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Sample records for operating licenses

  1. Operator licensing examiner standards

    International Nuclear Information System (INIS)

    1987-05-01

    The Operator Licensing Examiner Standards provide policy and guidance to NRC examiners and establish the procedures and practices for examining and licensing of applicants for NRC operator licenses pursuant to Part 55 of Title 10 of the Code of Federal Regulations (10 CFR 55). They are intended to assist NRC examiners and facility licensees to understand the examination process better and to provide for equitable and consistent administration of examinations to all applicants by NRC examiners. These standards are not a substitute for the operator licensing regulations and are subject to revision or other internal operator examination licensing policy changes

  2. Operator licensing examiner standards

    International Nuclear Information System (INIS)

    1983-10-01

    The Operator Licensing Examiner Standards provide policy and guidance to NRC examiners and establish the procedures and practices for examining and licensing of applicants for NRC operator licenses pursuant to Part 55 of Title 10 of the Code of Federal Regulations (10 CFR 55). They are intended to assist NRC examiners and facility licensees to understand the examination process better and to provide for equitable and consistent administration of examinations to all applicants by NRC examiners. These standards are not a substitute for the operator licensing regulations and are subject to revision or other internal operator examination licensing policy changes. As appropriate, these standards will be revised periodically to accommodate comments and reflect new information or experience

  3. Operator licensing examiner standards

    International Nuclear Information System (INIS)

    1993-01-01

    The Operator Licensing Examiner Standards provide policy and guidance to NRC examiners and establish the procedures and practices for examining licensees and applicants for reactor operator and senior reactor operator licenses at power reactor facilities pursuant to Part 55 of Title 10 of the Code of Federal Regulations (10 CFR 55). The Examiner Standards are intended to assist NRC examiners and facility licensees to better understand the initial and requalification examination processes and to ensure the equitable and consistent administration of examinations to all applicants. These standards are not a substitute for the operator licensing regulations and are subject to revision or other internal operator licensing policy changes

  4. Operator licensing examiner standards

    International Nuclear Information System (INIS)

    1994-06-01

    The Operator Licensing Examiner Standards provide policy and guidance to NRC examiners and establish the procedures and practices for examining licensees and applicants for reactor operator and senior reactor operator licenses at power reactor facilities pursuant to Part 55 of Title 10 of the Code of Federal Regulations (10 CFR 55). The Examiner Standards are intended to assist NRC examiners and facility licensees to better understand the initial and requalification examination processes and to ensure the equitable and consistent administration of examinations to all applicants. These standards are not a substitute for the operator licensing regulations and are subject to revision or other internal operator licensing policy changes. Revision 7 was published in January 1993 and became effective in August 1993. Supplement 1 is being issued primarily to implement administrative changes to the requalification examination program resulting from the amendment to 10 CFR 55 that eliminated the requirement for every licensed operator to pass an NRC-conducted requalification examination as a condition for license renewal. The supplement does not substantially alter either the initial or requalification examination processes and will become effective 30 days after its publication is noticed in the Federal Register. The corporate notification letters issued after the effective date will provide facility licensees with at least 90 days notice that the examinations will be administered in accordance with the revised procedures

  5. Operating reactors licensing actions summary

    International Nuclear Information System (INIS)

    1982-07-01

    The operating reactors licensing actions summary is designed to provide the management of the Nuclear Regulatory Commission (NRC) with an overview of licensing actions dealing with operating power and nonpower reactors. These reports utilize data collected from the Division of Licensing in the Office of Nuclear Reactor Regulation and are prepared by the Office of Management and Program Analysis. This summary report is published primarily for internal NRC use in managing the operating reactors licensing actions program. Its content will change based on NRC management informational requirements

  6. Operating reactors licensing actions summary

    International Nuclear Information System (INIS)

    1982-05-01

    The operating reactors licensing actions summary is designed to provide the management of the Nuclear Regulatory Commission (NRC) with an overview of licensing actions dealing with operating power and nonpower reactors. These reports utilize data collected from the Division of Licensing in the Office of Nuclear Reactor Regulation and are prepared by the Office of Management and Program Analysis. This summary report is published primarily for internal NRC use in managing the operating reactors licensing actions program. Its content will change based on NRC management informational requirements

  7. Operating reactors licensing actions summary

    International Nuclear Information System (INIS)

    1983-01-01

    The operating reactors licensing actions summary is designed to provide the management of the Nuclear Regulatory Commission (NRC) with an overview of licensing actions dealing with operating power and nonpower reactors. These reports utilize data collected from the Division of Licensing in the Office of Nuclear Reactor Regulation and are prepared by the Office of Management and Program Analysis. This summary report is published primarily for internal NRC use in managing the operating reactors licensing actions program. Its content will change based on NRC management informational requirements

  8. Operating reactors licensing actions summary

    International Nuclear Information System (INIS)

    1983-03-01

    The operating reactors licensing actions summary is designed to provide the management of the Nuclear Regulatory Commission (NRC) with an overview of licensing actions dealing with operating power and nonpower reactors. These reports utilize data collected from the Division of Licensing in the Office of Nuclear Reactor Regulation and are prepared by the Office of Management and Program Analysis. This summary report is published primarily for internal NRC use in managing the operating reactors licensing actions program. Its content will change based on NRC management informational requirements

  9. Operating reactors licensing actions summary

    International Nuclear Information System (INIS)

    1982-11-01

    The operating reactors licensing actions summary is designed to provide the management of the Nuclear Regulatory Commission (NRC) with an overview of licensing actions dealing with operating power and nonpower reactors. These reports utilize data collected from the Division of Licensing in the Office of Nuclear Reactor Regulation and are prepared by the Office of Management and Program Analysis. This summary report is published primarily for internal NRC use in managing the operating reactors licensing actions program. Its content will change based on NRC management informational requirements

  10. Operating reactors licensing actions summary

    International Nuclear Information System (INIS)

    1982-10-01

    The operating reactors licensing actions summary is designed to provide the management of the Nuclear Regulatory Commission (NRC) with an overview of licensing actions dealing with operating power and nonpower reactors. These reports utilize data collected from the Division of Licensing in the Office of Nuclear Reactor Regulation and are prepared by the Office of Management and Program Analysis. This summary report is published primarily for internal NRC use in managing the operating reactors licensing actions program. Its content will change based on NRC management informational requirements

  11. Operating reactors licensing actions summary

    International Nuclear Information System (INIS)

    1982-08-01

    The operating reactors licensing actions summary is designed to provide the management of the Nuclear Regulatory Commission (NRC) with an overview of licensing actions dealing with operating power and nonpower reactors. These reports utilize data collected from the Division of Licensing in the Office of Nuclear Reactor Regulation and are prepared by the Office of Management and Program Analysis. This summary report is published primarily for internal NRC use in managing the operating reactors licensing actions program. Its content will change based on NRC management informational requirements

  12. Operating reactors licensing actions summary

    International Nuclear Information System (INIS)

    1982-09-01

    The operating reactors licensing actions summary is designed to provide the management of the Nuclear Regulatory Commission (NRC) with an overview of licensing actions dealing with operating power and nonpower reactors. These reports utilize data collected from the Division of Licensing in the Office of Nuclear Reactor Regulation and are prepared by the Office of Management and Program Analysis. This summary report is published primarily for internal NRC use in managing the operating reactors licensing actions program. Its content will change based on NRC management informational requirements

  13. Operating reactors licensing actions summary

    International Nuclear Information System (INIS)

    1982-04-01

    The operating reactors licensing actions summary is designed to provide the management of the Nuclear Regulatory Commission (NRC) with an overview of licensing actions dealing with operating power and nonpower reactors. These reports utilize data collected from the Division of Licensing in the Office of Nuclear Reactor Regulation and are prepared by the Office of Management and Program Analysis

  14. Operating reactors licensing actions summary

    International Nuclear Information System (INIS)

    1981-08-01

    The Operating Reactors Licensing Actions Summary is designed to provide the management of the Nuclear Regulatory Commission (NRC) with an overview of licensing actions dealing with operating power and nonpower reactors

  15. Nuclear reactor operator licensing

    International Nuclear Information System (INIS)

    Bursey, R.J.

    1978-01-01

    The Atomic Energy Act of 1954, which was amended in 1974 by the Energy Reorganization Act, established the requirement that individuals who had the responsibility of operating the reactors in nuclear power plants must be licensed. Section 107 of the act states ''the Commission shall (1) prescribe uniform conditions for licensing individuals; (2) determine the qualifications of such individuals; and (3) issue licenses to such individuals in such form as the Commission may prescribe.'' The article discusses the types of licenses, the selection and training of individuals, and the administration of the Nuclear Regulatory Commission licensing examinations

  16. Nuclear power plant operator licensing

    International Nuclear Information System (INIS)

    1997-01-01

    The guide applies to the nuclear power plant operator licensing procedure referred to the section 128 of the Finnish Nuclear Energy Degree. The licensing procedure applies to shift supervisors and those operators of the shift teams of nuclear power plant units who manipulate the controls of nuclear power plants systems in the main control room. The qualification requirements presented in the guide also apply to nuclear safety engineers who work in the main control room and provide support to the shift supervisors, operation engineers who are the immediate superiors of shift supervisors, heads of the operational planning units and simulator instructors. The operator licensing procedure for other nuclear facilities are decided case by case. The requirements for the basic education, work experience and the initial, refresher and complementary training of nuclear power plant operating personnel are presented in the YVL guide 1.7. (2 refs.)

  17. Licensing of nuclear reactor operators

    International Nuclear Information System (INIS)

    1979-09-01

    Recommendations are presented for the licensing of nuclear reactor operators in units licensed according to the legislation in effect. They apply to all physical persons designated by the Operating Organization of the nuclear reactor or reactors to execute any of the following functional activities: a) to manipulate the controls of a definite reactor b) to direct the authorized activities of the reactor operators licesed according to the present recommendations. (F.E.) [pt

  18. Non-Power Reactor Operator Licensing Examiner Standards

    International Nuclear Information System (INIS)

    1994-06-01

    The Non-Power Reactor Operator Licensing Examiner Standards provide policy and guidance to NRC examiners and establish the procedures and practices for examining and licensing of applicants for NRC operator licenses pursuant to Part 55 of Title 10 of the Code of Federal Regulations (10 CFR Part 55). They are intended to assist NRC examiners and facility licensees to understand the examination process better and to provide for equitable and consistent administration of examinations to all applicants by NRC examiners. These standards are not a substitute for the operator licensing regulations and are subject to revision or other internal operator examination licensing policy changes. As appropriate, this standard will be revised periodically to accommodate comments and reflect new information or experience

  19. Licensed operating reactors

    International Nuclear Information System (INIS)

    1989-11-01

    The US Nuclear Regulatory Commission's monthly Licensed Operating Reactors Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Information Resources Management, from the Headquarters Staff of NRC's Office of Inspection and Enforcement, from NRC's Regional Offices, and from utilities. Since all of the data concerning operation of the units is provided by the utility operators less than two weeks after the end of the month, necessary corrections to published information are shown on the errata page

  20. Why operators fail licensing examinations

    International Nuclear Information System (INIS)

    Roth, D.R.; Zerbo, J.N.

    1975-01-01

    A survey was conducted among nuclear utility operators who have taken NRC licensing examinations to determine which factors they considered important in their success or failure. The operators also compared the actual NRC examination with their expectations prior to taking the examination. The results of the survey supplement NRC statistics with regard to failure rates. Over 350 operators and 20 utilities participated in the survey and a good cross section of the nuclear community is represented. Reactor theory and emergency procedures are important areas in which operators found NRC emphasis to be different than expected. Observation Training and Design Lecture Series are two training segments which appear to require improvement. Recommendations are made for the use of data collected through this survey and for continuation of the effort to give operators a mechanism of supplying feedback to the training and licensing process

  1. Operating reactors licensing actions summary. Volume 5, No. 2

    International Nuclear Information System (INIS)

    1985-04-01

    The Operating Reactors Licensing Actions Summary is designed to provide the management of the Nuclear Regulatory Commission (NRC) with an overview of licensing actions dealing with operating power and nonpower reactors. These reports utilize data collected from the Division of Licensing in the Office of Nuclear Reactor Regulation and are prepared by the Office of Resource Management. This summary report is published primarily for internal NRC use in managing the Operating Reactors Licensing Actions Program

  2. TMI-related requirements for new operating licenses. Technical report

    International Nuclear Information System (INIS)

    1980-06-01

    There are four types of TMI-related requirements and actions approved by the Commission for new operating licenses: (1) those required to be completed by a license applicant prior to receiving a fuel-loading and low-power testing license, (2) those required to be completed by a license applicant prior to receiving a license to operate at appreciable power levels up to full power, (3) those the NRC will take prior to issuing a fuel-loading and low-power testing or a full-power operating license, and (4) those required to be completed by a licensee prior to a specified date. In this report, only those dated requirements that have already been issued are of interest. Other dated requirements are expected to be issued in the future as work progresses in accordance with the TMI Action Plan. This report summarizes the several parts of the list of TMI-related requirements approved by the Commission for new operating licenses

  3. Operating reactors licensing actions summary. Vol. 3, No. 3

    International Nuclear Information System (INIS)

    1983-04-01

    The operating reactors licensing actions summary is designed to provide the management of the Nuclear Regularory Commission (NRC) with an overview of licensing actions dealing with operating power and nonpower reactors. These reports utilize data collected from the Division of Licensing in the Office of Nuclear Reactor Regulation and are prepared by the Office of Management and Program Analysis. This summary report is published primarily for internal NRC use in managing the operating reactors licensing actions program

  4. Licensed operating reactors

    International Nuclear Information System (INIS)

    1989-08-01

    THE OPERATING UNITS STATUS REPORT - LICENSED OPERATING REACTORS provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Information Resources Management from the Headquarters staff of NRC's Office of Enforcement (OE), from NRC's Regional Offices, and from utilities. The three sections of the report are: monthly highlights and statistics for commercial operating units, and errata from previously reported data; a compilation of detailed information on each unit, provided by NRC's Regional Offices, OE Headquarters and the utilities; and an appendix for miscellaneous information such as spent fuel storage capability, reactor-years of experience and non-power reactors in the US

  5. Licensed operating reactors

    International Nuclear Information System (INIS)

    1990-04-01

    The Operating Units Status Report --- Licensed Operating Reactors provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Information Resources Management from the Headquarters staff on NRC's Office of Enforcement (OE), from NRC's Regional Offices, and from utilities. The three sections of the report are: monthly highlights and statistics for commercial operating units, and errata from previously reported data; a compilation of detailed information on each unit, provided by NRC's Regional Offices, OE Headquarters and the utilities; and an appendix for miscellaneous information such as spent fuel storage capability, reactor-years of experience and non- power reactors in the US

  6. Non-Power Reactor Operator Licensing Examiner Standards. Revision 1

    International Nuclear Information System (INIS)

    1995-06-01

    The Non-Power Reactor Operator Licensing Examiner Standards provide policy and guidance to NRC examiners and establish the procedures and practices for examining and licensing of applicants for NRC operator licenses pursuant to Part 55 of Title 10 of the Code of Federal Regulations (10 CFR 55). They are intended to assist NRC examiners and facility licensees to understand the examination process better and to provide for equitable and consistent administration of examinations to all applicants by NRC examiners. These standards are not a substitute for the operator licensing regulations and are subject to revision or other internal operator examination licensing policy changes. As appropriate, these standards will be revised periodically to accommodate comments and reflect new information or experience

  7. Non-Power Reactor Operator Licensing Examiner Standards. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-06-01

    The Non-Power Reactor Operator Licensing Examiner Standards provide policy and guidance to NRC examiners and establish the procedures and practices for examining and licensing of applicants for NRC operator licenses pursuant to Part 55 of Title 10 of the Code of Federal Regulations (10 CFR 55). They are intended to assist NRC examiners and facility licensees to understand the examination process better and to provide for equitable and consistent administration of examinations to all applicants by NRC examiners. These standards are not a substitute for the operator licensing regulations and are subject to revision or other internal operator examination licensing policy changes. As appropriate, these standards will be revised periodically to accommodate comments and reflect new information or experience.

  8. Operating reactors licensing actions summary. Vol. 3, No. 6

    International Nuclear Information System (INIS)

    1983-07-01

    The operating reactors licensing actions summary is designed to provide the management of the Nuclear Regulatory Commission (NRC) with an overview of licensing actions dealing with operating power and nonpower reactors. These reports utilize data collected from the Division of Licensing in the Office of Nuclear Reactor Regulation and are prepared by the Office of Management and Program Analysis. This summary report is published primarily for internal NRC use in managing the operating reactors licensing actions program. Its content will change based on NRC management informational requirements

  9. Operating reactors licensing actions summary. Volume 5, No. 6

    International Nuclear Information System (INIS)

    1985-08-01

    The operating reactors licensing actions summary is designed to provide the management of the Nuclear Regulatory Commission (NRC) with an overview of licensing actions dealing with operating power and nonpower reactors. These reports utilize data collected from the Division of Licensing in the Office of Nuclear Reactor Regulation and are prepared by the Office of Resource Management. This summary report is published for internal NRC use in managing the Operating Reactors Licensing Actions Program. Its content will change based on NRC management informational requirements

  10. Licensed operating reactors

    International Nuclear Information System (INIS)

    Hartfield, R.A.

    1994-03-01

    The Nuclear Regulatory Commissions annual summary of licensed nuclear power reactor data is based primarily on the report of operating data submitted by licensees for each unit for the month of December, the year to date (in this case calendar year 1993) and cumulative data, usually for the date of commercial operation. The data is not independently verified, but various computer checks are made. The report is divided into two sections. The first contains summary highlights and the second contains data on each individual unit in commercial operation. Section 1 capacity and availability factors are simple arithmetic averages. Section 2 items in the cumulative column are generally as reported by the licensee and notes as to the use of weighted averages and starting dates other than commercial operation are provided

  11. Operating reactors licensing actions summary. Volume 5, No. 7

    International Nuclear Information System (INIS)

    1985-09-01

    The Operating Reactors Licensing Actions Summary is designed to provide the management of the Nuclear Regulatory Commission (NRC) with an overview of licensing actions dealing with operating power and nonpower reactors. These reports utilize data collected from the Division of Licensing in the Office of Nuclear Reactor Regulation and are prepared by the Office of Resource Management

  12. Operating reactors licensing actions summary. Vol.4, No. 4

    International Nuclear Information System (INIS)

    1984-06-01

    The operating reactors licensing actions summary is designed to provide the management of the Nuclear Regulatory Commission (NRC) with an overview of licensing actions dealing with operating power and nonpower reactors

  13. Licensed operating reactors

    International Nuclear Information System (INIS)

    1991-08-01

    The Nuclear Regulatory Commission's annual summary of licensed nuclear power reactor data is based primarily on the report of operating data submitted by licensees for each unit for the month of December because that report contains data for the month of December, the year to date (in this case calendar 1990) and cumulative data, usually from the date of commercial operation. The data is not independently verified, but various computer checks are made. The report is divided into two sections. The first contains summary highlights and the second contains data on each individual unit in commercial operation. Section 1 capacity and availability factors are simple arithmetic averages. Section 2 items in the cumulative column are generally as reported by the licensee and notes as to the use of weighted averages and starting dates other than commercial operation are provided

  14. Licensed operating reactors

    International Nuclear Information System (INIS)

    1990-01-01

    The US Nuclear Regulatory Commission's monthly LICENSED OPERATING REACTORS Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Information Resources Management, from the Headquarters Staff of NRC's Office of Inspection and Enforcement, from NRC's Regional Offices, and from utilities. Since all of the data concerning operation of the units is provided by the utility operators less than two weeks after the end of the month, necessary corrections to published information are shown on the ERRATA page. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

  15. Licensed operating reactors

    International Nuclear Information System (INIS)

    1989-06-01

    The US Nuclear Regulatory Commission's monthly LICENSED OPERATING REACTORS Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Information Resources Management, from the Headquarters Staff of NRC's Office of Inspection and Enforcement, from NRC's Regional Offices, and from utilities. Since all of the data concerning operation of the units are provided by the utility operators less than two weeks after the end of the month, necessary corrections to published information are shown on the ERRATA page. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

  16. Psychological characteristics of licensed nuclear power plant operators

    International Nuclear Information System (INIS)

    Sajwaj, T.; Ford, T.; McGee, R.K.

    1987-01-01

    The safe production of electricity by nuclear power plants has been the focus of considerable attention. Much of this concern has been focused on equipment and procedural issues, with less attention to the psychological factors that affect the operations staff of the plants, i.e., those individuals who are most directly responsible for a plant's operations. Stress and type A qualities would be significant for these individuals because of their relationships to job performance and health. Of equal significance would be work-related factors, such as job involvement and work pressure. Also of interest would be hostile tendencies because of the need for cooperation and communications among operations staff. Two variables could influence these psychological factors. One is the degree of responsibility for a plant's nuclear reactors. The individuals with the greatest responsibility are licensed by the US Nuclear Regulatory Commission (NRC). There are also individuals with less direct responsibilities who are not licensed. A second variable is the operating status of the plant, whether or not the plant is currently producing electricity. Relative to ensuring the safe operation of nuclear power plants, these data suggest a positive view of licensed operators. Of interest are the greater stress scores in the licensed staff of the operating plant in contrast with their peers in the nonoperating plant

  17. Licensed operating reactors

    International Nuclear Information System (INIS)

    1990-01-01

    The US Nuclear Regulatory Commission's monthly LICENSED OPERATING REACTORS Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Information Resources Management, from the Headquarters Staff of NRC's Office of Inspection and Enforcement, from NRC's Regional Offices, and from utilities. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

  18. Licensed operating reactors

    International Nuclear Information System (INIS)

    Hartfield, R.A.

    1990-03-01

    The US Nuclear Regulatory Commission's monthly Licensed Operating Reactors Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Information Resources Management, from the Headquarters Staff of NRC's Office of Inspection and Enforcement, from NRC's Regional Offices, and from utilities. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

  19. Licensed operating reactors

    International Nuclear Information System (INIS)

    1989-08-01

    The US Nuclear Regulatory Commission's monthly LICENSED OPERATING REACTORS Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Information Resources Management, from the Headquarters Staff of NRC's Office of Inspection and Enforcement, from NRC's Regional Offices, and from utilities. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

  20. Operating reactors licensing actions summary. Volume 5, Number 1

    International Nuclear Information System (INIS)

    1985-03-01

    This document is designed to provide the management of the Nuclear Regulatory Commission (NRC) with an overview of licensing actions dealing with operating power and nonpower reactors. These reports utilize data collected from the Division of Licensing in the Office of Nuclear Reactor Regulation and are prepared by the Office of Resource Management. This summary report is published primarily for internal NRC use in managing the operating reactors licensing actions program

  1. Licensing operators for commercial nuclear power plants

    International Nuclear Information System (INIS)

    Hannon, J.N.

    1988-01-01

    The human element in the operation of commercial nuclear power plants is of utmost importance. Not only must the operators be technically competent in the execution of numerous complicated tasks, they must be capable of working together as a team to diagnose dynamic plant conditions to ensure that their plants are operated safely. The significance of human interaction skills and crew communications has been demonstrated most vividly in TMI and Chernobyl. It follows that the NRC must retain its high standards for licensing operators. This paper discusses activities and initiatives being employed by the NRC to enhance the reliability of its licensing examinations, and to build a highly qualified examiner work force

  2. Selection/licensing of nuclear power plant operators

    International Nuclear Information System (INIS)

    Saari, L.M.

    1983-07-01

    An important aspect of nuclear power plant (NPP) safety is the reactor operator in the control room. The operators are the first individuals to deal with an emergency situation, and thus, effective performance on their part is essential for safe plant operations. Important issues pertaining to NPP reactor operators would fall within the personnel subsystem of our safety system analysis. While there are many potential aspects of the personnel subsystem, a key first step in this focus is the selection of individuals - attempting to choose individuals for the job of reactor operator who will safely perform the job. This requires a valid (job-related) selection process. Some background information on the Nuclear Regulatory Commission (NRC) licensing process used for selecting NPP reactor operators is briefly presented and a description of a research endeavor now underway at Battelle for developing a valid reactor operator licensing examination is included

  3. NPP long term operation in Spain - First application for license renewal

    International Nuclear Information System (INIS)

    Francia, L.; Gorrochategui, I.; Marcos, R.

    2007-01-01

    Full text: In the operation of the Spanish nuclear power plants (NPP), safety is always the prime consideration. Plant Life Management Programmes have been set up with the strategic objective to operate the NPPs as long as they are considered safe and reliable. The safety of each NPP is reviewed by the Spanish nuclear regulatory authority (CSN) under a continuous process. In addition, experience is gained from operating the plants and from exchanges with operators of similar units. Current Spanish regulatory framework for renewing NPP operating licenses requires performing a Periodic Safety Review (PSR) to be performed every 10 years and submitted when applying for a new renewal of the NPP operating license. A few years ago, CSN issued a document regarding the licensing requirements that nuclear power plants should meet in order to be granted with an operating license for long term operation (i.e, operation beyond the original plant design life, typically 40 years). Besides the traditional PSR requirements, specific requirements regarding to long term operation (LTO) include: - An Aging Management and Evaluation Program, including the identification and evaluation of Time Limited Aging Analysis (TLAA). - An updated Radiological Impact Study. - A review and assessment of regulation/standard applicability. Garona NPP (GE, BWR/3 design) operated by Spanish utility Nuclenor from 1971 has a current operating license up to 2009. A decision was made to apply for a new operating license, being Garona plant the first one in Spain to face with the new long term operation requirements. The paper will provide an overview of the methodology used in Spain to address and perform the required analyses to support the LTO application for the operating license renewal. In particular, focus will be paid on the project developed in Garona (2002-2006) whose result has been the first Spanish application for License Renewal for LTO. Also it will be reported the ongoing work necessary to

  4. 78 FR 29393 - University of Missouri-Columbia Facility Operating License No. R-103

    Science.gov (United States)

    2013-05-20

    ... Facility Operating License No. R-103 AGENCY: Nuclear Regulatory Commission. ACTION: License renewal... the renewal of Facility Operating License No. R-103 (``Application''), which currently authorizes the... application for the renewal of Facility Operating License No. R-103, which, currently authorizes the licensee...

  5. Personality Factors and Nuclear Power Plant Operators: Initial License Success

    Science.gov (United States)

    DeVita-Cochrane, Cynthia

    Commercial nuclear power utilities are under pressure to effectively recruit and retain licensed reactor operators in light of poor candidate training completion rates and recent candidate failures on the Nuclear Regulatory Commission (NRC) license exam. One candidate failure can cost a utility over $400,000, making the successful licensing of new operators a critical path to operational excellence. This study was designed to discover if the NEO-PI-3, a 5-factor measure of personality, could improve selection in nuclear utilities by identifying personality factors that predict license candidate success. Two large U.S. commercial nuclear power corporations provided potential participant contact information and candidate results on the 2014 NRC exam from their nuclear power units nation-wide. License candidates who participated (n = 75) completed the NEO-PI-3 personality test and results were compared to 3 outcomes on the NRC exam: written exam, simulated operating exam, and overall exam result. Significant correlations were found between several personality factors and both written and operating exam outcomes on the NRC exam. Further, a regression analysis indicated that personality factors, particularly Conscientiousness, predicted simulated operating exam scores. The results of this study may be used to support the use of the NEO-PI-3 to improve operator selection as an addition to the current selection protocol. Positive social change implications from this study include support for the use of a personality measure by utilities to improve their return-on-investment in candidates and by individual candidates to avoid career failures. The results of this study may also positively impact the public by supporting the safe and reliable operation of commercial nuclear power utilities in the United States.

  6. Nuclear safety requirements for operation licensing of Egyptian research reactors

    International Nuclear Information System (INIS)

    Ahmed, E.E.M.; Rahman, F.A.

    2000-01-01

    From the view of responsibility for health and nuclear safety, this work creates a framework for the application of nuclear regulatory rules to ensure safe operation for the sake of obtaining or maintaining operation licensing for nuclear research reactors. It has been performed according to the recommendations of the IAEA for research reactor safety regulations which clearly states that the scope of the application should include all research reactors being designed, constructed, commissioned, operated, modified or decommissioned. From that concept, the present work establishes a model structure and a computer logic program for a regulatory licensing system (RLS code). It applies both the regulatory inspection and enforcement regulatory rules on the different licensing process stages. The present established RLS code is then applied to the Egyptian Research Reactors, namely; the first ET-RR-1, which was constructed and still operating since 1961, and the second MPR research reactor (ET-RR-2) which is now in the preliminary operation stage. The results showed that for the ET-RR-1 reactor, all operational activities, including maintenance, in-service inspection, renewal, modification and experiments should meet the appropriate regulatory compliance action program. Also, the results showed that for the new MPR research reactor (ET-RR-2), all commissioning and operational stages should also meet the regulatory inspection and enforcement action program of the operational licensing safety requirements. (author)

  7. 78 FR 17450 - Notice of Issuance of Materials License Renewal, Operating License SUA-1341, Uranium One USA, Inc...

    Science.gov (United States)

    2013-03-21

    ... License Renewal, Operating License SUA-1341, Uranium One USA, Inc., Willow Creek Uranium In Situ Recovery.... SUA- 1341 to Uranium One USA, Inc. (Uranium One) for its Willow Creek Uranium In Situ Recovery (ISR... Commission License No. SUA-1341 For Uranium One USA, Inc., Irigaray and Christensen Ranch Projects (Willow...

  8. Operator licensing examination standards for power reactors. Interim revision 8

    International Nuclear Information System (INIS)

    1997-01-01

    These examination standards are intended to assist NRC examiners and facility licensees to better understand the processes associated with initial and requalification examinations. The standards also ensure the equitable and consistent administration of examinations for all applicants. These standards are for guidance purposes and are not a substitute for the operator licensing regulations (i.e., 10 CFR Part 55), and they are subject to revision or other changes in internal operator licensing policy. This interim revision permits facility licensees to prepare their initial operator licensing examinations on a voluntary basis pending an amendment to 10 CFR Part 55 that will require facility participation. The NRC intends to solicit comments on this revision during the rulemaking process and to issue a final Revision 8 in conjunction with the final rule

  9. Operating reactors licensing actions summary. Volume 5, No. 9

    International Nuclear Information System (INIS)

    1985-11-01

    This document is designed to provide the management of the Nuclear Regulatory Commission (NRC) with an overview of licensing actions dealing with operating power and nonpower reactors. These reports utilize data collected from the Division of Licensing in the Office of Nuclear Reactor Regulation and are prepared by the Office of Resource Management

  10. Operating reactors licensing actions summary. Volume 5, No. 8

    International Nuclear Information System (INIS)

    1985-10-01

    This summary is designed to provide the management of the Nuclear Regulatory Commission (NRC) with an overview of licensing actions dealing with operating power and nonpower reactors. These reports utilize data collected from the Division of Licensing in the Office of Nuclear Reactor Regulation and are prepared by the Office of Resource Management

  11. Operating reactors licensing actions summary. Volume 4, No. 9

    International Nuclear Information System (INIS)

    1984-11-01

    This document is designed to provide the management of the Nuclear Regulatory Commission (NRC) with an overview of licensing actions dealing with operating power and nonpower reactors. These reports utilize data collected from the division of licensing in the Office of Nuclear Reactor Regulation and are prepared by the Office of Resource Management

  12. Operating reactors licensing actions summary. Vol. 4, No. 2

    International Nuclear Information System (INIS)

    1984-04-01

    This summary is designed to provide the management of the Nuclear Regulatory Commission (NRC) with an overview of licensing actions dealing with operating power and nonpower reactors. These reports utilize data collected from the Division of Licensing in the Office of Nuclear Reactor Regulation and are prepared by the Office of Resource Management

  13. 47 CFR 13.201 - Qualifying for a commercial operator license or endorsement.

    Science.gov (United States)

    2010-10-01

    ... class of license or endorsement specified below must pass, or otherwise receive credit for, the... endorsement. 13.201 Section 13.201 Telecommunication FEDERAL COMMUNICATIONS COMMISSION GENERAL COMMERCIAL RADIO OPERATORS Examination System § 13.201 Qualifying for a commercial operator license or endorsement...

  14. 77 FR 26321 - Reed College, Reed Research Nuclear Reactor, Renewed Facility Operating License No. R-112

    Science.gov (United States)

    2012-05-03

    ... Nuclear Reactor, Renewed Facility Operating License No. R-112 AGENCY: Nuclear Regulatory Commission... Commission (NRC or the Commission) has issued renewed Facility Operating License No. R- 112, held by Reed... License No. R-112 will expire 20 years from its date of issuance. The renewed facility operating license...

  15. Renewal of operating licenses: the U.S. model

    International Nuclear Information System (INIS)

    Petroll, M.; Tveiten, B.

    2006-01-01

    Nearly half of the American nuclear power plants by now have been granted permits allowing them to be operated for twenty years more than originally planned. Procedures to this effect are under way for one quarter of U.S. nuclear power plants. For the operators, plant life extension, as a rule, is economically preferable to building new baseload plants or buying electricity from other sources. In the licensing procedures, the U.S. regulatory authority examines both environmental aspects and safety aspects of extended operation. The technical basis of assessment is the GALL report (Generic Aging Lessons Learnt) which by now has become the consolidated yardstick used by the authorities for safety assessment. In these procedures, the licensee is required to present updated design documents and, if applicable, extend or create from scratch programs of aging management. The case of the oldest nuclear power plant in operation in the United States is described to show the steps of an American licensing and administrative court procedure. Granting renewed operating permits began before President Bush's term and will continue independent of the change in government in 2008. (orig.)

  16. Comparison of licensing activities for operating plants designed by Babcock and Wilcox

    International Nuclear Information System (INIS)

    Thoma, J.O.

    1985-01-01

    This report provides a comparison of a number of licensing activities for the operating Babcock and Wilcox (B and W) plants with emphasis on Rancho Seco. The factors selected were a comparison of staff resources expended in FY84, active licensing action reviews, implementation of NUREG-0737 modifications, exemptions to regulations, SALP reports, enforcement actions, and Licensee Event Reports (LERs). The eight licensed operating plants examined are as follows: Arkansas Nuclear One Unit 1 (ANO-1), Crystal River Unit 3, Davis Besse, Oconee Units 1, 2, and 3, Rancho Seco, and Three Mile Island Unit 1 (TMI-1)

  17. 77 FR 68155 - The Armed Forces Radiobiology Research Institute TRIGA Reactor: Facility Operating License No. R-84

    Science.gov (United States)

    2012-11-15

    ... Research Institute TRIGA Reactor: Facility Operating License No. R-84 AGENCY: Nuclear Regulatory Commission... considering an application for the renewal of Facility Operating License No. R-84 (Application), which... the renewal of Facility Operating License No. R-84, which currently authorizes the licensee to operate...

  18. Analyses of operating license renewal for nuclear power plants in USA

    International Nuclear Information System (INIS)

    Chiba, Goro

    2007-01-01

    Although the originally-approved operating period for nuclear power plants in the U.S. is 40 years, the operating periods of many plants have been extended by license renewal for another 20 years. On the other hand, in Japan, plant life management is carried out assuming long-term operation of the plant, and the electric power company submits reports, such as aging technology assessment, and receives evaluation by the authorities. In this paper, the situation regarding plant life management was investigated and a Japan-U.S. comparison was made. As a result, differences were found in the procedure, the background, the manpower, the review period, etc. in Japan and the U.S. but there is no difference between Japan and the U.S. in aiming for a check of the integrity of components, assuming long-term operation for 60 years. Moreover, trend analysis using the overseas fault database of INSS examined the effect on the preservation activities of a license renewal. As a result, there is a tendency for license renewal not to be applied for in units in which the number of aging faults increases with the increase in elapsed years. The U.S. license renewal system was considered to be effective in plant life management, and suggested the validity of plant life management in Japan which is employing the equivalent system to the U.S. (author)

  19. The development of reactor operator license examination question bank

    International Nuclear Information System (INIS)

    Kim, In Hwan; Woo, S. M.; Kam, S. C.; Nam, K. J.; Lim, H. P.

    2001-12-01

    The number of NPP keeps increasing therefore there is more need of reactor operators. This trend requires the more efficiency in managing the license examination. Question bank system will help us to develop good quality examination materials and keep them in it. The ultimate purpose of the bank system is for selecting qualified reactor operators who are primarily responsible for the safety of reactor operation in NPP

  20. 76 FR 62868 - Washington State University; Notice of Issuance of Renewed Facility Operating License No. R-76

    Science.gov (United States)

    2011-10-11

    ...; Notice of Issuance of Renewed Facility Operating License No. R-76 AGENCY: Nuclear Regulatory Commission. ACTION: Notice of issuance of renewed facility operating license No. R- 76. ADDRESSES: You can access.... Nuclear Regulatory Commission (NRC, the Commission) has issued renewed Facility Operating License No. R-76...

  1. Decommissioning of the nuclear licensed facilities at the Fontenay aux Roses CEA Center; cleanup of nuclear licensed facility 57 and monitoring of operations and operating feedback

    International Nuclear Information System (INIS)

    Estivie, D.; Bohar, M.P.; Jeanjacques, M.; Binet, C.; Bremond, M.P.; Poyau, C.; Mandard, L.; Boissonneau, J.F.; Fouquereau, A.; Pichereau, E.

    2008-01-01

    This is a summary of the program for the decommissioning of all the CEA Licensed Nuclear Facilities in Fontenay aux Roses. The particularity of this center is now it is located in a built-up area. It is presented like example the operations to clean up the equipment of the Nuclear Licensed Facility 57 (NLF 57). Due to the diversity of the research and development work carried out on the reprocessing of spent fuel in it, this installation is emblematic of many of the technical and organizational issues liable to be encountered in the final closure of nuclear facilities. It was developed a method applied to establish the multi-annual budget, monitor the progress of operations and integrate, as work continues, the operating feedback. (author)

  2. Decentralization of operating reactor licensing reviews: NRR Pilot Program

    International Nuclear Information System (INIS)

    Hannon, J.N.

    1984-07-01

    This report, which has incorporated comments received from the Commission and ACRS, describes the program for decentralization of selected operating reactor licensing technical review activities. The 2-year pilot program will be reviewed to verify that safety is enhanced as anticipated by the incorporation of prescribed management techniques and application of resources. If the program fails to operate as designed, it will be terminated

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

    International Nuclear Information System (INIS)

    Xu Pingsheng

    2007-01-01

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

  4. 78 FR 46255 - Revisions to Environmental Review for Renewal of Nuclear Power Plant Operating Licenses; Correction

    Science.gov (United States)

    2013-07-31

    ... Environmental Review for Renewal of Nuclear Power Plant Operating Licenses; Correction AGENCY: Nuclear... nuclear power plant. Compliance with the provisions of the rule is required by June 20, 2014. This... environmental effect of renewing the operating license of a nuclear power plant. This document is necessary to...

  5. Guide to the selection, training, and licensing or certification of reprocessing plant operators. Volume I

    International Nuclear Information System (INIS)

    1976-06-01

    The Code of Federal Regulations, Title 10, Part 55, establishes procedures and criteria for the licensing of operators, including senior operators, in ''Production and Utilization Facilities'', which includes plants for reprocessing irradiated fuel. A training guide is presented which will facilitate the licensing of operators for nuclear reprocessing plants by offering generalized descriptions of the basic principles (theory) and the unit operations (mechanics) employed in reprocessing spent fuels. In the present volume, details about the portions of a training program that are of major interest to management are presented

  6. Guide to the selection, training, and licensing or certification of reprocessing plant operators. Volume I

    Energy Technology Data Exchange (ETDEWEB)

    None

    1976-06-01

    The Code of Federal Regulations, Title 10, Part 55, establishes procedures and criteria for the licensing of operators, including senior operators, in ''Production and Utilization Facilities'', which includes plants for reprocessing irradiated fuel. A training guide is presented which will facilitate the licensing of operators for nuclear reprocessing plants by offering generalized descriptions of the basic principles (theory) and the unit operations (mechanics) employed in reprocessing spent fuels. In the present volume, details about the portions of a training program that are of major interest to management are presented. (JSR)

  7. Recruitment training and licensing of operating personnel for nuclear power plants

    International Nuclear Information System (INIS)

    Palabrica, R.J.

    1979-01-01

    This article covers the step-by-step and most rigid recruitment, training, and licensing procedures undertaken in the selection for personnel involved in nuclear power plant operations. These procedures are true to all countries. However, for developing countries such as the Philippines, a bachelor's degree may be required as compared with the U.S. wherein a high school diploma is the minimum requirement. Because of the complexity of a nuclear facility, the work will require highly capable individuals with mature judgement who can render correct decisions even under highly stressed conditions. Thus during the selection and recruitment of applicants for the operator position, they are not only given aptitude tests but are also subjected to a series of psychological examintions. Once they are accepted, they are made to undergo a comprehensive and in-depth training to ensure that they will be capable of operating the nuclear power plant safely and effectively. Finally, those prospective operators have to pass licensing examinations in order to prove their competence and skills. Retraining programs follow after their training to maintain their skills. (RTD)

  8. 77 FR 7613 - Dow Chemical Company; Dow Chemical TRIGA Research Reactor; Facility Operating License No. R-108

    Science.gov (United States)

    2012-02-13

    ... NUCLEAR REGULATORY COMMISSION [Docket No. 50-264; NRC-2012-0026] Dow Chemical Company; Dow Chemical TRIGA Research Reactor; Facility Operating License No. R-108 AGENCY: Nuclear Regulatory Commission... Facility Operating License No. R-108 (``Application''), which currently authorizes the Dow Chemical Company...

  9. Assessment of specialized educational programs for licensed nuclear reactor operators

    International Nuclear Information System (INIS)

    Melber, B.D.; Saari, L.M.; White, A.S.; Geisendorfer, C.L.; Huenefeld, J.C.

    1986-02-01

    This report assesses the job-relatedness of specialized educational programs for licensed nuclear reactor operators. The approach used involved systematically comparing the curriculum of specialized educational programs for college credit, to academic knowledge identified as necessary for carrying out the jobs of licenses reactor operators. A sample of eight programs, including A.S. degree, B.S. degree, and coursework programs were studied. Subject matter experts in the field of nuclear operations curriculum and training determined the extent to which individual program curricula covered the identified job-related academic knowledge. The major conclusions of the report are: There is a great deal of variation among individual programs, ranging from coverage of 15% to 65% of the job-related academic knowledge. Four schools cover at least half, and four schools cover less than one-third of this knowledge content; There is no systematic difference in the job-relatedness of the different types of specialized educational programs, A.S. degree, B.S. degree, and coursework; and Traditional B.S. degree programs in nuclear engineering cover as much job-related knowledge (about one-half of this knowledge content) as most of the specialized educational programs

  10. Ignalina plant licensing process, international co-operation and assistance

    International Nuclear Information System (INIS)

    Bystedt, P.

    1999-01-01

    The challenge for Lithuania as a country with regained independence was to perform a licensing review in a way never done before in the country and in a time schedule that was extremely short. The work included establishing of the licensing base, strengthening the regulatory authority and organising the technical support, establish and implement a safety improvement program, production of the safety case and review of the safety case, and to derive a conclusion regarding whether to issue a licence or not. This was to be done together with other tasks, such as implementation of modifications included in the safety improvement programme at Ignalina, implementation of a new storage for spent fuel and, most important of all, to manage the operational safety at the plant. The achievements are impressive seen in view of the point of start and in view of the time and resources that have been available. Lithuania has put forward a unique safety documentation of an RBMK reactor and presented an in-depth safety evaluation in full openness to Western experts, giving the unique possibility to compare the safety of the Ignalina reactors to Western standards. The co-operation that has been established between Lithuania and Western experts through different assistance programmes is of outmost value, for all involved parties. Co-operation should continue as one element of the challenges for the future

  11. The licensing procedure for construction and operation of nuclear power plants

    International Nuclear Information System (INIS)

    Salvatore, J.E.L.

    1980-03-01

    The licensing procedure for the construction and operation of the nuclear power plants in Brazil is analysed, according to the International Atomic Energy Agency orientation. The risks related to the nuclear energy is also emphasized. (A.L.) [pt

  12. 78 FR 37281 - Revisions to Environmental Review for Renewal of Nuclear Power Plant Operating Licenses

    Science.gov (United States)

    2013-06-20

    ... factors: (1) License renewal will involve nuclear power plants for which the environmental impacts of...) Changes in the environment around nuclear power plants are gradual and predictable. The 1996 GEIS improved... environmental impacts that may occur from renewing commercial nuclear power plant operating licenses; (2...

  13. License renewal

    International Nuclear Information System (INIS)

    Newberry, S.

    1993-01-01

    This article gives an overview of the process of license renewal for nuclear power plants. It explains what is meant by license renewal, the significance of license renewal, and goes over key elements involved in the process of license renewal. Those key elements are NRC requirements embodied in 10 CFR Part 54 (Reactor Safety) and 10 CFR Part 51 (Environmental Issues). In addition Industry Reports must be developed and reviewed. License renewal is essentially the process of applying for a 20 year extension to the original 40 year operating license granted for the plant. This is a very long term process, which involves a lot of preparation, and compliance with regulatory rules and guidelines. In general it is a process which is expected to begin when plants reach an operating lifetime of 20 years. It has provisions for allowing the public to become involved in the review process

  14. Licensing Support Experience of the BN-600 Operation

    International Nuclear Information System (INIS)

    Khrennikov, N.; Sintsov, A.

    2013-01-01

    License procedure - Main principle: • All works, including fatigue tests of new types of fuel, are carried out at the unit 3 Beloyarsk nuclear power plants with the BN-600 reactor with the justification of the regulatory body. • Justification procedure is standard for all power units and independent from the reactor types. • The regulatory body and independent experts or technical support organizations, which can be involved in this work by the regulatory body, review SAR, operational manuals and other operator documents. • Safety requirements (i.e. Federal rules and codes). The project and design documents shall meet safety requirements. • The technical and organizational measures for safety guarantee shall meet well-known results of the research investigations or shall be experimental validate

  15. WIPP - Pre-Licensing and Operations: Developer and Regulator Perspectives

    International Nuclear Information System (INIS)

    Peake, Tom; Patterson, R.

    2014-01-01

    The Waste Isolation Pilot Plant (WIPP) is a disposal system for defense-related transuranic (TRU) radioactive waste. Developed by the Department of Energy (DOE), WIPP is located in Southeastern New Mexico: radioactive waste is disposed of 2,150 feet underground in an ancient layer of salt with a total capacity of 6.2 million cubic feet of waste. Congress authorized the development and construction of WIPP in 1980 for the express purpose of providing a research and development facility to demonstrate the safe disposal of radioactive wastes resulting from the defense activities and programs of the United States. This paper makes a historical review of the site development, site operations (waste disposal operations started in 1999), communications between US EPA and DOE, the chronology of pre-licensing and pre-operations, the operational phase and the regulatory challenges, and the lessons learned after 12 years of operations

  16. Technological evaluation for the extension of the operation license to the nuclear power plant of Laguna Verde

    International Nuclear Information System (INIS)

    Arganis J, C. R.; Medina A, A. L.

    2010-01-01

    At the present time one of the tendencies in the nuclear industry is the renovation of operation licenses of the nuclear power plants, with the purpose of prolonging their operation 20 years more than the time settled down in their original license, which is of 30 years for the case of the nuclear power plant of Laguna Verde. This allows the electric power generation for a major period of time and to a relatively low price, giving this way a bigger competitiveness to the power stations of nuclear power. However, to request the license extension of the nuclear power plant requires to get ready the documentation and necessary studies for: to maintain a high level of security, to optimize the operation, maintenance and service life of the structures, systems and components, to maintain an acceptable level of performance, to maximize the recovery of the investment about the service of the nuclear power plant and to preserve the sure conditions for a major operation period at the license time. This paper describes the studies conducted by the Materials Technology Department of the Instituto Nacional de Investigaciones Nucleares (ININ) to substantiate the required documentation for obtaining the extension of operating license of the nuclear power plant. These studies are focused mainly in the reactor pressure vessels of both units, as well as in the deposit of noble metals and the influence of the sludges (crud s) in this deposit. (Author)

  17. Licensing process in Finland

    International Nuclear Information System (INIS)

    Tiippana, Petteri

    2011-01-01

    In accordance with the Nuclear Energy Act, the use of nuclear energy constitutes operations subject to license. The licensing process and conditions for granting a license is defined in the legislation. The licenses are applied from and granted by the Government. This paper discusses briefly the licensing process in Finland and also the roles and responsibilities of main stakeholders in licensing. Licensing of a nuclear power plant in Finland has three steps. The first step is the Decision in Principle (DiP). Goal of DiP is to decide whether using nuclear power is for the overall good for the Finnish society. The second step is Construction License (CL) and the goal of CL phase is to determine whether the design of the proposed plant is safe and that the participating organisations are capable of constructing the plant to meet safety goals. The third step is the Operating License (OL) and the goal of the OL phase is to determine whether the plant operates safely and licensee is capable to operate the plant safely. Main stakeholders in the licensing process in Finland are the utility (licensee) interested in using nuclear power in Finland, Ministry of Employment and the Economy (MEE), Government, Parliament, STUK, the municipality siting the plant and the general public. Government grants all licenses, and Parliament has to ratify Government's Decision in Principle. STUK has to assess the safety of the license applications in each step and give statement to the Ministry. Municipality has to agree to site the plant. Both STUK and the municipality have a veto right in the licensing process

  18. Selection, training, qualification and licensing of Three Mile Island reactor operating personnel

    International Nuclear Information System (INIS)

    Eytchison, R.M.

    1980-01-01

    The various programs which were intended to staff Three Mile Island with competent, trained operators and supervisors are reviewed. The analysis includes a review of the regulations concerning operator training and licensing, and describes how the requirements were implemented by the NRC, Metropolitan Edison Company, and Babcock and Wilcox Company. Finally the programs conducted by these three organisations are evaluated. (U.K.)

  19. The Monticello license renewal project

    International Nuclear Information System (INIS)

    Clauss, J.M.; Harrison, D.L.; Pickens, T.A.

    1993-01-01

    Today, 111 nuclear power plants provide over 20 percent of the electrical energy generated in the United States. The operating license of the oldest operating plant will expire in 2003, one-third of the existing operating licenses will expire by 2010 and the newest plant's operating license will expire in 2033. The National Energy Strategy (NES) prepared by the Department of Energy (DOE) assumes that 70 percent of the current operating plants will continue to operate beyond their current license expiration. Power from current operating plants can assist in ensuring an adequate, diverse, and environmentally acceptable energy supply for economic growth and improved U.S. competitiveness. In order to preserve this energy resource, three major tasks must be successfully completed: (1) establishment of regulations, technical standards, and procedures for the preparation and review of License Renewal Applications (LRAs); (2) development of technical criteria and bases for monitoring, refurbishing or replacing plant equipment; and (3) demonstration of the regulatory process by a plant obtaining a renewed license. Since 1986, the DOE has been working with the nuclear industry and the Nuclear Regulatory Commission (NRC) to establish and demonstrate the option to extend the life of a nuclear power plant by renewing the operating license. The Monticello Lead Plant demonstration project was initiated in September 1988, following the Pilot Plant studies. This paper is primarily focused on the status and insights gained from the Northern States Power Company (NSP) Monticello Lead Plant demonstration project. The following information is included: (1) Current Status - Monticello License Renewal Application; (2) Economic Analysis; (3) License Renewal Regulatory Uncertainty Issues; (4) Key Decisions; (5) Management Structure; (6) Technical and Licensing Perspective; (7) NRC Interactions; (8) Summary

  20. Answers to questions at public meetings regarding implementation of Title 10, Code of Federal Regulations, Part 55 on operators' licenses

    International Nuclear Information System (INIS)

    1987-11-01

    This document presents questions and answers based on the transcripts of four public meetings (and from written questions submitted after the meetings) conducted from April 9 to April 20, 1987 by the staff of the US Nuclear Regulatory Commission. The meetings discussed implementation of the Commission's final rule governing Operators' Licenses and Conforming Amendments (10 CFR Parts 55 and 50). The rule became effective May 26, 1987 and is intended to clarify the regulations for issuing licenses to operators and senior operators; revise the requirements and scope of written examinations and operating tests for operators and senior operators, require a simulation facility; clarify procedures for administering requalification examinations; and describe the form and content for operator license applications

  1. 78 FR 40519 - Cooper Nuclear Station; Application and Amendment to Facility Operating License Involving...

    Science.gov (United States)

    2013-07-05

    ... NUCLEAR REGULATORY COMMISSION [Docket No. 50-298; NRC-2013-0139] Cooper Nuclear Station; Application and Amendment to Facility Operating License Involving Proposed No Significant Hazards..., issued to Nebraska Public Power District (the licensee), for operation of the Cooper Nuclear Station (CNS...

  2. 47 CFR 90.473 - Operation of internal transmitter control systems through licensed fixed control points.

    Science.gov (United States)

    2010-10-01

    ... 47 Telecommunication 5 2010-10-01 2010-10-01 false Operation of internal transmitter control... Transmitter Control Internal Transmitter Control Systems § 90.473 Operation of internal transmitter control systems through licensed fixed control points. An internal transmitter control system may be operated...

  3. Safety evaluation report related to the full-term operating license for San Onofre Nuclear Generating Station, Unit 1 (Docket No. 50-206)

    International Nuclear Information System (INIS)

    1991-07-01

    The safety evaluation report for the full-term operating license application filed by the Southern California Edison Company and the San Diego Gas and Electric Company has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located in San Diego County, California. The staff has evaluated the issues related to the conversion of the provisional operating license to a full-term operating license and concluded that the facility can continue to be operated without endangering the health and safety of the public following the license conversion. 43 refs., 3 figs., 3 tabs

  4. The intelligent customer: considerations around build-own-operate business and licensing models for small modular reactors in Canada

    International Nuclear Information System (INIS)

    Jones, K.

    2014-01-01

    An organization planning a proposal for a build-own-operate business model needs to address expanded licensee responsibilities under this model, associated regulatory impacts and how this affects their role as an 'intelligent customer'. This is particularly important for cases where builder-owner-operators plan to manufacture factory-fuelled designs and ship them to a site for installation and operation. The primary responsibility for safe conduct of licensed activities rests with the licensee. A build-own-operate model expands the scope of licensed activities to include design, manufacturing, transport, construction, and operation. The licensee must be able to demonstrate they are qualified to conduct all licensed activities including sufficient competent resources within the licensee's organization to oversee('Intelligent Customer') any work it commissions externally and the subsequent flow down through of the supply chain. This paper examines aspects that organizations need to assess the suitability of approaches that it may take to maintain in-house expertise for the control and oversight of licensed activities at all times. It considers the approach to identification of: core capabilities the licensee would need to understand its safety case under a build-own-operate model to manage licensed activities in accordance with requirements under the Nuclear Safety and Control Acta licensee's 'intelligent customer' capabilities in particular around understanding, specifying, overseeing and accepting work undertaken on its behalf by contractors. While this paper is focused on small modular reactors, being an intelligent customer applies to large commercial or research reactors equally; the size of reactor is immaterial.

  5. The intelligent customer: considerations around build-own-operate business and licensing models for small modular reactors in Canada

    Energy Technology Data Exchange (ETDEWEB)

    Jones, K., E-mail: kenneth.jones@cnsc-ccsn.gc.ca [Canadian Nuclear Safety Commission, Ottawa, Ontario (Canada)

    2014-07-01

    An organization planning a proposal for a build-own-operate business model needs to address expanded licensee responsibilities under this model, associated regulatory impacts and how this affects their role as an 'intelligent customer'. This is particularly important for cases where builder-owner-operators plan to manufacture factory-fuelled designs and ship them to a site for installation and operation. The primary responsibility for safe conduct of licensed activities rests with the licensee. A build-own-operate model expands the scope of licensed activities to include design, manufacturing, transport, construction, and operation. The licensee must be able to demonstrate they are qualified to conduct all licensed activities including sufficient competent resources within the licensee's organization to oversee('Intelligent Customer') any work it commissions externally and the subsequent flow down through of the supply chain. This paper examines aspects that organizations need to assess the suitability of approaches that it may take to maintain in-house expertise for the control and oversight of licensed activities at all times. It considers the approach to identification of: core capabilities the licensee would need to understand its safety case under a build-own-operate model to manage licensed activities in accordance with requirements under the Nuclear Safety and Control Acta licensee's 'intelligent customer' capabilities in particular around understanding, specifying, overseeing and accepting work undertaken on its behalf by contractors. While this paper is focused on small modular reactors, being an intelligent customer applies to large commercial or research reactors equally; the size of reactor is immaterial.

  6. Social license to operate: case from brazilian mining industry

    Science.gov (United States)

    Santiago, Ana Lúcia F.; Demajorovic, Jacques; Aledo, Antonio

    2015-04-01

    The approach of the Social License to Operate (SLO) emerges as an important element in academic discussions and business practices related to extractive industries. It appears that in productive activities with great potential to produce economic, social and environmental impacts, conventional approaches based on legal compliance no longer sufficient to legitimize the actions of companies and engagement stakeholders. Studies highlight the need of mining activities receiving a SLO "issued" by companies stakeholders, including society, government, non-governmental organizations, media and communities. However, local communities appears as major stakeholders in governance arrangements, by virtue of its proximity to extractive areas and ability to affect the company's results. Stakeholders with unmet expectations can generate conflicts and risks to the company, the knowledge of these expectations and an awareness of company managers of the importance of Social License to Operate (SLO), can generate strategies and mitigating actions to prevent and or minimize possible conflicts. The concept of SLO arises in engineering extractive industry, when you need to respond to social challenges, beyond the usual environmental challenges, technological and management. According to Franks and Cohen (2012) there is a tendency of engineering sectors, sustainability, environmental, safety and especially in risk mappings, treat the technological issues in a neutral manner, separating the technological research projects of social influences. I want to contribute to the advancement of the debate on stakeholder engagement and adopting as focus on the company's relationship with the community, the aim of this study was to understand how a social project held by one of the largest mining companies in Brazil contributed to the process of SLO. This methodological procedure adopted was a qualitative, descriptive, and exploratory interviews with the communities located in rural areas of direct

  7. License renewal process

    International Nuclear Information System (INIS)

    Fable, D.; Prah, M.; Vrankic, K.; Lebegner, J.

    2004-01-01

    The purpose of this paper is to provide information about license renewal process, as defined by Nuclear Regulatory Commission (NRC). The Atomic Energy Act and NRC regulations limit commercial power reactor licenses to an initial 40 years but also permit such licenses to be renewed. This original 40-year term for reactor licenses was based on economic and antitrust considerations not on limitations of nuclear technology. Due to this selected time period; however, some structures and components may have been engineered on the basis of an expected 40-year service life. The NRC has established a timely license renewal process and clear requirements codified in 10 CFR Part 51 and 10 CFR Part 54, that are needed to assure safe plant operation for extended plant life. The timely renewal of licenses for an additional 20 years, where appropriate to renew them, may be important to ensuring an adequate energy supply during the first half of the 21st Century. License renewal rests on the determination that currently operating plants continue to maintain adequate levels of safety, and over the plant's life, this level has been enhanced through maintenance of the licensing bases, with appropriate adjustments to address new information from industry operating experience. Additionally, NRC activities have provided ongoing assurance that the licensing bases will continue to provide an acceptable level of safety. This paper provides additional discussion of license renewal costs, as one of key elements in evaluation of license renewal justifiability. Including structure of costs, approximately value and two different approaches, conservative and typical. Current status and position of Nuclear Power Plant Krsko, related to license renewal process, will be briefly presented in this paper. NPP Krsko is designed based on NRC Regulations, so requirements from 10 CFR 51, and 10 CFR 54, are applicable to NPP Krsko, as well. Finally, this paper will give an overview of current status of

  8. Comparison of the inspection practices in relation to the control room operator and shift supervisor licenses

    International Nuclear Information System (INIS)

    Aro, Ilari; Koizumi, Hiroyoshi; Manzella, Pietro

    1998-01-01

    The CNRA believes that safety inspections are a major element in the regulatory authority's efforts to ensure the safe operation of nuclear facilities. Considering the importance of these issues, the Committee has established a special Working Group on Inspection Practices (WGIP). The purpose of WGIP, is to facilitate the exchange of information and experience related to regulatory safety inspections between CNRA Member countries In 1996, members of WGIP discussed various ways in which regulatory inspectors look at and evaluate how licenses are given to control room operators and shift supervisors in the Member countries. As a result of these discussions it was proposed to put together a short comparison report on this issue. The CNRA approved work on this at its annual meeting that year. This CNRA/WGIP study concentrates on the regulatory inspection of control room operator competence and authorisation. As noted in the text, fourteen Member countries supplied input by responding to the questionnaire. This report presents a comparison of inspection practices in participating OECD countries relating to control room operator and shift supervisor licenses. The report has been derived from answers to a questionnaire on the basis of guidance given in Appendix 1.1 with the detailed answers being given in Appendix 1. Key questions for this comparison were 'What are the regulatory or licensee requirements for holding and up-keeping a license or authorisation' and 'How does the regulatory body inspect the training and competence of shift teams and individual operators'. The main conclusion from the comparison is that the general practice within the participating countries for ensuring the competence of operators is broadly similar although regulatory practices differ markedly. For example, the regulatory bodies in some countries are actively involved in the examination and licensing process of individual operators whereas other regulatory bodies

  9. State Licenses & Permits

    Data.gov (United States)

    Small Business Administration — Starting a business? Confused about whether you need a business license or permit? Virtually every business needs some form of license or permit to operate legally....

  10. Licensed operating reactors status summary report data as of January 31, 1989

    International Nuclear Information System (INIS)

    Schwartz, I.

    1989-03-01

    The US Nuclear Regulatory Commission's monthly LICENSED OPERATING REACTORS Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information, such as spent fuel storage capability, reactor years of experience, and non-power reactors in the United States

  11. Licensed operating reactors: status summary report, data as of May 31, 1982

    International Nuclear Information System (INIS)

    1982-06-01

    The US Nuclear Regulatory Commission's monthly LICENSED OPERATING REACTORS Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

  12. Licensed operating reactors: Status summary report, data as of 02-28-89

    International Nuclear Information System (INIS)

    1989-03-01

    The US Nuclear Regulatory Commission's monthly Licensed Operating Reactor Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

  13. Licensed operating reactors status summary report, data as of December 31, 1988

    International Nuclear Information System (INIS)

    1989-02-01

    The US Nuclear Regulatory Commission's monthly LICENSED OPERATING REACTORS Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

  14. Licensed operating reactors. Status summary report data as of October 31, 1982

    International Nuclear Information System (INIS)

    1982-11-01

    The US Nuclear Regulatory Commission's monthly LICENSED OPERATING REACTORS Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

  15. Licensed operating reactors. Status summary report, data as of 8-31-82

    International Nuclear Information System (INIS)

    1982-09-01

    The US Nuclear Regulatory Commission's monthly LICENSED OPERATING REACTORS Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

  16. Licensed operating reactors: Status summary report data as of 9-30-86

    International Nuclear Information System (INIS)

    1987-03-01

    The US Nuclear Regulatory Commission's monthly Licensed Operating Reactors Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices. IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

  17. Licensed operating reactors: Status summary report, data as of 11-30-88

    International Nuclear Information System (INIS)

    1989-01-01

    The US Nuclear Regulatory Commission's monthly LICENSED OPERATING REACTORS Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information, such as spent fuel storage capability, reactor years of experience, and non-power reactors in the United States

  18. Licensed operating reactors: Status summary report, data as of 11-30-86

    International Nuclear Information System (INIS)

    1987-06-01

    The operating units status report - licensed operating reactors provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Administration and Resources Management from the Headquarters staff of NRC's Office of Enforcement (OE), from NRC's Regional Offices, OE Headquarters and the utilities; and an appendix for miscellaneous information such as spent fuel storage capability, reactor-years of experience and non-power reactors in the US. It is hoped the report is helpful to all agencies and individuals interested in maintaining an awareness of the US energy situation as a whole

  19. Licensed operating reactors: Status summary report, Data as of 08-31-86

    International Nuclear Information System (INIS)

    1987-03-01

    The US Nuclear Regulatory Commission's monthly LICENSED OPERATING REACTORS Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

  20. Licensing of nuclear and radioactive installations in Peru

    International Nuclear Information System (INIS)

    Medina Gironzini, E.

    1987-01-01

    In Peru, the Regulation for Ionizing Radiation Sources is applied, which establishes the norms and procedures to follow in the nuclear and radioactive installations of the country in order to assure their correct operation as concerns to the nuclear safety and radiological protection, allowing the emission of the respective licenses. As for the nuclear facilities, this authorization includes the Previous License, the Construction License and the Operation License (provisional and definitive) and for radioactive facilities and equipment generating ionizing radiations: the Construction License and the Operation License. The personnel also require a license that can be an operator license (as for nuclear reactors) or a supervisor license (for nuclear and radioactive facilities). In spite of the above mentioned regulation and its long enforcement period, less than 10% of radioactive facilities in this country are licensed, due to different problems which will be solved in the medium term. (Author)

  1. License renewal in the United States

    International Nuclear Information System (INIS)

    Brons, Jack

    2002-01-01

    Full text: Nuclear plants in the United States are licensed for 40 years, a length specified in the Atomic Energy Act of 1954, which laid out much of the regulatory basis for the commercial nuclear industry. The Act, however, made provision for license renewal. The original 40-year license period was chosen arbitrarily by the U.S. Congress because it was the typical period over which utilities recovered their investment in electricity generating plants. Nuclear plants, however, are subject to a rigorous program of Nuclear Regulatory Commission oversight, maintenance and equipment replacement. In effect, they must be in the same operating condition on the last day of their licenses as they were on the first. As the industry matured, it became apparent that there was no physical limitation on the continued operation of nuclear plants past 40 years. The industry turned its attention toward license renewal. When the issue was first raised, the NRC considered stringent process equivalent to seeking a new operating license for each plant. The complexity, length and cost of the process made it unlikely that many nuclear plants would seek license renewal. The nuclear industry worked successfully with NRC on the application of generic principles to license renewal, however, and in 1995, the NRC issued an efficient, tightly-focused rule that made license renewal a safe, viable option. To extend the operating license for a reactor, a company must demonstrate to the NRC that aging effects will be adequately managed during the renewal terms, thus ensuring equipment functionality. The rule allows licensees to apply for extensions of up to 20 years. The first license renewal application was filed in 1998 by the owner of the two-unit Calvert Cliffs plant. Shortly thereafter, an application was filed for the three-unit Oconee Nuclear Station. The NRC renewed the licenses for all five units in 2000, and since then, five more licenses have been renewed. The NRC has received 37

  2. Licensing and Operations of the Clive, Utah Low-Level Containerized Radioactive Waste Disposal Facility- A Continuation of Excellence

    International Nuclear Information System (INIS)

    Ledoux, M. R.; Cade, M. S.

    2002-01-01

    Envirocare's Containerized Waste Facility (CWF) is the first commercial low-level radioactive waste disposal facility to be licensed in the 21st century and the first new site to be opened and operated since the late 1970's. The licensing of this facility has been the culmination of over a decade's effort by Envirocare of Utah at their Clive, Utah site. With the authorization to receive and dispose of higher activity containerized Class A low-level radioactive waste (LLRW), this facility has provided critical access to disposal for the nuclear power industry, as well as the related research and medical communities. This paper chronicles the licensing history and operational efforts designed to address the disposal of containerized LLRW in accordance with state and federal regulations

  3. Long Term Operation R and D to Investigate the Technical Basis for Life Extension and License Renewal Decisions

    International Nuclear Information System (INIS)

    Gaertner, John

    2012-01-01

    Establishing an improved technical basis for long term operation of existing plants is a nuclear industry priority. The Electric Power Research Institute (EPRI) has responded with a comprehensive Long Term Operation (LTO) Program addressing this need for existing nuclear power plants world-wide. The program supports both the business decisions necessary to achieve high performance operation and the licensing requirements for operation beyond 60 years. The program selects its R and D priorities in a structured and objective way with much industry input to provide useful results for decisions in the 2014 to 2019 time frame. The program is highly collaborative with U.S. Department of Energy (DOE) and with EPRI-member utilities. The R and D portfolio includes materials aging (metals, concrete, and cables), modernization of information and control technology, enhanced safety analysis, advanced fuel design, demonstration plant activities, life cycle management, and identification of aging management program need for subsequent license renewal. The program has focussed stakeholders world-wide on the technical issues of long term operation, and it is on-track to provide practical results for life extension and license renewal decisions. (author)

  4. Licensing and Operations of the Clive, Utah Low-Level Containerized Radioactive Waste Disposal Facility- A Continuation of Excellence

    Energy Technology Data Exchange (ETDEWEB)

    Ledoux, M. R.; Cade, M. S.

    2002-02-25

    Envirocare's Containerized Waste Facility (CWF) is the first commercial low-level radioactive waste disposal facility to be licensed in the 21st century and the first new site to be opened and operated since the late 1970's. The licensing of this facility has been the culmination of over a decade's effort by Envirocare of Utah at their Clive, Utah site. With the authorization to receive and dispose of higher activity containerized Class A low-level radioactive waste (LLRW), this facility has provided critical access to disposal for the nuclear power industry, as well as the related research and medical communities. This paper chronicles the licensing history and operational efforts designed to address the disposal of containerized LLRW in accordance with state and federal regulations.

  5. Contestable Licensing

    OpenAIRE

    Zvika Neeman; Gerhard O. Orosel

    2000-01-01

    We analyze a model of repeated franchise bidding for natural monopoly with contestable licensing - a franchisee halds an (exclusive) license to operate a franchise until another rm offers to pay more for it. In a world where quality is observable but not veri able, the simple regulatory scheme we describe combines market-like incentives with regulatory oversight to generate efficient outcomes.

  6. 78 FR 5840 - Notice of License Termination for University of Illinois Advanced TRIGA Reactor, License No. R-115

    Science.gov (United States)

    2013-01-28

    ... University of Illinois Advanced TRIGA Reactor, License No. R-115 The U.S. Nuclear Regulatory Commission (NRC) is noticing the termination of Facility Operating License No. R-115, for the University of Illinois... Operating License No. R-115 is terminated. The above referenced documents may be examined, and/or copied for...

  7. Licensed operating reactors. Status summary report data as of December 31, 1993

    Energy Technology Data Exchange (ETDEWEB)

    Hartfield, R.A.

    1994-03-01

    The Nuclear Regulatory Commissions annual summary of licensed nuclear power reactor data is based primarily on the report of operating data submitted by licensees for each unit for the month of December, the year to date (in this case calendar year 1993) and cumulative data, usually for the date of commercial operation. The data is not independently verified, but various computer checks are made. The report is divided into two sections. The first contains summary highlights and the second contains data on each individual unit in commercial operation. Section 1 capacity and availability factors are simple arithmetic averages. Section 2 items in the cumulative column are generally as reported by the licensee and notes as to the use of weighted averages and starting dates other than commercial operation are provided.

  8. NUPLEX Licensing Subcommittee

    International Nuclear Information System (INIS)

    Edwards, D.W.; Allen, S.R.

    1988-01-01

    The NUPLEX Licensing Subcommittee was organized to seek a formal license renewal mechanism that institutionalizes the current licensing basis and consequent level of safety of a plant as the legitimate standard for acceptance and approval of an application for extended operation. Along with defining the most workable approach to and scope of review for license renewal, this paper explains the reasons why a regulatory framework is needed by the early 1990s. The initial results of development work on two key issues, licensing criteria and hearing process, are also presented. at this point six potential license renewal criteria have emerged: evaluation of existing monitoring/maintenance programs, revalidation of current licensing basis, conformance to special regulations, evaluation to a safety goal, plant performance history, and environmental assessment. The work on a hearing process has led to the development of two models for future consideration: hybrid legislative and hybrid adjudicatory

  9. Role of cognitive models of operators in the design, operation and licensing of nuclear power plants

    International Nuclear Information System (INIS)

    Rasmussen, J.

    1982-01-01

    Cognitive models of the behavior of nuclear power plant operators - that is, models developed in terms of human properties rather than external task characteristics - are assuming increasingly important roles in plant design, operation and licensing. This is partly due to an increased concern for human decision making during unfamiliar plant conditions, and partly due to problems that arise when modern information technology is used to support operators in complex situations. Some of the problems identified during work on interface design and risk analysis are described. First, the question of categories of models is raised. Next, the use of cognitive models for system design is discussed. The use of the available cognitive models for more effective operator training is also advocated. The need for using cognitive models in risk analysis is also emphasized. Finally, the sources of human performance data, that is, event reports, incident analysis, experiments, and training simulators are mentioned, and the need for a consistent framework for data analysis based on cognitive models is discussed

  10. 75 FR 61521 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No...

    Science.gov (United States)

    2010-10-05

    ... revises the charcoal testing criteria in Technical Specification 5.5.9, ``Ventilation Filter Testing... staffing from two to four, allow in-plant protective actions to be performed by personnel assigned to other functions, and replace a Mechanical Maintenance person with a Non-Licensed Operator. Date of issuance...

  11. 76 FR 39136 - Applications and Amendments to Facility Operating Licenses Involving Proposed No Significant...

    Science.gov (United States)

    2011-07-05

    ... the Commission's ``Rules of Practice for Domestic Licensing Proceedings'' in 10 CFR part 2. Interested... Generator (SG) Program,'' to exclude a portion of the tubes below the top of the steam generator tubesheet from periodic steam generator tube inspections during Refueling Outage 14 and the subsequent operating...

  12. 76 FR 73727 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No...

    Science.gov (United States)

    2011-11-29

    ..., Donald C. Cook Nuclear Plant, Unit 2 (DCCNP-2), Berrien County, Michigan; Date of amendment request... Counsel, Indiana Michigan Power Company, One Cook Place, Bridgman, MI 49106. NRC Acting Branch Chief: Thomas J. Wengert. Notice of Issuance of Amendments to Facility Operating Licenses During the period...

  13. NPP License Renewal and Aging Management: Revised Guidance

    International Nuclear Information System (INIS)

    Hull, A.B.; Hiser, A.L.; Lindo-Talin, S.E.

    2012-01-01

    Based on the Atomic Energy Act, the NRC issues licenses for commercial power reactors to operate for up to 40 years and allows these licenses to be renewed for up to another 20 years. NRC has approved license renewal for well over 50% of U.S. located reactors originally licensed to operate for 40 years. Of these 104 reactors (69 PWRs, 35 BWRs), the NRC has issued renewed licenses for 71 units and is currently reviewing applications for another 15 units. As of May 1, 2012, ten plants at nine sites had entered their 41st year of operation and thus are in their first period of extended operation (PEO). Five more plants will enter the PEO by the end of 2012. One foundation of the license renewal process has been license renewal guidance documents (LRGDs). The U.S. Nuclear Regulatory Commission (NRC) revised key guidance documents used for nuclear power license renewal in 2010 and 2011. These include NUREG-1800, 'Standard Review Plan for Review of License Renewal Applications,' revision 2 (SRP-LR), and NUREG-1801, 'Generic Aging Lessons Learned (GALL) Report,' revision 2 (GALL Report). The guidance documents were updated to reflect lessons learned and operating experience gained since the guidance documents were last issued in 2005. (author)

  14. Licensed operating reactors: Status summary report: Data as of February 29, 1988

    International Nuclear Information System (INIS)

    1988-04-01

    The US Nuclear Regulatory Commission's monthly Licensed Operating Reactors Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Information Resources Management, from the Headquarters Staff of NRC's Office of Inspection and Enforcement, from NRC's Regional Offices, and from utilities. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

  15. NPP License Renewal and Aging Management: Revised Guidance

    International Nuclear Information System (INIS)

    Hull, A.B.; Hiser, A.L.; Lindo-Talin, S.E.

    2012-01-01

    Based on the Atomic Energy Act, the NRC issues licenses for commercial power reactors to operate for up to 40 years and allows these licenses to be renewed for up to another 20 years. NRC has approved license renewal (LR) for well over 50% of U.S. located reactors originally licensed to operate for 40 years. Of these 104 reactors (69 PWRs, 35 BWRs), the NRC has issued renewed licenses for 71 units and is currently reviewing applications for another 15 units. As of May 1, 2012, ten plants at nine sites had entered their 41st year of operation and thus are in their first period of extended operation (PEO). Five more plants will enter the PEO by the end of 2012. One foundation of the license renewal process has been license renewal guidance documents (LRGDs). The U.S. Nuclear Regulatory Commission (NRC) revised key guidance documents used for nuclear power LR in 2010 and 2011. These include NUREG-1800, 'Standard Review Plan for Review of License Renewal Applications,' revision 2 (SRP-LR), and NUREG-1801, 'Generic Aging Lessons Learned (GALL) Report,' revision 2 (GALL Report). The guidance documents were updated to reflect lessons learned and operating experience gained since the guidance documents were last issued in 2005. The reactor LRGDs referenced in this poster can all be accessed at http://www.nrc.gov/reactors/operating/licensing/renewal/guidance.html (author)

  16. Licensed operating reactors: Status summary report, Data as of July 31, 1987

    International Nuclear Information System (INIS)

    1987-10-01

    The Operating Units Status Report - Licensed Operating Reactors provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Administration and Resources Management from the Headquarters staff of NRC's Office of Enforcement (OE), from NRC's Regional Offices, and from utilities. The three sections of the report are: monthly highlights and statistics for commercial operating units, and errata from previously reported data; a compilation of detailed information on each unit, provided by NRC's Regional Offices, OE Headquarters and the utilities; and an appendix for miscellaneous information such as spent fuel storage capability, reactor-years of experience and non-power reactors in the US. It is hoped the report is helpful to all agencies and individuals interested in maintaining an awareness of the US energy situation as a whole

  17. Licensed operating reactors: Status summary report data as of December 31, 1992

    International Nuclear Information System (INIS)

    Hartfield, R.A.

    1993-03-01

    The Nuclear Regulatory Commission's annual summary of licensed nuclear power reactor data is based primarily on the report of operating data submitted by licensees for each unit for the month of December because that report contains data for the month of December, the year to date (in this case calendar year 1992) and cumulative data, usually from the date of commercial operation. ne data is not independently verified, but various computer checks are made. The report is divided into two sections. The first contains summary highlights and the second contains data on each individual unit in commercial operation Section 1 capacity and availability factors are simple arithmetic averages. Section 2 items in the cumulative column are generally as reported by the licensee and notes as to the use of weighted averages and starting dates other than commercial operation are provided

  18. Licensed operating reactors: Status summary report, data as of 07-31-86

    International Nuclear Information System (INIS)

    1986-12-01

    The Operating Units Status Report - Licensed Operating Reactors provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Resource Management from the Headquarters staff of NRC's Office of Inspection and Enforcement, from NRC's Regional Offices, and from utilities. The three sections of the report are: monthly highlights and statistics for commercial operating units, and errata from previously reported data; a compilation of detailed information on each unit, provided by NRC's Regional Offices, IE Headquarters and the utilities; and an appendix for miscellaneous information such as spent fuel storage capability, reactor-years of experience and non-power reactors in the US. It is hoped the report is helpful to all agencies and individuals interested in maintaining an awareness of the US energy situation as a whole

  19. Licensed operating reactors: status summary report, data as of 6-30-81

    International Nuclear Information System (INIS)

    1981-07-01

    The Operating Units Status Report - Licensed Operating Reactors provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Management and Program Analysis from the Headquarters staff of NRC's Office of Inspection and Enforcement, from NRC's Regional Offices, and from utilities. The three sections of the report are: monthly highlights and statistics for commercial operating units, and errata from previously reported data; a compilation of detailed information on each unit, provided by NRC's Regional Offices, IE Headquarters and the utilities; and an appendix for miscellaneous information such as spent fuel storage capability, reactor-years of experience and non-power reactors in the U.S. It is hoped the report is helpful to all agencies and individuals interested in maintaining an awareness of the U.S. energy situation as a whole

  20. Licensed operating reactors: Status summary report, Data as of May 31, 1987

    International Nuclear Information System (INIS)

    1987-10-01

    The OPERATING UNITS STATUS REPORT - LICENSED OPERATING REACTORS provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Administration and Resources Management from the Headquarters staff of NRC's Office of Enforcement (OE), from NRC's Regional Offices, and from utilities. The three sections of the report are: monthly highlights and statistics for commercial operating units, and errata from previously reported data; a compilation of detailed information on each unit, provided by NRC's Regional Offices, OE Headquarters and the utilities; and an appendix for miscellaneous information such as spent fuel storage capability, reactor-years of experience and non-power reactors in the US. It is hoped the report is helpful to all agencies and individuals interested in maintaining an awareness of the US energy situation as a whole

  1. Licensed operating reactors: Status summary report, Data as of June 30, 1987

    International Nuclear Information System (INIS)

    1987-07-01

    The Operating Units Status Report - Licensed Operating Reactors provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Administration and Resources Management from the Headquarters staff of NRC's Office of Enforcement (OE), from NRC's Regional Offices, and from utilities. The three sections of the report are: monthly highlights and statistics for commercial operating units, and errata from previously reported data; a compilation of detailed information on each unit, provided by NRC's Regional Offices, OE Headquarters and the utilities; and an appendix for miscellaneous information such as spent fuel storage capability, reactor-years of experience and non-power reactors in the US. It is hoped the report is helpful to all agencies and individuals interested in maintaining an awareness of the US energy situation as a whole

  2. Licensed operating reactors: Status summary report, data as of 12-31-89

    International Nuclear Information System (INIS)

    1990-02-01

    The Operating Units Status Report - Licensed Operating Reactors provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Information Resources Management from the Headquarters staff of NRC's Office of Enforcement (OE), from NRC's Regional Offices, and from utilities. The three sections of the report are: monthly highlights and statistics for commercial operating units, and errata from previously reported data; a compilation of detailed information on each unit, provided by NRC's Regional Offices, OE Headquarters and the utilities; and an appendix for miscellaneous information such as spent fuel storage capability, reactor-years of experience and non-power reactors in the US. It is hoped the report is helpful to all agencies and individuals interested in maintaining an awareness of the US energy situation as a whole

  3. Licensed operating reactors: Status summary report, data as of September 30, 1989

    International Nuclear Information System (INIS)

    1989-12-01

    THE OPERATING UNITS STATUS REPORT -- LICENSED OPERATING REACTORS provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Information Resources Management from the Headquarters staff of NRC's Office of Enforcement (OE), from NRC's Regional Offices, and from utilities. The three sections of the report are: monthly highlights and statistics for commercial operating units, and errata from previously reported data; a compilation of detailed information on each unit, provided by NRC's Regional Offices, OE Headquarters and the utilities; and an appendix for miscellaneous information such as spent fuel storage capability, reactor-years of experience and non-power reactors in the US. It is hoped the report is helpful to all agencies and individuals interested in maintaining an awareness of the US energy situation as a whole

  4. Licensed operating reactors: Status summary report, data as of August 31, 1987

    International Nuclear Information System (INIS)

    1987-12-01

    The Operating Units Status Report - Licensed Operating Reactors provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Administration and Resources Management from the Headquarters staff of NRC's Office of Enforcement (OE), from NRC's Regional Offices, and from utilities. The three sections of the report are: monthly highlights and statistics for commercial operating units, and errata from previously reported data; a compilation of detailed information on each unit, provided by NRC's Regional Offices, OE Headquarters and the utilities; and an appendix for miscellaneous information such as spent fuel storage capability, reactor-years of experience and non-power reactors in the US. It is hoped the report is helpful to all agencies and individuals interested in maintaining an awareness of the US energy situation as a whole

  5. Licensed operating reactors: Status summary report, Data as of October 31, 1987

    International Nuclear Information System (INIS)

    Schwartz, I.

    1987-12-01

    The operating units status report - licensed operating reactors provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Administration and Resources Management from the Headquarters staff of NRC's Office of Enforcement (OE), from NRC's Regional Offices, and from utilities. The three sections of the report are: monthly highlights and statistics for commercial operating units, and errata from previously reported data; a compilation of detailed information on each unit, provided by NRC's Regional Offices, OE Headquarters and the utilities; and an appendix for miscellaneous information such as spent fuel storage capability, reactor-years of experience and non-power reactors in the US. It is hoped the report is helpful to all agencies and individuals interested in maintaining an awareness of the US energy situation as a whole

  6. Licensed operating reactors: Status summary report, data as of 9-30-87

    International Nuclear Information System (INIS)

    1987-10-01

    The OPERATING UNITS STATUS REPORT - LICENSED OPERATING REACTORS provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Administration and Resources Management from the Headquarters staff of NRC's Office of Enforcement (OE), from NRC's Regional Offices, and from utilities. The three sections of the report are: monthly highlights and statistics for commercial operating units, and errata from previously reported data; a compilation of detailed information on each unit, provided by NRC's Regional Offices, OE Headquarters and the utilities; and an appendix for miscellaneous information such as spent fuel storage capability, reactor-years of experience and non-power reactors in the US. It is hoped the report is helpful to all agencies and individuals interested in maintaining an awareness of the US energy situation as a whole

  7. Licensed operating reactors: Status summary report, Data as of 2-28-87

    International Nuclear Information System (INIS)

    1987-10-01

    The Operating Units Status Report- Licensed Operating Reactors provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Administration and Resources Management from the Headquarters staff of NRC's Office of Enforcement (OE), from NRC's Regional Offices, and from utilities. The three sections of the report are: monthly highlights and statistics for commercial operating units, and errata from previously reported data; a compilation of detailed information on each unit, provided by NRC's Regional Offices, OE Headquarters and the utilities; and an appendix for miscellaneous information such as spent fuel storage capability, reactor-years of experience and non-power reactors in the US. It is hoped the report is helpful to all agencies and individuals interested in maintaining an awareness of the US energy situation as a whole

  8. Cause trending analysis for licensing operational events in Daya Bay Nuclear Power Station

    International Nuclear Information System (INIS)

    Wang Dewei

    2005-01-01

    The human causal factors for all human error licensing operational events on Daya Bay nuclear power station since 1993 to 2003 are categorized, the trend of these causal factors is analyzed. The emphasis is placed on analyzing the deficiencies on complying with and executing regulations and procedures. The results provide directional reference for nuclear power station to improve human performance. (author)

  9. The United States nuclear regulatory commission license renewal process

    International Nuclear Information System (INIS)

    Holian, B.E.

    2009-01-01

    The United States (U.S.) Nuclear Regulatory Commission (NRC) license renewal process establishes the technical and administrative requirements for the renewal of operating power plant licenses. Reactor ope-rating licenses were originally issued for 40 years and are allowed to be renewed. The review process for license renewal applications (L.R.A.) provides continued assurance that the level of safety provided by an applicant's current licensing basis is maintained for the period of extended operation. The license renewal review focuses on passive, long-lived structures and components of the plant that are subject to the effects of aging. The applicant must demonstrate that programs are in place to manage those aging effects. The review also verifies that analyses based on the current operating term have been evaluated and shown to be valid for the period of extended operation. The NRC has renewed the licenses for 52 reactors at 30 plant sites. Each applicant requested, and was granted, an extension of 20 years. Applications to renew the licenses of 20 additional reactors at 13 plant sites are under review. As license renewal is voluntary, the decision to seek license renewal and the timing of the application is made by the licensee. However, the NRC expects that, over time, essentially all U.S. operating reactors will request license renewal. In 2009, the U.S. has 4 plants that enter their 41. year of ope-ration. The U.S. Nuclear Industry has expressed interest in 'life beyond 60', that is, requesting approval of a second renewal period. U.S. regulations allow for subsequent license renewals. The NRC is working with the U.S. Department of Energy (DOE) on research related to light water reactor sustainability. (author)

  10. 77 FR 29701 - Impact of Construction (Under a Combined License) of New Nuclear Power Plant Units on Operating...

    Science.gov (United States)

    2012-05-18

    ... New Nuclear Power Plant Units on Operating Units at Multi-Unit Sites AGENCY: Nuclear Regulatory... construct and operate new nuclear power plants (NPPs) on multi-unit sites to provide an evaluation of the... License) of New Nuclear Power Plants on Operating Units at Multi-Unit Sites (Package). ML112630039 Federal...

  11. Licensed operating reactors: Status summary report, data as of 07-31-88

    International Nuclear Information System (INIS)

    1988-09-01

    The US Nuclear Regulatory Commission's monthly LICENSED OPERATING REACTORS Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Information Resources Management, from the Headquarters Staff of NRC's Office of Inspection and Enforcement, from NRC's Regional Offices, and from utilities. Since all of the data concerning operation of the units is provided by the utility operators less than two weeks after the end of the month, necessary corrections to published information are shown on the ERRATA page. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

  12. Licensed operating reactors: Status summary report, data as of October 31, 1988

    International Nuclear Information System (INIS)

    1988-12-01

    The US Nuclear Regulatory Commission's monthly Licensed Operating Reactors Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Information Resources Management, from the Headquarters Staff of NRC's Office of Inspection and Enforcement, from NRC's Regional Offices, and from utilities. Since all of the data concerning operation of the units is provided by the utility operators less than two weeks after the end of the month, necessary corrections to published information are shown on the Errata page. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

  13. Licensed operating reactors: Status summary report, data as of August 31, 1988

    International Nuclear Information System (INIS)

    1988-10-01

    The US Nuclear Regulatory Commission's monthly LICENSED OPERATING REACTORS Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Information Resources Management, from the Headquarters Staff of NRC's Office of Inspection and Enforcement, from NRC's Regional Offices, and from utilities. Since all of the data concerning operation of the units is provided by the utility operators less than two weeks after the end of the month, necessary corrections to published information are shown on the ERRATA page. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

  14. Licensed operating reactors: Status summary report, data as of May 31, 1988

    International Nuclear Information System (INIS)

    Schwartz, I.

    1988-07-01

    The US Nuclear Regulatory Commission's monthly LICENSED OPERATING REACTORS Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Information Resource Management from the Headquarters Staff of NRC's Office of Inspection and Enforcement, from NRC's Regional Offices, and from utilities. Since all of the data concerning operation of the units is provided by the utility operators less than two weeks after the end of the month, necessary corrections to published information are shown on the ERRATA page. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operation units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by the NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

  15. Licensed operating reactors status summary report, data as of April 30, 1989

    International Nuclear Information System (INIS)

    1989-06-01

    The US Nuclear Regulatory Commission's monthly LICENSED OPERATING REACTORS Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Information Resources Management, from the Headquarters Staff of NRC's Office of Inspection and Enforcement, from NRC's Regional Offices, and from utilities. Since all of the data concerning operation of the units is provided by the utility operators less than two weeks after the end of the month, necessary corrections to published information are shown on the the ERRATA page. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

  16. Licensed operating reactors. Status summary report, data as of 3-31-82

    International Nuclear Information System (INIS)

    1982-04-01

    The US Nuclear Regulatory Commission's monthly Licensed Operating Reactors Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Management and Program Analysis, from the Headquarters Staff of NRC's Office of Inspection and Enforcement, from NRC's Regional Offices, and from utilities. Since all of the data concerning operation of the units is provided by the utility operators less than two weeks after the end of the month, necessary corrections to published information are shown on the Errata page. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

  17. Licensed operating reactors: Status summary report data as of June 30, 1988

    International Nuclear Information System (INIS)

    1988-07-01

    The US Nuclear Regulatory Commission's monthly Licensed Operating Reactors Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the office of Information Resources Management, from the Headquarters Staff of NRC's Office of Inspection and Enforcement, from NRC's Regional Offices, and from utilities. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

  18. Licensed operating reactors. Status summary report, data as of April 30, 1982

    International Nuclear Information System (INIS)

    1982-05-01

    The US Nuclear Regulatory Commission's monthly LICENSED OPERATING REACTORS Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Management and Program Analysis, from the Headquarters Staff of NRC's Office of Inspection and Enforcement, from NRC's Regional Offices, and from utilities. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

  19. Licensed operating reactors: Status summary report, data as of December 31, 1995. Volume 20

    International Nuclear Information System (INIS)

    1996-06-01

    The US Nuclear Regulatory Commission's monthly summary of licensed nuclear power reactor data is based primarily on the operating data report submitted by licensees for each unit. This report is divided into two sections: the first contains summary highlights and the second contains data on each individual unit in commercial operation. Section 1 availability factors, capacity factors, and forced outage rates are simple arithmetic averages. Section 2 items in the cumulative column are generally as reported by the licensees and notes to the use of weighted averages and starting dates other than commercial operation are provided

  20. 77 FR 33782 - License Amendment To Construct and Operate New In Situ Leach Uranium Recovery Facility; Uranium...

    Science.gov (United States)

    2012-06-07

    ... and Operate New In Situ Leach Uranium Recovery Facility; Uranium One Americas; Ludeman AGENCY: Nuclear... provided the first time that a document is referenced. The Ludeman facility In Situ Leach Uranium Recovery... request to amend Source Material License SUA-1341 to construct and operate a new in situ leach uranium...

  1. The SLOWPOKE licensing model

    Energy Technology Data Exchange (ETDEWEB)

    Snell, V. G.; Takats, F.; Szivos, K.

    1989-08-15

    The SLOWPOKE Energy System (SES-10) is a 10 MW heating reactor that has been developed in Canada. It will be capable of running without a licensed operator in continuous attendance, and will be sited in urban areas. It has forgiving safety characteristics, including transient time-scales of the order of hours. A process called `up-front` licensing has been evolved in Canada to identify, and resolve, regulatory concerns early in the process. Because of the potential market in Hungary for nuclear district heating, a licensing plan has been developed that incorporates Canadian licensing experience, identifies specific Hungarian requirements, and reduces the risk of licensing delays by seeking agreement of all parties at an early stage in the program.

  2. PBMR-SA licensing project organization

    International Nuclear Information System (INIS)

    Clapisson, G.A.; Metcalf, P.E.; Mysen, A.

    2001-01-01

    The South African nuclear regulatory authority, the Council for Nuclear Safety (CNS), is beginning the safety review of the Pebble Bed Modular Reactor (PBMR) design under development by the South African National Electrical Utility, Eskom. This paper describes the CNS licensing process, including the establishment of basic licensing criteria, general design criteria, and specific design rules, as well the safety assessment to be conducted in accordance with the established structure. It also summarises the CNS PBMR review project activities, including the overall organisational arrangements, licensing basis, safety and risk assessment, general operating rules and plant design engineering, and pre-operational testing. (author)

  3. 76 FR 61391 - Biweekly Notice Applications and Amendments to Facility Operating Licenses Involving No...

    Science.gov (United States)

    2011-10-04

    ... ''Rules of Practice for Domestic Licensing Proceedings'' in 10 CFR part 2. Interested person(s) should... to be operable in MODES 1, 2, and 3, as well as in MODE 4 when a steam generator (SG) is relied upon... stored diesel fuel oil inventory will require that a 7 day supply be available for each diesel generator...

  4. To License or Not to License Remanufacturing Business?

    Directory of Open Access Journals (Sweden)

    Zu-Jun Ma

    2018-01-01

    Full Text Available Many original equipment manufacturers (OEMs face the choice of whether to license an independent remanufacturer (IR to remanufacture their used products. In this paper, we develop closed-loop supply chain models with licensed and unlicensed remanufacturing operations to analyze the competition and cooperation between an OEM and an IR. The OEM sells new products and collects used products through trade-ins, while the IR intercepts the OEM’s cores to produce remanufactured products and sell them in the same market. We derive optimal decisions for each of the two types of firms in licensed and unlicensed remanufacturing scenarios and identify conditions under which the OEM and the IR would be most likely to cooperate with each other in implementing remanufacturing. The results show although it is beneficial for an OEM to license an IR to remanufacture its cores, it is not always necessary for an IR to accept OEM’s authorization. Moreover, we contrast the result for licensed remanufacturing scenario in the decentralized system with that in the centrally coordinated system to quantify potential inefficiency resulting from decentralization of decision making.

  5. Experience acquired by Furnas for licensing nuclear power plants

    International Nuclear Information System (INIS)

    Silva, A.J.C. da; Xavier, E.E.

    1986-01-01

    The system for licensing of Almirante Alvaro Alberto Nuclear Power Plant-Unit 1 is presented. The process phases for reactor construction and operation are described: preliminary site approval; bases for safety review; partial construction permits; final construction permits; emission of final report of safety analysis; initial operation license and permanent operation license. (M.C.K.) [pt

  6. U.S. licensing process and ABWR certification

    International Nuclear Information System (INIS)

    Quirk, J.F.; Williams, W.A.

    1996-01-01

    Part 50 of Title 10 of the Code of Federal Regulation (CFR) establishes a two-step licensing process by which the U.S. Nuclear Regulatory Committee (NRC) authorizes nuclear reactor plant construction through issuance of a construction permit and authorizes operation by issuance of an operating license. At each stage, the NRC Staff conducts technical reviews and there is potential for public hearings. In 1989, the NRC issued a new, simplified licensing process: Part 52. The purpose of the Part 52 licensing process is to provide a regulatory framework that brings about earlier resolution of licensing issues. Because issues are not resolved early in the Part 50 licensing process, approval of an operating license is not assured until after a significant investment has been made in the plant. Part 52 increases the stability and certainty of the licensing process by providing for the early resolution of safety and environmental issues. The Part 52 licensing process features (1) early site permits, (2) design certification, and (3) combined construction permit and operating licenses. As part of the U.S. Advanced Light Water Reactor (ALWR) Program to revitalize the nuclear option through the integration of government/utility/industry efforts, GE undertook the role of applying for certification for its latest product line, the Advanced Boiling Water Reactor (ABWR), under the U.S. ABWR certification program. The ABWR design is an essentially complete plant. Initial application for design certification was in 1987 under Part 50. GE reapplied in late 1991 under the newly promulgated Part 52. Following seven years of intensive interactions with the NRC and ACRS, GE was awarded the first Final Design Approval (FDA) under Part 52. The Commission initiated rulemaking by publishing the proposed ABWR Certification Rule in the Federal Register in early 1995. Certification is anticipated mid-1996. (J.P.N.)

  7. NRC's license renewal regulations

    International Nuclear Information System (INIS)

    Akstulewicz, Francis

    1991-01-01

    In order to provide for the continuity of the current generation of nuclear power plant operating licenses and at the same time ensure the health and safety of the public, and the quality of the environment, the US Nuclear Regulatory Commission (NRC) established a goal of developing and issuing regulations and regulatory guidance for license renewal in the early 1990s. This paper will discuss some of those activities underway to achieve this goal. More specifically, this paper will discuss the Commission's regulatory philosophy for license renewal and the two major license renewal rule makings currently underway. The first is the development of a new Part 54 to address procedural and technical requirements for license renewal; the second is a revision to existing Part 51 to exclude environmental issues and impacts from consideration during the license renewal process. (author)

  8. Obtaining college credit for licensed operator courses at the Wolf Creek Generating Station

    International Nuclear Information System (INIS)

    Russo, C.W.; Coulthard, R.C.

    1985-01-01

    The presentation examined alternatives to formal college courses as a means to obtain college credit toward a baccalaureate degree for station operations personnel. The focus is on the American Council on Education (ACE-PONSI) program which evaluates and makes credit recommendations for courses sponsored by organizations, like utilities, whose primary function is not education. Significant elements of the licensed operator program were prepared for an ACE-PONSI review and determined to be equivalent to college level nuclear engineering technology course work. The ACE-PONSI evaluation provides a good foundation and a significant amount of the training program evaluation required prior to the INPO accreditation effort

  9. On the reform of nuclear licensing procedures for plants and operation

    International Nuclear Information System (INIS)

    Lecheler, H.

    1977-01-01

    The nuclear licensing procedures require basic reforming. In doing so, there must be a differentiation between (concrete) licensing of plants and (abstract) decisions on site provision. The provision of sites is exercised directly by the diets of the Laender. For this purpose they enact planning laws on sites for nuclear power plants of different sizes. As far as the Federal law is touched upon (especially the Federal act on construction), the Federal legislator has to concede competences to the Laender. No. 6 of section 7 II of the Atomic Energy Act would have to be deleted. The plant licensing procedure is to be limited to a mere safety check-up of a concrete plant. Licensing prerequisites of the Atomic Energy Act are to be made more precise by the Federal legislator, namely by deciding unequivocally the purpose of the law, whether priority is given to promotion or to protection, and by making the enacting of tangible regulations a duty. When these licensing prerequisites exist, the law has to concede the applicant a plain title to licensing. (orig.) [de

  10. A Post Licensing Study of Community Effects at Two Operating Nuclear Power Plants. Final Report.

    Science.gov (United States)

    Purdy, Bruce J.; And Others

    In an effort to identify and assess the social, economic, and political effects of nuclear power plant construction and operation upon two host communities (Plymouth, Massachusetts and Waterford, Connecticut), a post-licensing review revealed that the primary impact of the nuclear power plants in both communities was an increase in the property…

  11. Safety-evaluation report related to renewal of the operating license for the Texas A and M University Research Reactor. Docket No. 50-128, License R-83

    International Nuclear Information System (INIS)

    1983-03-01

    This Safety Evaluation Report for the application filed by the Texas A and M University (Texas A and M) for a renewal of operating license number R-83 to continue to operate a research reactor has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is owned and operated by the Texas Engineering and Experiment Station of the Texas A and M University and is located on the campus in College Station, Brazos County, Texas. The staff concludes that the TRIGA reactor facility can continue to be operated by Texas A and M University without endangering the health and safety of the public

  12. Methodology to identify, review, and evaluate components for license renewal

    International Nuclear Information System (INIS)

    Carlson, D.D.; Gregor, F.E.; Walker, R.S.

    1988-01-01

    A methodology has been developed to systematically identify, review, and evaluate plant equipment for license renewal. The method builds upon the existing licensing basis, operating history, and accepted deterministic and probabilistic techniques. Use of these approaches provides a focus for license renewal upon those safety-significant systems and components that are not routinely replaced, refurbished, or subject to detailed inspection as part of the plant's existing test, maintenance, and surveillance programs. Application of the method identified the PWR and BWR systems that should be subjected to detailed license renewal review. Detailed examination of two example systems demonstrates the approach. The review and evaluation of plant equipment for license renewal differ from the initial licensing of the plant. A substantial operating history has been established, the licensing basis has evolved from the original one, and plant equipment has been subject to periodic maintenance and surveillance throughout its life. In consideration of these differences, a basis for license renewal is needed. License renewal should be based upon continuation of the existing licensing basis and recognition of existing programs and operating history

  13. Licensing of New Nuclear Power Plants in Canada

    International Nuclear Information System (INIS)

    Schwarz, Garry; Miller, Doug

    2011-01-01

    The regulatory process for new power plant licensing in Canada, from receipt of the initial application to commercial operation, can be divided into three phases: - Environmental Assessment (EA) and License to Prepare Site; - License to Construct; and - License to Operate. The Nuclear Safety and Control Act (NSCA) does not have provisions for combined licenses for site preparation, construction, or operation. Separate licenses must, therefore, be granted for each phase, and would be issued in sequence. However, applications to prepare a site, to construct and to operate a new nuclear power plant could be assessed in parallel. The total duration from the application for the License to Prepare Site to the issuance of the License to Operate (which is a prerequisite for first fuel load) has been established as 9 years subject to certain factors. To help facilitate this timeline, the CNSC has undertaken an aggressive program of documenting regulatory practices, requirements and guidance to assist applicants in submitting complete applications. Working level procedures to assist CNSC staff in their review of submissions are also under development. Extensive program and project management has been introduced to ensure that timelines will be achieved. In parallel with the above activities, regulatory oversight measures to be employed during site preparation activities and plant construction and commissioning are also being developed. On the international front, the CNSC is participating in the MDEP program to leverage the resources and knowledge of other national regulatory authorities in reviews the CNSC is undertaking. The CNSC also participates in IAEA and other international activities to utilize/adapt international practices as appropriate in Canada. (authors)

  14. Challenges in the Licensing of New Nuclear Power Plant, Service Life Extension of Operating Ones (Safeguards-Safety-Security Aspects)

    International Nuclear Information System (INIS)

    Horvath, K.

    2016-01-01

    The Hungarian Atomic Energy Authority (HAEA), as the Hungarian nuclear regulator is faced with dual challenges meant by the licensing of the planned construction of two AES-2006 type nuclear power plant units and the licensing of the service life extension of the existing units that have been operating for more than 30 years. The HAEA has full regulatory competence; its mission is to oversee the safety and security of all the peaceful applications of atomic energy. Accordingly, the licensing scope covers safeguards, safety as well as security. The paper shows the current status of the Hungarian nuclear programme and the future plans, as well as summarizes the regulatory approach followed by HAEA. (author)

  15. Regulatory analysis for amendments to regulations for the environmental review for renewal of nuclear power plant operating licenses. Final report

    International Nuclear Information System (INIS)

    1996-05-01

    This regulatory analysis provides the supporting information for a proposed rule that will amend the Nuclear Regulatory Commission's environmental review requirements for applications for renewal of nuclear power plant operating licenses. The objective of the proposed rulemaking is to improve regulatory efficiency by providing for the generic evaluation of certain environmental impacts associated with nuclear plant license renewal. After considering various options, the staff identified and analyzed two major alternatives. With Alternative A, the existing regulations would not be amended. This option requires that environmental reviews be performed under the existing regulations. Alternative B is to assess, on a generic basis, the environmental impacts of renewing the operating license of individual nuclear power plants, and define the issues that will need to be further analyzed on a case-by-case basis. In addition, Alternative B removes from NRC's review certain economics-related issues. The findings of this assessment are to be codified in 10 CFR 51. The staff has selected Alternative B as the preferred alternative

  16. Investment issues in nuclear plant license renewal

    International Nuclear Information System (INIS)

    Eynon, R.T.

    1999-01-01

    A method that determines the operating lives for existing nuclear power plants is discussed. These assumptions are the basis for projections of electricity supply through 2020 reported in the Energy Information Administration's (EIA's) Annual Energy Outlook 1999. To determine if plants will seek license renewal, one must first determine if they will be operating to the end of their current licenses. This determination is based on an economic test that assumes an investment of $150/kW will be required after 30 yr of operation for plants with older designs. This expenditure is intended to be equivalent to the cost that would be associated with any of several needs such as a one0time investment to replace aging equipment (steam generators), a series of investments to fix age-related degradation, increases in operating costs, or costs associated with decreased performance. This investment is compared with the cost of building and operating the lowest-cost new plant over the same 10-yr period. If a plant fails this test, it is assumed to be retired after 30 yr of service. All other plants are then considered candidates for license renewal. The method used to determine if it is economic to apply for license renewal and operate plants for an additional 20 yr is to assume that plants face an investment of $250 million after 40 yr of operation to refurbish aging components. This investment is compared with the lowest-cost new plant alternative evaluated over the same 20 yr that the nuclear plant would operate. If the nuclear plant is the lowest cost option, it is projected to continue to operate. EIA projects that it would be economic to extend the operating licenses for 3.7 GW of capacity (6 units)

  17. Generic evaluation of feedwater transients and small break loss-of-coolant accidents in GE-designed operating plants and near-term operating license applications

    International Nuclear Information System (INIS)

    1980-01-01

    The results are presented of a generic evaluation of feedwater transients, small-break loss-of-coolant accidents (LOCAs), and other TMI-2-related events for General Electric Company (GE)-designed operating plants and near-term operating license applications to confirm or establish the bases for the continued safe operation of the operating plants. The results of this evaluation are presented in this report in the form of a set of findings and recommendations in each of the principal review areas. Additional review of the accident is continuing and further information is being obtained and evaluated. Any new information will be reviewed and modifications will be made as appropriate

  18. Licensed operating reactors. Status summary report data as of 12-31-94: Volume 19

    International Nuclear Information System (INIS)

    1995-04-01

    The Nuclear Regulatory Commission's annual summary of licensed nuclear power reactor data is based primarily on the report of operating data submitted by licensees for each unit for the month of December because that report contains data for the month of December, the year to date (in this case calendar year 1994) and cumulative data, usually from the date of commercial operation. The data is not independently verified, but various computer checks are made. The report is divided into two sections. The first contains summary highlights and the second contains data on each individual unit in commercial operation. Section 1 capacity and availability factors are simple arithmetic averages. Section 2 items in the cumulative column are generally as reported by the licensee and notes as to the use of weighted averages and starting dates other than commercial operation are provided

  19. Licensed operating reactors. Status summary report data as of 12-31-94: Volume 19

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-04-01

    The Nuclear Regulatory Commission`s annual summary of licensed nuclear power reactor data is based primarily on the report of operating data submitted by licensees for each unit for the month of December because that report contains data for the month of December, the year to date (in this case calendar year 1994) and cumulative data, usually from the date of commercial operation. The data is not independently verified, but various computer checks are made. The report is divided into two sections. The first contains summary highlights and the second contains data on each individual unit in commercial operation. Section 1 capacity and availability factors are simple arithmetic averages. Section 2 items in the cumulative column are generally as reported by the licensee and notes as to the use of weighted averages and starting dates other than commercial operation are provided.

  20. Community engagement as conflict prevention: Understanding the social license to operate

    Science.gov (United States)

    Knih, Dejana

    This thesis examines community engagement as a form of conflict prevention in order to obtain the social license to operate (SLO) in Alberta's oil and gas industry. It does this by answering the question: what are the key elements of the Social License to Operate and how can these elements be applied to community engagement/consultation in a way that prevents conflicts in Alberta's oil and gas industry? The underlying assumption of this thesis is that building good relationships and working collaboratively functions as a form of conflict prevention and that this in turn leads to the SLO. This thesis outlines the key features of both successful community engagement and of the SLO, to provide a guideline for what is needed to obtain the SLO. Data was collected from semi-structured interviews and through a literature review. The data analysis concluded that there are direct parallels between the key elements of effective community engagement and the key elements of the SLO as identified in the interviews. These parallels are: knowing the community, addressing community needs, corporate social responsibility, relationship building, follow through and evidence for what has been done, executive buy-in, excellent communication, and open dialogue, all within a process which is principled (there is trust, understanding, transparency and respect), inclusive, dynamic, flexible, ongoing, and long-term. Moreover, the key elements of effective community engagement and of the SLO identified in the interviews also overlapped with those found in the literature review, with only one exception. The literature review explicitly named early involvement as a key element of both effective community engagement and the SLO, whereas the interview participants only explicitly indicated it as a key factor of community engagement and implied it to be a key element of the SLO.

  1. Challenges of SMR licensing practices

    Energy Technology Data Exchange (ETDEWEB)

    Soderholm, K., E-mail: kristiina.soderholm@fortum.com [Fortum Power, Espoo (Finland)

    2012-12-15

    This paper aims to increase the understanding of high level Nuclear Power Plant (NPP) licensing processes in Finland, France, the UK, Canada and the USA. These countries have been selected for this study because of their different licensing processes and recent actions in new NPP construction. After discussing their similarities and differences, suitable features for Small Modular Reactor licensing can be emphasized and suggested. Some of the studied licensing processes have elements that are already quite well suited for application to SMRs, but all of these different national processes can benefit from studying and implementing lessons learned from SMR specific licensing needs. The main SMR features to take into account in licensing are standardization of the design, modularity, mass production and serial construction. Modularity can be divided into two different categories: the first category is simply a single unit facility constructed of independently engineered modules (e.g., construction process for Westinghouse AP-1000 NPP) and the second is a facility structure composed of many reactor modules where modules are manufactured in factories and installed into the facility as needed (e.g., NuScale Power SMR design). Short construction schedules will not be fully benefited from if the long licensing process prolongs the commissioning and approach to full-power operation. The focus area of this study is to better understand the possibility of SMR deployment in small nuclear countries, such as Finland, which currently has four operating NPPs. The licensing process needs to be simple and clear to make SMR deployment feasible from an economical point of view. This paper uses public information and interviews with experts to establish the overview of the different licensing processes and their main steps. A high-level comparison of the licensing steps has been carried out. Certain aspects of the aviation industry licensing process have also been studied and certain

  2. Licensing of the Ignalina NPP

    International Nuclear Information System (INIS)

    Kutas, S.

    1999-01-01

    Since 1991 State Nuclear Power Safety Inspectorate (VATESI) has regulated Ignalina NPP operation by issuing annual operating permits. Those have been issued following submission of specified documents by the Ignalina NPP that have been reviewed by VATESI. However, according to to the procedures that are now established in the Law on Nuclear Energy and subordinate regulations the use of nuclear energy in the Republic of Lithuania is subject to strict licensing. Therefore a decision about the licence for continued operation of unit 1 should be taken. Licence would be granted by VATESI in cooperation with the Ministry of Health, Ministry of Environment and the institutions of local authorities. Ignalina NPP presented to the VATESI safety analysis report (SAR) with other documents. SAR was made mainly by foreign experts and financed by European Bank for Reconstruction and Development (EBRD). VATESI in this process is supported by western regulators. A special project LAP - Licensing Assistance Project was launched to help VATESI perform licensing according western practices

  3. Licensed operating reactors status summary report data as of April 30, 1983. Vol. 7, No. 5

    International Nuclear Information System (INIS)

    1983-05-01

    The US Nuclear Regulatory Commission's monthly Licensed Operating Reactors Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

  4. Licensed operating reactors: status summary report, data as of May 31, 1983. Volume 7, No. 6

    International Nuclear Information System (INIS)

    1983-06-01

    The US Nuclear Regulatory Commission's monthly Licensed Operating Reactors Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

  5. Economics of license renewal in the U.S. - entergy's perspective

    International Nuclear Information System (INIS)

    Young, Garry G.

    2003-01-01

    License renewal of operating nuclear plants in the United States has become one of the most successful U.S. nuclear regulatory activities in the past few years. In 1995, the U.S. Nuclear Regulatory Commission (NRC) published a revised rule in 10 CFR Part 54 that provided the requirements for an operating nuclear plant to seek license renewal. At that time, many people believed that only a select few operating nuclear plants would pursue license renewal and that most plants would operate for no more than 40 years. By mid-2003, the owners of approximately 52% of the U.S. nuclear fleet of 103 operating nuclear plants have decided to pursue license renewal and more are expected to follow. This change in direction since 1995 can be attributed to the improving economics of U.S. nuclear power plant operation and to the improved regulatory process resulting from the 1995 revision to 10 CFR Part 54. In 2000, Entergy submitted a license renewal application for Arkansas Nuclear One, Unit 1 (ANO-1). This application was the third to be submitted to the NRC at a time when it was still unclear how successful the regulatory process might be. However, less than 17 months later, in June 2001, the NRC granted a renewed operating license for ANO-1 at a total cost of approximately $11 million. Due in part to the ANO-1 license renewal success, Entergy now has tentative plans to pursue license renewal for the entire fleet of operating nuclear power plants. Without license renewal, Entergy's current nuclear fleet capacity of approximately 9,000 MW(e) would begin to decline in 2012. With license renewal, Entergy's nuclear fleet capacity can remain in place until 2032. This projection does not include the expected improvements in capacity due to power uprate that is currently planned. The combination of power uprate and license renewal will add significant economic value to Entergy's nuclear fleet. One of the major factors in strong performance is capacity factor. In 1990, the average

  6. Licensing of ''grandfather's'' facilities: Ukrainian experience

    International Nuclear Information System (INIS)

    Mikolaitchouk, H.; Bogdan, L.; Steinberg, N.

    1995-01-01

    In the former USSR, unlike most countries, radioactive waste management activities including waste disposal needed no license. But after the USSR breakdown the Ukrainian Parliament -- Verkhovna Rada -- invoked the revised Law on Business activities. According to Article 4 of the Law, in order to treat or to dispose radioactive waste every enterprise has to get a special permission or license. In compliance with the Law, the Cabinet of Ministers by its Ordinance of January 13, 1993, authorized the Ukrainian State Committee for Nuclear and Radiation Safety (UkrSCNRS) to issue special permissions or licenses for waste treatment and disposal. And that requirement was valid not only for future activities but also for existing facilities in operation. Taking into account the undergoing legislative process, SCNRS began to develop its licensing process without waiting for the special nuclear laws to be passed. On the basis of the legislation already in effect, first of all the Law on Enterprises (full responsibility of enterprises for their activities) and Law on Business activities (requirement to have a license for special types of activities), the newly formed national regulatory body had to identify all the enterprises that needed to be licensed, to establish relevant procedures, to develop related regulatory documents, to implement these procedures and documents at operating enterprises, and for each case to make a decision concerning feasibility of issuing a license, period of validity and license conditions

  7. 47 CFR 25.137 - Application requirements for earth stations operating with non-U.S. licensed space stations.

    Science.gov (United States)

    2010-10-01

    ... space stations. (a) Earth station applicants or entities filing a “letter of intent” or “Petition for... Union. (d) Earth station applicants requesting authority to operate with a non-U.S.-licensed space... 47 Telecommunication 2 2010-10-01 2010-10-01 false Application requirements for earth stations...

  8. Licensing reform in the USA

    International Nuclear Information System (INIS)

    1991-01-01

    The licensing process for nuclear power plants in the USA is currently in two distinct stages: the issuance of a construction permit followed later by the issuance of an operation license. The ''two-step'' process has come under heavy criticism from the U.S. nuclear industry on the grounds that it causes uncertainty and delays and therefore inhibits new commitments to nuclear power plants. In 1989 the NRC published new regulations for the licensing of nuclear power plants which provide for the issuance of early site permits, safety certifications of standard designs, and combined construction permits and operating licences. The new rule was challenged by intervenors representing antinuclear groups who filed a legal challenge seeking to have the rule set aside on the grounds that it violates the Atomic Energy Act which they allege makes two-step licensing mandatory. In November 1990 the US Court of Appeals upheld the NRC's authority to issue combined licenses. An appeal for a rehearing has been filed. The paper analyses the events and the possible consequences of an adverse court decision. It reviews the options open to the NRC and industry if the court decision is upheld. The possibility of congressional action to amend the Atomic Energy Act is discussed. (author)

  9. Perspective about the US license Renewal for NNPP's

    International Nuclear Information System (INIS)

    Lehnert, D. F.

    2004-01-01

    This article provides and overview of the US License Renewal Rule, 10 CFR 54, and its implementation in the US leading to the preparation and review of a license renewal application. The key regulatory documents and the industry's methodology and guidance for successfully implementing the Rule are discussed. While the process still undergoes change and optimization, it has become predictable and reliable, such that utilities can establish realistic schedules and budgets to complete the license renewal process. Nearly 60% of the US operating units have either received and extended operating license, have submitted their application for review, or have committed to submit an application in the next few years. The article concludes with a discussion of lessons learned from this wealth of experience and some emerging issues that may affect license renewal process. (Author)

  10. Aging management review for license renewal and plant life management

    International Nuclear Information System (INIS)

    Rinckel, M.A.; Young, G.G.

    2002-01-01

    Full text: United States nuclear power plants are initially licensed for a period of 40-years. The 40-year term, which was established by the Atomic Energy Commission in the 1950s, is believed to be based on engineering judgement and is consistent with the typical amortization schedule for purchasing fossil power plants. Under 10 CFR Part 54, the license renewal rule, additional terms of 20-years may be obtained through the preparation of a license renewal application that must be reviewed and approved by the Nuclear Regulatory Commission (NRC). The license renewal rule requires that applicants perform ageing management reviews on passive long-lived structures and components to demonstrate that ageing will be managed during the period of extended operation (i.e., additional 20 years of operation). ageing of active components, which are excluded from 10 CFR Part 54, is accomplished through the Maintenance Rule, 10 CFR Part 65, using performance-based monitoring. The license renewal rule, 10 CFR Part 54, was initially published in 1991. After significant interaction with the nuclear industry from 1991 through 1994, the NRC revised the rule in 1995 to focus on passive long-lived structures and components. In 1998, the first two applications for license renewal were submitted to the NRC by Baltimore Gas and Electric for the two-unit Calvert Cliffs nuclear power plant and by Duke Energy for the three-unit Oconee nuclear power plant. In March 2000, the NRC approved the application for the two-unit Calvert Cliffs nuclear power plant for an additional 20 years. Two months later, the NRC approved the renewal of the operating licenses for the three-unit Oconee nuclear station. The NRC completed these reviews in a timely, predictable, and stable manner. As of February 2002, the NRC has approved renewal of operating licenses for eight nuclear units and has applications under review for 15 more units. Twelve additional companies have notified the NRC of their intention to seek

  11. Guide to request license for teletherapy practice

    International Nuclear Information System (INIS)

    2000-01-01

    In this work the steps to request license for teletherapy practice are described , among these steps they it continued it plows to request the qualified personnel's yams, the operation authorization, application purpose, license type

  12. The need for legislative framework (licensing)

    International Nuclear Information System (INIS)

    Krech, H.

    1977-01-01

    For reasons of public acceptance the basis of a licensing system should be laid down in a law, details can be fixed in regulations below the law-level. The competence for licensing nuclear installations should be attributed to one body, which is not a the same time charged with the promotion of nuclear energy. The licensing authority has to be provided with sufficient technical advice, given by experts organized in advisory bodies. Normally a licensing procedure is split into several steps (site approval, construction permit, operation licence), each step can be subdivided. Some general aspects of licensing conditions (personal, technical and financial) as well as of the licensing procedure are outlined. The participation of the public is of particular importance but also involves most intricate problems. The paper concludes with some critical remarks on the role of administrative courts with respect to the licensing of nuclear power plants. (orig.) [de

  13. Nuclear power plant simulators for operator licensing and training. Part I. The need for plant-reference simulators. Part II. The use of plant-reference simulators

    International Nuclear Information System (INIS)

    Rankin, W.L.; Bolton, P.A.; Shikiar, R.; Saari, L.M.

    1984-05-01

    Part I of this report presents technical justification for the use of plant-reference simulators in the licensing and training of nuclear power plant operators and examines alternatives to the use of plant-reference simulators. The technical rationale is based on research on the use of simulators in other industries, psychological learning and testing principles, expert opinion and user opinion. Part II discusses the central considerations in using plant-reference simulators for licensing examination of nuclear power plant operators and for incorporating simulators into nuclear power plant training programs. Recommendations are presented for the administration of simulator examinations in operator licensing that reflect the goal of maximizing both reliability and validity in the examination process. A series of organizational tasks that promote the acceptance, use, and effectiveness of simulator training as part of the onsite training program is delineated

  14. License renewal - an idea whose time has come. Hatch nuclear plant license renewal program: an actual example of application of the license renewal rule to the Intake Structure

    International Nuclear Information System (INIS)

    Chandiwala, F.; Evans, W.P.

    1999-01-01

    After the NRC issued a revised license renewal rule in May 1995, the nuclear industry focussed on developing generic industry for implementing the rule and testing the guidance through various demonstration programs and work products in conjunction with the NRC. In addition, plant-specific programs also proceeded forward. These activities show that implementation issues continue to exist. Since the issuance of the rule, the NRC has issued a draft standard review plan for license renewal (SRP-LR), working draft, September 1997. Southern Nuclear Operating Company (SNC) has begun development work on a license renewal application for Plant Hatch Units 1 and 2. Plant Hatch Units 1 and 2 are BWR 4, Mark I plants whose operating licenses expire in 2014 and 2018, respectively. The Plant Hatch initiative also involves teaming with other boiling water reactors (BWRs) to develop the license renewal technology within the BWR fleet, and to support Plant Hatch by providing an oversight role for the application process. The teaming effort involved two other utilities, each being assigned to prepare a common report on a mechanical system or a structure. The common report could be presented to the NRC with modifications to suit the individual plants, thereby saving time and money, and hopefully resulting in quicker approval by the NRC. The desired license renewal process end result is a renewed license with up to a 20 year extension (10CFR 54.31(b)). (orig.)

  15. The USNCR license renewal process

    International Nuclear Information System (INIS)

    Kuo, Pao-Tsin

    2002-01-01

    The US Congress promulgated a law in 1954, entitled 'Atomic Energy Act'. This Act states that operating licenses for commercial nuclear power plants are limited to a fixed term of 40 years, but they may be renewed for a period not to exceed 20 years. The terms were established mainly for economic considerations, not based on technical limitations. The U.S. Nuclear Regulatory Commission (USNRC) published the license renewal rule, Title 10 of the Code of Federal Regulations, Part 54 (10 CFR Part 54), in December, 1991. The rule has since been amended in May, 1995. The underlying principle of the rule is that the regulatory process is adequate for ensuring safety of operating plants. The regulatory process includes NRC's issuance of Orders, Bulletins, Generic Letters, and Information Notices, as well as a number of special inspections in addition to the continuous oversight and routine inspection activities performed by on-site inspectors. Because of this comprehensive regulatory process, compilation of the current license basis or re-verification of the current licensing basis is not considered necessary for a license renewal review. The USNRC also determined on the basis of the findings of its research programs that active structures and components are well maintained by the existing programs. Therefore, the focus of the license renewal review is on passive, long-lived structures and components and on time-limited ageing analyses. The time-limited ageing analyses are for those structures and components which were originally designed to a 40 year service life

  16. The Role of License Renewal in PLiM for U.S. Nuclear Power Plants

    International Nuclear Information System (INIS)

    Young, G.G.

    2012-01-01

    At the 2nd International Symposium on Nuclear Power Plant Life Management (PLiM) in 2007, it was reported that the NRC had approved renewal of operating licenses for 48 nuclear units, which would allow operation for up to 60 years (i.e., an additional 20 years from the original 40-year license term). Of the 104 operating nuclear units in the U.S. in 2007, it was anticipated that almost 100% would eventually pursue license renewal. At that time, it was also concluded that the regulatory process was stable and predictable for license renewal, and that successful PLiM activities were helping to ensure the safety, economic, and political factors in the U.S. remained favorable for continued success with license renewal. The status of license renewal in 2012 is even better than it was in 2007. As of April 2012, the NRC has approved renewal of the operating licenses for 71 nuclear units and has applications under review for 15 more units. In addition, nuclear plant owners of at least 14 more units have announced plans to submit license renewal applications over the next few years. This brings the total of renewed licenses and announced plans for license renewal to 96% of the 104 currently operating nuclear units in the U.S. The prediction that almost 100% would eventually pursue license renewal is assured. This positive trend for long term operation of nuclear power plants in the U.S. is attributed to: (1) the success of PLiM activities in achieving an excellent safety record for the nuclear power industry and in ensuring on-going positive economics for nuclear plant operation, and (2) the stable and predictable regulatory process for license renewal. U.S. efforts are now underway to consider long term operation for more than 60 years and the process of preparing a second round of license renewals for up to 80 years of operation is likely to begin within the next few years. (author)

  17. Licensing and Environmental Issues of Wave Energy Projects

    DEFF Research Database (Denmark)

    Neumann, Frank; Tedd, James; Prado, Miguel

    2006-01-01

    a special standing or facilitated access to operating licenses due to their experimental character, the move of wave energy projects towards commercial applications implies complex procedures for obtaining licenses both with respect to the construction and deployment and operation phases, as well......The major non-technical barrier for large-scale wave energy implementation is the wide range of licensing issues and potential environmental concerns, in addition to significant National/regional differences in licensing procedures and permit requirements. Whereas some pilot plants have had...... as concerning ocean space use and environmental concerns. Despite recent efforts to streamline European EIA (Environmental Impact Assessment) in general, potential project developers are far from having a clear view of present and future requirements concerning these barriers on a trans-national level...

  18. Regulator process for the authorization of an amendment to the operation license of a nuclear power plant in Mexico

    International Nuclear Information System (INIS)

    Perez, R.; Espinosa V, J.M.; Salgado, J.R.; Mamani, Y.R.

    2005-01-01

    The regulator process by which an authorization is granted from an amendment to the License of Operation of a nuclear power station in Mexico is described. It makes an appointment the effective legal mark, the technical characteristics of the modification, the evaluation process and deposition upon oath of tests and finally the elaboration of the Safety report and the Technical Verdict that is a correspondent for the regulator organism to the Secretary of Energy, the one that in turn is the responsible of granting the amendment the License just as it establishes it the Law. (Author)

  19. Foundation for the adequacy of the licensing bases

    International Nuclear Information System (INIS)

    1991-12-01

    The objective of this report is to describe the regulatory processes that assures that any plant-specific licensing bases will provide reasonable assurance that the operation of nuclear power plants will not be inimical to the public health and safety to the end of the renewal period. It is on the adequacy of this process that the Commission has determined that a formal renewal licensing review against the full range of current safety requirements would not add significantly to safety and is not needed to assure that continued operation throughout the renewal term is not inimical to the public health and safety or common defense and security. This document illustrates in general terms how the regulatory process has evolved in major safety issue areas. It also provides examples illustrating why it is unnecessary to re-review an operating plant's basis, except for age-related degradation unique to license renewal, at the time of license renewal. The report is a supplement to the Statement of Considerations for the Nuclear Regulatory Commission's rule (10 CFR Part 54) that established the criteria and standards governing nuclear power plant license renewal

  20. Licensed operating reactors. Status summary report as of February 29, 1984. Volume 8, No. 3

    International Nuclear Information System (INIS)

    1984-04-01

    The US Nuclear Regulatory Commission's monthly Licensed Operating Reactors Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Resource Management, from the Headquarters Staff of NRC's Office of Inspection and Enforcement (IE), from NRC's Regional Offices, and from utilities. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

  1. Nuclear licensing in Slovenia

    International Nuclear Information System (INIS)

    Prah, M.; Spiler, J.; Vojnovic, D.; Pristavec, M.

    1998-01-01

    The article presents the approach to nuclear licensing in Slovenia. The paper describes, the initialization, internal authorization and review process in the Krsko NPP. The overall process includes preparation, internal independent evaluation, the Krsko Operating Committee and the Krsko Safety Committee review and internal approval. In addition, the continuation of the licensing process is discussed which includes independent evaluation by an authorized institution and a regulatory body approval process. This regulatory body approval process includes official hearing of the licensee, communication with the licensee, and final issuance of a license amendment. The internal evaluation, which follows the methodology of US NRC (defined in 10 CFR 50.59 and NUMARC 125) is described. This concept is partially implemented in domestic legislation.(author)

  2. Building social license to operate through community engagement: the WUSC-Rio Tinto Alcan partnership in Ghana

    OpenAIRE

    Eaton, Chris

    2016-01-01

    Presenting the case study of the WUSC-Rio Tinto Alcan partnership in Ghana, this article focuses on the benefits and challenges of a multi-stakeholder partnership between an NGO, a mining company, governments and local communities. Strong community empowerment, alignment of multiple stakeholders’ interests, and the contribution of an expert development NGO definitely contributed to the success of the project, while also strengthening Rio Tinto’s social license to operate.

  3. Opportunistic tri-band carrier aggregation in licensed spectrum for multi-operator 5G hetnet

    Science.gov (United States)

    Maksymuk, Taras; Kyryk, Maryan; Klymash, Mykhailo; Jo, Minho; Romaniuk, Ryszard; Kotyra, Andrzej; Zhanpeisova, Aizhan; Kozbekova, Ainur

    2017-08-01

    Increasing capacity of mobile networks is a real challenge due to rapid increasing of traffic demands and spectrum scarcity. Carrier aggregation technology is aimed to increase the user data rate by combining the throughput of few spectrum bands, even if they are not physically collocated. Utilization of unlicensed Wi-Fi 5 GHz band for mobile transmission opens new perspectives for carrier aggregation due to vast amount of spectrum range, which can be available for aggregation to supplement data rates for end users. There are many solutions proposed to enable mobile data transmission in unlicensed band without disturbing interference for the existing Wi-Fi users. The paper presents a new approach for opportunistic carrier aggregation in licensed and unlicensed band for multi-operator 5G network. It allows multiple network operators to utilize unlicensed spectrum opportunistically if it is not currently used by Wi-Fi or other mobile network operators. Performance of the proposed approach has been simulated in case of two competing operators. Simulation results reveal that applying the proposed method ensures achieving satisfactory performance of carrier aggregation for the case of two network operators.

  4. Evaluation of experience and trends in international co-operation in nuclear safety and licensing

    International Nuclear Information System (INIS)

    Stadie, K.B.; Strohl, P.

    1977-01-01

    The paper traces the development of co-operation in nuclear safety technology between the OECD Member countries which began as early as 1965 and is now organised under the auspices of the Committee on the Safety of Nuclear Installations of the OECD Nuclear Energy Agency. The principal objective is to exchange and evaluate information on relevant R and D and hence broaden the technical basis for decision-making by licensing authorities in the different countries. The membership of the Committee on the Safety of Nuclear Installations combines expertise in nuclear safety R and D and in licensing questions so that licensing procedures in the different countries may be exposed continuously to the influence of overall technological progress. The Committee actively seeks to narrow the differences between administrative procedures and traditional legal practices in Member countries as these affect the licensing of nuclear installations, primarily by assessing and comparing the methods employed. The paper shows how the Committee's working arrangements provide for maximum flexibility: the various co-ordinated programmes are selected after in-depth evaluation of potential areas of priority and are implemented through ad hoc Working Groups, specialist meetings or task forces, or in the form of special studies involving all interested countries. The results, conclusions and recommendations emerging from each programme are reviewed by the Committee before dissemination. Hitherto the greater part of the Committee's activities has been concerned with the safety of light water reactors and related subjects, but more attention is now being given to other topics such as LMFBR safety technology and the safety of fuel cycle facilities, particularly those at the end of the process, the so-called ''back-end'' plants. The paper discusses certain problems and constraints encountered in implementing the programme, some of which stem from Member countries' different degrees of penetration

  5. Economic implications of nuclear plant license renewal in the U.S

    International Nuclear Information System (INIS)

    Smith, L.J.

    2001-01-01

    The NRC and the nuclear industry struggled for many years with the development of a viable license renewal rule. Now that a workable rule appears to have been developed, and the first license renewal applicants have received renewed licenses, the floodgates have opened and a large number of nuclear utilities have announced intentions to seek renewed NRC operating licenses. In this time when profound changes are being experienced in the electric generation markets in the United States, nuclear plant license renewal can have several economic effects that should be considered by utilities prior to the pursuit of an NRC license renewal. This paper examines some of the factors that may be affected by the prospect of an additional 20-year operating life of a nuclear plant. (author)

  6. MEX04/058 supporting the license renewal of the LVNPP

    International Nuclear Information System (INIS)

    Diaz, A.; Arganis, C.; Viais, J.; Mendoza, G.; Lucatero, M. A.; Contreras, A.

    2010-10-01

    Nuclear power plants in the United States are authorized to operate for 40 years. However, this 40-year period was chosen based on economic considerations and not on technological restrictions or safety aspects. In general, the operation of equipment, systems and components in a nuclear power plant is subject to rigorous maintenance and inspection monitoring under strict surveillance programs throughout their life. In fact, according to the Nuclear Energy Institute, in December 2009, 59 nuclear power plants in the United States had already reached the 40 years of the original operating license and carried out their renewal process, extending their operation for up to 20 more years. These 59 nuclear power plants carried out their renewal process, basing their operation mainly on safety reviews that validated the good working order of systems, structures and components, meeting the technical specifications required, as well as complying with the specific safety provisions for prolonging the use of a operating license. The owner is responsible for showing the Regulatory Agency that it is capable of effectively managing the aging of the systems, structures and components,guaranteeing their good working order during the renewal period. In the specific case of Mexico, Unit 1 of the Laguna Verde Nuclear Power Plant (LVNPP) has an original 30-year license, with almost 20 years of proper operation, for which, in order to request a license extension, it is necessary to begin management activities, which allow for constituting and submitting the license renewal application to the Regulatory Agency in order to continue its commercial operation. This paper presents some of most important activities carried out by Instituto Nacional de Investigaciones Nucleares and LVNPP in the international project MEX04/058, related to Plant Life Management as a support of the beginning of plant license renewal process. (Author)

  7. 77 FR 63343 - Biweekly Notice: Applications and Amendments to Facility Operating Licenses and Combined Licenses...

    Science.gov (United States)

    2012-10-16

    ... in accordance with the Commission's ``Rules of Practice for Domestic Licensing Proceedings'' in 10... for an inoperable diesel generator (DG). A commensurate change is also proposed to extend the maximum... alternating current power source (i.e., a supplemental diesel generator) with the capability to power any E...

  8. 77 FR 73684 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses...

    Science.gov (United States)

    2012-12-11

    ... in accordance with the Commission's ``Rules of Practice for Domestic Licensing Proceedings'' in 10... emergency diesel generator, and the stored lube oil inventory will also continue to require that a 7-day supply be available for each diesel generator. The changes are consistent with NRC-approved Technical...

  9. 13 CFR 107.1900 - Surrender of license.

    Science.gov (United States)

    2010-01-01

    ... 13 Business Credit and Assistance 1 2010-01-01 2010-01-01 false Surrender of license. 107.1900 Section 107.1900 Business Credit and Assistance SMALL BUSINESS ADMINISTRATION SMALL BUSINESS INVESTMENT COMPANIES Ending Operations as a Licensee § 107.1900 Surrender of license. You may not surrender your...

  10. NUMARC view of license renewal criteria

    International Nuclear Information System (INIS)

    Edwards, D.W.

    1989-01-01

    The Atomic Energy Act and the implementing regulations of the US Nuclear Regulatory Commission (NRC) permit the renewal of nuclear plant operating licenses upon expiration of their 40-year license term. However, the regulatory process by which license renewal may be accomplished and the requirements for the scope and content of renewal applications are yet to be established. On August 29, 1988, the NRC published an Advanced Notice of Proposed Rulemaking regarding the subject of license renewal. This Advanced Notice and the NUREG which it references, NUREG-1317, Regulatory Options for Nuclear Plant License Renewal, provide the most recent regulatory thought on this issue. The basic issue addressed by NUREG-1317 is the definition of an adequate licensing basis for the renewal of a plant license. The report contemplates three alternatives in this regard. This paper discusses each of these three proposals. The NUMARC NUPLEX Working Group endorses a license renewal process based on a plant's current licensing basis along with an evaluation of the pertinent components, systems, and structures affected by age-related degradation. The NUMARC NUPLEX Working group believes that an appropriate scope for NRC review of the license renewal application should focus on those safety-significant structures systems, and components subject to significant age-related degradation that are not subject to existing recognized effective replacement, refurbishment, or inspection programs. The paper also briefly discusses NUMARC's view of the role of the Backfit Rule in the license renewal process

  11. Safety Evaluation Report related to the renewal of the operating license for the research reactor at Pennsylvania State University

    International Nuclear Information System (INIS)

    1986-01-01

    This Safety Evaluation Report for the application filed by the Pennsylvania State University for a renewal of Operating License R-2 to continue to operate the Pennsylvania State University Breazeale Reactor (PSBR) has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located on the campus in University Park, Pennsylvania. On the basis of its technical review, the staff concludes that the reactor facility can continue to be operated by the university without endangering the health and safety of the public or the environment

  12. Atomic Safety and Licensing Board Panel annual report

    International Nuclear Information System (INIS)

    1991-09-01

    In Fiscal Year 1990, The Atomic Safety and Licensing Board Panel (Panel) handled 40 proceedings involving the construction, operation, and maintenance of commercial nuclear power reactors or other activities requiring a license from the Nuclear Regulatory Commission. This report summarizes, highlights, and analyzes how the judges and licensing boards of the Panel addressed the wide-ranging issues raised in these proceedings during the year

  13. Licensing safety critical software

    International Nuclear Information System (INIS)

    Archinoff, G.H.; Brown, R.A.

    1990-01-01

    Licensing difficulties with the shutdown system software at the Darlington Nuclear Generating Station contributed to delays in starting up the station. Even though the station has now been given approval by the Atomic Energy Control Board (AECB) to operate, the software issue has not disappeared - Ontario Hydro has been instructed by the AECB to redesign the software. This article attempts to explain why software based shutdown systems were chosen for Darlington, why there was so much difficulty licensing them, and what the implications are for other safety related software based applications

  14. 47 CFR 80.53 - Application for a portable ship station license.

    Science.gov (United States)

    2010-10-01

    ... 47 Telecommunication 5 2010-10-01 2010-10-01 false Application for a portable ship station license... SPECIAL RADIO SERVICES STATIONS IN THE MARITIME SERVICES Applications and Licenses § 80.53 Application for a portable ship station license. The Commission may grant a license permitting operation of a...

  15. 77 FR 70837 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses...

    Science.gov (United States)

    2012-11-27

    ... intervene shall be filed in accordance with the Commission's ``Rules of Practice for Domestic Licensing... request: The proposed change will delete Function 14, SG [Steam Generator] Water Level--Low, Coincident... capability to shut down the reactor when required on Low--Low Steam Generator water level. The ability to...

  16. 78 FR 16876 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses...

    Science.gov (United States)

    2013-03-19

    ... intervene shall be filed in accordance with the Commission's ``Rules of Practice for Domestic Licensing... proposes to replace the VHS with an onsite diesel generator as the AAC power source providing this... power source (the VHS) with an additional onsite AAC power source (diesel generator). This equipment can...

  17. 77 FR 67679 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses...

    Science.gov (United States)

    2012-11-13

    ... diesel generator surveillance requirements. Margin of safety is related to the ability of the fission... evaluated; or (3) involve a significant reduction in a margin of safety. The basis for this proposed... accordance with the Commission's ``Rules of Practice for Domestic Licensing Proceedings'' in 10 CFR Part 2...

  18. 78 FR 14126 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses...

    Science.gov (United States)

    2013-03-04

    ... in accordance with the Commission's ``Rules of Practice for Domestic Licensing Proceedings'' in 10... of the document. The E-Filing system also distributes an email notice that provides access to the... Completion Time has no impact on the consequences of any design basis accident since the consequences of an...

  19. Licensed operating reactors status summary report, data as of December 31, 1985. Volume 10, No. 1

    International Nuclear Information System (INIS)

    1986-01-01

    The US Nuclear Regulatory Commission's monthly Licensed Operating Reactors Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Resource Management, from the Headquarters Staff of NRC's Office of Inspection and Enforcement, from NRC's Regional Offices, and from utilities. Since all of the data concerning operation of the units is provided by the utility operators less than two weeks after the end of the month, necessary corrections to published information are shown on the Errata page. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

  20. The strategy of experimental power reactor licensing in Indonesia

    International Nuclear Information System (INIS)

    Moch Djoko Birmano

    2015-01-01

    Currently, BATAN has being planned to develop Experimental Power Reactor (EPR), that is the research nuclear reactor that can generate power (electricity or heat). The EPR is planned will be built in the National Center for Research of Science and Technology (Puspiptek) area at Serpong, South Tangerang, Banten Province, with the choice of reactor types is HTGR with the power size of 10 MWth. As stated in the Act No. 10 year 1997 on Nuclear Power, that every construction and operation of nuclear reactors and other nuclear installations and decommissioning of nuclear reactors required to have a permit. Furthermore, the its implementation arrangements is regulated in Government Regulation (GR) No. 2 year 2014 on Licensing of Nuclear Installations and Nuclear Material Utilization, which contains the requirements and procedures for the licensing process since site, construction, commissioning, operation, and decommissioning, it means licensing is implemented during the activity of construction, operation and decommissioning of NPPs.While, for the more detailed licensing arrangements available in the guidelines of BAPETEN Chairman Regulation (BCR). This study was conducted to understand the legal and institutional aspects, types and stages, and the licensing process of RDE, and identify licensing strategy so that timely as planned. Methodologies used include the literature study, consultation with experts in BAPETEN, discussions in the national seminar including FGD. (author)

  1. Streamlining the license renewal review process

    International Nuclear Information System (INIS)

    Dozier, J.; Lee, S.; Kuo, P.T.

    2001-01-01

    The staff of the NRC has been developing three regulatory guidance documents for license renewal: the Generic Aging Lessons Learned (GALL) report, Standard Review Plan for License Renewal (SRP-LR), and Regulatory Guide (RG) for Standard Format and Content for Applications to Renew Nuclear Power Plant Operating Licenses. These documents are designed to streamline the license renewal review process by providing clear guidance for license renewal applicants and the NRC staff in preparing and reviewing license renewal applications. The GALL report systematically catalogs aging effects on structures and components; identifies the relevant existing plant programs; and evaluates the existing programs against the attributes considered necessary for an aging management program to be acceptable for license renewal. The GALL report also provides guidance for the augmentation of existing plant programs for license renewal. The revised SRP-LR allows an applicant to reference the GALL report to preclude further NRC staff evaluation if the plant's existing programs meet the criteria described in the GALL report. During the review process, the NRC staff will focus primarily on existing programs that should be augmented or new programs developed specifically for license renewal. The Regulatory Guide is expected to endorse the Nuclear Energy Institute (NEI) guideline, NEI 95-10, Revision 2, entitled 'Industry Guideline for Implementing the Requirements of 10 CFR Part 54 - The License Renewal Rule', which provides guidance for preparing a license renewal application. This paper will provide an introduction to the GALL report, SRP-LR, Regulatory Guide, and NEI 95-10 to show how these documents are interrelated and how they will be used to streamline the license renewal review process. This topic will be of interest to domestic power utilities considering license renewal and international ICONE participants seeking state-of-the-art information about license renewal in the United States

  2. Department of Energy licensing strategy

    International Nuclear Information System (INIS)

    Frei, M.W.

    1984-01-01

    The Department of Energy (DOE) is authorized by the Nuclear Waste Policy Act of 1982 (Act) to site, design, construct, and operate mined geologic repositories for high-level radioactive wastes and is required to obtain licenses from the Nuclear Regulatory Commission (NRC) to achieve that mandate. To this end the DOE has developed a licensing approach which defines program strategies and which will facilitate and ease the licensing process. This paper will discuss the regulatory framework within which the repository program is conducted, the DOE licensing strategy, and the interactions between DOE and NRC in implementing the strategy. A licensing strategy is made necessary by the unique technical nature of the repository. Such a facility has never before been licensed; furthermore, the duration of isolation of waste demanded by the proposed EPA standard will require a degree of reliance on probabilistic performance assessment as proof of compliance that is a first of a kind for any industry. The licensing strategy is also made necessary by the complex interrelationships among the many involved governmental agencies and even within DOE itself, and because these relationships will change with time. Program activities which recognize these relationships are essential for implementing the Act. The guiding principle in this strategy is an overriding commitment to safeguarding public health and safety and to protecting the environment

  3. The end game must end before license renewal begins

    International Nuclear Information System (INIS)

    Allen, S.R.; Edwards, D.W.

    1995-01-01

    The quest for a process and strategy to achieve license renewal was begun in the mid-1980s with the view that renewal was an imperative. A major portion of the nation's future electric supply seemed to be at stake. For plants who were becoming noncompetitive because of annual capital recovery, license renewal also appeared as the means of survival. These two perceptions led to a third: License renewal should be sought immediately upon completion of the first 20 yr of operation. Although the basic engineering premise of license renewal remains sound, the perceptions regarding timing of an application may be incorrect. This paper suggests that a gauntlet of uncertainty exists for all plants. Further, it is most severe between the 20th and 30th years of operation. Thus, the competitive viability of the plant must be sustained for most of the initial term before license renewal can become a serious option

  4. THE SOCIAL OPERATING LICENSE OF CORPORATIONS: MINING COMPANIES AND THEIR CONSTITUENTS

    OpenAIRE

    Dumitru Borțun; Camelia Crişan

    2012-01-01

    Several authors from the CSR literature have proposed the term “license to operate” when referring to companies and their activities in the relevant communities (Visser, 2008, Post, Preston & Sachs, 2002). Others have implied this term when referring to the types of responsibilities a company needs to have in order to be able to exercise its activity in the society (Blair [1994] 2004, Clarke [1998] 2004 and Philips 2003). Consultancy companies have already coined the term: social license to o...

  5. Licensing of away-from-reactor (AFR) installations

    International Nuclear Information System (INIS)

    Gray, P.L.

    1980-01-01

    Storage of spent fuel at Away-From-Reactor (AFR) installations will allow reactors to continue to operate until reprocessing or other fuel disposal means are available. AFR installations must be licensed by the Nuclear Regulatory Commission (NRC). Although wide experience in licensing reactors exists, the licensing of an AFR installation is a relatively new activity. Only one has been licensed to date. This paper delineates the requirements for licensing an AFR installation and projects a licensing schedule. Because the NRC is developing specific AFR requirements, this schedule is based primarily on draft NRC documents. The major documents needed for an AFR license application are similar to those for a reactor. They include: a Safety Analysis Report (SAR), and Environmental Report (ER), safeguards and security plans, decommissioning plans, proposed technical specifications, and others. However, the licensing effort has one major difference in that for AFR installations it will be a one-step effort, with follow-up, rather than the two-step process used for reactors. The projected licensing schedule shows that the elapsed time between filing an application and issuance of a license will be about 32 months, assuming intervention. The legal procedural steps will determine the time schedule and will override considerations of technical complexity. A license could be issued in about 14 months in the absence of intervention

  6. 10 CFR Appendix N to Part 52 - Standardization of Nuclear Power Plant Designs: Combined Licenses To Construct and Operate...

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Standardization of Nuclear Power Plant Designs: Combined Licenses To Construct and Operate Nuclear Power Reactors of Identical Design at Multiple Sites N Appendix N... FOR NUCLEAR POWER PLANTS Pt. 52, App. N Appendix N to Part 52—Standardization of Nuclear Power Plant...

  7. 77 FR 24712 - Ocean Transportation Intermediary License; Applicants

    Science.gov (United States)

    2012-04-25

    ... Global Logistics LLC (OFF), 9816 Whithorn Drive, Suite B, Houston, TX 77095, Officer: Herbert R. Hogg, Operating Manager (Qualifying Individual), Application Type: New OFF License. Toyo Logistics America, Inc... Individual), Application Type: New NVO License. Choiceone Logistics, Inc. (NVO & OFF), 10025 NW 116th Way, 17...

  8. 75 FR 69080 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2010-11-10

    ... license as a Non-Vessel-Operating Common Carrier (NVO), and/or Ocean Freight Forwarder (OFF)--Ocean..., Building 14-A, Kenner, LA 70062, Officers: Gary J. Cheramie, President (Qualifying Individual), George...: License Transfer. Total Global Solutions, Inc. (NVO & OFF), 4290 Bells Ferry Road 224, Suite 106, Kennesaw...

  9. Nuclear power plant licensing in Canada

    International Nuclear Information System (INIS)

    Tong, J.S.C.; Waddington, J.G.

    1997-01-01

    The Canadian nuclear power plant licensing practice which has evolved over three decades provides a regulatory framework that promotes safe design and operation of CANDU power plants. From the very outset, it recognizes the need for simple and reliable safety systems which are separate from the systems that are normally used to produce electricity. Further, it requires the reliability of safety systems be demonstrated by routine tests during plant operation. Over the three decades, the analysis requirements to demonstrate the performance and reliability of plant systems that have a role in the detection and mitigating of accidents have also evolved. Today's requirements are defined in consultative documents C-6 and C-98. One recurring theme throughout the evolution of the licensing practice is the maxim of prescribing only basic safety requirements and rules so that designers and operators have the freedom to devise the best possible design features and operating practices

  10. Roundtable discussion: Materials management issues supporting licensing renewal

    International Nuclear Information System (INIS)

    1991-01-01

    The purpose of this technical session is to discussion the relationships between nuclear materials management/procurement engineering and plant license renewal. The basis for the discussion is DG-1009 'Standard format and content of technical information for applications to renew nuclear power plant operating licenses', dated 12/90

  11. Four Essays on Technology Licensing and Firm Innovation

    DEFF Research Database (Denmark)

    Moreira, Solon

    &D strategies. On the supply side, the existing literature has been focused on understanding how technology licensing can be used by firms as a mechanism to recover investments in innovative activities and to foster learning opportunities. On the demand side, it has been shown that licensing is an important...... source that firms can tap into to feed their internal needs for innovative knowledge. While several studies have examined technology licensing through the lens of the licensor, research on how firms rely on licensing contracts to acquire knowledge and improve their innovation performance still leaves......Licensing contracts represent one of the most widely used mechanisms to exchange technologies and transfer know-how between firms. Due to the opportunities that licensing creates for firms operating on both sides of the markets for technology, it has increasingly become an integral part of firms’ R...

  12. Safety-evaluation report related to the renewal of the operating license for the Cornell University TRIGA Research Reactor. Docket No. 50-157

    International Nuclear Information System (INIS)

    1983-08-01

    This Safety Evaluation Report for the application filed by the Cornell University for a renewal of Operating License R-80 to continue to operate a research reactor has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is owned and operated by Cornell University and is located on the Cornell campus in Ithaca, New York. The staff concludes that the TRIGA reactor facility can continue to be operated by Cornell without endangering the health and safety of the public

  13. U.S. regulatory requirements for nuclear plant license renewal: The B and W Owners Group License Renewal Program

    International Nuclear Information System (INIS)

    Staudinger, Deborah K.

    2004-01-01

    This paper discusses the current U.S. Regulatory Requirements for License Renewal and describes the Babcock and Wilcox Owners Group (B and WOG) Generic License Renewal Program (GLRP). The B and W owners, recognizing the need to obtain the maximum life for their nuclear generating units, embarked on a program to renew the licenses of the seven reactors in accordance with the requirements of the Atomic Energy Act of 1954 and further defined by Title 10 of the Code of Federal Regulation Part 54 (10 CFR 54). These reactors, owned by five separate utilities, are Pressurized Water Reactors (PWR) ranging in net rated capacity from approximately 800 to 900 MW. The plants, predominately constructed in the 70s, have USNRC Operating Licenses that expire between 2013 to 2017. (author)

  14. Safety Evaluation Report related to the renewal of the operating license for the Westinghouse research reactor at Zion, Illinois (Docket No. 50-87)

    International Nuclear Information System (INIS)

    1984-09-01

    This Safety Evaluation Report, for the application filed by the Westinghouse Electric Company, for renewal of operating license number R-119 to continue to operate the research reactor, has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is operated by Westinghouse and is located in Zion, Illinois. The staff concludes that the reactor facility can continue to be operated by Westinghouse without endangering the health and safety of the public

  15. RM - ODP to express nuclear licensing

    International Nuclear Information System (INIS)

    Barbosa, E.A.; Martucci, M. Jr.

    2002-01-01

    The scope of CNEN (Comissao Nacional de Energia Nuclear) is established by standards and procedures, which allow one context where several activities for nuclear licensing are realized by persons, machines and other entities of real world and by software systems. The CNEN objectives for licensing nuclear installations can be specified and they define how the systems are consisted, its nature, and which important elements were considered relevant for its constitution. The behavior, where the software will be operated, was likely defined in this paper through all aspects of its business process, which means from its licensing context. The concepts and definition showed here defined one specifics business domain, through ODP context. The functionalities of nuclear licensing process, the relationship scope and the rules of interaction that contributed for to specify the nuclear licensing process were defined, too. Therefore, the definition of the domain follows the orientation of architecture concepts and allows to implement the reflection model, where, with the auxiliary from IDEF0 (Integration Definition for Function Modeling) diagrams, the interactions between extern domains were mapped

  16. SSM's licensing review of a spent nuclear fuel repository in Sweden

    International Nuclear Information System (INIS)

    Dverstorpand, Bjoern; Stroemberg, Bo

    2014-01-01

    On 16 March 2011 the Swedish Nuclear Fuel and Waste Management Co. (SKB) submitted license applications for a general license to construct, possess and operate a KBS-3 type spent nuclear fuel repository at the Forsmark site, in Oesthammar municipality, and an encapsulation plant in Oskarshamn municipality. The KBS-3 method, which has been developed by SKB over a period of more than 30 years, entails disposing of the spent fuel in copper canisters, surrounded by a swelling bentonite clay, at about 500 m depth in crystalline basement rock. SKB's applications are being evaluated in parallel by the Swedish Radiation Safety Authority (SSM) according to the Act on Nuclear Activities and by the Land and Environmental Court according to the Environmental Code. During the review SSM will act as an expert review body to the Land and Environmental Court in the areas of radiation protection, safety and security/non-proliferation. Both SSM and the court will produce a statement with a recommendation regarding a licensing decision and licensing conditions to the government. The government will make the final decision after consulting the municipalities concerned by SKB's facilities (municipal veto applies). The current licensing decision is just one of several licensing decisions that will be required for the repository. However it is arguably the most important one, because it is the last licensing stage with a broad societal involvement including an environmental impact assessment (EIA) process, national consultations and municipal veto for the concerned municipalities. The licensing steps to follow, should SKB be granted a license by the government, only require approval by SSM. These steps include application for start of actual construction work, test operation and routine operation. (authors)

  17. Comparative Analysis of Hydraulic Fracturing Wastewater Practices in Unconventional Shale Development: Newspaper Coverage of Stakeholder Concerns and Social License to Operate

    Directory of Open Access Journals (Sweden)

    Joel Gehman

    2016-09-01

    Full Text Available In this article we review prior literature regarding the concept of social license to operate, and related concepts, including corporate social responsibility, sustainable development, stakeholder management and cumulative effects. Informed by these concepts, we search for newspaper articles published in North American provinces and states where the Barnett, Duvernay, Marcellus and Montney shale plays are located. Using these data, we tabulate coverage of stakeholder concerns related to hydraulic fracturing and wastewater practices, and compare the extent to which these concerns vary over place and time. Our vocabulary analyses identify differences in the types and quantities of newspaper coverage devoted to concerns regarding hydraulic fracturing activities in general and wastewater practices in particular. We interpret these differences as suggesting that obtaining a social license to operate is likely not a one size fits all proposition. By understanding which stakeholder concerns are most salient in particular places and times, oil and gas operators and regulators can better tailor their strategies and policies to address local concerns. In other words, the findings from this study indicate that conventional understandings of risk as a technical or economic problem may not be adequate for dealing with unconventional resource challenges such as hydraulic fracturing. Operators and regulators may also need to manage social and cultural risks.

  18. 78 FR 66713 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2013-11-06

    ..., Washington, DC 20573, by telephone at (202) 523-5843 or by email at [email protected] . Action One Logistics, Inc..., Operating Manager (QI), Joseph Lam, Member, Application Type: New NVO License. Altex US, LLC (NVO & OFF), 1... President, Application Type: New NVO & OFF License. Andes Logistics USA LLC (NVO & OFF) 7500 NW 25 Street, 7...

  19. Safety evaluation report related to the renewal of the operating license for the Washington State University TRIGA reactor. Docket No. 50-27

    International Nuclear Information System (INIS)

    1982-05-01

    This Safety Evaluation Report for the application filed by the Washington State University (WSU) for a renewal of operating license number R-76 to continue to operate a research reactor has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is owned and operated by the Washington State University and is located on the WSU campus in Pullman, Whitman County, Washington. The staff concludes that the TRIGA reactor facility can continue to be operated by WSU without endangering the health and safety of the public

  20. 10 CFR Appendix N to Part 50 - Standardization of Nuclear Power Plant Designs: Permits To Construct and Licenses To Operate...

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 1 2010-01-01 2010-01-01 false Standardization of Nuclear Power Plant Designs: Permits To Construct and Licenses To Operate Nuclear Power Reactors of Identical Design at Multiple Sites N Appendix N... FACILITIES Pt. 50, App.N Appendix N to Part 50—Standardization of Nuclear Power Plant Designs: Permits To...

  1. 10 CFR 40.33 - Issuance of a license for a uranium enrichment facility.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 1 2010-01-01 2010-01-01 false Issuance of a license for a uranium enrichment facility... License Applications § 40.33 Issuance of a license for a uranium enrichment facility. (a) The Commission... the licensing of the construction and operation of a uranium enrichment facility. The Commission will...

  2. Licensing of the TRIGA Mark III reactor at the Mexican Nuclear Centre

    International Nuclear Information System (INIS)

    Ramirez, R.M.; Arrendondo, R.R.

    1990-01-01

    The TRIGA Mark III reactor at the Mexican Nuclear Centre went critical in 1968 and remained so until 1979 when the National Commission for Nuclear Safety and Safeguards (CNSNS), the Mexican regulatory authority, was set up. The reactor was therefore operating without a formal operating license, and the CNSNS accordingly requested the ININ to license the reactor under the existing conditions and to ensure that any modification of the original design complied with Standards ANSI/ANS-15 and with the code of practice set out in IAEA Safety Series No. 35. The most relevant points in granting the operating licence were: (a) the preparation of the Safety Report; (b) the formulation and application of the Quality Assurance Programme; (c) the reconditioning of the following reactor systems: the cooling systems; the ventilation and exhaust system; the monitoring system and control panel; (d) the training of the reactor operating staff at junior and senior levels; and (e) the formulation of procedures and instructions. Once the provisional operating license was obtained for the reactor it was considered necessary to modify the reactor core, which has been composed of 20% enriched standards fuel, to a mixed core based on a mixture of standard fuel and FLIP-type fuel with 70% 235 U enrichment. The CNSNS therefore requested that the mixed core be licensed and a technical report was accordingly annexed to the Safety Report, its contents including the following subjects: (a) neutron analysis of the proposed configuration; (b) reactor shutdown margins; (c) accident analysis; and (d) technical specifications. The licensing process was completed this year and we are now hoping to obtain the final operating license

  3. Licensing issues associated with the use of computers in the nuclear industry

    International Nuclear Information System (INIS)

    Ehrenberger, W.D.; Bloomfield, R.E.

    1987-01-01

    Computers are increasingly important to ensuring the safety of nuclear power stations. They have been proposed or introduced into operator information systems, operational control systems, as well as into systems for core protection and plant protection. Although the developments in the individual countries are not at the same pace, they do tend to render similar results. Particular licensing problems arise because of the increasing complexity of computer systems and the software involved. In the past licensing has been closely connected with the mental understanding of the systems to be licensed. This understanding is endangered with greater complexity of the systems. Although several ''manual'' methods of licensing exist, the problem of cost effective licensing is still more or less unsolved. For the future it is expected that tools will reduce the licensing efforts leaving the licenser and assessor free to concentrate on the most important issues. Such tools will probably make use of artificial intelligence techniques. They will enable the inclusion of more complex functions into safety systems and thereby increase the number of safety criteria and the number of echelons od defense. Another important use of artificial intelligence techniques will be the area of operator information systems and maintenance, including computer hardware maintenance. They will provide early detection of problems in the plant and thereby largely enhance plant availability and safety. Further studies are being proposed in the fields of software licensing tools, artificial intelligence, fail-safe and fault-tolerant software architectures, test procedures and system specification

  4. Whom to Choose as License Partner?

    DEFF Research Database (Denmark)

    Laursen, Keld; Reichstein, Toke; Trombini, Giulia

    2013-01-01

    benefits and obviate issues related to technology transfer and knowledge recombination. At the same time, firms wish to select a partner operating in a different product market to minimize competitive downside issues and to access other product markets, skills and resources. We contend interdependence...... between technology and market forces: if partners are market distant, the likelihood of technology license contractual partnership decreases with partners’ technological distance. Using data on the formation of license partnerships in the global biopharmaceutical industry over the period 1994...

  5. Establishment of regulatory framework for the development reactor licensing

    International Nuclear Information System (INIS)

    Jo, Jong C.; Yune, Young G.; Kim, Woong S.; Ahn, Sang K.; Kim, In G.; Kim, Hho J.

    2003-01-01

    With a trend that various types of advanced reactor designs are currently under development worldwide, the Korea Atomic Energy Research Institute has been developing an advanced reactor called ' System-integrated Modular Advanced Reactor (SMART)', which is a small sized integral type pressurized water reactor with a rated thermal power of 330 MW. To demonstrate the safety and the performance of the SMART reactor design, the SMART Research and Development Center has embarked to build a scaled-down pilot plant of SMART, called 'SMART-P' with a rated thermal power of 65 MW. In preparation for the forthcoming applications for both construction permit and operating license of SMART-P in the near future, the Korea Institute of Nuclear Safety is developing a new regulatory framework for licensing review of such a development reactor, which covers establishment of licensing process, identification and resolution of technical and safety issues, development of regulatory evaluation or verification-purpose computer codes and analytical methods, and establishment of design-specific, general design and operating criteria, regulations, and associated regulatory guides. This paper presents the current activities for establishing a regulatory framework for the licensing of a research and development reactor. Discussions are made on the SMART-P development program, the current Korean regulatory framework for reactor licensing, the SMART-P licensing-related issues, and the approach and strategy for developing an effective regulatory framework for the SMART-P licensing

  6. Trends in CANDU licensing

    International Nuclear Information System (INIS)

    Snell, V.G.; Grant, S.D.

    1997-01-01

    Modern utilities view nuclear power more and more as a commodity - it must compete 'today' with current alternatives to attract their investment. With its long construction times and large capital investment, nuclear plants are vulnerable to delays once they have been committed. There are two related issues. Where the purchaser and the regulator are experienced in CANDU, the thrust is a very practical one: to identify and resolve major licensing risks at a very early stage in the project. Thus for a Canadian project, the designer (AECL) and the prospective purchaser would deal directly with the AECB. However CANDU has also been successfully licensed in other countries, including Korea, Romania, Argentina, India and Pakistan. Each of these countries has its own regulatory agency responsible for licensing the plant. In addition, however, the foreign customer and regulator may seek input from the AECB, up to and including a statement of licensability in Canada; this is not normally needed for a ''repeat'' plant and/or if the customer is experienced in CANDU, but can be requested if the plant configuration has been modified significantly from an already-operating CANDU. It is thus the responsibility of the designer to initiate early discussions with the AECB so the foreign CANDU meets the expectations of its customers

  7. Future of nuclear licensing

    International Nuclear Information System (INIS)

    Denton, H.R.

    1984-01-01

    The following topics are outlined: Comparison of US and best foreign experience in nuclear power plant construction and operation; Status of licensing and construction; Observed attributes; Reduced construction time; Fewer reactor trips; Higher capacity factor; Diesel generator reliability; Steam generator tube leakage; and US regulatory initiatives: NRC efforts and industry efforts

  8. Motorcycle Training for California Driver Licensing Personnel. Final Report.

    Science.gov (United States)

    California State Dept. of Motor Vehicles, Sacramento.

    The development of a 6-hour motorcycle course of instruction for personnel responsible for motorcycle licensing is described in this project report. The primary goals are stated and include (1) training driver licensing personnel in motorcycle safety and principles of operation, and (2) purchasing and installing appropriate motorcycle skill…

  9. Analysis of license renewal at U.S. Nuclear Power Plants

    International Nuclear Information System (INIS)

    Nagayama, Munehiro

    2017-01-01

    The U.S. NRC had implemented the rules for LR (License Renewal) of NPPs (Nuclear Power Plants) and the LR rules allow plus 20-year operation of NPPs adding to initial 40-year term for reactor license. The U.S. NRC has already issued ROL (Renewed Operating License) for over forty NPPs. The Atomic Energy Act do not limit the number of LR, so the fleet of U.S. Nuclear, including agency, industry and academy, is continuing efforts to develop rules for SLR (Subsequent License Renewal). The framework of SLR rules has been developed and there is a plan of implementation of SLR for a pilot plant on FY 2018. The total operating term of a SLR plant is 80-year. The LR/SLR of NPPs is effective for stable power supply, greenhouse gas suppression, maintenance of technology, and securing employment. These profits will return to society. It is important to maintain required function of SSCs (Structure, System, and Components) for period of long term operation of NPPs. The U.S. fleet has established integrated ageing management strategy and each NPPs is developing their maintenance plans for long term operation. These adequate maintenance plans may enable to achieve good capacity factor of LR applied NPPs. In this report, domestic LR position will be considered by referring the good performance of U.S. NPPs which entered long term operation beyond 40-year and some conditions such as energy security. (author)

  10. Environmental assessment for final rule on nuclear power plant license renewal

    International Nuclear Information System (INIS)

    1991-12-01

    The Atomic Energy Act and Nuclear Regulatory Commission (NRC) regulations provide for the renewal of nuclear power plant operating licenses beyond their initial 40-year term. The Act and NRC regulations, however, do not specify the procedures, criteria, and standards that must be satisfied in order to renew a license. The NRC is promulgating a rule (10 CFR Part 54) to codify such requirements prior to the receipt of applications for license renewal. The NRC has assessed the possible environmental effects of promulgating requirements in 10 CFR Part 54 now rather than employing such requirements in an ad hoc manner in individual licensing actions. The final part 54 rule requires the development of information and analyses to identify aging problems of systems, structures, and components unique to license renewal that will be of concern during the period of extended operation and will not be controlled by existing effective programs. In general, licensee activities for license renewal may involve replacement, refurbishment, inspection, testing, or monitoring. Such actions will be generally be within the range of similar actions taken for plants during the initial operating term. These actions would be primarily confined within the plants with potential for only minor disruption to the environment. It is unlikely that these actions would change the operating conditions of plants in ways that would change the environmental effects already being experienced. Relicensing under existing regulations would also be primarily focused on aging degradation and would likely result in requirements similar to those that will result from relicensing under the final rule

  11. Managing the high level waste nuclear regulatory commission licensing process

    International Nuclear Information System (INIS)

    Baskin, K.P.

    1992-01-01

    This paper reports that the process for obtaining Nuclear Regulatory Commission permits for the high level waste storage facility is basically the same process commercial nuclear power plants followed to obtain construction permits and operating licenses for their facilities. Therefore, the experience from licensing commercial reactors can be applied to the high level waste facility. Proper management of the licensing process will be the key to the successful project. The management of the licensing process was categorized into four areas as follows: responsibility, organization, communication and documentation. Drawing on experience from nuclear power plant licensing and basic management principles, the management requirement for successfully accomplishing the project goals are discussed

  12. Nuclear fuel licensing requirements: present status and future trends

    International Nuclear Information System (INIS)

    Gantchev, T.; Vitkova, M.; Gorinov, I.; Datcheva, D.; Rashkova, N.

    2001-01-01

    The nuclear fuel licensing process must be directed to establishing of criteria for licensing (fuel safety criteria) and relationship between safety limits, technical specifications and operational conditions. This paper discusses the fuel safety criteria as used by NRC and Russian vendor. A survey on the available fuel behavior, modeling and related computer codes is given with respect to help the licensing process including new safety features of general changes in fuel design and operational conditions. Several types of computer codes that are used in safety analysis are sensitive to fuel-related parameters. The need for further code development and verification has been stated on many occasions: new design elements, such as different cladding materials, higher burnup, different fuel microstructure and use of MOX fuel can affect the performance of these codes. Regulatory inspection practices during operation and refueling in different countries are also shown. Future trends are discussed in particular with regard to the coming high burnup and to new core management schemes

  13. Licensing of MAPLE reactors in Canada

    International Nuclear Information System (INIS)

    Lee, A.G.; Labrie, J.P.; Langman, V.J.

    1999-01-01

    Full text: The Operating Licence for a MAPLE reactor (i.e., a 10 MW(th), pool-type reactor), has been approved by the Atomic Energy Control Board (AECB) on August 16th, 1999. This Operating Licence has been obtained within three years of the initiation of the MDS Nordion Medical Isotopes Reactor (MMIR) project, which entails the design, construction and commissioning of two 10 MW MAPLE reactors at AECL's Chalk River Laboratories. The scope and nature of the information required by the AECB, the licensing process and highlights of the events which led to successfully obtaining the Operating Licence for the MAPLE reactor are discussed. These discussions address all phases of the licensing process (i.e., the environmental assessment in support of siting, the Preliminary Safety Analysis Report, PSAR, in support of design, procurement and construction, the Final Safety Analysis Report, FSAR, in support of commissioning and operations, and the development of suitable quality assurance subprograms for each phase). An overview of some of the unique technical aspects associated with the MAPLE reactors, and how they have been addressed during the licensing process are also provided (e.g., applying CSA N285.0, General Requirements for Pressure-Retaining Systems and Components in CANDU Nuclear Power Plants, to a small, low pressure, low temperature research reactor, confirmation of the performance of the driver fuel via laboratory and/or in-reactor testing, validation of the computer codes used to perform the safety analyses, critical parameter uncertainty assessment, full scale hydraulic testing of the performance of the design, fuel handling, human factors validation, operator training and certification). (author)

  14. Future of Nuclear Power: NRC emergency preparedness licensing activities agenda

    International Nuclear Information System (INIS)

    Essig, T.H.

    1995-01-01

    This talk summary addresses the issue of how future policies of the NRC will affect nuclear power in areas such as construction, emergency preparedness, and licensing. Specific topics covered include the following: Emergent EP licensing issues for operating nuclear Power Plants; 10CFR Part 52 and the process for licensing of Advanced Light Water Reactors (ALWRs); and potential revisions to emergency preparedness programs for future nuclear power plants

  15. Safety Evaluation Report related to the renewal of the operating license for the research reactor at Manhattan College (Docket No. 50-199)

    International Nuclear Information System (INIS)

    1985-02-01

    This Safety Evaluation Report for the application filed by Manhattan College (MC) for a renewal of Operating License R-94 to continue to operate the MC 0.1-W open-pool training reactor has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is owned and operated by MC and is located two blocks away from the MC main campus in the Riverdale area of New York City, New York. The staff concludes that the reactor facility can continue to be operated by MC without endangering the health and safety of the public

  16. Nuclear regulation. License renewal questions for nuclear plants need to be resolved

    International Nuclear Information System (INIS)

    Fultz, Keith O.; Kruslicky, Mary Ann; McDowell, William D. Jr.; Coleman, Robert L.

    1989-04-01

    A December 1986 pipe rupture at Virginia Power's Surry unit 2 nuclear power plant injured eight workers; four later died. As a result of this accident, Representative Edward J. Markey requested GAO to examine the Surry accident and assess the problems confronting aging nuclear plants. In March 1988 we reported our findings concerning the accident and a July 1987 incident at the Trojan nuclear plant in Oregon. This report addresses problems confronting aging nuclear plants by examining the Nuclear Regulatory Commission's (NRC) program to develop a license renewal policy and accompanying regulations, and the initiatives underway by the Department of Energy (DOE) and the electric utility industry to extend the operating lives of these plants. Nuclear power has become second only to coal as the largest producer of electricity in the United States. The 110 nuclear plants currently in service are operated by 54 utilities, provide about 20 percent of the nation's electricity, and represent a capital investment of over $200 billion. The Atomic Energy Act authorizes NRC to issue nuclear plant operating licenses for up to 40 years and provides for license extensions beyond the initial operating period. The act does not, however, stipulate the criteria for evaluating a utility request to operate a nuclear plant longer than 40 years. The oldest operating license currently in effect will expire in the year 2000. According to NRC, about one-half of the existing operating licenses will terminate by the year 2015, and most licenses will expire by about 2030. Many utilities will have to decide in the early 1990s whether to continue operating older nuclear plants or to construct new generating capacity. A clear understanding of the terms and conditions governing the license renewal process will be a key element in deciding how to meet future electricity demand. Although NRC has developed 3 possible license renewal policy options and identified 15 areas of regulatory uncertainty that

  17. The changing shape of U.S. licensing philosophy

    International Nuclear Information System (INIS)

    Remick, F.J.

    1992-01-01

    The shape of U.S. nuclear licensing and regulatory philosophy and process has already changed. The new process requires NRC review and approval of the vendor designs before a prospective utility license applicant purchases the design and begins construction. The new philosophy has resulted from the lessons learned from extensive operating experience accumulated in the United States. New criteria established for judging reactor designs include the capability of future designs to be more tolerant of accidents beyond the traditional design basis events. Qualitative and quantitative goals have been chosen as a guide for allocating resources for regulation of the currently operating plants. The changing shape of nuclear licensing and regulatory philosophy is also a result of economic circumstances in the United States. All will have a better opportunity to take part in the process which is most likely to encourage further development of safe nuclear energy in the United States. (author)

  18. Safety Evaluation Report related to the full-term operating license for Dresden Nuclear Power Station, Unit 2 ( Docket No. 50-237)

    International Nuclear Information System (INIS)

    1990-10-01

    The Safety Evaluation Report for the full-term operating license application filed by Commonwealth Edison Company for the Dresden Nuclear Power Station, Unit 2, has been prepared by the Office of Nuclear Regulation of the US Nuclear Regulatory Commission. The facility is located in Grundy County, Illinois. Subject to favorable resolution of the items discussed in this report, the staff concludes that the facility can continue to be operated without endangering the health and safety of the public. 72 refs

  19. Safety evaluation report related to the renewal of the operating license for the Zero-Power Reactor at Cornell University, Docket No. 50-97

    International Nuclear Information System (INIS)

    1983-09-01

    This Safety Evaluation Report for the application filed by Cornell University (CU) for a renewal of Operating License R-80 to continue to operate a zero-power reactor (ZPR) has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is owned and operated by Cornell University and is located on the Cornell campus in Ithaca, New York. The staff concludes that the ZPR facility can continue to be operated by CU without endangering the health and safety of the public

  20. Experience in Cuba in the licensing during import, commissioning and operation of an Irradiator LLCo ISOGAMMA

    International Nuclear Information System (INIS)

    Forteza, Yamil Lopez; Reyes, Yolanda Perez; Garcia, Jose R. Quevedo; Molina, Igor I. Sarabia; Gonzalez, Leonel Omarovich; Zubiaur, Omar Cruz

    2013-01-01

    This work presented the experiences during the process of licensing an irradiator ISOGAMMA LLCo model according to the recommendations of the International Atomic Energy (IAEA). Aspects of the safety assessment are detailed, as well as control and verification requirements for radiation safety and security at different stages of the process (import, transportation, installation irradiator loading 60Co sources, commissioning and operation) of irradiator recently installed in Cuba. The results of the evaluation carried a source of reference and consultation necessary for the work of the regulator to consider for similar processes that lie ahead in other facilities irradiation

  1. Dry spent fuel storage licensing

    International Nuclear Information System (INIS)

    Sturz, F.C.

    1995-01-01

    In the US, at-reactor-site dry spent fuel storage in independent spent fuel storage installations (ISFSI) has become the principal option for utilities needing storage capacity outside of the reactor spent fuel pools. Delays in the geologic repository operational date at or beyond 2010, and the increasing uncertainty of the US Department of Energy's (DOE) being able to site and license a Monitored Retrievable Storage (MRS) facility by 1998 make at-reactor-site dry storage of spent nuclear fuel increasingly desirable to utilities and DOE to meet the need for additional spent fuel storage capacity until disposal, in a repository, is available. The past year has been another busy year for dry spent fuel storage licensing. The licensing staff has been reviewing 7 applications and 12 amendment requests, as well as participating in inspection-related activities. The authors have licensed, on a site-specific basis, a variety of dry technologies (cask, module, and vault). By using certified designs, site-specific licensing is no longer required. Another new cask has been certified. They have received one new application for cask certification and two amendments to a certified cask design. As they stand on the brink of receiving multiple applications from DOE for the MPC, they are preparing to meet the needs of this national program. With the range of technical and licensing options available to utilities, the authors believe that utilities can meet their need for additional spent fuel storage capacity for essentially all reactor sites through the next decade

  2. ITER licensing

    International Nuclear Information System (INIS)

    Gordon, C.W.

    2005-01-01

    ITER was fortunate to have four countries interested in ITER siting to the point where licensing discussions were initiated. This experience uncovered the challenges of licensing a first of a kind, fusion machine under different licensing regimes and helped prepare the way for the site specific licensing process. These initial steps in licensing ITER have allowed for refining the safety case and provide confidence that the design and safety approach will be licensable. With site-specific licensing underway, the necessary regulatory submissions have been defined and are well on the way to being completed. Of course, there is still work to be done and details to be sorted out. However, the informal international discussions to bring both the proponent and regulatory authority up to a common level of understanding have laid the foundation for a licensing process that should proceed smoothly. This paper provides observations from the perspective of the International Team. (author)

  3. Safety Evaluation Report related to the renewal of the operating license for the research reactor at Purdue University: Docket No. 50-182

    International Nuclear Information System (INIS)

    1988-04-01

    This Safety Evaluation Report for the application filed by Purdue University for a renewal of Operating License R-87 to continue to operate a research reactor has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is owned by Purdue University and is located on the campus in West Lafayette, Indiana. On the basis of its technical review, the staff concludes that the reactor facility can continue to be operated by the university without endangering the health and safety of the public or the enviroment

  4. NRC Licensing Status Summary Report for NGNP

    Energy Technology Data Exchange (ETDEWEB)

    Moe, Wayne Leland [Idaho National Lab. (INL), Idaho Falls, ID (United States); Kinsey, James Carl [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2014-11-01

    The Next Generation Nuclear Plant (NGNP) Project, initiated at Idaho National Laboratory (INL) by the U.S. Department of Energy (DOE) pursuant to provisions of the Energy Policy Act of 2005, is based on research and development activities supported by the Department of Energy Generation IV Nuclear Energy Systems Initiative. The principal objective of the NGNP Project is to support commercialization of high temperature gas-cooled reactor (HTGR) technology. The HTGR is a helium-cooled and graphite moderated reactor that can operate at temperatures much higher than those of conventional light water reactor (LWR) technologies. The NGNP will be licensed for construction and operation by the Nuclear Regulatory Commission (NRC). However, not all elements of current regulations (and their related implementation guidance) can be applied to HTGR technology at this time. Certain policies established during past LWR licensing actions must be realigned to properly accommodate advanced HTGR technology. A strategy for licensing HTGR technology was developed and executed through the cooperative effort of DOE and the NRC through the NGNP Project. The purpose of this report is to provide a snapshot of the current status of the still evolving pre-license application regulatory framework relative to commercial HTGR technology deployment in the U.S. The following discussion focuses on (1) describing what has been accomplished by the NGNP Project up to the time of this report, and (2) providing observations and recommendations concerning actions that remain to be accomplished to enable the safe and timely licensing of a commercial HTGR facility in the U.S.

  5. Presentation of reports for licensing of industrial irradiators

    International Nuclear Information System (INIS)

    2000-04-01

    This Regulation refers to the requirements of the Regulation CNEN-NE.6.02. 'Licensing of Radioactive Facilities', expressed in the section 6 related to the information for Previous Approval, in the subsection 7.2 related to the information for the Construction Licensing and in the subsection 9.2, related to the information for the Authorization for operation, for the specific case of industrial irradiators

  6. Regulations and the licensing process in Austria

    International Nuclear Information System (INIS)

    Matulla, Herbert U.

    1979-01-01

    A review of the licensing process which took place from 1971 to 1978 shows which laws, regulations and standards were used in checking the safety aspects of the nuclear power plant and which organisations participated in the licensing process. The internal organisation of the Austrian main-expert in the procedure is illustrated. Examples of detail-work are explained. The importance of intensive co-operation of the different technical groups and the problems of comparable examination depth are underlined. (author)

  7. License plate recognition using DTCNNs

    NARCIS (Netherlands)

    ter Brugge, M.H; Stevens, J.H; Nijhuis, J.A G; Spaanenburg, L; Tavsanonoglu, V

    1998-01-01

    Automatic license plate recognition requires a series of complex image processing steps. For practical use, the amount of data to he processed must be minimized early on. This paper shows that the computationally most intensive steps can be realized by DTCNNs. Moreover; high-level operations like

  8. Licensing the California low-level radioactive waste disposal facility

    International Nuclear Information System (INIS)

    Dressen, A.L.; Serie, P.J.; Junkert, R.

    1992-01-01

    California has made significant progress toward the issuance of a license to construct and operate the Southwestern Compact's low-level radioactive waste disposal facility. However, obstacles to completing construction and preparing to receive waste still exist. This paper will describe the technical licensing issues, EIR/S process, political events, and public interactions that have impacted on California regulators' ability to complete the license application review and reach a decision on issuing a license. Issues associated with safely and liability evaluations, finalization of the environmental impact report, and land transfer processes involving multiple state, federal, and local agencies will be identified. Major issues upon which public and political opposition is focusing will also be described. (author)

  9. The licensing process of the design modifications of Cernavoda 2 NPP resulting from the operating experience of CANDU plants

    International Nuclear Information System (INIS)

    Goicea, L.

    2005-01-01

    The CANDU 6 plant now under construction in Cernavoda include over two hundred significant improvements made in order to comply with current codes and standards and licensing requirements relative to the operating CANDU 6 in Romania. These evolutionary improvements are incorporated in CANDU 6 design taking advance of CANDU operating experience, of the designer company research and development and technical advances worldwide in order to further enhance safety, reliability and economics. This paper gives a general idea of the evaluation of the modifications of the Cernavoda 2 nuclear power plant against the design of Cernavoda 1 and states the safety principles and requirements which are the basis for this evaluation. (author)

  10. AV Licensing Brings Kids & Media Together

    Science.gov (United States)

    Watson, Elizabeth; Maloney, Brenda D.

    1975-01-01

    The Fitchburg, Massachusetts, Public Library holds training sessions for children on the use of audiovisual equipment, and licenses children who have learned how to operate the equipment so they may check it out and take it home. (LS)

  11. 78 FR 37324 - Preparation of Environmental Reports for Nuclear Power Plant License Renewal Applications

    Science.gov (United States)

    2013-06-20

    ... Environmental Reports for Nuclear Power Plant License Renewal Applications AGENCY: Nuclear Regulatory Commission... for Nuclear Power Plant License Renewal Applications.'' This regulatory guide provides guidance to... renewal of a nuclear power plant operating license. Applicants should use this regulatory guide when...

  12. Safety Evaluation Report related to the renewal of the operating license for the research reactor at Michigan State University (Docket No. 50-294)

    International Nuclear Information System (INIS)

    1984-08-01

    This Safety Evaluation Report for the application filed by the Michigan State University (MSU) for a renewal of operating license number R-114 to continue to operate the TRIGA Mark I research reactor has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is owned and operated by the Michigan State University and is located on the campus of Michigan State University in East Lansing, Ingham County, Michigan. The staff concludes that the TRIGA reactor facility can continue to be operated by MSU without endangering the health and safety of the public

  13. Issues related to the licensing of final disposal facilities for radioactive waste

    International Nuclear Information System (INIS)

    Medici, M.A.; Alvarez, D.E.; Lee Gonzales, H.; Piumetti, E.H.; Palacios, E.

    2010-01-01

    The licensing process of a final disposal facility for radioactive waste involves the design, construction, pre-operation, operation, closure and post closure stages. While design and pre-operational stages are, to a reasonable extent, similar to other kind of nuclear or radioactive facilities, construction, operation, closure and post-closure of a radioactive waste disposal facility have unique meanings. As consequence of that, the licensing process should incorporate these particularities. Considering the long timeframes involved at each stage of a waste disposal facility, it is convenient that the development of the project being implemented in and step by step process, be flexible enough as to adapt to new requirements that would arise as a consequence of technology improvements or due to variations in the socio-economical and political conditions. In Argentina, the regulatory Standard AR 0.1.1 establishes the general guideline for the 'Licensing of Class I facilities (relevant facilities)'. Nevertheless, for radioactive waste final disposal facilities a new specific guidance should be developed in addition to the Basic Standard mentioned. This paper describes the particularities of final disposal facilities indicating that a specific licensing system for this type of facilities should be foreseen. (authors) [es

  14. Atomic Safety and Licensing Board Panel annual report, fiscal year 1989

    International Nuclear Information System (INIS)

    Cotter, B.P. Jr.

    1990-07-01

    In Fiscal Year 1989, the Atomic Safety and Licensing Board Panel (ASLBP) handled 40 proceedings involving the construction, operation and maintenance of commercial nuclear power reactors or other activities requiring a license from the Nuclear Regulatory Commission. This report summarizes, highlights and analyzes how the wide-ranging issues raised in these proceedings were addressed by the Judges and Licensing Boards of the ASLBP during the year. 5 figs., 3 tabs

  15. Safety evaluation report related to the renewal of the operating license for the research reactor at the University of Florida. Docket No. 50-83

    International Nuclear Information System (INIS)

    1982-05-01

    This Safety Evaluation Report for the application filed by the University of Florida (UF) for a renewal of Operating License R-56 to continue to operate its Argonaut-type research reactor has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is owned and operated by the University of Florida and is located on the UF campus in Gainesville, Alachua County, Florida. The staff concludes that the reactor facility can continue to be operated by UF without endangering the health and safety of the public

  16. Lessons learned from the licensing process and the operational performance of the important to safety digital application implemented at the Mexican nuclear facilities

    International Nuclear Information System (INIS)

    Ledesma-Carrion, R.

    1998-01-01

    This paper describes the main concerns detected during the licensing processes performed by the Mexican Nuclear Regulatory Commission (CNSNS) for the NUMAC-PRNM, the Integrated Computer Systems at the Laguna Verde Nuclear Power Station (LVNPS) and for the Digital Control Console of the Triga Mark III Research Reactor (TMRR). The review and approval process was performed following the guidelines of the US Nuclear Regulatory Commission (USNRC); the regulatory frame applied includes the Code of Federal Regulation (10CFR50), some Regulatory Guides, such as: RG 1.152, RG 1.153, some Industrial Standards, for example: IEEE-279, IEEE-603, IEEE-7.4.3-2. Also, based on the operational experience taken from the LVNPS License Event Report (LER) reported under the 10CFR50.72 and 10CFR50.73 USNRC rules, and from the Report of Events to be Analyzed (REA) issued for a CNSNS agreement with the utility stated by the necessity to determine failure rates of digital equipment, some case studies and a preliminary failure cause classification is shown. The Event Report evaluation covered topics related to the software, hardware and firmware issues. Finally, the lessons learned from the licensing assessments and from the operational experience of the digital applications implemented are presented. It will also give the regulatory activities related to an IAEA international cooperation project on I and C digital upgrade concerns. (author)

  17. Safety evaluation report related to the renewal of the operating license for the University of New Mexico Research Reactor (Docket No. 50-252)

    International Nuclear Information System (INIS)

    1987-03-01

    This Safety Evaluation Report for the application filed by the University of New Mexico (UNM) for renewal of Operating License No. R-102 to continue to operate its research reactor has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located on the campus of the University of New Mexico in Albuquerque, New Mexico. The staff concludes that the reactor can continue to be operated by the University of New Mexico without endangering the health and safety of the public. 7 refs., 7 figs., 2 tabs

  18. Safety Evaluation Report related to the renewal of the operating license for the General Electric-Nuclear Test Reactor (GE-NTR) (Docket No. 50-73)

    International Nuclear Information System (INIS)

    1984-09-01

    This Safety Evaluation Report for the application filed by the General Electric Company (GE) for a renewal license number R-33 to continue to operate its research reactor has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is owned and operated by GE and is located in Pleasanton, California. The staff concludes that the reactor can continue to be operated by GE without endangering the health and safety of the public

  19. Safety and licensing issues for Indian PHWRs

    International Nuclear Information System (INIS)

    Srinivasan, G.R.; Das, M.

    1997-01-01

    India has achieved competency in design, construction, commissioning and operation of Pressurized Heavy Water Reactor based Nuclear Power Plants and has completed more than 120 reactor operating years with an extremely satisfactory safety record. In this paper, the safety management in NPCIL and operational safety aspects are discussed, licensing and regulatory approach is described and some of the main safety issues for Indian PHWRs are brought out. (author)

  20. Atomic Safety and Licensing Board Panel annual report, Fiscal year 1992

    International Nuclear Information System (INIS)

    1993-09-01

    In Fiscal Year 1992, the Atomic Safety and Licensing Board Panel (''the Panel'') handled 38 proceedings. The cases addressed issues in the construction, operation, and maintenance of commercial nuclear power reactors and other activities requiring a license from the Nuclear Regulatory Commission. This reports sets out the Panel's caseload during the year and summarizes, highlights, and analyzes how the wide-ranging issues raised in those proceedings were addressed by the Panel's judges and licensing boards

  1. Demonstrating safety during license renewal should not be a large task

    International Nuclear Information System (INIS)

    Berto, D.S.

    1993-01-01

    The principal regulatory goal related to nuclear power plant operation is to ensure the health and safety of the public. The principal goal of extended plant operation via the license renewal process is also to ensure the health and safety of the public. The license renewal documentation issued by the Nuclear Regulatory Commission (NRC) provides guidance on what will be acceptable to the NRC in a license renewal application to demonstrate that this goal will be met. Application of this guidance is currently open to wide interpretation, with many of the current approaches proving to be extremely costly, complex, and uncertain of acceptability. This paper evaluates the requirements necessary to ensure the continued health and safety of the public during any license renewal term. This evaluation is based on the stated goals of the License Renewal Rule and on the published bases for the Rule. An approach to License Renewal is recommended that: (1) meets the stated goals of the NRC; (2) is consistent with current regulatory practices; and (3) will continue to ensure the health and safety of the public. This recommended approach is also much less costly than other current approaches, and can be easily agreed to by all participants. This approach will meet regulatory goals, while removing the cost and uncertainty obstacles currently being confronted by utilities. Providing a viable approach to license renewal will allow the renewal process to be pursued by utilities. Without such an approach, safe and reliable nuclear power plants will be permanently shut down at the arbitrary 40 year license limit

  2. Licensing reform: a case study in public participation in the nuclear field

    International Nuclear Information System (INIS)

    Nordlinger, M.S.

    1993-01-01

    Political process and legal procedures join to accord the public a significant role in nuclear energy policy decision-making in the United States. We changed the two-stage license process in a combined license process with no separation between the construction and operating license, the policy statement requests public comment, allowing days for responses. It is a middle way between information and taking part in decision

  3. AP1000R licensing and deployment in the United States

    International Nuclear Information System (INIS)

    Jordan, R. P.; Russ, P. A.; Filiak, P. P.; Castiglione, L. L.

    2012-01-01

    In recent years, both domestic and foreign utilities have turned to the standardized Westinghouse AP1000 plant design in satisfying their near - and long-term - sustainable energy needs. As direct support to these actions, licensing the AP1000 design has played a significant role by providing one of the fundamental bases in clearing regulatory hurdles leading to the start of new plant construction. Within the U.S. alone, Westinghouse AP1000 licensing activities have reached unprecedented milestones with the approvals of both AP1000 Design Certification and Southern Company's combined construction permit and operating license (COL) application directly supporting the construction of two new nuclear plants in Georgia. Further COL application approvals are immediately pending for an additional two AP1000 plants in South Carolina. And, across the U.S. nuclear industry spectrum, there are 10 other COL applications under regulatory review representing some 16 new plants at 10 sites. In total, these actions represent the first wave of new plant licensing under the regulatory approval process since 1978. Fundamental to the Nuclear Regulatory Commission's AP1000 Design Certification is the formal recognition of the AP1000 passive safety design through regulatory acceptance rulemaking. Through recognition and deployment of the AP1000 Design Certification, the utility licensee / operator of this reactor design are now offered an opportunity to use a simplified 'one-step' combined license process, thereby managing substantial back-end construction schedule risk from regulatory and intervention delays. Application of this regulatory philosophy represents both acceptance and encouragement of standardized reactor designs like the AP1000. With the recent AP1000 Design Certification and utility COL acceptances, the fundamental licensing processes of this philosophy have successfully proven the attainment of significant milestones with the next stage licensing actions directed

  4. Importance of the licensing process on the safety culture in the Brazilian nuclear fuel cycle facilities

    International Nuclear Information System (INIS)

    Motta, E.S.; Sousa, A.L.B. de; Paiva, R.L.C. de; Mezrahi, A.

    2013-01-01

    The main objective of the Nuclear Fuel Cycle Facilities licensing processes is to ensure the safety of these installations in their entire life cycle (in the installation site selection, designing, construction, pre-operational tests, operational and decommissioning phases). The Brazilian licensing process requires from the operator, among others, before the operating license: (I) a Site Report and a Final Safety Analysis Report, ensuring that all safety related issues are adequately analyzed and understood; (II) a formal structured Management System focused on the installation safety; and (III) dissemination of safety related information to all involved operator employees and subcontractors. Therefore, these requirements reflect in an adequate operator actions and practices, ensuring a working environment with a high level of safety culture. (author)

  5. Importance of the licensing process on the safety culture in the Brazilian nuclear fuel cycle facilities

    Energy Technology Data Exchange (ETDEWEB)

    Motta, E.S.; Sousa, A.L.B. de; Paiva, R.L.C. de; Mezrahi, A., E-mail: emotta@cnen.gov.br [Comissao Nacional de Energia Nuclear (CNEN-RJ), Rio de Janeiro, RJ (Brazil)

    2013-07-01

    The main objective of the Nuclear Fuel Cycle Facilities licensing processes is to ensure the safety of these installations in their entire life cycle (in the installation site selection, designing, construction, pre-operational tests, operational and decommissioning phases). The Brazilian licensing process requires from the operator, among others, before the operating license: (I) a Site Report and a Final Safety Analysis Report, ensuring that all safety related issues are adequately analyzed and understood; (II) a formal structured Management System focused on the installation safety; and (III) dissemination of safety related information to all involved operator employees and subcontractors. Therefore, these requirements reflect in an adequate operator actions and practices, ensuring a working environment with a high level of safety culture. (author)

  6. The role the safety analysis report and other documents in the licensing procedure in the Federal Republic of Germany

    International Nuclear Information System (INIS)

    Albrecht, E.; Ballhaus, S.

    1975-01-01

    Legal requirements for the licensing procedure, requirements for and preparation of licensing documents, authorities and experts participating in the licensing procedure, course of the atomic licensing procedure e.g. application for construction and operation, public hearing, site and concept license, partial licenses. (HP) [de

  7. 77 FR 20353 - United States Warehouse Act; Export Food Aid Commodities Licensing Agreement

    Science.gov (United States)

    2012-04-04

    ... licensing agreement include, but are not limited to, corn soy blend, vegetable oil, and pulses such as peas, beans, and lentils. USWA licensing is a voluntary program. Warehouse operators that apply for USWA...

  8. Safety Evaluation Report related to renewal of the operating license for the CAVALIER Training Reactor at the University of Virginia (Docket No. 50-396)

    International Nuclear Information System (INIS)

    1985-05-01

    This Safety Evaluation Report for the application filed by the University of Virginia for a renewal of Operating License R-123 to continue to operate the CAVALIER (Cooperatively Assembled Virginia Low Intensity Educational Reactor) has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is owned and operated by the University of Virginia and is located on the campus in Charlottesville, Virginia. Based on its technical review, the staff concludes that the reactor facility can continue to be operated by the university without endangering the health and safety of the public or the environment

  9. Safety evaluation report related to the renewal of the operating license for the Worcester Polytechnic Institute open-pool training reactor, Docket No. 50-134

    International Nuclear Information System (INIS)

    1982-12-01

    This Safety Evaluation Report for the application filed by the Worcester Polytechnic Institute (WPI) for a renewal of Operating License R-61 to continue to operate the WPI 10-kW open-pool training reactor has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is owned and operated by the Worcester Polytechnic Institute and is located on the WPI campus in Worcester, Worcester County, Massachusetts. The staff concludes that the reactor facility can continue to be operated by WPI without endangering the health and safety of the public

  10. Safety Evaluation Report related to the renewal of the operating license for the research reactor at the University of Kansas (Docket No. 50-148)

    International Nuclear Information System (INIS)

    1984-05-01

    This Safety Evaluation Report for the application filed by the University of Kansas (KU) for a renewal of Operating License R-78 to continue to operate the KU 250-kW open-pool training reactor has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is owned and operated by the University of Kansas and is located on the KU campus in Lawrence, Douglas County, Kansas. The staff concludes that the reactor facility can continue to be operated by KU without endangering the health and safety of the public. 17 references, 11 figures, 4 tables

  11. CNRA/CSNI workshop on licensing and operating experience of computer-based I and C systems - Summary and conclusions

    International Nuclear Information System (INIS)

    2002-01-01

    The OECD Workshop on Licensing and Operating Experience of Computer-Based I and C Systems, was sponsored by both the Committee on Nuclear Regulatory Activities (CNRA) and the Committee on the Safety of Nuclear Installations (CSNI) of the OECD Nuclear Energy Agency (NEA). It was organised in collaboration with the Czech State Office for Nuclear Safety (SUJB), the Czech Power Board CEZ a.s., I and C Energo a.s. and the Nuclear Research Institute, Rez near Prague. The objectives of the Workshop were to exchange the experience gained by both the regulators and the industry in different countries in the licensing and operation of computer-based I and C systems, to discuss the existing differences in their licensing approaches in various countries, to consider the safety aspects of their practical use, and to discuss the ways of promoting future international co-operation in the given area. The scope of the Workshop included: - review of the progress made since the CNRA/CSNI workshop which was held in 1996 - current and future regulatory needs and/or requirements for the computer-based I and C systems - progress made in software life cycle activities, including verification and validation, and safety/hazards analysis - benefits of applying the computer-based I and C systems to improve plant performance and safety. The Technical Sessions and Discussion Sessions covered the following topics: Opening Session: Advances made in the use and planning of computer-based I and C systems; Topic 1: National and international standards and guides for computer-based safety systems; Topic 2: Regulatory aspects; Topic 3: Analysis and assessment of digital I and C systems; Topic 4: Software life cycle activities; Topic 4: Experience with applications, system aspects, potential limits and future trends and needs; Final Session: Workshop summary. The workshop provided a unique opportunity for people with experience in licensing, developing, manufacturing, implementing, maintaining or

  12. Safety Evaluation Report, related to the renewal of the operating license for the critical experiment facility of the Rensselaer Polytechnic Institute (Docket No. 50-225)

    International Nuclear Information System (INIS)

    1983-10-01

    This Safety Evaluation Report for the application filed by the Rensselaer Polytechnic Institute (RPI) for a renewal of operating license CX-22 to continue to operate a critical experiment facility has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is owned and operated by Rensselaer Polytechnic Institute and is located at a site in the city of Schenectady, New York. The staff concludes that this critical facility can continue to be operated by RPI without endangering the health and safety of the public

  13. Licensing process for future applications of advanced-design nuclear reactors

    International Nuclear Information System (INIS)

    Miller, C.L.

    1990-01-01

    The existing 10CFR50 two-step licensing process in the Code of Federal Regulations can continue to be a viable licensing vehicle for future applications, at least for the near future. The US Nuclear Regulatory Commission (NRC) Commissioners and staff, the public, and the utilities (along with supporting architect/engineers and nuclear steam supply system vendors) have a vast body of experience and knowledge of the existing part 50 licensing process. All these participants are familiar with their respective roles in this process, and history shows this process to be a workable licensing vehicle. Nevertheless, the use of 10CFR52 should be encouraged for future applications. This proposed new rule is intended to achieve the early resolution of licensing issues, to reduce the complexity and uncertainty of the licensing process, and enhance the safety and reliability of nuclear power plants. Part 52's overall purpose is to improve reactor safety and streamline the licensing process by encouraging the use of standard reactor designs and by allowing the early resolution of site environmental and reactor safety issues. The public should be afforded an earlier entry into the licensing process as a result of design certification rulemaking process and combined construction permit/operating license hearings

  14. Licensing authority's control of radiation sources and nuclear materials in Brazil

    International Nuclear Information System (INIS)

    Binns, D.A.C.

    2002-01-01

    Full text: The Brazilian Nuclear Energy Commission is the national licensing authority and among its responsibilities is the control of nuclear materials and radiation sources. This control is carried out in three different ways: 1) Control of the import and export of nuclear materials and radiation sources. To be able to import or export any nuclear material or radiation source, the user has to have an explicit permission of the licensing authority. This is controlled by electronic means in which the user has to fill a special form found on the licensing authority's home page, where he has to fill in his name, license number, license number of his radiation protection officer and data of the material to be imported or exported. These data are checked with a data base that contains all the information of the licensed users and qualified personnel before authorization is emitted. The airport authorities have already installed x-ray machines to check all baggages entering or leaving the country. 2) Transport and transfer permit for radiation sources. In order to transport and/or transfer radiations sources and nuclear materials within the country, the user(s) have to submit an application to the licensing authority. The user(s) fill out an application form where he fills in his company's name, licensing I.D., radiation protection officer's name and I.D and identification of the sources involved. These information are checked with the licensing operations data before the operations is permitted. 3) Inspections and radiation monitoring systems. Routine and regulatory inspections are continuously carried out where the user's radiation sources and nuclear materials inventory are checked. Also the physical security and protection of these materials are verified. The installation of monitoring systems is an item that is being discussed with the airport authorities so as to increase the possibilities of detecting any illegal transport of these materials. (author)

  15. Overview of the role of economics in plant life management license renewal in the U.S

    International Nuclear Information System (INIS)

    Young, G.G.; Nelson, A.P.

    2002-01-01

    Full text: In 1995, the U.S. Nuclear Regulatory Commission (NRC) published a revised rule in 10 CFR Part 54 that provides the requirements for an operating nuclear plant to seek license renewal. U.S. nuclear power plants obtain a 40-year initial operating license, but under 10 CFR Part 54, additional terms of 20-years each may be obtained through license renewal. Prior to 1995, the estimated cost just to prepare a license renewal application was about $40 million. Under the revised rule, the cost to prepare an application was reduced to about $10 million or less. Although the revised rule generated considerable interest, the decision to seek license renewal is fundamentally an economic decision. In 1995, many people believed that only a select few operating nuclear plants would pursue license renewal and that most would operate for no more than 40 years. The primary reason for this belief was that the cost of keeping U.S. nuclear plants running did not appear to be competitive with other forms of electricity generation. By 1998, the economic conditions in the U.S. were changing dramatically. Electricity deregulation was moving ahead, the need for electricity was growing, and the operating costs for nuclear power plants were declining. Also, in 1998, the first two applications for license renewal were submitted to the NRC by Baltimore Gas and Electric for the two-unit Calvert Cliffs nuclear power plant and by Duke Energy for the three-unit Oconee nuclear power plant. The U.S. nuclear industry was somewhat skeptical that the NRC could complete the license renewal process in a timely and predictable manner. This skepticism was due to the protracted and unpredictable process used by the NRC to approve the original operating licenses, especially in the 1980's and early 1990's. In March 2000, the NRC approved the renewal of the 40-year operating licenses for the two-unit Calvert Cliffs nuclear power plant for an additional 20 years. Two months later, the NRC approved the

  16. 10 CFR 50.43 - Additional standards and provisions affecting class 103 licenses and certifications for...

    Science.gov (United States)

    2010-01-01

    ..., paragraphs (a) through (e) of this section apply in the case of a class 103 license for a facility for the... electric energy, if otherwise qualified, from obtaining a construction permit or operating license under... over a sufficient range of normal operating conditions, transient conditions, and specified accident...

  17. 47 CFR 13.17 - Replacement license.

    Science.gov (United States)

    2010-10-01

    ... 47 Telecommunication 1 2010-10-01 2010-10-01 false Replacement license. 13.17 Section 13.17 Telecommunication FEDERAL COMMUNICATIONS COMMISSION GENERAL COMMERCIAL RADIO OPERATORS General § 13.17 Replacement... request a replacement. The application must be accompanied by the required fee and submitted to the...

  18. The current role of simulators for performance evaluations and licensing (case of Mexico)

    International Nuclear Information System (INIS)

    Maldonado A, H.

    1997-01-01

    The main purpose of this paper is to share the experience acquired by the National Commission of Nuclear Safety and Safeguards (CNSNS) during the administration of both certification and licensing operational exams applied to Senior Reactor Operators (SRO) and Reactor OPerators (RO) by using a full-scope simulator. The licensing operational exams are administered to examinate candidates for a SRO or RO license while the certification operational exams are administered to all personnel that possess a SRO or RO license in order to renew their licenses within a six years period. A general description with the most important simulator antecedents from the initial authorization for its usage to provide the ''Initial Simulator Training Course'' until currently in which it has been started the installation and testing performance of a new computer equipment that will improve and increase the simulation capacity of the Laguna Verde Nuclear Power Plant (LVNPP) simulator. In other hand, it is showed the process that the CNSNS will apply during the next verification of the simulator certification which should be performed due to the old computer equipment is being replaced with a more modern computer equipment so that the simulation capability will be improved. The verification process was discussed with the utility personnel and as result of this an agreement has been established to carry into effect this hard task. Finally, the conclusions and recommendations from regulators point of view are presented regarding to the importance of perform a well both evaluation and verification of simulators performance. (author)

  19. License application approach for the California LLRW disposal facility

    International Nuclear Information System (INIS)

    Gaynor, R.K.; Romano, S.A.; Hanrahan, T.P.

    1990-01-01

    US Ecology, Inc. is the State of California's license designee to site, develop and operate a low-level radioactive waste (LLRW) disposal facility to serve member states of the Southwestern Compact. US Ecology identified a proposed site in the Ward Valley of southeastern California in March 1988. Following proposed site selection, US Ecology undertook studies required to prepare a license application. US Ecology's license application for this desert site was deemed complete for detailed regulatory review by the California Department of Health Services (DHS) in December 1989. By mutual agreement, disposal of mixed waste is not proposed pending the State of California's decision on appropriate management of this small LLRW subset

  20. Compliance with driver's license laws and illegal licensing among commercial bus drivers in Lagos, Nigeria: policy implications and evidence for action.

    Science.gov (United States)

    Okafor, I P; Odeyemi, K A; Dolapo, D C; Adegbola, A A

    2014-09-01

    To determine the level of compliance with driver's license laws among commercial bus drivers in Lagos, Nigeria. Two intercity motor parks were selected by simple random sampling and all consenting minibus drivers participated in the study. Key Informant Interviews (KIIs) were also conducted with selected officials in the driver training and licensing authorities. Compliance with the minimum age for driving was high (93.6%), so also was having driving test prior to driver's license procurement (83.3%). Formal driver training and VA testing were very low, (26.1% and 32.9% respectively) Overall, only 9.3% of them were found to have fulfilled all the pre-license obligations before obtaining their first driver's license. The odds of a driver with a secondary education having formal driver training is 3.33 times higher than those with no education (OR 3.33, 95% CI 1.01-11.35). Drivers who were 60 years or older were 3.62 times more likely to be compliant than those who were between 20-29 years (OR 3.62, 95% CI 0.56-29.19). For the 98.3% of them who possessed valid licenses, 52.3% of them obtained them illegally. All the key officials saw RTIs as a serious public health problem but faced several challenges in the course of their work. Overall compliance with pre-license regulations was very poor. There is need for a review and strict enforcement of driver's license laws to improve compliance. Also vital are fostering inter-sectoral collaboration and improvement in the operations of all establishments involved in driver training and license procurement in Nigeria.

  1. Comparative Analysis of Hydraulic Fracturing Wastewater Practices in Unconventional Shale Development: Newspaper Coverage of Stakeholder Concerns and Social License to Operate

    OpenAIRE

    Joel Gehman; Dara Y. Thompson; Daniel S. Alessi; Diana M. Allen; Greg G. Goss

    2016-01-01

    In this article we review prior literature regarding the concept of social license to operate, and related concepts, including corporate social responsibility, sustainable development, stakeholder management and cumulative effects. Informed by these concepts, we search for newspaper articles published in North American provinces and states where the Barnett, Duvernay, Marcellus and Montney shale plays are located. Using these data, we tabulate coverage of stakeholder concerns related to hydra...

  2. Safety Evaluation Report related to the construction permit and operating license for the research reactor at the University of Texas (Docket No. 50-602)

    International Nuclear Information System (INIS)

    1985-05-01

    This Safety Evaluation Report for the application filed by the University of Texas for a construction permit and operating license to construct and operate a TRIGA research reactor has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is owned and operated by the University of Texas and is located at the university's Balcones Research Center, about 7 miles (11.6 km) north of the main campus in Austin, Texas. The staff concludes that the TRIGA reactor facility can be constructed and operated by the University of Texas without endangering the health and safety of the public

  3. Management of the licensing of users of radioactive materials should be improved

    International Nuclear Information System (INIS)

    1976-01-01

    Radioactive material licenses are required for manufacturing nuclear fuel for reactors and for industrial, commercial, medical, and educational uses of radioactive materials. This type of license is not for constructing or operating nuclear power reactors and facilities for processing used nuclear fuels. This report discusses the need for better management improvements in the NRC's program for licensing the users. As of December 31, 1974, there were 8,253 active NRC-issued material licenses held by 6,310 licensees. The study reviewed NRC's policies, procedures, and practices, and examined recent evaluations of state programs to identify problems encountered by the states

  4. Role of check operators in achieving operational excellence at Virginia Power's nuclear stations

    International Nuclear Information System (INIS)

    Shriver, B.L.; Williams, T.M.; Stewart, W.L.

    1987-01-01

    Virginia Power has implemented a Check Operator Program as a part of its commitment to excellence in the operation of the North Anna and Surry nuclear power stations. The Check Operator Program utilizes highly qualified licensed personnel to independently evaluate the performance of licensed operators and senior operators during normal, abnormal and simulated emergency conditions. Emphasis is placed upon individual and team performance as well as the procedures and training which support the operators. The check operators report to line management to ensure that their recommendations are implemented into the overall operations philosophy of the power station

  5. Licensing of the proposed PBMR-SA

    International Nuclear Information System (INIS)

    Clapisson, G.A.; Henderson, N.R.; Hill, T.F.; Keenan, N.H.; Metcalf, P.E.; Mysenkov, A.

    1997-01-01

    This paper describes the preliminary criteria, which are intended to be used by the South African regulatory authority (CNS), for licensing of the ESKOM proposed - South African high temperature gas-cooled Pebble Bed Modular Reactor (PBMR-SA). The CNS intends to apply the existing CNS licensing approach together with some international design criteria used for advanced reactors as well as international experience gained from the safety evaluation of the MHTGR, THTR, etc. A major requirement to this type of reactor is that it should comply with the current CNS risk criteria and provide, as a minimum, the same degree of protection to the operator, public and environment that is required for the current generation of nuclear reactors. (author)

  6. Licensing process for safety-critical software-based systems

    Energy Technology Data Exchange (ETDEWEB)

    Haapanen, P. [VTT Automation, Espoo (Finland); Korhonen, J. [VTT Electronics, Espoo (Finland); Pulkkinen, U. [VTT Automation, Espoo (Finland)

    2000-12-01

    System vendors nowadays propose software-based technology even for the most critical safety functions in nuclear power plants. Due to the nature of software faults and the way they cause system failures new methods are needed for the safety and reliability evaluation of these systems. In the research project 'Programmable automation systems in nuclear power plants (OHA)', financed together by the Radiation and Nuclear Safety Authority (STUK), the Ministry of Trade and Industry (KTM) and the Technical Research Centre of Finland (VTT), various safety assessment methods and tools for software based systems are developed and evaluated. As a part of the OHA-work a reference model for the licensing process for software-based safety automation systems is defined. The licensing process is defined as the set of interrelated activities whose purpose is to produce and assess evidence concerning the safety and reliability of the system/application to be licensed and to make the decision about the granting the construction and operation permissions based on this evidence. The parties of the licensing process are the authority, the licensee (the utility company), system vendors and their subcontractors and possible external independent assessors. The responsibility about the production of the evidence in first place lies at the licensee who in most cases rests heavily on the vendor expertise. The evaluation and gauging of the evidence is carried out by the authority (possibly using external experts), who also can acquire additional evidence by using their own (independent) methods and tools. Central issue in the licensing process is to combine the quality evidence about the system development process with the information acquired through tests, analyses and operational experience. The purpose of the licensing process described in this report is to act as a reference model both for the authority and the licensee when planning the licensing of individual applications

  7. Licensing process for safety-critical software-based systems

    International Nuclear Information System (INIS)

    Haapanen, P.; Korhonen, J.; Pulkkinen, U.

    2000-12-01

    System vendors nowadays propose software-based technology even for the most critical safety functions in nuclear power plants. Due to the nature of software faults and the way they cause system failures new methods are needed for the safety and reliability evaluation of these systems. In the research project 'Programmable automation systems in nuclear power plants (OHA)', financed together by the Radiation and Nuclear Safety Authority (STUK), the Ministry of Trade and Industry (KTM) and the Technical Research Centre of Finland (VTT), various safety assessment methods and tools for software based systems are developed and evaluated. As a part of the OHA-work a reference model for the licensing process for software-based safety automation systems is defined. The licensing process is defined as the set of interrelated activities whose purpose is to produce and assess evidence concerning the safety and reliability of the system/application to be licensed and to make the decision about the granting the construction and operation permissions based on this evidence. The parties of the licensing process are the authority, the licensee (the utility company), system vendors and their subcontractors and possible external independent assessors. The responsibility about the production of the evidence in first place lies at the licensee who in most cases rests heavily on the vendor expertise. The evaluation and gauging of the evidence is carried out by the authority (possibly using external experts), who also can acquire additional evidence by using their own (independent) methods and tools. Central issue in the licensing process is to combine the quality evidence about the system development process with the information acquired through tests, analyses and operational experience. The purpose of the licensing process described in this report is to act as a reference model both for the authority and the licensee when planning the licensing of individual applications. Many of the

  8. Finnish experiences on licensing and using of programmable digital systems in nuclear power plants

    International Nuclear Information System (INIS)

    Haapanen, P.; Maskuniitty, M.; Heimburger, H.; Hall, L.E.; Manninen, T.

    1993-01-01

    Finnish utility companies, Imatran Voima Oy (IVO) and Teollisuuden Voima (TVO), and the licensing authority, the Finnish Centre for Radiation and Nuclear Safety (STUK), are preparing for a new nuclear power plant in Finland. Plant vendors are proposing programmable digital automation systems for both the safety-related and the operational I and C (instrumentation and control) systems in this new unit. Also in existing plant units the replacement of certain old analog systems with state-of-the-art digital ones will become necessary in the years to come. Licensing of programmable systems for safety critical applications requires a new approach due to the special properties and failure modes of these systems. The major difficulties seem to be in the assessment and quantification of software reliability. The Technical Research Centre of Finland has in co-operation with the authority and the utilities conducted a project (AJA) to develop domestically applicable licensing requirements, guidelines and practices. International standards, guidelines and licensing practices have been analyzed in order to specify national licensing requirements. The paper describes and discusses the findings and experiences of the AJA project so far. The experience in introducing advanced programmable digital control and computer systems in the operating nuclear power plants will be covered briefly. Although these systems are not safety-related but systems of more general interest regarding nuclear safety, some routines regarding the licensing of safety- related systems have been followed. In these backfitting and replacement projects some experience have been gained in how to license safety-related programmable systems. (Author) 31 refs., 2 figs

  9. ASTM standards associated with PWR and BWR power plant licensing, operation and surveillance

    International Nuclear Information System (INIS)

    McElroy, W.N.; McElroy, R.J.; Gold, R.; Lippincott, E.P.; Lowe, A.L. Jr.

    1994-01-01

    This paper considers ASTM Standards that are available, under revision, and are being considered in support of Pressurized Water Reactor (PWR) and Boiling Water Reactor (BWR) Nuclear Power Plant (NPP) licensing, regulation, operation, surveillance and life attainment. The current activities of ASTM Committee E10 and its Subcommittees E10.02 and current activities of ASTM Committee E10 and its Subcommittees E10.02 and E10.05 and their Task Groups (TG) are described. A very important aspect of these efforts is the preparation, revision, and balloting of standards identified in the ASTM E706 Standard on Master Matrix for Light Water Reactor (LWR) Pressure Vessel (PV) Surveillance Standards. The current version (E706-87) of the Master Matrix identifies 21 ASTM LWR physics-dosimetry-metallurgy standards for Reactor Pressure Vessel (RPV) and Support Structure (SS) surveillance programs, whereas, for the next revision 34 standards are identified. The need for national and international coordination of Standards Technology Development, Transfer and Training (STDTT) is considered in this and other Symposium papers that address specific standards related physics-dosimetry-metallurgy issues. 69 refs

  10. LIPAc personnel protection system for realizing radiation licensing conditions on injector commissioning with deuteron beam

    Energy Technology Data Exchange (ETDEWEB)

    Takahashi, Hiroki, E-mail: takahashi.hiroki@jaea.go.jp [IFMIF/EVEDA Accelerator Group, Japan Atomic Energy Agency (JAEA), Rokkasho, Aomori (Japan); Narita, Takahiro; Kasugai, Atsushi [IFMIF/EVEDA Accelerator Group, Japan Atomic Energy Agency (JAEA), Rokkasho, Aomori (Japan); Kojima, Toshiyuki [Gitec Co. Ltd., Hachinohe, Aomori (Japan); Marqueta, Alvaro; Nishiyama, Koichi [IFMIF/EVEDA Project Team, Rokkasho, Aomori (Japan); Sakaki, Hironao [Quantum Beam Science Center, JAEA, Kizu, Kyoto (Japan); Gobin, Raphael [Commissariat à l’Energie Atomique et aux Energies Alternatives, CEA/Saclay, DSM/IRFU, Gif/Yvette (France)

    2016-11-01

    Highlights: • Personnel Protection System (PPS) is developed to adapt the radiation licensing. • PPS achieves the target performance to secure the personnel safety. • Pulse Duty Management System (PDMS) is developed to manage the beam-operation-time. • Satisfying performance of PDMS is confirmed by injector operation with H+ beam. • By the result of PPS and PDMS tests, the radiation license was successfully obtained. - Abstract: The performance validation of the Linear IFMIF Prototype Accelerator (LIPAc), up to the energy of 9 MeV deuteron beam with 125 mA continuous wave (CW), is planned in Rokkasho, Japan. There are three main phases of LIPAc performance validation: Injector commissioning, RFQ commissioning and LIPAc commissioning. Injector commissioning was started by H{sup +} and D{sup +} beam. To apply the radiation licensing for the Injector commissioning, the entering/leaving to/from accelerator vault should be under control, and access to the accelerator vault has to be prohibited for any person during the beam operation. The Personnel Protection System (PPS) was developed to adapt the radiation licensing conditions. The licensing requests that PPS must manage the accumulated D{sup +} current. So, to manage the overall D{sup +} beam time during injector operation, Pulse Duty Management System (PDMS) was developed as a configurable subsystem as part of the PPS. The PDMS was tested during H{sup +} beam (as simulated D{sup +}) operation, to confirm that it can handle the beam inhibit from Injector before the beam accumulation is above the threshold value specified in the radiation licensing condition. In this paper, the design and configuration of these systems and the result of the tests are presented.

  11. Licensing of the OPAL reactor during construction and commissioning

    International Nuclear Information System (INIS)

    Summerfield, M.

    2007-01-01

    This paper presents a description of the licensing activities associated with the construction and commissioning of the Australian Nuclear Science and Technology Organisation's (ANSTO) OPAL reactor. It addresses the Construction Licence, the interface between ANSTO, INVAP (the contractor with responsibility for design and construction of the facility) and the Australian Radiation Protection and Nuclear Safety Agency (ARPANSA, the Australian nuclear regulator) during the construction of OPAL, specific licensing issues that have arisen during the construction and commissioning process, and the Operating Licence Application. Particular emphasis will be given to the way in which the licensing process is integrated into the overall project program and the lessons learnt that may be of benefit to other licensees and regulators

  12. The Atomic Energy Control Board requirements for the radioisotope licensing of a radiopharmaceutical facility

    International Nuclear Information System (INIS)

    Kennedy, P.

    1980-01-01

    Items that must be addressed by an applicant for a radioisotope license in Canada are described. Site, design and operating conditions, safety assessment, organization, emergency procedures and operating policies and procedures must be described to the Atomic Energy Control Board (AECB), in support of any license application. All information submitted in support of the application is subject to AECB's policy on public access to that information. (OT)

  13. The licensing support system (LSS): Who should operate it and will it work?

    International Nuclear Information System (INIS)

    Macnabb, M.L.; Pflum, C.

    1991-01-01

    The development of the mammoth Licensing Support System (LSS), a management information system intended to handle documentation relevant to the licensing application of the DOE for the High Level Nuclear Waste Repository is not conforming to statute, regulation or intent. At the present stage of its development, it is a quagmire of legal, regulatory and technical difficulties which has the DOE and the NRC arguing over its implementation and budget. This paper examines some of the failures of the system and concludes that many of the DOE functions should now be transferred to a disinterested and independent third party under the auspices of the NRC in order to meet the intent of its creators

  14. The licensing procedure under Atomic Energy Law

    International Nuclear Information System (INIS)

    Ronellenfitsch, M.

    1983-01-01

    This post-doctoral thesis of 1981 has been updated to include developments in this field up to the year 1983. The author discusses in detail all questions relating to the peaceful uses of nuclear energy in the Federal Republic of Germany, predominantly from the point of view of administrative law. He investigates nuclear energy and its contribution to electricity supplies with a view to other energy sources, renewable energy sources, alternative energy policies, nuclear fuel and the fuel cycle, development of the nuclear industry, nuclear power stations in operation, under construction, or in development. Following a survey of the nuclear controversy, both on the national and the international level, the author reviews the legal system and arising controversies in the Federal Republic of Germany, defining the purpose of this thesis to be the systematic analysis of the available legal instruments, in order to show structural deficiencies in the planning law relating to nuclear power stations, and thus reasons of ambiguities within the licensing procedure. The author studies the following terms and requirements: licensing requirements and licensability, the licensing method and scenario, the legal character of licences, their contents and effects within the stepwise procedure, and due publication. (HSCH) [de

  15. Image simulation for automatic license plate recognition

    Science.gov (United States)

    Bala, Raja; Zhao, Yonghui; Burry, Aaron; Kozitsky, Vladimir; Fillion, Claude; Saunders, Craig; Rodríguez-Serrano, José

    2012-01-01

    Automatic license plate recognition (ALPR) is an important capability for traffic surveillance applications, including toll monitoring and detection of different types of traffic violations. ALPR is a multi-stage process comprising plate localization, character segmentation, optical character recognition (OCR), and identification of originating jurisdiction (i.e. state or province). Training of an ALPR system for a new jurisdiction typically involves gathering vast amounts of license plate images and associated ground truth data, followed by iterative tuning and optimization of the ALPR algorithms. The substantial time and effort required to train and optimize the ALPR system can result in excessive operational cost and overhead. In this paper we propose a framework to create an artificial set of license plate images for accelerated training and optimization of ALPR algorithms. The framework comprises two steps: the synthesis of license plate images according to the design and layout for a jurisdiction of interest; and the modeling of imaging transformations and distortions typically encountered in the image capture process. Distortion parameters are estimated by measurements of real plate images. The simulation methodology is successfully demonstrated for training of OCR.

  16. Licensing and accident reviews for an HNEC

    International Nuclear Information System (INIS)

    Clark, R.G.

    1978-09-01

    The purpose of this review was to identify siting or other concerns that may indicate limitations on the ability to license a nuclear energy center at Hanford. Several studies on nuclear energy centers have been completed and some have included licensing (regulatory) aspects of siting nuclear power centers. This review however, was primarily to identify any limitations that may affect licensing specifically at an HNEC. The scope included examining existing criteria for siting nuclear facilities, including single reactor and multireactor (multi-unit) sites. To fill a void in other analyses and to gain some perspective on another impact of an HNEC, the scope was extended to analyze the consequences within the HNEC, of a class nine accident at a unit at one site. A predictive model utilized in this analysis was developed from meteorological parameters based on thirty years of meteorological records at Hanford. From this analysis, additional perspective was developed on the relative severity of the effects of rare events, both man made and from unstable conditions in nature, on the operation of (and the ability to license) an energy center at Hanford

  17. Conceptual Design of On-line Based Licensing Review and Assesment System of Nuclear Installations and Nuclear Materials ('PRIBEN')

    International Nuclear Information System (INIS)

    Melani, Ai; Chang, Soon Heung

    2008-01-01

    At the present Indonesia has no nuclear power plant in operation yet, although it is expected that the first nuclear power plant will be operated and commercially available in around the year of 2016 to 2017 in Muria Peninsula. There are only three research reactors, one nuclear fuel fabrication plant for research reactors, and one experimental fuel fabrication plant for nuclear power, one isotope production facility and some other research facilities. All the facility is under Nuclear Energy Regulatory Agency (BAPETEN) controlling through regulation, licensing and inspection. The organizations operation submits licensing application to BAPETEN before utilizing the facility. According to the regulation before BAPETEN give license they perform review and assessment for the utility application. Based on the review and assessment result, BAPETEN may stipulate, reject, delay or terminate the license. In anticipation of expansion of the nuclear program in Indonesia, BAPETEN should have an integrated and updated system for review and asses the licensing application. For this reason, an expert system for the review and asses the licensing application, so-called PRIBEN (Perizinan Reaktor, Instalasi dan Bahan Nuklir/Licensing of Reactor, Nuclear Installations and Nuclear Materials), is developed which runs on the online-based reality environment

  18. AGING MANAGMENT OF REACTOR COOLANT SYSTEM MECHANICAL COMPONENTS FOR LICENSE RENEWAL

    International Nuclear Information System (INIS)

    SUBUDHI, M.; MORANTE, R.; LEE, A.D.

    2002-01-01

    The reactor coolant system (RCS) mechanical components that require an aging management review for license renewal include the primary loop piping and associated connections to other support systems, reactor vessel, reactor vessel internals, pressurizer. steam generators, reactor coolant pumps, and all other inter-connected piping, pipe fittings, valves, and bolting. All major RCS components are located inside the reactor building. Based on the evaluation findings of recently submitted license renewal applications for pressurized water reactors, this paper presents the plant programs and/or activities proposed by the applicants to manage the effects of aging. These programs and/or activities provide reasonable assurance that the intended function(s) of these mechanical components will be maintained for the period of extended operation. The license renewal application includes identification of RCS subcomponents that are within the scope of license renewal and are vulnerable to age-related degradation when exposed to environmental and operational conditions. determination of the effects of aging on their intended safety functions. and implementation of the aging management programs and/or activities including both current and new programs. Industry-wide operating experience, including generic communication by the NRC, is part of the aging management review for the RCS components. In addition, this paper discusses time-limited aging analyses associated with neutron embrittlement of the reactor vessel beltline region and thermal fatigue

  19. Safety Evaluation Report related to the renewal of the operating license for the training and research reactor at the University of Lowell (Docket No. 50-223)

    International Nuclear Information System (INIS)

    1985-11-01

    This Safety Evaluation Report for the application filed by the University of Lowell (UL) for renewal of operating license number R-125 to continue to operate its research reactor has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located on the North Campus of the University of Lowell in Lowell, Massachusetts. The staff concludes that the reactor can continue to be operated by the University of Lowell without endangering the health and safety of the public

  20. Licensed operating reactors. Status summary report, data as of October 31, 1985. Volume 9, No. 11

    International Nuclear Information System (INIS)

    1985-12-01

    The US Nuclear Regulatory Commission's monthly Licensed Operating Reactors Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Resource Management, from the Headquarters Staff of NRC's Office of Inspection and Enforcement, from NRC's Regional Offices, and from utilities. Since all of the data concerning operation of the units is provided by the utility operators less than two weeks after the end of the month, necessary corrections to published information are shown on the errata page. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States. The percentage computations, Items 20 through 24 in Section 2, the vendor capacity factors on page 1-7, and actual vs potential energy production on page 1-2 are computed using actual data for the period of consideration. The percentages listed in power generation on page 1-2 are computed as an arithmetic average. The factors for the life-span of each unit (the ''Cumulative'' column) are reported by the utility and are not entirely re-computed by NRC. Utility power production data is checked for consistency with previously submitted statistics

  1. Two Approaches to Reactor Decommissioning: 10 CFR Part 50 License Termination and License Amendment, Lessons Learned from the Regulatory Perspective

    International Nuclear Information System (INIS)

    Watson, B.A.; Buckley, J.T.; Craig, C.M.

    2006-01-01

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

  2. Safety aspects of nuclear plant licensing in Canada

    International Nuclear Information System (INIS)

    Jennekens, J.H.F.

    1975-01-01

    The legislative authority is laid down in the Atomic Energy Control Act, 1946, declaring atomic energy a matter of national interest and establishing the Atomic Energy Control Board (AECB) as the competent body for regulating all aspects of atomic energy. The Act also vests a Minister designated by the Government with research and exploitation functions; thus, by Ministerial order, Atomic Energy of Canada Limited was established in 1952 as a State-owned company. The Nuclear Liability Act, 1970, channels all liability for nuclear damage to the operator of a nuclear installation and requires him to obtain insurance in the amount of $75 million, part of which may be re-insured by the Government. The licensing requirements comprise the issuance of a site approval, a construction licence and an operating licence. The AECB is assisted in its licensing functions by its Nuclear Plant Licensing Directorate and by the Reactor Safety Advisory Committee co-operating with each other in making extensive safety assessments of a licence application. A site evaluation report, a preliminary safety report and a final safety report are required in relation to the siting, construction and operation of a nuclear power plant. The Canadian reactor safety philosophy is based on the concept of defence in depth, implemented through a multi-step approach, which includes avoidance of malfunctions, provision of special safety systems, periodic inspection and testing, and avoidance of human errors. Specific criteria and principles have evolved in applying this basic safety philosophy and radiation protection standards are derived from international recommendations. Stringent control is exercised over the management of radioactive waste and management facilities must meet the engineering and procedural requirements of AECB before they can be placed in operation. (author)

  3. The selection, licensing, and operation of a low-level radioactive waste incinerator

    International Nuclear Information System (INIS)

    Arrowsmith, H.W.; Dalton, D.

    1990-01-01

    The Scientific Ecology Group has just completed the selection, procurement, licensing, and start-up of a low-level radioactive waste incinerator. This incinerator is the only commercial radioactive waste incinerator in the US and was licensed by the Environmental Protection Agency, the State of Tennessee, the City of Oak Ridge, and the Tennessee Valley Authority. This incinerator has a thermal capacity of 13,000,000 BTUs and can burn approximately 1,000 pounds per hour of typical radioactive waste. Waste to be incinerated is sorted in a new waste sorting system at the SEG facility. The sorting is essential to assure that the incinerator will not be damaged by any unexpected waste and to maintain the purity of the incinerator off-gas. The volume reduction expected for typical waste is approximately 100:1. After burning, the incinerator ash is compacted or vitrified before shipment to burial sites

  4. Technology licensing in China

    DEFF Research Database (Denmark)

    Wang, Yuandi; Li-Ying, Jason; Chen, Jin

    2015-01-01

    We explore the landscape of technology licensing among Chinese entities in the period 2000–12, using a unique database on technological licensing from the State Intellectual Property Office of China. We find that: first, among Chinese licensee organizations, firms have dominated in terms...... of the number of licensed technologies; second, the geographical distribution of licensed technologies among the provinces has gradually reached a new quantitative balance; third, utility models are the most popular technologies to be licensed and the majority of technology licensing in China has been between...... Chinese entities, and most transactions have been local within provinces; and finally, Chinese firms have gradually in-licensed newer and newer technologies, but the technologies in-licensed from foreign sources are by no means state-of-the-art. We make several suggestions for innovation policy...

  5. Regulatory framework for nuclear power plant operation

    International Nuclear Information System (INIS)

    Perez Alcaniz, T.; Esteban Barriendos, M.

    1995-01-01

    As the framework of standards and requirements covering each phase of nuclear power plant project and operation developed, plant owners defined their licensing commitments (codes, rules and design requirements) during the project and construction phase before start-up and incorporated regulatory requirements imposed by the regulatory Body during the licensing process prior to operation. This produces a regulatory framework for operating a plant. It includes the Licensing Basis, which is the starting point for analyzing and incorporating new requirements, and for re-evaluation of existing ones. This presentation focuses on the problems of applying this regulatory framework to new operating activities, in particular to new projects, analyzing new requirements, and reconsidering existing ones. Clearly establishing a plant's licensing basis allows all organizations involved in plant operation to apply the requirements in a more rational way. (Author)

  6. 75 FR 61116 - Refunds Under the Cable Statutory License

    Science.gov (United States)

    2010-10-04

    ... Copyright Act, before it was amended to allow a cable system to calculate its royalty fees on a community-by... statutory license set forth in Section 111 are required to pay royalty fees to the Copyright Office... the methodology for a cable operator to calculate royalty fees. Cable operators now pay royalty fees...

  7. Safety Evaluation Report related to the renewal of the operating license for the TRIGA training and research reactor at the University of Arizona (Docket No. 50-113)

    International Nuclear Information System (INIS)

    1990-05-01

    This Safety Evaluation Report for the application filed by the University of Arizona for the renewal of Operating License R-52 to continue operating its research reactor at an increased operating power level has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located on the University of Arizona campus in Tucson, Arizona. The staff concludes that the reactor can continue to be operated by the University of Arizona without endangering the health and safety of the public. 20 refs., 8 figs., 5 tabs

  8. 37 CFR 404.4 - Authority to grant licenses.

    Science.gov (United States)

    2010-07-01

    ... past infringement. Any license shall not confer on any person immunity from the antitrust laws or from... immunized from the operation of state or federal law by reason of the source of the grant. [71 FR 11512, Mar...

  9. Safety evaluation report related to the renewal of the operating license for the training and research reactor at the University of Maryland (Docket No. 50-166)

    International Nuclear Information System (INIS)

    1984-03-01

    This Safety Evaluation Report for the application filed by the University of Maryland (UMD) for a renewal of operating license R-70 to continue to operate a training and research reactor facility has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is owned and operated by the University of Maryland and is located at a site in College Park, Prince Georges County, Maryland. The staff concludes that this training reactor facility can continue to be operated by UMD without endangering the health and safety of the public

  10. ISO 14000 and the nuclear licensing

    International Nuclear Information System (INIS)

    Martins, Nadia Soido Falcao

    1999-01-01

    As concern grows for maintaining and improving the quality of the environment and protecting human health, all the world is turning its attention to the potential environmental in pact of their industrial activities. One of the most important contribution in that way is the International Standard ISO 14000 series. In the utilization of nuclear energy, right from the inception, the safety of personnel, environment and the population has been the basic consideration. Over the years well established licenses criteria have been proposed to limit and control the environmental impact of the plant operation and emergencies situation. In this paper are discussed some specific requirements for implementation of the environmental management system specified by ISO 14000 compared to the environmental requirements for nuclear licensing. (author)

  11. Reactor licensing process: a status report

    International Nuclear Information System (INIS)

    Long, J.A.

    1977-01-01

    The Nuclear Regulatory Commission (NRC), in its review of applications for licenses to construct and operate nuclear power plants, is required to consider those measures necessary to ensure the protection of the health and safety of the public and the environment. The article discusses the NRC staff procedures and policies for conducting the detailed safety, environmental, and antitrust reviews that provide the basis for these assurances. Included is a discussion of the improvements to the licensing process currently being proposed or implemented to enhance its stability and predictability for the benefit of all involved with the regulation of nuclear power. The views and opinions expressed in the article are those of the author alone and do not represent positions of the NRC

  12. Spatial service delivery system for smart licensing & enforcement management

    Science.gov (United States)

    Wahap, N. A.; Ismail, N. M.; Nor, N. M.; Ahmad, N.; Omar, M. F.; Termizi, A. A. A.; Zainal, D.; Noordin, N. M.; Mansor, S.

    2016-06-01

    Spatial information has introduced a new sense of urgency for a better understanding of the public needs in term of what, when and where they need services and through which devices, platform or physical locations they need them. The objective of this project is to value- add existing license management process for business premises which comes under the responsibility of Local Authority (PBT). Manipulation of geospatial and tracing technology via mobile platform allows enforcement officers to work in real-time, use a standardized system, improve service delivery, and optimize operation management. This paper will augment the scope and capabilities of proposed concept namely, Smart Licensing/Enforcement Management (SLEm). It will review the current licensing and enforcement practice of selected PBT in comparison to the enhanced method. As a result, the new enhanced system is expected to offer a total solution for licensing/enforcement management whilst increasing efficiency and transparency for smart city management and governance.

  13. Conversion to low-enriched fuel in research reactor aspects of licensing the Federal Republic of Germany

    International Nuclear Information System (INIS)

    Jacquemin, J.

    1985-01-01

    Conversion to low-enriched fuel and usage of new developed highly densified fuel in research-reactors will be an essential alteration in operating the reactor. According to the German Energy Act this has to be licensed. here might be some risk to the licensee of an older research-reactor by suspending his operating license because he cannot meet current requirements to be fulfilled or because of a court decision.Disposal of irradiated fuel elements of the new fuel type is a further significant problem which has to be solved before issuing a new license. (author)

  14. AP1000{sup R} licensing and deployment in the United States

    Energy Technology Data Exchange (ETDEWEB)

    Jordan, R. P.; Russ, P. A.; Filiak, P. P.; Castiglione, L. L. [Westinghouse Electric Company LLC, 1000 Westinghouse Drive, Cranberry Township, PA 16066 (United States)

    2012-07-01

    In recent years, both domestic and foreign utilities have turned to the standardized Westinghouse AP1000 plant design in satisfying their near - and long-term - sustainable energy needs. As direct support to these actions, licensing the AP1000 design has played a significant role by providing one of the fundamental bases in clearing regulatory hurdles leading to the start of new plant construction. Within the U.S. alone, Westinghouse AP1000 licensing activities have reached unprecedented milestones with the approvals of both AP1000 Design Certification and Southern Company's combined construction permit and operating license (COL) application directly supporting the construction of two new nuclear plants in Georgia. Further COL application approvals are immediately pending for an additional two AP1000 plants in South Carolina. And, across the U.S. nuclear industry spectrum, there are 10 other COL applications under regulatory review representing some 16 new plants at 10 sites. In total, these actions represent the first wave of new plant licensing under the regulatory approval process since 1978. Fundamental to the Nuclear Regulatory Commission's AP1000 Design Certification is the formal recognition of the AP1000 passive safety design through regulatory acceptance rulemaking. Through recognition and deployment of the AP1000 Design Certification, the utility licensee / operator of this reactor design are now offered an opportunity to use a simplified 'one-step' combined license process, thereby managing substantial back-end construction schedule risk from regulatory and intervention delays. Application of this regulatory philosophy represents both acceptance and encouragement of standardized reactor designs like the AP1000. With the recent AP1000 Design Certification and utility COL acceptances, the fundamental licensing processes of this philosophy have successfully proven the attainment of significant milestones with the next stage licensing

  15. Safety Evaluation Report related to the renewal of the operating license for the training and research reactor at the University of Michigan (Docket No. 50-2)

    International Nuclear Information System (INIS)

    1985-07-01

    This Safety Evaluation Report for the application filed by the University of Michigan (UM) for renewal of the Ford Nuclear Reactor (FNR) operating license number R-28 to continue to operate its research reactor has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located on the North Campus of the University of Michigan in Ann Arbor, Michigan. The staff concludes that the reactor can continue to be operated by the University of Michigan without endangering the health and safety of the public

  16. Safety Evaluation Report related to the renewal of the operating license for the research reactor at the Universiy of Missouri-Rolla (Docket No. 5-123)

    International Nuclear Information System (INIS)

    1984-12-01

    This Safety Evaluation Report for the application filed by the University of Missouri-Rolla for a renewal of Operating License R-79 to continue to operate a research reactor has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is owned by the University of Missouri and is located on the campus in Rolla, Missouri. On the basis of its technical review, the staff concludes that the reactor facility can continue to be operated by the university without endangering the health and safety of the public or the environment

  17. USNRC licensing process as related to nuclear criticality safety

    International Nuclear Information System (INIS)

    Ketzlach, N.

    1987-01-01

    The U.S. Code of Federal Regulations establishes procedures and criteria for the issuance of licenses to receive title to, own, acquire, deliver, receive, possess, use, and initially transfer special nuclear material; and establishes and provides for the terms and conditions upon which the Nuclear Regulatory Commission (NRC) will issue such licenses. Section 70.22 of the regulations, ''Contents of Applications'', requires that applications for licenses contain proposed procedures to avoid accidental conditions of criticality. These procedures are elements of a nuclear criticality safety program for operations with fissionable materials at fuels and materials facilities (i.e., fuel cycle facilities other than nuclear reactors) in which there exists a potential for criticality accidents. To assist the applicant in providing specific information needed for a nuclear criticality safety program in a license application, the NRC has issued regulatory guides. The NRC requirements for nuclear criticality safety include organizational, administrative, and technical requirements. For purely technical matters on nuclear criticality safety these guides endorse national standards. Others provide guidance on the standard format and content of license applications, guidance on evaluating radiological consequences of criticality accidents, or guidance for dealing with other radiation safety issues. (author)

  18. Guidelines for preparing and reviewing applications for the licensing of non-power reactors: Format and Content. NUREG-1537, Part 1

    International Nuclear Information System (INIS)

    1996-02-01

    NUREG - 1537, Part 1 gives guidance to non-power reactor licensees and applicants on the format and content of applications to the Nuclear Regulatory Commission for licensing actions. These licensing actions include construction permits and initial operating licenses, license renewals, amendments, conversions from highly enriched uranium to low-enriched uranium, decommissioning, and license termination

  19. Guidelines for preparing and reviewing applications for the licensing of non-power reactors: Format and Content. NUREG-1537, Part 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-02-01

    NUREG - 1537, Part 1 gives guidance to non-power reactor licensees and applicants on the format and content of applications to the Nuclear Regulatory Commission for licensing actions. These licensing actions include construction permits and initial operating licenses, license renewals, amendments, conversions from highly enriched uranium to low-enriched uranium, decommissioning, and license termination.

  20. Resolving the issues arisen during the development of License Renewal Application at PAKS NPP

    International Nuclear Information System (INIS)

    Ratkai, Sandor; Katona, Tamas Janos

    2012-01-01

    Operational license of the four VVER-440/213 units at Paks NPP, Hungary is limited to the design lifetime of 30 years. Extension by an additional 20 years of the original license is one of the main goals of the plant owner. In 2008 a programme for long-term operation (LTO) was developed and submitted to the Hungarian Atomic Energy Authority. The LTO Programme defines the activities for ensuring the extension of the operational lifetime and contains the justification of the safe LTO. The LTO Programme has to be implemented and comprehensive justification of the safe LTO has to be provided in the formal License Renewal Applications unit by unit. This work has been completed by the end of 2011, and the application has been submitted for approval for the Unit 1. The authority review and the approval of the License Renewal Application for Unit 1 should be finished before the expiration of the original design lifetime in 2012. In line with the regulations and supporting the License Renewal Application, a large number of engineering tasks have been performed. In this paper the entire project will be reported. The issues will be discussed, which have been arisen during the development of the application. The difficulties caused by the Hungarian technical and regulatory peculiarities will be presented. (author)

  1. Libraries and licensing

    Directory of Open Access Journals (Sweden)

    Maja Žumer

    2001-01-01

    Full Text Available In the mid 90s, the abundance of various electronic publications exposed libraries to the problems of licensing electronic content. Various licensing principles have been prepared recently to help libraries in the process; it can be said that in general, the knowledge of licensing issues has improved in libraries of all types. Libraries form consortia in order to gain stronger negotiating positions and obtain better conditions.In the article, new licensing principles are presented in more detail, as well as some domestic and foreign experiences with consortia forming.

  2. Safety evaluation report related to the renewal of the operating license for the research reactor at North Carolina State University

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-04-01

    This safety evaluation report (SER) summarizes the findings of a safety review conducted by the staff of the U.S. Nuclear Regulatory Commission (NRC), Office of Nuclear Reactor Regulation (NRR). The staff conducted this review in response to a timely application filed by North Carolina State University (the licensee or NCSU) for a 20-year renewal of Facility Operating License R-120 to continue to operate the NCSU PULSTAR research reactor. The facility is located in the Burlington Engineering Laboratory complex on the NCSU campus in Raleigh, North Carolina. In its safety review, the staff considered information submitted by the licensee (including past operating history recorded in the licensee`s annual reports to the NRC), as well as inspection reports prepared by NRC Region H personnel and first-hand observations. On the basis of this review, the staff concludes that NCSU can continue to operate the PULSTAR research reactor, in accordance with its application, without endangering the health and safety of the public. 16 refs., 31 figs., 7 tabs.

  3. Safety evaluation report related to the renewal of the operating license for the research reactor at North Carolina State University

    International Nuclear Information System (INIS)

    1997-04-01

    This safety evaluation report (SER) summarizes the findings of a safety review conducted by the staff of the U.S. Nuclear Regulatory Commission (NRC), Office of Nuclear Reactor Regulation (NRR). The staff conducted this review in response to a timely application filed by North Carolina State University (the licensee or NCSU) for a 20-year renewal of Facility Operating License R-120 to continue to operate the NCSU PULSTAR research reactor. The facility is located in the Burlington Engineering Laboratory complex on the NCSU campus in Raleigh, North Carolina. In its safety review, the staff considered information submitted by the licensee (including past operating history recorded in the licensee's annual reports to the NRC), as well as inspection reports prepared by NRC Region H personnel and first-hand observations. On the basis of this review, the staff concludes that NCSU can continue to operate the PULSTAR research reactor, in accordance with its application, without endangering the health and safety of the public. 16 refs., 31 figs., 7 tabs

  4. ONR Licensing and Regulation of a Geological Disposal Facility in the UK

    International Nuclear Information System (INIS)

    Boydon, Frans; Glazbrook, David

    2014-01-01

    Document available in abstract form only. Full text follows: The UK has substantial quantities of waste which has arisen from operation and decommissioning of legacy nuclear plant. While a disposal route for Low Level Waste (LLW) has been in operation in the UK for many years, there is as yet no such route for Higher Activity Waste. The government invited local communities to express an interest in hosting a Geological Disposal Facility (GDF). However, the Scottish government is opposed to deep disposal and proposes long-term interim storage in Scotland. This paper describes the work underway and current progress in developing a GDF for the UK. In particular it describes the current legal system in the UK that enables nuclear facilities to be licensed and the background underpinning licensing of existing disposal facilities. It identifies changes which will be necessary to legislation to enable a GDF to be licensed and work which it is performing in close co-operation with the Environment Agency which operate a permitting regime for environmental aspects. The Office of Nuclear Regulation (ONR) regulates safety, security and transport associated with nuclear sites. This paper focuses on the regulation of safety and radioactive waste. The UK licensing regime is non-prescriptive and proportionate, allowing for a flexible approach to licensing. The licence is not time-limited but is designed to be used from construction, through commissioning for the lifetime of the facility. Under the Nuclear Installations Act 1965 (as amended) ONR may attach licence conditions: - In the interests of safety; or - with respect to the handling, treatment and disposal of nuclear matter. ONR has developed a suite of 36 Licence conditions, which typically require the operator to made 'adequate arrangements' to ensure safety. These arrangements would involve the use of 'hold points' beyond which the operator must not proceed without ONR's agreement. In determining

  5. 78 FR 18592 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2013-03-27

    ...), Veronica Alcestte, Manager, Application Type: New NVO & OFF License Worldcraft Logistics LLC (NVO & OFF.... Salvat, Vice President, Application Type: Add NVO Service Bayshore Logistics & Services, LLC (NVO & OFF), 909 Westfield Avenue, Elizabeth, NJ 07208, Officers: Raquel Velez, Operating Manager (QI), Jose Moreno...

  6. SAFSTOR and License Renewal: Making Them Coexist

    International Nuclear Information System (INIS)

    Henries, William PE

    2008-01-01

    proximity of Unit 1 to the operating units and the fact that a number of Unit 1 systems are shared with Unit 2. Over the past few decades, additional Unit 1 space (primarily within the turbine building) has been cleaned out and is being used to support the operating Units. The original plan to maintain Unit 1 in a SAFSTOR condition until it could be safely dismantled along with Unit 2 at the end of the Unit 2 operating license in 2012, requires some level of re-thinking now that Units 2 and 3 are applying for renewal of their licenses with the desire to continue operation until the 2033 time frame. The remainder of this paper summarizes the inspections and assessments undertaken by Entergy to investigate and document the condition of Indian Point Unit 1 and the resulting steps taken to assure that it would not pose a threat to the license extension efforts being under taken by Units 2 and 3. In conclusion: the Entergy Indian Point management team has systematically undertaken an effort to ensure the Unit 1 SAFSTOR condition and has implemented programs and procedural controls which will assure that it will continue to be safely maintained and will not impact the continued safe operation of Units 2 and 3 during their license renewal period

  7. Safety Evaluation Report related to the renewal of the operating license for the TRIGA training and research reactor at the University of Utah (Docket No. 50-407)

    International Nuclear Information System (INIS)

    1985-03-01

    This Safety Evaluation Report for the application filed by the University of Utah (UU) for a renewal of operating license R-126 to continue to operate a training and research reactor facility has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is owned and operated by the University of Utah and is located on its campus in Salt Lake City, Salt Lake County, Utah. The staff concludes that this training reactor facility can continue to be operated by UU without endangering the health and safety of the public

  8. Fort Calhoun Station, Unit 2. License application, PSAR, general information

    International Nuclear Information System (INIS)

    1975-09-01

    Application for construction and operating licenses for Calhoun-2 Reactor is presented. Financial data concerning the Omaha Public Power District and the Nebraska Public Power District are included. (DCC)

  9. 78 FR 15747 - Charlissa C. Smith (Denial of Senior Reactor Operator License)

    Science.gov (United States)

    2013-03-12

    ... NUCLEAR REGULATORY COMMISSION [Docket No. 55-23694-SP; ASLBP No. 13-925-01-SP-BD01] Charlissa C... Reconstitution Pursuant to 10 CFR 2.313(c) and 2.321(b), the Atomic Safety and Licensing Board (Board) in the above-captioned Charlissa C. Smith case is hereby reconstituted because Administrative Judge Alan S...

  10. Conformation of an evaluation process for a license renovation solicitude of a nuclear power plant in Mexico

    International Nuclear Information System (INIS)

    Serrano R, M. L.

    2012-10-01

    So that the construction stages, of operation, closing, dismantlement and the radioactive waste disposal of a nuclear power plant (NPP) are carried out in Mexico, is necessary that the operator has a license, permission or authorization for each stage. In Mexico, these licenses, permissions or authorizations are granted by the Energy Secretariat with base in the verdict of the Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS). The operation licenses ar the moment effective for the reactors of the Nuclear Power Plant of Laguna Verde (NPP-L V) they will expire respectively in the year 2020 and 2025 for the Unit 1 and Unit 2, for what the CNSNS has begun its preparation before a potential solicitude of the licensee to continue the operation of the NPP-L V. Defining the process to continue and to generate the documents that would help in this phase as normalization, guides, procedures, regulations, controls, etc., is the task that intends to be carried out the regulator body so that the evaluation process is effective and efficient, so much for the same regulator body as for the licensee. This work exposes the advance that the CNSNS has in this aspect and is centered specifically in the conformation of an evaluation process of license renovation solicitude, taking as base what the regulator body of the United States of North America (US NRC) established and following to the IAEA. Also, this work includes statistical of electric power production in Mexico, licensing antecedents for the NPP-L V, a world perspective of the license renovations and the regulation of the US NRC related to the license renovation of a NPP. (Author)

  11. 76 FR 13972 - United States Warehouse Act; Export Food Aid Commodities Licensing Agreement

    Science.gov (United States)

    2011-03-15

    ..., nuts, cottonseed, and dry beans. Warehouse operators that apply voluntarily agree to be licensed... program for port and transload facility operators storing EFAC. This proposal is in response to the...

  12. Demarcation of the licensing and supervisory procedures for nuclear engineering installations

    International Nuclear Information System (INIS)

    Schattke, H.

    1986-01-01

    The remarks can be summed up under 12 points: 1) The protective purpose outlined in Paragraph 1 No. 2 of the Atomic Energy Law is the top priority for both licensing and regulatory authorities. 2) Both authorities must aim at the best possible prevention of hazards and precautions against risks. 3) The licensing procedures cover applications for licenses, the regulatory procedures check and supervise actual activities. 4) The licensing procedures take precedence in chronology and in substance over the regulatory procedure. 5) The licensing procedure is a preliminary check on the intention to carry out nuclear activities before the event; whereas the regulatory procedure controls the licensee after the event to ensure that the latter's activities really do conform to the framework laid down in the license. 6) The licensing procedure must be verified by state supervision with regard to its prognostic activity. 7) The examination criteria are largely identical for both the authorites. 8) The examination tools for the licensing and regulatory authorities also coincide to a large extent. Legal differences in the possible means of enforcement have no effect in practice. 9) Decisions made by either authority can be either in the licensee's favour or to its disadvantage. Nevertheless, the contents of decisions differ widely between the two authorities. 10) The regulatory authorities execute and prepare the decisions of the licensing authorites. 11) Licensing decisions can be designated static/prognostic, whereas regulatory measures accompany the actual performance of the plant and the operating personnel in a dynamic/controlling manner. 12) Regulatory instructions are usually of a temporary nature, whereas licensing actions are permanent as a rule. (orig.) [de

  13. 47 CFR 80.13 - Station license required.

    Science.gov (United States)

    2010-10-01

    ... signals using a marine radio operating in the 156-162 MHz band, any type of AIS, any type of EPIRB, and any type of radar installation. All other transmissions must be authorized under a ship station... paragraph (c) of this section, stations in the maritime service must be licensed by the FCC either...

  14. The regulatory review of construction license application and the supporting safety case

    International Nuclear Information System (INIS)

    Heinonen, Jussi

    2014-01-01

    Finland is one of the foremost countries in the world in developing the disposal of spent fuel. The construction license application for the Olkiluoto spent fuel disposal facility was submitted to the authorities at the end of 2012 and the facility is expected to start operation around 2020. This has been a long-term project with over 30 years of parallel development of the repository project and the regulatory approach to spent fuel management. In 1983 the government made a strategic decision on the objectives and target time schedule for the research, development and technical planning of nuclear waste management. While an export and international disposal solution was still the preferred option, this decision required the licensees without this possibility to prepare for disposal in Finland and it also gave the time line for the milestones on the way to an operating disposal facility by 2020. The licensing procedure for a disposal facility has several steps that are similar to all nuclear facilities in Finland and are defined in Nuclear Energy Act and Decree (1987, 1988). These licensing steps are: - Decision-in-principle is required for a nuclear facility having considerable general significance. This is essentially a political decision: the government decides if the construction project is in line with the overall good of society. The decision can be applied for one or more sites, the host municipality has a veto right and the parliament has the choice of ratifying or not ratifying the decision. - Construction license is granted by the government and authorises the construction of the disposal facility. The actual construction is regulated by STUK and includes several review and approval steps, hold points and viewpoints. - Operational license is granted by the government and authorises the operation of the facility for a certain period. The operational license is needed before nuclear waste can be disposed. The first step in the licensing process was reached

  15. Guidelines for preparing and reviewing applications for the licensing of non-power reactors: Standard review plan and acceptance criteria. NUREG - 1537, Part 2

    International Nuclear Information System (INIS)

    1996-02-01

    NUREG - 1537, Part 2 gives guidance on the conduct of licensing action reviews to NRC staff who review non-power reactor licensing applications. These licensing actions include construction permits and initial operating licenses, license renewals, amendments, conversions from highly enriched uranium to low-enriched uranium, decommissioning, and license termination

  16. Guidelines for preparing and reviewing applications for the licensing of non-power reactors: Standard review plan and acceptance criteria. NUREG - 1537, Part 2

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-02-01

    NUREG - 1537, Part 2 gives guidance on the conduct of licensing action reviews to NRC staff who review non-power reactor licensing applications. These licensing actions include construction permits and initial operating licenses, license renewals, amendments, conversions from highly enriched uranium to low-enriched uranium, decommissioning, and license termination.

  17. Assuring the Quality of Licensing and Certification Programs.

    Science.gov (United States)

    Shimberg, Benjamin

    When one considers the importance and social significance of licensing and certification examinations, it is amazing that the enterprise operates with virtually no societal oversight. The "Standards for Educational and Psychological Testing" and the "Code of Fair Testing Practices in Education" of the American Psychological…

  18. Socio-economic impacts of nuclear generating stations: summary report on the NRC post-licensing studies

    International Nuclear Information System (INIS)

    Chalmers, J.; Pijawka, D.; Branch, K.; Bergmann, P.; Flynn, J.; Flynn, C.

    1982-07-01

    Information is presented concerning the conceptual framework for the assessment of socioeconomic impacts; methodology for the post-licensing case studies; socioeconomic changes due to the construction and operation of nuclear generating stations; public response to the construction and operation of nuclear generating stations; socioeconomic consequences of the accident at Three Mile Island; the significance of socioeconomic change due to the construction and operation of nuclear generating stations; findings of the post-licensing studies relative to the nuclear station impact literature; and implications of the findings for projective assessments and planning studies

  19. The Brazilian Audit Tribunal's role in improving the federal environmental licensing process

    International Nuclear Information System (INIS)

    Lima, Luiz Henrique; Magrini, Alessandra

    2010-01-01

    This article describes the role played by the Brazilian Audit Tribunal (Tribunal de Contas da Uniao - TCU) in the external auditing of environmental management in Brazil, highlighting the findings of an operational audit conducted in 2007 of the federal environmental licensing process. Initially, it records the constitutional and legal framework of Brazilian environmental licensing, describing the powers and duties granted to federal, state and municipal institutions. In addition, it presents the responsibilities of the TCU in the environmental area, comparing these with those of other Supreme Audit Institutions (SAI) that are members of the International Organization of Supreme Audit Institutions (INTOSAI). It also describes the work carried out in the operational audit of the Brazilian environmental licensing process and its main conclusions and recommendations. Finally, it draws a parallel between the findings and recommendations made in Brazil with those of academic studies and audits conducted in other countries.

  20. Reactor licensing

    International Nuclear Information System (INIS)

    Harvie, J.D.

    2002-01-01

    This presentation discusses reactor licensing and includes the legislative basis for licensing, other relevant legislation , the purpose of the Nuclear Safety and Control Act, important regulations, regulatory document, policies, and standards. It also discusses the role of the CNSC, its mandate and safety philosophy

  1. Licensing Process for Nuclear Power Plants in Pakistan and its comparison with other Countries

    International Nuclear Information System (INIS)

    Iqbal, Javed; Choi, Kwang Sik

    2012-01-01

    Pakistan Nuclear Regulatory Authority (PNRA) was established in January 2001 with the promulgation of the Ordinance, No-III of 2001. Pakistan is one of the countries in the world who intend to expand its nuclear power program for energy generation upto 8800 MWe by 2030. Presently, there are two research reactors and three nuclear power plants in operation and two power plants are under various stages of construction which are expected to be in commercial operation in 2016. It is obvious that the primary responsibility of ensuring safety of nuclear power plants (NPPs) operation rests with the Pakistan Atomic Energy Commission (PAEC). However, PNRA's prime mission is to ensure the safe operation of nuclear and radiation facilities, safe use of radioactive sources and protection of the radiation workers, general public and the environment from the harmful hazards of radiation by formulating and implementing effective regulations. Pakistan Nuclear Regulatory Authority issues authorizations for nuclear power plants in three stages i.e. site permit, construction license and operation license after detailed safety review. This paper presents the licensing process for NPPs in Pakistan and its comparison with SSG-12, USA and Finland

  2. License renewal demonstration program: NRC observations and lessons learned

    International Nuclear Information System (INIS)

    Prato, R.J.; Kuo, P.T.; Newberry, S.F.

    1996-12-01

    This report summarizes the Nuclear Regulatory Commission staff's observations and lessons learned from the five License Renewal Demonstration Program (LRDP) site visits performed by the staff from March 25, 1996, through August 16, 1996. The LRDP was a Nuclear Energy Institute (NEI) program intended to assess the effectiveness of the guidance provided by NEI 95-10, Revision 0, open-quotes Industry Guideline for Implementing the Requirements of 10 CFR Part 54 - The License Renewal Rule,close quotes to implement the requirements of Title 10 of the Code of Federal Regulations, Part 54 (10 CFR Part 54), open-quotes Requirements for Renewal of Operating Licenses for Nuclear Power Plants.close quotes In general, NEI 95-10 appeared to contain the basic guidance needed for scoping, screening, identifying aging effects, developing aging management programs, and performing time-limited aging analyses. However, inconsistent implementation of this guidance in some areas was an indication that clarification of existing guidance and/or the inclusion-of some new guidance may be needed for applicants to develop a license renewal program that is consistent with the intent of the rule

  3. 76 FR 45695 - Notice and Recordkeeping for Use of Sound Recordings Under Statutory License

    Science.gov (United States)

    2011-08-01

    ... operating under these licenses are required to, among other things, pay royalty fees and report to copyright... LIBRARY OF CONGRESS Copyright Royalty Board 37 CFR Parts 370 and 382 [Docket No. RM 2011-5] Notice and Recordkeeping for Use of Sound Recordings Under Statutory License AGENCY: Copyright Royalty Board...

  4. 47 CFR 24.709 - Eligibility for licenses for frequency Blocks C or F.

    Science.gov (United States)

    2010-10-01

    ..., revenue from operations or other investments, business development, or expanded service shall not be... block licenses (1895-1900 MHz paired with 1975-1980 MHz); (B) For Tier 2 BTAs, two of the 10 MHz C block licenses (1895-1900 MHz paired with 1975-1980 MHz; 1900-1905 MHz paired with 1980-1985 MHz) and all 15 MHz...

  5. Safety philosophy and licensing practice in different member states of IAEA: Spain

    International Nuclear Information System (INIS)

    Alonso, A.

    1981-01-01

    With the aim of presenting the licensing experience in Spain, the countries with nuclear activities are divided into three main groups: exporters, qualified importers and importers, being Spain in the second group. The licensing problems, and therefore the licensing experience, are different in the different groups of countries. Moreover, the experience in Spain is enriched by the following facts: an early start, a substantial program and a diversity of types, pressurized and boiling water reactors, and suppliers, American and German plants. Reference is made to the basic legal documents governing licensing in Spain, together with the difficulties in adopting and applying detailed regulations. Within this framework, the licensing experience in Spain is described with reference to the reference plant concept, later enlarged to include the reference-site reference plant concept, ending in the most practical approach of the reference problem concept. Finally specific licensing problems are introduced with reference to the Spanish operating nuclear power plants, the ones under commissioning and in an advanced state of construction and the ones just staring construction. (orig./RW)

  6. Licensing in an international triopoly

    Science.gov (United States)

    Ferreira, Fernanda A.; Ferreira, Flávio

    2011-12-01

    We study the effects of entry of two foreign firms on domestic welfare in the presence of licensing, when the incumbent is technologically superior to the entrants. We consider two different situations: (i) the cost-reducing innovation is licensed to both entrants; (ii) the cost-reducing innovation is licensed to just one of the entrants. We analyse three kind of license: (lump-sum) fixed-fee; (per-unit) royalty; and two-part tariff, that is a combination of a fixed-fee and a royalty. We prove that a two part tariff is never an optimal licensing scheme for the incumbent. Moreover, (i) when the technology is licensed to the two entrants, the optimal contract consists of a licensing with only output royalty; and (ii) when the technology is licensed to just one of the entrants, the optimal contract consists of a licensing with only a fixed-fee.

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

    International Nuclear Information System (INIS)

    1985-10-01

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

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

    International Nuclear Information System (INIS)

    1986-08-01

    This report, prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission, supplements the Safety Evaluation Report (NUREG-1143, October 1985). It fulfills a commitment to provide the Advisory Committee on Reactor Safeguards report, identifies the changes that have occurred since the Safety Evaluation Report was issued, and specifies the effective lifetime for the Full-Term Operating License

  9. Licensed operating reactors. Status summary report data as of March 31, 1986. Volume 10, No. 4

    International Nuclear Information System (INIS)

    1986-05-01

    The US Nuclear Regulatory Commission's monthly LICENSED OPERATING REACTORS Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Resource Management, from the Headquarters Staff of NRC's Office of Inspection and Enforcement, from NRC's Regional Offices, and from utilities. Since all of the data concerning operation of the units is provided by the utility operators less than two weeks after the end of the month, necessary corrections to published information are shown on the ERRATA page. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States. The percentage computations, Items 20 through 24 in Section 2, the vendor capacity factors on page 1-7, and actual vs potential energy production on page 1-2 are computed using actual data for the period of consideration. The percentages listed in power generation on page 1-2 are computed as a arithmetic average. The factors for the life-span of each unit (the ''Cumulative'' column) are reported by the utility and are not entirely recomputed by NRC. Utility power production data is checked for consistency with previously submitted statistics. It is hoped this status report proves informative and helpful to all agencies and individuals interested in analyzing trends in the nuclear industry which might have safety implications, or in maintaining an awareness of the US energy situation as a whole

  10. Licensing and supervision of nuclear facilities in Finland; Genehmigung und Aufsicht von nuklearen Anlagen in Finnland

    Energy Technology Data Exchange (ETDEWEB)

    Laaksonen, J. [STUK - Radiation and Nuclear Safety Authority, Helsinki (Finland)

    2006-01-01

    In Finland, the licensing process of all nuclear facilities is specified in the Nuclear Energy Act. The licensing procedure comprises three steps, each of which requires a decision by the government: basic decision, construction permit, and operating license. All licensing decisions are taken upon application to the Ministry of Trade and Industry. The Ministry invites comments and opinions on a broad basis and drafts a statement for the government. The basic decision by the government is political, pre-supposing a positive statement by the Central Office for Nuclear Safety (STUK) and a positive decision by the local government of the planned plant location. The construction permit and the operating license are mainly based on points of nuclear safety. STUK is the independent nuclear supervisory agency with administrative powers; its staff has the technical and scientific competence required for safety assessments and for supervision. STUK operates under the supervision of the Ministry for Social Affairs and Health which, to demonstrate its independence, has no duties in the energy sector and, in addition, supervises STUK in administrative matters, not in scientific and technical decisions. Internal rules of STUK ensure neutrality also of its staff in matters of energy policy. The activities of STUK as a supervisory and licensing authority in Finland are described in detail for the management of spent nuclear fuel and the new Olkiluoto 3 nuclear power plant currently under construction. (orig.)

  11. 14 CFR 431.73 - Continuing accuracy of license application; application for modification of license.

    Science.gov (United States)

    2010-01-01

    ... 14 Aeronautics and Space 4 2010-01-01 2010-01-01 false Continuing accuracy of license application; application for modification of license. 431.73 Section 431.73 Aeronautics and Space COMMERCIAL SPACE... Conditions § 431.73 Continuing accuracy of license application; application for modification of license. (a...

  12. Fuel Receiving and Storage Station. License application, amendment 7

    International Nuclear Information System (INIS)

    1976-02-01

    Amendment No. 7 to Allied-General Nuclear Services application for licensing of the Fuel Receiving and Storage Station consists of revised pages for: Amendment No. 7 to AG-L 105, ''Technical Description in Support of Application for FRSS Operation''; Amendment No. 1 to AG-L 105A, ''Early Operation of the Service Concentrator''; and Amendment No. 2 to AG-L 110, ''FRSS Summary Preoperational Report.''

  13. 76 FR 38651 - Ocean Transportation Intermediary License; Applicants

    Science.gov (United States)

    2011-07-01

    ... Shipping (NVO), 1861 Western Way, Torrance, CA 90501. Officers: Hseanrus (Stephen) H. Lin, President/Vice..., President, Application Type: New NVO & OFF License. F.H.L. Logistics, Inc. (NVO & OFF), 1354 NW 78th Avenue..., Gardena, CA 90248. Officers: Anna W. Liu, Vice President (Operations), (Qualifying Individual), Quincy H...

  14. Fire safety regulations and licensing

    International Nuclear Information System (INIS)

    Berg, H.P.

    1998-01-01

    Experience of the past tow decades of nuclear power plant operation and results obtained from modern analytical techniques confirm that fires may be a real threat to nuclear safety and should receive adequate attention from the design phase throughout the life of the plant. Fire events, in particular influence significantly plant safety due to the fact that fires have the potential to simultaneously damage components of redundant safety-related equipment. Hence, the importance of fire protection for the overall safety of a nuclear power plant has to be reflected by the fire safety regulations and to be checked during the licensing process of a plant as well as during the continuous supervision of the operating plant

  15. Licensed Healthcare Facilities

    Data.gov (United States)

    California Natural Resource Agency — The Licensed Healthcare Facilities point layer represents the locations of all healthcare facilities licensed by the State of California, Department of Health...

  16. 75 FR 23808 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No...

    Science.gov (United States)

    2010-05-04

    ... most adverse moderation conditions feasible by unborated water. By meeting this criteria, the removal... Risk Assessment in Risk-Informed Decisions On Plant-Specific Changes to the Licensing Basis,'' and RG 1...

  17. Fuel licensing process for an industrial use. ATF licensing process for an industrial use - Utility's perspective

    International Nuclear Information System (INIS)

    Waeckel, Nicolas

    2013-01-01

    To develop and license a breakthrough nuclear fuel technology for commercial use is becoming challenging. All the former safety analysis design limits (SAFDLs) defined in the 1970's for the standard UO 2 -Zr fuels, might no longer be applicable. Identification of the appropriate safety analysis design limits For each type of innovative fuel, the developers will have to identify and investigate all the possible failure/ruins scenarios (not only those related to severe accidents but also those related to normal operation). In order to save time and to focus on the best options, those failure scenarios (which could be 'killers' for the ATF concept) have to be determined early enough in the development process. Based on the above failure scenarios, the developers will have to propose the licensing limits (and the experimental protocol to determine and to justify them). As mentioned earlier, the licensing limits should not be defined against the accidental conditions only. For the operators, the (good) in-reactor fuel behaviour is crucial. As an example, in the case of the new fuel concepts coming with an outer coating, it is important to include the analysis of the consequences of the loss of this protective outer layer in the licensing process due to a manufacturing defect or an inevitable in-reactor fretting wear. Obviously, the new/specific SAFDLs will have to be endorsed by the regulators (which could be a long process by itself). Identification of a commercial reactor to irradiate the first ATF A commercial NPP is not a material test reactor (MTR); irradiating lead test fuel rods (LTFRs) or lead test assemblies (LTAs) implies strict requirements regarding the manufacturing processes [which should not include chemicals (additives or solvents) potentially incompatible with the nuclear technical specifications], the compatibility with the hosting fuel core (in terms of geometry, enrichment, thermal hydraulic performances, etc.) and the robustness and

  18. 2015 Business Licenses

    Data.gov (United States)

    City of Jackson, Mississippi — This data displays all business license information for the year of 2015. This information details license classifications and status. This information will updated...

  19. Status of long term operation of nuclear power plants in the US

    Energy Technology Data Exchange (ETDEWEB)

    Young, G., E-mail: gyoung4@entergy.com [Entergy Nuclear, License Renewal, New Orleans, LA (United States)

    2014-07-01

    As of early-2014, the U.S. Nuclear Regulatory Commission (NRC) has renewed the operating licenses for 73 of the 100 U.S. operating nuclear units, allowing for up to 60 years of safe operation. In addition, the NRC has license renewal applications under review for 18 more units and up to 8 additional units have announced plans to submit applications by 2018. This brings the total of renewed licenses and announced plans for renewal to 99% of the operating nuclear units in the U.S. In addition, by the end of 2014, there will be 38 nuclear plants that will have operated for more than 40 years and will be eligible to seek a subsequent license renewal to allow operation up to 80 years. Although some of the operating nuclear units are expected to shutdown due to economic issues, most of the remaining operating plant owners are keeping the option open for long term operation beyond 60 years. NRC and the U.S. nuclear industry have made significant progress in preparing the way for subsequent license renewal applications. This presentation covers the status of the U.S. license renewal process and issues being addressed for possible applications for subsequent renewals for up to 80 years of operation. (author)

  20. Teenagers' licensing decisions and their views of licensing policies: a national survey.

    Science.gov (United States)

    Williams, Allan F

    2011-08-01

    One objective was to determine teenage licensing rates on a national basis, interest in early licensure, and reasons for delay. A second objective was to learn teenagers' opinions about licensing policies, important in states considering ways to upgrade their current licensing systems. One thousand three hundred eighty-three 15- to 18-year-olds completed an online survey in November 2010. They were drawn from a nationally representative panel of US households recruited using probability-based sampling. The panel included cell phone-only households, and Internet access was provided to those without it. Weighting procedures were applied so that the study population represented the national US population of 15- to 18-year-olds. Most teens said that they were interested in getting a license as soon as legally possible, but many had not started the process. At 16, teens were about equally divided among those who had not started, those in the learner stage, and those with a restricted or full license. At 18, 62 percent had full licenses; 22 percent had not started. For those old enough to start, lack of a car, costs, parent availability, ability to get around without a car, and being busy with other activities were leading reasons for delay. The majority of teens were not in favor of higher licensing ages. Forty-six percent thought the minimum learner age should be 16; 30 percent thought the full license age should be 18 or older. The majority approved of night (78%) and passenger (57%) restrictions, and 85 and 93 percent endorsed cell phone and texting bans, respectively. When these policies were packaged together in a single law that included an age 16 start, night, passenger, cell phone and texting bans, and a full license at age 18, 74 percent of teens were in favor. Teenagers are not as supportive of strong licensing policies as parents of teens, but there is evidence that they will support comprehensive policies likely to lead to further reductions in teen crash

  1. Coopetitive Business Models in Future Mobile Broadband with Licensed Shared Access (LSA)

    OpenAIRE

    P. Ahokangas; M. Matinmikko; I. Atkova; L.F. Minervini; S. Yrjölä; M. Mustonen

    2016-01-01

    Spectrum scarcity forces mobile network operators (MNOs) providing mobile broadband services to develop new business models that address spectrum sharing. It engages MNOs into coopetitive relationship with incumbents. Licensed Shared Access (LSA) concept complements traditional licensing and helps MNOs to access new spectrum bands on a shared basis. This paper discusses spectrum sharing with LSA from business perspective. It describes how coopetition and business model are linked conceptually...

  2. Interim licensing criteria for physical protection of certain storage of spent fuel

    International Nuclear Information System (INIS)

    Dwyer, P.A.

    1994-11-01

    This document presents interim criteria to be used in the physical protection licensing of certain spent fuel storage installations. Installations that will be reviewed under this criteria are those that store power reactor spent fuel at decommissioned power reactor sites; independent spent fuel storage installations located outside of the owner controlled area of operating nuclear power reactors; monitored retrievable storage installations owned by the Department of Energy, designed and constructed specifically for the storage, of spent fuel; the proposed geologic repository operations area; or permanently shutdown power reactors still holding a Part 50 license. This criteria applies to both dry cask and pool storage. However, the criteria in this document does not apply to the storage of spent fuel within the owner-controlled area of operating nuclear power reactors

  3. Radiopharmaceutical licensing

    International Nuclear Information System (INIS)

    Mather, S.J.

    1992-01-01

    Recent health service legislation, and especially the loss of crown immunity has once again focussed attention on the arrangements for licensing of radiopharmaceuticals. The aim of the article is to describe in general terms the UK licensing system and in particular to provide guidance to those responsible for the supply of radiopharmaceuticals in hospitals. (author)

  4. License to build

    International Nuclear Information System (INIS)

    Huntelaar, Mark; Vos, Renate de; Roobol, Lars

    2007-01-01

    Full text: A new license under the nuclear power act is applied for at the Dutch Government for the building of a High Active Repackaging Unit (HAVA-VU in Dutch) at NRG in Petten, The Netherlands. This new building is necessary to comply with our nuclear license to dispose of high active nuclear waste at Petten to the intermediate storage facility (COVRA). In the first part of this paper attention is given to the formal procedure followed by the Government, what type of documents are to be submitted, what time frames are followed, how citizen participation is organized, and as final result a new license. In the second part more detailed information is given about the present license renewal needed for the High Active Repackaging Unit

  5. Atomic Safety and Licensing Board Panel Biennial Report, Fiscal Years 1993--1994. Volume 6

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-08-01

    In Fiscal Year 1993, the Atomic Safety and Licensing Board Panel (``the Panel``) handled 30 proceedings. In Fiscal Year 1994, the Panel handled 36 proceedings. The cases addressed issues in the construction, operation, and maintenance of commercial nuclear power reactors and other activities requiring a license form the Nuclear Regulatory Commission. This report sets out the Panel`s caseload during the year and summarizes, highlight, and analyzes how the wide- ranging issues raised in those proceedings were addressed by the Panel`s judges and licensing boards.

  6. Atomic Safety and Licensing Board Panel Biennial Report, Fiscal Years 1993--1994. Volume 6

    International Nuclear Information System (INIS)

    1995-08-01

    In Fiscal Year 1993, the Atomic Safety and Licensing Board Panel (''the Panel'') handled 30 proceedings. In Fiscal Year 1994, the Panel handled 36 proceedings. The cases addressed issues in the construction, operation, and maintenance of commercial nuclear power reactors and other activities requiring a license form the Nuclear Regulatory Commission. This report sets out the Panel's caseload during the year and summarizes, highlight, and analyzes how the wide- ranging issues raised in those proceedings were addressed by the Panel's judges and licensing boards

  7. The U.S. Nuclear Regulatory Commission's antitrust review of nuclear power plants: the conditioning of licenses

    International Nuclear Information System (INIS)

    Penn, D.W.; Delaney, J.B.; Honeycutt, T.C.

    1976-04-01

    The 1970 amendments to Section 105 of the Atomic Energy Act require the Nuclear Regulatory Commission to conduct a prelicensing antitrust review of applications for licenses to construct and operate nuclear power plants. The Commission must make a finding as to whether the granting of a license 'would create or maintain a situation inconsistent with the antitrust laws,' and it has the authority to issue or continue a license, to refuse to issue a license, to rescind or amend a license, and to issue a license with conditions that it deems appropriate. This report provides information about the antitrust license conditions that have resulted from the NRC's antitrust review process. The process itself is described and a catalog of the applications requiring antitrust license conditions is presented. For each application, the license conditions are put into the general categories of unit access, transmission services, coordination, and contractual provisions. For completeness, the report also catalogs applications requiring no antitrust license conditions, and lists applications that were exempted from the 1970 amendments, are the subject of litigation, or have been withdrawn

  8. THTR steam generator licensing experience as seen by the manufacturer

    International Nuclear Information System (INIS)

    Fricker, H.W.

    1981-01-01

    This paper describes the licensing procedures of the manufacture of the 300 MWe THTR steam generator. The following problems are discussed: operating data, design, materials used, manufacture and installation of the generator, and also quality control

  9. Cyclotron facilities in Brazil: Current status and licensing aspects

    International Nuclear Information System (INIS)

    Facure, A.; Carvalho, S.M.; Di Prinzio, R.; Silveira, C.S.; Gasparian, P.B.R.; Franca, W.F.

    2017-01-01

    Positron Emission Tomography (PET) is a highly sensitive and accurate nuclear medicine imaging technology but the major problem of this technique is the use of radioisotopes with short half-life, less than two hours. The production and selling of short half-life radioisotopes used to be monopoly of the Brazilian Government. In 2006, a Constitutional Amendment revoked the state monopoly due to the need for the use of short half-life radioisotopes in nuclear medicine centers very far from the government production facilities. The aim of this study is to describe the current status of short half-life radioisotopes production in Brazil and discuss some licensing process. In Brazil, as has been occurring worldwide, the number of nuclear medicine centers is increasing. Currently there are 123 services performing PET scans in Brazil. There are 14 cyclotrons operating in Brazil. The type of licensing process conducted in Brazil does not take into account the population density of each state, with a free competition model being adopted. Because of this there is a lot of equipment concentrated in the Southeast and no cyclotrons operating in the Northern part of the country. One of the biggest obstacles during the licensing process is the designation of qualified personnel as operation workers and radiation safety officers. The number of cyclotron accelerators and PET/CT equipment increased in recent years. However, a number of external factors such as the distance from the nuclear medicine centers, and qualified personnel have proved crucial for the economic viability of this type of facility. (author)

  10. Cyclotron facilities in Brazil: Current status and licensing aspects

    Energy Technology Data Exchange (ETDEWEB)

    Facure, A.; Carvalho, S.M.; Di Prinzio, R.; Silveira, C.S.; Gasparian, P.B.R.; Franca, W.F., E-mail: facure@cnen.gov.br [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil)

    2017-09-01

    Positron Emission Tomography (PET) is a highly sensitive and accurate nuclear medicine imaging technology but the major problem of this technique is the use of radioisotopes with short half-life, less than two hours. The production and selling of short half-life radioisotopes used to be monopoly of the Brazilian Government. In 2006, a Constitutional Amendment revoked the state monopoly due to the need for the use of short half-life radioisotopes in nuclear medicine centers very far from the government production facilities. The aim of this study is to describe the current status of short half-life radioisotopes production in Brazil and discuss some licensing process. In Brazil, as has been occurring worldwide, the number of nuclear medicine centers is increasing. Currently there are 123 services performing PET scans in Brazil. There are 14 cyclotrons operating in Brazil. The type of licensing process conducted in Brazil does not take into account the population density of each state, with a free competition model being adopted. Because of this there is a lot of equipment concentrated in the Southeast and no cyclotrons operating in the Northern part of the country. One of the biggest obstacles during the licensing process is the designation of qualified personnel as operation workers and radiation safety officers. The number of cyclotron accelerators and PET/CT equipment increased in recent years. However, a number of external factors such as the distance from the nuclear medicine centers, and qualified personnel have proved crucial for the economic viability of this type of facility. (author)

  11. Generic data sources for the update of an environmental report in support of license renewal

    International Nuclear Information System (INIS)

    Mauro, John J.

    1991-01-01

    Over the past 2 years, our organization has been providing assistance to the NUMARC PLEX working group in matters pertaining to the environmental impacts of license renewal. Part of this support was the identification of data sets and publications that may be useful to the NRC in the preparation of their Environment Report Supplements (ERSs). The following presents a strategy for preparing an ERS, along with references and data sets pertinent to each ER topic. Each section of the ERS should present the following information: (1) Updated information on plant design and operating experience, along with projections of the plant impacts through the end of its currently licensed period of operation. These impacts are used as a baseline against which to compare the projected impacts for the period of license renewal. In addition, the baseline impacts may be compared to the impacts projected in the plant's original Environmental Report and Environmental Impact Statement. (2) Projections of how the impacts may change during the period of license renewal. The purpose of this information will be to determine the degree to which the projected impacts differ significantly from the impacts presented in the original ER and those that have actually occurred during the period of plant operation. We believe that the ERS will reveal that (1) the actual impacts that have occurred during the period of plant operation are comparable to, or less than, those predicted in the original ER, (2) many impacts have been decreasing with time, such as routine radioactive emissions, and (3) the impacts predicted for the period of license renewal will be comparable to, or less than, the baseline impacts. (author)

  12. Evaluation of Terminated Nuclear Material Licenses

    International Nuclear Information System (INIS)

    Spencer, K.M.; Zeighami, E.A.

    1999-01-01

    This report presents the results of a six-year project that reviewed material licenses that had been terminated during the period from inception of licensing until approximately late-1994. The material licenses covered in the review project were Part 30, byproduct material licenses; Part 40, source material licenses; and Part 70, special nuclear material licenses. This report describes the methodology developed for the project, summarizes the findings of the license file inventory process, and describes the findings of the reviews or evaluations of the license files. The evaluation identified nuclear material use sites that need review of the licensing material or more direct follow-up of some type. The review process also identified licenses authorized to possess sealed sources for which there was incomplete or missing documentation of the fate of the sources

  13. LTO License Application Project NPP Borssele

    International Nuclear Information System (INIS)

    Jong, A.E. de; Blom, F.J.; Leilich, J.

    2012-01-01

    Borssele NPP plans to extend its operating life with 20 years until 2034. Borssele has started the project LTO 'bewijsvoering' (LTO 'Justification') in order to meet the requirements of the Dutch regulator. The outline of the project is based on IAEA safety guide 57 'Safe Long Term Operation of Nuclear Power Plants'. This paper describes the contents and coherence of the different parts in the project and how these respond to the IAEA guidelines on LTO. The goal of the project LTO 'bewijsvoering' is to ensure that safety and safety relevant systems, structures and components continue to perform their intended functions during long term operation. The outcome of the project LTO 'bewijsvoering' will be used for a license change application and this will be submitted to the Dutch regulator KFD for approval of prolonged operation of Borssele NPP after 2013. (author)

  14. Licensing, supervision, retrofitting

    International Nuclear Information System (INIS)

    Steinkemper, H.

    1991-01-01

    The following proposals for the amendment to the Atomic Energy Act are made: the term of provisions against damage and the content and scope of the principle of commensurability should be defined by law. Their concretization should be left to the level of the statutory instruments and technical codes. In usage the scope of application of the subsequent obligation should be approximated to the category of element relevant to licensing. Lability to indemnification for subsequent obligations should be abolished. The need for a backfitting licence in the case of 'substantial' alterations requires a closer definition. A legal obligation should be placed on operators of nuclear reactors to carry out periodical safety checks. (orig./HSCH) [de

  15. Licensing and decommissioning of nuclear installations in Japan

    International Nuclear Information System (INIS)

    Shimoyama, Shunji.

    1986-01-01

    The present report discusses the current status of Japan's licensing system and legislation concerning reactor decommissioning operations. Besides Japan is working to promote worldwide nuclear safety research. However, developing nuclear safety regulations that are uniformely applicable is a difficult job due to big differences in geographical, political, economical, and technological conditions. (CW) [de

  16. 47 CFR 22.949 - Unserved area licensing process.

    Science.gov (United States)

    2010-10-01

    ..., the licensee in the adjacent market (on the requested channel block) has the right to enter into such... sets forth the process for licensing unserved areas in cellular markets on channel blocks for which the... file competing applications for authority to operate a new cellular system in or to expand an existing...

  17. 7 CFR 4290.390 - Licensing as a RBIC.

    Science.gov (United States)

    2010-01-01

    ... financial information concerning the RBIC in order to qualify for a Leverage commitment; and (4) Enter into... a participant or potential participant in the RBIC program. (d) Effect of a RBIC license. The... following: (1) Approval to operate as a RBIC under the Act; (2) A commitment of Leverage; and (3) An...

  18. The Finnish Experience with the Construction of Onkalo. Licensing of a repository for nuclear waste in Finland

    International Nuclear Information System (INIS)

    Avolahti, Jaana

    2014-01-01

    Pursuant to the Nuclear Energy Act (990/1987), a license holder whose operations result, or have resulted, in the generation of nuclear waste must perform all measures included in the management of nuclear waste and preparation thereof and bear all the costs of nuclear waste management. Under law, spent nuclear fuel is regarded as nuclear waste. According to the amendment made to the Nuclear Energy Act in 1994, nuclear waste generated in Finland must be handled, stored and permanently disposed of in Finland. Nuclear waste generated elsewhere may not be handled, stored and permanently disposed of in Finland. The Finnish nuclear legislation defines spent fuel as nuclear waste and requires that it has to be disposed of in the Finnish bedrock. Over 30 years of systematic R and D has been carried out to develop the repository concept, site selection, technologies, safety assessment and the regulatory approach. Activities are based on the Finnish Government's long term strategies since 1983. The stepwise development and future plans for disposal are presented in Table 1. The licensing procedure for a disposal facility has several steps that are similar to all nuclear facilities in Finland and are defined in Nuclear Energy Act (990/1987) and Decree (161/1988). These licensing steps are: - Decision in Principle (DiP); - Construction License; - Operational License. An Environmental Impact Assessment (EIA) shall be conducted prior to the first authorization step of a major nuclear waste facility. The EIA procedure for the final disposal of spent nuclear fuel from three units of the Olkiluoto nuclear power plant and two units of the Loviisa nuclear power plant was carried out in 1998-1999 and extended to one more unit at Olkiluoto in 2008- 2009. Pursuant to the Nuclear Energy Act, before making the DiP the Government shall ascertain whether the municipality planned as the location of the nuclear facility is in favour of the facility, and ensure that no facts indicating a

  19. 76 FR 13973 - United States Warehouse Act; Processed Agricultural Products Licensing Agreement

    Science.gov (United States)

    2011-03-15

    ... security of goods in the care and custody of the licensee. The personnel conducting the examinations will..., Warehouse Operations Program Manager, FSA, United States Department of Agriculture, Mail Stop 0553, 1400... continuing compliance with the standards of approval and operation. FSA will conduct examinations of licensed...

  20. Safety-evaluation report related to the renewal of the operating license for the research reactor at the Iowa State University (Docket No. 50-116)

    International Nuclear Information System (INIS)

    1983-09-01

    This Safety Evaluation Report for the application filed by the Iowa State University (ISU) for a renewal of the Class 104 Operating License R-59 to continue to operate its Argonaut-type research reactor has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is owned and operated by the Iowa State University, and is located on the ISU campus in Ames, Story County, Iowa. The staff concludes that the reactor facility can continue to be operated by ISU without endangering the health and safety of the public. The principal matters reviewed are: design, testing, and performance of the reactor components and systems; the expected consequences of credible accidents; the licensee's management organization; the method used for the control of radiological effluents; the licensee's technical specifications; financial data and information; the physical protection program; procedures for training reactor operators; and emergency plans. 11 references, 15 figures, 13 tables

  1. Project 2019 of Garona Nuclear power plant. First project to licensing renew more than 40 years in Spain

    International Nuclear Information System (INIS)

    Fernandez, R. A.; Torralbo, J. R.

    2004-01-01

    NUCLENOR has been developing lifetime management and modernisation activities at Santa Maria de Garona NPP since the end of the 80's and the plant is now in optimum technical conditions to continue in operation beyond its original lifetime planned in the design (40 years). In the USA, the country of origin of the project, a good number of power plants with a similar design, age and history to SMG are in the process of obtaining or have already obtained, a licensing extension of up to 60 years from the NRC. In Spain, the activities required for requesting a long-term operating licensing extension include the Ageing Assessment and Management of the plant systems, structures and components, in accordance with the american regulation 10CFR54, a Radiological Impact Study for the new operating period, and an Analysis of New Legislation, not included in the licensing bases and considered to be important to safety by the CSN. With a view to obtaining a renewal of the current operating permit for the period 2009-2019, NUCLENOR has launched the Proyecto 2019, which extends to technical and licensing aspects, as it involves all the company's personnel. (Author)

  2. Nuclear plant license renewal

    International Nuclear Information System (INIS)

    Gazda, P.A.; Bhatt, P.C.

    1991-01-01

    During the next 10 years, nuclear plant license renewal is expected to become a significant issue. Recent Electric Power Research Institute (EPRI) studies have shown license renewal to be technically and economically feasible. Filing an application for license renewal with the Nuclear Regulatory Commission (NRC) entails verifying that the systems, structures, and components essential for safety will continue to perform their safety functions throughout the license renewal period. This paper discusses the current proposed requirements for this verification and the current industry knowledge regarding age-related degradation of structures. Elements of a license renewal program incorporating NRC requirements and industry knowledge including a schedule are presented. Degradation mechanisms for structural components, their significance to nuclear plant structures, and industry-suggested age-related degradation management options are also reviewed

  3. 75 FR 76757 - Licensing Support System Advisory Review Panel

    Science.gov (United States)

    2010-12-09

    ... provide advice on the fundamental issues of design and development of an electronic information management... the disposal of high-level radioactive waste, and on the operation and maintenance of the system. This electronic information management system was known as the Licensing Support System (LSS). In November, 1998...

  4. 31 CFR 596.306 - License.

    Science.gov (United States)

    2010-07-01

    ... ASSETS CONTROL, DEPARTMENT OF THE TREASURY TERRORISM LIST GOVERNMENTS SANCTIONS REGULATIONS General Definitions § 596.306 License. Except as otherwise specified, the term license means any license or...

  5. Understanding Licensing Behavior

    DEFF Research Database (Denmark)

    Cabaleiro, Goretti; Moreira, Solon; Reichstein, Toke

    The potential for rent dissipation has been argued to be the main cause of firms? licensing out behavior being stifled.However, this aspect has been scarcely studied empirically. We draw on rent dissipation arguments, and hypothesize that firms suffering from the not-invented-here (NIH) syndrome......, firms in competitive product markets, and firms that have incurred substantial sunk cost are associated with lower rates of technology out-licensing. We also posit that sunk costs negatively moderate the relationship between competition in the licensor?s product market, and licensing rate. We test our...

  6. Nuclear power stations licensing

    International Nuclear Information System (INIS)

    Solito, J.

    1978-04-01

    The judicial aspects of nuclear stations licensing are presented. The licensing systems of the United States, Spain, France and Federal Republic of Germany are focused. The decree n 0 60.824 from July 7 sup(th), 1967 and the following legislation which define the systematic and area of competence in nuclear stations licensing are analysed [pt

  7. Safety evaluation report related to the renewal of the operating license for the Research Reactor at the State University of New York at Buffalo, Docket No. 50-57

    International Nuclear Information System (INIS)

    1983-05-01

    This Safety Evaluation Report for the application filed by the State University of New York at Buffalo for a renewal of Operating License R-77 to continue to operate a research reactor has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is owned by the State University of New York and is located on the campus in Buffalo, New York. Based on its technical review, the staff concludes that the reactor facility can continue to be operated by the University without endangering the health and safety of the public or endangering the environment

  8. 76 FR 77565 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No...

    Science.gov (United States)

    2011-12-13

    ... intervene shall be filed in accordance with the Commission's ''Rules of Practice for Domestic Licensing...- conservative emergency diesel generator fuel oil supply volumes, incorporate portions of Technical... of the associated Technical Specifications to require an adequate emergency diesel generator and...

  9. Control room habitability survey of licensed commercial nuclear power generating stations

    International Nuclear Information System (INIS)

    Driscoll, J.W.

    1988-10-01

    This document presents the results of a survey of control room habitability systems at twelve commercial nuclear generating stations. The survey, conducted by Argonne National Laboratory (ANL), is part of an NRC program initiated in response to concerns and recommendations of the Advisory Committee on Reactor Safeguards (ACRS). The major conclusion of the report is that the numerous types of potentially significant discrepancies found among the surveyed plants may be indicative of similar discrepancies throughout the industry. The report provides plant-specific and generalized findings regarding safety functions with respect to the consistency of the design, construction, operation and testing of control room habitability systems and corresponding Technical Specifications compared with descriptions provided in the license basis documentation including assumptions in the operator toxic gas concentration and radiation dose calculations. Calculations of operator toxic gas concentrations and radiation doses were provided in the license basis documentation and were not performed by the ANL survey team. Recommendation for improvements are provided in the report

  10. Licensing new nuclear energy plants in the 90s

    International Nuclear Information System (INIS)

    Miller, J.H. III; Bishop, R.W.

    1992-01-01

    This paper reports that the framework for nuclear regulation in the United States was established by Congress in the Atomic Energy Act of 1954 (AEA). Under the AEA, the nuclear power program in the United States was launched with a technology just being developed and a nuclear power industry in its infancy. The regulations fashioned by the Atomic Energy Commission under the AEA took into account the evolving state of the technology and the emerging industry in those formative years. The process required a utility desiring to build and operate a nuclear power plant to obtain two separate licenses: one authorizing construction and one authorizing operation. At the construction permit stage, generally only preliminary design information was available and a construction permit could be issued with as little as ten to fifteen percent of the facility design completed. Thereafter, design completion, along with research and development required to address open technical issues, progressed in tandem with construction in what is fairly characterized as a design-as-you-go process. Only as plant construction approached completion was the adequacy of the final design evaluated in connection with the operating license review process

  11. Comparative assessment of licensing processes of uranium mines in Brazil

    International Nuclear Information System (INIS)

    Silva, K.M.; Menezes, R.M.; Mezrahi, A.

    2002-01-01

    Commercial operation of uranium mining and milling started in Brazil, at the Pocos de Caldas Unit, State of Minas Gerais, in 1982. The Pocos de Caldas Unit was licensed by the Brazilian Regulatory Body (CNEN) and its is now in the decommissioning process. In 2000, a new mining and milling installation, the Caetite Unit, located in State of Bahia, started operation. This paper will discuss how Brazilian Nuclear Energy Commission is licensing the Caetite Unit based on the lessons learned from the Pocos de Caldas Unit. The objective is to draw attention to the importance of the safety assessment for a new unit, specially considering that some wrong decisions were taken for the Pocos de Caldas unit. These decisions lead to less effective long term solutions to protect the environment. Notwithstanding the differences between the two units, it is of great value to use the acquired experience to avoid or minimize the short, medium and long term impacts to the environment and population in the new operation. (author)

  12. FOSS License Selection and Code Management

    OpenAIRE

    Vescuso, Peter

    2011-01-01

    With nearly 2,000 free and open source software (FLOSS) licenses, software license proliferation¿ can be a major headache for software development organizations trying to speed development through software component reuse, as well as companies redistributing software packages as components of their products. Scope is one problem: from the Free Beer license to the GPL family of licenses to platform-specific licenses such as Apache and Eclipse, the number and variety of licenses make it difficu...

  13. Learning-by-Licensing: How Chinese Firms Benefit From Licensing-In Technologies

    DEFF Research Database (Denmark)

    Wang, Yuandi; Roijakkers, N.; Vanhaverbeke, W.

    2012-01-01

    This paper explores how interfirm variations in their in-licensed technology portfolios influence subsequent innovation performance. Existing studies mainly assume licensed technologies are homogeneously accessible to firms, and a prevailing explanation as to why firms vary in their innovation pe...

  14. Regulatory analysis for final rule on nuclear power plant license renewal

    International Nuclear Information System (INIS)

    1991-12-01

    This regulatory analysis provides the supporting information for the final rule (10 CFR Part 54) that defines the Nuclear Regulatory Commission's requirements for renewing the operating licenses of commercial nuclear power plants. A set of four specific alternatives for the safety review of license renewal applications is defined and evaluated. These are: Alternative A-current licensing basis; Alternative B-extension of Alternative A to require assessment and managing of aging; Alternative C -- extension of Alternative B to require assessment of design differences against selected new-plant standards using probabilistic risk assessment; and Alternative D -- extension of Alternative B to require compliance with all new-plant standards. A quantitative comparison of the four alternatives in terms of impact-to-value ratio is presented, and Alternative B is the most cost-beneficial safety review alternative

  15. Use of the Legal-Institutional Analysis Model to assess hydropower licensing negotiations

    Science.gov (United States)

    Burkardt, N.; Lamb, B.L.; Lamb, B.L.; Garcia de Jalon, D.; Sabaton, C.; Souchon, Y.; Tamai, N.; Robinette, H.R.; Waddle, T.J.; Brinson, A.

    2003-01-01

    In the United States, the Federal Energy Regulatory Commission (FERC) is responsible for issuing or renewing licenses for hydropower projects owned and operated by power companies. During the licensing process, these companies are required to consult with agencies and other parties that are affected by project operating regimes. Typical participants include state and federal fish and wildlife agencies, environmental interest groups, and the FERC. One of the most difficult tasks facing participants is to reach agreement about what kinds of environmental conditions should be placed on license. Researchers at the United States Geological Survey developed a model to analyze the institutional context of natural resource disputes. The Legal-Institutional Analysis Model (LIAM) is a computerized model that allows an analyst to determine the likely behavior of each organization in a conflict. The model also analyzes the types and levels of negotiating power held by each organization. Researchers at the USGS have used the model in several cases involving hydropower license applications. To use the model, they facilitate workshops for stakeholder groups in order to develop a shared understanding of the likely obstacles and opportunities for successful resolution of the issues. This allows a systematic workshop analyses to develop strategies for successful negotiations, because they are able to better understand the negotiation problem and work more effectively with both their allies and their competitors.

  16. Flexible licensing

    Directory of Open Access Journals (Sweden)

    Martyn Jansen

    2012-07-01

    Full Text Available The case is presented for a more flexible approach to licensing online library resources. Today's distributed education environment creates pressure for UK higher and further education institutions (HEI/FEIs to form partnerships and to develop educational products and roll them out across the globe. Online library resources are a key component of distributed education and yet existing licensing agreements struggle to keep pace with the increasing range of users and purposes for which they are required. This article describes the process of developing a flexible approach to licensing and proposes a new model licence for online library resources which has the adaptability needed in this new global educational landscape. These ideas have been presented and discussed at various workshops across Eduserv's and JISC Collections' higher education and publisher communities, and further consultation is ongoing.

  17. Trends in nuclear licensing

    Energy Technology Data Exchange (ETDEWEB)

    Dalton, N W [Council for Nuclear Safety, Hennopsmeer, Pretoria (South Africa)

    1990-06-01

    The development of nuclear safety and licensing is briefly reviewed in four stages namely: The Formative Period (1946-1959), The Expansive Period (1960-1969), The Mature Period (1970-1979) and the Apprehensive Period (1980-1989). Particular safety issues in the respective periods are highlighted to indicate the changing emphasis of nuclear licensing over the past thirty years or so. Against this background, nuclear licensing. (author)

  18. Trends in nuclear licensing

    International Nuclear Information System (INIS)

    Dalton, N.W.

    1990-01-01

    The development of nuclear safety and licensing is briefly reviewed in four stages namely: The Formative Period (1946-1959), The Expansive Period (1960-1969), The Mature Period (1970-1979) and the Apprehensive Period (1980-1989). Particular safety issues in the respective periods are highlighted to indicate the changing emphasis of nuclear licensing over the past thirty years or so. Against this background, nuclear licensing. (author)

  19. Nuclear fuel licensing procedures in Bulgaria

    Energy Technology Data Exchange (ETDEWEB)

    Harizanov, Y [Komitet za Mirno Izpolzuvane na Atomnata Energiya, Sofia (Bulgaria). Komysia za Biologichni i Selskostopanski Nauki

    1994-12-31

    A brief description of the structure and role of the Committee on the Use of Atomic Energy for Peaceful Purposes (BG) as a main governmental institution responsible for safety atomic energy management is presented. The main documentation and licensing procedures adopted for import, export, operation, storage and transportation of nuclear material including nuclear fuel for NPP are outlined. The corresponding institutions are facing now the urgent need for changing some regulations to meet the requirements of the international treaties and conventions recently signed by Bulgarian authorities. A new version of Atomic Law disposed at the Parliament for adoption is essential for updating the management of NPP in Bulgaria where four WWER-440 and two WWER-1000 are under operation.

  20. An overview of Class I Structures license renewal Industry Report

    International Nuclear Information System (INIS)

    Statton, J.A.; Renfro, L.J.; Peeifer, B.W.; Deng, D.Z.; Byron, J.

    1991-01-01

    The results of this evaluation indicate that license renewal of Class I Structures is technically achievable and that most age-related degradation can be managed by existing effective programs such that the continued safe operation of the plant is assured. Existing effective programs are satisfactory as long as plant-unique verification of design and operating features is performed. Thus, the conclusions of this IR can be applied to individual plants. (author)

  1. Evaluation of the contribution of license renewal of nuclear power plants to fault reduction in the U.S

    International Nuclear Information System (INIS)

    Chiba, Goro

    2008-01-01

    Although nuclear power plants in the U.S. were originally permitted to operate for 40 years, operating periods of many plants have been extended by license renewal for another 20 years. On the other hand, plant life management of nuclear power plants in Japan is carried out assuming long-term operation, and the licensee submits aging technology assessment reports before the plant has been operating commercially for 30 years, and then every ten years thereafter, and receives an evaluation by the authorities. In this paper, trend analysis using the INSS database on faults at nuclear power plants overseas, state of implementation of relevant aging management programs, and the effects of license renewal on preservation activities are examined. It is shown that the aging management program identified that many of the cases of fatigue, FAC, and a closed cycle cooling system have been addressed. As a result of analyzing the fault number for each unit, the number of aging faults trends to decrease after applying for license renewal. Therefore, the U.S. license renewal system is considered to be effective for plant life management, and hence the plant life management in Japan, which is substantially equivalent to the U.S. system, is valid. (author)

  2. Status report on the HFR conversion and re-licensing project

    International Nuclear Information System (INIS)

    Wijtsma, F.G.

    2003-01-01

    In 1999 the HFR license holder (JRC, Petten, the Netherlands) initiated a project to study the conversion of the HFR from HEU to LEU. The first phase of this project consisted of a parametric study to determine the optimum fuel element and control rod design within given boundary conditions such as geometry, density, performance and cycle length. Results of this study are a 22 plates fuel element (550 g 235 U) at a density of 4.8 g.cm -3 and a 17 plates control rod (440 g 235 U). The second phase contains all aspects related to the conversion including a full-scale test irradiation of a prototype LEU element. The actual conversion of the HFR requires a new license. For this reason the re-licensing project has started in 2001. In this context many studies have been performed e.g. Risk Scoping Study, Safety Analyses, TOPA (Technical, Operational, Personnel and Administrative) evaluation. The license application will be based on a new Safety Report and an Environmental Impact Statement and will be submitted to the competent Authorities at the end of October 2003. (author)

  3. 75 FR 37471 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No...

    Science.gov (United States)

    2010-06-29

    ... accordance with the Commission's ``Rules of Practice for Domestic Licensing Proceedings'' in 10 CFR Part 2... Specifications (TSs) to extend the allowed outage time (AOT) for the ``A'' and ``B'' emergency diesel generators... emergency diesel generators are safety related components which provide backup electrical power supply to...

  4. Reactor licensing in the United States and Federal Republic of Germany

    International Nuclear Information System (INIS)

    Salvatore, J.E.L.

    1980-02-01

    The licensing procedure for nuclear power plants in the United States and in the Federal Republic of Germany is analysed. The security policy, the inspections and the supervision during their construction and operation are discussed. (A.L.) [pt

  5. How to ensure the safety of extended operations: Practice and experience of Paks NPP

    International Nuclear Information System (INIS)

    Kovacs, J.

    2005-01-01

    The Paks Nuclear Power Plant strategy is to extend the operational lifetime of the plant and renew the operational license for 20 years over the designed and licensed lifetime. In the paper the preconditions of long-term operation are discussed and the basic findings and experience of the license renewal works are also presented. The further plans fo NPP Paks for ensuring safe operation in long-term are discussed. (author)

  6. Special feature of the facilities for final disposal of radioactive waste and its potential impact on the licensing process

    International Nuclear Information System (INIS)

    Lee Gonzales, Horacio M.; Medici, Marcela A.; Alvarez, Daniela E.; Biaggio, Alfredo L.

    2009-01-01

    During the lifetime of a radioactive waste disposal facility it is possible to identify five stages: design, construction, operation, closure and post-closure. While the design, and pre-operation stages are, to some extent, similar to other kind of nuclear or radioactive facilities; construction, operation, closure and post-closure have quite special meanings in the case of radioactive waste disposal systems. For instance, the 'closure' stage of a final disposal facility seems to be equivalent to the commissioning stage of a conventional nuclear or radioactive facility. This paper describes the unique characteristics of these stages of final disposal systems, that lead to concluded that their licensing procedure can not be assimilated to the standard licensing procedures in use for other nuclear or radioactive facilities, making it necessary to develop a tailored license system. (author)

  7. Exploitation of BEPU Approach for the Licensing Process

    International Nuclear Information System (INIS)

    D'Auria, F.; Petruzzi, A.; Muellner, A.N.; Mazzantini, O.

    2011-01-01

    Within the licensing process of the Atucha II PHWR (Pressurized Heavy Water Reactor) the BEPU (Best Estimate Plus Uncertainty) approach has been selected for issuing of the Chapter 15 on FSAR (Final Safety Analysis Report). The key steps of the entire process are basically two: a) the selection of PIE (Postulated Initiating Events) and, b) the analysis by best estimate models supported by uncertainty evaluation. The key elements of the approach are: 1) availability of qualified computational tools including suitable uncertainty method; 2) demonstration of quality; 3) acceptability and endorsement by the licensing authority. The effort of issuing Chapter 15 is terminated at the time of issuing of the present paper and the safety margins available for the operation of the concerned NPP (Nuclear Power Plant) have been quantified. (authors)

  8. Compulsory licensing in Canada and Thailand: comparing regimes to ensure legitimate use of the WTO rules.

    Science.gov (United States)

    Lybecker, Kristina M; Fowler, Elisabeth

    2009-01-01

    This paper examines two recent examples of compulsory licensing legislation: one globally embraced regime and one internationally controversial regime operating under the same WTO rules. In particular, we consider Canadian legislation and the use of compulsory licensing for HIV/AIDS drugs destined for a developing country. This is then contrasted with the conditions under which Thai authorities are pursuing compulsory licenses, the outcomes of their compulsory licenses, as well as the likely impact of the Thai policy. Finally, we construct a rubric to evaluate characteristics of a successful regime. This is used to analyze the Canadian and Thai regimes and frame the expected implications of each national policy. It is hoped that the assessment will guide changes to compulsory licensing design to ensure that legitimate regimes are embraced while illegitimate ones are disallowed.

  9. Public perspectives on proposed license renewal regulations for nuclear power plants

    International Nuclear Information System (INIS)

    Ligon, D.; Hughes, A.; Seth, S.

    1991-01-01

    On 17 July 1990, the U.S Nuclear Regulatory Commission (NRC) issued for public comment its proposed rule for renewing the operating licenses of nuclear power plants (55 FR 29043). This solicitation marked the fourth time that NRC has Invited public comments on its efforts to develop regulatory requirements for re licensing nuclear power plants. Previously, NRC solicited public comments on establishing a policy statement on plant life extension, and on the issues and options for license renewal discussed in NUREG-1317. On 13-14 November 1989, NRC held a public workshop where the NRC staff discussed a conceptual approach to the rule and solicited written comments on the regulatory philosophy, conceptual rule, and on certain questions. NRC is taking into account all comments received in its development of the final rule which is scheduled for issuance in the summer of 1991

  10. Graduated driver licensing and differential deterrence: The effect of license type on intentions to violate road rules.

    Science.gov (United States)

    Poirier, Brigitte; Blais, Etienne; Faubert, Camille

    2018-01-01

    In keeping with the differential deterrence theory, this article assesses the moderating effect of license type on the relationship between social control and intention to violate road rules. More precisely, the article has two objectives: (1) to assess the effect of license type on intentions to infringe road rules; and (2) to pinpoint mechanisms of social control affecting intentions to violate road rules based on one's type of driver license (a restricted license or a full license). This effect is examined among a sample of 392 young drivers in the province of Quebec, Canada. Drivers taking part in the Graduated Driver Licensing (GDL) program have limited demerit points and there is zero tolerance for drinking-and-driving. Propensity score matching techniques were used to assess the effect of the license type on intentions to violate road rules and on various mechanisms of social control. Regression analyses were then conducted to estimate the moderating effect of license type. Average treatment effects from propensity score matching analyses indicate that respondents with a restricted license have lower levels of intention to infringe road rules. While moral commitment and, to a lesser extent, the perceived risk of arrest are both negatively associated with intentions to violate road rules, the license type moderates the relationship between delinquent peers and intentions to violate road rules. The effect of delinquent peers is reduced among respondents with a restricted driver license. Finally, a diminished capability to resist peer pressure could explain the increased crash risk in months following full licensing. Copyright © 2017 Elsevier Ltd. All rights reserved.

  11. Training programme for direct operating functions

    International Nuclear Information System (INIS)

    Reuhl, R.

    1986-01-01

    In the lecture the initial and retraining programs for licensed and non-licensed nuclear power plant shift personnel will be commented. The programs were developed by Biblis Nuclear Power Plant Operations Management (RWE-Betriebsverwaltung) with regard to one decade of operational experience in Biblis nuclear power plants (2 PWR, 1300/1204 MW) and on the basis of the existing guidelines issued by the German Federal Ministry of the Interior. During the application and the constant development of the training programs emphasis was put on the connection of theory and practice following a special training strategy using different training facilities. In this context the role and qualification of the licensed instructors with shift supervisor experience get high importance. (orig./GL)

  12. 76 FR 52699 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No...

    Science.gov (United States)

    2011-08-23

    ... proposes to credit the automatic trip of the main turbine upon the initiation of a manual reactor trip for... credited manual reactor trip action that is part of the current licensing basis. Considerable defense-in... more robust AREVA Advanced W17 high thermal performance (HTP) fuel at Sequoyah Nuclear Plant (SQN...

  13. 75 FR 48370 - Biweekly Notice Applications and Amendments to Facility Operating Licenses Involving No...

    Science.gov (United States)

    2010-08-10

    ... ensures the timely transfer of plant safety system loads to the Emergency Diesel Generators in the event a... a margin of safety. The basis for this proposed determination for each amendment request is shown... Commission's ``Rules of Practice for Domestic Licensing Proceedings'' in 10 CFR Part 2. Interested person(s...

  14. 75 FR 52039 - Biweekly Notice Applications and Amendments to Facility Operating Licenses Involving No...

    Science.gov (United States)

    2010-08-24

    ... the design earthquake, the double design earthquake, the Hosgri earthquake, and the loss-of-coolant... by the Chief Administrative Judge of the Atomic Safety and Licensing Board Panel, will rule on the....m. Eastern Time on the due date. Upon receipt of a transmission, the E-Filing system time-stamps the...

  15. Development and licensing of a melting plant for Chernobyl scrap

    International Nuclear Information System (INIS)

    Sappok, M.; Zunk, H.; Fashevsky, K.A.

    1998-01-01

    One decade after the accident at unit 4 of the Chernobyl nuclear power station, a melting plant for radioactively contaminated metallic materials, the so-called SURF facility, is being planned and licensed for erection in the direct neighbourhood of the NPP area. Main goal is the recycling of the material largely decontaminated by the melting process, by means of manufacturing of casks and containers for waste disposal and of shielding equipment. The melting plant will be part of the Ukrainian waste handling centre (CPPRO). The technology is based on the long-term experience gained at Siempelkamp's CARLA plant in Krefeld. Within 1995 and 1996 the licensing conditions were defined, the licensing documents prepared and the formal procedure initiated. The complex is scheduled to start operation in 2001, in case the necessary financing is allocated. To this end the proposed site of the facility has undergone the state assessment. The technical documentation for construction is at the stage of development. (author)

  16. Establishing a safety and licensing basis for generation IV advanced reactors. License by test

    International Nuclear Information System (INIS)

    Kadak, Andrew C.

    2001-01-01

    The license by test approach to licensing is a novel method of licensing reactors. It provides an opportunity to deal with innovative non-water reactors in a direct way on a time scale that could permit early certification based on tests of a demonstration reactor. The uncertainties in the design and significant contributors to risk would be identified in the PRA during the design. Deterministic analysis computer codes could be tested on a real reactor. Scaling effects and associated uncertainties would be minimized. License by test is an approach that has sufficient merit to be developed and tested

  17. French legislation on food irradiation - Licensing procedure

    International Nuclear Information System (INIS)

    Souverain, R.

    1977-01-01

    French legislation on food irradiation subjects marketing of such foodstuffs to a prior licence granted by an interministerial order on the type of goodstuff concerned. The basic text on the licensing procedure is the Decree of 8 May 1970 whose purpose is to ensure the health and safety of the consumer by laying down instructions for the operations, surveillance and labelling, which must set out clearly the type of treatment. (NEA) [fr

  18. 22 CFR 96.30 - State licensing.

    Science.gov (United States)

    2010-04-01

    ... Licensing and Corporate Governance § 96.30 State licensing. (a) The agency or person is properly licensed or... person follows applicable State licensing and regulatory requirements in all jurisdictions in which it provides adoption services. (c) If it provides adoption services in a State in which it is not itself...

  19. Safety philosophy and licensing practice in different member states of IAEA: Canada

    International Nuclear Information System (INIS)

    Boyd, F.C.

    1981-01-01

    The lecture will provide an outline of the Canadian nuclear organization and basic characteristics of the CANDU reactor as a background for a brief description of the nuclear power plant licensing process and the safety philosophy followed. The regulatory agency (Atomic Energy Control Board) follows a three step licensing procedure, Site Acceptance, Construction Approval, Operating Licence. Defense in depth is followed as a general safety concept, but is applied in a special way. Completely separate and independant safety systems are required and basic criteria established through reference dose limits for any assumed failure (or initiating event) in any process (operating) system and for any such failure combined with complete failure at any safety system. The application of the Canadian approach in other countries will be mentioned. (orig./RW)

  20. NRC as referee (reactor licensing following the Three Mile Island accident)

    International Nuclear Information System (INIS)

    Eisenhut, D.G.

    1984-01-01

    In this article, the NRC's licensing director reports on the progress made by US utilities in complying with the key regulations stemming from the Three Mile Island accident. Over 130 items must be improved at more than 65 reactors. The actions taken by France in response to its own analysis of the accident are discussed. New NRC requirements with regard to operational safety, design, and emergency-response capability are outlined. Nearly all the training, or software, items in Nureg-0737 (''Clarification of TMI Action Plan Requirements'') and more than half of the mechanical, or hardware, items have been completed at plants with operating reactors. The Committee to Review Generic Requirements was created to develop means for controlling the number and nature of NRC requirements placed on licensees. Probabilistic risk-assessment techniques were not widely used by the NRC until after the Three Mile Island accident. The NRC has directed licensees and applicants for operating licenses to conduct control-room design reviews to identify and correct human-engineering discrepancies. Includes 2 tables

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

    International Nuclear Information System (INIS)

    Freers, S.M.; Hyman, M.

    1987-01-01

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

  2. Licensing of ANSTO's Replacement Research Reactor

    International Nuclear Information System (INIS)

    Summerfield, M.W.; Garea, V.

    2003-01-01

    This paper presents a general description of the licensing of the 20 MW Pool-type Replacement Research Reactor (RRR) currently being built by the Australian Nuclear Science and Technology Organisation (ANSTO) at their Lucas Heights site. The following aspects will be addressed: 1) The influence of ARPANSA's (the Australian regulator) Regulatory Assessment Principles and Design Criteria on the design of the RRR. 2) The Site Licence Application, including the EIS and the supporting siting documentation. 3) The Construction Licence Application, including the PSAR and associated documentation. 4) The review process, including the IAEA Peer Review and the Public Submissions as well as ARPANSA's own review. 5) The interface between ANSTO, INVAP and ARPANSA in relation to the ongoing compliance with ARPANS Regulation 51 and 54. 6) The future Operating Licence Application, including the draft FSAR and associated documentation. These aspects are all addressed from the point of view of the licensee ANSTO and the RRR Project. Particular emphasis will be given to the way in which the licensing process is integrated into the overall project program and how the licensing and regulatory regime within Australia influenced the design of the RRR. In particular, the safety design features that have been incorporated as a result of the specific requirements of ANSTO and the Australian regulator will be briefly described. The paper will close with a description of how the RRR meets, and in many aspects exceeds the requirements of ANSTO and the Australian regulator. (author)

  3. Decay power evaluation for licensing analysis

    International Nuclear Information System (INIS)

    Tran, H.; Schrock, V.E.

    1987-01-01

    The ANSI/ANS 5.1-1979 Standard on Decay Power in shutdown reactors has been available as the basis for accident analysis for the past 7 yr. The US Nuclear Regulatory Commission has made a commitment to use this standard in new licensing approaches and has approved a licensing model for boiling water. More sweeping changes in the licensing rules are currently under review that will involve the use of best-estimate models and a statistical evaluation of the uncertainty (95% confidence level) in the key results. The structure of the decay power standard is well suited for such applications because it provides a statistically meaningful uncertainty in the decay power from fission products. The normalized decay power is a function specific to each point in the reactor volume due to the fact that the fuel composition develops a spatial dependence as burnup proceeds and decay power depends on the mix of fissioning nuclides. For reactor safety calculations it is desirable to employ a single temporal decay power function for the whole core inasmuch as many variations of accident parameters are required. This is the usual approach in large system thermal-hydraulics codes. Such a single representative or generic curve for a specified total operating power history can be acceptable but at the expense of some increase in the uncertainty. In this paper, the author present a method of evaluating the additional uncertainty in the decay power associated with use of a generic curve

  4. Licensing in an International Market

    Science.gov (United States)

    Ferreira, Fernanda A.

    2008-09-01

    We study the effects of entry of a foreign firm on domestic welfare in the presence of licensing, when the entrant is technologically superior to the incumbent. We show that foreign entry increases domestic welfare for sufficiently large technological differences between the firms under both fixed-fee licensing and royalty licensing.

  5. 22 CFR 120.20 - License.

    Science.gov (United States)

    2010-04-01

    ... 22 Foreign Relations 1 2010-04-01 2010-04-01 false License. 120.20 Section 120.20 Foreign Relations DEPARTMENT OF STATE INTERNATIONAL TRAFFIC IN ARMS REGULATIONS PURPOSE AND DEFINITIONS § 120.20 License. License means a document bearing the word “license” issued by the Directorate of Defense Trade...

  6. 48 CFR 227.7203-4 - License rights.

    Science.gov (United States)

    2010-10-01

    ... Software and Computer Software Documentation 227.7203-4 License rights. (a) Grant of license. The... license, under an irrevocable license granted or obtained by the contractor which developed the software... granted to the Government. The scope of a computer software license is generally determined by the source...

  7. Enhancing operational safety

    Energy Technology Data Exchange (ETDEWEB)

    Wiebe, J S

    1997-09-01

    The presentation briefly considers the following aspects concerning enhancing operational safety of NPP: licensed control room supervision, reactivity changes, personnel access to control room, simulator training.

  8. Current status of construction license of PEFP

    International Nuclear Information System (INIS)

    Kim, J. Y.; Cho, J. S.; Min, Y. S.; Nam, J. M.; Jeon, G. P.; Park, S. S.; Jo, J. H.; Song, I. T.

    2012-01-01

    Since 2010 August, PEFP(Proton Engineering Frontier Project)'s Proton Accelerator Research Center has been under construction so far. Generally, in advance of construction startup, many kinds of licenses should be acquired along with the types of construction works. To acquire a license in time, each item should meet the standard by the related regulation, including not only procedural but also content aspect. In the advent of internet era, electronic government system has been adopted in many governmental functions: So is the national construction license acquisition system. Owing to the system, both approval and documentation functions in licensing are integrated in online computer network which provide us simplification in process and easy accessibility to license data. However, aside from these construction licenses, other types of licenses still remain separately managed: Machinery, electric facilities, and so on. Moreover, all the licenses have the priority order and take legal term in processing. So, to avoid any time delay in license acquisition, we organized license hierarchy and found out the priority among them. Thereafter, according to their legal term in approval and acquisition, whole license acquisition schedule was arranged and we completed all the necessary licenses acquisition in time In this study, we summarize the current status of license acquisition on Proton Accelerator Research Center Construction, and manifest how they have been and will be managed systematically

  9. Current status of construction license of PEFP

    Energy Technology Data Exchange (ETDEWEB)

    Kim, J. Y.; Cho, J. S.; Min, Y. S.; Nam, J. M.; Jeon, G. P.; Park, S. S.; Jo, J. H.; Song, I. T. [KAERI, Daejeon (Korea, Republic of)

    2012-10-15

    Since 2010 August, PEFP(Proton Engineering Frontier Project)'s Proton Accelerator Research Center has been under construction so far. Generally, in advance of construction startup, many kinds of licenses should be acquired along with the types of construction works. To acquire a license in time, each item should meet the standard by the related regulation, including not only procedural but also content aspect. In the advent of internet era, electronic government system has been adopted in many governmental functions: So is the national construction license acquisition system. Owing to the system, both approval and documentation functions in licensing are integrated in online computer network which provide us simplification in process and easy accessibility to license data. However, aside from these construction licenses, other types of licenses still remain separately managed: Machinery, electric facilities, and so on. Moreover, all the licenses have the priority order and take legal term in processing. So, to avoid any time delay in license acquisition, we organized license hierarchy and found out the priority among them. Thereafter, according to their legal term in approval and acquisition, whole license acquisition schedule was arranged and we completed all the necessary licenses acquisition in time In this study, we summarize the current status of license acquisition on Proton Accelerator Research Center Construction, and manifest how they have been and will be managed systematically.

  10. Technology Licensing and Firm Innovation

    DEFF Research Database (Denmark)

    Moreira, Solon

    acquisition. The findings indicate that technology licensing is positively related to the number of inventions produced by the licensee in the years subsequent to the licensing deal. Subsequently, I investigate the moderating effect that organizational slack and myopia have on this main relationship....... The findings also suggest that high levels of Organizational Slack (available financial resources) strengthen the positive effect of licensing on innovation. However, higher levels of Organizational Myopia (the extent to which a firm draws on its own knowledge) can decrease the main effect of licensing....

  11. Considerations about the licensing process of special nuclear industrial facilities

    Energy Technology Data Exchange (ETDEWEB)

    Talarico, M.A., E-mail: talaricomarco@hotmail.com [Marinha do Brasil, Rio de Janeiro, RJ (Brazil). Coordenacao do Porgrama de Submarino com Propulsao Nuclear; Melo, P.F. Frutuoso e [Coordenacao dos Programas de Pos-Graduacao em Engenharia (COPPE/UFRJ), Rio de Janeiro, RJ (Brazil). Programa de Engenharia Nuclear

    2015-07-01

    This paper brings a discussion about the challenges involved in the development of a new kind of nuclear facility in Brazil, a naval base for nuclear submarines, with attention to the licensing process and considerations about the risk-informed decision making application to the licensing process. Initially, a model of such a naval base, called in this work, special industrial facility, is proposed, with its systems and respective sets of basic requirements, in order to make it possible the accomplishment of the special industrial facility support function to the nuclear submarine. A discussion about current challenges to overcome in this project is presented: the challenges due to the new characteristics of this type of nuclear facility; existence of several interfaces between the special industrial facilities systems and nuclear submarine systems in design activities; lack of specific regulation in Brazil to allow the licensing process of special industrial facilities by the nuclear safety authority; and comments about the lack of information from reference nuclear facilities, as is the case with nuclear power reactors (for example, the German Grafenrheinfeld nuclear plant is the reference plant for the Brazilian Angra 2 nuclear plant). Finally, in view of these challenges, an analysis method of special industrial facility operational scenarios to assist the licensing process is proposed. Also, considerations about the application of risk-informed decision making to the special industrial facility activity and licensing process in Brazil are presented. (author)

  12. Considerations about the licensing process of special nuclear industrial facilities

    International Nuclear Information System (INIS)

    Talarico, M.A.; Melo, P.F. Frutuoso e

    2015-01-01

    This paper brings a discussion about the challenges involved in the development of a new kind of nuclear facility in Brazil, a naval base for nuclear submarines, with attention to the licensing process and considerations about the risk-informed decision making application to the licensing process. Initially, a model of such a naval base, called in this work, special industrial facility, is proposed, with its systems and respective sets of basic requirements, in order to make it possible the accomplishment of the special industrial facility support function to the nuclear submarine. A discussion about current challenges to overcome in this project is presented: the challenges due to the new characteristics of this type of nuclear facility; existence of several interfaces between the special industrial facilities systems and nuclear submarine systems in design activities; lack of specific regulation in Brazil to allow the licensing process of special industrial facilities by the nuclear safety authority; and comments about the lack of information from reference nuclear facilities, as is the case with nuclear power reactors (for example, the German Grafenrheinfeld nuclear plant is the reference plant for the Brazilian Angra 2 nuclear plant). Finally, in view of these challenges, an analysis method of special industrial facility operational scenarios to assist the licensing process is proposed. Also, considerations about the application of risk-informed decision making to the special industrial facility activity and licensing process in Brazil are presented. (author)

  13. 31 CFR 596.309 - Specific license.

    Science.gov (United States)

    2010-07-01

    ... FOREIGN ASSETS CONTROL, DEPARTMENT OF THE TREASURY TERRORISM LIST GOVERNMENTS SANCTIONS REGULATIONS General Definitions § 596.309 Specific license. The term specific license means any license or...

  14. Online driver's license renewal.

    Science.gov (United States)

    2015-09-01

    The Kentucky Department of Vehicle Regulation is exploring the possibility of developing and implementing online : drivers license renewal. The objective of this project was to: 1) evaluate online drivers license and REAL ID renewal : programs ...

  15. 31 CFR 596.305 - General license.

    Science.gov (United States)

    2010-07-01

    ... FOREIGN ASSETS CONTROL, DEPARTMENT OF THE TREASURY TERRORISM LIST GOVERNMENTS SANCTIONS REGULATIONS General Definitions § 596.305 General license. The term general license means any license or authorization...

  16. 75 FR 13786 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No...

    Science.gov (United States)

    2010-03-23

    ... earthquake (DE), double design earthquake (DDE), Hosgri earthquake (HE), and loss of coolant accident (LOCA... Administrative Judge of the Atomic Safety and Licensing Board Panel, will rule on the request and/or petition...-Filing system no later than 11:59 p.m. Eastern Time on the due date. Upon receipt of a transmission, the...

  17. New trends in the evaluation and implementation of the safety-related operating experience associated with NRC-licensed reactors

    International Nuclear Information System (INIS)

    Michelson, C.; Heltemes, C.J.

    1981-01-01

    This article is an overview of the Nuclear Regulatory Commission program for the evaluation and dissemination of the safety-related operating experience associated with all NRC-licensed reactors. It discusses the historical background and past problems that led to the recent formation of NRC's Office for Analysis and Evaluation of Operational Data (AEOD) and details its activities, organization, staffing, and proposed analysis and evaluation methodology. The programs of industry organizations and nuclear plant licensees and the integration of foreign operating experience are included in the overview. The problems and limitations of the Licensee Event Report (LER) program and the Nuclear Plant Reliability Data system program are discussed. The AEOD analysis and evaluation methodology program includes some new improvements in the assessment of safety-related operating experience. Of particular note is the sequence coding and search procedure being developed by AEOD under a contract with the Nuclear Safety Information Center at the Oak Ridge National Laboratory. This computer-based retrieval system will have markedly improved search strategy capability for such items as commoncause failures or complex system interactions involving various failure sequences and other relationships associated with an event. The system retrieves failure data and information on the principal LER occurrence and on related component and system responses. The computer-generated Power Reactor Watch List enables AEOD to monitor all critical or unusual situations warranting close attention because of potential public health and safety. This listing is supported by a preestablished computer search strategy of the historical data base permitting identification of all past events and statistical information that are applicable to the situation being watched

  18. Licensing procedures and safety criteria for core conversion in Japan

    International Nuclear Information System (INIS)

    Kanda, K.; Nakagome, Y.; Hayashi, M.

    1983-01-01

    In Japan, the establishment and operation of nuclear installations are governed mainly by the Law for Regulation of Nuclear Source Material, Nuclear Fuel Material and Reactors. This law lays down the regulations and conditions for licensing of the various installations involved in the nuclear fuel cycle, namely licensing of installations for refining, fabricating and reprocessing; and reactors, as well as licensing of the use of nuclear fuels in research facilities. Although procedures for the installations listed above vary depending on the installation concerned, only those relating to construction and operation of reactor facilities will be analysed in this study, as the conditions and principles applying to licensing and control of other installations are, to a large extent, similar to those concerning reactor facilities. The second part of this presentation describes the safety review of the KUCA reactor core conversion form HEU to MEU. For the safety review of the core conversion, the Committee on Examination of Reactor Safety of Japanese Government examined mainly the the nuclear characteristics and the integrity of aluminide fuel plates, which was very severe because we had no experience to use aluminide fuel plates in Japan. The integrity of fuel plates and the results of the worst accident analysis for the MEU core are shown with the comparison between the HEU and MEU cores. The significant difference was not observed between them. All the regulatory procedures were completed in September 1980. Fabrication of MEU fuel elements for the KUCA experiments by CERCA in France was started in September 1980, and will be completed in March 1981. The critical experiments in the KUCA with MEU fuel will be started on a single-core in May 1981 as a first step. Those on a coupled-core will follow

  19. Licensing an assured isolation facility for low-level radioactive waste. Volume 1: Licensing strategy and issues

    International Nuclear Information System (INIS)

    Silverman, D.J.; Bauser, M.A.; Baird, R.D.

    1998-07-01

    This report provides a detailed set of proposed criteria and guidance for the preparation of a license application for an assured isolation facility (AIF). The report is intended to provide a detailed planning basis upon which a prospective applicant may begin pre-licensing discussions with the Nuclear Regulatory Commission and initiate development of a license application. The report may also be useful to the NRC or to state regulatory agencies that may be asked to review such an application. Volume 1 of this report provides background information, and describes the licensing approach and methodology. Volume 2 identifies specific information that is recommended for inclusion in a license application

  20. EMPIRICAL STUDY OF CAR LICENSE PLATES RECOGNITION

    Directory of Open Access Journals (Sweden)

    Nasa Zata Dina

    2015-01-01

    Full Text Available The number of vehicles on the road has increased drastically in recent years. The license plate is an identity card for a vehicle. It can map to the owner and further information about vehicle. License plate information is useful to help traffic management systems. For example, traffic management systems can check for vehicles moving at speeds not permitted by law and can also be installed in parking areas to se-cure the entrance or exit way for vehicles. License plate recognition algorithms have been proposed by many researchers. License plate recognition requires license plate detection, segmentation, and charac-ters recognition. The algorithm detects the position of a license plate and extracts the characters. Various license plate recognition algorithms have been implemented, and each algorithm has its strengths and weaknesses. In this research, I implement three algorithms for detecting license plates, three algorithms for segmenting license plates, and two algorithms for recognizing license plate characters. I evaluate each of these algorithms on the same two datasets, one from Greece and one from Thailand. For detecting li-cense plates, the best result is obtained by a Haar cascade algorithm. After the best result of license plate detection is obtained, for the segmentation part a Laplacian based method has the highest accuracy. Last, the license plate recognition experiment shows that a neural network has better accuracy than other algo-rithm. I summarize and analyze the overall performance of each method for comparison.

  1. Renewing the licenses of US nuclear plants: An assessment of the socioeconomic impacts

    International Nuclear Information System (INIS)

    Schweitzer, M.; Saulsbury, J.W.; Schexnayder, S.M.

    1993-01-01

    In recent years, increased national attention has been focused on the potential effects of renewing, or not renewing, the licenses of nuclear power plants as the oldest of them approach the end of the 40-year operating period allowed by their original licenses. As part of a larger study for the US Nuclear Regulatory commission (NRC), the authors conducted an assessment of the potential socioeconomic impacts to those communities throughout the country in which nuclear power plants are located and which, therefore, are most directly affected by renewal of nuclear power plant licenses. This paper focuses on six key issues that are traditionally considered essential in the assessment of social impacts: Population; housing; tax payments; local public services; land use and development; and economic structure

  2. 19 CFR 111.45 - Revocation by operation of law.

    Science.gov (United States)

    2010-04-01

    ... operation of law. (a) License. If a broker that is a partnership, association, or corporation fails to have, during any continuous period of 120 days, at least one member of the partnership or at least one officer... operation of law of the license and any permits issued to the partnership, association, or corporation. The...

  3. Licensing system for primary category radioactive installations

    International Nuclear Information System (INIS)

    Ramirez Riquelme, Angelica Beatriz

    1997-01-01

    The development of a licensing system for primary category radioactive installations is described, which aims to satisfy the needs of the Chilean Nuclear Energy Commission's Department of Nuclear and Radiological Safety, particularly the sections for Licensing Outside Radioactive Installations and Safety Control. This system involves the identification, control and inspection of the installations, their personnel and connected activities, for the purpose of protecting the population's health and the environment. Following the basic cycle methodology, a systems analysis and engineering stage was prepared, establishing the functions of the system's elements and defining the requirements, based on interviews with the users. This stage was followed by the design stage, focusing on the data structure, the software architecture and the procedural detail. The codification stage followed, which translated the design into legible machine-readable format. In the testing stage, the entries that were defined were proven to produce the expected data. Finally and operational and maintenance stage was developed, when the system was installed and put to use. All the above generated a useful system for the Licensing section of the Department of Nuclear and Radiological Safety, since it provides faster and easier access to information. A project is described that introduces new development tools in the Computer department following standards established by the C.CH.E.N. (author)

  4. Generic environmental impact statement for license renewal of nuclear plants. Final report

    International Nuclear Information System (INIS)

    1996-05-01

    This GEIS examines the possible environmental impacts that could occur as a result of renewing the licenses of individual nuclear power plants under 10 CFR 54. To the extent possible, it establishes the bounds and significance of these potential impacts. The analysis encompasses all operating light-water reactors. For each type of environmental impact, the GEIS attempts to establish generic findings covering as many plants as possible. While plant and site-specific information is used in developing the generic findings, the NRC does not intend for the GEIS to be a compilation of individual plant environmental impacts statements. This document has three principal objectives: (1) to provide an understanding of the types and severity of environmental impacts that may occur as a result of license renewal, (2) to identify and assess those impacts that are expected to be generic to license renewal, and (3) to support rulemaking (10 CFR 51) to define the number and scope of issues that need to be addressed by the applicants in plant-by-plant license renewal proceedings

  5. Licensing aspects regarding the RBMN project

    International Nuclear Information System (INIS)

    Cuccia, Valeria; Sacramento, Arivaldo M.; Aleixo, Bruna L.; Ferreira, Vinicius V.M.

    2013-01-01

    The licensing process of a waste disposal facility is a complex and demanding undertaking. It proceeds in phases, starting with the site selection and ending many decades later, when the radionuclides decayed and no longer offer possible hazard. That is one of the reasons why the licensing process for the Brazilian repository for low and intermediate level radioactive waste (RBMN Project) is a challenge for all the technicians involved. Besides that, the only national experience associated to this subject arose after a radiological accident in the State of Goias, in 1987. Two different institutions are involved in this licensing process: IBAMA, for environmental licensing, and CNEN, for nuclear licensing. Both of them will evaluate the possible impacts caused by the waste disposal, so it is essential to avoid conflicts and duplications of activities. The RBMN project has different teams for each main activity, and one of them is the Licensing group. This team has been planning the licensing activities for the repository, studying the legal framework and estimating costs and execution time for each step. This paper presents the status of the licensing activities regarding to the RBMN project done by the CNEN staff. (author)

  6. Managing Licensing in a Market for Technology

    DEFF Research Database (Denmark)

    Arora, Ashish; Rønde, Thomas; Fosfuri, Andrea

    the technology makes licensing decisions—to centralized licensing. The business unit has superior information about licensing opportunities but may not have the appropriate incentives because its rewards depend upon product market performance. If licensing is decentralized, the business unit forgoes valuable...... licensing opportunities since the rewards for licensing are (optimally) weaker than those for product market profits. This distortion is stronger when production-based incentives are more powerful, making centralization more attractive. Growth of technology markets favors centralization and drives higher...

  7. Licensing for industrial gamma and X-ray radiography installation in Peru

    International Nuclear Information System (INIS)

    Medina G, E.

    1988-01-01

    According the regulations for ionizing radiation source installations an application to the Peruvian National Authority should be forwarded in order to get the construction on operation license both industrial gamma and X-ray. Radiography is considered as well as personnel aspects. The proceedings are described

  8. New Reactor Siting, Licensing and Construction Experience. Proceedings of the 2. CNRA International Workshop on 'New Reactor Siting, Licensing and Construction Experience'

    International Nuclear Information System (INIS)

    2013-01-01

    This report documents the proceedings from the 2. Workshop on New Reactor Siting, Licensing and Construction Experience. A total of 45 specialists from 16 countries and international organisations attended. The meeting was sponsored by the OECD Nuclear Energy Agency Committee on Nuclear Regulatory Activities and hosted by the US Nuclear Regulatory Commission (U.S.NRC). The objectives of the workshop were to provide a forum to exchange information on lessons learned from siting, licensing and constructing new nuclear power plants around the world. Key focus areas included siting practices and regulatory positions that have been enhanced as a result of the Fukushima accident; lessons learned from licensing and design review approaches and challenges, construction experience and recommendations for regulatory oversight; and regulatory cooperation on generic and design specific issues through the MDEP specific working groups. The workshop was structured in 4 technical sessions, each followed by ample time for panel discussions. The first technical session was devoted to regulatory cooperation on generic and design specific issues, MDEP working groups (EPR, AP1000), vendor inspection co-operation, digital I and C, and codes and standards. The second technical session was intended to discuss and share regulatory positions on siting practices and enhancements as a result of lessons learned from Fukushima accident. The third technical session addressed the construction experience and regulatory oversight of new reactor construction activities. And the fourth technical session included presentations on the lessons learned from regulatory licensing reviews of new reactor designs

  9. Perspective about the US license Renewal for NNPP's; Perspectiva sobre la renovacion de licencia para centrales nucleares en los Estados Unidos

    Energy Technology Data Exchange (ETDEWEB)

    Lehnert, D. F.

    2004-07-01

    This article provides and overview of the US License Renewal Rule, 10 CFR 54, and its implementation in the US leading to the preparation and review of a license renewal application. The key regulatory documents and the industry's methodology and guidance for successfully implementing the Rule are discussed. While the process still undergoes change and optimization, it has become predictable and reliable, such that utilities can establish realistic schedules and budgets to complete the license renewal process. Nearly 60% of the US operating units have either received and extended operating license, have submitted their application for review, or have committed to submit an application in the next few years. The article concludes with a discussion of lessons learned from this wealth of experience and some emerging issues that may affect license renewal process. (Author)

  10. Application of up-front licensing

    Energy Technology Data Exchange (ETDEWEB)

    Grant, S D [Atomic Energy of Canada Ltd., Saskatoon, SK (Canada); Snell, V G [Atomic Energy of Canada Ltd., Mississauga, ON (Canada)

    1996-12-31

    AECL has been pioneering `up-front` licensing of new reactor designs. The CANDU 3 design has been formally reviewed by AECB staff for a number of years. The CANDU 9 design has just started the up-front licensing process. The process gives designers, regulators and potential customers early confidence in the licensability of future plants. (author). 4 refs., 2 tabs.

  11. Application of up-front licensing

    International Nuclear Information System (INIS)

    Grant, S.D.; Snell, V.G.

    1995-01-01

    AECL has been pioneering 'up-front' licensing of new reactor designs. The CANDU 3 design has been formally reviewed by AECB staff for a number of years. The CANDU 9 design has just started the up-front licensing process. The process gives designers, regulators and potential customers early confidence in the licensability of future plants. (author). 4 refs., 2 tabs

  12. Regulatory systems-based licensing guidance documentation

    International Nuclear Information System (INIS)

    Delligatti, M.S.

    1991-01-01

    The US Nuclear Regulatory Commission (NRC) has developed a series of licensing guidance documents based on the regulatory requirements in Part 60 of Title 10 of the Code of Federal Regulations (10 CFR Part 60). This regulatory systems-based approach to licensing guidance documentation relies on the definition of the high-level waste repository in 10 CFR Part 60. A document which is important for the frame-work it gives to other programmatic licensing guidance is the Draft Regulatory Guide open-quotes Format and Content for the License Application for the High-Level Waste Repositoryclose quotes (FCRG). The FCRG describes a format and content acceptable to NRC for a high-level waste repository license application pursuant to the requirements of 10 CFR Part 60. Other licensing guidance documents will be compatible with the FCRG

  13. 78 FR 70356 - Compliance With Order EA-13-109, Order Modifying Licenses With Regard to Reliable Hardened...

    Science.gov (United States)

    2013-11-25

    ... Licenses With Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident... Regard to Reliable Hardened Containment Vents Capable of Operation under Severe Accident Conditions... capable of a operation under severe accident conditions. This ISG also endorses, with clarifications, the...

  14. Regulatory licensing, status summary report; Systematic evaluation program

    International Nuclear Information System (INIS)

    1978-01-01

    This document is part of a management information system presenting a logical flow of events that represent the evaluation of 11 of the older operating nuclear reactors. Information collected will be used to determine the degree to which the 11 plants meet current licensing requirements and to develop an overall balanced position concerning any needed backfitting of the facilities and the documentation of the results of such evaluations

  15. Small modular reactors: current status, economic aspects and licensing

    International Nuclear Information System (INIS)

    Zimbron E, E.; Puente E, F.

    2014-10-01

    Interest for nuclear energy had resurgence since the beginning of the new century. This was a consequence of the new world conditions and needs: increasing energy demands (mainly from developing countries), awareness of the importance of energetic security and the necessity of limiting carbon emissions. In this nuclear boom, Small Modular Reactors (SMRs) develop and start to consolidate as a viable option for the present energy market. Their modular characteristics, lower initial capital cost, passive safety features and their niche applications, situate them as a technology with various advantages. The following study will present and analysis that will help to comprehend the SMRs present status. Information will show planned reactors, reactors in construction and in operation, advantages and challenges of their implementation, relevant economic aspects and important licensing factors that need to be highlighted. The analysis showed that the SMR technology is still in an initial stage that could reach and important development point in the next ten years. In this period, many of the reactors that are in design stage or that are through their licensing process might be constructed and could be getting ready for a commercial status. On the other hand, it has been observed that there are two main economic factors that need to be considered for any SMRs implementation project. First, the costs (initial, operation, maintenance, fuel and decommissioning) and second their possible niche market applications. Additionally, it has been noted that the licensing process is one of the greatest challenges for SMR general development. Licensing is mainly related to topic such as Emergency Planning Zone, first-of-a-kind engineering, passive safety features, proliferation resistance, multiple module designs and staffing. Previous information will serve as a base for carrying out a feasibility assessment analysis for SMR in Mexico. This part will be the last section of the project

  16. Small modular reactors: current status, economic aspects and licensing

    Energy Technology Data Exchange (ETDEWEB)

    Zimbron E, E. [Instituto Tecnologico de Estudios Superiores de Monterrey, Campus Santa Fe, Av. Carlos Lazo No. 100, Santa Fe, 01389 Mexico D. F. (Mexico); Puente E, F., E-mail: erick.zimbron@gmail.com [ININ, Direccion de Investigacion Cientifica, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2014-10-15

    Interest for nuclear energy had resurgence since the beginning of the new century. This was a consequence of the new world conditions and needs: increasing energy demands (mainly from developing countries), awareness of the importance of energetic security and the necessity of limiting carbon emissions. In this nuclear boom, Small Modular Reactors (SMRs) develop and start to consolidate as a viable option for the present energy market. Their modular characteristics, lower initial capital cost, passive safety features and their niche applications, situate them as a technology with various advantages. The following study will present and analysis that will help to comprehend the SMRs present status. Information will show planned reactors, reactors in construction and in operation, advantages and challenges of their implementation, relevant economic aspects and important licensing factors that need to be highlighted. The analysis showed that the SMR technology is still in an initial stage that could reach and important development point in the next ten years. In this period, many of the reactors that are in design stage or that are through their licensing process might be constructed and could be getting ready for a commercial status. On the other hand, it has been observed that there are two main economic factors that need to be considered for any SMRs implementation project. First, the costs (initial, operation, maintenance, fuel and decommissioning) and second their possible niche market applications. Additionally, it has been noted that the licensing process is one of the greatest challenges for SMR general development. Licensing is mainly related to topic such as Emergency Planning Zone, first-of-a-kind engineering, passive safety features, proliferation resistance, multiple module designs and staffing. Previous information will serve as a base for carrying out a feasibility assessment analysis for SMR in Mexico. This part will be the last section of the project

  17. Environmental assessment proposed license renewal of Nuclear Metals, Inc. Concord, Massachusetts

    International Nuclear Information System (INIS)

    Miller, R.L.; Easterly, C.E.; Lombardi, C.E.; Treitler, I.E.; Winbow, R.T.; Zimmerman, G.P.

    1997-02-01

    The US Nuclear Regulatory Commission (NRC) has prepared this Environmental Assessment (EA) to evaluate environmental issues associated with the renewal of licenses issued by NRC for facilities operated by Nuclear Metals, Inc. (NMI) in Concord, Massachusetts. By renewing the licenses, NRC proposes to allow the continuation of ongoing operations involving radioactive materials at NMI's facilities. This EA focuses on the potential impacts related to air emissions at NMI during normal (incident-free) operations and accidental releases. Findings indicate that there are only two areas of potential concern. First, modeling results for sulfur dioxide (SO 2 ) emissions from the boilers during normal operations indicate that the potential exists for exceeding the short-term National Ambient Air Quality Standards (NAAQS). NMI is prepared to undertake mitigative action to prevent potential exceedances of the short-term SO 2 NAAQS, and the Massachusetts Department of Environmental Protection is prepared to resolve the issue via a permit/approval change or through a Consent Order. Second, in the unlikely event of a severe fire, predicted sulfuric acid (H 2 SO 4 ) concentrations based on conservative (upper bound) modeling exceed the Emergency Response Planning Guideline (ERPG) levels. NMI has committed to NRC to give a briefing for local emergency response officials regarding the potential for an accidental H 2 SO 4 release

  18. 77 FR 66486 - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving...

    Science.gov (United States)

    2012-11-05

    ... available; and (iii) the filing has been submitted in a timely fashion based on the availability of the....12 to >= 1.17. The change is required to support the LSCS, Unit 2, Cycle 15, operation. Cycle 15 will be the first cycle of operation with a mixed core containing the following fuel types: Global Nuclear...

  19. Current status of LTO licensing programme for Bohunice nuclear power plant

    International Nuclear Information System (INIS)

    Borak, J.; Kupca, L.

    2012-01-01

    The objective of long term operation (LTO) licensing programme for Bohunice nuclear power plant is to demonstrate that the relevant structures and components shall perform their functions throughout the entire LTO period during which they shall meet all the relevant safety requirements. All the activities-which should result in utility's request to obtain the licence for LTO-must be performed in line with the relevant legal basis. As of May 2012, the anticipated duration of currently running programme is thirteen months. All relevant documentation, required by the established legal basis, shall be submitted to the licensing authority one year before the Unit 3 design life expiry. (author)

  20. Data bank usage in reload design and licensing

    International Nuclear Information System (INIS)

    Goudey, J.L.; Hansen, E.C.; Scigliano, S.M.; Williams, R.D.

    1986-01-01

    In 1977 the Nuclear Energy Business Operations of General Electric Company (GE) began a major project to automate sequential execution of the data transfer between the various computer programs used in performing calculations to support design, release, licensing, and core management of fuel used in boiling water reactors (BWRs). A centralized and controlled data bank was designed and implemented to complement the data management system and to achieve the following objectives: (1) enhance the quality and reliability of engineering data used for design and licensing of BWR fuel; (2) provide for traceability and long-term retrievability of engineering data as required by 10CFR50, Appendix B; (3) standardize the location and minimize the redundancy of engineering data; and (4) make engineering data readily available to all individuals and computer programs with a need for it. The structure of this data bank, which has become known as the BWR Engineering Data Bank or BWR/EDB, was purposefully left flexible and expandable with the ability to accommodate numerical, logical, and textual data. The BWR/EDB has been used by GE during fuel release, fuel and core design, reload licensing, and core management activities for 30 to 40 commercial power reactors over the past several years

  1. 78 FR 37325 - License Renewal of Nuclear Power Plants; Generic Environmental Impact Statement and Standard...

    Science.gov (United States)

    2013-06-20

    ... Nuclear Power Plants; Generic Environmental Impact Statement and Standard Review Plans for Environmental... for Nuclear Power Plants, Supplement 1: Operating License Renewal'' (ESRP). The ESRP serves as a guide... published a final rule, ``Revisions to Environmental Review for Renewal of Nuclear Power Plant Operating...

  2. Algeria schedules onshore licensing round

    International Nuclear Information System (INIS)

    Anon.

    1992-01-01

    This paper reports that Algeria's Sonatrach will conduct its first international onshore exploration licensing round in a move designed to triple drilling activity in the country. A second round will follow next April. Sonatrach plans to drill 200 wells during 1991-95, which will require the current level of 37/year to be almost trebled toward the end of the period. To this end foreign operators are being courted in an open exploration bidding round. Deadline for bid submittal in Nov. 30. Companies may enter singly or in groups to form partnerships with Sonatrach. Foreign licensees will be able to take a maximum 49% of production under Algerian law

  3. Specification of requirements to get a license for an Independent Spent Fuel Dry Storage Installation (ISFSI) at the site of the NPP-LV

    International Nuclear Information System (INIS)

    Serrano R, M. L.

    2015-09-01

    This article describes some of the work done in the Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS) to define specifically the requirements that the Federal Electricity Commission (CFE) shall meet to submit for consideration of CNSNS an operation request of an Independent Spent Fuel Dry Storage Installation (ISFSI). The project of a facility of this type arose from the need to provide storage capacity for spent nuclear fuel in the nuclear power plant of Laguna Verde (NPP-LV) and to continue the operation at the same facility in a safe manner. The licensing of these facilities in the United States of America has two modes: specific license or general license. The characteristics of these licenses are described in this article. However, in Mexico the existing national legislation is not designed for such license types, in fact there is a lack of standards or regulations in this regard. The regulatory law of Article 27 of the Constitution in the nuclear matter, only generally establishes that this type of facility requires an authorization from the Ministry of Energy. For this reason and because there is not a national legislation, was necessary to use the legislation that provides the Nuclear Regulatory Commission of USA, the US NRC. However, it cannot be applied as is established, so was necessary that the CNSNS analyze one by one the requirements of both types of license and determine what would be required to NPP-LV to submit its operating license of ISFSI. The American regulatory applicable to an ISFSI, the 10-Cfr-72 of the US NRC, establishes the requirements for both types of licenses. Chapter 10-Cfr was analyzed in all its clauses and coupled to the laws, regulations and standards as well as to the requirements established by CNSNS, all associated with a store spent fuel on site; the respective certification of containers for spent fuel dry storage was not included in this article, even though the CNSNS also performed that activity under the

  4. Licensed reactor nuclear safety criteria applicable to DOE reactors

    International Nuclear Information System (INIS)

    1991-04-01

    The Department of Energy (DOE) Order DOE 5480.6, Safety of Department of Energy-Owned Nuclear Reactors, establishes reactor safety requirements to assure that reactors are sited, designed, constructed, modified, operated, maintained, and decommissioned in a manner that adequately protects health and safety and is in accordance with uniform standards, guides, and codes which are consistent with those applied to comparable licensed reactors. This document identifies nuclear safety criteria applied to NRC [Nuclear Regulatory Commission] licensed reactors. The titles of the chapters and sections of USNRC Regulatory Guide 1.70, Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants, Rev. 3, are used as the format for compiling the NRC criteria applied to the various areas of nuclear safety addressed in a safety analysis report for a nuclear reactor. In each section the criteria are compiled in four groups: (1) Code of Federal Regulations, (2) US NRC Regulatory Guides, SRP Branch Technical Positions and Appendices, (3) Codes and Standards, and (4) Supplemental Information. The degree of application of these criteria to a DOE-owned reactor, consistent with their application to comparable licensed reactors, must be determined by the DOE and DOE contractor

  5. Free Software Licenses and Other Free Licenses: Genetic Code of Digital Common Goods

    OpenAIRE

    Marco Ciurcina

    2017-01-01

    This article explores the history and describes the main features of free software licenses and other free licenses in an attempt to shed light on the reasons for their success in promoting individual behaviors converging towards the collective construction of digital commons.

  6. Managing Licensing in a Market for Technology

    DEFF Research Database (Denmark)

    Arora, Ashish; Fosfuri, Andrea; Rønde, Thomas

    2013-01-01

    , we find that interdependency across business units may result in more, not less, decentralization. Furthermore, even though centralization results in less information, centralized licensing deals are larger. Our model conforms to the existing evidence that reports heterogeneity across firms in both......Technology licensing is an important means for companies to extract more value from their intellectual assets. We build a model that helps understand how licensing activity should be organized within large corporations. More specifically, we compare decentralization—where the business unit using...... the technology makes licensing decisions—to centralized licensing. The business unit has superior information about licensing opportunities but may not have the appropriate incentives because its rewards depend on product market performance. If licensing is decentralized, the business unit forgoes valuable...

  7. Strategic Basis for License Application Planning for a Potential Yucca Mountain Repository

    International Nuclear Information System (INIS)

    Newberry, C. M.; Brocoum, S. J.; Gamble, R. P.; Murray, R. C.; Cline, M.

    2002-01-01

    If Yucca Mountain, Nevada is designated as the site for development of a geologic repository for disposal of spent nuclear fuel and high-level radioactive waste, the Department of Energy (DOE) must obtain Nuclear Regulatory Commission (NRC) approval first for repository construction, then for an operating license, and, eventually, for repository closure and decommissioning. The licensing criteria defined in Code of Federal Regulations, Title 10, Part 63 (10 CFR Part 63) establish the basis for these NRC decisions. Submittal of a license application (LA) to the NRC for authorization to construct a repository at the Yucca Mountain site is, at this point, only a potential future action by the DOE. The policy process defined in the Nuclear Waste Policy Act (NWPA), as amended, for recommendation and designation of Yucca Mountain as a repository site makes it difficult to predict whether or when the site might be designated. The DOE may only submit a LA to the NRC if the site designation takes effect. In spite of this uncertainty, the DOE must take prudent and appropriate action now, and over the next several years, to prepare for development and timely submittal of a LA. This is particularly true given the need for the DOE to develop, load, and certify the operation of its electronic information system to provide access to its relevant records as part of the licensing support network (LSN) in compliance with NRC requirements six months prior to LA submittal. The DOE must also develop a LA, which is a substantially different document from those developed to support a Site Recommendation (SR) decision. The LA must satisfy NRC licensing criteria and content requirements, and address the acceptance criteria defined by the NRC in its forthcoming Yucca Mountain Review Plan (YMRP). The content of the LA must be adequate to facilitate NRC acceptance and docketing for review, and the LA and its supporting documents must provide the documented basis for the NR C findings required

  8. Decommissioning Licensing Process of Nuclear Installations in Spain

    International Nuclear Information System (INIS)

    Correa Sainz, Cristina

    2016-01-01

    The Enresa experience related to the decommissioning of nuclear facilities includes the decommissioning of the Vandellos I and Jose Cabrera NPPs. The Vandellos I gas-graphite reactor was decommissioned in about five years (from 1998 to 2003) to what is known as level 2. In February 2010, the decommissioning of Jose Cabrera power plant has been initiated and it is scheduled to be finished by 2018. The decommissioning of a nuclear power plant is a complex administrative process, the procedure for changing from operation to decommissioning is established in the Spanish law. This paper summarizes the legal framework defining the strategies, the main activities and the basic roles of the various agents involved in the decommissioning of nuclear facilities in Spain. It also describes briefly the Licensing documents required to obtain the decommissioning authorization and the Enresa point of view, as licensee, on the licensing decommissioning process. (author)

  9. M5TM alloy high burnup behavior and worldwide licensing

    International Nuclear Information System (INIS)

    Mardon, J.P.; Hoffmann, P.B.; Garner, G.L.

    2005-01-01

    The in-reactor behavior of advanced PWR Zirconium alloys at burnups equal to or below licensing limits has been widely reported. Specifically, the advanced alloy M5 has demonstrated impressive improvements over Zircaloy-4 for fuel rod cladding and fuel assembly structural components. To demonstrate superiority of the alloy at burnups beyond current licensing limits, M5 has been operated in PWR at burnups exceeding 71 GWd/tU in the United States and 78 GWd/tU in Europe. Two extensive irradiation programs have been performed in the United States to demonstrate alloy M5 performance beyond current licensing limits. Four M5 TM fuel rods were exposed to four 24-month cycles in a 15x15 reactor beginning in 1995. Additionally, one 17x17 lead assembly containing M5 fuel rods and guide tubes was operated for four 18-month cycles beginning from 1997. Post-irradiation examinations (PIE) performed after all four cycles in the 15x15 demonstration program revealed excellent performance in the licensed burnup and in the high burnup stages of the experience. Examination of the 4th cycle 17x17 assembly will be accomplished in two stages the first of which is scheduled for June 2005. Moreover, several irradiation campaigns have been performed in Europe in order to confirm the excellent M5 in-pile behavior in demanding PWRs irradiation conditions with regard to void fraction, heat flux, lithium content and temperature. Results from the high burnup fuel examinations verify that the excellent performance achieved up to 62 GWd/tU was continued into higher burnup. The results of high burnup PIE campaigns for European and American PWR's are presented in this paper. Measured performance indicators include fuel assembly dimensional stability parameters (assembly length, fuel rod length, assembly bow, fuel rod bow, fuel rod radial creep and spacer grid width), oxidation measurements (fuel rod and guide tube) and hydrogen pick-up data (fuel rod). In the framework of PCI studies, power ramp

  10. Decree No. 83/7405 of 18 November 1983 on the licensing procedure for nuclear installations

    International Nuclear Information System (INIS)

    1983-01-01

    This Decree (No. 83/7405) on the licensing procedure for nuclear installations came into force on 19 December 1983 and supersedes Decree No. 7/9141 of 5 December 1974 on the same subject. The general lines of the licensing procedure laid down by this new Decree are similar to that provided by the 1979 Decree; it is also carried out in three stages: site, construction and operating licences are delivered in succession. (NEA) [fr

  11. ACR: Licensing and design readiness

    International Nuclear Information System (INIS)

    Alizadeh, A.

    2009-01-01

    Full text The Canadian nuclear technology has a long history dating back to the 1940s. In this regard, Canada is in a unique situation, shared only by a very few countries, where original nuclear power technology has been invented and further developed. Canadian Nuclear Safety Commission (CNSC), then called AECB, was established in 1946. CNSC focuses on nuclear security, nuclear safety, establishing health and safety regulations, and has also played an instrumental role in the formation of the IAEA. CNSC has provided assistance to the establishment of regulatory authorities in AECL's client countries such as Korea, Argentina, China and Romania. AECL has developed the Gen III+ ACR 1000 as evolutionary advancement of the current CANDU 6 reactor. ACR-1000 has evolved from AECL's in depth experience with CANDU systems, components, and materials, as well as the feedback received from owners and operators of CANDU plants. The ACR-1000 design retains the proven strengths and features of CANDU reactors, while incorporating innovations and state-of-the-art technology. It also features major improvements in economics, inherent safety characteristics, and performance. ACR-1000 has completed its Basic Engineering, has advanced in the licensing process in Canada, and is ready for deployment in Canadian and world markets. EC6 is an evolution of CANDU 6 and is a Gen III natural uranium fuelled reactor. Its medium size and potential for fuel localization and advanced fuel cycles is an optimal strategic solution in many markets.AECL's reactor products are shown to be compliant with a variety of licensing and regulatory requirements. These include the new CNSC DRD-337, IAEA NS-R1, and EUR. This allows the countries interested in CANDU reactor products to be confident of its licensing in their own regulatory regimes.

  12. A review of healthy condition for reactor operators of NPP

    International Nuclear Information System (INIS)

    Zhang Chi; Yang Di; Zhu Lixin; Zhou Limin

    2008-01-01

    Physical health is one of fundamental elements and the necessary qualification for holding operator license or senior operator license of a nuclear power plant issued by NNSA. Based upon requirements for healthy qualification of reactor operators in nuclear safety regulations and some new issued regulations, especially some involved national standard (GB), review direction, relevant contents and criteria were described, and some suggestions were provided in this paper. (authors)

  13. 7 CFR 6.28 - Transfer of license.

    Science.gov (United States)

    2010-01-01

    ... Licensing Authority will transfer to such other person the historical, nonhistorical or designated license... escrow with the sole condition for return of escrow being that the Licensing Authority determines that... to whom the historical licenses were issued during the quota year in which the sale or conveyance...

  14. Free Software Licenses and Other Free Licenses: Genetic Code of Digital Common Goods

    Directory of Open Access Journals (Sweden)

    Marco Ciurcina

    2017-06-01

    Full Text Available This article explores the history and describes the main features of free software licenses and other free licenses in an attempt to shed light on the reasons for their success in promoting individual behaviors converging towards the collective construction of digital commons.

  15. Conformation of an evaluation process for a license renovation solicitude of a nuclear power plant in Mexico. Part 2

    International Nuclear Information System (INIS)

    Serrano R, M. de L.

    2013-10-01

    At the present time the operation licenses in force for the reactors of the Nuclear Power Plant of Laguna Verde (NPP-L V) will expire in the year 2020 and 2025 for the Unit-1 and Unit-2, respectively, for which the Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS) has begun its preparation to assist a solicitude of the licensee to continue the operation of the NPP-L V. The present work has the purpose of defining the steps to continue and to generate the documents that would help in this process, as the normative, guides, procedures, regulations, controls, etc. so that the evaluation process will be effective and efficient, as much for the regulator organ as for the licensee. The advance carried out in the continuation of the conformation of an evaluation process of license renovation solicitude is also exposed, taking like base the requirements established by the CNSNS, the regulator organ of the United States (US NRC), and the IAEA for license renovation solicitude of this type. A summary of the licenses granted from the beginning of commercial operation of the NPP-L V is included, both units and the amendments to these licenses, explaining the reason of the amendment shortly and in the dates they were granted. A brief exposition of the nuclear power plants to world level that have received extension of its operation is included. The normative that can be applied in a life extension evaluation is presented, the evaluation process to continue with the guides of the US NRC, the reach of the evaluation and the minimum information required to the licensee that should accompany to their solicitude. (author)

  16. 78 FR 57418 - Compliance With Order EA-13-109, Order Modifying Licenses With Regard to Reliable Hardened...

    Science.gov (United States)

    2013-09-18

    ... Licenses With Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident... Capable of Operation under Severe Accident Conditions.'' (ADAMS Accession No. ML13247A417) This draft JLD... Containment Vents Capable of Operation under Severe Accident Conditions'' (ADAMS Accession No. ML13130A067...

  17. Licensing Teachers: Lessons from Other Professions.

    Science.gov (United States)

    Haberman, Martin

    1986-01-01

    The licensing of teachers should be modeled against professions similar to teaching rather than professions like medicine and architecture that are vastly different. Applying similar licensing practices can raise the status of teaching. Ignoring these licensing practices will prevent teachers from functioning as professionals. (MD)

  18. TVA experience in BWR reload design and licensing

    International Nuclear Information System (INIS)

    Robertson, J.D.

    1986-01-01

    TVA has developed and implemented the capability to perform BWR reload core design and licensing analyses. The advantages accruing from this capability include the tangible cost-savings from performing reload analyses in-house. Also, ''intangible'' benefits such as increased operating flexibility and the ability to accommodate multivendor fuel designs have been demonstrated. The major disadvantage with performing in-house analyses is the cost associated with development and maintenance of the analytical methods and staff expertise

  19. Business planning for license renewal and plant acquisitions. Panel Discussion

    International Nuclear Information System (INIS)

    Quinn, Edward L.; Grimes, Chris; Walters, Doug; Doroshuk, Barth; Gasper, Joe; Salmon, Harry; Bier, Vicki M.; Hagen, Ronald; Richardson, Charles J.

    2001-01-01

    Full text of publication follows: Subsequent to Calvert Cliffs and Oconee license renewals in 2000, many plants have not applied for license renewal. Industry is moving to standardize and streamline the process to make it as efficient and effective as possible. At the same time, it is focusing on business practices and competitiveness of nuclear plants in the long-term market-both under regulated and deregulated state formats. In addition, new acquisitions and consolidation in the nuclear market have created several large owner-operators that have specialized business needs. Speakers with experience in the foregoing facets have been selected from the U.S. Nuclear Regulatory Commission, the Nuclear Energy Institute, and utilities to address the business challenges facing them now and in the future. (authors)

  20. The licensing processes influence on nuclear market

    International Nuclear Information System (INIS)

    Locatelli, Giorgio; Mancini, Mauro; Sainati, Tristano; Sallinen, Liisa

    2011-01-01

    The paper deals with the licensing nuclear power plants; it focuses primarily on the licensing process implications into the international nuclear market. Nowadays there are twenty-six countries that are planning to build new nuclear facilities, and thirty-seven where nuclear reactors are proposed; on the other hand, there are mainly ten international reactor vendors. At international level, there are few vendors that have sufficient resources, capabilities and experience to carry out the design and delivering of a nuclear power plant in the international market; On the other hand, the licensing processes are strictly dependent on national law frameworks, and on the nuclear policies. The paper proposes a comparison of six licensing processes (the ones established in Finland, France, Italy, South Korea, USA and UK), and analyzes its main features and implications; the IAEA licensing process is taken as reference point. The objective of the paper is to propose a systemic approach for considering the licensing procedures. The framework proposed enables facilitating the licensing management and inferring the main features of licensing contexts. The paper concludes with a forecast of the nuclear licensing context, especially with respect to the fourth generation of nuclear reactors. (author)

  1. Whom to Choose as License Partner?

    DEFF Research Database (Denmark)

    Laursen, Keld; Reichstein, Toke; Trombini, Giulia

    2013-01-01

    between technology and market forces: if partners are market distant, the likelihood of technology license contractual partnership decreases with partners’ technological distance. Using data on the formation of license partnerships in the global biopharmaceutical industry over the period 1994......This paper investigates the matching of firms on the market for technology. The paper forwards two dimensions along which license formation occurs: technology and product-market. Both sides of the market search for a partner representing potential for high technology synergies to maximize licensing...

  2. Exporting the Canadian licensing program

    International Nuclear Information System (INIS)

    Whelan, D.J.

    1981-06-01

    This paper deals with the problems of an overseas regulatory agency in licensing a Canadian-supplied nuclear plant which is referenced to a plant in Canada. Firstly, the general problems associated with the use of a reference plant are discussed. This is followed by a discussion of specific problems which arise from the licensing practices in Canada. The paper concludes with recommendations to simplify the task of demonstrating the licensability of an overseas CANDU plant

  3. 7 CFR 6.32 - Globalization of licenses.

    Science.gov (United States)

    2010-01-01

    ... 7 Agriculture 1 2010-01-01 2010-01-01 false Globalization of licenses. 6.32 Section 6.32 Agriculture Office of the Secretary of Agriculture IMPORT QUOTAS AND FEES Dairy Tariff-Rate Import Quota Licensing § 6.32 Globalization of licenses. If the Licensing Authority determines that entries of an article...

  4. 42 CFR 431.710 - Provisional licenses.

    Science.gov (United States)

    2010-10-01

    ... Licensing Nursing Home Administrators § 431.710 Provisional licenses. To fill a position of nursing home... 42 Public Health 4 2010-10-01 2010-10-01 false Provisional licenses. 431.710 Section 431.710 Public Health CENTERS FOR MEDICARE & MEDICAID SERVICES, DEPARTMENT OF HEALTH AND HUMAN SERVICES...

  5. Product Licenses Database Application

    CERN Document Server

    Tonkovikj, Petar

    2016-01-01

    The goal of this project is to organize and centralize the data about software tools available to CERN employees, as well as provide a system that would simplify the license management process by providing information about the available licenses and their expiry dates. The project development process is consisted of two steps: modeling the products (software tools), product licenses, legal agreements and other data related to these entities in a relational database and developing the front-end user interface so that the user can interact with the database. The result is an ASP.NET MVC web application with interactive views for displaying and managing the data in the underlying database.

  6. Health requirements for nuclear reactor operators

    International Nuclear Information System (INIS)

    1980-05-01

    The health prerequisites established for the qualification of nuclear reactor operators according to CNEN-NE-1.01 Guidelines Licensing of nuclear reactor operators, CNEN-12/79 Resolution, are described. (M.A.) [pt

  7. Licensing plan for UMTRA project disposal sites

    International Nuclear Information System (INIS)

    1993-09-01

    The Uranium Mill Tailings Remedial Action (UMTRA) Project Office developed a plan to define UMTRA Project licensing program objectives and establish a process enabling the DOE to document completion of remedial actions in compliance with 40 CFR 1 92 and the requirements of the NRC general license. This document supersedes the January 1987 Project Licensing Plan (DOE, 1987). The plan summarizes the legislative and regulatory basis for licensing, identifies participating agencies and their roles and responsibilities, defines key activities and milestones in the licensing process, and details the coordination of these activities. This plan provides an overview of the UMTRA Project from the end of remedial actions through the NRC's acceptance of a disposal site under the general license. The licensing process integrates large phases of the UMTRA Project. Other programmatic UMTRA Project documents listed in Section 6.0 provide supporting information

  8. Development model to public hearing for environmental licensing of nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Vasques, Luciana Gomes; Aquino, Afonso Rodrigues de, E-mail: lu_vasques@usp.br, E-mail: araquino@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2015-07-01

    The use of nuclear technology has always been a matter of concern from an environmental point of view. Although disputed, the generation of electricity in nuclear reactors was considered a source of clean emission in relation to emission of gases responsible for the greenhouse effect. In Brazil, nuclear activities are regulated and supervised by the Brazilian Commission of Nuclear Energy - CNEN. Environmental issues associated with nuclear activities are described by CONAMA, and the developments in this area are licensed by IBAMA, regardless of obtaining nuclear licenses issued by CNEN. Obtaining environmental licenses (prior, installation and operation) depends initially on preparing the Environmental Impact Study - EIS and the Environmental Impact Report - EIR, consisting of a presentation of EIS in language accessible to all. EIR is forwarded to bodies and entities with some connection to the enterprise, to be manifested with IBAMA about the relevance of its content. This information serves as a resource for Public Hearings, which are meetings organized by entrepreneurs, conducted by IBAMA, and rely on public participation, can be considered as a licensing step. Public Hearings are subject to subjectivity, and the model proposed in this research becomes more objective ill-defined, difficult to understand actions for the entrepreneur. (author)

  9. Development model to public hearing for environmental licensing of nuclear facilities

    International Nuclear Information System (INIS)

    Vasques, Luciana Gomes; Aquino, Afonso Rodrigues de

    2015-01-01

    The use of nuclear technology has always been a matter of concern from an environmental point of view. Although disputed, the generation of electricity in nuclear reactors was considered a source of clean emission in relation to emission of gases responsible for the greenhouse effect. In Brazil, nuclear activities are regulated and supervised by the Brazilian Commission of Nuclear Energy - CNEN. Environmental issues associated with nuclear activities are described by CONAMA, and the developments in this area are licensed by IBAMA, regardless of obtaining nuclear licenses issued by CNEN. Obtaining environmental licenses (prior, installation and operation) depends initially on preparing the Environmental Impact Study - EIS and the Environmental Impact Report - EIR, consisting of a presentation of EIS in language accessible to all. EIR is forwarded to bodies and entities with some connection to the enterprise, to be manifested with IBAMA about the relevance of its content. This information serves as a resource for Public Hearings, which are meetings organized by entrepreneurs, conducted by IBAMA, and rely on public participation, can be considered as a licensing step. Public Hearings are subject to subjectivity, and the model proposed in this research becomes more objective ill-defined, difficult to understand actions for the entrepreneur. (author)

  10. Nuclear facilities licensing

    International Nuclear Information System (INIS)

    Carvalho, A.J.M. de.

    1978-01-01

    The need for the adoption of a legal and normative system, defining objectives, pescriptions and the process of nuclear licensing and building of nuclear power plants in Brazil is enphasized. General rules for the development of this system are presented. The Brazilian rules on the matter are discussed. A general view of the German legal system for nuclear power plant licensing and the IAEA recommendations on the subject are finally presented. (A.L.S.L.) [pt

  11. To License or Not to License: An Examination of State Statutes Regarding Private Investigators and Digital Examiners

    Directory of Open Access Journals (Sweden)

    Thomas Lonardo

    2008-09-01

    Full Text Available In this paper the authors examine statutes that regulate, license, and enforce investigative functions in each US state. After identification and review of Private Investigator licensing requirements, the authors find that very few state statutes explicitly differentiate between Private Investigators and Digital Examiners. After contacting all state agencies the authors present a distinct grouping organizing state approaches to professional Digital Examiner licensing. The authors conclude that states must differentiate between Private Investigator and Digital Examiner licensing requirements and oversight.

  12. Impact of New Radiation Safety Standards on Licensing Requirements of Nuclear Power Plant

    International Nuclear Information System (INIS)

    Strohal, P.; Subasic, D.; Valcic, I.

    1996-01-01

    As the outcomes of the newly introduced safety philosophies, new and more strict safety design requirements for nuclear installation are expected to be introduced. New in-depth defence measures should be incorporated into the design and operation procedure for a nuclear installation, to compensate for potential failures in protection or safety measures. The new requirements will also apply to licensing of NPP's operation as well as to licensing of nuclear sites, especially for radioactive waste disposal sites. This paper intends to give an overview of possible impacts of new internationally agreed basic safety standards with respect to NPP and related technologies. Recently issued new basic safety standards for radiation protection are introducing some new safety principles which may have essential impact on future licensing requirements regarding nuclear power plants and radioactive waste installations. These new standards recognize exposures under normal conditions ('practices') and intervention conditions. The term interventions describes the human activities that seek to reduce the existing radiation exposure or existing likelihood of incurring exposure which is not part of a controlled practice. The other new development in safety standards is the introduction of so called potential exposure based on the experience gained from a number of radiation accidents. This exposure is not expected to be delivered with certainty but it may result from an accident at a source or owing to an event or sequence of events of a probabilistic nature, including equipment failures and operating errors. (author)

  13. Analysis of replies to an IAEA questionnaire on procedures for accreditation of training programmes and for authorization and licensing of nuclear power plant operations personnel

    International Nuclear Information System (INIS)

    1991-06-01

    The intent of this survey was to gather data and present results to facilitate the international exchange of information and experience in this field. This was accomplished using a questionnaire developed by the IAEA that was sent in September, 1989 to the thirty-one Member States having nuclear power plants operating or under construction. Of these, twenty-one responses were received. The questionnaire was constructed in two parts: (1) Accreditation of Training Programmes; and (2) Authorization and (Formal) Licensing of Operations Personnel. The analysis was conducted by IAEA staff with the assistance of consultants and resulted in an identification of the commonalities and differences in approach on these issues. An advisory group subsequently considered this analysis, interpreted the results relative to the original responses, and reached conclusions that are contained in this document

  14. Criteria of classification applied to licensing of particle accelerators

    International Nuclear Information System (INIS)

    Costa, Evaldo L.C.; Melo, Paulo F.F.

    2013-01-01

    This work aims to bring to discussion the proposal of a new classification model toward to generating ionizing radiation, specifically particle accelerators, considering two parameters: the size of these facilities and the level of energy they operate, emphasizing large accelerators, which typically operate at higher levels of energy. Also motivated by the fact that the Brazilian rules do not provide an adequate standard of licensing for this size of installation, this work will seek to revise the existing classification, where generators of ionizing radiation (including particle accelerators) are considered up to the level of energy of 50 MeV

  15. Cleansing and dismantling of CEA-Saclay nuclear licensed facilities

    International Nuclear Information System (INIS)

    Jeanjacques, Michel; Delaire, Isabelle; Glevarec, Rebecca; Mandard, Lionel; Martin, Jean-Louis; Serrano, Roger

    2013-01-01

    This summary presents the cleansing and dismantling operations currently realized on the CEA center of Saclay (CEA-Saclay). It was initiated at the beginning of the 2000 years a cleansing and dismantling program of the old Nuclear Licensed Facilities (NLF). Currently this program relates the dismantling operations to the Hot Laboratories (Laboratoires de Haute Activite: LHA) and the old workshops of the Liquid Waste Treatment Plant (Station des Effluents Liquides: STEL), the dismantling preparation of Ulysse reactor and the dismantling studies to the Solid Waste Management Plant (SWMP; Zone de Gestion des Dechets Solides) and the Osiris reactor. (authors)

  16. 77 FR 71404 - Notice of Intent to License Government-Owned Inventions; Intent to License on a Partially...

    Science.gov (United States)

    2012-11-30

    ... DEPARTMENT OF DEFENSE Department of the Army Notice of Intent to License Government-Owned Inventions; Intent to License on a Partially-Exclusive Basis AGENCY: Department of the Army, DoD. ACTION... by the Secretary of the Army. The US Army Edgewood Chemical Biological Center intends to license...

  17. Review process for license renewal applications

    International Nuclear Information System (INIS)

    Craig, John W.; Kuo, P.T.

    1991-01-01

    In preparation for license renewal reviews, the Nuclear Regulatory Commission has recently published for public review and comment a proposed rule for license renewal and a draft Standard Review Plan as well as a draft Regulatory Guide relating to the implementation of the proposed rule. In support of future license renewal applications, the nuclear industry has also submitted 11 industry reports for NRC review and approval. This paper briefly describe how these parallel regulatory and industry activities will be factored into the NRC review process for license renewal. (author)

  18. 78 FR 31978 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses...

    Science.gov (United States)

    2013-05-28

    ... (iii) the filing has been submitted in a timely fashion based on the availability of the subsequent...-up during the current operating cycle. Basis for proposed no significant hazards consideration... most reactive state throughout the operating cycle. Basis for proposed no significant hazards...

  19. MARSSIM guidelines for non-impacted area identification in support of partial site release prior to license termination

    International Nuclear Information System (INIS)

    Parish, D.

    1999-01-01

    Regulations are in place which allow plants undergoing decommissioning to remove obsolete requirements from their licenses. Large buffer areas to the site boundary, needed for emergency planning purposes during power operation, are not required for permanently defueled facilities. It is important that non-impacted areas be removed from license restrictions as soon as possible post shutdown to allow rapid asset recovery and return the large environmental resources these areas represent to beneficial use. License termination surveys are not required for non-impacted areas in accordance with the guidance of US Nuclear Regulatory Commission (NRC) NUREG-1575 (MARSSIM), and NRC Draft Regulatory Guide DG-4006. Thus, such areas do not fall under the license termination requirements of 10CFR50.82 (US Code of Federal Regulations). This report describes methods of classifying areas as non-impacted in accordance with MARRSIM and other NRC guidance, and the licensing options for release of non-impacted areas prior to license termination. The status of Big Rock Point's efforts toward early release of non-impacted areas also is provided. (author)

  20. General aspects of radiological protection to consider for the licensing a hospital cyclotron

    International Nuclear Information System (INIS)

    Andrada Contardi, F.A.; Fruttero, N.H.; Bozzo, R.H.; Moschella, E.G.

    2010-01-01

    The use of PET/PET-CT studies for a variety of diagnoses has increased significantly on a global scale. Modern medical cyclotrons must be placed in or near hospitals on account of the short radioactive half-life of the pharmaceuticals used in such studies. Many countries in Latin America are now licensing cyclotrons and laboratories for the production of radio-pharmaceuticals for the first time, and most are expected to have installations within the near future. This report outlines the general aspects of radiological protection important to consideration during the licensing of these facilities, and includes the following: general operation of the cyclotron and laboratory for the production of radiopharmaceuticals, safety systems (shielding, interlocks, ventilation, manual safety systems, alarms and monitors), and general aspects for licensing an installation (monitoring, accidental and incidental events, activation of components, etc.) and personnel. (authors) [es

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