued in September 1985 by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission with respect to the application filed by Northeast Nuclear Energy Company (applicant and agent for the owners) for a license to operate Millstone Nuclear Power Station, Unit No. 3 (Docket 50-423). The facility is located in the Town of Waterford, New London County, Connecticut, on the north shore of Long Island Sound. This supplement provides more recent information regarding resolution or updating of some of the open and confirmatory items and license conditions identified in the Safety Evaluation Report

  12. Power Reactor Docket Information

    International Nuclear Information System (INIS)

    1976-08-01

    A listing of citations and subject indexing for documentation associated with the regulation of commercial nuclear facilities is presented. This documentation for the most part is that submitted to the U.S. Nuclear Regulatory Commission in accordance with regulatory processes in support of applications for construction permits and operating licenses. The citations are listed in Docket Number order. The citations are preceded by two tables of contents that allow the correlation of Docket Numbers and Facility Names. An alphabetic subject index follows the citations

  13. Safety evaluation report related to the operation of Palo Verde nuclear generating station, Units 1, 2, and 3. Docket Nos. STN 50-528, STN 50-529, and STN 50-530, Arizona Public Service Company

    International Nuclear Information System (INIS)

    1982-05-01

    On November 13, 1981, the Nuclear Regulatory Commission (NRC) staff issued its Safety Evaluation Report (SER) relating to the application for licenses to operate the Palo Verde Nuclear Generating Station, Unit Nos. 1, 2 and 3 (PVNGS 1-3); Supplement No. 1 to the SER was issued on February 4, 1982. In the SER and Supplement No. 1, the staff identified certain issues where either further information was required of the applicant or additional staff effort was necessary to complete the review of the application. The purpose of this supplement is to update the SER by providing (1) the evaluation of additional information submitted by the applicant since Supplement No. 1 to the SER was issued, and (2) the evaluation of the matters that the staff had under review and Supplement No. 1 was issued

  14. Safety Evaluation Report related to the operation of Wolf Creek Generating Station, Unit No. 1 (Docket No. STN 50-482). Supplement No. 6

    International Nuclear Information System (INIS)

    1985-06-01

    This report supplements the Safety Evaluation Report (SER) for the application filed by the Kansas Gas and Electric Company, as applicant and agent for the owners, for a license to operate the Wolf Creek Generating Station, Unit 1 (Docket No. STN 50-482). The facility is located in Coffey County, Kansas. This supplement provides recent information regarding resolution of the license conditions identified in the SER. Because of the favorable resolution of the items discussed in this report, the staff concludes that the facility can be operated by the licensee at power levels greater than 5% without endangering the health and safety of the public

  15. 75 FR 80496 - Registration Review; Pesticide Dockets Opened for Review and Comment and Other Docket Actions

    Science.gov (United States)

    2010-12-22

    ... in hard copy form. Publicly available docket materials are available either in the electronic docket at http://www.regulations.gov , or, if only available in hard copy, at the OPP Regulatory Public... 155, subpart C. Section 3(g) of FIFRA provides, among other things, that the registrations of...

  16. 76 FR 38166 - Registration Review; Pesticide Dockets Opened for Review and Comment and Other Docket Actions

    Science.gov (United States)

    2011-06-29

    ... in hard copy form. Publicly available docket materials are available either in the electronic docket at http://www.regulations.gov , or, if only available in hard copy, at the OPP Regulatory Public.... Section 3(g) of FIFRA provides, among other things, that the registrations of pesticides are to be...

  17. 77 FR 18810 - Registration Review; Pesticide Dockets Opened for Review and Comment and Other Docket Act

    Science.gov (United States)

    2012-03-28

    ... and will be publicly available only in hard copy form. Publicly available docket materials are available either in the electronic docket at http://www.regulations.gov , or, if only available in hard copy.... Section 3(g) of FIFRA provides, among other things, that the registrations of pesticides are to be...

  18. 76 FR 60822 - Registration Review; Pesticide Dockets Opened for Review and Comment and Other Docket Actions

    Science.gov (United States)

    2011-09-30

    ... placed on the Internet and will be publicly available only in hard copy form. Publicly available docket... available in hard copy, at the OPP Regulatory Public Docket in Rm. S-4400, One Potomac Yard (South Bldg... 155, subpart C. Section 3(g) of FIFRA provides, among other things, that the registrations of...

  19. Safety Evaluation Report related to the operation of Millstone Nuclear Power Station, Unit No. 3 (Docket No. 50-423). Supplement No. 4

    International Nuclear Information System (INIS)

    1985-11-01

    This report supplements the Safety Evaluation Report (NUREG-1031) issued in July 1984, Supplement 1 issued in March 1985, Supplement 2 issued in September 1985, and Supplement 3 issued in November 1985, by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission with respect to the application filed by Northeast Nuclear Energy Company (applicant and agent for the owners) for a license to operate Millstone Nuclear Power Station, Unit No. 3 (Docket 50-423). The facility is located in the Town of Waterford, New London County, Connecticut, on the north shore of Long Island Sound. This supplement provides more recent information supporting the license for initial criticality and power ascension to 5% power operation for Millstone 3. 37 refs., 10 tabs

  20. Safety Evaluation Report related to the operation of Wolf Creek Generating Station, Unit No. 1 (Docket No. STN 50-482). Supplement No. 5

    International Nuclear Information System (INIS)

    1985-03-01

    This report supplements the Safety Evaluation Report (SER) for the application filed by the Kansas Gas and Electric Company, as applicant and agent for the owners, for a license to operate the Wolf Creek Generating Station, Unit 1 (Docket No. STN 50-482). The facility is located in Coffey County, Kansas. This supplement has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission and provides recent information regarding resolution of the open items identified in the SER. Because of the favorable resolution of the items discussed in this report, the staff concludes that the facility can be operated by the applicant without endangering the health and safety of the public

  1. 78 FR 14361 - In the Matter of Luminant Generation Company LLC, Comanche Peak Nuclear Power Plant, Units 1 and...

    Science.gov (United States)

    2013-03-05

    ... NUCLEAR REGULATORY COMMISSION [NRC-2012-0310; Docket Nos. 50-445 and 50-446; License Nos. NPF-87 and NPF-89] In the Matter of Luminant Generation Company LLC, Comanche Peak Nuclear Power Plant, Units... Nuclear Power Plant, Units 1 and 2 (CPNPP), and its Independent Spent Fuel Storage Installation Facility...

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

    International Nuclear Information System (INIS)

    1986-07-01

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

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

    International Nuclear Information System (INIS)

    1975-04-01

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

  4. 48 CFR 352.239-71 - Standard for encryption language.

    Science.gov (United States)

    2010-10-01

    ... language. 352.239-71 Section 352.239-71 Federal Acquisition Regulations System HEALTH AND HUMAN SERVICES... Standard for encryption language. As prescribed in 339.101(d)(2), the Contracting Officer shall insert the following clause: Standard for Encryption Language (January 2010) (a) The Contractor shall use Federal...

  5. 21 CFR 352.20 - Permitted combinations of active ingredients.

    Science.gov (United States)

    2010-04-01

    ... 21 Food and Drugs 5 2010-04-01 2010-04-01 false Permitted combinations of active ingredients. 352.20 Section 352.20 Food and Drugs FOOD AND DRUG ADMINISTRATION, DEPARTMENT OF HEALTH AND HUMAN... effective date was stayed until further notice. For the convenience of the user, the text is set forth as...

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

    International Nuclear Information System (INIS)

    1986-05-01

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

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

    International Nuclear Information System (INIS)

    1986-02-01

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

  8. 48 CFR 352.237-71 - Crime Control Act-reporting of child abuse.

    Science.gov (United States)

    2010-10-01

    ...-reporting of child abuse. 352.237-71 Section 352.237-71 Federal Acquisition Regulations System HEALTH AND... Clauses 352.237-71 Crime Control Act—reporting of child abuse. As prescribed in 337.103-70(b), the Contracting Officer shall insert the following clause: Crime Control Act of 1990—Reporting of Child Abuse...

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

    International Nuclear Information System (INIS)

    1988-11-01

    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

  10. Safety evaluation report related to the operation of Millstone Nuclear Power Station, Unit No. 3 (Docket No. 50-423). Supplement No. 5

    International Nuclear Information System (INIS)

    1986-01-01

    This report supplements the Safety Evaluation Report (NUREG-1031) issued in July 1984, Supplement 1 issued in March 1985, Supplement 2 issued in September 1985, Supplement 3 issued in November 1985, and Supplement 4 issued in November 1985 by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission with respect to the application filed by Northeast Nuclear Energy Company (licensee and agent for the owners) for a license to operate Millstone Nuclear Power Station, Unit No. 3 (Docket 50-423). The supplement provides more recent information regarding resolution of license conditions identified in the SER. Because of the favorable resolution of the items discussed in this report, the staff concludes that Millstone Nuclear Power Station, Unit No. 3, can be operated by the licensee at power levels greater than 5% without endangering the health and safety of the public. 13 refs

  11. 32 CFR Appendix to Part 352a - Delegations of Authority

    Science.gov (United States)

    2010-07-01

    ...) ORGANIZATIONAL CHARTERS DEFENSE FINANCE AND ACCOUNTING SERVICE (DFAS) Pt. 352a, App. Appendix to Part 352a..., Directives, and Instructions, the Director, Defense Finance and Accounting Service (DFAS), or in the absence... promulgation of common accounting and finance regulations, instructions, and reference documents, and changes...

  12. 48 CFR 352.234-4 - Partial earned value management system.

    Science.gov (United States)

    2010-10-01

    ... management system. 352.234-4 Section 352.234-4 Federal Acquisition Regulations System HEALTH AND HUMAN....234-4 Partial earned value management system. As prescribed in 334.203-70(d), the Contracting Officer shall insert the following clause: Partial Earned Value Management System (October 2008) (a) The...

  13. Safety evaluation report related to the operation of Sequoyah Nuclear Plant, Units 1 and 2, Docket Nos. 50-327 and 50-328, Tennessee Valley Authority. Supplement No. 4

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1981-01-01

    On September 17, 1980, the Nuclear Regulatory Commission (NRC) issued the facility operating license DPR-77 to the Tennessee Valley Authority for the Sequoyah Nuclear Plant, Unit 1, located in Hamilton County, Tennessee. The license authorized operation of Unit 1 at 100 percent power; however, a license condition regarding the adequacy of the hydrogen control system was included that required resolution by January 31, 1981. The purpose of Supplement No. 4 to the SER is to further update our Safety Evaluation Reports on the hydrogen control measures (Section 22.2, II.B.7), and to comply with the license condition which is as follows: 'By January 31, 1981, TVA shall by testing and analysis show to the satisfaction of the NRC staff that an interim hydrogen control system will provide with reasonable assurance protection against breach of containment in the event that a substantial quantity of hydrogen is generated.' TVA submitted on December 11, 1980, the first quarterly report on the research program for hydrogen control. Also, TVA revised volume 2 of the Sequoyah Core Degradation Program Report to incorporate additional information on the overall program. Section II.B.7 of Supplement No. 4 responds to the license condition. Each section is supplementary to and not in lieu of discussion in the Safety Evaluation Report and Supplements Nos. 1, 2, and 3, except where specifically noted. Supplements No. 2 and 3 to the Safety Evaluation Report provided a basis for concluding that the full-power licensing of Sequoyah Unit 1 need not await completion of ongoing work on hydrogen control measures. This supplement concludes that operation of the IDIS for an interim period of one year is appropriate.

  14. Power Reactor Docket Information. Annual cumulation (citations)

    International Nuclear Information System (INIS)

    1977-12-01

    An annual cumulation of the citations to the documentation associated with civilian nuclear power plants is presented. This material is that which is submitted to the U.S. Nuclear Regulatory Commission in support of applications for construction and operating licenses. Citations are listed by Docket number in accession number sequence. The Table of Contents is arranged both by Docket number and by nuclear power plant name

  15. 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

  16. 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

  17. 48 CFR 352.234-3 - Full earned value management system.

    Science.gov (United States)

    2010-10-01

    ... management system. 352.234-3 Section 352.234-3 Federal Acquisition Regulations System HEALTH AND HUMAN....234-3 Full earned value management system. As prescribed in 334.203-70(c), the Contracting Officer shall insert the following clause: Full Earned Value Management System (October 2008) (a) The Contractor...

  18. 9 CFR 352.6 - Denial or withdrawal of inspection service.

    Science.gov (United States)

    2010-01-01

    ... improper means; (4) has knowingly represented that any exotic animal carcass, or exotic animal product, has... 9 Animals and Animal Products 2 2010-01-01 2010-01-01 false Denial or withdrawal of inspection service. 352.6 Section 352.6 Animals and Animal Products FOOD SAFETY AND INSPECTION SERVICE, DEPARTMENT OF...

  19. 32 CFR 352a.1 - Purpose.

    Science.gov (United States)

    2010-07-01

    ... DEFENSE FINANCE AND ACCOUNTING SERVICE (DFAS) § 352a.1 Purpose. Pursuant to the authority vested in the... Finance and Accounting Service (DFAS) as an Agency of the Department of Defense with responsibilities...

  20. 76 FR 1197 - Arizona Public Service Company, Palo Verde Nuclear Generating Station; Notice of Availability of...

    Science.gov (United States)

    2011-01-07

    ... NUCLEAR REGULATORY COMMISSION [Docket Nos. 50-528, 50-529, 50-530; NRC-2009-0012] Arizona Public Service Company, Palo Verde Nuclear Generating Station; Notice of Availability of the Final Supplement 43... of operation for the Palo Verde Nuclear Generating Station (PVNGS). Possible alternatives to the...

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

    International Nuclear Information System (INIS)

    1977-02-01

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

  2. Callaway Plant Units 1 and 2: Final environmental statement (Docket Nos. STN 50-483 and STN 50-486)

    International Nuclear Information System (INIS)

    1975-03-01

    The proposed action is the issuance of a construction permit to the Union Electric company for the construction of the Callaway Plant Units 1 and 2. The Callaway Plant, located 5 m north of the Missouri River in Callaway County, Missouri, will employ a pressurized water reactor to produce up to 3425 megawatts thermal (MWt) from each unit. A steam turbine-generator will use the heat to provide 1120 MWe (net) of electrical power capacity. A stretch power level of 3579 MWt (1160 MWe) is anticipated at a future date and is considered in the assessments contained in this statement. The exhaust steam will be cooled in a closed cycle mode, with water from the Missouri River. Constructing the plant and adjacent facilities will disturb an area of about 600 acres, of which less than 300 acres will be occupied by the operating plant and road and rail access to it. The land presently consists of cropland, pasture and forest. About 1140 acres will be required for the transmission line routes. The land presently consists of forest, pasture and cropland. No unique land usage is involved. Siltation and erosion during construction generally will have minor adverse effects, based upon the extent of protection measures the applicant plans to impose. The effect on Logan Creek is expected to be minor, but further assessment is needed, including possible additional precautions. About 14% of the benthic invertebrate population will be lost in the rectangular area defined by the river width and the length of the area to be dredged for shoreline structures. 28 figs., 53 tabs

  3. Technical specifications: Diablo Canyon Nuclear Power Plant, Units 1 and 2 (Docket Nos. 50-275 and 50-323)

    International Nuclear Information System (INIS)

    1985-08-01

    Safety limits and limiting safety system settings are presented for the reactivity control systems; power distribution limits; instrumentation; reactor coolant system; emergency core cooling system; containment systems; plant systems; electrical power systems; refueling operations; special test exceptions; radioactive effluents; and radiological environmental monitoring

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

    International Nuclear Information System (INIS)

    1975-10-01

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

  5. 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

  6. 78 FR 40200 - Duke Energy Carolinas, LLC, Oconee Nuclear Station Units 1, 2, and 3; Independent Spent Fuel...

    Science.gov (United States)

    2013-07-03

    ... NUCLEAR REGULATORY COMMISSION [Docket Nos. 72-1004, 72-40, 50-269, 50-270, and 50-287; NRC-2013-0135] Duke Energy Carolinas, LLC, Oconee Nuclear Station Units 1, 2, and 3; Independent Spent Fuel Storage Installation; Environmental Assessment and Finding of No Significant Impact AGENCY: Nuclear...

  7. 78 FR 45575 - Duke Energy Carolinas, LLC; Oconee Nuclear Station Units 1, 2, and 3; Independent Spent Fuel...

    Science.gov (United States)

    2013-07-29

    ... NUCLEAR REGULATORY COMMISSION [Docket Nos.: 72-1004, 72-40, 50-269, 50-270, 50-287; and NRC-2013- 0135] Duke Energy Carolinas, LLC; Oconee Nuclear Station Units 1, 2, and 3; Independent Spent Fuel Storage Installation AGENCY: Nuclear Regulatory Commission. ACTION: Exemption; issuance. SUMMARY: The NRC...

  8. 75 FR 13606 - Arizona Public Service Company, Palo Verde Nuclear Generating Station, Units 1, 2, and 3...

    Science.gov (United States)

    2010-03-22

    ... NUCLEAR REGULATORY COMMISSION [Docket Nos. STN 50-528, STN 50-529, and STN 50-530; NRC-2010-0114] Arizona Public Service Company, Palo Verde Nuclear Generating Station, Units 1, 2, and 3; Environmental...-74, issued to Arizona Public Service Company (APS, the licensee), for operation of the Palo Verde...

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

    International Nuclear Information System (INIS)

    1986-09-01

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

  10. 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

  11. 42 CFR 422.352 - Basic requirements.

    Science.gov (United States)

    2010-10-01

    ...) MEDICARE PROGRAM MEDICARE ADVANTAGE PROGRAM Provider-Sponsored Organizations § 422.352 Basic requirements... effectively controlled by the provider or, in the case of a group, by one or more of the affiliated providers... provider or the affiliated providers responsible for operating the PSO. Substantial proportion means— (1...

  12. 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...

  13. 32 CFR 352a.6 - Authorities.

    Science.gov (United States)

    2010-07-01

    ... CHARTERS DEFENSE FINANCE AND ACCOUNTING SERVICE (DFAS) § 352a.6 Authorities. The Director, DFAS, is specifically delegated authority to: (a) Represent the C, DoD, on finance and accounting matters. (b) Have free... Agencies concerning finance and accounting activities, as necessary. (c) Enter into agreements with DoD...

  14. 76 FR 56968 - [Docket No. FAA-2011-0490; Airspace Docket No. 11-AWP-5

    Science.gov (United States)

    2011-09-15

    ... DEPARTMENT OF TRANSPORTATION Federal Aviation Administration 14 CFR Part 71 [Docket No. FAA-2011... Administration (FAA), DOT. ACTION: Final rule. SUMMARY: This action modifies Class E airspace at Tonopah, NV, to... reference action under 1 CFR Part 51, subject to the annual revision of FAA Order 7400.9 and publication of...

  15. 75 FR 75704 - Pacific Gas and Electric Company (Diablo Canyon Nuclear Power Plant, Units 1 And 2); Notice of...

    Science.gov (United States)

    2010-12-06

    ... NUCLEAR REGULATORY COMMISSION [Docket Nos. 50-275-LR; 50-323-LR] Pacific Gas and Electric Company (Diablo Canyon Nuclear Power Plant, Units 1 And 2); Notice of Appointment of Adjudicatory Employee... Seismologist, Office of Nuclear Material Safety and Safeguards, has been appointed as a Commission adjudicatory...

  16. 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...

  17. Histidine 352 (His352 and tryptophan 355 (Trp355 are essential for flax UGT74S1 glucosylation activity toward secoisolariciresinol.

    Directory of Open Access Journals (Sweden)

    Kaushik Ghose

    Full Text Available Flax secoisolariciresinol diglucoside (SDG lignan is a natural phytoestrogen for which a positive role in metabolic diseases is emerging. Until recently however, much less was known about SDG and its monoglucoside (SMG biosynthesis. Lately, flax UGT74S1 was identified and characterized as an enzyme sequentially glucosylating secoisolariciresinol (SECO into SMG and SDG when expressed in yeast. However, the amino acids critical for UGT74S1 glucosyltransferase activity were unknown. A 3D structural modeling and docking, site-directed mutagenesis of five amino acids in the plant secondary product glycosyltransferase (PSPG motif, and enzyme assays were conducted. UGT74S1 appeared to be structurally similar to the Arabidopsis thaliana UGT72B1 model. The ligand docking predicted Ser357 and Trp355 as binding to the phosphate and hydroxyl groups of UDP-glucose, whereas Cys335, Gln337 and Trp355 were predicted to bind the 7-OH, 2-OCH3 and 17-OCH3 of SECO. Site-directed mutagenesis of Cys335, Gln337, His352, Trp355 and Ser357, and enzyme assays revealed an alteration of these binding sites and a significant reduction of UGT74S1 glucosyltransferase catalytic activity towards SECO and UDP-glucose in all mutants. A complete abolition of UGT74S1 activity was observed when Trp355 was substituted to Ala355 and Gly355 or when changing His352 to Asp352, and an altered metabolite profile was observed in Cys335Ala, Gln337Ala, and Ser357Ala mutants. This study provided for the first time evidence that Trp355 and His352 are critical for UGT74S1's glucosylation activity toward SECO and suggested the possibility for SMG production in vitro.

  18. 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...

  19. 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...

  20. 75 FR 14206 - FPL Energy Point Beach, LLC; Point Beach Nuclear Plant, Units 1 and 2; Environmental Assessment...

    Science.gov (United States)

    2010-03-24

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

  1. 76 FR 6830 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No...

    Science.gov (United States)

    2011-02-08

    ...- and 6- day supply is based on the diesel generator manufacturer's consumption values for the run time... different kind of accident from any accident previously evaluated; or (3) involve a significant reduction in... Company, Docket Nos. 50-325 and 50-324, Brunswick Steam Electric Plant, Units 1 and 2, Brunswick County...

  2. 77 FR 16091 - Order Modifying Licenses With Regard to Requirements for Mitigation Strategies for Beyond-Design...

    Science.gov (United States)

    2012-03-19

    ... Francisco, CA 94105 Donald C. Cook Nuclear Plant Indiana Michigan Power Co., Docket Nos. 50-315 and 50-316..., Indiana Michigan Power Company, Nuclear Generation Group, One Cook Place, Bridgman, MI 49106 Dresden.... Thomas Joyce, President and Chief Nuclear Officer, PSEG Nuclear LLC-N09, P. O. Box 236, Hancocks Bridge...

  3. 48 CFR 352.270-2 - Indian preference.

    Science.gov (United States)

    2010-10-01

    ...-2 Section 352.270-2 Federal Acquisition Regulations System HEALTH AND HUMAN SERVICES CLAUSES AND... regulations), sex, religion, or Tribal affiliation. To the extent feasible and consistent with the efficient... to existing laws and regulations), sex, religion, or Tribal affiliation. The Contractor also agrees...

  4. Technical evaluation report TMI action: NUREG-0737 (II.D.1) relief and safety valve testing,. Diablo Canyon Units 1 and 2 (Docket Nos. 50-275, 50-323)

    International Nuclear Information System (INIS)

    Miller, G.K.; Magleby, H.L.; Nalezny, C.L.

    1984-07-01

    Light water reactor operators have experienced a number of occurrences of improper performance of safety and relief valves installed in their primary coolant systems. Because of this, the authors of NUREG-0578 (TMI-2 Lessons Learned Task Status Report and Short-Term Recommendations) and subsequently NUREG-0737 (Clarification of TMI Action Plan Requirements) recommended that programs be developed and completed which would reevaluate the functional performance capabilities of Pressurized Water Reactor (PWR) safety, relief, and block valves and which would verify the integrity of the piping systems for normal, transient and accident conditions. This report provides the results of the review of these programs and their results by the Nuclear Regulatory Commission (NRC) and their consultant, EG and G Idaho, Inc. Specifically, this report has examined the response of the Licensee for Diablo Canyon Units 1 and 2, to the requirements of NUREG-0578 and NUREG-0737 and finds that the Licensee has provided an acceptable response, reconfirming that the General Design Criteria 14, 15 and 30 of Appendix A to 10 CRF 50 have been met. 18 refs

  5. 9 CFR 352.3 - Application by official exotic animal establishment for inspection services.

    Science.gov (United States)

    2010-01-01

    .... (a) Any person desiring to process an exotic animal, exotic animal carcasses, exotic animal meat and... 9 Animals and Animal Products 2 2010-01-01 2010-01-01 false Application by official exotic animal establishment for inspection services. 352.3 Section 352.3 Animals and Animal Products FOOD SAFETY AND...

  6. 75 FR 16201 - FPL Energy Point Beach, LLC; Point Beach Nuclear Plant, Units 1 and 2; Exemption

    Science.gov (United States)

    2010-03-31

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

  7. 25 CFR 1000.352 - What are “trust resources” for the purposes of the trust evaluation process?

    Science.gov (United States)

    2010-04-01

    ..., property, assets, or claims, and any intangible right or interest in any of the foregoing; (2) Any other... evaluation process? 1000.352 Section 1000.352 Indians OFFICE OF THE ASSISTANT SECRETARY, INDIAN AFFAIRS... INDIAN SELF-DETERMINATION AND EDUCATION ACT Trust Evaluation Review § 1000.352 What are “trust resources...

  8. Midland Plant, Units 1 and 2 (Docket Nos. 50-329 and 50-330): Draft supplement to the Final environmental statement

    International Nuclear Information System (INIS)

    1977-01-01

    The Midland Plant, Units 1 and 2 is to be owned and operated by the Consumers Power Company of Michigan. The approximately 1190-acre plant is on the south of the Tittabawassee River immediately across from the Dow Chemical Company's main industrial complex which is within the Midland city limits. The site itself was, and the area south of the site is, partially wooded flat land with farming the only economically significant human activity. To the east and north within one mile of the site, the land is industrial, both developed and undeveloped. To the west, the land is used for suburban residences and light farming. The plant will utilize two pressurized-water nuclear reactor systems. The Consumers Power Company filed with AEC (now NRC) an application for construction permits and operating licenses for the Midland Plant on January 13, 1969. The Final Environmental Statement was issued in March 1972 and on December 15, 1972 construction permits were issued for the Midland Plant. On July 21, 1976, the US Court of Appeals for the District of Columbia Circuit handed down decisions in the generic fuel cycle rulemaking and Midland appeals ruling that nuclear waste disposal and fuel reprocessing issues had been insufficiently considered by the AEC. In addition to consideration of the fuel cycle issues, the Court of Appeals remanded Consumer Power's construction permits for Midland to the NRC for further proceedings to consider energy conservation as an alternative to plant construction, and to consider any changed circumstances concerning the need of Dow for the process steam from the Midland Plant. 10 refs., 13 tabs

  9. Final environmental statement related to construction of Midland Plant, Units 1 and 2 (Docket Nos. 50-329 and 50-330)

    International Nuclear Information System (INIS)

    1977-01-01

    This is a Final Detailed Statement on Environmental Considerations associated with construction and operation of Midland Plant Units 1 and 2 at Midland, Michigan, pursuant to a construction permit and operating license which has been applied for by the Consumers Power Company. The application is under review by the US Atomic Energy Commission's Regulatory Staff. The environmental impact, including adverse and beneficial effects, of the Midland Plant includes reassignment of use of about 1100 acres of agricultural and residential land for the cooling pond (the plant buildings are located on industrial zoned land); this resulted in the dislocation of approximately 25 residences and relocation of the Midland County Farm to a newly built structure; the destruction of a maximum of 4400 tons of phytoplankton per year at the intake of makeup water from the Tittabawassee River; and a predicted small increase in fogging effects in the near vicinity of the cooling pond. 34 refs., 19 figs., 26 tabs

  10. 75 FR 4111 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No...

    Science.gov (United States)

    2010-01-26

    ... value for all steam generators, both hot and cold legs, in Table RA124-2. Specifically, for the... possibility of a new or different kind of accident from any accident previously evaluated; or (3) involve a...-mail to [email protected] . Arizona Public Service Company, et al., Docket Nos. STN 50-528, STN 50...

  11. Technical Specifications, Limerick Generating Station, Unit No. 2 (Docket No. 50-353)

    International Nuclear Information System (INIS)

    1989-08-01

    The Limerick, Unit 2, Technical Specifications were prepared by the US Nuclear Regulatory Commission to set 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

  12. Technical specifications, Limerick Generating Station, Unit No. 2 (Docket No. 50-353)

    International Nuclear Information System (INIS)

    1989-07-01

    The Limerick, Unit 2, Technical Specifications were prepared by the US Nuclear Regulatory Commission to set 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

  13. Technical specifications Limerick Generating Station, Unit No.1 (Docket No. 50-352). Appendix ''A'' to License No. NPF-39

    International Nuclear Information System (INIS)

    1985-06-01

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

  14. 48 CFR 352.227-70 - Publications and publicity.

    Science.gov (United States)

    2010-10-01

    ... article the Contractor submits for publication shall be promptly sent to the Contracting Officer's... 48 Federal Acquisition Regulations System 4 2010-10-01 2010-10-01 false Publications and publicity... AND FORMS SOLICITATION PROVISIONS AND CONTRACT CLAUSES Texts of Provisions and Clauses 352.227-70...

  15. Tectonic evolution of the outer Izu-Bonin-Mariana fore arc system: initial results from IODP Expedition 352

    Science.gov (United States)

    Kurz, W.; Ferre, E. C.; Robertson, A. H. F.; Avery, A. J.; Kutterolf, S.

    2015-12-01

    During International Ocean Discovery Program (IODP) Expedition 352, a section through the volcanic stratigraphy of the outer fore arc of the Izu-Bonin-Mariana (IBM) system was drilled to trace magmatism, tectonics, and crustal accretion associated with subduction initiation. Structures within drill cores, borehole and site survey seismic data indicate that tectonic deformation in the outer IBM fore arc is mainly post-magmatic. Extension generated asymmetric sediment basins such as half-grabens at sites 352-U1439 and 352-U1442 on the upper trench slope. Along their eastern margins the basins are bounded by west-dipping normal faults. Deformation was localized along multiple sets of faults, accompanied by syn-tectonic pelagic and volcaniclastic sedimentation. The lowermost sedimentary units were tilted eastward by ~20°. Tilted beds were covered by sub-horizontal beds. Biostratigraphic constraints reveal a minimum age of the oldest sediments at ~ 35 Ma; timing of the sedimentary unconformities is between ~ 27 and 32 Ma. At sites 352-U1440 and 352-U1441 on the outer fore arc strike-slip faults are bounding sediment basins. Sediments were not significantly affected by tectonic tilting. Biostratigraphy gives a minimum age of the basement-cover contact between ~29.5 and 32 Ma. The post-magmatic structures reveal a multiphase tectonic evolution of the outer IBM fore arc. At sites 352-U1439 and 352-U1442, shear with dominant reverse to oblique reverse displacement was localized along subhorizontal fault zones, steep slickensides and shear fractures. These were either re-activated as or cut by normal-faults and strike-slip faults. Extension was also accommodated by steep to subvertical mineralized veins and extensional fractures. Faults at sites 352-U1440 and 352-U1441 show mainly strike-slip kinematics. Sediments overlying the igneous basement(maximum Late Eocene to Recent age), document ash and aeolian input, together with mass wasting of the fault-bounded sediment ponds.

  16. 32 CFR 352a.4 - Responsibilities and functions.

    Science.gov (United States)

    2010-07-01

    ...) ORGANIZATIONAL CHARTERS DEFENSE FINANCE AND ACCOUNTING SERVICE (DFAS) § 352a.4 Responsibilities and functions. (a) The Director, Defense Finance and Accounting Service (DFAS), is the principal DoD executive for finance and accounting requirements, systems, and functions identified in DoD Directive 5118.3, 1 and...

  17. 78 FR 16824 - Tobacco Product Manufacturing Practice; Establishment of a Public Docket

    Science.gov (United States)

    2013-03-19

    ... manufacturing operations. DATES: Submit electronic or written comments on the tobacco companies' recommendations... DEPARTMENT OF HEALTH AND HUMAN SERVICES Food and Drug Administration 21 CFR Chapter I [Docket No. FDA-2013-N-0227] Tobacco Product Manufacturing Practice; Establishment of a Public Docket AGENCY: Food...

  18. 75 FR 38521 - Registration Review; Biopesticide Dockets Opened for Review and Comment

    Science.gov (United States)

    2010-07-02

    ... in hard copy form. Publicly available docket materials are available either in the electronic docket at http://www.regulations.gov , or, if only available in hard copy, at the OPP Regulatory Public.... Section 3(g) of FIFRA provides, among other things, that the registrations of pesticides are to be...

  19. Post-magmatic tectonic deformation of the outer Izu-Bonin-Mariana forearc system: initial results of IODP Expedition 352

    Science.gov (United States)

    Kurz, Walter; Ferré, Eric C.; Robertson, Alastair; Avery, Aaron; Christeson, Gail L.; Morgan, Sally; Kutterorf, Steffen; Sager, William W.; Carvallo, Claire; Shervais, John; Party IODP Expedition 352, Scientific

    2015-04-01

    IODP Expedition 352 was designed to drill through the entire volcanic sequence of the Bonin forearc. Four sites were drilled, two on the outer fore arc and two on the upper trench slope. Site survey seismic data, combined with borehole data, indicate that tectonic deformation in the outer IBM fore arc is mainly post-magmatic. Post-magmatic extension resulted in the formation of asymmetric sedimentary basins such as, for example, the half-grabens at sites 352-U1439 and 352-U1442 located on the upper trench slope. Along their eastern margins these basins are bounded by west-dipping normal faults. Sedimentation was mainly syn-tectonic. The lowermost sequence of the sedimentary units was tilted eastward by ~20°. These tilted bedding planes were subsequently covered by sub-horizontally deposited sedimentary beds. Based on biostratigraphic constraints, the minimum age of the oldest sediments is ~ 35 Ma; the timing of the sedimentary unconformities lies between ~ 27 and 32 Ma. At sites 352-U1440 and 352-U1441, located on the outer forearc, post-magmatic deformation resulted mainly in strike-slip faults possibly bounding the sedimentary basins. The sedimentary units within these basins were not significantly affected by post-sedimentary tectonic tilting. Biostratigraphic ages indicate that the minimum age of the basement-cover contact lies between ~29.5 and 32 Ma. Overall, the post-magmatic tectonic structures observed during Expedition 352 reveal a multiphase tectonic evolution of the outer IBM fore arc. At sites 352-U1439 and 352-U1442, shear with dominant reverse to oblique reverse displacement was localized along distinct subhorizontal cataclastic shear zones as well as steeply dipping slickensides and shear fractures. These structures, forming within a contractional tectonic regime, were either re-activated as or cross-cut by normal-faults as well as strike-slip faults. Extension was also accommodated by steeply dipping to subvertical mineralized veins and

  20. 32 CFR 352a.3 - Organization and management.

    Science.gov (United States)

    2010-07-01

    ...) ORGANIZATIONAL CHARTERS DEFENSE FINANCE AND ACCOUNTING SERVICE (DFAS) § 352a.3 Organization and management. (a... control of the Comptroller of the Department of Defense (C, DoD). (b) The DFAS shall consist of a Director, selected by the Secretary of Defense, and such subordinate organizational elements as are established by...

  1. 48 CFR 352.233-71 - Litigation and claims.

    Science.gov (United States)

    2010-10-01

    ... the action in good faith. The Government shall not be liable for the expense of defending any action... compensated by insurance which was required by law or regulation or by written direction of the Contracting... FORMS SOLICITATION PROVISIONS AND CONTRACT CLAUSES Texts of Provisions and Clauses 352.233-71 Litigation...

  2. 75 FR 60117 - Registration Review; Biopesticides Dockets Opened for Review and Comment

    Science.gov (United States)

    2010-09-29

    ... publicly available only in hard copy form. Publicly available docket materials are available either in the electronic docket at http://www.regulations.gov , or, if only available in hard copy, at the OPP Regulatory.... Section 3(g) of FIFRA provides, among other things, that the registrations of pesticides are to be...

  3. 75 FR 77017 - Nextera Energy Seabrook, LLC Seabrook Station Independent Spent Fuel Storage Installation; Exemption

    Science.gov (United States)

    2010-12-10

    ... NUCLEAR REGULATORY COMMISSION [Docket Nos. 50-443, 72-63; NRC-2010-0381] Nextera Energy Seabrook, LLC Seabrook Station Independent Spent Fuel Storage Installation; Exemption 1.0 Background NextEra Energy Seabrook, LLC (NextEra, the licensee) is the holder of Facility Operating License No. NPF-86...

  4. Safety Evaluation Report related to the operation of Seabrook Station, Units 1 and 2 (Docket Nos. 50-443 and 50-444)

    International Nuclear Information System (INIS)

    1990-03-01

    This report is Supplement No. 9 to the Safety Evaluation Report (SER) (NUREG-0896, March 1983) for the application filed by the Public Service Company of New Hampshire, et al., for licenses to operate Seabrook Station, Units 1 and 2. It has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission and provides recent information on open items identified in the SER. The facility is located in Seabrook, New Hampshire. Subject to favorable resolution of the items discussed in this report, the staff concludes that the facility can be operated by the applicant without endangering the health and safety of the public. 70 refs., 1 fig., 1 tab

  5. Final environmental statement for William B. McGuire Nuclear Station, Units 1 and 2: (Docket Nos. 50-369 and 50-370)

    International Nuclear Information System (INIS)

    1976-04-01

    The proposed action is the issuance of operating licenses to the Duke Power Company for the startup and operation of the William B. McGuire Nuclear Station, Units 1 and 2 (the plant) located on the Lake Norman in Mecklenburg County, 17 miles north-northwest of Charlotte, North Carolina. The units will be cooled by once-through flow of water from Lake Norman. Two units, each with a net electrical capacity of 1180 MWe will be added to the resources of the Duke Power Company. This will have a favorable effect on reserve margins and provide a cost savings of $77 to $122 million in production costs in 1979 if the units come on line as scheduled, and cost savings in subsequent years. Approximately 200 acres of rural, partially wooded land owned by the applicant will be unavailable for other uses during the 40-year life of the plant. Approximately 61.6 acres of additional land will be utilized for transmission line corridors and/or switchyard and maintained under controlled conditions. Land-use patterns will necessarily conform to the needs of the application but will not be changed significantly from present usage. At full power, condenser cooling water could be heated to as high as 96/degree/F (35.6/degree/C) as a monthly average and will be discharged at a rate of up to 4492 cfs. The temperature rise of the water will be 16/degree/F (8.8/degree/C) to 32/degree/F (17.8/degree/C) above ambient. The heated water will mix with the cooler water of Lake Norman, where the heat will be dissipated to the atmosphere. The increase in temperature will cause a loss of approximately 31 cfs of water as a result of increased evaporation. 26 figs., 46 tabs

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

    International Nuclear Information System (INIS)

    1976-09-01

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

  7. Washington Public Power Supply System Nuclear Projects 3 and 5 (Docket Nos. STN 50-508 and 50-509): Final environmental statement

    International Nuclear Information System (INIS)

    1975-06-01

    The proposed action is the issuance of construction permits to the Washington Public Power Supply System for the construction of the Washington Nuclear Projects 3 and 5 (WNP 3 and 5). The 2170-acre site is predominately forest. Construction-related activities on the site would disturb about 300 acres. The portion of this land not to be used for the plant facilities, parking lots, roads, etc., will be restored by seeding and landscaping. The temporary removal of vegetation will tend to promote erosion. Increased siltation and turbidity can be expected in local rivers and streams during construction, but stringent measures will be undertaken to minimize these effects. A maximum of 72.5 cfs of cooling water will be withdrawn from the Chehalis River of which 12.5 cfs will be returned to the river via pipeline with the dissolved solids concentration increased by a factor of about 6. About 60 cfs will be evaporated to the atmosphere by the cooling towers. Minor and temporary impacts to the biota of the river and its south bank will result from construction activities. The volume of thermal discharge (12.5 cfs) is small compared with the river flow (annual mean is about 6600 cfs) and the effect on the river ecosystem is not expected to be significant. Chemical discharges from the plant, including chlorine, will be diluted to concentrations below those which might adversely affect aquatic biota. The risk associated with accidental radiation exposure will be very low. 37 figs., 58 tabs

  8. 29 CFR 501.38 - Notice of docketing.

    Science.gov (United States)

    2010-07-01

    ... 29 Labor 3 2010-07-01 2010-07-01 false Notice of docketing. 501.38 Section 501.38 Labor Regulations Relating to Labor (Continued) WAGE AND HOUR DIVISION, DEPARTMENT OF LABOR REGULATIONS ENFORCEMENT OF CONTRACTUAL OBLIGATIONS FOR TEMPORARY ALIEN AGRICULTURAL WORKERS ADMITTED UNDER SECTION 218 OF THE...

  9. 29 CFR 502.38 - Notice of docketing.

    Science.gov (United States)

    2010-07-01

    ... 29 Labor 3 2010-07-01 2010-07-01 false Notice of docketing. 502.38 Section 502.38 Labor Regulations Relating to Labor (Continued) WAGE AND HOUR DIVISION, DEPARTMENT OF LABOR REGULATIONS ENFORCEMENT OF CONTRACTUAL OBLIGATIONS FOR TEMPORARY ALIEN AGRICULTURAL WORKERS ADMITTED UNDER SECTION 218 OF THE...

  10. 48 CFR 352.237-70 - Pro-Children Act.

    Science.gov (United States)

    2010-10-01

    ... 48 Federal Acquisition Regulations System 4 2010-10-01 2010-10-01 false Pro-Children Act. 352.237...-Children Act. As prescribed in 337.103-70(a), the Contracting Officer shall insert the following clause: Pro-Children Act (January 2006) (a) Public Law 103-227, Title X, Part C, also known as the Pro...

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1981-03-01

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

  12. Expression analysis of NOS family and HSP genes during thermal stress in goat ( Capra hircus)

    Science.gov (United States)

    Yadav, Vijay Pratap; Dangi, Satyaveer Singh; Chouhan, Vikrant Singh; Gupta, Mahesh; Dangi, Saroj K.; Singh, Gyanendra; Maurya, Vijay Prakash; Kumar, Puneet; Sarkar, Mihir

    2016-03-01

    Approximately 50 genes other than heat shock protein (HSP) expression changes during thermal stress. These genes like nitric oxide synthase (NOS) need proper attention and investigation to find out their possible role in the adaptation to thermal stress in animals. So, the present study was undertaken to demonstrate the expressions of inducible form type II NOS (iNOS), endothelial type III NOS (eNOS), constitutively expressed enzyme NOS (cNOS), HSP70, and HSP90 in peripheral blood mononuclear cells (PBMCs) during different seasons in Barbari goats. Real-time polymerase chain reaction, western blot, and immunocytochemistry were applied to investigate messenger RNA (mRNA) expression, protein expression, and immunolocalization of examined factors. The mRNA and protein expressions of iNOS, eNOS, cNOS, HSP70, and HSP90 were significantly higher ( P goats.

  13. Safety evaluation report related to the preliminary design of the Standard Nuclear Steam Supply Reference System, RESAR SP/90 (Docket No. STN 50-601)

    International Nuclear Information System (INIS)

    1991-04-01

    On October 24, 1983, the Westinghouse Electric Corporation tendered its application for a preliminary design approval of the advanced pressurized-water reactor design for the SP/90 reactor. The Westinghouse Reference Safety Analysis Report (RESAR SP/90, Docket No. STN 50-601), describing the design of the facility, was submitted from October 24, 1983 through March 9, 1987. Staff of the US Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, has prepared this safety evaluation report of the RESAR SP/90 on the basis of its review. Because of the stage of the design, there are open issues that have not been resolved. These issues are discussed in detail throughout this report, and a summary is provided in Section 1.6 of this report. The applicant will be required to address these and any additional such concerns that may be raised during the course of the staff's review of advanced light-water reactors in support of a final design approval application. This report shall not constitute a commitment to issue a permit or license or in any way affect the authority of the Commission, its adjudicatory boards, and other presiding officers in any proceeding under Subpart G of Title 10 of the Code of Federal Regulations, Part 2

  14. 48 CFR 352.234-1 - Notice of earned value management system-pre-award Integrated Baseline Review.

    Science.gov (United States)

    2010-10-01

    ... 48 Federal Acquisition Regulations System 4 2010-10-01 2010-10-01 false Notice of earned value management system-pre-award Integrated Baseline Review. 352.234-1 Section 352.234-1 Federal Acquisition... provision: Notice of Earned Value Management System—Pre-Award Integrated Baseline Review (October 2008) The...

  15. 48 CFR 352.234-2 - Notice of earned value management system-post-award Integrated Baseline Review.

    Science.gov (United States)

    2010-10-01

    ... 48 Federal Acquisition Regulations System 4 2010-10-01 2010-10-01 false Notice of earned value management system-post-award Integrated Baseline Review. 352.234-2 Section 352.234-2 Federal Acquisition... provision: Notice of Earned Value Management System—Post-Award Integrated Baseline Review (October 2008) (a...

  16. 7 CFR 352.29 - Administrative instructions: Avocados from Mexico.

    Science.gov (United States)

    2010-01-01

    ... 7 Agriculture 5 2010-01-01 2010-01-01 false Administrative instructions: Avocados from Mexico. 352....29 Administrative instructions: Avocados from Mexico. Avocados from Mexico may be moved through the.... Before moving the avocados through the United States, the owner must obtain a formal permit in accordance...

  17. 75 FR 60119 - Registration Review; Antimicrobial Pesticide Dockets Opened for Review and Comment

    Science.gov (United States)

    2010-09-29

    ... and will be publicly available only in hard copy form. Publicly available docket materials are available either in the electronic docket at http://www.regulations.gov , or, if only available in hard copy... 155, subpart C. Section 3(g) of FIFRA provides, among other things, that the registrations of...

  18. Technical Specifications, Comanche Peak Steam Electric Station, Unit 1 (Docket No. 50-445)

    International Nuclear Information System (INIS)

    1990-04-01

    The Technical Specifications for Comanche Peak Steam Electric Station, Unit 1 were prepared by the US Nuclear Regulatory Commission. They set forth the limits, operating conditions, and other requirements applicable to a nuclear reactor facility, as set forth in Section 50.36 of Title 10 of the Code of Federal Regulations Part 50, for the protection of the health and safety of the public

  19. MGE-derived nNOS+ interneurons promote fear acquisition in nNOS-/- mice.

    Science.gov (United States)

    Zhang, Lin; Yuan, Hong-Jin; Cao, Bo; Kong, Cheng-Cheng; Yuan, Fang; Li, Jun; Ni, Huan-Yu; Wu, Hai-Yin; Chang, Lei; Liu, Yan; Luo, Chun-Xia

    2017-12-02

    Neuronal nitric oxide synthase (nNOS) 1 , mainly responsible for NO release in central nervous system (CNS) 2 , plays a significant role in multiple physiological functions. However, the function of nNOS + interneurons in fear learning has not been much explored. Here we focused on the medial ganglionic eminences (MGE) 3 -derived nNOS + interneurons in fear learning. To determine the origin of nNOS + interneurons, we cultured neurons in vitro from MGE, cortex, lateral ganglionic eminence (LGE) 4 , caudal ganglionic eminences (CGE) 5 and preoptic area (POA) 6 . The results showed that MGE contained the most abundant precursors of nNOS + interneurons. Moreover, donor cells from E12.5 embryos demonstrated the highest positive rate of nNOS + interneurons compared with other embryonic periods (E11.5, E12, E13, E13.5 and E14). Additionally, these cells from E12.5 embryos showed long axonal and abundant dendritic arbors after 10 days culture, indicating the capability to disperse and integrate in host neural circuits after transplantation. To investigate the role of MGE-derived nNOS + interneurons in fear learning, donor MGE cells were transplanted into dentate gyrus (DG) 7 of nNOS knock-out (nNOS -/- ) or wild-type mice. Results showed that the transplantation of MGE cells promoted the acquisition of nNOS -/- but not the wild-type mice, suggesting the importance of nNOS + neurons in fear acquisition. Moreover, we transplanted MGE cells from nNOS -/- mice or wild-type mice into DG of the nNOS -/- mice and found that only MGE cells from wild-type mice but not the nNOS -/- mice rescued the deficit in acquisition of the nNOS -/- mice, further confirming the positive role of nNOS + neurons in fear learning. Copyright © 2017 Elsevier Inc. All rights reserved.

  20. 10 CFR 2.643 - Acceptance and docketing of application for limited work authorization.

    Science.gov (United States)

    2010-01-01

    ... application is docketed, the Director will cause to be published in the Federal Register and send to the... complete. (e) If part two of the application is docketed, the Director will cause to be published in the... § 2.101(a)(9) is incomplete and not acceptable for processing, the Director of New Reactors or the...

  1. 38 CFR 3.352 - Criteria for determining need for aid and attendance and “permanently bedridden.”

    Science.gov (United States)

    2010-07-01

    ... need for aid and attendance and âpermanently bedridden.â 3.352 Section 3.352 Pensions, Bonuses, and... attendance and “permanently bedridden.” (a) Basic criteria for regular aid and attendance and permanently bedridden. The following will be accorded consideration in determining the need for regular aid and...

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

    International Nuclear Information System (INIS)

    1975-09-01

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

  3. 38 CFR 17.352 - Amounts and use of grant funds for the replacement and upgrading of equipment.

    Science.gov (United States)

    2010-07-01

    ... funds for the replacement and upgrading of equipment. 17.352 Section 17.352 Pensions, Bonuses, and... Amounts and use of grant funds for the replacement and upgrading of equipment. Grants awarded under § 17... States for the purpose. Funds appropriated for the upgrading and replacement of equipment at the Veterans...

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

    International Nuclear Information System (INIS)

    1986-10-01

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

  5. Final environmental statement related to the operation of South Texas Project, Units 1 and 2 (Docket Nos. 50-498 and 50-499)

    International Nuclear Information System (INIS)

    1986-08-01

    This Final Environmental Statement contains the second assessment of the environmental impact associated with the operation of the South Texas Project, Units 1 and 2, pursuant to the National Environmental Policy Act of 1969 (NEPA) and Title 10 of the Code of Federal Regulations, Part 51, as amended, of the Nuclear Regulatory Commission regulations. This statement examines the environmental impacts, environmental consequences and mitigating actions, and environmental and economic benefits and costs associated with station operation. Land use and terrestrial and aquatic ecological impacts will be small. No operational impacts to historic and archeological sites are anticipated. The effects of routine operations, energy transmission, and periodic maintenance of rights-of-way and transmission facilities should not jeopardize any populations of endangered or threatened species. No significant impacts are anticipated from normal operational releases of radioactivity. The risk of radiation exposure associated with accidental release of radioactivity is very low. Socioeconomic impacts of the project are anticipated to be minimal. The action called for is the issuance of an operating license for South Texas Project, Units 1 and 2

  6. nNOS inhibitors attenuate methamphetamine-induced dopaminergic neurotoxicity but not hyperthermia in mice.

    Science.gov (United States)

    Itzhak, Y; Martin, J L; Ail, S F

    2000-09-11

    Methamphetamine (METH)-induced dopaminergic neurotoxicity is associated with hyperthermia. We investigated the effect of several neuronal nitric oxide synthase (nNOS) inhibitors on METH-induced hyperthermia and striatal dopaminergic neurotoxicity. Administration of METH (5 mg/kg; q. 3 h x 3) to Swiss Webster mice produced marked hyperthermia and 50-60% depletion of striatal dopaminergic markers 72 h after METH administration. Pretreatment with the nNOS inhibitors S-methylthiocitrulline (SMTC; 10 mg/kg) or 3-bromo-7-nitroindazole (3-Br-7-NI; 20 mg/kg) before each METH injection did not affect the persistent hyperthermia produced by METH, but afforded protection against the depletion of dopaminergic markers. A low dose (25 mg/kg) of the nNOS inhibitor 7-nitroindazole (7-NI) did not affect METH-induced hyperthermia, but a high dose (50 mg/kg) produced significant hypothermia. These findings indicate that low dose of selective nNOS inhibitors protect against METH-induced neurotoxicity with no effect on body temperature and support the hypothesis that nitric oxide (NO) and peroxynitrite have a major role in METH-induced dopaminergic neurotoxicity.

  7. 77 FR 11385 - Security Considerations for Lavatory Oxygen Systems

    Science.gov (United States)

    2012-02-27

    ... considerations for lavatory oxygen systems (77 FR 12550). The interim final rule addresses a security... and taken to restore the oxygen system with a design that would consider the security risk. Boeing... [Docket No. FAA-2011-0186; Amdt. Nos. 21-94, 25-133, 121-354, 129-50; SFAR 111] RIN 2120-AJ92 Security...

  8. Stress-restress evokes sustained iNOS activity and altered GABA levels and NMDA receptors in rat hippocampus

    DEFF Research Database (Denmark)

    Harvey, Brian H; Oosthuizen, Frasia; Brand, Linda

    2004-01-01

    . The NOS isoform involved, and the role of stress-mediated corticosterone release in NOS activation, was verified with the administration of selective iNOS and nNOS inhibitors, aminoguanidine (50 mg/kg/day i.p.) and 7-nitroindazole (12.5 mg/kg/day i.p.), and the steroid synthesis inhibitor, ketoconazole...... (24 mg/kg/day i.p.), administered for 21 days prior to and during the stress procedure. RESULTS: Stress evoked a sustained increase in NOS activity, but reduced NMDA receptor density and total GABA levels. Aminoguanidine or ketoconazole, but not 7-nitroindazole or saline, blocked stress-induced NOS...

  9. Draft environmental statement: Related to operation of the Edwin I. Hatch Nuclear Plant Unit No. 2, Georgia Power Company: Docket No. 50-366

    International Nuclear Information System (INIS)

    1977-04-01

    The proposed action is the issuance of an operation license to the Georgia Power Company for the startup and operation of the Edwin I. Hatch Nuclear Plant, Unit No. 2 (Docket No. 50-366), located on the Altamaha River in Appling County, approximately 11 miles north from Baxley, Georgia. The information in this Statement represents the second, assessment of the environmental impact associated with the Edwin I. Hatch Nuclear Plant, Unit No. 2, pursuant to the guidelines of the National Environmental Policy Act of 1969 (NEPA) and 10 CFR Part 51 of the Commission's Regulations. After receipt of an application, in 1970, to construct this plant, the staff carried out a review of impact that would occur during the construction and operation of this plant. That evaluation was issued as a Final Environmental Statement in October 1972. As the result of that environmental review, a safety review, an evaluation by the Advisory Committee on Reactor Safeguards, and a public hearing in Baxley, Georgia and Washington, D.C., the AEC (now NRC) issued a permit in December 1972, for the construction of Unit No. 2 of the Edwin I. Hatch Nuclear Plant. As of February 1977, the construction of Unit No. 2 was 70% complete. With a proposed fuel-loading date of April 1978 for Unit No. 2, the applicant has petitioned for license to operate Unit No. 2 and has submitted (July 1975) the required safety and environmental reports to substantiate this petition. 97 refs., 18 figs., 37 tabs

  10. Priority Queuing on the Docket: Universality of Judicial Dispute Resolution Timing

    Directory of Open Access Journals (Sweden)

    Satyam Mukherjee

    2018-01-01

    Full Text Available This paper analyzes court priority queuing behavior by examining the time lapse between when a case enters a court's docket and when it is ultimately disposed of. Using data from the Supreme courts of the United States, Massachusetts, and Canada we show that each court's docket features a slow decay with a decreasing tail. This demonstrates that, in each of the courts examined, the vast majority of cases are resolved relatively quickly, while there remains a small number of outlier cases that take an extremely long time to resolve. We discuss the implications for this on legal systems, the study of the law, and future research.

  11. 75 FR 2163 - Constellation Energy; Notice of Docketing of Special Nuclear Material License SNM-2505 Amendment...

    Science.gov (United States)

    2010-01-14

    ... NUCLEAR REGULATORY COMMISSION [Docket No. 72-8; NRC-2010-0011] Constellation Energy; Notice of Docketing of Special Nuclear Material License SNM-2505 Amendment Application for the Calvert Cliffs... Constellation Energy (Constellation) to amend its Special Nuclear Material License No. SNM-2505, under the...

  12. 78 FR 18586 - Registration Review; Pesticide Dockets Opened for Review and Comment and Other Docket Acts

    Science.gov (United States)

    2013-03-27

    ...With this document, EPA is opening the public comment period for several registration reviews. Registration review is EPA's periodic review of pesticide registrations to ensure that each pesticide continues to satisfy the statutory standard for registration, that is, the pesticide can perform its intended function without unreasonable adverse effects on human health or the environment. Registration review dockets contain information that will assist the public in understanding the types of information and issues that the Agency may consider during the course of registration reviews. Through this program, EPA is ensuring that each pesticide's registration is based on current scientific and other knowledge, including its effects on human health and the environment. This document also announces the Agency's intent not to open registration review dockets for iodomethane or ethametsulfuron-methyl. Iodomethane and ethametsulfuron-methyl are undergoing phase-outs of all U.S. pesticide registrations. The cancellations of the iodomethane end use registrations became effective on December 31, 2012, and the cancellation of the sole technical product registration will become effective on December 1, 2015. The cancellations of all ethametsulfuron-methyl product registrations became effective on February 20, 2013. Therefore, iodomethane and ethametsulfuron-methyl are not scheduled for review under the registration review program. This document also announces the registration review case closures for the pesticides alkyl amine hydrochloride (case 3051) and halofenozide (case 7425), and the availability of their respective Case Closure Documents. The cancellation of all alkyl amine hydrochloride registrations became effective on October 17, 2012. The cancellation of all U.S. halofenozide registrations became effective December 21, 2012. These case closure are being announced herein with no comment period.

  13. 75 FR 3871 - Promoting Diversification of Ownership in Broadcast Services; Suspension of Filing Date

    Science.gov (United States)

    2010-01-25

    ... FEDERAL COMMUNICATIONS COMMISSION 47 CFR Part 73 [MB Docket Nos. 07-294, 06-121, 02-277, 04-228; MM Docket Nos. 01-235, 01-317, 00-244; DA 09-2618] Promoting Diversification of Ownership in...); Promoting Diversification in the Broadcasting Services, Order, DA 09-2165 (rel. Oct. 2, 2009). See also...

  14. 76 FR 22094 - Notice of Effectiveness of Exempt Wholesale Generator Status

    Science.gov (United States)

    2011-04-20

    ... Wholesale Generator Status Docket Nos. LSP Energy, Inc EG11-43-000 Milford Wind Corridor Phase II, LLC EG11-44-000 Elk Wind Energy LLC EG11-45-000 Grande Prairie Generation, Inc EG11-46-000 Mountain View Power... CoGen Company EG11-50-000 CPV Batesville, LLC EG11-51-000 Mount Miller Wind Energy Limited Partner...

  15. 75 FR 57269 - Notice of Effectiveness of Exempt Wholesale Generator Status

    Science.gov (United States)

    2010-09-20

    ... Effectiveness of Exempt Wholesale Generator Status September 13, 2010. Taloga Wind, LLC Docket Nos. EG10-40-000... Alta Wind V, LLC EG10-47-000 Synergics Roth Rock Wind Energy, LLC...... EG10-49-000 Synergics Roth Rock North Wind Energy, LLC EG10-50-000 Take notice that during the month of August 2010, the status of the...

  16. Safety Evaluation Report related to the operation of Byron Station, Units 1 and 2 (Dockets Nos. STN 50-454 and STN 50-455)

    International Nuclear Information System (INIS)

    1984-10-01

    Supplement No. 5 to the Safety Evaluation Report related to Commonwealth Edison Company's application for licenses to operate the Byron Station, Units 1 and 2, located in Rockvale Township, Ogle County, Illinois, has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement reports the status of certain items that had not been resolved at the time of publication of the Safety Evaluation Report. Because of the favorable resolution of the items discussed in this report, the staff concludes that there is reasonable assurance that the facility can be operated by the applicant without endangering the health and safety of the public

  17. 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

  18. Final environmental statement related to the operation of Braidwood Station, Units 1 and 2 (Docket Nos. STN 50-456 and STN 50-457)

    International Nuclear Information System (INIS)

    1984-06-01

    This Final Environmental Statement contains the second assessment of the environmental impact associated with the operation of Braidwood Station, Units 1 and 2, pursuant to the National Environmental Policy Act of 1969 (NEPA) and Title 10 of the Code of Federal Regulations, Part 51, as amended, of the Nuclear Regulatory Commission regulations. This statement examines the environment, environmental consequences and mitigating actions, and environmental and economic benefits and costs. Land use and terrestrial and aquatic ecological impacts will be small. Operational impacts to historic and archeologic sites will be moderate. The effects of routine operations, energy transmission, and periodic maintenance of rights of way and transmission facilities should not jeopardize any populations of endangered or threatened species. No significant impacts are anticipated from normal operational releases of radioactivity. The risk of radiation exposure associated with accidental release of radioactivity is very low. The net socioeconomic effects of the project will be beneficial. On the basis of the analysis and evaluation set forth in this environmental statement, it is concluded that the action called for under NEPA and 10 CFR 51 is the issuance of operating licenses for Braidwood Station, Units 1 and 2. 27 figures, 23 tables

  19. 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

  20. Draft environmental statement related to the operation of Braidwood Station, Units 1 and 2 (Docket Nos. STN 50-456 and STN 50-457)

    International Nuclear Information System (INIS)

    1983-12-01

    The Draft Environment Statement contains the second assessment of the environmental impact associated with the operation of Braidwood Station, Units 1 and 2, pursuant to the National Environmental Policy Act of 1969 (NEPA) and Title 10 of the Code of Federal Regulations, Part 51, as amended, of the Nuclear Regulatory Commission regulations. This statement examines the environment, environmental consequences and mitigating actions, and environmental and economic benefits and costs. Land use and terrestrial and aquatic ecological impacts will be small. Operational impacts to historic and archeologic sites will be negligible. The effects of routine operations, energy transmission, and periodic maintenance of rights of way and transmission facilities should not jeopardize any populations of endangered or threatened species. No significant impacts are anticipated from normal operational releases of radioactivity. The risk of radiation exposure associated with accidental release of radioactivity is very low. The net socioeconomi effects of the project will be beneficial. On the basis of the analysis and evaluation set forth in this environmental statement, it is concluded that the action called for under NEPA and 10 CFR 51 is the issuance of operating licenses for Braidwood Station, Units 1 and 2

  1. Safety-Evaluation Report related to the operation of Grand Gulf Nuclear Station, Units 1 and 2. Docket Nos. 50-416 and 50-417

    International Nuclear Information System (INIS)

    1983-05-01

    Supplement 4 to the Safety Evaluation Report for Mississippi Power and Light Company, et. al., joint application for licenses to operate the Grand Gulf Nuclear Station, Units 1 and 2, located on the east bank of the Mississippi River near Port Gibson in Claiborne County, Mississippi, has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement reports the status on the resolution of those issues that required further evaluation before authorizing operation of Unit 1 above 5% rated power and other issues that were to be evaluated during the first cycle of power operation

  2. 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

  3. Safety Evaluation Report, related to the operation of Byron Station, Units 1 and 2 (Docket Nos. STN 50-454 and STN 50-455)

    International Nuclear Information System (INIS)

    1983-11-01

    Supplement No. 3 to the Safety Evaluation Report related to Commonwealth Edison Company's application for licenses to operate the Byron Station, Units 1 and 2, located in Rockvale Township, Ogle County, Illinois, has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement reports the status of certain items that had not been resolved at the time of publication of the Safety Evaluation Report

  4. Report of the South Texas Project Allegations Review Team. Docket Nos. 50-498 and 50-499, Houston Lighting and Power Company et al.

    Energy Technology Data Exchange (ETDEWEB)

    Kokajko, L.; Skay, D.; Wang, H.; Murphy, D. [Nuclear Regulatory Commission, Washington, DC (United States)

    1995-03-01

    This report provides the results of the South Texas Project Allegations Review Team of the US Nuclear Regulatory Commission. This team was formed to obtain and review allegations from individuals represented by three attorneys who had contacted Congressional staff members. The allegers were employed in various capacities at South Texas Project Electric Generating Station, licensed by Houston Lighting and Power Company, et al.; therefore, the allegations are confined to this site. The South Texas Project Allegations Review Team reviewed, referred, and dispositioned concerns related to discriminatory issues (harassment and intimidation), falsification of records and omission of information, and various technical issues. The team was able to substantiate certain technical issues of minor safety significance or regulatory concern at the South Texas Project facility, but it did not find widespread discriminatory practices such as harassment and intimidation.

  5. Safety evaluation report related to the operation of Watts Bar Nuclear Plant, Units 1 and 2: Docket Nos. 50-390 and 50-391

    International Nuclear Information System (INIS)

    1982-09-01

    Additional information is presented concerning the seismic and dynamic qualification of Seismic Category 1 mechanical and electrical equipment; steam generators; physical security plan; and report to the Advisory Committee on Reactor Safeguards

  6. Safety Evaluation Report related to the operation of Byron Station, Units 1 and 2 (Docket Nos. STN 50-454 and STN 50-455)

    International Nuclear Information System (INIS)

    1984-05-01

    Supplement No. 4 to the Safety Evaluation Report related to Commonwealth Edison Company's application for licenses to operate the Byron Station, Units 1 and 2, located in Rockvale Township, Ogle County, Illinois, has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement reports the status of certain items that had not been resolved at the time of publication of the Safety Evaluation Report

  7. Safety evaluation report related to the operation of Byron Station, Units 1 and 2. Docket Nos. STN 50-454 and STN 50-455

    International Nuclear Information System (INIS)

    1983-01-01

    Supplement No. 2 to the Safety Evaluation Report related to Commonwealth Edison Company's application for licenses to operate the Byron Station, Units 1 and 2, located in Rockvale Township, Ogle County, Illinois, has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement reports the status of certain items that had not been resolved at the time of publication of the Safety Evaluation Report

  8. Report of the South Texas Project Allegations Review Team. Docket Nos. 50-498 and 50-499, Houston Lighting and Power Company et al

    International Nuclear Information System (INIS)

    Kokajko, L.; Skay, D.; Wang, H.; Murphy, D.

    1995-03-01

    This report provides the results of the South Texas Project Allegations Review Team of the US Nuclear Regulatory Commission. This team was formed to obtain and review allegations from individuals represented by three attorneys who had contacted Congressional staff members. The allegers were employed in various capacities at South Texas Project Electric Generating Station, licensed by Houston Lighting and Power Company, et al.; therefore, the allegations are confined to this site. The South Texas Project Allegations Review Team reviewed, referred, and dispositioned concerns related to discriminatory issues (harassment and intimidation), falsification of records and omission of information, and various technical issues. The team was able to substantiate certain technical issues of minor safety significance or regulatory concern at the South Texas Project facility, but it did not find widespread discriminatory practices such as harassment and intimidation

  9. Safety Evaluation Report related to the operation of LaSalle County Station, Units 1 and 2. Docket Nos. 50-373 and 50-374

    International Nuclear Information System (INIS)

    1984-03-01

    This supplement to the Safety Evaluation Report of Commonwealth Edison Company's application for a license to operate its La Salle County Station, Unit 2, located in Brookfield Township, La Salle County, Illinois, has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement is to update evaluations on Unit 2 issues identified in the previous Safety Evaluation Report and Supplements that need resolution prior to issuance of the full power operating license for Unit 2

  10. Safety evaluation report related to the operation of Byron Station, Units 1 and 2 (Docket Nos. STN 50-454 and STN 50-455)

    International Nuclear Information System (INIS)

    1987-03-01

    Supplement No. 8 to the Safety Evaluation Report related to Commonwealth Edison Company's application for licenses to operate the Byron Station, Units 1 and 2, located in Rockvale Township, Ogle County, Illinois, has been prepared by th Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement provides recent information regarding resolution of the license conditions identified in the SER. Because of the favorable resolution of the items discussed in this report, the staff concludes that the Byron Station, Unit 2 can be operated by the licensee at power levels greater than 5% without endangering the health and safety of the public

  11. Final supplement to the final environmental statement related to operation of Three Mile Island Nuclear Station, Unit 2: (Docket No. 50-320)

    International Nuclear Information System (INIS)

    1976-12-01

    The proposed action is the continuation of construction permit CPPR-66 and the issuance of operating license to Metropolitan Edison Company, Jersey Central Power and Light Company, and the Pennsylvania Electric Company (the Applicants) for the operation of the Three Mile Island Nuclear Station, Unit 2, Docket No. 50-320, near Harrisburg in Dauphin County, Pennsylvania. The Three Mile Island Nuclear Station Unit Number 2 has a designed thermal rating of 2772 megawatts with a maximum electrical output of 959 megawatts. Two natural draft cooling towers are utilized for dissipating the waste heat from the closed cycle cooling system. Extension of TMINS-Bechtelsville 500 kV transmission line an additional 7.36 miles from Bechtelsville to Hosensack required acquisition of additional 175 foot wide right-of-way along an existing 150 foot wide 230 kV corridor. Construction of this line segment resulted in clearing of 21 acres of woodland, spanning over 134.5 acres of agricultural land and diverting of 0.4 acres from agriculture to use under tower bases. About 550 curies of radionuclides in liquid effluents (0.24 Ci/yr excluding tritium and 550 Ci/yr of tritium) will be released to the environment annually. Gaseous releases will be approximately 6700 Ci/yr of noble gases, 0.01 Ci/yr of iodine-131, 560 Ci/yr of tritium, 25 Ci/yr of argon-41, and 0.06 Ci/yr of particulates. No significant environmental impacts are anticipated from normal operational releases of radioactive materials. The calculated dose to the estimated year 1990 US population is less than 540 manrem/yr. This value is less than the natural fluctuation in the approximately 28,000,000 manrem/yr dose this population would receive from background radiation

  12. 5 CFR 352.309 - Retirement, health benefits, and group life insurance.

    Science.gov (United States)

    2010-01-01

    ... Organizations § 352.309 Retirement, health benefits, and group life insurance. (a) Agency action. An employee... entitled to retain coverage for retirement, health benefits, and group life insurance purposes if he or she... he or she wishes to retain coverage under the retirement, health benefits, and group life insurance...

  13. Low shear stress induces vascular eNOS uncoupling via autophagy-mediated eNOS phosphorylation.

    Science.gov (United States)

    Zhang, Jun-Xia; Qu, Xin-Liang; Chu, Peng; Xie, Du-Jiang; Zhu, Lin-Lin; Chao, Yue-Lin; Li, Li; Zhang, Jun-Jie; Chen, Shao-Liang

    2018-05-01

    Uncoupled endothelial nitric oxide synthase (eNOS) produces O 2 - instead of nitric oxide (NO). Earlier, we reported rapamycin, an autophagy inducer and inhibitor of cellular proliferation, attenuated low shear stress (SS) induced O 2 - production. Nevertheless, it is unclear whether autophagy plays a critical role in the regulation of eNOS uncoupling. Therefore, this study aimed to investigate the modulation of autophagy on eNOS uncoupling induced by low SS exposure. We found that low SS induced endothelial O 2 - burst, which was accompanied by reduced NO release. Furthermore, inhibition of eNOS by L-NAME conspicuously attenuated low SS-induced O 2 - releasing, indicating eNOS uncoupling. Autophagy markers such as LC3 II/I ratio, amount of Beclin1, as well as ULK1/Atg1 were increased during low SS exposure, whereas autophagic degradation of p62/SQSTM1 was markedly reduced, implying impaired autophagic flux. Interestingly, low SS-induced NO reduction could be reversed by rapamycin, WYE-354 or ATG5 overexpression vector via restoration of autophagic flux, but not by N-acetylcysteine or apocynin. eNOS uncoupling might be ascribed to autophagic flux blockade because phosphorylation of eNOS Thr495 by low SS or PMA stimulation was also regulated by autophagy. In contrast, eNOS acetylation was not found to be regulated by low SS and autophagy. Notably, although low SS had no influence on eNOS Ser1177 phosphorylation, whereas boosted eNOS Ser1177 phosphorylation by rapamycin were in favor of the eNOS recoupling through restoration of autophagic flux. Taken together, we reported a novel mechanism for regulation of eNOS uncoupling by low SS via autophagy-mediated eNOS phosphorylation, which is implicated in geometrical nature of atherogenesis. Copyright © 2018 Elsevier B.V. All rights reserved.

  14. 78 FR 21085 - Establishment of a Public Docket for Administrative Detention Under the Food and Drug...

    Science.gov (United States)

    2013-04-09

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Food and Drug Administration 21 CFR Chapter I [Docket No. FDA-2013-N-0365] Establishment of a Public Docket for Administrative Detention Under the Food and Drug Administration Safety and Innovation Act AGENCY: Food and Drug Administration, HHS. ACTION: Establishment of...

  15. 78 FR 11169 - North Sky River Energy, LLC, et al; Notice of Effectiveness of Exempt Wholesale Generator Status

    Science.gov (United States)

    2013-02-15

    ... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Docket Nos. EG13-6-000, et al] North Sky River Energy, LLC, et al; Notice of Effectiveness of Exempt Wholesale Generator Status Docket Nos. North Sky River Energy, LLC EG13-6-000 Black Bear SO, LLC EG13-7-000 Black Bear Development Holdings...

  16. 77 FR 27763 - Quantum Choctaw Power, LLC, USG Nevada LLC, et al.; Notice of Effectiveness of Exempt Wholesale...

    Science.gov (United States)

    2012-05-11

    ... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Docket Nos. EG12-31-000; EG12-32-000; et al.] Quantum Choctaw Power, LLC, USG Nevada LLC, et al.; Notice of Effectiveness of Exempt Wholesale Generator Status Docket Nos. Quantum Choctaw Power, LLC EG12-31-000 USG Nevada LLC EG12-32-000...

  17. 76 FR 35882 - Paulding Wind Farm II, LLC, et al.;

    Science.gov (United States)

    2011-06-20

    ... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Docket Nos. EG11-61-000, etc.] Paulding Wind Farm II, LLC, et al.; Notice of Effectiveness of Exempt Wholesale Generator Status Docket Nos. Paulding Wind Farm II LLC EG11-61-000 Macho Springs Power I, LLC EG11-63-000 Alta Wind III Owner Lessor A...

  18. Final environmental statement related to the proposed manufacture of floating nuclear power plants: (Docket No. STN 50-437): Part 2, A generic environmental statement considering the siting and operation of floating nuclear power plants

    International Nuclear Information System (INIS)

    1976-09-01

    The proposed action is the issuance of a manufacturing license to Offshore Power Systems for the startup and operation of a proposed manufacturing facility located at Blount Island, Jacksonville, Florida (Docket No. STN 50-437). No nuclear fuel will be handled or stored at the manufacturing site. The plants will be fueled after they have been towed to and moored within protected basins at specific locations designated by the purchaser and after an operating license has been issued by the Nuclear Regulatory Commission. Each nuclear generating plant, mounted on a floating platform, has a net capacity of 1150 MWe. This energy is provided by a pressurized water reactor steam supply system consisting of a Westinghouse four-loop 3425-MWt unit with an ice-condenser containment system. When one or more of these units is located within a single breakwater, the installation is designated an offshore power station. 226 figs., 95 tabs

  19. A High Current Proton Linac with 352 MHz SC Cavities

    CERN Document Server

    Pagani, C; Pierini, P

    1996-01-01

    A proposal for a 10-120 mA proton linac employing superconducting beta-graded, CERN type, four cell cavities at 352 MHz is presented. The high energy part (100 MeV-1 GeV) of the machine is split in three beta-graded sections, and transverse focusing is provided via a periodic doublet array. All the parameters, like power in the couplers and accelerating fields in the cavities, are within the state of the art, achieved in operating machines. A first stage of operation at 30 mA beam current is proposed, while the upgrade of the machine to 120 mA operation can be obtained increasing the number of klystrons and couplers per cavity. The additional coupler ports, up to four, will be integrated in the cavity design. Preliminary calculations indicate that beam transport is feasible, given the wide aperture of the 352 MHz structures. A capital cost of less than 100 M$ at 10 mA, reaching up to 280 M$ for the 120 mA extension, has been estimated for the superconducting high energy section (100 MeV-1 GeV). The high effic...

  20. 76 FR 79173 - Registration Review; Pesticide Dockets Opened for Review and Comment, and Notice of Availability...

    Science.gov (United States)

    2011-12-21

    ... placed on the Internet and will be publicly available only in hard copy form. Publicly available docket... available in hard copy, at the OPP Regulatory Public Docket in Rm. S-4400, One Potomac Yard (South Bldg.... Section 3(g) of FIFRA provides, among other things, that the registrations of pesticides are to be...

  1. 1 MW, 352.2 MHz, CW and Pulsed RF test stand

    International Nuclear Information System (INIS)

    Badapanda, M.K.; Tripathi, Akhilesh; Upadhyay, Rinki; Tyagi, Rajiv; Hannurkar, P.R.

    2011-01-01

    A 1 MW, 352.2 MHz, RF test stand based on Thales make TH 2089 klystron amplifier is being developed at Raja Ramanna Centre for Advanced Technology (RRCAT), Indore for characterization and qualification of RF components, cavities and related subsystems. Provision to vary RF power from 50 kW to 1 MW with adequate flexibility for testing wide range of HV components, RF components and cavities is incorporated in this test stand. The paper presents a brief detail of various power supplies like high voltage cathode bias power supply, modulating anode power supply, filament power supply, electromagnet power supplies and ion pump power supplies along with their interconnections for biasing TH 2089 klystron amplifier. A digital control and interlock system is being developed to realize proper sequence of operation of various power supplies and to monitor the status of crucial parameters in this test set up. This RF test stand will be a unique national facility, capable of providing both CW and pulse RF power for realizing reliable RF power sources for various projects including the development of high energy proton linac under ADSS program of the Department of Atomic Energy. (author)

  2. 14 CFR 11.35 - Does FAA include sensitive security information and proprietary information in the Federal Docket...

    Science.gov (United States)

    2010-01-01

    ... RULEMAKING PROCEDURES Rulemaking Procedures General § 11.35 Does FAA include sensitive security information and proprietary information in the Federal Docket Management System (FDMS)? (a) Sensitive security information. You should not submit sensitive security information to the rulemaking docket, unless you are...

  3. 78 FR 35622 - Notice of Effectiveness of Exempt Wholesale Generator Status

    Science.gov (United States)

    2013-06-13

    ... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [ Docket Nos. EG13-17-000 et al.] Notice of Effectiveness of Exempt Wholesale Generator Status Docket Nos. CPV Shore, LLC EG13-17-000 Goldwaite Wind Energy LLC EG13-18-000 Patua Project LLC EG13-19-000 Alta Wind X, LLC EG13-21-000 Alta Wind...

  4. Fracionamento de manganês acumulado nos tecidos de mudas de caramboleira

    Directory of Open Access Journals (Sweden)

    Amanda Hernandes

    2011-10-01

    Full Text Available A caramboleira (Averrhoa carambola tende a acumular grande quantidade de Mn nos seus tecidos, mas são escassas as informações sobre a forma como o excesso desse nutriente permanece na planta. Com o objetivo de contribuir para o esclarecimento desse aspecto, neste trabalho foram cultivadas mudas de caramboleira em solução nutritiva de Furlani (1999 com concentrações crescentes de Mn (0; 0,5; 25; e 50 mg L-1 de Mn, e aos 30, 60, 90 e 120 dias os tecidos de caule, folha e raiz foram colhidos e submetidos a uma sequência de soluções extratoras: água, DTPA (ácido dietilenotriaminopentacético e HCl (ácido clorídrico 1 mol L-1, com posterior determinação da quantidade de Mn nos extratos e nos tecidos remanescentes. Foram encontrados teores crescentes de Mn nos extratos de água, DTPA e HCl 1 mol L-1. A maior parte (cerca de 50 % do Mn permaneceu no tecido vegetal, mesmo após subsequentes extrações com as diferentes soluções extratoras, indicando que essa parte está fortemente ligada aos tecidos. Os maiores teores de Mn foram encontrados nas raízes e, os menores, no caule e nas folhas, sugerindo que a caramboleira tende a fixar o Mn nas raízes, possivelmente como mecanismo para limitar o transporte para a parte área, evitando a intoxicação da planta.

  5. 20 CFR 501.8 - Clerk of the Office of the Appellate Boards; docket of proceedings; records.

    Science.gov (United States)

    2010-04-01

    ... 20 Employees' Benefits 3 2010-04-01 2010-04-01 false Clerk of the Office of the Appellate Boards; docket of proceedings; records. 501.8 Section 501.8 Employees' Benefits EMPLOYEES' COMPENSATION APPEALS BOARD, DEPARTMENT OF LABOR RULES OF PROCEDURE § 501.8 Clerk of the Office of the Appellate Boards; docket of proceedings; records. (a) Location...

  6. 76 FR 13610 - Notice of Effectiveness of Exempt Wholesale Generator Status

    Science.gov (United States)

    2011-03-14

    ... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Docket Nos. EG11-33-000 et al.] Notice of Effectiveness of Exempt Wholesale Generator Status Windstar Energy, LLC Docket No. EG11-33-000. Hatchet Ridge Wind 2010-B........ Docket No. EG11-34-000. Hatchet Ridge Wind 2010-B, Docket No. EG11-35...

  7. Production and Test of 352 MHZ Niobum-Sputtered Reduced-$\\beta$ Cavities

    CERN Document Server

    Benvenuti, Cristoforo; Calatroni, Sergio; Chiaveri, Enrico; Tückmantel, Joachim

    1997-01-01

    Three types of 352 MHz single-cell cavities foreseen for different particle speeds (v/c=0.8, 0.625 and 0.48) have been designed and built with the niobium sputtered on copper technique. We report on the results of the cold tests at 4.5 and 2.5 K and the actual status of the data analysis.

  8. Safety evaluation report related to the operation of WPPSS Nuclear Project No. 2, (Docket No. 50-397). Supplement No. 4

    International Nuclear Information System (INIS)

    1983-12-01

    Supplement No. 4 to the Safety Evaluation Report on the application filed by Washington Public Power Supply System for a license to operate the WPPSS Nuclear Project No. 2, located in Richland, Washington, has been prepared by the Division of Licensing, Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement reports the status of certain items that had not been resolved at the time of publication of the Safety Evaluation Report and Supplement Nos. 1, 2 and 3

  9. Nitric Oxide Synthase Enzymes in the Airways of Mice Exposed to Ovalbumin: NOS2 Expression Is NOS3 Dependent

    Directory of Open Access Journals (Sweden)

    Jennifer M. Bratt

    2010-01-01

    Full Text Available Objectives and Design. The function of the airway nitric oxide synthase (NOS isoforms and the lung cell types responsible for its production are not fully understood. We hypothesized that NO homeostasis in the airway is important to control inflammation, which requires upregulation, of NOS2 protein expression by an NOS3-dependent mechanism. Materials or Subjects. Mice from a C57BL/6 wild-type, NOS1−/−, NOS2−/−, and NOS3−/− genotypes were used. All mice strains were systemically sensitized and exposed to filtered air or ovalbumin (OVA aerosol for two weeks to create a subchronic model of allergen-induced airway inflammation. Methods. We measured lung function, lung lavage inflammatory and airway epithelial goblet cell count, exhaled NO, nitrate and nitrite concentration, and airway NOS1, NOS2, and NOS3 protein content. Results. Deletion of NOS1 or NOS3 increases NOS2 protein present in the airway epithelium and smooth muscle of air-exposed animals. Exposure to allergen significantly reduced the expression of NOS2 protein in the airway epithelium and smooth muscle of the NOS3−/− strain only. This reduction in NOS2 expression was not due to the replacement of epithelial cells with goblet cells as remaining epithelial cells did not express NOS2. NOS1−/− animals had significantly reduced goblet cell metaplasia compared to C57Bl/6 wt, NOS2−/−, and NOS3−/− allergen-exposed mice. Conclusion. The airway epithelial and smooth muscle cells maintain a stable airway NO concentration under noninflammatory conditions. This “homeostatic” mechanism is unable to distinguish between NOS derived from the different constitutive NOS isoforms. NOS3 is essential for the expression of NOS2 under inflammatory conditions, while NOS1 expression contributes to allergen-induced goblet cell metaplasia.

  10. Nitric Oxide Synthase Enzymes in the Airways of Mice Exposed to Ovalbumin: NOS2 Expression Is NOS3 Dependent

    Science.gov (United States)

    Bratt, Jennifer M.; Williams, Keisha; Rabowsky, Michelle F.; Last, Michael S.; Franzi, Lisa M.; Last, Jerold A.; Kenyon, Nicholas J.

    2010-01-01

    Objectives and Design. The function of the airway nitric oxide synthase (NOS) isoforms and the lung cell types responsible for its production are not fully understood. We hypothesized that NO homeostasis in the airway is important to control inflammation, which requires upregulation, of NOS2 protein expression by an NOS3-dependent mechanism. Materials or Subjects. Mice from a C57BL/6 wild-type, NOS1−/−, NOS2−/−, and NOS3−/− genotypes were used. All mice strains were systemically sensitized and exposed to filtered air or ovalbumin (OVA) aerosol for two weeks to create a subchronic model of allergen-induced airway inflammation. Methods. We measured lung function, lung lavage inflammatory and airway epithelial goblet cell count, exhaled NO, nitrate and nitrite concentration, and airway NOS1, NOS2, and NOS3 protein content. Results. Deletion of NOS1 or NOS3 increases NOS2 protein present in the airway epithelium and smooth muscle of air-exposed animals. Exposure to allergen significantly reduced the expression of NOS2 protein in the airway epithelium and smooth muscle of the NOS3−/− strain only. This reduction in NOS2 expression was not due to the replacement of epithelial cells with goblet cells as remaining epithelial cells did not express NOS2. NOS1−/− animals had significantly reduced goblet cell metaplasia compared to C57Bl/6 wt, NOS2−/−, and NOS3−/− allergen-exposed mice. Conclusion. The airway epithelial and smooth muscle cells maintain a stable airway NO concentration under noninflammatory conditions. This “homeostatic” mechanism is unable to distinguish between NOS derived from the different constitutive NOS isoforms. NOS3 is essential for the expression of NOS2 under inflammatory conditions, while NOS1 expression contributes to allergen-induced goblet cell metaplasia. PMID:20953358

  11. Orthodontic force stimulates eNOS and iNOS in rat osteocytes

    NARCIS (Netherlands)

    Tan, S.D.; Xie, R.; Klein Nulend, J.; van Rheden, R.E.; Bronckers, A.L.J.J.; Kuijpers-Jagtman, A.M.; Von den Hoff, J.W.; Maltha, J.C.

    2009-01-01

    Mechanosensitive osteocytes are essential for bone remodeling. Nitric oxide, an important regulator of bone remodeling, is produced by osteocytes through the activity of constitutive endothelial nitric oxide synthase (eNOS) or inducible nitric oxide synthase (iNOS). We hypothesized that these

  12. Orthodontic force stimulates eNOS and iNOS in rat osteocytes.

    NARCIS (Netherlands)

    Tan, S.D.; Xie, R.; Klein-Nulend, J.; Rheden, R.E.M. van; Bronckers, A.L.; Kuijpers-Jagtman, A.M.; Hoff, J.W. Von den; Maltha, J.C.

    2009-01-01

    Mechanosensitive osteocytes are essential for bone remodeling. Nitric oxide, an important regulator of bone remodeling, is produced by osteocytes through the activity of constitutive endothelial nitric oxide synthase (eNOS) or inducible nitric oxide synthase (iNOS). We hypothesized that these

  13. 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

  14. Safety evaluation report related to operation of Sequoyah Nuclear Plant, Units 1 and 2, Docket nos. 50-327 and 50-328, Tennessee Valley Authority

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1979-03-01

    A safety evaluation of the Tennessee Valley Authority's application for a license to operate its Sequoyah Nuclear Plant, Units 1 and 2, located in Hamilton County, Tennessee, has been prepared by the Office of Nuclear Reactor Regulation of the Nuclear Regulatory Commission. It consists of a technical review and staff evaluation of applicant information on: (1) population density, land use, and physical characteristics of the site area; (2) design, fabrication, construction, testing criteria, and performance characteristics of plant structures, systems, and components important to safety; (3) expected response of the facility to anticipated operating transients, and to postulated design basis accidents; (4) applicant engineering and construction organization, and plans for the conduct of plant operations; and (5) design criteria for a system to control the plant's radiological effluents. The staff has concluded that the plant can be operated by the Tennessee Valley Authority without endangering the health and safety of the public provided that the outstanding matters discussed in the report are favorably resolved. (author)

  15. 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

  16. 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

  17. Final environmental statement related to the operation of Midland Plant, Units 1 and 2. Docket Nos. 50-329 and 50-330, Consumers Power Company

    International Nuclear Information System (INIS)

    1982-07-01

    This final environmental statement contains the second assessment of the environmental impact associated with operation of the Midland Plant, Units 1 and 2 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 purpose and need for the Midland project, alternatives to the project, the affected environment, environment consequences and mitigating actions, and environmental and economic benefits and costs

  18. 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

  19. 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)

    1985-10-01

    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, and 6 to that report. This supplement also lists the new issues that have been identified since Supplement 6 was issued and includes the evaluations for licensing items resolved in this interim period. Supplement 5 has not been issued. Supplements 7, 8, 9, 10, and 11 were limited to the staff evaluations of allegations investigated by the NRC Technical Review Team, and items identified therein are not included in this supplement

  20. Final environmental statement related to the operation of Comanche Peak Steam Electric Station, Units 1 and 2: (Docket Nos. 50-445 and 50-446)

    International Nuclear Information System (INIS)

    1981-09-01

    The proposed action is the issuance of operating licenses to the Texas Utilities Generating Company for the startup and operation of Units 1 and 2 of the Comanche Peak Steam Electric Station located on Squaw Creek Reservoir in Somervell County, Texas, about 7 km north-northeast of Glen Rose, Texas, and about 65 km southwest of Fort Worth in north-central Texas. The information in this environmental statement represents the second assessment of the environmental impact associated with the Comanche Peak Steam Electric Station pursuant to the guidelines of the National Environmental Policy Act of 1969 (NEPA) and 10 CFR Part 51 of the Commission's Regulations. After receiving an application to construct this station, the staff carried out a review of impact that would occur during its construction and operation. This evaluation was issued as a Final Environmental Statement -- Construction Phase. After this environmental review, a safety review, an evaluation by the Advisory Committee on Reactor Safeguards, and public hearings in Glen Rose, Texas, the US Atomic Energy Commission (now US Nuclear Regulatory Commission) issued construction permits for the construction of Units 1 and 2 of the Comanche Peak Steam Electric Station. 16 figs., 34 tabs

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

    International Nuclear Information System (INIS)

    1975-02-01

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

  2. 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)

    1984-11-01

    This supplement reports the status of certain issues that had not been resolved at the time of publication of the Safety Evaluation Report and Supplement 1, 2, 3, and 4 of that report. (Supplement 5, currently in preparation, will document the staff's evaluation findings pertaining solely to an independent design verification, conducted for the applicant by the CYGNA Corporation in late 1983-early 1984, and does not update the status of issues since the release of Supplement 4.)

  3. Safety evaluation report related to the construction of Skagit/Hanford Nuclear Project, Units 1 and 2. Docket Nos. STN 50-522 and 50-523

    International Nuclear Information System (INIS)

    1982-12-01

    Supplement 3 to the Safety Evaluation Report for the application filed by Puget Sound Power and Light Company on behalf of itself, the Pacific Power and Light Company, The Washington Water Power Company, and the Portland General Electric Company for construction permits to build the Skagit/Hanford Nuclear Project has been issued by the Office of Nuclear Reactor Regulation of the United States Nuclear Regulatory Commission. This supplement is an evaluation of the site relocation amendment to the Preliminary Safety Analysis Report. The proposed site has been relocated from Skagit County, Washington, to the Department of Energy's Hanford Reservation

  4. 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

  5. Draft environmental statement related to construction of Yellow Creek Nuclear Plant, Units 1 and 2: (Docket Nos. STN 50-566 and STN 50-567)

    International Nuclear Information System (INIS)

    1977-06-01

    The proposed action is the issuance of construction permits to the Tennessee Valley Authority for the construction of the Yellow Creek Nuclear Plant Units 1 and 2. The 470-hectare site is predominantly wooded. Construction-related activities on the site would disturb about 59 hectares. The portion of this land not to be used for plant facilities, parking lots, roads, etc., will be restored by seeding and landscaping. The temporary removal of vegetation will tend to promote erosion. Increased siltation and turbidity can be expected in the Yellow Creek embayment during construction, but measures will be taken to minimize these effects. A maximum of 237.6 m 3 /min of make-up water will be withdrawn from the Yellow Creek embayment, of which 106 m 3 /min will be returned to Pickwick Lake via a pipeline with the dissolved solids concentration increased by a factor of about two. About 106 m 3 /min will be evaporated to the atmosphere by the cooling towers. The volume of thermal discharge (106 m 3 /min) is small compared with the flow in Pickwick Lake (minimum daily average flow of 7812 m 3 /min) and the effect on the Pickwick Lake ecosystem is not expected to be significant. During periods of average flow the plant could use about 24% of the flow through Yellow Creek embayment. Chemical discharges (with the possible exception of copper) from the plant will be diluted to concentrations below those which might adversely affect aquatic biota. The risk associated with accidental radiation exposure will be very low. 42 figs., 100 tabs

  6. Intoxicação em suínos pela ingestão de sementes de Aeschynomene indica (Leg.Papilionoideae)

    OpenAIRE

    Oliveira,Fabiano N.; Rech,Raquel R.; Rissi,Daniel R.; Barros,Ricardo R.; Barros,Claudio S.L.

    2005-01-01

    Relata-se um surto espontâneo de intoxicação em suínos pela ingestão de sementes de Aeschynomene indica e a reprodução da doença nessa espécie animal. O surto espontâneo ocorreu numa propriedade de criação de suínos localizada na região central do Rio Grande do Sul. Nessa propriedade havia 100 suínos (20 matrizes e 80 suínos jovens de várias categorias). Os suínos eram alimentados com uma ração feita na propriedade pela mistura de 50% farelo de milho, 25% de farelo de soja, 5% de um suplement...

  7. Participação nos Lucros ou Resultados

    Directory of Open Access Journals (Sweden)

    Luiz Felipe Ferreira

    2007-03-01

    Full Text Available A participação nos lucros ou resultados é uma forma de remuneração variável, pela qual não há incidência de encargos sociais, além de incentivar o aumento da produtividade, podendo assim ser utilizada pelas empresas como estratégia, para enfrentarem os desafios dinâmicos e competitivos em que atuam. Esta pesquisa caracteriza-se como sendo exploratória, com abordagem qualitativa e tem como objetivo conceituar e explanar as formas pela quais são praticadas a participação nos lucros ou resultados em empresas do setor alimentício em Santa Catarina, que foram escolhidas por meio do critério de acessibilidade e disponibilidade. Dos dados coletados, pode-se verificar que as empresas: COC Alimentos, Moinho Catarinense e Pepsico do Brasil utilizam a participação nos resultados e a Perdigão utiliza a participação mista. A Moinho Catarinense distribui para todos os empregados um salário nominal, como a CDC Alimentos, exceto para os gerentes. A Perdigão beneficia todos os empregados, sendo que 60% da distribuição é pelo lucro líquido e 40% por indicadores de desempenho. A Pepsico do Brasil distribui aos empregados operacionais 50% de um salário nominal e para os empregados da administração central um salário nominal, atrelado ao cumprimento de metas, especificadas no programa de participação nos lucros ou resultados.

  8. 75 FR 22602 - Front-of-Pack and Shelf Tag Nutrition Symbols; Establishment of Docket; Request for Comments and...

    Science.gov (United States)

    2010-04-29

    ... Obesity Among U.S. Adults,'' 1999 to 2008, Journal of the American Medical Association, 2010;303(3):235... DEPARTMENT OF HEALTH AND HUMAN SERVICES Food and Drug Administration [Docket No. FDA-2010-N-0210... Information AGENCY: Food and Drug Administration, HHS. ACTION: Notice; establishment of docket; request for...

  9. Vasoactive and radioprotective properties of isothiourea derivatives having NOS-inhibitory activity

    Energy Technology Data Exchange (ETDEWEB)

    Filimonova, Marina V.; Shevchenko, Ludmila I.; Ulyanenko, Stepan E.; Makarchuk, Victorya M.; Kuznetsova, Mary N.; Shevchuk, Aza S.; Lushnikova, Galina A.; Chesnakova, Ekaterina A. [Medical Radiological Research Center Health Ministry of Russia, 4, Korolev street, Obninsk, 249036, Kaluga region (Russian Federation)

    2014-07-01

    We studied vasoactive and radioprotective properties of new original N-acyl, S-alkyl isothiourea derivatives which are potent inhibitors of nitric oxide synthases (preferably eNOS and iNOS). These compounds have a moderate toxicity (LD50 - 400-550 mg/kg), and are stable in aqueous solutions. In hemodynamic studies, these compounds exhibited high vasotropic activity. The use of these compounds in doses of 5-15 mg/kg (0,01-0,03 LD{sub 50}) in the experimental animals in a state of the severe hemorrhagic or endo-toxic shock causes a potent vasopressor effect, accompanied by a significant and continuous rise in blood pressure. The increasing of vascular tone developed over 2-5 min after injection and persisted for at least 60-90 minutes, excelling at least 3-5 times the duration of α1-adreno-mimetic vasopressor action. The rapid increase in vascular tone under the influence of these compounds in normo-tonic animals caused protective baroreflex to prevent high blood pressure. At doses of 10-15 mg/kg the reflex reaction was mild, but at higher doses (30-40 mg/kg) the reaction was fierce and prolonged, and was accompanied by severe bradycardia, decreasing of the cardiac output and a significant weakening of the peripheral blood flow. In all cases, the hemodynamic response was reflexive and easily eliminated by atropine. The ability of these compounds to induce circulatory hypoxia was the basis for the study of their radioprotective properties. The study of radioprotective effect on the survival of animals exposed to lethal doses of γ-radiation (10 Gy) and on the survival of hematopoietic clonogenic cells showed that these compounds in doses of 80-150 mg/kg (0,2-0,3 LD50) have considerable radioprotective action, which is comparable with the protective effect of the maximum tolerated dose of cystamine. The factor of change in dose for γ-radiation, estimated by the LD{sub 50}, was 1,42-1,58. We also investigated the ability of the test compounds, due to their hypoxic

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

    International Nuclear Information System (INIS)

    1978-07-01

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

  11. 75 FR 16114 - Registration Review; Biopesticides Dockets Opened for Review and Comment

    Science.gov (United States)

    2010-03-31

    ... ENVIRONMENTAL PROTECTION AGENCY [EPA-HQ-OPP-2010-0118; FRL-8816-1] Registration Review; Biopesticides Dockets Opened for Review and Comment AGENCY: Environmental Protection Agency (EPA). ACTION...: March 25, 2010. Keith A. Matthews, Acting Director, Biopesticides and Pollution Prevention Division...

  12. 77 FR 48448 - Connect America Fund; A National Broadband Plan for Our Future; Establishing Just and Reasonable...

    Science.gov (United States)

    2012-08-14

    ... costs of universal service fund (USF) contributions by passing through an explicit charge to customers... Docket No. 09-51; CC Docket Nos. 01-92, 96-45; WT Docket No. 10-208; DA 12-870] Connect America Fund; A...; High-Cost Universal Service Support AGENCY: Federal Communications Commission. ACTION: Final rule...

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

    International Nuclear Information System (INIS)

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

    1984-01-01

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

  14. Safety Evaluation Report related to the operation of Grand Gulf Nuclear Station, Units 1 and 2 (Docket Nos. 50-416 and 50-417). Supplement 6

    International Nuclear Information System (INIS)

    1984-08-01

    Supplement 6 to the Safety Evaluation Report for Mississippi Power and Light Company et al. joint application for licenses to operate the Grand Gulf Nuclear Station, Units 1 and 2, located on the east bank of the Mississippi River near Port Gibson in Claiborne County, Mississippi, has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement reports the NRC staff's evaluation of open items from previous supplements and Technical Specification changes required before authorizing operation of Unit 1 above 5% of rated power

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

    International Nuclear Information System (INIS)

    1976-03-01

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

  16. Safety evaluation report related to the operation of Sequoyah Nuclear Plant, Units 1 and 2, Docket Nos. 50-327 and 50-328, Tennessee Valley Authority

    International Nuclear Information System (INIS)

    1982-12-01

    Supplement No. 6 to the Safety Evaluation Report (SER) related to the operation of the Tennessee Valley Authority's Sequoyah Nuclear Plant, Units 1 and 2, located in Hamilton County, Tennessee, 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 staff's evaluations of the issues related to the hydrogen mitigation system identified in the SER and previous supplements as needing resolution

  17. Safety evaluation report related to the operation of Susquehanna Steam Electric Station, Units 1 and 2 (Docket Nos. 50-387 and 50-388). Suppl.6

    International Nuclear Information System (INIS)

    1984-03-01

    In April 1981, the staff of the Nuclear Regulatory Commission issued its Safety Evaluation Report (NUREG-0776) regarding the application of the Pennsylvania Power and Light Company (the applicant and/or licensee) and the Allegheny Electric Cooperative, Inc. (co-applicant) for licenses to operate the Susquehanna Steam Electric Station, Units 1 and 2, located on a site in Luzerne County, Pennsylvania. This supplement to NUREG-0776 addresses the remaining issues that required resolution before licensing operation of Unit 2 and closes them out

  18. 78 FR 41803 - Establishment of a Public Docket for Comment on the Report Prepared Under the Food and Drug...

    Science.gov (United States)

    2013-07-11

    ... Administration Safety and Innovation Act (FDASIA) Section 1138, enacted July 9, 2012, and posted on the FDA Web... DEPARTMENT OF HEALTH AND HUMAN SERVICES Food and Drug Administration [Docket No. FDA-2013-N-0757] Establishment of a Public Docket for Comment on the Report Prepared Under the Food and Drug Administration...

  19. (--Epigallocatechin gallate attenuates NADPH-d/nNOS expression in motor neurons of rats following peripheral nerve injury

    Directory of Open Access Journals (Sweden)

    Tseng Chi-Yu

    2011-06-01

    Full Text Available Abstract Background Oxidative stress and large amounts of nitric oxide (NO have been implicated in the pathophysiology of neuronal injury and neurodegenerative disease. Recent studies have shown that (--epigallocatechin gallate (EGCG, one of the green tea polyphenols, has potent antioxidant effects against free radical-mediated lipid peroxidation in ischemia-induced neuronal damage. The purpose of this study was to examine whether EGCG would attenuate neuronal expression of NADPH-d/nNOS in the motor neurons of the lower brainstem following peripheral nerve crush. Thus, young adult rats were treated with EGCG (10, 25, or 50 mg/kg, i.p. 30 min prior to crushing their hypoglossal and vagus nerves for 30 seconds (left side, at the cervical level. The treatment (pre-crush doses of EGCG was continued from day 1 to day 6, and the animals were sacrificed on days 3, 7, 14 and 28. Nicotinamide adenine dinucleotide phosphate-diaphorase (NADPH-d histochemistry and neuronal nitric oxide synthase (nNOS immunohistochemistry were used to assess neuronal NADPH-d/nNOS expression in the hypoglossal nucleus and dorsal motor nucleus of the vagus. Results In rats treated with high dosages of EGCG (25 or 50 mg/kg, NADPH-d/nNOS reactivity and cell death of the motor neurons were significantly decreased. Conclusions The present evidence indicated that EGCG can reduce NADPH-d/nNOS reactivity and thus may enhance motor neuron survival time following peripheral nerve injury.

  20. Coupler Development and Gap Field Analysis for the 352 MHz Superconducting CH-Cavity

    CERN Document Server

    Liebermann, H; Ratzinger, U; Sauer, A C

    2004-01-01

    The cross-bar H-type (CH) cavity is a multi-gap drift tube structure based on the H-210 mode currently under development at IAP Frankfurt and in collaboration with GSI. Numerical simulations and rf model measurements showed that the CH-type cavity is an excellent candidate to realize s.c. multi-cell structures ranging from the RFQ exit energy up to the injection energy into elliptical multi-cell cavities. The reasonable frequency range is from about 150 MHz up to 800 MHz. A 19-cell, β=0.1, 352 MHz, bulk niobium prototype cavity is under development at the ACCEL-Company, Bergisch-Gladbach. This paper will present detailed MicroWave Studio simulations and measurements for the coupler development of the 352 MHz superconducting CH cavity. It will describe possibilities for coupling into the superconducting CH-Cavity. The development of the coupler is supported by measurement on a room temperature CH-copper model. We will present the first results of the measurements of different couplers, e.g. capacitiv...

  1. Three-dimensional simulation studies of 10 MeV, 352.2 MHz drift ...

    Indian Academy of Sciences (India)

    It is proposed to build a drift tube Linac (DTL) at Raja Ramanna Centre for Advanced Technology, Indore, India, that will form a part of the future Spallation Neutron Source. This DTL will accelerate 30 mA H-ion beam from 3 MeV to 10 MeV. The DTL is designed to operate at 352.2 MHz with a maximum duty cycle of 3%.

  2. 48 CFR 352.219-71 - Mentor-protégé program reporting requirements.

    Science.gov (United States)

    2010-10-01

    ... 48 Federal Acquisition Regulations System 4 2010-10-01 2010-10-01 false Mentor-protégé program... Clauses 352.219-71 Mentor-protégé program reporting requirements. As prescribed in 319.270-1(b), the Contracting Officer shall insert the following clause: Mentor-Protégé Program Reporting Requirements (January...

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

    International Nuclear Information System (INIS)

    1975-11-01

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

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

    International Nuclear Information System (INIS)

    1989-05-01

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

  5. iNOS-dependent increase in colonic mucus thickness in DSS-colitic rats.

    Directory of Open Access Journals (Sweden)

    Olof Schreiber

    Full Text Available AIM: To investigate colonic mucus thickness in vivo in health and during experimental inflammatory bowel disease. METHODS: Colitis was induced with 5% DSS in drinking water for 8 days prior to experiment, when the descending colonic mucosa of anesthetized rats was studied using intravital microscopy. Mucus thickness was measured with micropipettes attached to a micromanipulator. To assess the contributions of NOS and prostaglandins in the regulation of colonic mucus thickness, the non-selective NOS-inhibitor L-NNA (10 mg/kg bolus followed by 3 mg/kg/h, the selective iNOS-inhibitor L-NIL (10 mg/kg bolus followed by 3 mg/kg/h and the non-selective COX-inhibitor diclofenac (5 mg/kg were administered intravenously prior to experiment. To further investigate the role of iNOS in the regulation of colonic mucus thickness, iNOS -/- mice were used. RESULTS: Colitic rats had a thicker firmly adherent mucus layer following 8 days of DSS treatment than untreated rats (88±2 µm vs 76±1 µm. During induction of colitis, the thickness of the colonic mucus layer initially decreased but was from day 3 significantly thicker than in untreated rats. Diclofenac reduced the mucus thickness similarly in colitic and untreated rats (-16±5 µm vs -14±2 µm. While L-NNA had no effect on colonic mucus thickness in DSS or untreated controls (+3±2 µm vs +3±1 µm, L-NIL reduced the mucus thickness significantly more in colitic rats than in controls (-33±4 µm vs -10±3 µm. The importance of iNOS in regulating the colonic mucus thickness was confirmed in iNOS-/- mice, which had thinner colonic mucus than wild-type mice (35±3 µm vs 50±2 µm, respectively. Furthermore, immunohistochemistry revealed increased levels of iNOS in the colonic surface epithelium following DSS treatment. CONCLUSION: Both prostaglandins and nitric oxide regulate basal colonic mucus thickness. During onset of colitis, the thickness of the mucus layer is initially reduced followed by an iNOS

  6. Tu nos aposte protege

    DEFF Research Database (Denmark)

    Frederiksen, Britta Olrik

    2007-01-01

    Aspirationen af p, t og k i dansk er stedmoderligt behandlet af den gren af den historiske sprogforskning der bygger på skriftligt kildemateriale. Skrivemåden tu nos aposte protege for tu nos ab hoste protege 'bekyt du os mod fjenden' i en tilskrift fra anden halvdel af 1300-tallet i...

  7. Neuronal NOS localises to human airway cilia.

    Science.gov (United States)

    Jackson, Claire L; Lucas, Jane S; Walker, Woolf T; Owen, Holly; Premadeva, Irnthu; Lackie, Peter M

    2015-01-30

    Airway NO synthase (NOS) isoenzymes are responsible for rapid and localised nitric oxide (NO) production and are expressed in airway epithelium. We sought to determine the localisation of neuronal NOS (nNOS) in airway epithelium due to the paucity of evidence. Sections of healthy human bronchial tissue in glycol methacrylate resin and human nasal polyps in paraffin wax were immunohistochemically labelled and reproducibly demonstrated nNOS immunoreactivity, particularly at the proximal portion of cilia; this immunoreactivity was blocked by a specific nNOS peptide fragment. Healthy human epithelial cells differentiated at an air-liquid interface (ALI) confirmed the presence of all three NOS isoenzymes by immunofluorescence labelling. Only nNOS immunoreactivity was specific to the ciliary axonemeand co-localised with the cilia marker β-tubulin in the proximal part of the ciliary axoneme. We report a novel localisation of nNOS at the proximal portion of cilia in airway epithelium and conclude that its independent and local regulation of NO levels is crucial for normal cilia function. Copyright © 2014 Elsevier Inc. All rights reserved.

  8. 75 FR 4344 - Foreign-Trade Zone 50-Long Beach, California Application for Subzone Allegro Mfg. Inc. (Cosmetic...

    Science.gov (United States)

    2010-01-27

    ... DEPARTMENT OF COMMERCE Foreign-Trade Zones Board [Docket 6-2010] Foreign-Trade Zone 50--Long Beach, California Application for Subzone Allegro Mfg. Inc. (Cosmetic, Organizer and Electronic Bags and Accessories) Commerce, CA An application has been submitted to the Foreign-Trade Zones Board (the Board) by the Port of...

  9. The influence of authentic scientific research experiences on teachers' conceptions of the nature of science (NOS) and their NOS teaching practices

    Science.gov (United States)

    Moriarty, Meghan A.

    This study explored the influence of teachers' authentic scientific research experiences (ASREs) on teachers' conceptions of the nature of science (NOS) and teachers' NOS instruction. Twelve high school biology teachers participated in this study. Six of the participants had authentic scientific research experience (ASRE) and six had not participated in authentic scientific research. Data included background surveys, modified Views of the Nature of Science (VNOS) questionnaires, interviews, and teaching observations. Data was coded based on the eight NOS understandings outlined in 2013 in the Next Generation Science Standards (NGSS). Evidence from this study indicates participating in authentic scientific research as a member of a scientific community has dual benefits of enabling high school science teachers with informed understandings of the NOS and positioning them to teach with the NOS. However, these benefits do not always result from an ASRE. If the nature of the ASRE is limited, then it may limit teachers' NOS understandings and their NOS teaching practices. The results of this study suggest that participation in ASREs may be one way to improve teachers' NOS understandings and teaching practices if the experiences themselves offer a comprehensive view of the NOS. Because ASREs and other science learning experiences do not always offer such experiences, pre-service teacher education and professional development opportunities may engage science teachers in two ways: (1) becoming part of a scientific community may enable them to teach with NOS and (2) being reflective about what being a scientist means may improve teachers' NOS understandings and better position them to teach about NOS.. Keywords: nature of science, authentic scientific research experiences, Next Generation Science Standards, teaching about NOS, teaching with NOS.

  10. Safety Evaluation Report related to the operation of Grand Gulf Nuclear Station, Units 1 and 2 (Docket Nos. 50-416 and 50-417). Supplement No. 5

    International Nuclear Information System (INIS)

    1984-08-01

    Supplement 5 to the Safety Evaluation Report for Mississippi Power and Light Company, et al., joint application for licenses to operate the Grand Gulf Nuclear Station, Units 1 and 2, located on the east bank of the Mississippi River near Port Gibson in Claiborne County, Mississippi, has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement reports the status on the resolution of those issues that require further evaluation before authorizing operation of Unit 1 above 5% of rated power

  11. Safety evaluation report related to the operation of LaSalle County Station, Units 1 and 2. Docket Nos. 50-373 and 50-374, Commonwealth Edison Company

    International Nuclear Information System (INIS)

    1982-04-01

    Information is presented concerning design criteria for structures, systems, and components; electric power systems; auxiliary systems; conduct of operations; accident analysis; and TMI-2 action plan requirements

  12. Safety Evaluation Report related to the operation of Byron Station, Units 1 and 2 (Docket Nos. STN 50-454 and STN 50-455). Supplement No. 7

    International Nuclear Information System (INIS)

    1986-11-01

    Supplement No. 7 to the Safety Evaluation Report related to Commonwealth Edison Company's application for licenses to operate the Byron Station, Units 1 and 2, located in Rockvale Township, Ogle County, Illinois, has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement provides additional information supporting the license for initial criticality and power ascension to full-power operation for Unit 2

  13. Safety evaluation report related to the operation of LaSalle County Station, Units 1 and 2. Docket Nos. 50-373 and 50-374. Suppl. No. 5

    International Nuclear Information System (INIS)

    1983-08-01

    Revised information is presented concerning seismic qualification of components; fuel assembly stress analysis; in-service inspection of primary coolant circuits and engineered safety systems; instrumentation; electric equipment; auxiliary systems; operational security; and TMI-2 requirements

  14. Operation of south Texas Project, Units 1 and 2, Docket Nos. 50-498 and 50-499, Houston Lighting and Power Company et. al., Matagorda County, Texas

    International Nuclear Information System (INIS)

    1986-03-01

    The draft version of the environmental impact statement, EPA No. 860106D, deals with licensing a startup of Units 1 and 2 of the South Texas Project, both pressurized water reactors. The plant will permanently eliminate over 3000 acres of farmland and affect another 6000 acres of neighboring farmland. It will discharge cooling water into the Colorado River. Mitigation plans call for 1700 acres of bottom land to become a wildlife preserve and for no use of herbicides in grazing areas. Positive impacts will be increased employment for the area with a corresponding increase in revenues. Negative impacts may be changes in marsh productivity and species composition. There may be a loss of habitat for the American alligator. Risks associated with the accidental release of radiation are rated as very low. The Federal Water Pollution Control Act of 1972 and Nuclear Regulatory Commission Licensing provide legal mandates

  15. Operation of South Texas Project, Units 1 and 2 Docket Nos. 50-498 and 50-499, Houston Lighting and Power Company et.al., Matagorda County, Texas

    International Nuclear Information System (INIS)

    1986-08-01

    The final environmental impact statement (EPA No. 860376F) on a proposal to issue operating licenses for units 1 and 2 of the South Texas Project describes the two pressurized waters reactors that will produce 1250 MWe per unit. A closed-cycle will use water from the Colorado River for cooling. The site will include prime farmland. The study finds no significant effect on aquatic productivity of the river and no disruptions of the terrestrial biota. Economic benefits will include about 1800 new jobs, which will raise tax revenues and spur the local economy. Area marsh lands and wildlife habitat will suffer. The risk of exposure to accidental radiation is considered very low. The Federal Water Pollution Control Act of 1972 and Nuclear Regulatory Commission Licensing require the impact study

  16. Safety evaluation report related to the operation of Watts Bar Nuclear Plant, Units 1 and 2 (Docket Nos. 50-390 and 50-391). Supplement No. 18

    International Nuclear Information System (INIS)

    Tam, P.S.

    1995-10-01

    In June 1982, the Nuclear Regulatory Commission staff (NRC staff or staff) issued a Safety Evaluation Report, NUREG-0847, regarding the application by the Tennessee Valley Authority (TVA or the applicant) for licenses to operate the Watts Bar Nuclear Plant, Units 1 and 2. Each of the following sections and appendices of this supplement is numbered the same as the section or appendix of the SER that is being updated, and the discussions are supplementary to, and not in lieu of, the discussion in the SER, unless otherwise noted. Accordingly, Appendix A continues the chronology of the safety review. Appendix E lists principal contributors to this supplement. Appendix FF is added in this supplement. The other appendices are not changed by this supplement

  17. Draft environmental statement related to the operation of Shearon Harris Nuclear Power Plant, Units 1 and 2. Docket Nos. STN 50-400 and STN 50-401

    International Nuclear Information System (INIS)

    1983-04-01

    This Draft Environmental Statement contains the second assessment of the environmental impact associated with the operation of the Shearon Harris Nuclear Power Plant, Units 1 and 2, pursuant to the National Environmental Policy Act of 1979 (NEPA) and 10 CFR 51, as amended, of the NRC regulations. This statement examines the environment, environmental consequences and mitigating actions, and environmental and economic benefits and costs. Land use and terrestrial and aquatic-ecological impacts will be small. Operational impacts to historic and archeological sites will be negligible. The effects of routine operations, energy transmission, and periodic maintenance of rights-of-way and transmission facilities should not jeopardize any populations of endangered or threatened species. No significant impacts are anticipated from normal operational releases of radioactivity. The risk of radiation exposure associated with accidental release of radioactivity is very low. The net socio-economic effects of the project will be beneficial. The action called for is the issuance of an operating license for Shearon Harris PLant, Units 1 and 2

  18. Safety evaluation report related to the operation of LaSalle County Station, Units 1 and 2, (Docket Nos. 50-373 and 50-374). Supplement No. 7

    International Nuclear Information System (INIS)

    1983-12-01

    Supplement No. 7 to the Safety Evaluation Report of Commonwealth Edison Company's application for a license to operate its La Salle County Station, Unit 2, located on Brookfield Township, La Salle County, Illinois, has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement is to update our evaluations on Unit 2 issues identified in the previous Safety Evaluation Report and Supplements that need resolution prior to issuance of the operating license for Unit 2

  19. Safety evaluation report related to the operation of Watts Bar Nuclear Plant, Units 1 and 2. Docket Nos. 50-390 and 50-391, Tennessee Valley Authority

    International Nuclear Information System (INIS)

    1982-06-01

    Information is presented concerning site characteristics; design criteria; reactor coolant system and connected systems; engineered safety systems; instrumentation and controls; electric power systems; auxiliary systems; steam and power conversion system; radioactive waste system; radiation protection; conduct of operations; accident analysis; and quality assurance

  20. Final Environmental Statement related to the operation of Shearon Harris Nuclear Power Plant, Units 1 and 2 (Docket Nos. STN 50-400 and STN 50-401)

    International Nuclear Information System (INIS)

    1983-10-01

    This Final Environmental Statement contains the second assessment of the environmental impact associated with the operation of the Shoran Harris Nuclear Power Plant, Units 1 and 2, pursuant to the National Environmental Policy Act of 1969 (NEPA) and 10 CFR 51, as amended, of the NRC regulations. This statement examines the environment, environmental consequences and mitigating actions, and environmental economic benefits and costs. Land use and terrestrial and aquatic-ecological impacts will be small. Operational impacts to historic and archaeological sites will be negligible. The effects of routine operations, energy transmission, and periodic maintenance of rights-of-way and transmission facilities should not jeopardize any populations of endangered or threatened species. No significant impacts are anticipated from normal operational releases of radioactivity. The risk of radiation exposure associated with accidental release of radioactivity is very low. The net socioeconomic effects of the project will be beneficial. 19 figs., 21 tabs

  1. iNOS-dependent sweating and eNOS-dependent cutaneous vasodilation are evident in younger adults, but are diminished in older adults exercising in the heat.

    Science.gov (United States)

    Fujii, Naoto; Meade, Robert D; Alexander, Lacy M; Akbari, Pegah; Foudil-Bey, Imane; Louie, Jeffrey C; Boulay, Pierre; Kenny, Glen P

    2016-02-01

    Nitric oxide synthase (NOS) contributes to sweating and cutaneous vasodilation during exercise in younger adults. We hypothesized that endothelial NOS (eNOS) and neuronal NOS (nNOS) mediate NOS-dependent sweating, whereas eNOS induces NOS-dependent cutaneous vasodilation in younger adults exercising in the heat. Further, aging may upregulate inducible NOS (iNOS), which may attenuate sweating and cutaneous vasodilator responses. We hypothesized that iNOS inhibition would augment sweating and cutaneous vasodilation in exercising older adults. Physically active younger (n = 12, 23 ± 4 yr) and older (n = 12, 60 ± 6 yr) adults performed two 30-min bouts of cycling at a fixed rate of metabolic heat production (400 W) in the heat (35°C). Sweat rate and cutaneous vascular conductance (CVC) were evaluated at four intradermal microdialysis sites with: 1) lactated Ringer (control), 2) nNOS inhibitor (nNOS-I, NPLA), 3) iNOS inhibitor (iNOS-I, 1400W), or 4) eNOS inhibitor (eNOS-I, LNAA). In younger adults during both exercise bouts, all inhibitors decreased sweating relative to control, albeit a lower sweat rate was observed at iNOS-I compared with eNOS-I and nNOS-I sites (all P exercise protocol (all P exercise bouts (all P > 0.05). We show that iNOS and eNOS are the main contributors to NOS-dependent sweating and cutaneous vasodilation, respectively, in physically active younger adults exercising in the heat, and that iNOS inhibition does not alter sweating or cutaneous vasodilation in exercising physically active older adults. Copyright © 2016 the American Physiological Society.

  2. Safety evaluation report related to the operation of Palo Verde Nuclear Generating Station, Units, 1, 2, and 3: Docket Nos. STN 50-528, STN 50-529, and STN 50-530

    International Nuclear Information System (INIS)

    1983-03-01

    Information is presented concerning site characteristics; mechanical systems and components; reactor coolant system; engineered safety systems; reactor instrumentation; reactor operations; and quality assurance

  3. Safety evaluation report related to the operation of Palo Verde Nuclear Generating Station, Units 1, 2, and 3: Docket Nos. STN 50-528, STN 50-529, and STN 50-530

    International Nuclear Information System (INIS)

    1982-09-01

    Additional information is presented concerning site characteristics; inservice testing of pumps and valves; reactor coolant system; engineered safety systems; electric power systems; auxiliary systems; and quality assurance

  4. Charge-state distributions of 100, 175, 275, and 352 MeV gold ions emerging from thin carbon foils

    International Nuclear Information System (INIS)

    Martin, J.A.; Auble, R.L.; Erb, K.A.; Jones, C.M.; Olsen, D.K.

    1985-01-01

    These measurements were undertaken as a consequence of our failure early this year to accelerate Au +46 ions in the Oak Ridge Isochronous Cyclotron using an injected beam of 352 MeV 197 Au +17 from the 25 MV tandem accelerator. Following that unsuccessful test, we made a preliminary measurement of the charge-state distribution of 352 MeV 197 Au ions emerging from a carbon foil using the bending magnet that is a part of the cyclotron beam injection system. The measured mean charge was approx.38.5, about 4.5 charge-states lower than predicted by the Sayer semi-empirical formula. The measurements reported here were done more precisely and systematically confirm that preliminary result. 12 refs., 5 figs., 4 tabs

  5. Charge-state distributions of 100, 175, 275, and 352 MeV gold ions emerging from thin carbon foils

    Energy Technology Data Exchange (ETDEWEB)

    Martin, J.A.; Auble, R.L.; Erb, K.A.; Jones, C.M.; Olsen, D.K.

    1985-01-01

    These measurements were undertaken as a consequence of our failure early this year to accelerate Au/sup +46/ ions in the Oak Ridge Isochronous Cyclotron using an injected beam of 352 MeV /sup 197/Au/sup +17/ from the 25 MV tandem accelerator. Following that unsuccessful test, we made a preliminary measurement of the charge-state distribution of 352 MeV /sup 197/Au ions emerging from a carbon foil using the bending magnet that is a part of the cyclotron beam injection system. The measured mean charge was approx.38.5, about 4.5 charge-states lower than predicted by the Sayer semi-empirical formula. The measurements reported here were done more precisely and systematically confirm that preliminary result. 12 refs., 5 figs., 4 tabs.

  6. 75 FR 38532 - Medical Devices; Availability of Safety and Effectiveness Summaries for Premarket Approval...

    Science.gov (United States)

    2010-07-02

    ... summaries of safety and effectiveness data to the Division of Dockets Management (HFA-305), Food and Drug... Safety and Effectiveness Summaries for Premarket Approval Applications AGENCY: Food and Drug... DEPARTMENT OF HEALTH AND HUMAN SERVICES Food and Drug Administration [Docket Nos. FDA-2010-M-0068...

  7. 78 FR 35284 - Medical Devices; Availability of Safety and Effectiveness Summaries for Premarket Approval...

    Science.gov (United States)

    2013-06-12

    ... summaries of safety and effectiveness data to the Division of Dockets Management (HFA-305), Food and Drug... DEPARTMENT OF HEALTH AND HUMAN SERVICES Food and Drug Administration [Docket Nos. FDA-2013-M-0036... Devices; Availability of Safety and Effectiveness Summaries for Premarket Approval Applications AGENCY...

  8. 76 FR 31965 - Medical Devices; Availability of Safety and Effectiveness Summaries for Premarket Approval...

    Science.gov (United States)

    2011-06-02

    ... summaries of safety and effectiveness data to the Division of Dockets Management (HFA-305), Food and Drug... DEPARTMENT OF HEALTH AND HUMAN SERVICES Food and Drug Administration [Docket Nos. FDA-2011-M-0034... Devices; Availability of Safety and Effectiveness Summaries for Premarket Approval Applications AGENCY...

  9. Noscapinoids bearing silver nanocrystals augmented drug delivery, cytotoxicity, apoptosis and cellular uptake in B16F1, mouse melanoma skin cancer cells.

    Science.gov (United States)

    Soni, Naina; Jyoti, Kiran; Jain, Upendra Kumar; Katyal, Anju; Chandra, Ramesh; Madan, Jitender

    2017-06-01

    Noscapine (Nos) and reduced brominated analogue of noscapine (Red-Br-Nos) prevent cellular proliferation and induce apoptosis in cancer cells either alone or in combination with other chemotherapeutic drugs. However, owing to poor physicochemical properties, Nos and Red-Br-Nos have demonstrated their anticancer activity at higher and multiple doses. Therefore, in present investigation, silver nanocrystals of noscapinoids (Nos-Ag 2+ nanocrystals and Red-Br-Nos-Ag 2+ nanocrystals) were customized to augment drug delivery, cytotoxicity, apoptosis and cellular uptake in B16F1 mouse melanoma cancer cells. Nos-Ag 2+ nanocrystals and Red-Br-Nos-Ag 2+ nanocrystals were prepared separately by precipitation method. The mean particle size of Nos-Ag 2+ nanocrystals was measured to be 25.33±3.52nm, insignificantly (P>0.05) different from 27.43±4.51nm of Red-Br-Nos-Ag 2+ nanocrystals. Furthermore, zeta-potential of Nos-Ag 2+ nanocrystals was determined to be -25.3±3.11mV significantly (Pcellular uptake. The Nos-Ag 2+ nanocrystals and Red-Br-Nos-Ag 2+ nanocrystals exhibited an IC 50 of 16.6μM and 6.5μM, significantly (Pcellular morphological alterations in B16F1 cells upon internalization of Nos-Ag 2+ nanocrystals and Red-Br-Nos-Ag 2+ nanocrystals provided the evidences for accumulation within membrane-bound cytoplasmic vacuoles and in enlarged lysosomes and thus triggered mitochondria mediated apoptosis via caspase activation. Preliminary investigations substantiated that Nos-Ag 2+ nanocrystals and Red-Br-Nos-Ag 2+ nanocrystals must be further explored and utilized for the delivery of noscapinoids to melanoma cancer cells. Copyright © 2017 Elsevier Masson SAS. All rights reserved.

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

    International Nuclear Information System (INIS)

    1975-04-01

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

  11. 78 FR 50422 - Medical Devices; Availability of Safety and Effectiveness Summaries for Premarket Approval...

    Science.gov (United States)

    2013-08-19

    ... summaries of safety and effectiveness data to the Division of Dockets Management (HFA-305), Food and Drug... of Safety and Effectiveness Summaries for Premarket Approval Applications AGENCY: Food and Drug... DEPARTMENT OF HEALTH AND HUMAN SERVICES Food and Drug Administration [Docket Nos. FDA-2013-M-0462...

  12. 75 FR 36099 - Medical Devices; Availability of Safety and Effectiveness Summaries for Premarket Approval...

    Science.gov (United States)

    2010-06-24

    ... summaries of safety and effectiveness data to the Division of Dockets Management (HFA-305), Food and Drug...; Availability of Safety and Effectiveness Summaries for Premarket Approval Applications AGENCY: Food and Drug... DEPARTMENT OF HEALTH AND HUMAN SERVICES Food and Drug Administration [Docket Nos. FDA-2009-M-0317...

  13. Federal Communications Commission Semiannual Regulatory Agenda

    Science.gov (United States)

    2010-12-20

    ... Telecommunications Act of 1996 (CC Docket Nos. 96-146, 93-22)......... 498 Implementation of the Subscriber Selection... Regarding AM Radio Service 3060-AJ17 Directional Antenna Performance Verification (MM Docket No. 93-177) 545... 498. IMPLEMENTATION OF THE SUBSCRIBER SELECTION CHANGES PROVISION OF THE TELECOMMUNICATIONS ACT OF...

  14. 352.2 MHz rf system for the ESRF

    International Nuclear Information System (INIS)

    Jacob, J.; David, C.

    1988-01-01

    This paper reports that ESRF's 352.2 MHz RF system that uses 1 MW-CW klystrons and five-cell LEP type cavities has been adopted. In the storage ring (SR), two klystrons will feed a total of four cavities in order to provide the maximum required accelerating voltage of 8.9 MV. In the injector synchrotron (SY), two cavities fed by one klystron in a cycling mode at 10 Hz will give the maximum needed accelerating voltage of 7.3 MV. In multibunch operation of the SR, coupled bunch oscillations will be driven by the higher order modes (HOMs) of the cavities, and may limit the maximum beam current to about 60 mA. Spare ports will allow to install HOM dampers on the cavities in order to raise the instability thresholds above the design current of 100 mA. In addition, active feed back systems may be implemented

  15. Final environmental statement related to the proposed manufacture of floating nuclear power plants by Offshore Power Systems: (Docket No. STN 50-437): Part 2, A generic environmental statement considering the siting and operation of floating nuclear power plants

    International Nuclear Information System (INIS)

    1976-09-01

    The proposed action is the issuance of a manufacturing license to Offshore Power Systems for the startup and operation of a proposed manufacturing facility located at Blount Island, Jacksonville, Florida (Docket No. STN 50-437). No nuclear fuel will be handled or stored at the manufacturing site. The plants will be fueled after they have been towed to and moored within protected basins at specific locations designated by the purchaser and after an operating license has been issued by the Nuclear Regulatory Commission. Each nuclear generating plant, mounted on a floating platform, has a net capacity of 1150 MWe. This energy is provided by a pressurized water reactor steam supply system consisting of a Westinghouse four-loop 3425-MWt unit with an ice-condenser containment system. When one or more of these units is located within a single breakwater, the installation is designated an offshore power station. Volume 2 contains the siting criteria, regulations, effects of construction, effects of operation, and a safety analysis. 2 figs., 2 tabs

  16. Sildenafil Ameliorates Gentamicin-Induced Nephrotoxicity in Rats: Role of iNOS and eNOS

    Directory of Open Access Journals (Sweden)

    Mohamed A. Morsy

    2014-01-01

    Full Text Available Gentamicin, an aminoglycoside antibiotic, is used for the treatment of serious Gram-negative infections. However, its usefulness is limited by its nephrotoxicity. Sildenafil, a selective phosphodiesterase-5 inhibitor, was reported to prevent or decrease tissue injury. The aim of this study is to evaluate the potential protective effects of sildenafil on gentamicin-induced nephrotoxicity in rats. Male Wistar rats were injected with gentamicin (100 mg/kg/day, i.p. for 6 days with and without sildenafil. Sildenafil administration resulted in nephroprotective effect in gentamicin-intoxicated rats as it significantly decreased serum creatinine and urea, urinary albumin, and renal malondialdehyde and nitrite/nitrate levels, with a concomitant increase in renal catalase and superoxide dismutase activities compared to gentamicin-treated rats. Moreover, immunohistochemical examination revealed that sildenafil treatment markedly reduced inducible nitric oxide synthase (iNOS expression, while expression of endothelial nitric oxide synthase (eNOS was markedly enhanced. The protective effects of sildenafil were verified histopathologically. In conclusion, sildenafil protects rats against gentamicin-induced nephrotoxicity possibly, in part, through its antioxidant activity, inhibition of iNOS expression, and induction of eNOS production.

  17. 47 CFR 36.352 - Other property plant and equipment expenses-Account 6510 (Class B telephone companies); Accounts...

    Science.gov (United States)

    2010-10-01

    ... 47 Telecommunication 2 2010-10-01 2010-10-01 false Other property plant and equipment expenses... Plant Expenses-Other § 36.352 Other property plant and equipment expenses—Account 6510 (Class B... JURISDICTIONAL SEPARATIONS PROCEDURES; STANDARD PROCEDURES FOR SEPARATING TELECOMMUNICATIONS PROPERTY COSTS...

  18. 75 FR 70042 - In the Matter of All Power Reactor Licensees and Research Reactor Licensees Who Transport Spent...

    Science.gov (United States)

    2010-11-16

    ... NUCLEAR REGULATORY COMMISSION [Docket Nos (Redacted), License Nos (Redacted), EA (Redacted); NRC- 2010-0351] In the Matter of All Power Reactor Licensees and Research Reactor Licensees Who Transport Spent Nuclear Fuel; Order Modifying License (Effective Immediately) I. The licensees identified in...

  19. 75 FR 79423 - In the Matter of All Power Reactor Licensees and Research Reactor Licensees Who Transport Spent...

    Science.gov (United States)

    2010-12-20

    ... NUCLEAR REGULATORY COMMISSION [Docket Nos. (Redacted), License Nos.: (Redacted), EA (Redacted); NRC- 2010-0351] In the Matter of All Power Reactor Licensees and Research Reactor Licensees Who Transport Spent Nuclear Fuel; Order Modifying License (Effective Immediately) I The licensees identified in...

  20. Safety-evaluation report related to the operation of Diablo Canyon Nuclear Power Plant, Units 1 and 2 (Docket Nos. 50-275 and 50-323). Supplement No. 16

    International Nuclear Information System (INIS)

    1983-08-01

    This supplement addresses certain allegations received by the staff concerning safety deficiencies at the Diablo Canyon project, specifically those relative to design aspects of the component cooling water system (CCWS), including its seismic classification, single failure considerations, and its heat removal capabilities. It is based on the staff's re-review of the Diablo Canyon Final Safety Analysis Report (FSAR); on a site walkdown conducted on January 12, 1983; on information obtained during meetings with the applicant dated March 15, 18, and 25, April 4, 7, and 15, and May 3 and 18, 1983

  1. Safety Evaluation Report related to the operation of Comanche Peak Steam Electric Station, Units 1 and 2 (Docket Nos. 50-445 and 50-446). Supplement No. 9

    International Nuclear Information System (INIS)

    1985-03-01

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

  2. 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. 10

    International Nuclear Information System (INIS)

    1985-04-01

    This Supplement provides the results of the staff's evaluation and resolution of approximately 400 technical concerns and allegations in the mechanical and piping area regarding construction practices at the Comanche Peak facility. This report does not address the Walsh/Doyle allegations regarding deficiencies in the pipe support design process and the new allegations recently received by the staff

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

  4. Final Environmental Statement related to the operation of Perry Nuclear Power Plant, Units 1 and 2 Docket Nos. 50-440 and 50-441, Cleveland Electric Illuminating Company

    International Nuclear Information System (INIS)

    1982-08-01

    The information in this Final Environmental Statement is the second assessment of the environmental impact associated with the construction and operation of the Perry Nuclear Power Plant, Units 1 and 2, located on Lake Erie in Lake County, about 11 km (7 mi) northeast of Painesville, Ohio. The first assessment was the Final Environmental Statement related to the construction of the plant issued in April 1974, prior to issuance of the construction permits (CPRR-148 and CPPR-149). Plant construction for Unit 1 is currently about 83% complete, and Unit 2 about 43% complete. Fuel loading for Units 1 and 2 currently estimated by the licensee (Cleveland Electric Illuminating Company) for November 1983, with Unit 2 fuel load scheduled for May 1987. The present assessment is the result of the NRC staff review of the activities associated with the proposed operation of the plant

  5. Draft environmental statement related to the operation of South Texas Project, Units 1 and 2 (Docket Nos. 50-498 and 50-499). Houston Lighting and Power Company

    International Nuclear Information System (INIS)

    1986-03-01

    This Draft Environmental Statement contains the second assessment of the environmental impact associated with the operation of the South Texas Project, Units 1 and 2, pursuant to the National Environmental Policy Act of 1969 (NEPA) and Title 10 of the ''Code of Federal Regulations,'' Part 51, as amended, of the Nuclear Regulatory Commission regulations. This statement examines the environmental impacts, environmental consequences and mitigating actions, and environmental and economic benefits and costs associated with station operation. Land use and terrestrial and aquatic ecological impacts will be small. No operational impacts to historic and archaeological sites are anticipated. The effects of routine operations, energy transmission, and periodic maintenance of rights-of-way and transmission facilities should not jeopardize any populations of endangered or threatened species. No significant impacts are anticipated from normal operational releases of radioactivity. The risk of radiation exposure associated with accidental release of radioactivity is very low. Socioeconomic impacts of the project are anticipated to be minimal. The action called for is the issuance of an operating license for South Texas Project, Units 1 and 2

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

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

    International Nuclear Information System (INIS)

    1983-01-01

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

  8. Mechanisms of suppression of inducible nitric oxide synthase (iNOS) expression in RAW 264.7 cells by andrographolide

    Science.gov (United States)

    Chiou, Wen-Fei; Chen, Chieh-Fu; Lin, Jin-Jung

    2000-01-01

    Andrographolide, an active component found in leaves of Andrographis paniculata, has been reported to exhibit nitric oxide (NO) inhibitory property in endotoxin-stimulated macrophages, however, the detailed mechanisms remain unclear. In the present study we investigated the effect of andrographolide on the expression of inducible NO synthase (iNOS) mRNA, protein, and enzyme activity in RAW 264.7 macrophages stimulated with lipopolysaccharide (LPS) plus interferon-γ (IFN-γ).RAW 264.7 cells stimulated with LPS/IFN-γ activated NO production; in this condition andrographolide (1–100 μM) inhibited NO production in a dose-dependent manner with an IC50 value of 17.4±1.1 μM. Andrographolide also reduces the expression of iNOS protein level but without a significant effect on iNOS mRNA. The reduction of iNOS activity is thought to be caused by decreased expression of iNOS protein.In a protein stability assay, andrographolide moderately but significantly reduced the amount of iNOS protein as suggested by accelerating degradation. Furthermore, andrographolide also inhibited total protein de novo synthesis as demonstrated by [35S]-methionine incorporation.As a whole, these data suggest that andrographolide inhibits NO synthesis in RAW 264.7 cells by reducing the expression of iNOS protein and the reduction could occur through two additional mechanisms: prevention of the de novo protein synthesis and decreasing the protein stability via a post-transcriptional mechanism. It is also possible that inhibition of iNOS protein expression and NO production under immune stimulation and/or bacteria infection may explain, in part, the beneficial effects of andrographolide as an anti-inflammatory agent. PMID:10780958

  9. Technical Specifications: Clinton Power Station, Unit No. 1 (Docket No. 50-461): Appendix ''A'' to License No. NPF-62

    International Nuclear Information System (INIS)

    1987-04-01

    The Clinton Power Station, Unit No. 1 Technical Specifications were prepared by the US Nuclear Regulatory Commission to set forth limits, operating conditions, and other requirements applicable to a nuclear reactor facility as set forth in Section 50.36 of 10 CFR 50 for the protection of the health and safety of the public

  10. Oxidative damage mediated iNOS and UCP-2 upregulation in rat brain after sub-acute cyanide exposure: dose and time-dependent effects.

    Science.gov (United States)

    Bhattacharya, Rahul; Singh, Poonam; John, Jebin Jacob; Gujar, Niranjan L

    2018-04-03

    Cyanide-induced chemical hypoxia is responsible for pronounced oxidative damage in the central nervous system. The disruption of mitochondrial oxidative metabolism has been associated with upregulation of uncoupling proteins (UCPs). The present study addresses the dose- and time-dependent effect of sub-acute cyanide exposure on various non-enzymatic and enzymatic oxidative stress markers and their correlation with inducible-nitric oxide synthase (iNOS) and uncoupling protein-2 (UCP-2) expression. Animals received (oral) triple distilled water (vehicle control), 0.25 LD50 potassium cyanide (KCN) or 0.50 LD50 KCN daily for 21 d. Animals were sacrificed on 7, 14 and 21 d post-exposure to measure serum cyanide and nitrite, and brain malondialdehyde (MDA), reduced glutathione (GSH), glutathione disulfide (GSSG), cytochrome c oxidase (CCO), superoxide dismutase (SOD), glutathione peroxidase (GPx), glutathione reductase (GR) and catalase (CA) levels, together with iNOS and UCP-2 expression, and DNA damage. The study revealed that a dose- and time-dependent increase in cyanide concentration was accompanied by corresponding CCO inhibition and elevated MDA levels. Decrease in GSH levels was not followed by reciprocal change in GSSG levels. Diminution of SOD, GPx, GR and CA activity was congruent with elevated nitrite levels and upregulation of iNOS and UCP-2 expression, without any DNA damage. It was concluded that long-term cyanide exposure caused oxidative stress, accompanied by upregulation of iNOS. The upregulation of UCP-2 further sensitized the cells to cyanide and accentuated the oxidative stress, which was independent of DNA damage.

  11. Demonstration of 352 Gbit/s Photonically-enabled D-Band Wireless Delivery in one 2x2 MIMO System

    DEFF Research Database (Denmark)

    Puerta Ramírez, Rafael; Yu, Jianjun; Li, Xinying

    2017-01-01

    First demonstration of photonically-enabled independent side-bands D-Band wireless transmission up to 352 Gbit/s with a BER below 3.8×10-3. These results were achieved by means of advanced DSP and antenna polarization multiplexing (2x2 MIMO)....

  12. 78 FR 13662 - Cobra Pipeline Ltd.; Notice of Petition

    Science.gov (United States)

    2013-02-28

    ... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Docket Nos. PR13-32-000; PR13-33-000] Cobra Pipeline Ltd.; Notice of Petition Take notice that on February 4, 2013, Cobra Pipeline Ltd. (Cobra... Docket No. PR13-11-000, as more fully detailed in the petitions. Any person desiring to participate in...

  13. 75 FR 9201 - DCP Raptor Pipeline, LLC; Notice of Compliance Filing

    Science.gov (United States)

    2010-03-01

    ... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Docket No. PR09-32-002] DCP Raptor... Raptor Pipeline, LLC (Raptor) filed its Statement of Operating Conditions in compliance with the January 27, 2010 Letter Order (January 27th Letter Order) in Docket Nos. PR09-32-000 and PR09-32-001. Raptor...

  14. 75 FR 5779 - Notice Providing Agenda for Technical Conference on RTO/ISO Responsiveness

    Science.gov (United States)

    2010-02-04

    ... Conference on RTO/ISO Responsiveness January 27, 2010. California Independent System Operator Docket No. ER09.... Southwest Power Pool, Inc Docket Nos. ER09-1050-000, ER09- 1192-000. ISO New England, Inc. and New England.... Agenda--Technical Conference on RTO/ISO Responsiveness February 4, 2010 12:30 Panel 1--Stakeholder...

  15. Report on the intercomparison run IAEA-352 radionuclides in tuna fish flesh

    International Nuclear Information System (INIS)

    Ballestra, S.; Vas, D.; Lopez, J.J.; Noshkin, V.

    1990-08-01

    The results of an intercomparison exercise on a sample of tuna fish flesh from the Mediterranean Sea, IAEA-352, designed for the determination of artificial and natural radionuclides levels, are reported. The data from 63 laboratories from 31 countries have been evaluated. The following are the recommended values, with confidence intervals, for the most frequently measured radionuclides (Reference data: 1 January 1989): 137 Cs 2.7 Bq kg -1 , 90 Sr 0.2 Bq Kg -1 , 40 K 391 Bq Kg -1 , 210 Pb 0.6 Bq Kg -1 , 210 Po 2.2 Bq Kg -1 . Tabs

  16. Technical Specifications, South Texas Project, Unit No. 1 (Docket No. 50-498): Appendix ''A'' to License No. NPF-76

    International Nuclear Information System (INIS)

    1988-03-01

    The South Texas Project, Unit No. 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 50 for the protection of the health and safety of the public. This report is Appendix A to License No. NPF-76

  17. 40 CFR 1612.3 - Published reports and material contained in the public incident investigation dockets.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 32 2010-07-01 2010-07-01 false Published reports and material... Published reports and material contained in the public incident investigation dockets. (a) Demands for published investigation reports should be directed to the Office of Congressional and Public Affairs, U.S...

  18. 78 FR 6316 - Big Blue Wind Farm, LLC, et al.; Notice of Effectiveness of Exempt Wholesale Generator Status

    Science.gov (United States)

    2013-01-30

    ... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Docket No. EG13-1-000, et al.] Big Blue Wind Farm, LLC, et al.; Notice of Effectiveness of Exempt Wholesale Generator Status Docket Nos. Big Blue Wind Farm, LLC EG13-1-000 Calpine Bosque Energy Center, LLC EG13-2-000 Homer City Generation, L.P...

  19. Alan R. Barton Nuclear Plant Units 1, 2, 3 and 4: Draft environmental statement (Docket Nos. 50-524, 525, 526 and 527)

    International Nuclear Information System (INIS)

    1975-04-01

    The proposed action is the issuance of construction permits to the Alabama Power Company for the construction of the Alan R. Barton Nuclear Plant Units 1, 2, 3 and 4. The Barton Plant, located on the Coosa River in Chilton and Elmore Counties, Alabama, will employ boiling water reactors to produce up to 3579 megawatts thermal (MWt) from each unit. A steam turbine-generator will use the heat to provide 1159 MWe (net) of electrical power capacity. A stretch power level of 3758 MWt (1209 MWe) is anticipated from design data and is considered in the assessments contained in this statement. The exhaust steam will be cooled in a closed cycle mode by mechanical cooling towers with water from the Coosa River. Construction of the plant and adjacent facilities will disturb an area of about 1025 acres. the land presently consists of forest land and some cropland. The impact is considered minor. About 18,460 acres will be required for the transmission line routes. The land presently consists of forest, pasture and cropland. No unique land usage is involved in the routes selected. The impacts are considered minor. Station construction will involve some community impacts. Highway congestion, due to increased traffic associated with construction and commuting activities, will have a moderate adverse impact on the local area. The number of construction workers moving into the area is expected to place a strain on the local school systems, housing and community services. Noise, dust, and odor during construction will have a minor adverse effect upon nearby residents in the sparsely populated area. 125 refs., 25 figs., 56 tabs

  20. A blowout numerical model for the supernova remnant G352.7-0.1

    OpenAIRE

    Toledo Roy, J. C.; Velazquez, P. F.; Esquivel, A.; Giacani, Elsa Beatriz

    2017-01-01

    We present 3D hydrodynamical simulations of the Galactic supernova remnant G352.7−0.1. This remnant is peculiar for having a shell-like inner ring structure and an outer arc in radio observations. In our model, the supernova explosion producing the remnant occurs inside and near the border of a spherical cloud with a density higher than that of the surrounding interstellar medium. A blowout is produced when the remnant reaches the border of the cloud. We have then used the results of our hydr...

  1. Multifaceted NOS Instruction: Contextualizing Nature of Science with Documentary Films

    Science.gov (United States)

    Bloom, Mark; Binns, Ian C.; Koehler, Catherine

    2015-01-01

    This research focuses on inservice science teachers' conceptions of nature of science (NOS) before and after a two-week intensive summer professional development (PD). The PD combined traditional explicit NOS instruction, numerous interactive interventions that highlighted NOS aspects, along with documentary films that portrayed NOS in context of…

  2. 76 FR 50724 - Sawgrass Storage, L.L.C.; Notice of Application

    Science.gov (United States)

    2011-08-16

    ... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Docket Nos. CP11-523-000; PF10-20-000] Sawgrass Storage, L.L.C.; Notice of Application Take notice that on July 27, 2011, Sawgrass Storage, L.L.C..., filed an application in Docket No. CP11-523-000 pursuant to Section 7(c) of the Natural Gas Act (NGA...

  3. Identification of hamster inducible nitric oxide synthase (iNOS) promoter sequences that influence basal and inducible iNOS expression

    Science.gov (United States)

    Saldarriaga, Omar A.; Travi, Bruno L.; Choudhury, Goutam Ghosh; Melby, Peter C.

    2012-01-01

    IFN-γ/LPS-activated hamster (Mesocricetus auratus) macrophages express significantly less iNOS (NOS2) than activated mouse macrophages, which contributes to the hamster's susceptibility to intracellular pathogens. We determined a mechanism responsible for differences in iNOS promoter activity in hamsters and mice. The HtPP (1.2 kb) showed low basal and inducible promoter activity when compared with the mouse, and sequences within a 100-bp region (−233 to −133) of the mouse and hamster promoters influenced this activity. Moreover, within this 100 bp, we identified a smaller region (44 bp) in the mouse promoter, which recovered basal promoter activity when swapped into the hamster promoter. The mouse homolog (100-bp region) contained a cis-element for NF-IL-6 (−153/−142), which was absent in the hamster counterpart. EMSA and supershift assays revealed that the hamster sequence did not support the binding of NF-IL-6. Introduction of a functional NF-IL-6 binding sequence into the hamster promoter or its alteration in the mouse promoter revealed the critical importance of this transcription factor for full iNOS promoter activity. Furthermore, the binding of NF-IL-6 to the iNOS promoter (−153/−142) in vivo was increased in mouse cells but was reduced in hamster cells after IFN-γ/LPS stimulation. Differences in the activity of the iNOS promoters were evident in mouse and hamster cells, so they were not merely a result of species-specific differences in transcription factors. Thus, we have identified unique DNA sequences and a critical transcription factor, NF-IL-6, which contribute to the overall basal and inducible expression of hamster iNOS. PMID:22517919

  4. Safety evaluation report related to the operation of Sequoyah Nuclear Plant, Units 1 and 2, Docket Nos. 50-327 and 50-328, Tennessee Valley Authority. Supplement No. 3

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1980-09-01

    It was stated in Supplement No. 2 to the Safety Evaluation Report that except for the hydrogen control measures for the Sequoyah units, all matters had been resolved to the extent that the activities authorized by the license can be conducted without endangering the health and safety of the public. The staff is presently reviewing a recent report from TVA entitled 'Report on the Safety Evaluation of the Interim Distributed Ignition System' (Volume 1 and 2) dated September 2, 1980. This supplement provides further information and reviews on the hydrogen issue. Pending further action which may be required as a result of rulemaking, but no later than January 31, 1981, TVA shall by testing and analysis show to the NRC's satisfaction that the interim distributed ignition system will function in a manner that will mitigate the risk which could stem from the generation of hydrogen.

  5. Safety evaluation report related to the operation of Sequoyah Nuclear Plant, Units 1 and 2, Docket Nos. 50-327 and 50-328, Tennessee Valley Authority. Supplement No. 2

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1980-08-01

    The purpose of this supplement is to further update the Safety Evaluation Report by providing (1) our evaluation of additional information submitted by the licensee since the issuance of Supplement No. 1 to the Safety Evaluation Report, (2) our evaluation and status of the Non-TMI-2 outstanding issues identified in Part I of SER Supplement No. 1, (3) our evaluation of TMI-2 requirements which must be completed prior to the issuance of a full-power operating license, (4) our evaluation of dated requirements which the licensee must implement by the dates identified in NUREG-0694, TMI-Related Requirements for New Operating Licenses, and (5) our evaluation of additional information for those sections of the Safety Evaluation Report where further discussion or changes are in order.

  6. Final supplement to the final environmental statement related to construction of Skagit Nuclear Power Project, Units 1 and 2: (Docket Nos. STN 50-522 and STN 50-523)

    International Nuclear Information System (INIS)

    1977-04-01

    The proposed action is the issuance of construction permits to the Puget Sound Power and Light Company, Pacific Power and Light Company, Washington Water Power Company and the Portland General Electric Company, for the construction of Skagit Nuclear Power Projects Units 1 and 2 in Skagit County, Washington (about 64 miles north of Seattle and 6 miles ENE of Sedro Woolley). These units are scheduled for commercial service in 1984 and 1986, respectively. The exhaust steam from the turbine-generators will be cooled in condensers which will utilize one hyperbolic-type natural-draft cooling tower per unit to dissipate heat to the atmosphere. Water (106 cfs max.) for the cooling tower makeup (82.4 cfs) and other plant uses will be withdrawn from the Skagit River through Ranney Collectors embedded in the north bank of the river and pumped to the plant through a pipeline about 35,000 ft. long. Cooling tower blowdown (7 cfs max.) from the project and dilution water (20 cfs max.) will flow through a pipeline back to the river where it will be discharged through a diffuser. Approximately 1750 acres of forested and agricultural land will be removed from harvesting for the life of the power plant; 360 acres of this land will be diverted to industrial use. This will affect less than 0.5% of standing forest in Skagit County and 16 acres in cultivated crops and pasturage. Increased siltation of onsite creeks and the Skagit River from construction work and the small amounts of heat and chemicals discharged to the river during plant operation will have insignificant impacts on water quality and aquatic biota due to erosion control efforts and dilution by the large river flow. (16,200 cfs average; 4740 cfs 7-day, 10-yr low). 18 figs

  7. Safety evaluation report related to the operation of Sequoyah Nuclear Plant, Units 1 and 2, Docket Nos. 50-327 and 50-328, Tennessee Valley Authority. Supplement No. 3

    International Nuclear Information System (INIS)

    1980-09-01

    It was stated in Supplement No. 2 to the Safety Evaluation Report that except for the hydrogen control measures for the Sequoyah units, all matters had been resolved to the extent that the activities authorized by the license can be conducted without endangering the health and safety of the public. The staff is presently reviewing a recent report from TVA entitled 'Report on the Safety Evaluation of the Interim Distributed Ignition System' (Volume 1 and 2) dated September 2, 1980. This supplement provides further information and reviews on the hydrogen issue. Pending further action which may be required as a result of rulemaking, but no later than January 31, 1981, TVA shall by testing and analysis show to the NRC's satisfaction that the interim distributed ignition system will function in a manner that will mitigate the risk which could stem from the generation of hydrogen

  8. 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

  9. 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

  10. Safety evaluation report related to the operation of Sequoyah Nuclear Plant, Units 1 and 2, Docket Nos. 50-327 and 50-328, Tennessee Valley Authority. Supplement No. 2

    International Nuclear Information System (INIS)

    1980-08-01

    The purpose of this supplement is to further update the Safety Evaluation Report by providing (1) our evaluation of additional information submitted by the licensee since the issuance of Supplement No. 1 to the Safety Evaluation Report, (2) our evaluation and status of the Non-TMI-2 outstanding issues identified in Part I of SER Supplement No. 1, (3) our evaluation of TMI-2 requirements which must be completed prior to the issuance of a full-power operating license, (4) our evaluation of dated requirements which the licensee must implement by the dates identified in NUREG-0694, TMI-Related Requirements for New Operating Licenses, and (5) our evaluation of additional information for those sections of the Safety Evaluation Report where further discussion or changes are in order

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

    International Nuclear Information System (INIS)

    1984-03-01

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

  12. Technical specifications for Grand Gulf Nuclear Station, Unit 1 (Docket No. 50-416). Appendix A to License No. NPF-13

    International Nuclear Information System (INIS)

    1984-08-01

    The Grand Gulf Nuclear 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 facility as set forth in Section 50.36 of 10 CFR part 50 for the protection of the health and safety of the public

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

    International Nuclear Information System (INIS)

    1989-04-01

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

  14. St36 electroacupuncture activates nNOS, iNOS and ATP-sensitive potassium channels to promote orofacial antinociception in rats.

    Science.gov (United States)

    Almeida, R T; Galdino, G; Perez, A C; Silva, G; Romero, T R; Duarte, I D

    2017-02-01

    Orofacial pain is pain perceived in the face and/or oral cavity, generally caused by diseases or disorders of regional structures, by dysfunction of the nervous system, or through referral from distant sources. Treatment of orofacial pain is mainly pharmacological, but it has increased the number of reports demonstrating great clinical results with the use of non-pharmacological therapies, among them electroacupuncture. However, the mechanisms involved in the electroacupuncture are not well elucidated. Thus, the present study investigate the involvement of the nitric oxide synthase (NOS) and ATP sensitive K + channels (KATP) in the antinociception induced by electroacupuncture (EA) at acupoint St36. Thermal nociception was applied in the vibrissae region of rats, and latency time for face withdrawal was measured. Electrical stimulation of acupoint St36 for 20 minutes reversed the thermal withdrawal latency and this effect was maintained for 150 min. Intraperitoneal administration of specific inhibitors of neuronal nitric oxide synthase (nNOS), inducible nitric oxide synthase (iNOS) and a KATP channels blocker reversed the antinociception induced by EA. Furthermore, nitrite concentration in cerebrospinal fluid (CSF) and plasma, increased 4 and 3-fold higher, respectively, after EA. This study suggests that NO participates of antinociception induced by EA by nNOS, iNOS and ATP-sensitive K + channels activation.

  15. 75 FR 57782 - Registration Review; Pesticide Dockets Opened for Review and Comment; Amended Work Plan for...

    Science.gov (United States)

    2010-09-22

    ... announcing that the docket for formetanate hydrochloride, which was planned for September 2010, has been... hydrochloride, which was planned for September 2010, has been postponed until December 2010. Table 1... (7417) EPA-HQ-OPP-2010-0214 Carissa Cyran, (703) 347-8781, [email protected] Sodium cyanide (8002...

  16. Obesity, inflammation, and exercise training: relative contribution of iNOS and eNOS in the modulation of vascular function in the mouse aorta

    Directory of Open Access Journals (Sweden)

    Josiane Fernandes da Silva

    2016-09-01

    Full Text Available Background - The understanding of obsesity-related vascular dysfunction remains controversial mainly because of the diseases associated with vascular injury. Exercise training is known to prevent vascular dysfunction. Using an obesity model without comorbidities, we aimed at investigating the underlying mechanism of vascular dysfunction and how exercise interferes with this process.Methods - High-sugar diet was used to induce obesity in mice. Exercise training was performed 5 days/week. Body weight, energy intake, and adipose tissues were assessed; blood metabolic and hormonal parameters were determined; and serum TNFα was measured. Blood pressure and heart rate were assessed by plethysmography. Changes in aortic isometric tension were recorded on myograph. Western blot was used to analyze protein expression. Nitric oxide (NO was evaluated using fluorescence microscopy. Antisense oligodeoxynucleotides were used for inducible nitric oxide synthase isoform (iNOS knockdown.Results - Body weight, fat mass, total cholesterol, low-density lipoprotein cholesterol fraction, insulin, and leptin were higher in the sedentary obese group (SD than in the sedentary control animals (SS. Exercise training prevented these changes. No difference in glucose tolerance, insulin sensitivity, blood pressure, and heart rate was found. Decreased vascular relaxation and reduced endothelial nitric oxide synthase (eNOS functioning in the SD group were prevented by exercise. Contractile response to phenylephrine was decreased in the aortas of the wild SD mice, compared with that of the SS group; however, no alteration was noted in the SD iNOS-/- animals. The decreased contractility was endothelium-dependent, and was reverted by iNOS inhibition or iNOS silencing. The aortas from the SD group showed increased basal NO production, serum TNFα, TNF receptor-1, and phospho-IκB. Exercise training attenuated iNOS-dependent reduction in contractile response in high-sugar diet

  17. Zinc regulates iNOS-derived nitric oxide formation in endothelial cells

    Science.gov (United States)

    Cortese-Krott, Miriam M.; Kulakov, Larissa; Opländer, Christian; Kolb-Bachofen, Victoria; Kröncke, Klaus-D.; Suschek, Christoph V.

    2014-01-01

    Aberrant production of nitric oxide (NO) by inducible NO synthase (iNOS) has been implicated in the pathogenesis of endothelial dysfunction and vascular disease. Mechanisms responsible for the fine-tuning of iNOS activity in inflammation are still not fully understood. Zinc is an important structural element of NOS enzymes and is known to inhibit its catalytical activity. In this study we aimed to investigate the effects of zinc on iNOS activity and expression in endothelial cells. We found that zinc down-regulated the expression of iNOS (mRNA+protein) and decreased cytokine-mediated activation of the iNOS promoter. Zinc-mediated regulation of iNOS expression was due to inhibition of NF-κB transactivation activity, as determined by a decrease in both NF-κB-driven luciferase reporter activity and expression of NF-κB target genes, including cyclooxygenase 2 and IL-1β. However, zinc did not affect NF-κB translocation into the nucleus, as assessed by Western blot analysis of nuclear and cytoplasmic fractions. Taken together our results demonstrate that zinc limits iNOS-derived high output NO production in endothelial cells by inhibiting NF-κB-dependent iNOS expression, pointing to a role of zinc as a regulator of iNOS activity in inflammation. PMID:25180171

  18. High BMI levels associate with reduced mRNA expression of IL10 and increased mRNA expression of iNOS (NOS2) in human frontal cortex

    DEFF Research Database (Denmark)

    Lauridsen, J K; Olesen, R H; Vendelbo, J

    2017-01-01

    analysis was performed with BMI as variable on data on IL10, IL1β, IL6, PTGS2 (COX2) and NOS2 (iNOS). Increasing BMI is associated with a decrease in the mRNA expression of IL10 (P=0.014) and an increase in the expression of NOS2 (iNOS; P=0.040). Expressions of IL10 and NOS2 (iNOS) were negatively...... correlated (PIL10 was mostly affected by individuals with BMI ⩾40. Multiple linear regression analyses with BMI, age, sex and race as variables were performed in order to identify potential confounders. In conclusion, increasing BMI could affect the IL10-mediated anti...

  19. Zinc regulates iNOS-derived nitric oxide formation in endothelial cells

    Directory of Open Access Journals (Sweden)

    Miriam M. Cortese-Krott

    2014-01-01

    Full Text Available Aberrant production of nitric oxide (NO by inducible NO synthase (iNOS has been implicated in the pathogenesis of endothelial dysfunction and vascular disease. Mechanisms responsible for the fine-tuning of iNOS activity in inflammation are still not fully understood. Zinc is an important structural element of NOS enzymes and is known to inhibit its catalytical activity. In this study we aimed to investigate the effects of zinc on iNOS activity and expression in endothelial cells. We found that zinc down-regulated the expression of iNOS (mRNA+protein and decreased cytokine-mediated activation of the iNOS promoter. Zinc-mediated regulation of iNOS expression was due to inhibition of NF-κB transactivation activity, as determined by a decrease in both NF-κB-driven luciferase reporter activity and expression of NF-κB target genes, including cyclooxygenase 2 and IL-1β. However, zinc did not affect NF-κB translocation into the nucleus, as assessed by Western blot analysis of nuclear and cytoplasmic fractions. Taken together our results demonstrate that zinc limits iNOS-derived high output NO production in endothelial cells by inhibiting NF-κB-dependent iNOS expression, pointing to a role of zinc as a regulator of iNOS activity in inflammation.

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

    International Nuclear Information System (INIS)

    1976-02-01

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

  1. Safety Evaluation Report related to the operation of Palo Verde Nuclear Generating Station, Units 1, 2, and 3 (Docket Nos. STN 50-528, STN 50-529, and STN 50-530). Supplement No. 8

    International Nuclear Information System (INIS)

    1985-05-01

    Purpose of this supplement is to update the Safety Evaluation Report by providing an evaluation of additional information submitted by the applicant since Supplement No. 7 was issued and matters that the staff had under review when Supplement No. 7 was issued, specifically those issues which required resolution prior to plant operation of Unit 1 above 5% full power

  2. Melanoma NOS1 expression promotes dysfunctional IFN signaling.

    Science.gov (United States)

    Liu, Qiuzhen; Tomei, Sara; Ascierto, Maria Libera; De Giorgi, Valeria; Bedognetti, Davide; Dai, Cuilian; Uccellini, Lorenzo; Spivey, Tara; Pos, Zoltan; Thomas, Jaime; Reinboth, Jennifer; Murtas, Daniela; Zhang, Qianbing; Chouchane, Lotfi; Weiss, Geoffrey R; Slingluff, Craig L; Lee, Peter P; Rosenberg, Steven A; Alter, Harvey; Yao, Kaitai; Wang, Ena; Marincola, Francesco M

    2014-05-01

    In multiple forms of cancer, constitutive activation of type I IFN signaling is a critical consequence of immune surveillance against cancer; however, PBMCs isolated from cancer patients exhibit depressed STAT1 phosphorylation in response to IFN-α, suggesting IFN signaling dysfunction. Here, we demonstrated in a coculture system that melanoma cells differentially impairs the IFN-α response in PBMCs and that the inhibitory potential of a particular melanoma cell correlates with NOS1 expression. Comparison of gene transcription and array comparative genomic hybridization (aCGH) between melanoma cells from different patients indicated that suppression of IFN-α signaling correlates with an amplification of the NOS1 locus within segment 12q22-24. Evaluation of NOS1 levels in melanomas and IFN responsiveness of purified PBMCs from patients indicated a negative correlation between NOS1 expression in melanomas and the responsiveness of PBMCs to IFN-α. Furthermore, in an explorative study, NOS1 expression in melanoma metastases was negatively associated with patient response to adoptive T cell therapy. This study provides a link between cancer cell phenotype and IFN signal dysfunction in circulating immune cells.

  3. Expression of beta-catenin, COX-2 and iNOS in colorectal cancer: relevance of COX-2 adn iNOS inhibitors for treatment in Malaysia.

    Science.gov (United States)

    Hong, Seok Kwan; Gul, Yunus A; Ithnin, Hairuszah; Talib, Arni; Seow, Heng Fong

    2004-01-01

    Promising new pharmacological agents and gene therapy targeting cyclooxygenase-2 (COX-2) and inducible nitric oxide synthase (iNOS) could modulate treatment of colorectal cancer in the future. The aim of this study was to elucidate the expression fo beta-catenin and teh presence of COX-2 and iNOS in colorectal cancer specimens in Malaysia. This is a useful prelude to future studies investigating interventions directed towards COX-2 adn iNOS. A cross-section study using retrospective data over a 2-year period (1999-2000) involved 101 archival, formalin-fixed, paraffin-embedded tissue samples of colorectal cancers that were surgically resected in a tertiary referral. COX-2 production was detected in adjacent normal tissue in 34 sample (33.7%) and in tumour tissue in 60 samples (59.4%). More tumours expressed iNOS (82/101, 81.2%) than COX-2. No iNOS expression was detected in adjacent normal tissue. Intense beta-catenin immunoreactivity at the cell-to-cell border. Poorly differentiated tumours had significantly lower total beta-catenin (p = 0.009) and COX-2 scores (p = 0.031). No significant relationships were established between pathological stage and beta-catenin, COX-2 and iNOS scores. the accumulation of beta-catenin does not seem to be sufficient to activate pathways that lead to increased COX-2 and iNOS expression. A high proportion of colorectal cancers were found to express COX-2 and a significant number produced iNOS, suggesting that their inhibitors may be potentially useful as chemotherapeutic agents in the management of colorectal cancer.

  4. Draft Environmental Statement related to the operation of Seabrook Station, Units 1 and 2. Docket Nos. 50-443 and 50-444, Public Service Company of New Hampshire, et al

    International Nuclear Information System (INIS)

    1982-05-01

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

  5. 21 CFR 10.20 - Submission of documents to Division of Dockets Management; computation of time; availability for...

    Science.gov (United States)

    2010-04-01

    ... Management; computation of time; availability for public disclosure. 10.20 Section 10.20 Food and Drugs FOOD... Management; computation of time; availability for public disclosure. (a) A submission to the Division of Dockets Management of a petition, comment, objection, notice, compilation of information, or any other...

  6. High BMI levels associate with reduced mRNA expression of IL10 and increased mRNA expression of iNOS (NOS2) in human frontal cortex

    DEFF Research Database (Denmark)

    Lauridsen, J K; Olesen, R H; Vendelbo, J

    2017-01-01

    unknown. Therefore we aim to examine the relationship between BMI and gene expression of central inflammatory markers in the human frontal cortex. Microarray data of 141 neurologically and psychiatrically healthy individuals were obtained through the BrainCloud database. A simple linear regression...... correlated (Plinear regression analyses with BMI, age, sex and race as variables were performed in order to identify potential confounders. In conclusion, increasing BMI could affect the IL10-mediated anti...... analysis was performed with BMI as variable on data on IL10, IL1β, IL6, PTGS2 (COX2) and NOS2 (iNOS). Increasing BMI is associated with a decrease in the mRNA expression of IL10 (P=0.014) and an increase in the expression of NOS2 (iNOS; P=0.040). Expressions of IL10 and NOS2 (iNOS) were negatively...

  7. Effects of cyclooxygenase inhibitor pretreatment on nitric oxide production, nNOS and iNOS expression in rat cerebellum.

    Science.gov (United States)

    Di Girolamo, G; Farina, M; Riberio, M L; Ogando, D; Aisemberg, J; de los Santos, A R; Martí, M L; Franchi, A M

    2003-07-01

    1. The therapeutic effect of nonsteroidal anti-inflammatory drugs (NSAIDs) is thought to be due mainly to its inhibition of cyclooxygenase (COX) enzymes, but there is a growing body of research that now demonstrates a variety of NSAIDs effects on cellular signal transduction pathways other than those involving prostaglandins. 2. Nitric oxide (NO) as a free radical and an agent that gives rise to highly toxic oxidants (peroxynitrile, nitric dioxide, nitron ion), becomes a cause of neuronal damage and death in some brain lesions such as Parkinson and Alzheimer disease, and Huntington's chorea. 3. In the present study, the in vivo effect of three NSAIDs (lysine clonixinate (LC), indomethacine (INDO) and meloxicam (MELO)) on NO production and nitric oxide synthase expression in rat cerebellar slices was analysed. Rats were treated with (a) saline, (b) lipopolysaccharide (LPS) (5 mg kg(-1), i.p.), (c) saline in combination with different doses of NSAIDs and (d) LPS in combination with different doses of NSAIDs and then killed 6 h after treatment. 4. NO synthesis, evaluated by Bred and Snyder technique, was increased by LPS. This augmentation was inhibited by coadministration of the three NSAIDs assayed. None of the NSAIDs tested was able to modify control NO synthesis. 5. Expression of iNOS and neural NOS (nNOS) was detected by Western blotting in control and LPS-treated rats. LC and INDO, but not MELO, were able to inhibit the expression of these enzymes. 6. Therefore, reduction of iNOS and nNOS levels in cerebellum may explain, in part, the anti-inflammatory effect of these NSAIDs and may also have importance in the prevention of NO-mediated neuronal injury.

  8. 14 CFR 406.113 - Filing documents with the Docket Management System (DMS) and sending documents to the...

    Science.gov (United States)

    2010-01-01

    ... 14 Aeronautics and Space 4 2010-01-01 2010-01-01 false Filing documents with the Docket Management System (DMS) and sending documents to the administrative law judge and Assistant Chief Counsel for... Management System (DMS) and sending documents to the administrative law judge and Assistant Chief Counsel for...

  9. The protein inhibitor of nNOS (PIN/DLC1/LC8) binding does not inhibit the NADPH-dependent heme reduction in nNOS, a key step in NO synthesis

    International Nuclear Information System (INIS)

    Parhad, Swapnil S.; Jaiswal, Deepa; Ray, Krishanu; Mazumdar, Shyamalava

    2016-01-01

    The neuronal nitric oxide synthase (nNOS) is an essential enzyme involved in the synthesis of nitric oxide (NO), a potent neurotransmitter. Although previous studies have indicated that the dynein light chain 1 (DLC1) binding to nNOS could inhibit the NO synthesis, the claim is challenged by contradicting reports. Thus, the mechanism of nNOS regulation remained unclear. nNOS has a heme-bearing, Cytochrome P450 core, and the functional enzyme is a dimer. The electron flow from NADPH to Flavin, and finally to the heme of the paired nNOS subunit within a dimer, is facilitated upon calmodulin (CaM) binding. Here, we show that DLC1 binding to nNOS-CaM complex does not affect the electron transport from the reductase to the oxygenase domain. Therefore, it cannot inhibit the rate of NADPH-dependent heme reduction in nNOS, which results in L-Arginine oxidation. Also, the NO release activity does not decrease with increasing DLC1 concentration in the reaction mix, which further confirmed that DLC1 does not inhibit nNOS activity. These findings suggest that the DLC1 binding may have other implications for the nNOS function in the cell. - Highlights: • The effect of interaction of nNOS with DLC1 has been debatable with contradicting reports in literature. • Purified DLC1 has no effect on electron transport between reductase and oxygenase domain of purified nNOS-CaM. • The NO release activity of nNOS was not altered by DLC1, supporting that DLC1 does not inhibit the enzyme. • These findings suggest that the DLC1 binding may have other implications for the nNOS function in the cell.

  10. The protein inhibitor of nNOS (PIN/DLC1/LC8) binding does not inhibit the NADPH-dependent heme reduction in nNOS, a key step in NO synthesis

    Energy Technology Data Exchange (ETDEWEB)

    Parhad, Swapnil S. [Tata Institute of Fundamental Research (TIFR), Homi Bhabha Road, Mumbai 400 005 (India); Jaiswal, Deepa [Tata Institute of Fundamental Research (TIFR), Homi Bhabha Road, Mumbai 400 005 (India); TIFR Centre for Interdisciplinary Sciences, 21 Brundavan Colony, Narsingi, Hyderabad 500075 (India); Ray, Krishanu, E-mail: krishanu@tifr.res.in [Tata Institute of Fundamental Research (TIFR), Homi Bhabha Road, Mumbai 400 005 (India); Mazumdar, Shyamalava, E-mail: shyamal@tifr.res.in [Tata Institute of Fundamental Research (TIFR), Homi Bhabha Road, Mumbai 400 005 (India)

    2016-03-25

    The neuronal nitric oxide synthase (nNOS) is an essential enzyme involved in the synthesis of nitric oxide (NO), a potent neurotransmitter. Although previous studies have indicated that the dynein light chain 1 (DLC1) binding to nNOS could inhibit the NO synthesis, the claim is challenged by contradicting reports. Thus, the mechanism of nNOS regulation remained unclear. nNOS has a heme-bearing, Cytochrome P450 core, and the functional enzyme is a dimer. The electron flow from NADPH to Flavin, and finally to the heme of the paired nNOS subunit within a dimer, is facilitated upon calmodulin (CaM) binding. Here, we show that DLC1 binding to nNOS-CaM complex does not affect the electron transport from the reductase to the oxygenase domain. Therefore, it cannot inhibit the rate of NADPH-dependent heme reduction in nNOS, which results in L-Arginine oxidation. Also, the NO release activity does not decrease with increasing DLC1 concentration in the reaction mix, which further confirmed that DLC1 does not inhibit nNOS activity. These findings suggest that the DLC1 binding may have other implications for the nNOS function in the cell. - Highlights: • The effect of interaction of nNOS with DLC1 has been debatable with contradicting reports in literature. • Purified DLC1 has no effect on electron transport between reductase and oxygenase domain of purified nNOS-CaM. • The NO release activity of nNOS was not altered by DLC1, supporting that DLC1 does not inhibit the enzyme. • These findings suggest that the DLC1 binding may have other implications for the nNOS function in the cell.

  11. iNOS inhibits hair regeneration in obese diabetic (ob/ob) mice.

    Science.gov (United States)

    Sasaki, Mari; Shinozaki, Shohei; Morinaga, Hironobu; Kaneki, Masao; Nishimura, Emi; Shimokado, Kentaro

    2018-07-02

    Previous studies have shown that androgenic alopecia is associated with metabolic syndrome and diabetes. However, the detailed mechanism whereby diabetes causes alopecia still remains unclear. We focused on the inflammatory response that is caused by diabetes or obesity, given that inflammation is a risk factor for hair loss. Inducible nitric oxide synthase (iNOS) is known to be upregulated under conditions of acute or chronic inflammation. To clarify the potential role of iNOS in diabetes-related alopecia, we generated obese diabetic iNOS-deficient (ob/ob; iNOS-KO mice). We observed that ob/ob; iNOS-KO mice were potentiated for the transition from telogen (rest phase) to anagen (growth phase) in the hair cycle compared with iNOS-proficient ob/ob mice. To determine the effect of nitric oxide (NO) on the hair cycle, we administered an iNOS inhibitor intraperitoneally (compound 1400 W, 10 mg/kg) or topically (10% aminoguanidine) in ob/ob mice. We observed that iNOS inhibitors promoted anagen transition in ob/ob mice. Next, we administered an NO donor (S-nitrosoglutathione, GSNO), to test whether NO has the telogen elongation effects. The NO donor was sufficient to induce telogen elongation in wild-type mice. Together, our data indicate that iNOS-derived NO plays a role in telogen elongation under the inflammatory conditions associated with diabetes in mice. Copyright © 2018 The Authors. Published by Elsevier Inc. All rights reserved.

  12. Ultrasonic examination of the PVRC plates Nos. 50/52, 51/53 and 204

    International Nuclear Information System (INIS)

    1979-01-01

    The imposed procedure for the ultrasonic examination of the three PVRC plates given to Europe is based on the ASME Boiler and Pressure Vessel Code, Section XI as it applies to a vessel in service and accessible from the outer surface only. This procedure is referred to as the PISC procedure. After one year of use it was modified and remained, until the end of the exercise, characterized by a 50% DAC cut-off. The three plates (50/52, 51/53 and 204) were examined following this procedure by several teams. Results were furnished: - as raw data given by the instrumentation, - as data interpreted by the team. Inspection teams also were allowed to use other procedures which in the report are called alternative procedures. The results of the examination by teams using alternative procedures were given as interpreted data by the team. Those data were corrected and arranged in a data bank on tape and on cards. Full drawings of the teams findings were also produced by the computer for easy understanding and verification of the data. Besides many defects in the welded zones, relevant base-material defects were declared by the teams

  13. Neuronal NOS inhibitor 1-(2-trifluoromethylphenyl)-imidazole augment the effects of antidepressants acting via serotonergic system in the forced swimming test in rats.

    Science.gov (United States)

    Ulak, Güner; Mutlu, Oguz; Akar, Füruzan Yildiz; Komsuoğlu, F Ipek; Tanyeri, Pelin; Erden, B Faruk

    2008-10-01

    Treatment-resistant depression has necessitated new therapeutic strategies in augmenting the therapeutic actions of currently existing antidepressant drugs. The aim of this study was to investigate the possibility of synergistic interaction between 1-(2-trifluoromethylphenyl)-imidazole (TRIM), a novel neuronal nitric oxide synthase (nNOS) inhibitor and conventional antidepressants of different classes in the forced swimming test (FST) in rats. TRIM decreased the immobility time at 50 mg/kg doses in the FST in rats. Treatment with a behaviourally subeffective dose of TRIM (20 mg/kg) augmented the behavioural effect of tricyclic antidepressant imipramine, selective serotonin re-uptake inhibitor (SSRI) citalopram and fluoxetine or selective serotonin reuptake enhancer tianeptine but failed to augment the antidepressant effect of reboxetine, a noradrenaline re-uptake inhibitor, in this test. Therefore inhibition of NOS augments the effects of antidepressants acting on serotonergic system in the FST. Neither TRIM (10-50 mg/kg) nor other drug treatments affected the locomotor activity of animals. These findings are in agreement with the view that antidepressant effects or augmentation of these effects in the FST may be explained with inhibition of NOS activity and this may be a new approach in offering greater therapeutic efficacy of antidepressants acting via serotonergic system.

  14. Intoxicação aguda com sementes de Crotalaria spectabilis (Leg. Papilionoideae em suínos

    Directory of Open Access Journals (Sweden)

    D.G. Ubiali

    2011-04-01

    Full Text Available Relata-se necrose hepatocelular em suínos após consumo de ração que continha grãos de sorgo-granífero (Sorghum bicolor acidentalmente contaminado com sementes de Crotalaria spectabilis. Morreram 76 suínos em quatro propriedades no município de Juscimeira, MT. Os sinais clínicos iniciaram-se 24-48 horas após o consumo da ração contaminada e foram caracterizados por depressão, letargia, apatia, inapetência, vômito, mucosas ictéricas ou pálidas, ascite, decúbito esternal, decúbito lateral com movimentos de pedalagem e convulsões, a evolução clínica foi de 48-60 horas seguida de morte. As Principais alterações macroscópicas foram fígado aumentado de tamanho com evidenciação do padrão lobular, ascite e hidrotórax com líquido de coloração amarelo avermelhado contendo filamentos com aspecto de fibrina, linfonodos aumentados e edema pulmonar interlobular. A doença foi reproduzida utilizando-se 16 suínos divididos em seis grupos que receberam sementes de C. spectabilis em diferentes doses. Necrose hepatocelular ocorreu em sete suínos, sendo dois que receberam doses diárias 2,5g/kg e cinco que receberam doses únicas de 5,0 e 9,5g/kg. Dez doses diárias de 0,5 e 1,25g/kg causaram fibrose hepática.

  15. Inhibitory Effect of Inflexinol on Nitric Oxide Generation and iNOS Expression via Inhibition of NF-κB Activation

    Directory of Open Access Journals (Sweden)

    Jae Woong Lee

    2007-01-01

    Full Text Available Inflexinol, an ent-kaurane diterpenoid, was isolated from the leaves of Isodon excisus. Many diterpenoids isolated from the genus Isodon (Labiatae have antitumor and antiinflammatory activities. We investigated the antiinflammatory effect of inflexinol in RAW 264.7 cells and astrocytes. As a result, we found that inflexinol (1, 5, 10 μM suppressed the expression of inducible nitric oxide synthase (iNOS and cyclooxygenase-2 (COX-2 as well as the production of nitric oxide (NO in LPS-stimulated RAW 264.7 cells and astrocytes. Consistent with the inhibitory effect on iNOS and COX-2 expression, inflexinol also inhibited transcriptional and DNA binding activity of NF-κB via inhibition of IκB degradation as well as p50 and p65 translocation into nucleus. These results suggest that inflexinol inhibits iNOS and COX-2 expression through inhibition of NF-κB activation, thereby inhibits generation of inflammatory mediators in RAW 264.7 cells and astrocytes, and may be useful for treatment of inflammatory diseases.

  16. The protein inhibitor of nNOS (PIN/DLC1/LC8) binding does not inhibit the NADPH-dependent heme reduction in nNOS, a key step in NO synthesis.

    Science.gov (United States)

    Parhad, Swapnil S; Jaiswal, Deepa; Ray, Krishanu; Mazumdar, Shyamalava

    2016-03-25

    The neuronal nitric oxide synthase (nNOS) is an essential enzyme involved in the synthesis of nitric oxide (NO), a potent neurotransmitter. Although previous studies have indicated that the dynein light chain 1 (DLC1) binding to nNOS could inhibit the NO synthesis, the claim is challenged by contradicting reports. Thus, the mechanism of nNOS regulation remained unclear. nNOS has a heme-bearing, Cytochrome P450 core, and the functional enzyme is a dimer. The electron flow from NADPH to Flavin, and finally to the heme of the paired nNOS subunit within a dimer, is facilitated upon calmodulin (CaM) binding. Here, we show that DLC1 binding to nNOS-CaM complex does not affect the electron transport from the reductase to the oxygenase domain. Therefore, it cannot inhibit the rate of NADPH-dependent heme reduction in nNOS, which results in l-Arginine oxidation. Also, the NO release activity does not decrease with increasing DLC1 concentration in the reaction mix, which further confirmed that DLC1 does not inhibit nNOS activity. These findings suggest that the DLC1 binding may have other implications for the nNOS function in the cell. Copyright © 2016 Elsevier Inc. All rights reserved.

  17. Endogenous angiotensin II modulates nNOS expression in renovascular hypertension

    Directory of Open Access Journals (Sweden)

    T.M.C. Pereira

    2009-07-01

    Full Text Available Nitric oxide (NO influences renal blood flow mainly as a result of neuronal nitric oxide synthase (nNOS. Nevertheless, it is unclear how nNOS expression is modulated by endogenous angiotensin II, an inhibitor of NO function. We tested the hypothesis that the angiotensin II AT1 receptor and oxidative stress mediated by NADPH oxidase contribute to the modulation of renal nNOS expression in two-kidney, one-clip (2K1C hypertensive rats. Experiments were performed on male Wistar rats (150 to 170 g body weight divided into 2K1C (N = 19 and sham-operated (N = 19 groups. nNOS expression in kidneys of 2K1C hypertensive rats (N = 9 was compared by Western blotting to that of 2K1C rats treated with low doses of the AT1 antagonist losartan (10 mg·kg-1·day-1; N = 5 or the superoxide scavenger tempol (0.2 mmol·kg-1·day-1; N = 5, which still remain hypertensive. After 28 days, nNOS expression was significantly increased by 1.7-fold in the clipped kidneys of 2K1C rats and by 3-fold in the non-clipped kidneys of 2K1C rats compared with sham rats, but was normalized by losartan. With tempol treatment, nNOS expression increased 2-fold in the clipped kidneys and 1.4-fold in the non-clipped kidneys compared with sham rats. The changes in nNOS expression were not followed by changes in the enzyme activity, as measured indirectly by the cGMP method. In conclusion, AT1 receptors and oxidative stress seem to be primary stimuli for increased nNOS expression, but this up-regulation does not result in higher enzyme activity.

  18. Asiatic Acid Alleviates Hemodynamic and Metabolic Alterations via Restoring eNOS/iNOS Expression, Oxidative Stress, and Inflammation in Diet-Induced Metabolic Syndrome Rats

    Directory of Open Access Journals (Sweden)

    Poungrat Pakdeechote

    2014-01-01

    Full Text Available Asiatic acid is a triterpenoid isolated from Centella asiatica. The present study aimed to investigate whether asiatic acid could lessen the metabolic, cardiovascular complications in rats with metabolic syndrome (MS induced by a high-carbohydrate, high-fat (HCHF diet. Male Sprague-Dawley rats were fed with HCHF diet with 15% fructose in drinking water for 12 weeks to induce MS. MS rats were treated with asiatic acid (10 or 20 mg/kg/day or vehicle for a further three weeks. MS rats had an impairment of oral glucose tolerance, increases in fasting blood glucose, serum insulin, total cholesterol, triglycerides, mean arterial blood pressure, heart rate, and hindlimb vascular resistance; these were related to the augmentation of vascular superoxide anion production, plasma malondialdehyde and tumor necrosis factor-alpha (TNF-α levels (p < 0.05. Plasma nitrate and nitrite (NOx were markedly high with upregulation of inducible nitric oxide synthase (iNOS expression, but dowregulation of endothelial nitric oxide synthase (eNOS expression (p < 0.05. Asiatic acid significantly improved insulin sensitivity, lipid profiles, hemodynamic parameters, oxidative stress markers, plasma TNF-α, NOx, and recovered abnormality of eNOS/iNOS expressions in MS rats (p < 0.05. In conclusion, asiatic acid improved metabolic, hemodynamic abnormalities in MS rats that could be associated with its antioxidant, anti-inflammatory effects and recovering regulation of eNOS/iNOS expression.

  19. ¿Las emociones nos distraen?

    Directory of Open Access Journals (Sweden)

    Antonia Pilar Pacheco-Unguetti

    2014-06-01

    Full Text Available ¿Leerás este artículo hasta el final sin interrupciones? Puede que, mientras lo intentas, recibas algún mensaje de whatsapp, se abra una ventana emergente en tu ordenador con una oferta de viajes al Caribe o el cartero llame dos veces a tu puerta. También puede ser que simplemente no tengas un buen día y te resulte especialmente difícil concentrarte. Vivimos expuestos a multitud de estímulos distractores externos, algunos tan inesperados o extraños que entorpecen irremediablemente nuestra concentración en una tarea (distracción por novedad. Pero la distracción también puede tener una causa interna y cómo nos sentimos puede influir en cuánto nos distraemos.

  20. Safety evaluation report related to the operation of San Onofre Nuclear Generating Station, Units 2 and 3. Docket Nos. 50-361 and 50-362, Southern California Edison Company, et al

    International Nuclear Information System (INIS)

    1982-06-01

    Information is presented concerning seismic design of structures, components, and equipment; reactor coolant system; conduct of operations; initial test program; quality assurance; and Three Mile Island-2 requirements

  1. Contribution of the nos-pdt operon to virulence phenotypes in methicillin-sensitive Staphylococcus aureus.

    Directory of Open Access Journals (Sweden)

    April M Sapp

    Full Text Available Nitric oxide (NO is emerging as an important regulator of bacterial stress resistance, biofilm development, and virulence. One potential source of endogenous NO production in the pathogen Staphylococcus aureus is its NO-synthase (saNOS enzyme, encoded by the nos gene. Although a role for saNOS in oxidative stress resistance, antibiotic resistance, and virulence has been recently-described, insights into the regulation of nos expression and saNOS enzyme activity remain elusive. To this end, transcriptional analysis of the nos gene in S. aureus strain UAMS-1 was performed, which revealed that nos expression increases during low-oxygen growth and is growth-phase dependent. Furthermore, nos is co-transcribed with a downstream gene, designated pdt, which encodes a prephenate dehydratase (PDT enzyme involved in phenylalanine biosynthesis. Deletion of pdt significantly impaired the ability of UAMS-1 to grow in chemically-defined media lacking phenylalanine, confirming the function of this enzyme. Bioinformatics analysis revealed that the operon organization of nos-pdt appears to be unique to the staphylococci. As described for other S. aureus nos mutants, inactivation of nos in UAMS-1 conferred sensitivity to oxidative stress, while deletion of pdt did not affect this phenotype. The nos mutant also displayed reduced virulence in a murine sepsis infection model, and increased carotenoid pigmentation when cultured on agar plates, both previously-undescribed nos mutant phenotypes. Utilizing the fluorescent stain 4-Amino-5-Methylamino-2',7'-Difluorofluorescein (DAF-FM diacetate, decreased levels of intracellular NO/reactive nitrogen species (RNS were detected in the nos mutant on agar plates. These results reinforce the important role of saNOS in S. aureus physiology and virulence, and have identified an in vitro growth condition under which saNOS activity appears to be upregulated. However, the significance of the operon organization of nos-pdt and

  2. Expression profiles of eNOS, iNOS and microRNA-27b in the corpus cavernosum of rats submitted to chronic alcoholism and Diabetes mellitus.

    Science.gov (United States)

    Cunha, Joao Paulo da; Lizarte, Fermino Sanches; Novais, Paulo Cezar; Gattas, Daniela; Carvalho, Camila Albuquerque Mello de; Tirapelli, Daniela Pretti da Cunha; Molina, Carlos Augusto Fernandes; Tirapelli, Luis Fernando; Tucci, Silvio

    2017-01-01

    To evaluate the expression of endothelial and inducible NOS in addition to the miRNA-27b in the corpus cavernosum and peripheral blood of healthy rats, diabetic rats, alcoholic rats and rats with both pathologies. Forty eight Wistar rats were divided into four groups: control (C), alcoholic (A), diabetic (D) and alcoholic-diabetic (AD). Samples of the corpus cavernosum were prepared to study protein expressions of eNOS and iNOS by immunohistochemistry and expression of miRNA-27b in the corpus cavernosum and peripheral blood. Immunohistochemistry for eNOS and iNOS showed an increase in cavernosal smooth muscle cells in the alcoholic, diabetic and alcoholic-diabetic groups when compared with the control group. Similarly, the mRNA levels for eNOS were increased in cavernosal smooth muscle (CSM) in the alcoholic, diabetic and alcoholic-diabetic groups and miRNA-27b were decreased in CSM in the alcoholic, diabetic and alcoholic-diabetic groups. The major new finding of our study was an impairment of relaxation of cavernosal smooth muscle in alcoholic, diabetic, and alcoholic-diabetic rats that involved a decrease in the nitric oxide pathway by endothelium-dependent mechanisms accompanied by a change in the corpus cavernosum contractile sensitivity.

  3. Marketing plan NOS: introducing pay per view

    OpenAIRE

    Pereira, Pedro Azeredo

    2016-01-01

    NOS, NOS Comunicações S.A., is a private telecommunications company of the portuguese market which is proud of being the “best communications and entertainment company in the market”. The company was born from a fusion between two of the biggest communications corporations in the country: on the fixed service (TV, fixed phone, fixed internet, etc.) from ZON; and on the mobile service (mobile phone, internet, etc.) from Optimus. It is a leader in all the sectors it operates. Bes...

  4. Changes of serum NO/iNOS after whole abdominal irradiation in rats

    International Nuclear Information System (INIS)

    Lin Hong; Wu Wei; Zhang Kunhe; Chen Jiang; Wang Yang; Luo Hui; Huang Xiaoqing

    2004-01-01

    Objective: To observe the changes of serum NO/NOS concentrations in rats after whole abdominal irradiation and their relationships with intestinal radiation injury. Methods: Thirty health rats were randomly divided into three groups: normal control group, irradiation control group, and IgY protection group. The sera of rats were collected and the NO and iNOS were assayed. Results: NO and iNOS levels increased evidently in the irradiation control group in contrast with those of the normal control group (P<0.01). NO and iNOS levels increased slightly in the IgY protection group in contrast with the irradiation control group (P<0.01) and were close to the levels of the normal control group. The changes of NO and NOS concentrations were synchronous. Conclusion: NO and iNOS are good indices for detecting intestinal radiation injury. (authors)

  5. NOAA NOS SOS, EXPERIMENTAL - Currents

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — The NOAA NOS SOS server is part of the IOOS DIF SOS Project. The stations in this dataset have currents data. *These services are for testing and evaluation use...

  6. NOAA NOS SOS, EXPERIMENTAL - Wind

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — The NOAA NOS SOS server is part of the IOOS DIF SOS Project. The stations in this dataset have wind data. *These services are for testing and evaluation use only*...

  7. Outcome following inhalation anesthesia in birds at a veterinary referral hospital: 352 cases (2004-2014).

    Science.gov (United States)

    Seamon, Amanda B; Hofmeister, Erik H; Divers, Stephen J

    2017-10-01

    OBJECTIVE To determine the outcome in birds undergoing inhalation anesthesia and identify patient or procedure variables associated with an increased likelihood of anesthesia-related death. DESIGN Retrospective case series. ANIMALS 352 birds that underwent inhalation anesthesia. PROCEDURES Medical records of birds that underwent inhalation anesthesia from January 1, 2004, through December 31, 2014, at a single veterinary referral hospital were reviewed. Data collected included date of visit, age, species, sex, type (pet, free ranging, or wild kept in captivity), body weight, body condition score, diagnosis, procedure, American Society of Anesthesiologists status, premedication used for anesthesia, drug for anesthetic induction, type of maintenance anesthesia, route and type of fluid administration, volumes of crystalloid and colloid fluids administered, intraoperative events, estimated blood loss, duration of anesthesia, surgery duration, recovery time, recovery notes, whether birds survived to hospital discharge, time of death, total cost of hospitalization, cost of anesthesia, and nadir and peak values for heart rate, end-tidal partial pressure of carbon dioxide, concentration of inhaled anesthetic, and body temperature. Comparisons were made between birds that did and did not survive to hospital discharge. RESULTS Of 352 birds, 303 (86%) were alive at hospital discharge, 12 (3.4%) died during anesthesia, 15 (4.3%) died in the intensive care unit after anesthesia, and 22 (6.3%) were euthanatized after anesthesia. Overall, none of the variables studied were associated with survival to hospital discharge versus not surviving to hospital discharge. CONCLUSIONS AND CLINICAL RELEVANCE Results confirmed previous findings that indicated birds have a high mortality rate during and after anesthesia, compared with mortality rates published for dogs and cats.

  8. Geochemistry of the Bonin Fore-arc Volcanic Sequence: Results from IODP Expedition 352

    Science.gov (United States)

    Godard, M.; Ryan, J. G.; Shervais, J. W.; Whattam, S. A.; Sakuyama, T.; Kirchenbaur, M.; Li, H.; Nelson, W. R.; Prytulak, J.; Pearce, J. A.; Reagan, M. K.

    2015-12-01

    The Izu-Bonin-Mariana intraoceanic arc system, in the western Pacific, results from ~52 My of subduction of the Pacific plate beneath the eastern margin of the Philippine Sea plate. Four sites were drilled south of the Bonin Islands during IODP Expedition 352 and 1.22 km of igneous basement was cored upslope to the west of the trough. These stratigraphically controlled igneous suites allow study of the earliest stages of arc development from seafloor spreading to convergence. We present the preliminary results of a detailed major and trace element (ICPMS) study on 128 igneous rocks drilled during Expedition 352. Mainly basalts and basaltic andesites were recovered at the two deeper water sites (U1440 and U1441) and boninites at the two westernmost sites (U1439 and U1442). Sites U1440 and U1441 basaltic suites are trace element depleted (e.g. Yb 4-6 x PM); they have fractionated REE patterns (LREE/HREE = 0.2-0.4 x C1-chondrites) compared to mid-ocean ridge basalts. They have compositions overlapping that of previously sampled Fore-Arc Basalts (FAB) series. They are characterized also by an increase in LILE contents relative to neighboring elements up-section (e.g. Rb/La ranging from <1 to 3-7 x PM at Site U1440) suggesting a progressive contamination of their source by fluids. This process in turn may have favored melting and efficient melt extraction from the source and thus its extreme depletion. Boninites are depleted in moderately incompatible elements with a decrease in their contents up-section (e.g. Yb = ~6.2 to 2.8 x C1-chondrite at Site U1439). These changes in trace element contents are associated with the development of a positive Zr-Hf anomaly relative to neighboring elements and a strong increase in LILE (e.g., Zr/Sm=~1 to 2.6 x PM and Rb/La=1-2 to 10-18). The progressive upward depletion of boninitic lavas could reveal the incorporation of harzburgitic residues from FAB generation into their mantle source.

  9. 76 FR 9612 - GE Hitachi Nuclear Energy; Acceptance for Docketing of an Application for Renewal of the U.S...

    Science.gov (United States)

    2011-02-18

    ... NUCLEAR REGULATORY COMMISSION [Docket No. 52-045; NRC-2011-0020] GE Hitachi Nuclear Energy... Certification On December 7, 2010, GE Hitachi Nuclear Energy (GEH) submitted an application to the U.S. Nuclear... and Approvals for Nuclear Power Plants.'' A notice of receipt and availability of this application was...

  10. iNOS Activity Modulates Inflammation, Angiogenesis, and Tissue Fibrosis in Polyether-Polyurethane Synthetic Implants.

    Science.gov (United States)

    Cassini-Vieira, Puebla; Araújo, Fernanda Assis; da Costa Dias, Filipi Leles; Russo, Remo Castro; Andrade, Silvia Passos; Teixeira, Mauro Martins; Barcelos, Luciola Silva

    2015-01-01

    There is considerable interest in implantation techniques and scaffolds for tissue engineering and, for safety and biocompatibility reasons, inflammation, angiogenesis, and fibrosis need to be determined. The contribution of inducible nitric oxide synthase (iNOS) in the regulation of the foreign body reaction induced by subcutaneous implantation of a synthetic matrix was never investigated. Here, we examined the role of iNOS in angiogenesis, inflammation, and collagen deposition induced by polyether-polyurethane synthetic implants, using mice with targeted disruption of the iNOS gene (iNOS(-/-)) and wild-type (WT) mice. The hemoglobin content and number of vessels were decreased in the implants of iNOS(-/-) mice compared to WT mice 14 days after implantation. VEGF levels were also reduced in the implants of iNOS(-/-) mice. In contrast, the iNOS(-/-) implants exhibited an increased neutrophil and macrophage infiltration. However, no alterations were observed in levels of CXCL1 and CCL2, chemokines related to neutrophil and macrophage migration, respectively. Furthermore, the implants of iNOS(-/-) mice showed boosted collagen deposition. These data suggest that iNOS activity controls inflammation, angiogenesis, and fibrogenesis in polyether-polyurethane synthetic implants and that lack of iNOS expression increases foreign body reaction to implants in mice.

  11. Crataegus Special Extract WS 1442 Effects on eNOS and microRNA 155.

    Science.gov (United States)

    Wang, Xinwen; Liang, Yan; Shi, Jian; Zhu, Hao-Jie; Bleske, Barry E

    2018-04-16

    Increased expression of microRNA 155 (miR-155) results in a decrease in endothelial nitric oxide synthase (eNOS) expression and impaired endothelial function. Factors that have been shown to increase expression of miR-155 may be mitigated by WS 1442, an extract of hawthorn leaves and flowers ( Crataegus special extract) that contains a range of pharmacologically active substances including oligomeric proanthocyanidins and flavonoids. The purpose of this study is to determine the effect of WS 1442 on the expression of miR-155 and eNOS in the presence of tumor necrosis factor (TNF- α ). Human umbilical vein endothelial cells (HUVECs) were studied after the exposure to TNF- α , with or without simvastatin (positive control) and WS 1442. The expression levels of eNOS, phosphorylated eNOS, and miR-155 in the different HUVEC treatment groups were determined by western blot and quantitative real-time polymerase chain reaction, respectively. To evaluate the effect of WS 1442 on the eNOS activity, the medium and intracellular nitrate/nitrite (NO) concentrations were also analyzed using a colorimetric Griess assay kit. The results demonstrated that TNF- α upregulated miR-155 expression and decreased eNOS expression and NO concentrations. WS 1442 also increased miR-155 expression and decreased eNOS expression but, unlike TNF- α , increased phosphorylated eNOS expression and NO concentrations. Surprisingly, WS 1442 increased miR-155 expression; however, WS 1442 mitigated the overall negative effect of miR-155 on decreasing eNOS expression by increasing expression of phosphorylated eNOS and resulting in an increase in NO concentrations. In the setting where miR-155 may be expressed, WS 1442 may offer vascular protection by increasing the expression of phosphorylated eNOS. Georg Thieme Verlag KG Stuttgart · New York.

  12. eNOS-uncoupling in age-related erectile dysfunction

    OpenAIRE

    Johnson, JM; Bivalacqua, TJ; Lagoda, GA; Burnett, AL; Musicki, B

    2011-01-01

    Aging is associated with ED. Although age-related ED is attributed largely to increased oxidative stress and endothelial dysfunction in the penis, the molecular mechanisms underlying this effect are not fully defined. We evaluated whether endothelial nitric oxide synthase (eNOS) uncoupling in the aged rat penis is a contributing mechanism. Correlatively, we evaluated the effect of replacement with eNOS cofactor tetrahydrobiopterin (BH4) on erectile function in the aged rats. Male Fischer 344 ...

  13. Penser Système : Découvrir nos modèles d'organisation

    NARCIS (Netherlands)

    Bryan, B.; Goodman, M.; Schaveling, J.

    2011-01-01

    Pourquoi le travail s’accumule-t-il sur nos bureaux alors que nous travaillons de plus en plus? Parfois « nos solutions » aggravent nos problèmes. Comment pouvons-nous éviter ces paradoxes ? Penser système donne de nouvelles perspectives dans des situations complexes. Cela vous permettra de

  14. LEMS: application of the method to study the static quadrupole moment of the K=35/2 isomer in 179W

    International Nuclear Information System (INIS)

    Neyens, G.; Vyvey, K.; Byrne, A.P.; Dracoulis, G.D.; Blaha, P.

    1997-01-01

    The method of the level mixing spectroscopy (LEMS) was applied for the first time for the study of the static quadrupole moments of high-K isomers in the A∼180 mass region. Results from a preliminary experiment for the static quadrupole moment of the 35/2 - (750 ns) isomer in 179 W give a limit for its upper value Q 2 <0.343. (orig.). With 1 fig

  15. 76 FR 22880 - Notice of Commission Meeting and Public Hearing

    Science.gov (United States)

    2011-04-25

    ... applicant's cement manufacturing plant from existing Wells Nos. 1 and 2 and an existing surface water intake... manufacturing facility. The previous DRBC approval--Docket No. D-1999-038-2 issued on May 10, 2007--expired on...

  16. X-RAYS FROM A RADIO-LOUD COMPACT BROAD ABSORPTION LINE QUASAR 1045+352 AND THE NATURE OF OUTFLOWS IN RADIO-LOUD BROAD ABSORPTION LINE QUASARS

    International Nuclear Information System (INIS)

    Kunert-Bajraszewska, Magdalena; Katarzynski, Krzysztof; Siemiginowska, Aneta; Janiuk, Agnieszka

    2009-01-01

    We present new results on X-ray properties of radio-loud broad absorption line (BAL) quasars and focus on broadband spectral properties of a high-ionization BAL (HiBAL) compact steep spectrum (CSS) radio-loud quasar 1045+352. This HiBAL quasar has a very complex radio morphology indicating either strong interactions between a radio jet and the surrounding interstellar medium or a possible re-start of the jet activity. We detected 1045+352 quasar in a short 5 ksec Chandra ACIS-S observation. We applied theoretical models to explain spectral energy distribution of 1045+352 and argue that non-thermal, inverse-Compton (IC) emission from the innermost parts of the radio jet can account for a large fraction of the observed X-ray emission. In our analysis, we also consider a scenario in which the observed X-ray emission from radio-loud BAL quasars can be a sum of IC jet X-ray emission and optically thin corona X-ray emission. We compiled a sample of radio-loud BAL quasars that were observed in X-rays to date and report no correlation between their X-ray and radio luminosity. However, the radio-loud BAL quasars show a large range of X-ray luminosities and absorption columns. This is consistent with the results obtained earlier for radio-quiet BAL quasars and may indicate an orientation effect in BAL quasars or more complex dependence between X-ray emission, radio emission, and an orientation based on the radio morphology.

  17. The effect of high protein diet and exercise on irisin, eNOS, and iNOS expressions in kidney.

    Science.gov (United States)

    Tastekin, Ebru; Palabiyik, Orkide; Ulucam, Enis; Uzgur, Selda; Karaca, Aziz; Vardar, Selma Arzu; Yilmaz, Ali; Aydogdu, Nurettin

    2016-08-01

    Long-term effects of high protein diets (HPDs) on kidneys are still not sufficiently studied. Irisin which increases oxygen consumption and thermogenesis in white fat cells was shown in skeletal muscles and many tissues. Nitric oxide synthases (NOS) are a family of enzymes catalyzing the production of nitric oxide (NO) from L-arginine. We aimed to investigate the effects of HPD, irisin and NO expression in kidney and relation of them with exercise and among themselves. Animals were grouped as control, exercise, HPD and exercise combined with HPD (exercise-HPD). Rats were kept on a HPD for 5 weeks and an exercise program was given them as 5 exercise and 2 rest days per week exercising on a treadmill with increasing speed and angle. In our study, while HPD group had similar total antioxidant capacity (TAC) levels with control group, exercise and exercise-HPD groups had lower levels (p highly selective and quite clear in this study. Effects of exercise and HPD on kidney should be evaluated with different exercise protocols and contents of the diet. İrisin, eNOS, and iNOS staining localizations should be supported with various research studies.

  18. Phenotyping of nNOS neurons in the postnatal and adult female mouse hypothalamus.

    Science.gov (United States)

    Chachlaki, Konstantina; Malone, Samuel A; Qualls-Creekmore, Emily; Hrabovszky, Erik; Münzberg, Heike; Giacobini, Paolo; Ango, Fabrice; Prevot, Vincent

    2017-10-15

    Neurons expressing nitric oxide (NO) synthase (nNOS) and thus capable of synthesizing NO play major roles in many aspects of brain function. While the heterogeneity of nNOS-expressing neurons has been studied in various brain regions, their phenotype in the hypothalamus remains largely unknown. Here we examined the distribution of cells expressing nNOS in the postnatal and adult female mouse hypothalamus using immunohistochemistry. In both adults and neonates, nNOS was largely restricted to regions of the hypothalamus involved in the control of bodily functions, such as energy balance and reproduction. Labeled cells were found in the paraventricular, ventromedial, and dorsomedial nuclei as well as in the lateral area of the hypothalamus. Intriguingly, nNOS was seen only after the second week of life in the arcuate nucleus of the hypothalamus (ARH). The most dense and heavily labeled population of cells was found in the organum vasculosum laminae terminalis (OV) and the median preoptic nucleus (MEPO), where most of the somata of the neuroendocrine neurons releasing GnRH and controlling reproduction are located. A great proportion of nNOS-immunoreactive neurons in the OV/MEPO and ARH were seen to express estrogen receptor (ER) α. Notably, almost all ERα-immunoreactive cells of the OV/MEPO also expressed nNOS. Moreover, the use of EYFP Vglut2 , EYFP Vgat , and GFP Gad67 transgenic mouse lines revealed that, like GnRH neurons, most hypothalamic nNOS neurons have a glutamatergic phenotype, except for nNOS neurons of the ARH, which are GABAergic. Altogether, these observations are consistent with the proposed role of nNOS neurons in physiological processes. © 2017 Wiley Periodicals, Inc.

  19. An Optimized Synthesis, Molecular Structure and Characterization of Benzylic Derivatives of 1,2,4-Triazin-3,5(2H,4H-dione

    Directory of Open Access Journals (Sweden)

    Long-Chih Hwang

    2017-11-01

    Full Text Available 4-Benzyl-1,2,4-triazin-3,5(2H,4H-dione (3-benzyl-6-azauracil, 2, and 2,4-dibenzyl-1,2,4-triazin-3,5(2H,4H-dione (1,3-dibenzyl-6-azauracil, 3 were synthesized by the reaction of 1,2,4-triazin-3,5(2H,4H-dione (6-azauracil, 1 with benzyl bromide and potassium carbonate in dry acetone via the 18-crown-6-ether catalysis. In these reaction methods, we developed more convenient and efficient methodologies to afford compounds 2 and 3 in good yields. These compounds were characterized by 1H- and 13C-NMR, MS spectrum, IR spectroscopy and elemental analysis. The structure of 2 was verified by 2D-NMR measurements, including gHSQC and gHMBC measurements. A single-crystal X-ray diffraction experiment indicated that compound 3, with the molecular formula C17H15N3O2, crystallized from a CH3OH/CH2Cl2 diffusion solvent system in a monoclinic space group P21/c with a = 13.7844(13, b = 8.5691(8, c = 13.0527(12 Å, β = 105.961(2°, V = 1482.3(2 Å3, Z = 4, resulting in a density Dcalc of 1.314 g/cm3. The crystal structure of compound 3 is tightly stabilized by contact with five other molecules from the six short contacts formed by intermolecular C−O···H−Car, C−H···Car, and weakly π···π stacking interactions. The dihedral angle 31.90° is formed by the mean planes of the benzene rings of the N-2 and N-4 benzyl groups.

  20. Angiotensin II blockade causes acute renal failure in eNOS-deficient mice

    Directory of Open Access Journals (Sweden)

    Jürgen Schnermann

    2001-03-01

    Full Text Available Compared with wild-type mice, adult endothelial nitric oxide synthase (eNOS knockout mice (eight months of age have increased blood pressure (BP (126±9 mmHg vs. 100±4 mmHg, and an increased renal vascular resistance (155±16 vs. 65±4 mmHg.min/ml. Renal vascular resistance responses to i.v. administration of noradrenaline were markedly enhanced in eNOS knockout mice. Glomerular filtration rate (GFR of anaesthetised eNOS -/- mice was 324±57 µl/min gKW, significantly lower than the GFR of 761±126 µl/min.gKW in wild-type mice. AT1-receptor blockade with i.v. candesartan (1—1.5 mg/kg reduced arterial blood pressure and renal vascular resistance, and increased renal blood flow (RBF to about the same extent in wild-type and eNOS -/- mice. Candesartan did not alter GFR in wild-type mice (761±126 vs. 720±95 µl/min.gKW, but caused a marked decrease in GFR in eNOS -/- mice (324.5±75.2 vs. 77±18 µl/min.gKW. A similar reduction in GFR of eNOS deficient mice was also caused by angiotensin-converting enzyme (ACE inhibition. Afferent arteriolar granularity, a measure of renal renin expression, was found to be reduced in eNOS -/- compared with wild-type mice. In chronically eNOS-deficient mice, angiotensin II (Ang II is critical for maintaining glomerular filtration pressure and GFR, presumably through its effect on efferent arteriolar tone.

  1. Outcome after BCG treatment for urinary bladder cancer may be influenced by polymorphisms in the NOS2 and NOS3 genes.

    Science.gov (United States)

    Ryk, Charlotta; Koskela, Lotta Renström; Thiel, Tomas; Wiklund, N Peter; Steineck, Gunnar; Schumacher, Martin C; de Verdier, Petra J

    2015-12-01

    Bacillus Calmette-Guérin (BCG)-treatment is an established treatment for bladder cancer, but its mechanisms of action are not fully understood. High-risk non-muscle invasive bladder-cancer (NMIBC)-patients failing to respond to BCG-treatment have worse prognosis than those undergoing immediate radical cystectomy and identification of patients at risk for BCG-failure is of high priority. Several studies indicate a role for nitric oxide (NO) in the cytotoxic effect that BCG exerts on bladder cancer cells. In this study we investigated whether NO-synthase (NOS)-gene polymorphisms, NOS2-promoter microsatellite (CCTTT)n, and the NOS3-polymorphisms-786T>C (rs2070744) and Glu298Asp (rs1799983), can serve as possible molecular markers for outcome after BCG-treatment for NMIBC. All NMIBC-patients from a well-characterized population based cohort were analyzed (n=88). Polymorphism data were combined with information from 15-years of clinical follow-up. The effect of BCG-treatment on cancer-specific death (CSD), recurrence and progression in patients with varying NOS-genotypes were studied using Cox proportional hazard-models and log rank tests. BCG-treatment resulted in significantly better survival in patients without (Log rank: p=0.006; HR: 0.12, p=0.048), but not in patients with a long version ((CCTTT)n ≧13 repeats) of the NOS2-promoter microsatellite. The NOS3-rs2070744(TT) and rs1799983(GG)-genotypes showed decreased risk for CSD (Log rank(TT): p=0.001; Log rank(GG): p=0.010, HR(GG): 0.16, p=0.030) and progression (Log rank(TT): p<0.001, HR(TT): 0.05, p=0.005; Log rank(GG): p<0.001, HR(GG): 0.10, p=0.003) after BCG-therapy compared to the other genotypes. There was also a reduction in recurrence in BCG-treated patients that was mostly genotype independent. Analysis of combined genotypes identified a subgroup of 30% of the BCG-treated patients that did not benefit from BCG-treatment. Our results suggest that the investigated polymorphisms influence patient response

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

    International Nuclear Information System (INIS)

    White, R.L.

    1981-01-01

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

  3. Exposure to diesel exhaust up-regulates iNOS expression in ApoE knockout mice

    International Nuclear Information System (INIS)

    Bai Ni; Kido, Takashi; Kavanagh, Terrance J.; Kaufman, Joel D.; Rosenfeld, Michael E.; Breemen, Cornelis van; Eeden, Stephan F. van

    2011-01-01

    Traffic related particulate matter air pollution is a risk factor for cardiovascular events; however, the biological mechanisms are unclear. We hypothesize that diesel exhaust (DE) inhalation induces up-regulation of inducible nitric oxide synthase (iNOS), which is known to contribute to vascular dysfunction, progression of atherosclerosis and ultimately cardiovascular morbidity and mortality. Methods: ApoE knockout mice (30-week) were exposed to DE (at 200 μg/m 3 of particulate matter) or filtered-air (control) for 7 weeks (6 h/day, 5 days/week). iNOS expression in the blood vessels and heart was evaluated by immunohistochemistry and western blotting analysis. To examine iNOS activity, thoracic aortae were mounted in a wire myograph, and vasoconstriction stimulated by phenylephrine (PE) was measured with and without the presence of the specific inhibitor for iNOS (1400 W). NF-κB (p65) activity was examined by ELISA. The mRNA expression of iNOS and NF-κB (p65) was determined by real-time PCR. Results: DE exposure significantly enhanced iNOS expression in the thoracic aorta (4-fold) and heart (1.5 fold). DE exposure significantly attenuated PE-stimulated vasoconstriction by ∼ 20%, which was partly reversed by 1400 W. The mRNA expression of iNOS and NF-κB was significantly augmented after DE exposure. NF-κB activity was enhanced 2-fold after DE inhalation, and the augmented NF-κB activity was positively correlated with iNOS expression (R 2 = 0.5998). Conclusions: We show that exposure to DE increases iNOS expression and activity possibly via NF-κB-mediated pathway. We suspect that DE exposure-caused up-regulation of iNOS contributes to vascular dysfunction and atherogenesis, which could ultimately lead to urban air pollution-associated cardiovascular morbidity and mortality. - Highlights: → Exposed ApoE knockout mice (30-week) to diesel exhaust (DE) for 7 weeks. → Examine iNOS expression and activity in the blood vessels and heart. → DE exposure

  4. Envolvimento nos direitos humanos e sistemas de valores

    OpenAIRE

    Pereira,Cícero; Ribeiro,Ana Raquel Correia; Cardoso,Sandro José

    2004-01-01

    Com base no modelo da análise quantitativa das representações sociais, o estudo (N = 300) tratou do posicionamento de estudantes universitários em relação aos Direitos Humanos (DHs) e à ancoragem social desse posicionamento nos sistemas de valores dos estudantes. Os resultados mostram que as representações dos estudantes sobre o envolvimento nos DHs envolvem quatro princípios organizadores: pessoal-abstrato; pessoal-concreto; governamental-abstrato; governamental-concreto. Em relação à ancora...

  5. Modelo experimental estável de aneurisma sacular em artéria carótida de suínos utilizando veia jugular interna

    Directory of Open Access Journals (Sweden)

    Severino Lourenço da Silva Júnior

    Full Text Available OBJETIVO: Desenvolver um modelo experimental estável de aneurisma sacular em carótida de suínos utilizando veia jugular interna. MÉTODOS: Em 12 suínos sadios, com peso variando entre 25 e 50kg, cinco machos e sete fêmeas, foi confeccionado aneurisma na artéria carótida comum direita. Após arteriotomia elíptica, foi realizada anastomose terminolateral com coto distal de veia jugular interna. O volume do aneurisma era calculado de maneira que o valor não excedesse em 27 vezes o valor da área da arteriotomia. Após seis dias, era realizada angiografia e análise microscópica do aneurisma para avaliar perviedade e trombose parcial ou total. RESULTADOS: Houve ganho de peso significante dos suínos no intervalo de tempo entre a confecção do aneurisma e a angiografia (p = 0,04. Foi observada perviedade aneurismática em dez suínos (83%. Ocorreram infecções de feridas operatórias em dois animais (16,6%, ambas com início de aparecimento em três dias após a confecção do aneurisma. Análise histológica dos aneurismas mostrou trombos ocluindo parcialmente a luz em nove suínos (75%. Nesses animais, observou-se que, em média, 9% da luz aneurismática estava preenchida por trombos. CONCLUSÃO: Pôde ser desenvolvido um modelo experimental estável de aneurisma sacular em carótida de suínos utilizando veia jugular interna.

  6. Development of a 352 MHz Cell-Coupled Drift Tube Linac Prototype

    CERN Document Server

    Cuvet, Y; Völlinger, C; Vretenar, M; Gerigk, F

    2004-01-01

    At linac energies above 40 MeV, alternative structures to the conventional Drift Tube Linac can be used to increase efficiency and to simplify construction and alignment. In the frame of the R&D activities for the CERN SPL and Linac4, a prototype of Cell-Coupled Drift Tube Linac (CCDTL) at 352 MHz has been designed and built. This particular CCDTL concept is intended to cover the energy range from 40 to 90 MeV and consists of modules of ~5 m length made of 3-gap DTL tanks linked by coupling cells. The focusing quadrupoles are placed between tanks, and are aligned independently from the RF structure. The CCDTL prototype consists of two half tanks connected by a coupling cell and requires an RF power of 120 kW to achieve the design gradient. RF tests will be made at low and high power, the latter up to a 20% duty cycle. This paper introduces the main features of this CCDTL design and describes the RF and mechanical design of the prototype.

  7. Resposta tecidual ao compósito 50% hidroxiapatita: 50% poli-hidroxibutirato para substituição óssea em coelhos Tissue response to the composite 50% hydroxyapatite: 50% polyhydroxybutyrate for bone substitution in rabbits

    Directory of Open Access Journals (Sweden)

    E.C. Carlo

    2009-08-01

    Full Text Available Avaliaram-se a biocompatibilidade, a osseointegração, a osseocondução e a biodegradação de compósitos de 50% hidroxiapatita (HAP-91® e 50% poli-hidroxibutirato. O compósito foi implantado em defeitos ósseos em 12 coelhos (grupo experimental, sendo comparado a defeitos não preenchidos (grupo-controle, de igual número. Os parâmetros clínicos dor, claudicação, infecção, deiscência e edema foram avaliados nos primeiros oito dias após a cirurgia e aos 45 e 90 dias. Radiografias foram realizadas aos oito, 45 e 90 dias após a cirurgia em quatro animais por grupo que, em seguida, foram submetidos à eutanásia para coleta de amostras destinadas a análises histológica e histomorfométrica. Não ocorreram diferenças entre os grupos para todos os parâmetros clínicos. Radiografias demonstraram um compósito com radiopacidade semelhante à do osso vizinho e contato direto entre osso e compósito aos 45 e 90 dias. Diferença significativa foi observada entre a porcentagem dos tecidos ósseo e conjuntivo dentro do defeito nos dias oito, 45 e 90, assim como na interface aos 45 e 90 dias. Foram observadas projeções dos tecidos ósseo e conjuntivo no interior do compósito e sinais de biodegradação na ausência de infiltrado inflamatório. Pode-se concluir que o compósito é biocompatível, osseocondutor, biodegradável e se integra ao tecido ósseo.The biocompatibility, osseointegration, osseoconductivity, and biodegradation of a 50-50% hydroxyapatite (HAP-91®-polyhydroxybutyrate were evaluated. The composite was implanted in bone defects of 12 rabbits (experimental group, being compared to unfilled defects (control group, 12 animals. The clinical parameters of pain, lameness, infection, dehiscence, and edema were evaluated during the first eight days and on the 45th and 90th days after surgery. Radiographs were taken in four animals per group at 8, 45, and 90 days after surgery, when animals were euthanized to collect samples for

  8. IODP Expedition 352 (Bonin Forearc): First Results

    Science.gov (United States)

    Pearce, J. A.; Reagan, M. K.; Stern, R. J.; Petronotis, K. E.

    2014-12-01

    IODP Expedition #352 (Testing Subduction Initiation and Ophiolite Models by Drilling the Outer Izu-Bonin-Mariana Forearc: July 30-Sept. 29, 2014) is just underway at the time of writing. It is testing the Stern-Bloomer hypothesis that subduction initiation (SI) was followed by a strongly extensional period of slab sinking and trench roll-back and then by a transitional period leading to the establishment of significant slab-parallel plate motion and hence normal subduction. The Expedition aims to carry out offset drilling at two sites near 28°30'N in the Bonin forearc. Ideally, these together will give the vertical volcanic stratigraphy needed to trace the geodynamic and petrogenetic processes associated with SI, and provide the complete reference section required for comparison with volcanic sequences of possible SI origin found on land in ophiolite complexes and elsewhere. We predict, but need to confirm, a c. 1.0-1.5km sequence with basal, MORB-like forearc basalts (known as FAB) marking the initial period of extension, boninites characterizing the transitional period, and tholeiitic and calc-alkaline lavas marking the establishment of normal arc volcanism. Study of such a sequence will enable us to understand the chemical gradients within and across these volcanic units, to reconstruct mantle flow and melting processes during the course of SI, and to test the hypothesis that fore-arc lithosphere created during SI is the birthplace of most supra-subduction zone ophiolites. Here, we present the first Expedition results, including (a) the volcanic stratigraphic record and subdivision into lava units, (b) the classifications and interpretations made possible by shipboard (portable XRF and ICP) analyses and down-hole measurements, and (c) the biostratigraphic, magnetic, mineralogical, sedimentary and structural constraints on the geological history of the SI section and the interactions between magmatic, hydrothermal and tectonic activity during its evolution.

  9. Perfil lipídico da carne e gordura de suínos alimentados com milheto

    Directory of Open Access Journals (Sweden)

    Rodrigo Caetano de Abreu

    2014-01-01

    Full Text Available O objetivo deste trabalho foi avaliar níveis de milheto na alimentação de suínos na composição lipídica e de colesterol da gordura subcutânea e da carne. Foram utilizados 48 animais, machos castrados, distribuídos em um delineamento experimental de blocos casualizados, com quatro níveis de milheto na dieta (0; 25; 50 e 75%, seis repetições, sendo cada unidade experimental constituída por dois animais. Foram analisados os perfis lipídicos da gordura e da carne através de cromatografia gasosa e a quantidade de colesterol nas amostras de carne foi determinada seguindo a metodologia de extração. O aumento do nível de milheto na dieta dos suínos reduziu (P<0,05 a concentração dos ácidos mirístico, palmítico, palmitoleico, heptadecanoico e aumentou a concentração do ácido linoleico na gordura subcutânea. O nível de inclusão de 50,82% de milheto na dieta possibilita máxima deposição do ácido linolênico na gordura. Os níveis de milheto não modificam o perfil de ácidos graxos e o teor de colesterol na carne suína. O nível de 42,09% de inclusão de milheto na dieta resulta no maior índice trombogênico da carne.

  10. Circulating Blood eNOS Contributes to the Regulation of Systemic Blood Pressure and Nitrite Homeostasis

    Science.gov (United States)

    Wood, Katherine C.; Cortese-Krott, Miriam M.; Kovacic, Jason C.; Noguchi, Audrey; Liu, Virginia B.; Wang, Xunde; Raghavachari, Nalini; Boehm, Manfred; Kato, Gregory J.; Kelm, Malte; Gladwin, Mark T.

    2013-01-01

    Objective Mice genetically deficient in endothelial nitric oxide synthase (eNOS−/−) are hypertensive with lower circulating nitrite levels, indicating the importance of constitutively produced nitric oxide (NO•) to blood pressure regulation and vascular homeostasis. While the current paradigm holds that this bioactivity derives specifically from expression of eNOS in endothelium, circulating blood cells also express eNOS protein. A functional red cell eNOS that modulates vascular NO• signaling has been proposed. Approach and Results To test the hypothesis that blood cells contribute to mammalian blood pressure regulation via eNOS-dependent NO• generation, we cross-transplanted WT and eNOS−/− mice, producing chimeras competent or deficient for eNOS expression in circulating blood cells. Surprisingly, we observed a significant contribution of both endothelial and circulating blood cell eNOS to blood pressure and systemic nitrite levels, the latter being a major component of the circulating NO• reservoir. These effects were abolished by the NOS inhibitor L-NAME and repristinated by the NOS substrate L-Arginine, and were independent of platelet or leukocyte depletion. Mouse erythrocytes were also found to carry an eNOS protein and convert 14C-Arginine into 14C-Citrulline in a NOS-dependent fashion. Conclusions These are the first studies to definitively establish a role for a blood borne eNOS, using cross transplant chimera models, that contributes to the regulation of blood pressure and nitrite homeostasis. This work provides evidence suggesting that erythrocyte eNOS may mediate this effect. PMID:23702660

  11. Microcystin-LR Induces Apoptosis via NF-κB /iNOS Pathway in INS-1 Cells

    Directory of Open Access Journals (Sweden)

    Kai Shen

    2011-07-01

    Full Text Available Cyanobacterial toxins, especially the microcystins, are found in eutrophied waters throughout the world, and their potential to impact on human and animal health is a cause for concern. Microcystin-LR (MC-LR is one of the common toxic microcystin congeners and occurs frequently in diverse water systems. Recent work suggested that apoptosis plays a major role in the toxic effects induced by MC-LR in hepatocytes. However, the roles of MC-LR in pancreatic beta cells have not been fully established. The aim of the present study was to assess possible in vitro effects of MC-LR on cell apoptosis in the rat insulinoma cell line, INS-1. Our results demonstrated that MC-LR promoted selectively activation of NF-κB (increasing nuclear p50/p65 translocation and increased the mRNA and protein levels of induced nitric oxide synthase (iNOS. The chronic treatment with MC-LR stimulated nitric oxide (NO production derived from iNOS and induced apoptosis in a dose dependent manner in INS-1 cells. Meanwhile, this effect was inhibited by the NF-κB inhibitor PDTC, which reversed the apoptosis induced by MC-LR. Our observations indicate that MC-LR induced cell apoptosis via an iNOS-dependent pathway. A well-known nuclear transcription factor, NF-κB, is activated and mediates intracellular nitric oxide synthesis. We suggest that the apoptosis induced by chronic MC-LR in vivo presents a possible cause of β-cell dysfunction, as a key environmental factor in the development of diabetes mellitus.

  12. Macrophages activate iNOS signaling in adventitial fibroblasts and contribute to adventitia fibrosis.

    Science.gov (United States)

    Zhang, Guannan; Li, Xiaodong; Sheng, Chengyu; Chen, Xiaohui; Chen, Yu; Zhu, Dingliang; Gao, Pingjin

    2016-12-30

    A large amount of NO is generated through the inducible nitric oxide synthase (iNOS) pathway from the vascular adventitia in various vascular diseases. However, it is currently not fully understood how the iNOS signaling pathway is activated. In the present study, this question was addressed in the context of adventitial cellular interactions. A rat model of acute hypertension in the contralateral carotid arteries was established through transverse aortic constriction (TAC) surgery. In this model, activated macrophages were found surrounded by a large quantity of iNOS-expressing adventitial fibroblasts (AFs), suggesting a possible causal relationship between macrophages and iNOS activation of the neighboring AFs. In an in vitro model, a macrophage-like cell line RAW 264.7 was first activated by LPS treatment. The supernatant was then harvested and applied to treat primary rat AFs. iNOS in AFs was activated robustly by the supernatant treatment but not by LPS itself. Treating AFs with interleukin-1β (IL-1β) also activated iNOS signaling, suggesting that the IL-1β pathway might be a possible mediator. As a consequence of the iNOS activation, total protein nitration and S-nitrosylation significantly increased in those AFs. Additionally, increased deposition of type I and type III collagens was observed in both in vitro and in vivo models. The collagen deposition was partially restored by an iNOS inhibitor, 1400 W. These findings highlight the importance of iNOS signaling during vascular inflammation, and advance our understanding of its activation through a cellular interaction perspective. Copyright © 2016 Elsevier Inc. All rights reserved.

  13. Alteration in cardiac uncoupling proteins and eNOS gene expression following high-intensity interval training in favor of increasing mechanical efficiency.

    Science.gov (United States)

    Fallahi, Ali Asghar; Shekarfroush, Shahnaz; Rahimi, Mostafa; Jalali, Amirhossain; Khoshbaten, Ali

    2016-03-01

    High-intensity interval training (HIIT) increases energy expenditure and mechanical energy efficiency. Although both uncoupling proteins (UCPs) and endothelial nitric oxide synthase (eNOS) affect the mechanical efficiency and antioxidant capacity, their effects are inverse. The aim of this study was to determine whether the alterations of cardiac UCP2, UCP3, and eNOS mRNA expression following HIIT are in favor of increased mechanical efficiency or decreased oxidative stress. Wistar rats were divided into five groups: control group (n=12), HIIT for an acute bout (AT1), short term HIIT for 3 and 5 sessions (ST3 and ST5), long-term training for 8 weeks (LT) (6 in each group). The rats of the training groups were made to run on a treadmill for 60 min in three stages: 6 min running for warm-up, 7 intervals of 7 min running on treadmill with a slope of 5° to 20° (4 min with an intensity of 80-110% VO2max and 3 min at 50-60% VO2max), and 5-min running for cool-down. The control group did not participate in any exercise program. Rats were sacrificed and the hearts were extracted to analyze the levels of UCP2, UCP3 and eNOS mRNA by RT-PCR. UCP3 expression was increased significantly following an acute training bout. Repeated HIIT for 8 weeks resulted in a significant decrease in UCPs mRNA and a significant increase in eNOS expression in cardiac muscle. This study indicates that Long term HIIT through decreasing UCPs mRNA and increasing eNOS mRNA expression may enhance energy efficiency and physical performance.

  14. Physical properties of fore-arc basalt and boninite in Izu-Bonin-Mariana forearc recovered by IODP Expedition 352

    Science.gov (United States)

    Honda, M.; Michibayashi, K.; Almeev, R. R.; Christeson, G. L.; Sakuyama, T.; Yamamoto, Y.; Watanabe, T.

    2016-12-01

    The Izu-Bonin-Mariana (IBM) arc is a typical intraoceanic arc system and is the type locality for subduction initiation. IODP-IBM project is aimed to understand subduction initiation, arc evolution, and continental crust formation. Expedition 352 is one of the IBM projects and that has drilled four sites at the IBM fore-arc. Expedition 352 has successfully recovered fore-arc basalts and boninites related to seafloor spreading during the subduction initiation as well as the earliest arc development. The fore-arc basalts were recovered from two sites (U1440 and U1441) at the deeper trench slope to the east, whereas the boninites were recovered from two sites (U1439 and U1442) at the shallower slope to the west. In this study, we studied textures and physical properties of both the fore-arc basalt and the boninite samples recovered by IODP Expedition 352. The fore-arc basalt samples showed aphyric texture, whereas the boninites showed hyaloclastic, aphyric and porphyritic textures. For the physical properties, we measured density, porosity, P-wave velocity and anisotropy of magnetic susceptibility. P-wave velocities were measured under ordinary and confining pressure. As a result, the densities are in a range between 2 g/cm3 and 3 g/cm3. The porosities are in a range between 5 % and 40 %. The P-wave velocities are in a wide range from 3 km/s to 5.5 km/s and have a positive correlation to the densities. The magnetic susceptibilities showed bimodal distributions so that the physical properties were classified into two groups: a high magnetic susceptibility group (>5×10-3) and a low magnetic susceptibility group (<5×10-3). The high magnetic susceptibility group is almost identical with the fore-arc basalt and boninite samples with the higher correlation trend between the P-wave velocities and the densities, whereas the low magnetic susceptibility group is only the boninite samples with the lower correlation trend between the P-wave velocities and the densities. It

  15. Association between nucleotide mutation of eNOS gene and serum ...

    African Journals Online (AJOL)

    Various mutation on endothelial nitric oxide synthase (eNOs) gene cause reduced production of NO, the expansion factor (VEF) and may accelerate the process of atherosclerosis. The study was designed to investigate the frequency of T-786C polymorphism of the gene or nucleotide mutation of eNOS gene in patients ...

  16. Development of high power CW and pulsed RF test facility based on 1 MW, 352.2 MHz klystron amplifier

    International Nuclear Information System (INIS)

    Badapanda, M.K.; Tripathi, Akhilesh; Upadhyay, Rinki; Rao, J.N.; Tiwari, Ashish; Jain, Akhilesh; Lad, M.R.; Hannurkar, P.R.

    2013-01-01

    A high power 1 MW, 352.2 MHz RF Test facility having CW and Pulse capability is being developed at Raja Ramanna Centre for Advanced Technology (RRCAT), Indore for performance evaluation of various RF components, accelerating structures and related subsystems. Thales make 1 MW, 352.2 MHz klystron amplifier (TH 2089) will be employed in this high power test facility, which is thoroughly tested for its performance parameters at rated operating conditions. Auxiliary power supplies like filament, electromagnet, ion pump and mod anode power supply as well as 200 W solid state driver amplifier necessary for this high power test facility have been developed. A high voltage floating platform is created for floating filament and mod anode power supplies. Interconnection of various power supplies and other subsystems of this test facility are being carried out. A high voltage 100 kV, 25 Amp DC crowbar less power supply and low conductivity water (LCW) plant required for this klystron amplifier are in advanced stage of development. NI make cRIO 9081 real time (RT) controller based control and interlock system has been developed to realize proper sequence of operation of various power supplies and to monitor the status of crucial parameters in this test facility. This RF test facility will provide confidence for development of RF System of future accelerators like SNS and ADSS. (author)

  17. Patogenicidade e virulência de Toxoplasma gondii isolado de suínos de criação artesanal no sul do Brasil

    Directory of Open Access Journals (Sweden)

    Plínio Aguiar de Oliveira

    2014-12-01

    Full Text Available Estudos com Toxoplasma gondii em suínos são relevantes porque seus produtos e subprodutos fazem parte da cadeia alimentar do ser humano. As principais vias de transmissão deste agente são o carnivorismo, fecal-oral e congênita. Seis isolados de Toxoplasma gondii de suínos de criação artesanal foram avaliados quanto à patogenicidade e virulência em camundongos suíços albinos. A suspensão de taquizoítos utilizada nos testes foi obtida através da punção ou lavagem da cavidade peritoneal de camundongos que apresentaram ascite. Cada amostra foi inoculada em grupos de cinco camundongos, com inóculo de 10¹, 10², 10³, 10(4, 10(5 e 10(6 taquizoítos vivos, via intraperitoneal. Dos isolados, 50% (3/6 foram letais e causaram sinais clínicos nos camundongos. A dose mínima letal foi de 10³ taquizoítos. A morte dos animais que apresentaram infecção aguda ocorreu entre 12 e 26 dias após a inoculação. Todos os isolados da região estudada apresentam alta capacidade de formar cistos, o que pode aumentar o risco de infecção pela ingestão de tecidos dos animais infectados pelos mesmos.

  18. Electroacupuncture Delays Hypertension Development through Enhancing NO/NOS Activity in Spontaneously Hypertensive Rats

    Directory of Open Access Journals (Sweden)

    Hye Suk Hwang

    2011-01-01

    Full Text Available Using spontaneously hypertensive rats (SHR, this study investigated whether electroacupuncture (EA could reduce early stage hypertension by examining nitric oxide (NO levels in plasma and nitric oxide synthase (NOS levels in the mesenteric resistance artery. EA was applied to the acupuncture point Governor Vessel 20 (GV20 or to a non-acupuncture point in the tail twice weekly for 3 weeks under anesthesia. In conscious SHR and normotensive Wistar Kyoto (WKY rats, blood pressure was determined the day after EA treatment by the tail-cuff method. We measured plasma NO concentration, and evaluated endothelial NO syntheses (eNOS and neuronal NOS (nNOS protein expression in the mesenteric artery. Systolic blood pressure (SBP and diastolic blood pressure (DBP were lower after 3 weeks of GV20 treatment than EA at non-acupuncture point and no treatment control in SHR. nNOS expression by EA was significantly different between both WKY and no treatment SHR control, and EA at GV20 in SHR. eNOS expression was significantly high in EA at GV 20 compared with no treatment control. In conclusion, EA could attenuate the blood pressure elevation of SHR, along with enhancing NO/NOS activity in the mesenteric artery in SHR.

  19. 78 FR 77508 - Duke Energy Carolinas, LLC; William States Lee III Nuclear Station, Units 1 and 2; Combined...

    Science.gov (United States)

    2013-12-23

    ... NUCLEAR REGULATORY COMMISSION [Docket Nos. 52-018 and 52-019; NRC-2008-0170] Duke Energy Carolinas, LLC; William States Lee III Nuclear Station, Units 1 and 2; Combined Licenses Application Review AGENCY: Nuclear Regulatory Commission. ACTION: Final environmental impact statement; availability...

  20. Expression of Beta-catenin, COX-2 and iNOS in Colorectal Cancer: Relevance of COX-2 and iNOS Inhibitors for Treatment in Malaysia

    Directory of Open Access Journals (Sweden)

    Seok Kwan Hong

    2004-01-01

    Conclusions: The accumulation of β-catenin does not seem to be sufficient to activate pathways that lead to increased COX-2 and iNOS expression. A high proportion of colorectal cancers were found to express COX-2 and a significant number produced iNOS, suggesting that their inhibitors may be potentially useful as chemotherapeutic agents in the management of colorectal cancer.