WorldWideScience

Sample records for regulations licenses authorizations

  1. 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)

  2. 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)

  3. 31 CFR 543.502 - Effect of license or authorization.

    Science.gov (United States)

    2010-07-01

    ... 31 Money and Finance: Treasury 3 2010-07-01 2010-07-01 false Effect of license or authorization. 543.502 Section 543.502 Money and Finance: Treasury Regulations Relating to Money and Finance... principles of law. ...

  4. 31 CFR 575.501 - Effect of license or authorization.

    Science.gov (United States)

    2010-07-01

    ... 31 Money and Finance: Treasury 3 2010-07-01 2010-07-01 false Effect of license or authorization. 575.501 Section 575.501 Money and Finance: Treasury Regulations Relating to Money and Finance... principles of law. ...

  5. 31 CFR 546.502 - Effect of license or authorization.

    Science.gov (United States)

    2010-07-01

    ... 31 Money and Finance: Treasury 3 2010-07-01 2010-07-01 false Effect of license or authorization. 546.502 Section 546.502 Money and Finance: Treasury Regulations Relating to Money and Finance... principles of law. ...

  6. 31 CFR 538.501 - Effect of license or authorization.

    Science.gov (United States)

    2010-07-01

    ... 31 Money and Finance: Treasury 3 2010-07-01 2010-07-01 false Effect of license or authorization. 538.501 Section 538.501 Money and Finance: Treasury Regulations Relating to Money and Finance... principles of law. ...

  7. 31 CFR 537.502 - Effect of license or authorization.

    Science.gov (United States)

    2010-07-01

    ... 31 Money and Finance: Treasury 3 2010-07-01 2010-07-01 false Effect of license or authorization. 537.502 Section 537.502 Money and Finance: Treasury Regulations Relating to Money and Finance... principles of law. ...

  8. 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)

  9. Regulation of Federal radioactive waste activities. Report to Congress on extending the Nuclear Regulatory Commission's licensing or regulatory authority to Federal radioactive waste storage and disposal activities

    International Nuclear Information System (INIS)

    1979-09-01

    The report contains two recommendations for extending the Commission's regulatory authority: (1) NRC licensing authority should be extended to cover all new DOE facilities for disposal of transuranic (TRU) waste and nondefense low-level waste. (2) A pilot program, focused on a few specific DOE waste management activities, should be established to test the feasibility of extending NRC regulatory authority on a consultative basis to DOE waste management activities not now covered by NRC's licensing authority or its extension as recommended in Recommendation 1

  10. 31 CFR 540.501 - Effect of license or authorization.

    Science.gov (United States)

    2010-07-01

    ... 31 Money and Finance: Treasury 3 2010-07-01 2010-07-01 false Effect of license or authorization. 540.501 Section 540.501 Money and Finance: Treasury Regulations Relating to Money and Finance... otherwise exist under ordinary principles of law. ...

  11. 31 CFR 535.502 - Effect of license or authorization.

    Science.gov (United States)

    2010-07-01

    ... 31 Money and Finance: Treasury 3 2010-07-01 2010-07-01 false Effect of license or authorization. 535.502 Section 535.502 Money and Finance: Treasury Regulations Relating to Money and Finance... respect to, any property which would not otherwise exist under ordinary principles of law. [44 FR 66833...

  12. 31 CFR 593.502 - Effect of license or authorization.

    Science.gov (United States)

    2010-07-01

    ... 31 Money and Finance: Treasury 3 2010-07-01 2010-07-01 false Effect of license or authorization. 593.502 Section 593.502 Money and Finance: Treasury Regulations Relating to Money and Finance... otherwise exist under ordinary principles of law. ...

  13. 31 CFR 594.502 - Effect of license or authorization.

    Science.gov (United States)

    2010-07-01

    ... 31 Money and Finance: Treasury 3 2010-07-01 2010-07-01 false Effect of license or authorization. 594.502 Section 594.502 Money and Finance: Treasury Regulations Relating to Money and Finance... interest in, or with respect to, any property which would not otherwise exist under ordinary principles of...

  14. 31 CFR 588.502 - Effect of license or authorization.

    Science.gov (United States)

    2010-07-01

    ... 31 Money and Finance: Treasury 3 2010-07-01 2010-07-01 false Effect of license or authorization. 588.502 Section 588.502 Money and Finance: Treasury Regulations Relating to Money and Finance... interest in, or with respect to, any property which would not otherwise exist under ordinary principles of...

  15. 31 CFR 596.501 - Effect of license or authorization.

    Science.gov (United States)

    2010-07-01

    ... 31 Money and Finance: Treasury 3 2010-07-01 2010-07-01 false Effect of license or authorization. 596.501 Section 596.501 Money and Finance: Treasury Regulations Relating to Money and Finance... interest in, or with respect to, any property which would not otherwise exist under ordinary principles of...

  16. 31 CFR 585.501 - Effect of license or authorization.

    Science.gov (United States)

    2010-07-01

    ... 31 Money and Finance: Treasury 3 2010-07-01 2010-07-01 false Effect of license or authorization. 585.501 Section 585.501 Money and Finance: Treasury Regulations Relating to Money and Finance... not otherwise exist under ordinary principles of law. ...

  17. 31 CFR 560.501 - Effect of license or authorization.

    Science.gov (United States)

    2010-07-01

    ... 31 Money and Finance: Treasury 3 2010-07-01 2010-07-01 false Effect of license or authorization. 560.501 Section 560.501 Money and Finance: Treasury Regulations Relating to Money and Finance... respect to, any property which would not otherwise exist under ordinary principles of law. (d) Specific...

  18. 31 CFR 536.501 - Effect of license or authorization.

    Science.gov (United States)

    2010-07-01

    ... 31 Money and Finance: Treasury 3 2010-07-01 2010-07-01 false Effect of license or authorization. 536.501 Section 536.501 Money and Finance: Treasury Regulations Relating to Money and Finance... exist under ordinary principles of law. ...

  19. 31 CFR 542.502 - Effect of license or authorization.

    Science.gov (United States)

    2010-07-01

    ... 31 Money and Finance: Treasury 3 2010-07-01 2010-07-01 false Effect of license or authorization. 542.502 Section 542.502 Money and Finance: Treasury Regulations Relating to Money and Finance... interest in, or with respect to, any property which would not otherwise exist under ordinary principles of...

  20. 31 CFR 597.501 - Effect of license or authorization.

    Science.gov (United States)

    2010-07-01

    ... 31 Money and Finance: Treasury 3 2010-07-01 2010-07-01 false Effect of license or authorization. 597.501 Section 597.501 Money and Finance: Treasury Regulations Relating to Money and Finance... not otherwise exist under ordinary principles of law. ...

  1. 31 CFR 587.502 - Effect of license or authorization.

    Science.gov (United States)

    2010-07-01

    ... 31 Money and Finance: Treasury 3 2010-07-01 2010-07-01 false Effect of license or authorization. 587.502 Section 587.502 Money and Finance: Treasury Regulations Relating to Money and Finance... not otherwise exist under ordinary principles of law. ...

  2. 31 CFR 547.502 - Effect of license or authorization.

    Science.gov (United States)

    2010-07-01

    ... 31 Money and Finance: Treasury 3 2010-07-01 2010-07-01 false Effect of license or authorization. 547.502 Section 547.502 Money and Finance: Treasury Regulations Relating to Money and Finance... otherwise exist under ordinary principles of law. ...

  3. 31 CFR 545.501 - Effect of license or authorization.

    Science.gov (United States)

    2010-07-01

    ... 31 Money and Finance: Treasury 3 2010-07-01 2010-07-01 false Effect of license or authorization. 545.501 Section 545.501 Money and Finance: Treasury Regulations Relating to Money and Finance... interest in, or with respect to, any property which would not otherwise exist under ordinary principles of...

  4. 31 CFR 586.502 - Effect of license or authorization.

    Science.gov (United States)

    2010-07-01

    ... 31 Money and Finance: Treasury 3 2010-07-01 2010-07-01 false Effect of license or authorization. 586.502 Section 586.502 Money and Finance: Treasury Regulations Relating to Money and Finance... property which would not otherwise exist under ordinary principles of law. Note to paragraph (c) of § 586...

  5. 31 CFR 544.502 - Effect of license or authorization.

    Science.gov (United States)

    2010-07-01

    ... 31 Money and Finance: Treasury 3 2010-07-01 2010-07-01 false Effect of license or authorization. 544.502 Section 544.502 Money and Finance: Treasury Regulations Relating to Money and Finance... not otherwise exist under ordinary principles of law. ...

  6. 31 CFR 595.501 - Effect of license or authorization.

    Science.gov (United States)

    2010-07-01

    ... 31 Money and Finance: Treasury 3 2010-07-01 2010-07-01 false Effect of license or authorization. 595.501 Section 595.501 Money and Finance: Treasury Regulations Relating to Money and Finance... exist under ordinary principles of law. ...

  7. 31 CFR 548.502 - Effect of license or authorization.

    Science.gov (United States)

    2010-07-01

    ... 31 Money and Finance: Treasury 3 2010-07-01 2010-07-01 false Effect of license or authorization. 548.502 Section 548.502 Money and Finance: Treasury Regulations Relating to Money and Finance... property which would not otherwise exist under ordinary principles of law. ...

  8. 31 CFR 541.502 - Effect of license or authorization.

    Science.gov (United States)

    2010-07-01

    ... 31 Money and Finance: Treasury 3 2010-07-01 2010-07-01 false Effect of license or authorization. 541.502 Section 541.502 Money and Finance: Treasury Regulations Relating to Money and Finance... interest in, or with respect to, any property which would not otherwise exist under ordinary principles of...

  9. Regulator process for the authorization of an amendment to the operation license of a nuclear power plant in Mexico; Proceso regulador para la autorizacion de una enmienda a la licencia de operacion de una central nuclear en Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Perez, R.; Espinosa V, J.M.; Salgado, J.R.; Mamani, Y.R. [CNSNS, Dr. Barragan 779, Col. Narvarte, 03020 Mexico D.F. (Mexico)

    2005-07-01

    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)

  10. 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

  11. The licensing of nuclear plants as an example of conflicts of authority in parallel licensing procedures

    International Nuclear Information System (INIS)

    Henseler, P.

    1982-01-01

    Although the results obtained cannot be translated into installation licences related to the clean air act or to building codes without reservations, they can be generalized as follows: If several authorities have to assess one and the same project in independent procedures, they do not only have to use the metric used for subject-specific licensing prerequisites, but also the one used for the common weal. Then the spheres of responsibility require division. Oriented towards the purpose of the relevant laws, it has to be settled first for the sake of which public interest the authorities involved substantiate of a licensing reservation at all. All the decisions which fall within the sphere of responsibility of a certain authority are reserved and may not be prejudged by other authorities involved by issuing acts of regulation with externally binding effects. Insofar as similar or related public interests are to be considered in several licencing procedures (to be conducted) and insofar as there is no possibility of assigning the safeguarding of these interests to a special field of activity of one of the authorities involved, diverging results have to be accepted. (orig./HP) [de

  12. Meeting licensing restrictions from a regulator's perspective

    International Nuclear Information System (INIS)

    Autry, V.R.; Ragan, F.A.

    1990-01-01

    The State of South Carolina was delegated the authority by the US Nuclear Regulatory Commission to regulate the receipt, possession, use and disposal of radioactive material as an Agreement State. Since 1970, the state has been the principal regulatory authority for the Barnwell Low-Level Waste Disposal Facility operated by Chem-Nuclear Systems, Inc. The radioactive material license issued authorizing the receipt and disposal of low level waste has experienced many changes necessitated by technical advancements which led to stricter controls and restrictions for shallow land disposal. Low level waste has evolved from simple contaminated items with minimal radioactivity, to complex waste streams requiring elaborate processing and containment of high quantities of radionuclides. Waste streams also require extensive analysis and qualification to meet many of the restrictions imposed at the burial facility and comply with national standards and regulations for classification. This paper presents a chronological history of many of these restrictions, the rationale for them, and the waste generators' abilities and inabilities to comply. In addition, case histories of some examples are discussed

  13. 47 CFR 25.113 - Station licenses and launch authority.

    Science.gov (United States)

    2010-10-01

    ... 47 Telecommunication 2 2010-10-01 2010-10-01 false Station licenses and launch authority. 25.113 Section 25.113 Telecommunication FEDERAL COMMUNICATIONS COMMISSION (CONTINUED) COMMON CARRIER SERVICES SATELLITE COMMUNICATIONS Applications and Licenses General Application Filing Requirements § 25.113 Station...

  14. Development regulation regarding with licensing of nuclear installation

    International Nuclear Information System (INIS)

    Bambang Riyono; Yudi Pramono; Dahlia Cakrawati Sinaga

    2011-01-01

    Provisions of Article 17 paragraph (3) of Law Number 10 Year 1997 on Nuclear cleary mandates for the establishment of government regulations (GR) on Nuclear licensing containing the requirements and procedure, both from the standpoint of their utilization and installation. To use has been rising GR No.29 Year 2008 on the Use of Ionizing Radiation Sources and Nuclear Materials, while for the installation has been published PP No.43 Year 2006 on Nuclear Reactor Licensing, and BAPETEN Chairman Decree No.3 Year 2006 on Non-reactor Nuclear Installation Licensing. Based on the background of the preparation of both the aforementioned are just regulate the reactor and utilization, not yet fully meet the mandate of Article 17 paragraph (3) of Law No.10 of 1997 on Nuclear, including other nuclear installations. For these reasons, it initiated the need for a separate regulation containing provisions concerning licensing of non-reactor nuclear installations. On the other side from the understanding the legal aspects and interpretations of the Law No.10 of 2004 on the Establishment Regulation Legislation, should be in single mandate of Article 17 paragraph (3) of Law No.10 of 1997 on Nuclear would only produce one of the requirements and procedure for the use or installation, or a maximum of two (2) GR related licensing the use and installation. This is encourages conducted the assessing or studies related to how possible it is according to the legal aspect is justified to combine in one Nuclear licensing regulations regarding both the use and installation, by looking at the complexity of installation and wide scope of utilization of nuclear energy in Indonesia. The results of this paper is expected to provide input in the preparation of GR on licensing of nuclear installations. (author)

  15. International Harmonization of Reactor Licensing Regulations

    International Nuclear Information System (INIS)

    Kuhnt, Dietmar.

    1977-01-01

    The purpose of a harmonization policy for reactor licensing regulations on the basis of already considerable experience is to attain greater rationalisation in this field, in the interest of economic policy and healthy competition, and most important, radiation protection and safety of installations. This paper considers the legal instruments for such harmonization and the conditions for their implementation, in particular within the Communities framework. (NEA) [fr

  16. 76 FR 53492 - South Carolina Public Service Authority (Also Referred to as Santee Cooper); Combined Licenses...

    Science.gov (United States)

    2011-08-26

    ... Carolina Public Service Authority (Also Referred to as Santee Cooper); Combined Licenses for Virgil C... as Santee Cooper), for two Title 10 of the Code of Federal Regulations (10 CFR) part 52 combined... Service Authority (Also Referred to as Santee Cooper) Application for the Virgil C. Summer Nuclear Station...

  17. CEQ regulations called peril to nuclear licensing process

    International Nuclear Information System (INIS)

    O'Neill, J.V.

    1979-01-01

    Court challenges are expected over regulations of the Council on Environmental Quality (CEQ) that were designed to improve nuclear-licensing decisions, but that have actually changed the meanings of National Environmental Policy Act (NEPA) regulations. The legal implications of these changes could, unless resolved, make the licensing process for nuclear facilities even more uncertain. Agency comments are thought to be critical, although the CEQ has declined to release them, and some question the Council's legality. The Nuclear Regulatory Commission faults the CEQ regulations for revising existing law, being inconsistent with the responsibilities of an independent regulatory body, and extending the CEQ's authority beyond the role assigned by NEPA and the President's Executive Order

  18. Regulation of Federal radioactive waste activities. Summary of report to Congress on extending the Nuclear Regulatory Commission's licensing or regulatory authority to Federal radioactive waste storage and disposal activities

    International Nuclear Information System (INIS)

    Smith, R.D.

    1979-09-01

    The NRC Authorization Bill for FY 1979 directed NRC to conduct a study of extending the Commission's licensing or regulatory authority to include categories of existing and future Federal radioactive waste storage and disposal activities not presently subject to such authority. The report includes a complete listing and inventory of all radioactive waste storage and disposal activities now being conducted or planned by Federal agencies. The NRC study has attempted to present a general comparison of the relative hazards associated with defense-generated and commercial wastes. Options for extending Commission authority were developed and analyzed. The implications of NEPA were analyzed in the context of these options. The national security implications of extending NRC's regulatory authority over DOE programs are examined and evaluated. Costs and benefits are identified and assessed. The Commission's recommendations, based on the study, are to extend licensing authority over new DOE disposal activities involving transuranic wastes and non-defense low-level waste and to initiate a pilot program to test the feasibility of NRC playing a consultative role in the evaluation of existing DOE activities

  19. Regulation and Licensing Aspect. Chapter 5

    International Nuclear Information System (INIS)

    Muhamat Omar; Zalina Laili

    2015-01-01

    The NORM industries must apply the Envionmental Quality Act 1974 (Act 127), Safety Act and Occupational Safety and Health Act (514), Atomic Energy Licensing Act 1984 (Act 304) and others related act depend on the industries nature and situation.

  20. 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...

  1. Exporting licensing regulations affecting US geothermal firms

    Energy Technology Data Exchange (ETDEWEB)

    1988-08-01

    This document presents a brief introduction and overview of the Department of Commerce's Export Administration Regulations which might affect potential US geothermal goods exporters. It is intended to make US geothermal firms officials aware of the existence of such regulations and to provide them with references, contacts and phone numbers where they can obtain specific and detailed information and assistance. It must be stressed however, that the ultimate responsibility for complying with the above mentioned regulations lies with the exporter who must consult the complete version of the regulations.

  2. TSO support to safety authorities in new reactor licensing

    Energy Technology Data Exchange (ETDEWEB)

    Numark, N.J.; Bowling, M.L. [Numark Associates, Inc., Washington, DC (United States)

    2013-07-01

    Technical Support Organizations (TSOs) can provide review assistance to a safety authority in a cost-effective and timely manner. TSO scope tailored to safety authority needs. TSOs must understand and adhere to safety authority priorities and culture. TSOs must be flexible in regulatory approaches, work locations, time zones, and languages. Safety authorities have varying technical support needs. For instance, authorities may have substantial staff and expertise on various types of commercial Nuclear Power Plants (NPP), substantial staff and expertise on a single type of commercial NPP, limited staff but with expertise on commercial NPPs or limited staff and no expertise on commercial NPPs.

  3. 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)

  4. 47 CFR 80.203 - Authorization of transmitters for licensing.

    Science.gov (United States)

    2010-10-01

    ... application a working unit of the type for which certification is desired. Manufacturers of radar equipment... this chapter. Transmitters of a model authorized before October 1, 1986 will be considered type...) Except for radar equipment, applicants for certification of radio equipment designed to satisfy Part II...

  5. Sharing of responsibilities between central and local authorities with regard to the licensing of nuclear installations

    International Nuclear Information System (INIS)

    Peltzer, P.

    1986-01-01

    With regard to sharing of responsibility in the field of nuclear licensing between central and local authorities, the Belgian State has entered into a new phase of regionalisation since the enactment of the law of August 8, 1980. This might entail a conflict of competence in case of the licensing of nuclear power plants. A general survey of foreign legislations seems to indicate that a similar risk also exists in other countries. (CW) [de

  6. An overview of the licensing approach of the South African nuclear regulatory authority

    International Nuclear Information System (INIS)

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

    1997-01-01

    This paper describes the approach adopted by the South African Nuclear Regulatory Authority, the Council for Nuclear Safety (CNS) in licensing nuclear installations in South Africa. An introduction to the current South African legislation and the CNS philosophy pertaining to the licensing of nuclear installations is discussed. A typical process for granting a nuclear licence is then presented. The risk assessment process, which is used to verify compliance with the fundamental safety standards and to establish licensing requirements for a specific nuclear installation, is discussed. Based on the outcome of this assessment process, conditions of licence are set down. The generic content of a nuclear licence and mechanisms to ensure ongoing compliance with the risk criteria are presented. The regulatory process discussed in this paper, based on such a fundamental approach, may be adapted to any type of nuclear installation taking into account plant specific designs and characteristics. (author)

  7. 7 CFR 56.10 - Who may be licensed and authorized.

    Science.gov (United States)

    2010-01-01

    ... person to act as a “quality assurance inspector” in the packaging and grade labeling of products. No... (CONTINUED) VOLUNTARY GRADING OF SHELL EGGS Grading of Shell Eggs Licensed and Authorized Graders § 56.10 Who... determined by an examination for competency and who is to perform grading service under this part, may be...

  8. 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...

  9. Development in France of nuclear safety technical regulations and standards used in the licensing procedure

    International Nuclear Information System (INIS)

    Lebouleux, P.

    1983-04-01

    Initially, the Commissariat a l'Energie Atomique was the overall structure which encompassed all nuclear activities in France, including those connected with radiological protection and nuclear safety. As other partners appeared, the Authorities have laid down national regulations relative to nuclear installations since 1963. These regulations more particularly provide for the addition of prescriptions with which the applicant must comply to obtain the necessary licenses and the establishment of General Technical Regulations pertaining to nuclear safety. The technical regulation related to nuclear safety in France is made of a set of regulation texts, of a different nature, that define the requirements for the construction, commissioning and operation of nuclear facilities. Simultaneously, the safety authorities (Service Central de Surete des Installations Nucleaires: SCSIN) issue recommendations or guides which are not strictly speaking regulations in the juridical sense; they are called ''Regles Fondamentales de Surete'' (RFS). The RFS set up and detail the conditions, the respect of which is deemed to be complying with the French regulation practice, for the subject to which they relate. Their purpose is to make known rules judged acceptable by safety authorities, thus making the safety review easier. A RFS, or a letter, can also give the result of the examination of the constructor and operator codes (RCC) by safety authorities

  10. 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

  11. Staged licensing: An essential element of the NRC's revised regulations

    International Nuclear Information System (INIS)

    Echols, F.S.

    1997-01-01

    Over the past several years, Congress has directed the Department of Energy (DOE), the Nuclear Regulatory Commission (NRC), and the Environmental Protection Agency (EPA) to abandon their efforts to assess an array of potential candidate geologic repository sites for the permanent disposal of spent nuclear reactor fuel and high level radioactive waste, to develop generally applicable requirements for licensing geologic repositories, and to develop generally applicable radiation protection standards for geologic repositories, and instead to focus their efforts to determine whether a single site located at Yucca Mountain, Nevada can be developed as a geologic repository which providing reasonable assurance that public health and safety and the environment will be adequately protected. If the Yucca Mountain site is found to be suitable for development as a geologic repository, then at each stage of development DOE will have to provide the NRC with progressively more detailed information regarding repository design and long-term performance. NRC regulations reflect the fact that it will not be until the repository has been operated for a number of years that the NRC will be able to make a final determination as to long-term repository performance. Nevertheless, the NRC will be able to allow DOE to construct and operate a repository, provided that the NRC believes that the documented results of existing studies, together with the anticipated results from continuing and future studies, will enable the NRC to make a final determination that it has reasonable assurance that the repository system's long-term performance will not cause undue risk to the public. Thus, in its efforts to revise its current regulations to assure that the technical criteria are specifically applicable to the Yucca Mountain site, the NRC should also make sure that it preserves and clarifies the concept of staged repository development

  12. 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

  13. 14 CFR 1204.506 - Delegation of authority to license the use of the Centennial of Flight Commission name.

    Science.gov (United States)

    2010-01-01

    ... of the Centennial of Flight Commission name. 1204.506 Section 1204.506 Aeronautics and Space NATIONAL....506 Delegation of authority to license the use of the Centennial of Flight Commission name. (a... 9 of the Centennial of Flight Commemoration Act, as amended (Pub. L. 105-389) to license the use of...

  14. Radiation protection and safety guide no. GRPB-G-2: notification and authorization by registration or licensing, exemption and exclusion

    International Nuclear Information System (INIS)

    Schandorf, C.; Darko, O.; Yeboah, J.; Osei, E.K.; Asiamah, S.D.

    1995-01-01

    The obligatory requirement for the notification of the Radiation Protection Board and application for authorization by registration or licensing are important elements of the national system for controlling radiation sources and practices which may be potentially harmful to people. The present document provides guidance for Notification and Authorization by Registration or Licensing. In pursuance of the provision of the Radiation Protection Instrument, 1993, L I 1559, Part II C ontrol and Use of Radiation Sources , the present Guide specifies the Radiation Protection Board (RPB) scheme of notification and authorization by registration of licensing. Criteria for exempting and excluding sources and practices from regulatory control are highlighted

  15. Federal supervisory authorities' power to issue directives in nuclear licensing procedures (Kalkar reactor)

    International Nuclear Information System (INIS)

    Anon.

    1990-01-01

    The Federal Constitutional Court (BVerfG) is concerned in its judgement with the legal instrument of Federal supervisory authorities' power to issue directives in nuclear licensing procedures (Kalkar reactor). Dealt with are questions concerning material and excercising competences, the Federal Government's right to issue directives and possible violation of Laender rights, as well as the legal position between Land and Federal Government, the necessity to issue clear directives, questions concerning the competence to issue directives and the Federal Government's duty to consider the overall interests (Federal Government and Laender interests), questions concerning constitutional state principles and the limits in the relations between Federal Government - Laender concerning legal competence. (RST) [de

  16. Aging baby boomers--a blessing or challenge for driver licensing authorities.

    Science.gov (United States)

    Dobbs, Bonnie M

    2008-08-01

    In less than 5 years, the first wave of baby boomers will begin turning 65, with the last wave of boomers entering their senior years in January 2029. Currently, boomers make up a significant percentage of the population in Canada, the United States, and other developed countries. The baby boom generation has had a profound impact on our society over the last six decades, and this large cohort will continue to exert its influence for several decades to come. Central to this article is the rapid growth in the number of persons 65 years of age and older, beginning in 2011, with a corresponding increase in the number of older drivers. The demographic shift has important implications for licensing authorities, the regulatory bodies charged with licensing and 'fitness to drive' decisions. The objectives of this paper are to summarize the published scientific literature on licensing policies and procedures currently in use for older drivers, discuss their limitations, and provide recommendations for meeting the upcoming challenges of an aging baby boomer population of drivers. Online searches were conducted using the following databases: PsycINFO, MEDLINE, Scopus, and TRIS. Google and Google Scholar also were searched for scientific articles. References identified from database and online searches were examined for relevant articles. A number of studies have investigated the utility of different licensing policies and procedures for identifying older drivers who may be at risk for impaired driving performance. Overall, results suggest that current policies and procedures are ineffective in identifying high-risk older drivers. The results also emphasize the need for a different approach for the identification of high risk older drivers by licensing agencies. Recommendations to assist with that goal are provided. The aging of the baby boomer population, combined with the projected high crash rates for this cohort of drivers as it moves through the senior years, underscores

  17. Nuclear power reactor licensing and regulation in the United States

    International Nuclear Information System (INIS)

    Shapar, H.K.

    1979-01-01

    The report is devoted to four subjects: an explanation of the origins, statutory basis and development of the present regulatory system in the United States; a description of the various actions which must be taken by a license applicant and by the Nuclear Regulatory Commission before a nuclear power plant can be constructed and placed on-line, an account of the current regulatory practices followed by the US NRC in licensing nuclear power reactors; an identification of some of the 'lessons learned' from the Three Mile Island accident and some proposed regulatory and legislative solutions. (NEA) [fr

  18. How a regulator is preparing for reviewing a license application file: The case of ASN

    International Nuclear Information System (INIS)

    Tanguy, Loic

    2014-01-01

    The French Nuclear Safety Authority (ASN) is an independent administrative authority. It prepares regulation pertaining to the management of radioactive waste, monitors the control of safety of basic nuclear installations that produce or treat waste or are involved in their disposal and performs inspections of waste producers (EDF, AREVA, CEA, hospitals, research centres, etc.) and Andra, the French National Radioactive Waste Management Agency. It regulates the overall system set up by Andra for accepting waste from producers and assesses waste management policy and the practices of radioactive waste producers. It reviews license applications and authorises commissioning of nuclear installations. In order to review technical documents, ASN benefits from the expertise of technical support organisations. The French Institute for Radiation Protection and Nuclear Safety (IRSN) is the main such organisation. ASN has been making efforts to diversify its experts for several years. In preparing its decisions, ASN also calls on the opinions and recommendations of seven Advisory Committees of Experts (GPE), with expert knowledge in the areas of waste, nuclear pressure equipment, medical exposure, non-medical radiation protection, reactors, transport, and laboratories and nuclear plants. ASN consults the GPEs in preparing its main decisions. In particular, they review the preliminary, provisional and final safety analysis reports for each nuclear installation. They can also be consulted about changes in regulations or doctrine. (authors)

  19. 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

  20. 78 FR 30914 - Grand River Dam Authority Notice of Application for Temporary Variance of License and Soliciting...

    Science.gov (United States)

    2013-05-23

    .... Description of Request: Grand River Dam Authority (GRDA) requests a temporary variance, for the year 2013, to... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Project No. 1494-416] Grand River Dam Authority Notice of Application for Temporary Variance of License and Soliciting Comments, Motions To...

  1. 75 FR 6301 - Revisions to License Exception GOV To Provide Authorization for Exports and Reexports of...

    Science.gov (United States)

    2010-02-09

    ... of the United States, Russia, Japan, Canada, Europe and Italy. (The Italian Space Agency has separate... subject to a license requirement when exported or reexported to Russia. However, even when BIS license... unexpected delays in a launch schedule, such as for mechanical failures in a launch vehicle or weather...

  2. 77 FR 71454 - Notice of Atomic Safety And Licensing Board Reconstitution, Tennessee Valley Authority (Watts Bar...

    Science.gov (United States)

    2012-11-30

    ... accordance with the NRC E-Filing rule. See 10 CFR 2.302 et seq. Issued at Rockville, Maryland this 16th day of November 2012. E. Roy Hawkens, Chief Administrative Judge, Atomic Safety and Licensing Board Panel...

  3. Dynamic assembly of Hda and the sliding clamp in the regulation of replication licensing.

    Science.gov (United States)

    Kim, Jin S; Nanfara, Michael T; Chodavarapu, Sundari; Jin, Kyeong S; Babu, Vignesh M P; Ghazy, Mohamed A; Chung, Scisung; Kaguni, Jon M; Sutton, Mark D; Cho, Yunje

    2017-04-20

    Regulatory inactivation of DnaA (RIDA) is one of the major regulatory mechanisms of prokaryotic replication licensing. In RIDA, the Hda-sliding clamp complex loaded onto DNA directly interacts with adenosine triphosphate (ATP)-bound DnaA and stimulates the hydrolysis of ATP to inactivate DnaA. A prediction is that the activity of Hda is tightly controlled to ensure that replication initiation occurs only once per cell cycle. Here, we determined the crystal structure of the Hda-β clamp complex. This complex contains two pairs of Hda dimers sandwiched between two β clamp rings to form an octamer that is stabilized by three discrete interfaces. Two separate surfaces of Hda make contact with the β clamp, which is essential for Hda function in RIDA. The third interface between Hda monomers occludes the active site arginine finger, blocking its access to DnaA. Taken together, our structural and mutational analyses of the Hda-β clamp complex indicate that the interaction of the β clamp with Hda controls the ability of Hda to interact with DnaA. In the octameric Hda-β clamp complex, the inability of Hda to interact with DnaA is a novel mechanism that may regulate Hda function. © The Author(s) 2017. Published by Oxford University Press on behalf of Nucleic Acids Research.

  4. The regulation and licensing of research reactors and associated facilities in the United Kingdom

    International Nuclear Information System (INIS)

    Weightman, M.W.; Willby, C.R.

    1990-01-01

    In the United Kingdom, the Nuclear Installations Inspectorate (NII) licenses nuclear facilities, including research reactors, on behalf of the Health and Safety Executive (HSE). The legislation, the regulatory organizations and the methods of operation that have been developed over the last 30 years result in a largely non-prescriptive form of control that is well suited to research reactors. The most important part of the regulatory system is the license and the attachment of conditions which it permits. These conditions require the licensee to prepare arrangements to control the safety of the facility. In doing so the licensee is encouraged to develop a 'safety culture' within its organization. This is particularly important for research reactors which may have limited staff resources and where the ability, and at times the need, to have access to the core is much greater than for nuclear power plants. Present day issues such as the ageing of nuclear facilities, public access to the rationale behind regulatory decisions, and the emergence of more stringent safety requirements, which include a need for quantified safety criteria, have been addressed by the NII. This paper explores the relevance of such issues to the regulation of research reactors. In particular, it discusses some of the factors associated with research reactors that should be considered in developing criteria for the tolerability of risk from these nuclear facilities. From a consideration of these factors, it is the authors' view that the range of tolerable risk to the public from the operation of new research reactors may be expected to be more stringent than similar criteria for new nuclear power plants, whereas the criteria for tolerable risk for research reactor workers are expected to be about the same as those for power reactor workers

  5. Reconsidering the relevance of social license pressure and government regulation for environmental performance of European SMEs

    NARCIS (Netherlands)

    Graafland, Johan; Smid, Hugo

    Whereas social license pressure is held as a strong motive for the corporate social performance (CSP) of large enterprises, it is argued in literature that it will not sufficiently motivate small and medium-sized enterprises (SMEs). In this view, government regulation is the most effective way to

  6. 76 FR 78483 - S.A.F.E. Mortgage Licensing Act (Regulations G & H)

    Science.gov (United States)

    2011-12-19

    ... BUREAU OF CONSUMER FINANCIAL PROTECTION 12 CFR Part 1007 and 1008 [Docket No. CFPB-2011-0023] RIN 3170-AA06 S.A.F.E. Mortgage Licensing Act (Regulations G & H) AGENCY: Bureau of Consumer Financial... number of consumer financial protection laws from seven Federal agencies to the Bureau of Consumer...

  7. Does Self-Licensing Benefit Self- Regulation Over Time? An Ecological Momentary Assessment Study of Food Temptations

    NARCIS (Netherlands)

    Prinsen, S.|info:eu-repo/dai/nl/369408217; Evers, C.|info:eu-repo/dai/nl/280594232; Wijngaards, Leoniek; van Vliet, Renee; de Ridder, D.T.D.|info:eu-repo/dai/nl/070706174

    2018-01-01

    Self-licensing, employing reasons to justify indulgence, may help resolve the conflict between immediate temptations and long-term goals in favor of the former. It was hypothesized that this conflict-resolving potential of self-licensing may benefit self-regulation over time. With a momentary

  8. 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

  9. 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.

  10. 31 CFR 545.526 - Certain importations for diplomatic or official personnel authorized.

    Science.gov (United States)

    2010-07-01

    ... TALIBAN (AFGHANISTAN) SANCTIONS REGULATIONS Licenses, Authorizations and Statements of Licensing Policy... ordinarily incident to the importation into the United States of any goods, software, technology or services...

  11. Responsibility without legal authority? Tackling alcohol-related health harms through licensing and planning policy in local government.

    Science.gov (United States)

    Martineau, F P; Graff, H; Mitchell, C; Lock, K

    2014-09-01

    The power to influence many social determinants of health lies within local government sectors that are outside public health's traditional remit. We analyse the challenges of achieving health gains through local government alcohol control policies, where legal and professional practice frameworks appear to conflict with public health action. Current legislation governing local alcohol control in England and Wales is reviewed and analysed for barriers and opportunities to implement effective population-level health interventions. Case studies of local government alcohol control practices are described. Addressing alcohol-related health harms is constrained by the absence of a specific legal health licensing objective and differences between public health and legal assessments of the relevance of health evidence to a specific place. Local governments can, however, implement health-relevant policies by developing local evidence for alcohol-related health harms; addressing cumulative impact in licensing policy statements and through other non-legislative approaches such as health and non-health sector partnerships. Innovative local initiatives-for example, minimum unit pricing licensing conditions-can serve as test cases for wider national implementation. By combining the powers available to the many local government sectors involved in alcohol control, alcohol-related health and social harms can be tackled through existing local mechanisms. © The Author 2013. Published by Oxford University Press on behalf of Faculty of Public Health.

  12. 40 CFR 146.2 - Law authorizing these regulations.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 22 2010-07-01 2010-07-01 false Law authorizing these regulations. 146.2 Section 146.2 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) WATER PROGRAMS (CONTINUED) UNDERGROUND INJECTION CONTROL PROGRAM: CRITERIA AND STANDARDS General Provisions § 146.2 Law...

  13. 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)

  14. The commission of energy regulation: statute, missions and authority

    International Nuclear Information System (INIS)

    Laffaille, D.; Bossoutrot, Ch.

    2008-01-01

    The commission of energy regulation (CRE), which has superseded the commission of electricity regulation, was created by the law no. 2000-108 from February 10, 2000, relative to the modernization and development of the French electric utility. This article presents the situation of CRE's statute, missions and authority seven years after its creation. The statute of CRE warrants its independence, autonomy and impartiality. Its operation means consist in budgetary and personnel resources. Its main mission is the control of the conditions of use of gas and electricity networks and the respect of competition rules: free and transparent access to networks and infrastructures, control of the good operation and development of networks and facilities, regulation of markets, strengthening of the public utility mission. Its authority concerns the management of networks, the book-keeping control of energy operators, the settlement of disputes, the attribution of sanctions, the monitoring of energy markets operation etc. (J.S.)

  15. Allocation of responsibilities between central and local authorities concerning nuclear power plant licensing

    International Nuclear Information System (INIS)

    Peltzer, P.

    1983-01-01

    This paper examines Belgian regulations on licences to construct and operate nuclear power plants in the context of implementation of the 1980 Act concerning regionalisation. It also reviews the relevant nuclear legislation in certain other countries. (NEA) [fr

  16. 76 FR 35275 - Export Control Reform Initiative: Strategic Trade Authorization License Exception

    Science.gov (United States)

    2011-06-16

    ... (c)(2) destinations are: Albania, Hong Kong, India, Israel, Malta, Singapore, South Africa, and... Exception Strategic Trade Authorization (STA) authorizes, with conditions, the export, reexport and transfer... BIS's workload and, without adequate preparation, could result in backlogs and delays. BIS is working...

  17. 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.

  18. Survey of the authorities competent for licensing and supervision in the field of radiation protection under the terms of the Atomic Energy Act (As of January 1980)

    International Nuclear Information System (INIS)

    1980-01-01

    Contents: 1. Portfolio of the Federal Minister of Defence. 2. Handling of other radioactive substances, equipment for the generation of ionizing radiation and activities in installations owned by third parties: 2.1 Licensing authorities; 2.2 competent authorities for the acception and documentation of notifications required under sections 4, sub-section 1, 17 sub-section 1, of the Radiation Protection Ordinance; 2.3 authorities competent for the registration of radiation records; 2.4 supervisory authorities. 3. Carriage of radioactive substances: 3.1 Federal authorities responsible for licensing and supervisions; 3.2 Land authorities responsible for licensing; 3.3 Land authorities responsible for supervision. 4. Permits concerning the design of equipment. 5. Import and export of radioactive substances: 5.1 Licensing authorities; 5.2 supervisory authorities. 6. Competent authorities in accordance with section 63 sub-section 3 paragraph 1 of the Radiation Protection Ordinance (monitoring stations) and according to the provisions of Land legislation. 7. Licensing and supervisory authorities for the treatment, processing or any other use of nuclear fuels under section 9 of the Atomic Energy Act. 8. Competences of the Laender in the implementation of the Atomic Energy Act and the Radiation Protection Ordinance. (orig.) [de

  19. Design and quality assurance of control and instrumentation systems, licensing practice in Austria

    International Nuclear Information System (INIS)

    Fasko, Peter.

    1978-01-01

    The practicised way how licensing of control and instrumentation systems is performed in Austria, is related. As there is no national regulations in Austria for licensing nuclear power plants, it tries to adopt international regulations for its own purpose. (author)

  20. Radiation protection technology. Specific course for authorized radiation protection representatives according the qualification guidelines technology for the radiation protection regulations (StrlSchV) and X-ray regulation (RoeV). 2. rev. ed.

    International Nuclear Information System (INIS)

    Rahn, Hans-Joachim

    2012-01-01

    The specific course for authorized radiation protection representatives according the qualification guidelines technology for the radiation protection regulations (StrlSchV) and X-ray regulation (RoeV). Covers the following issues: radiation protection - generally; licenses and notifications; scientific fundamentals; dosimetry, surveillance, control, documentation; technical radiation protection; radiation protection calculations.

  1. Relevance in print of law of administrative regulations according to paragraph 48 BImSchG in the licensing procedure

    International Nuclear Information System (INIS)

    Breuer, R.

    1978-01-01

    The author discusses in great detail the legal problem of administrative regulations according to paragraph 48 of the Bundes-Immissionsschutzgesetz, BImSchG (Federal Act for the prevention of immissions) and their relevance in point of law in licensing procedures. He very carefully and skilfully presents the different opinions stated in the precedents and by the body of doctrine and quite convincingly explains why he rejects the doctrine of allowing the administration some latitude in their judgement, and thus the doctrine of the defensible opinion with regard to the examination by the court of undefined legal terms. According to the auther's view, the administrative regulations should be regarded as anticipated expert opinions because of the way they are drawn up and because of the way the relevant committees setting up the rules are constituted, i.e. they can serve as a basis for judical decisions. In this connection the author points out that in any case it is left to the court's decisions whether a non-formal expert opinion is deemed to be sufficient, or whether the rules of procedure require a formal expert opinion. Furthermore, several ways of enhancing the binding effect of the administrative regulations pursuant to paragraph 48 of the BImSchG by means of legislatory measures are shown. (UN) [de

  2. Temporary authorization for use: does the French patient access programme for unlicensed medicines impact market access after formal licensing?

    Science.gov (United States)

    Degrassat-Théas, Albane; Paubel, Pascal; Parent de Curzon, Olivier; Le Pen, Claude; Sinègre, Martine

    2013-04-01

    To reach the French market, a new drug requires a marketing authorization (MA) and price and reimbursement agreements. These hurdles could delay access to new and promising drugs. Since 1992, French law authorizes the use of unlicensed drugs on an exceptional and temporary basis through a compassionate-use programme, known as Temporary Authorization for Use (ATU). This programme was implemented to improve early access to drugs under development or authorized abroad. However, it is suspected to be inflationary, bypassing public bodies in charge of health technology assessment (HTA) and of pricing. The aim of this study is to observe the market access after the formal licensing of drugs that went through this compassionate-use programme. We included all ATUs that received an MA between 1 January 2005 and 30 June 2010. We first examined market access delays from these drugs using the standard administrative path. We positioned this result in relation to launch delays observed in France (for all outpatient drugs) and in other major European markets. Second, we assessed the bargaining power of a hospital purchaser after those drugs had obtained an MA by calculating the price growth rate after the approval. During the study period, 77 ATUs were formally licensed. The study concluded that, from the patient's perspective, licensing and public bodies' review time was shortened by a combined total of 36 months. The projected 11-month review time of public bodies may be longer than delays usually observed for outpatient drugs. Nonetheless, the study revealed significant benefits for French patient access based on comparable processing to launch time with those of other European countries with tight price control policies. In return, a 12 % premium, on average, is paid to pharmaceutical companies while drugs are under this status (sub-analysis on 56 drugs). In many instances, the ATU programme responds to a public health need by accelerating the availability of new drugs

  3. Qualification, training, licensing/authorization and retraining of operating personnel in nuclear power plants. Some requirements and practices commonly shared in the European Community Member States

    International Nuclear Information System (INIS)

    Pele, J.P.

    1987-01-01

    At the end of the fifties a treaty was signed instituting between six countries of the European Community for Atomic Energy, or in brief, Euratom. This treaty, in addition to the Common Market Treaty and the Coal and Steel one, constitutes the legal frame of the European Community which, at present, comprises 12 Member States. A commission, the so-called Commission of the European Communities (or in brief CEC) has to implement the provisions laid down in the treaties. Qualification, training, licensing and re-training of operating personnel have been the subjects of an in-depth exchange of views and information in the frame of the work conducted by the Commission. The evaluation of the regulations and practices in countries of the EC and some other countries having a large nuclear energy program, has led to the identification of some generally valid concepts. This synthesis, made with the assistance of a consultant, is now published under the form of an EUR report (EUR 10981). The main topics addressed within this report are the following: shift staffing and staffing of the control room, personnel selection, qualifications necessary for recruitment, training and retraining, and licensing/authorization

  4. 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)

  5. 77 FR 55475 - Federal Acquisition Regulation; Information Collection; Permits, Authorities, or Franchises

    Science.gov (United States)

    2012-09-10

    ...; Information Collection; Permits, Authorities, or Franchises AGENCY: Department of Defense (DOD), General... approved information collection requirement concerning permits, authorities, or franchises for regulated..., Authorities, or Franchises, by any of the following methods: Regulations.gov : http://www.regulations.gov...

  6. Responsibilities of nuclear regulatory authority and overview of nuclear safety regulations in Slovakia

    International Nuclear Information System (INIS)

    Misak, J.

    1996-01-01

    The paper describes the organizational structure of the Nuclear Regulatory Authority of the Slovak Republic, its rights and duties, the status of nuclear legislation with emphasis on nuclear activities completely or partially covered, and licensing procedures

  7. License to Sin : A Justification-Based Account of Self-Regulation Failure

    NARCIS (Netherlands)

    De Witt Huberts, J.C.

    2012-01-01

    Few phenomena question the authority of reason over our behavior more than self-regulation failure. As a result, most accounts of self-regulation failure have explained such self-defeating behavior as arising from impulsive factors that undermine our ability to act as we intend. In the present

  8. Retailer licensing and tobacco display compliance: are some retailers more likely to flout regulations?

    Science.gov (United States)

    Fry, Rae; Burton, Suzan; Williams, Kelly; Walsberger, Scott; Tang, Anita; Chapman, Kathy; Egger, Sam

    2017-03-01

    To assess retailer compliance with a licensing scheme requiring tobacco retailers to list their business details with the government, to examine whether listed retailers are more likely to comply with a point-of-sale (POS) display ban and other in-store retailing laws and to explore variations in compliance between different retailer types and locations. An audit of 1739 retailers in New South Wales, Australia, was used to assess compliance with tobacco retailing legislation. Auditors actively searched for and audited unlisted retailers and all listed retailers in 122 metropolitan and regional postcodes. Multivariate generalised linear regression models were used to examine associations between compliance and retailer type, remoteness and demographic characteristics (socioeconomic level, proportion of population under 18 years and proportion born in Australia). One unlisted tobacco retailer was identified for every 12.6 listed tobacco retailers. Unlisted retailers were significantly more likely than listed retailers to breach in-store retailing laws (plaws was only 73.4%. Retailers in socioeconomically disadvantaged areas had lower compliance than those in high socioeconomic areas. Some tobacco retailers did not list their business details with the government as required, even though there was no financial cost to do so. Unlisted retailers were more likely to violate in-store regulations. The results suggest licensing schemes can be useful for providing a list of retailers, thus facilitating enforcement, but require a system to search for, and respond to, unlisted/unlicensed retailers. Published by the BMJ Publishing Group Limited. For permission to use (where not already granted under a licence) please go to http://www.bmj.com/company/products-services/rights-and-licensing/.

  9. Licensing of safety critical software for nuclear reactors. Common position of seven European nuclear regulators and authorised technical support organisations

    Energy Technology Data Exchange (ETDEWEB)

    2010-07-01

    It is widely accepted that the assessment of software cannot be limited to verification and testing of the end product, i.e. the computer code. Other factors such as the quality of the processes and methods for specifying, designing and coding have an important impact on the implementation. Existing standards provide limited guidance on the regulatory and safety assessment of these factors. An undesirable consequence of this situation is that the licensing approaches taken by nuclear safety authorities and by technical support organisations are determined independently with only limited informal technical co-ordination and information exchange. It is notable that several software implementations of nuclear safety systems have been marred by costly delays caused by difficulties in co-ordinating the development and qualification process. It was thus felt necessary to compare the respective licensing approaches, to identify where a consensus already exists, and to see how greater consistency and more mutual acceptance could be introduced into current practices. This report is the result of the work of a group of regulator and safety authorities' experts. The 2007 version was completed at the invitation of the Western European Nuclear Regulators' Association (WENRA). The major result of the work is the identification of consensus and common technical positions on a set of important licensing issues raised by the design and operation of computer based systems used in nuclear power plants for the implementation of safety functions. The purpose is to introduce greater consistency and more mutual acceptance into current practices. To achieve these common positions, detailed consideration was paid to the licensing approaches followed in the different countries represented by the experts of the task force. The report is intended to be useful: - to coordinate regulators' and safety experts' technical viewpoints in the design of regulators' national

  10. Licensing of safety critical software for nuclear reactors. Common position of seven European nuclear regulators and authorised technical support organisations

    International Nuclear Information System (INIS)

    2010-01-01

    It is widely accepted that the assessment of software cannot be limited to verification and testing of the end product, i.e. the computer code. Other factors such as the quality of the processes and methods for specifying, designing and coding have an important impact on the implementation. Existing standards provide limited guidance on the regulatory and safety assessment of these factors. An undesirable consequence of this situation is that the licensing approaches taken by nuclear safety authorities and by technical support organisations are determined independently with only limited informal technical co-ordination and information exchange. It is notable that several software implementations of nuclear safety systems have been marred by costly delays caused by difficulties in co-ordinating the development and qualification process. It was thus felt necessary to compare the respective licensing approaches, to identify where a consensus already exists, and to see how greater consistency and more mutual acceptance could be introduced into current practices. This report is the result of the work of a group of regulator and safety authorities' experts. The 2007 version was completed at the invitation of the Western European Nuclear Regulators' Association (WENRA). The major result of the work is the identification of consensus and common technical positions on a set of important licensing issues raised by the design and operation of computer based systems used in nuclear power plants for the implementation of safety functions. The purpose is to introduce greater consistency and more mutual acceptance into current practices. To achieve these common positions, detailed consideration was paid to the licensing approaches followed in the different countries represented by the experts of the task force. The report is intended to be useful: - to coordinate regulators' and safety experts' technical viewpoints in the design of regulators' national policies and in revisions

  11. 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

  12. Legal and administrative problems in regulating public participation in licensing of nuclear installations

    International Nuclear Information System (INIS)

    Cornelis, J.C.

    1981-10-01

    This general analysis of the question of public acceptance of nuclear activities focuses on the problems met by all governmental authorities in implementing their nuclear programmes. The author highlights the need for more specific regulations aimed at guaranteeing fuller information of the public and ensuring closer participation by it. (NEA) [fr

  13. 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

  14. Application of the New Decommissioning Regulation to the Nuclear Licensed Facilities (NLF) at Fontenay-aux-Roses's Nuclear Center (CEA)

    International Nuclear Information System (INIS)

    Sauret, Josiane; Piketty, Laurence; Jeanjacques, Michel

    2008-01-01

    This abstract describes the application of the new decommissioning regulation on all Nuclear Licensed Facilities (NLF is to say INB in French) at Fontenay-aux-Roses's Center (CEA/FAR). The decommissioning process has been applied in six buildings which are out of the new nuclear perimeter proposed (buildings no 7, no 40, no 94, no 39, no 52/1 and no 32) and three buildings have been reorganized (no 54, no 91 and no 53 instead of no 40 and no 94) in order to increase the space for temporary nuclear waste disposal and to reduce the internal transports of nuclear waste on the site. The advantages are the safety and radioprotection improvements and a lower operating cost. A global safety file was written in 2002 and 2003 and was sent to the French Nuclear Authority on November 2003. The list of documents required is given in the paragraph I of this paper. The main goals were two ministerial decrees (one decree for each NLF) getting the authorization to modify the NLF perimeter and to carry out cleaning and dismantling activities leading to the whole decommissioning of all NLF. Some specific authorizations were necessary to carry out the dismantling program during the decommissioning procedure. They were delivered by the French Nuclear Safety Authority (FNSA) or with limited delegation by the General Executive Director (GED) on the CEA Fontenay-aux-Roses's Center, called internal authorization. Some partial dismantling or decontamination examples are given below: - evaporator for the radioactive liquid waste treatment station (building no 53): FNSA authorization: phase realised in 2002/2003. - disposal tanks for the radioactive liquid waste treatment station (building no 53) FNSA authorization: phase realised in 2004, - incinerator for the radioactive solid waste treatment station (building no 07): FNSA authorization: operation realised in 2004, - research equipments in the building no. 54 and building no. 91: internal authorization ; realised in 2005, - sample

  15. PHITS code improvements by Regulatory Standard and Research Department Secretariat of Nuclear Regulation Authority

    International Nuclear Information System (INIS)

    Goko, Shinji

    2017-01-01

    As for the safety analysis to be carried out when a nuclear power company applies for installation permission of facility or equipment, business license, design approval etc., the Regulatory Standard and Research Department Secretariat of Nuclear Regulation Authority continuously conducts safety research for the introduction of various technologies and their improvement in order to evaluate the adequacy of this safety analysis. In the field of the shielding analysis of nuclear fuel transportation materials, this group improved the code to make PHITS applicable to this field, and has been promoting the improvement as a tool used for regulations since FY2013. This paper introduced the history and progress of this safety research. PHITS 2.88, which is the latest version as of November 2016, was equipped with the automatic generation function of variance reduction parameters [T-WWG] etc., and developed as the tool equipped with many effective functions in practical application to nuclear power regulations. In addition, this group conducted the verification analysis against nuclear fuel packages, which showed a good agreement with the analysis by MCNP, which is extensively used worldwide and abundant in actual results. It also shows a relatively good agreement with the measured values, when considering differences in analysis and measurement. (A.O.)

  16. 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)

  17. Progress in licensing ITER in Cadarache

    International Nuclear Information System (INIS)

    Rodriguez-Rodrigo, Lina; Girard, Jean-Philippe; Uzan-Elbez, Joelle; Marbach, Gabriel; Garin, Pascal; Rosanvallon, Sandrine

    2005-01-01

    The licensing procedure for ITER in Europe in the framework of the French regulations is a non-prescriptive approach based on a continuous dialogue between the nuclear installation owner (or its representative) and the safety authority. In this paper, the licensing procedure and main safety issues, which are being studied in this process, are presented

  18. 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

  19. Assessment of the U.S. regulations for fissile exemptions and fissile material general licenses

    International Nuclear Information System (INIS)

    Parks, C.V.; Hopper, C.M.; Lichtenwalter, J.J.; Easton, E.P.; Brochman, P.G.

    1998-05-01

    The paragraphs for general licenses for fissile material and exemptions (often termed exceptions in the international community) for fissile material have long been a part of the US Code of Federal Regulations (CFR) 10 CFR Part 71, Packaging and Transportation of Radioactive Material. More recently, the Nuclear Regulatory Commission (NRC) issued a final rule on Part 71 via emergency rule-making procedures in order to address an identified deficiency related to one of the fissile exemptions. To address the specified deficiency in a general fashion, the emergency rule adopted the approach of the 1996 Edition of the IAEA: Regulations for the Safe Transport of Radioactive Material (IAEA 1996), which places restrictions on certain moderating materials and limits the quantity of fissile material in a consignment. The public comments received by the NRC indicated general agreement with the need for restrictions on certain moderators (beryllium, deuterium, and graphite). The comments indicated concern relative to both the degree of restriction imposed (not more than 0.1% of fissile material mass) and the need to limit the fissile material mass of the consignment, particularly in light of the subsequent NRC staff position that the true intent was to provide control for limiting the fissile mass of the conveyance. The purpose of the review is to identify potential deficiencies that might be adverse to maintaining adequate subcriticality under normal conditions of transport and hypothetical accident conditions. In addition, ORNL has been asked to identify changes that would address any identified safety issues, enable inherently safe packages to continue to be unencumbered in transport, and seek to minimize the impact on current safe practices

  20. 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...

  1. Regulatory guidance for license renewal

    International Nuclear Information System (INIS)

    Thoma, John A.

    1991-01-01

    The proposed 10 CFR Part 54 rule proceduralizes the process for license renewal by identifying both the administrative and technical requirements for a renewal application. To amplify and support this regulation, written guidance has been provided in the form of a draft Regulatory Guide (DG 1009) and a draft Standard Review Plan for License Renewal (NUREG 1299). This guidance is scheduled to be finalized in 1992. Similar guidance will be provided for the proposed revisions to 10 CFR Part 51 concerning the environmental aspects of license renewal. (author)

  2. Crossing boundaries: a comprehensive survey of medical licensing laws and guidelines regulating the interstate practice of pathology.

    Science.gov (United States)

    Hiemenz, Matthew C; Leung, Stanley T; Park, Jason Y

    2014-03-01

    In the United States, recent judicial interpretation of interstate licensure laws has found pathologists guilty of malpractice and, more importantly, the criminal practice of medicine without a license. These judgments against pathologists highlight the need for a timely and comprehensive survey of licensure requirements and laws regulating the interstate practice of pathology. For all 50 states, each state medical practice act and state medical board website was reviewed. In addition, each medical board was directly contacted by electronic mail, telephone, or US registered mail for information regarding specific legislation or guidelines related to the interstate practice of pathology. On the basis of this information, states were grouped according to similarities in legislation and medical board regulations. This comprehensive survey has determined that states define the practice of pathology on the basis of the geographic location of the patient at the time of surgery or phlebotomy. The majority of states (n=32) and the District of Columbia allow for a physician with an out-of-state license to perform limited consultation to a physician with the specific state license. Several states (n=5) prohibit physicians from consultation without a license for the specific state. Overall, these results reveal the heterogeneity of licensure requirements between states. Pathologists who either practice in multiple states, send cases to out-of-state consultants, or serve as consultants themselves should familiarize themselves with the medical licensure laws of the states from which they receive or send cases.

  3. 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

  4. 10 CFR 51.107 - Public hearings in proceedings for issuance of combined licenses; limited work authorizations.

    Science.gov (United States)

    2010-01-01

    ... resolved in the early site permit proceeding; or (3) Raises any issue involving the impacts of construction... license hearing shall not admit contentions proffered by any party concerning severe accident mitigation... construction and operation of a nuclear power plant, and a construction permit was issued but construction of...

  5. Review of NRC Commission Papers on Regulatory Basis for Licensing and Regulating Reprocessing Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Park, Jae Yeong; Shin, Hyeong Ki [KINS, Daejeon (Korea, Republic of)

    2016-05-15

    Spent nuclear fuel (SNF) accumulated in nuclear power plant has been a serious issue in most countries with operating nuclear power plants. Direct disposal of SNF could be a solution of the problem but many countries including the Republic of Korea have had a hard time selecting a site for high level waste repository because of low public acceptance. SNF recycling technologies consisting of reprocessing and transmutation have been developed so as to reduce the final volume of the disposed radioactive waste and to diminish the radiotoxicity of the waste. The Republic of Korea is now developing pyroprocessing and sodium-cooled fast reactor (SFR) technology to be used for the recycling of the wastes. KAERI has a plan to construct a pyroprocessing facility with a capacity of 30 tHM/y and a facility manufacturing TRU fuel for SFR by 2025. However, to license these facility and secure the safety, the current regulatory system related to SNF treatment needs to be improved and amended since the system has been developed focusing on facilities to examine irradiated nuclear materials. Status of reprocessing facility regulations developed by U.S.NRC was reviewed based on SECY papers. U.S.NRC has approved the development of a new rule referred to nationally as '10CFR Part 7x'. Existing 10CFR 50 and 70 has been evolved mainly for nuclear power plants and fuel cycle facilities whose radiological hazard is much lower than reprocessing plants respectively. U.S.NRC also derived many regulatory gaps including safety assessment methods, technical specification, general design criteria and waste classification and continue to develop the regulatory framework limited in scope to the resolution of Gap 5.

  6. Licensing systems and inspection of nuclear installations

    International Nuclear Information System (INIS)

    1991-01-01

    The first study analysing the regulations governing the licensing and inspection of nuclear installations in OECD countries was published by OECD/NEA in 1980, and revised in 1986. Since then there have been amendments to national regulations on the subject, which have warranted updating of this publication. This new study provides a description of the licensing regulations and practices applied in the twenty OECD countries with provisions in that field. The national systems have been described according to a standard format to make comparisons and research easier. In most cases, the descriptions are supplemented by flow charts illustrating the procedures and specifying the different authorities involved in the licensing procedures [fr

  7. Independent regulatory authorities - a comparative study of European energy regulators

    International Nuclear Information System (INIS)

    Sander Johansen, K.; Holm Pedersen, L.; Moll Soerensen, E.

    2004-04-01

    Independent regulatory authorities are widely recommended as part of the institutional design of liberalised energy markets - not least by the European Commission. This report describes and compares the regulatory authorities for energy in the EU. Arguments for regulatory independence are presented and discussed, and an index is developed to measure the degree of conformance to theories of regulatory independence. It is established that the main pattern of variation is that countries, which formerly had strong state-owned companies, have chosen to create regulatory authorities at state level with many institutional safeguards for independence. (au)

  8. Activities of the TUV experts during the period of construction and commissioning of a nuclear power plant ordered by the licensing authorities of the FRG

    International Nuclear Information System (INIS)

    Dommke, J.; Fendler, H.

    1977-01-01

    The inspection organisations in the Federal Republic of Germany (Technische Uberwachungs-Vereine) are independent systems grouped on a regional basis. The competent licensing authorities of the various Lander consult them concerning assessments for site selection and the design, construction, commissioning and operation of nuclear power plants. Furthermore the TUV experts inspect the manufacture of components in the suppliers' facilities and on site. (NEA) [fr

  9. 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 ...

  10. Overview of the Yucca Mountain Licensing Process

    International Nuclear Information System (INIS)

    M. Wisenburg

    2004-01-01

    This paper presents an overview of the licensing process for a Yucca Mountain repository for high-level radioactive waste and spent nuclear fuel. The paper discusses the steps in the licensing proceeding, the roles of the participants, the licensing and hearing requirements contained in the Code of Federal Regulations. A description of the Nuclear Regulatory Commission (NRC) staff acceptance and compliance reviews of the Department of Energy (DOE) application for a construction authorization and a license to receive and possess high-level radioactive waste and spent nuclear fuel is provided. The paper also includes a detailed description of the hearing process

  11. Federal, state, and local regulation of radioactive-waste transportation: Progress toward a definition of regulatory authority

    International Nuclear Information System (INIS)

    Livingston-Behan, E.A.

    1986-01-01

    The supremacy clause, the commerce clause, and the equal-protection guarantees of the U.S. Constitution establish the basic framework for defining the authority of Federal, State, and local governments to regulate the transportation of radioactive waste. Court decisions and advisory rulings of the U.S. Department of Transportation (DOT) suggest that State and local regulation of the transportation of spent nuclear fuel and high-level radioactive waste is precluded under supremacy-clause principles to the extent that such regulation addresses nuclear safety or aspects of transportation that are already specifically regulated by the Federal government. Even where State and local requirements are found to be valid under the supremacy clause, they must still satisfy constitutional requirements under the commerce and equal-protection clauses. Despite stringent standards of review, State and local transportation requirements have been upheld where directly related to the traditional exercise of police powers in the area of transportation. Legitimate State and local police-power activities identified to date by the DOT and the courts include inspection and enforcement, immediate accident reporting, local regulation of traffic, and certain time-of-day curfews. The extent to which State and local permitting requirements and license fees may be determined valid by the DOT and the courts remains unclear. Continued clarification by the DOT and the courts as to the validity of permits and fees will serve to further define the appropriate balance for Federal, State, and local regulation of radioactive-waste transportation

  12. 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

  13. [Regulating radiological protection and the role of health authorities].

    Science.gov (United States)

    Arias, César F

    2006-01-01

    This article summarizes the development of protection against ionizing radiation and explains current thinking in the field. It also looks at the decisive role that regulatory agencies for radiological protection must play and the important contributions that can be made by health authorities. The latter should take an active part in at least three aspects: the formal education of health personnel regarding radiological protection; the medical care of individuals who are accidentally overexposed, and the radiological protection of patients undergoing radiological procedures. To this end, health professionals must possess sufficient knowledge about radiological protection, promote the use of proper equipment, and apply the necessary quality assurance procedures. Through their effective intervention, national health authorities can greatly contribute to reducing unnecessary doses of radiation during medical procedures involving radiation sources and decrease the chances that radiological accidents will take place.

  14. 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

  15. 78 FR 5451 - Federal Acquisition Regulation; Submission for OMB Review; Permits, Authorities, or Franchises

    Science.gov (United States)

    2013-01-25

    ...; Submission for OMB Review; Permits, Authorities, or Franchises AGENCIES: Department of Defense (DOD), General... approved information collection requirement concerning permits, authorities, or franchises for regulated..., Permits, Authorities, or Franchises, by any of the following methods: Regulations.gov : http://www...

  16. 78 FR 32945 - Amendments to Regulations Governing Ocean Transportation Intermediary Licensing and Financial...

    Science.gov (United States)

    2013-05-31

    ... may employ to carry on its business. The absence of a definition for ``principal'' where it refers to... services.'' 46 CFR Sec. 515.2(h)(5). The definition of ``advertisement'' is new along with a related new... their OTI principals) must include the OTI's name, license or registration number on all advertisements...

  17. Licensing of safety critical software for nuclear reactors. Common position of seven European nuclear regulators and authorised technical support organisations

    International Nuclear Information System (INIS)

    2007-01-01

    The major result of the work is the identification of consensus and common technical positions on a set of important licensing issues raised by the design and operation of computer-based systems used in Nuclear Power Plants for safety functions. The purpose is to introduce greater consistency and more mutual acceptance into current practices. To achieve these common positions, detailed consideration was paid to the licensing approaches followed in the different countries represented by the experts of the task force. The report is intended to be useful: - to coordinate regulators' and safety experts' technical viewpoints in the design of regulators' national policies and in revisions of guidelines; - as a reference in safety cases and demonstrations of safety of software based systems; - as guidance for system design specifications by manufacturers and major I and C suppliers on the international market. The task force decided at an early stage to focus attention on computer based systems used in Nuclear Power Plants for the implementation of safety functions; namely, those systems classified by the IAEA as 'Safety Systems'. Therefore, recommendations of this report - except those of chapter 1.11 - primarily address 'safety systems' and not 'safety related systems'. It was felt that the most difficult aspects of the licensing of digital programmable systems are rooted in the specific properties of the technology. The objective was therefore to delineate practical and technical licensing guidance, rather than discussing or proposing basic principles or requirements. The design requirements and the basic principles of nuclear safety in force in each member state are assumed to remain applicable. This report represents the consensus view achieved by the experts who contributed to the task force. It is the result of what was at the time of its initiation a first attempt at the international level to achieve consensus among nuclear regulators on practical methods for

  18. 16 CFR 1.8 - Nature, authority and use of trade regulation rules.

    Science.gov (United States)

    2010-01-01

    ... 16 Commercial Practices 1 2010-01-01 2010-01-01 false Nature, authority and use of trade regulation rules. 1.8 Section 1.8 Commercial Practices FEDERAL TRADE COMMISSION ORGANIZATION, PROCEDURES AND... Nature, authority and use of trade regulation rules. (a) For the purpose of carrying out the provisions...

  19. 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

  20. Dynamic assembly of Hda and the sliding clamp in the regulation of replication licensing

    OpenAIRE

    Kim, Jin S.; Nanfara, Michael T.; Chodavarapu, Sundari; Jin, Kyeong S.; Babu, Vignesh?M.?P.; Ghazy, Mohamed A.; Chung, Scisung; Kaguni, Jon M.; Sutton, Mark D.; Cho, Yunje

    2017-01-01

    Abstract Regulatory inactivation of DnaA (RIDA) is one of the major regulatory mechanisms of prokaryotic replication licensing. In RIDA, the Hda?sliding clamp complex loaded onto DNA directly interacts with adenosine triphosphate (ATP)-bound DnaA and stimulates the hydrolysis of ATP to inactivate DnaA. A prediction is that the activity of Hda is tightly controlled to ensure that replication initiation occurs only once per cell cycle. Here, we determined the crystal structure of the Hda?? clam...

  1. Medico-legal implications of sleep apnoea syndrome: Driving license regulations in Europe

    DEFF Research Database (Denmark)

    Alonderis, A.; Barbee, F.; Bonsignore, M.

    2008-01-01

    Background: Sleep apnoea syndrome (SAS), one of the main medical causes of excessive daytime sleepiness, has been shown to be a risk factor for traffic accidents. Treating SAS results in a normalized rate of traffic accidents. As part of the COST Action B-26, we looked at driving license regulati......Background: Sleep apnoea syndrome (SAS), one of the main medical causes of excessive daytime sleepiness, has been shown to be a risk factor for traffic accidents. Treating SAS results in a normalized rate of traffic accidents. As part of the COST Action B-26, we looked at driving license...... sleep apnoea syndrome is mentioned in 10 countries. A patient with untreated sleep apnoea is always considered unfit to drive. To recover the driving capacity, seven countries rely on a physician's medical certificate based on symptom control and compliance with therapy, whereas in two countries...... it is up to the patient to decide (on his doctor's advice) to drive again. Only FR requires a normalized electroencephalography (EEG)-based Maintenance of Wakefulness Test for professional drivers. Rare conditions (e.g., narcolepsy) are considered a driving safety risk more frequently than sleep apnoea...

  2. 14 CFR 1204.504 - Delegation of authority to grant leaseholds, permits, and licenses in real property.

    Science.gov (United States)

    2010-01-01

    ... the date specified by such notice. (iv) For any other reservations, exceptions, limitations, benefits... Engineering Division. (g) Services of the Corps of Engineers. In exercising the authority herein granted, the...

  3. 15 CFR 336.5 - Licenses.

    Science.gov (United States)

    2010-01-01

    ... 15 Commerce and Foreign Trade 2 2010-01-01 2010-01-01 false Licenses. 336.5 Section 336.5 Commerce and Foreign Trade Regulations Relating to Commerce and Foreign Trade (Continued) INTERNATIONAL TRADE... authorization in writing or by electronic notice to the importer and providing a copy of such authorization to...

  4. On the authority of the Federal Government to give directions in nuclear law licensing procedures - prerequisites and legal protection

    International Nuclear Information System (INIS)

    Wagner, H.

    1987-01-01

    Due to the differences about the future energy policies between the big political parties there is a growing confrontation between the Federal Government and some Laender about granting licences for the erection and operation of nuclear plants. On this background the author deals with the legal problem if a Land was directed by the Federal Government to grant the atomic licence and the Land would file an appeal. (WG) [de

  5. Qualification, training, licensing/authorization and retraining of operating personnel in nuclear power plants. Noteworthy topics identified by evaluation of the practices in countries of the European Communities

    International Nuclear Information System (INIS)

    Kraut, A.; Pfeffer, W.

    1987-01-01

    In the report EUR 10118 '' Qualification, training, licensing and retraining of operating shift personnel in nuclear power plants'' the current practice in the countries of the European Communities as well as the procedures and programmes applied in Sweden, Switzerland and the USA are outlined and evaluated. The intent was to derive fundamental and generally valid concepts concerning shift-staff training and other relevant aspects. Those items were identified that seemed to be noteworthy because they give some guidance on how to achieve and maintain the qualification of the shift staff of NPPs or how to improve the staffing of the control room. These noteworthy topics identified by evaluation of the practice in countries of the European Communities and also elsewhere are presented in the publication at hand. The report addresses the following topics: tasks of the shift personnel, nomenclature for different grades of the personnel; shift staffing and staffing of the control room; criteria for personnel selection when recruiting new shift staff; personnel qualification necessary for recruitment; training of shift personnel; retraining and preservation of qualification standards; training facilities, especially simulators; responsibility for training; licensing/authorization; retirement from shift work. Consideration of these more general aspects and concepts may lead to improvement in training. The job descriptions given in the Annex to the document are only intended to give a general understanding of the typical designations, tasks and responsibilities of shift staff

  6. Federal Trade Commission's authority to regulate marketing to children: deceptive vs. unfair rulemaking.

    Science.gov (United States)

    Pomeranz, Jennifer L

    2011-01-01

    Food and beverage marketing directed at children is of increasing concern to the public health and legal communities. The new administration at the Federal Trade Commission and abundant science on the topic make it a particularly opportune time for the government to reconsider regulating marketing directed at youth. This Article analyzes the Commission's authority to regulate food and beverage marketing directed at children under its jurisdiction over unfair and deceptive acts and practices to determine which avenue is most viable. The author finds that the Federal Trade Commission has the authority to regulate deceptive marketing practices directed at vulnerable populations. Although the Commission can issue individual orders, its remedial power to initiate rules would better address the pervasiveness of modern marketing practices. The Commission does not currently have the power to regulate unfair marketing to children; however, even if Congress reinstated this authority, the Commission's authority over deceptive marketing may be preferable to regulate these practices. Deceptive communications are not protected by the First Amendment and the deceptive standard matches the science associated with marketing to children. The Federal Trade Commission has the authority to initiate rulemaking in the realm of food and beverage marketing to children as deceptive communications in interstate commerce, in violation of the Federal Trade Commission Act. However, to effectuate this process, Congress would need to grant the Commission the authority to do so under the Administrative Procedures Act.

  7. Licensing issues

    International Nuclear Information System (INIS)

    Roberts, J.P.; Desell, L.J.; Birch, M.L.; Berkowitz, L.; Bader, J.F.

    1992-01-01

    To provide guidance for the Department of Energy's (DOE) Civilian Radioactive Waste Management Program, the Nuclear Regulatory Commission (NRC) has issued a draft regulatory guide on the Format and Content for the License Application for the High-Level Waste Repository (FCRG). To facilitate the development of the FCRG, NRC suggested that DOE use the draft guide as the basis for preparing an annotated outline for a license application. DOE is doing so using an iterative process called the Annotated Outline Initiative. DOE;s use of the Initiative will assist in achieving the desired incorporation of actual experience in the FCRG, contribute to the development of shared interpretation and understanding of NRC regulations, and provide other important programmatic benefits described in this paper

  8. 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

  9. Transition to e-government in Developing countries: The Case of Driver and Vehicle Licensing Authority (DVLA) e-Service Smart City Initiatives in Ghana

    DEFF Research Database (Denmark)

    Kofi Wireko, Joseph; Skouby, Knud Erik

    2016-01-01

    Most developing countries, especially in Africa are fighting corruption as a major barrier to development, and e-government is seen as a new way of addressing it. Besides generally being recognized as cost-efficient, e-government is thought to reduce corruption through increased transparency......, better accountability and, the disappearance of the “middle-man” in the acquisition of public services by the citizenry. This paper discusses the extent to which this has been achieved in Ghana by analyzing the implementation of e-government service of the Driver and Vehicle Licensing Authority (DVLA......) of Ghana using the “stages of growth” mode from a sociotechnical perspective. The outcome of the analysis suggests that the e-government service implementation by DVLA is still at its basic and rudimentary stage (Catalogue stage) and continuous presence of the “middle-man,” high level of corruption, lack...

  10. To License or Not to License Revisited: An Examination of State Statutes Regarding Private Investigators and Digital Examiners

    OpenAIRE

    Thomas Lonardo; Doug White; Alan Rea

    2009-01-01

    In this update to the previous year's study, 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 lice...

  11. 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)

  12. 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

  13. The exemption from the requirement of registration and/or licensing of some sources. machines and devices emitting ionizing and /or on ionizing radiation: a proposed draft for Israeli regulations

    Energy Technology Data Exchange (ETDEWEB)

    Schlesinger, T; Margaliot, M [Israel Atomic Energy Commission, Yavne (Israel). Soreq Nuclear Research Center

    1997-11-16

    The licensing and authorization of the import, purchase, distribution, transportation and application of radioactive materials and devices emitting ionizing and/or non-ionizing radiation are carried out in Israel by the Ministries of the Environment and of Health. The legal basis for file authority of these Ministries in radiation protection matters is file {sup P}harmacists Regulation- Radioactive Elements and Products Thereof, 1981 (revision 1994) (PRREPT). Licenses are issued by the Chief Radiation Executive (CUE) appointed by the Minister of the Environment and the Minister of Health. The Regulations include a clause which enables the CUE to exempt certain amounts of radioactive materials from file requirements laid down in the PRREPT. The exemption clause is general and does not indicate the types and amounts of radioactive material may be exempted. The proposed draft Israeli regulations are related to exemption of some sources, machines and devices emitting ionizing and non-ionizing radiation, wife a suggestion to extend file above mentioned exemption clause to include some machines and devices and to provide an explicit and detailed list of materials, sources and devices to be exempted. Among these are the following: (authors)

  14. The exemption from the requirement of registration and/or licensing of some sources. machines and devices emitting ionizing and /or on ionizing radiation: a proposed draft for Israeli regulations

    International Nuclear Information System (INIS)

    Schlesinger, T.; Margaliot, M.

    1997-01-01

    The licensing and authorization of the import, purchase, distribution, transportation and application of radioactive materials and devices emitting ionizing and/or non-ionizing radiation are carried out in Israel by the Ministries of the Environment and of Health. The legal basis for file authority of these Ministries in radiation protection matters is file P harmacists Regulation- Radioactive Elements and Products Thereof, 1981 (revision 1994) (PRREPT). Licenses are issued by the Chief Radiation Executive (CUE) appointed by the Minister of the Environment and the Minister of Health. The Regulations include a clause which enables the CUE to exempt certain amounts of radioactive materials from file requirements laid down in the PRREPT. The exemption clause is general and does not indicate the types and amounts of radioactive material may be exempted. The proposed draft Israeli regulations are related to exemption of some sources, machines and devices emitting ionizing and non-ionizing radiation, wife a suggestion to extend file above mentioned exemption clause to include some machines and devices and to provide an explicit and detailed list of materials, sources and devices to be exempted. Among these are the following: (authors)

  15. 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

  16. A Study on the regulation improvement through the analysis of domestic and international categorization and licensing process for large particle accelerator

    Energy Technology Data Exchange (ETDEWEB)

    Gwon, Da-Yeong; Jeon, Yeo-Ryeong; Kim, Yong-Min [Catholic University of Daegu, Gyeongsan (Korea, Republic of); Jung, Nam-Suk; Lee, Hee-Seock [POSTECH, Pohang (Korea, Republic of)

    2016-10-15

    Many foreign countries use separate criteria and regulation procedure according to the categorization of accelerators. In Korea, nuclear and radiation related facilities are divided into 4 groups: 1) Nuclear Reactor and related facilities, 2) Nuclear fuel cycle, nuclear material facilities, 3) Disposal and transport, 4) Radioisotope and radiation generating devices related facilities. All accelerator facilities are categorized as group 4 regardless of their size and type. For facilities that belong to group 1 and 2, Radiation Environmental Impact Assessment Report(REIR) and Preliminary Decommissioning Plan Report(PDPR) should be submitted in construction licensing stage, but there are no rules about above documents for large particle accelerator facilities. Facilities that belong to 4) RI and RG, only two documents of Radiation Safety Report(RSR) and Safety Control Regulation(SCR) are submitted in licensing stage. Because there is no detailed guidelines according to facilities type, properties of each facility are not considered in preparation and licensing process. If we set up the categorization of accelerator facilities, we can expect the effective and safe construction and operation of the large accelerator facilities on the licensing and operation process. Similarly to other counties' criteria, 50 MeV of particle energy could be used as energy band of large particle accelerator. According to categorization, it is necessary to adopt graded licensing stages and separated safety documents. In case of large particle accelerators, it is appropriate to divide the licensing stages to construction and operation. We currently submit PDPR in case of reactor and related facilities, nuclear fuel cycle, and nuclear material facilities. Depending on the energy of particle accelerators, it is necessary to prepare the decontamination and decommissioning for the decrease of current and future burden from radioactive waste. From the arrangement of separated guidelines on

  17. A Study on the regulation improvement through the analysis of domestic and international categorization and licensing process for large particle accelerator

    International Nuclear Information System (INIS)

    Gwon, Da-Yeong; Jeon, Yeo-Ryeong; Kim, Yong-Min; Jung, Nam-Suk; Lee, Hee-Seock

    2016-01-01

    Many foreign countries use separate criteria and regulation procedure according to the categorization of accelerators. In Korea, nuclear and radiation related facilities are divided into 4 groups: 1) Nuclear Reactor and related facilities, 2) Nuclear fuel cycle, nuclear material facilities, 3) Disposal and transport, 4) Radioisotope and radiation generating devices related facilities. All accelerator facilities are categorized as group 4 regardless of their size and type. For facilities that belong to group 1 and 2, Radiation Environmental Impact Assessment Report(REIR) and Preliminary Decommissioning Plan Report(PDPR) should be submitted in construction licensing stage, but there are no rules about above documents for large particle accelerator facilities. Facilities that belong to 4) RI and RG, only two documents of Radiation Safety Report(RSR) and Safety Control Regulation(SCR) are submitted in licensing stage. Because there is no detailed guidelines according to facilities type, properties of each facility are not considered in preparation and licensing process. If we set up the categorization of accelerator facilities, we can expect the effective and safe construction and operation of the large accelerator facilities on the licensing and operation process. Similarly to other counties' criteria, 50 MeV of particle energy could be used as energy band of large particle accelerator. According to categorization, it is necessary to adopt graded licensing stages and separated safety documents. In case of large particle accelerators, it is appropriate to divide the licensing stages to construction and operation. We currently submit PDPR in case of reactor and related facilities, nuclear fuel cycle, and nuclear material facilities. Depending on the energy of particle accelerators, it is necessary to prepare the decontamination and decommissioning for the decrease of current and future burden from radioactive waste. From the arrangement of separated guidelines on

  18. 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

  19. 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...

  20. License renewal in the United States

    International Nuclear Information System (INIS)

    Brons, Jack

    2002-01-01

    license renewal applications, and virtually every reactor in the United States is now expected to apply. License renewal is economically beneficial since the plants are fully amortized and operating and maintenance costs of an efficiently-operating plant is low. Continued operation of nuclear plants, by far the largest source of emission-free electricity generation in the U.S., will also bring environmental benefits. Nuclear plant operations avoided emissions of nearly 175 million metric tons of carbon dioxide in 2000, in addition to millions of tons of sulfur dioxide and nitrogen oxide. NEI continues to work with the NRC on generic principles and streamlining regulations, with the aim of further reducing both the time and the cost of license renewal. (author)

  1. Resolution 25/98 Regulation of Authorization of Practice Associated to the Radiations Ionizing Employment

    International Nuclear Information System (INIS)

    1998-01-01

    The present regulation has as objective to establish the general precepts that regulate the demands for the authorization of practices associated to the employment of ionizing radiations and their sources, with a view to guaranteeing the protection of the life, health, possessions and environment. Chapter I. is defined the objective and scope of the resolution, besides the terms and definitions. Chapter II, the Classification of the practices associated to the employment of the ionizing radiations. Chapter III try about the Regulatory Control of the practices and their sources. Chapter IV. the Procedures for the applications. Chapter V. procedure of Authorizations; and Chapter IV. Amendment, Modification, Renovation, Suspension and Renovation of Authorizations. Also a disposition referred to the validity of previous authorizations and 3 finals dispositions

  2. 15 CFR 335.5 - Licenses.

    Science.gov (United States)

    2010-01-01

    ... 15 Commerce and Foreign Trade 2 2010-01-01 2010-01-01 false Licenses. 335.5 Section 335.5 Commerce and Foreign Trade Regulations Relating to Commerce and Foreign Trade (Continued) INTERNATIONAL TRADE... its behalf by making such an authorization in writing or by electronic notice to the importer and...

  3. 31 CFR 560.508 - Telecommunications and mail transactions authorized.

    Science.gov (United States)

    2010-07-01

    ... 31 Money and Finance: Treasury 3 2010-07-01 2010-07-01 false Telecommunications and mail... REGULATIONS Licenses, Authorizations and Statements of Licensing Policy § 560.508 Telecommunications and mail... telecommunications and mail between the United States and Iran are authorized. For purposes of this section, the term...

  4. 31 CFR 585.522 - Donations of medical supplies authorized.

    Science.gov (United States)

    2010-07-01

    ... Security Council or a duly authorized body subordinate thereto to govern the shipment of medical supplies... 31 Money and Finance: Treasury 3 2010-07-01 2010-07-01 false Donations of medical supplies... SANCTIONS REGULATIONS Licenses, Authorizations, and Statements of Licensing Policy § 585.522 Donations of...

  5. 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)

  6. 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)

  7. 19 CFR 0.1 - Customs revenue function regulations issued under the authority of the Departments of the...

    Science.gov (United States)

    2010-04-01

    ... the authority of the Departments of the Treasury and Homeland Security. 0.1 Section 0.1 Customs Duties... TRANSFERRED OR DELEGATED AUTHORITY § 0.1 Customs revenue function regulations issued under the authority of... authority to prescribe all CBP regulations relating to customs revenue functions, except that the Secretary...

  8. Duty and role of Nuclear Regulation Authority facing a crucial moment

    International Nuclear Information System (INIS)

    Asaoka, Mie

    2013-01-01

    Duty of Nuclear Regulation Authority (NRA) was to restore public trust on nuclear regulation spoiled by the Fukushima nuclear accident. How applied such regulation as mandatory back-fitting based on latest knowledge and 40 year operational limit in principle became of great concern. Active faults issue on existing nuclear power station could be a touchstone. Safety side judgment and electric utilities side's proof responsibilities were required as more stringent criteria for active faults. The expert group had been working on assessment of fracture zones under the field survey. Reform of safety regulations should be done based on three important standpoints: (1) not business easiness but public safety was first (2) NRA keeping stance to judge its own safety standard and how NRA ought to be and (3) importance of public disclosure of information and participation in decision-making judging from greatness of public effects caused by nuclear disaster. (T. Tanaka)

  9. A Review of State Licensing Regulations to Determine Alignment with Best Practices to Prevent Human Norovirus Infections in Child-Care Centers.

    Science.gov (United States)

    Leone, Cortney M; Jaykus, Lee-Ann; Cates, Sheryl M; Fraser, Angela M

    2016-01-01

    Close, frequent contact between children and care providers in child-care centers presents many opportunities to spread human noroviruses. We compared state licensing regulations for child-care centers with national guidelines written to prevent human noroviruses. We reviewed child-care licensing regulations for all 50 U.S. states and the District of Columbia in effect in June 2015 to determine if these regulations fully, partially, or did not address 14 prevention practices in four topic areas: (1) hand hygiene, (2) exclusion of ill people, (3) environmental sanitation, and (4) diapering. Approximately two-thirds (8.9) of the 14 practices across all state regulations were partially or fully addressed, with few (2.6) fully addressed. Practices related to exclusion of ill people and diapering were fully addressed most often, while practices related to hand hygiene and environmental sanitation were fully addressed least often. Regulations based on guidelines for best practices are one way to prevent the spread of human noroviruses in child-care facilities, if the regulations are enforced. Our findings show that, in mid-2015, many state child-care regulations did not fully address these guidelines, suggesting the need to review these regulations to be sure they are based on best practices.

  10. 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

  11. 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

  12. Analysis of publications by the Nuclear Regulation Authority for the period 2000-2014

    International Nuclear Information System (INIS)

    Wallingre, G.V.; Carregado, M.A.; Barone, M.L.

    2015-01-01

    This paper analyzes the publication habits by the Nuclear Regulation Authority (ARN) of Argentina for the period 2000-2014, through indicators of volume, typology, language and co authorship. It makes focus on publications in academic journals and characterizes them by publication country, language and access, and at the same time measures their impact and visibility through their classification in the SJR (SCImago Journal Rank) and their Impact Factor. Finally, it makes an introduction of Open Access journals in which the ARN has published, and briefly describes this method of dissemination. (authors) [es

  13. PROCESS FOR LICENSE APPLICATION DEVELOPMENT FOR THE GEOLOGIC REPOSITORY

    International Nuclear Information System (INIS)

    DOUGLAS M. FRANKS AND NORMAN C. HENDERSON

    1997-01-01

    The Department of Energy (DOE), specifically the Office of Civilian Radioactive Waste Management (OCRWM) has been charged by the U.S. Congress, through the Nuclear Waste Policy Act (NWPA), with the responsibility for obtaining a license to develop a geologic repository. The NRC is the licensing authority for geologic disposal, and its regulations pertinent to construction authorization and license application are specified in 10 CFR Part 60, Disposal of High-Level Radioactive Wastes in Geologic Repositories, (section)60.21ff and (section)60.31ff. This paper discusses the process the Yucca Mountain Site Site Characterization Project (YMP) will use to identify and apply regulatory and industry guidance to development of the license application (LA) for a geologic repository at Yucca Mountain, Nevada. This guidance will be implemented by the ''Technical Guidance Document for Preparation of the License Application'' (TGD), currently in development

  14. Process for license application development for the geologic repository

    International Nuclear Information System (INIS)

    Franks, D.M.; Henderson, N.C.

    1998-01-01

    The Department of Energy (DOE), specifically the Office of Civilian Radioactive Waste Management (OCRWM) has been charged by the US Congress, through the Nuclear Waste Policy Act (NWPA), with the responsibility for obtaining a license to develop a geologic repository. The NRC is the licensing authority for geologic disposal, and its regulations pertinent to construction authorization and license application are specified in 10 CFR Part 60, Disposal of High-Level Radioactive Wastes in Geologic Repositories, section 60.21ff and section 60.31ff. This paper discusses the process the Yucca Mountain Site Characterization Project (YMP) will use to identify and apply regulatory and industry guidance to development of the license application (LA) for a geologic repository at Yucca Mountain, Nevada. This guidance will be implemented by the Technical Guidance Document for Preparation of the License Application (TGD), currently in development

  15. Parental Authority in the Regulation of the Civil Code in Quebec

    OpenAIRE

    Gavrilescu, Alin-Gheorghe

    2009-01-01

    The article analysis the institution of the parental authority, as it is regulated by the stipulations of the Civil Code in Quebec. After a short introduction, there are presented the parental rights and obligations regarding the minor’s person, the way of exerting and accomplishing them, the parental rights and obligations regarding the minor’s goods, the way of exerting and accomplishing them, the decline from the parental rights, and also the parental rights and obligations in case of adop...

  16. 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

  17. Conceptual frameworks of the notification, registration and licensing system applied in Cuba

    International Nuclear Information System (INIS)

    Jerez Verqueria, Pablo; Quevedo Garcia, Jose R.; Betancourt Hernadez, Luisa A.

    1996-01-01

    In our country, a safety regulations has been established whose objective is to establish the authorization system to apply and the requirements to fulfill by the license applications. The present work describes how such system has been conceptually conceived

  18. 47 CFR 90.751 - Minor modifications of Phase I, non-nationwide licenses.

    Science.gov (United States)

    2010-10-01

    ... SPECIAL RADIO SERVICES PRIVATE LAND MOBILE RADIO SERVICES Regulations Governing Licensing and Use of... relocate their initially authorized base station, i.e., locate their base station at a site other than its...

  19. JURISDICTION, COMPETENT JUDICIAL AUTHORITIES AND PROCEEDINGS UNDER REGULATION (EU NO 650/2012 ON SUCCESSION

    Directory of Open Access Journals (Sweden)

    Paula Poretti

    2016-01-01

    Full Text Available Novelties in the field of matters of succession brought by implementation of Regulation (EU No 650/2012 of the European Parliament and of the Council of 4 July 2012 on jurisdiction, applicable law, recognition and enforcement of decisions and acceptance and enforcement of authentic instruments in matters of succession and on the creation of a European Certificate of Succession are disscused in the paper. Especial emphasis is on jurisdiction, competent judicial authority and proceedings under Regulation on succession. In this sense, in the first part of the paper detailed analysis of provisions of Commission Implementing Regulation (EU No 1329/2014 of 9 December 2014 establishing the Forms referred to in Regulation (EU No 650/2012 of the European Parliament and of the Council on jurisdiction, applicable law, recognition and enforcement of decisions and acceptance and enforcement of authentic instruments in matters of succession and on the creation of a European Certificate of Succession and provisions of Croatian Law on implementation of Regulation (EU No 650/2012 of the European Parliament and of the Council on jurisdiction, applicable law, recognition and enforcement of decisions and acceptance and enforcement of authentic instruments in matters of succession and on the creation of a European Certificate of Succession is provided. In the second part of the paper case C404/14 Matoušková v. Republic of Czech is presented and difficulties in determining whether the case at issue falls within the scope of Regulation (EC No 2201/2003 or Regulation No 650/2012 on succession which could occur in matters of succession with cross-border implications are reffered to.

  20. ITER Safety and Licensing

    International Nuclear Information System (INIS)

    Girard, J-.P; Taylor, N.; Garin, P.; Uzan-Elbez, J.; GULDEN, W.; Rodriguez-Rodrigo, L.

    2006-01-01

    The site for the construction of ITER has been chosen in June 2005. The facility will be implemented in Europe, south of France close to Marseille. The generic safety scheme is now under revision to adapt the design to the host country regulation. Even though ITER will be an international organization, it will have to comply with the French requirements in the fields of public and occupational health and safety, nuclear safety, radiation protection, licensing, nuclear substances and environmental protection. The organization of the central team together with its partners organized in domestic agencies for the in-kind procurement of components is a key issue for the success of the experimentation. ITER is the first facility that will achieve sustained nuclear fusion. It is both important for the experimental one-of-a-kind device, ITER itself, and for the future of fusion power plants to well understand the key safety issues of this potential new source of energy production. The main safety concern is confinement of the tritium, activated dust in the vacuum vessel and activated corrosion products in the coolant of the plasma-facing components. This is achieved in the design through multiple confinement barriers to implement the defence in depth approach. It will be demonstrated in documents submitted to the French regulator that these barriers maintain their function in all postulated incident and accident conditions. The licensing process started by examination of the safety options. This step has been performed by Europe during the candidature phase in 2002. In parallel to the final design, and taking into account the local regulations, the Preliminary Safety Report (RPrS) will be drafted with support of the European partner and others in the framework of ITER Task Agreements. Together with the license application, the RPrS will be forwarded to the regulatory bodies, which will launch public hearings and a safety review. Both processes must succeed in order to

  1. IRIS pre-application licensing

    International Nuclear Information System (INIS)

    Carelli, Mario D.; Kling, Charles L.; Ritterbusch, Stanley E.

    2003-01-01

    This paper presents the approach to pre-application licensing by the International Reactor Innovative and Secure (IRIS), and advanced, integral reactor design with a thermal power of 1000 MW. The rationale for the pre-application licensing is discussed. Since IRIS technology is based on proven LWR experience, the project will rely on AP600/AP1000 precedent and will focus during the pre-application on long lead and novel items. A discussion of the evolution of the project to significantly reduce licensing issues is provided, followed by a summary of the IRIS safety-by-design which provides a formidable first step in the Defense in Depth approach. The effects of the safety-by-design, as well as of passive systems, on the IRIS safety will be investigated in a proposed testing program that will be reviewed by NRC during the pre-application. Documentation to be provided to NRC is discussed. Early design analyses indicate that the benefits of the IRIS safety-by-design approach are so significant that the basic premise of current emergency planning regulations (i.e., likelihood of core damage) will be reduced to the extent that special emergency response planning beyond the exclusion area boundary may not be needed. How this very significant outcome can be effected through a highly risk-informed licensing is discussed. (author)

  2. Stability in licensing requirements: a technical perspective

    International Nuclear Information System (INIS)

    Szalay, R.A.

    1978-01-01

    The serious difficulties encountered in the licensing procedure for nuclear power plants in the United States have resulted in the elaboration of a Bill on the siting and licensing of nuclear installations for the purpose of reforming the present system. The author fears, however, that this Bill will not reduce the complexity of present regulations and will be unable to reach the object sought which is to reduce the length of the procedure; he analyses the technical and political reasons underlying this situation, and in particular the role of the staff of the Nuclear Regulatory Commission. (NEA) [fr

  3. 31 CFR 545.519 - Payments and transfers authorized for goods and services exported to the territory of Afghanistan...

    Science.gov (United States)

    2010-07-01

    ...) SANCTIONS REGULATIONS Licenses, Authorizations and Statements of Licensing Policy § 545.519 Payments and... Taliban prior to the effective date. (a) Specific licenses may be issued on a case-by-case basis to permit... for the benefit of a person with respect to goods, software, technology, or services exported prior to...

  4. Organisational culture at the Radiation and Nuclear Safety Authority of Finland's department of Nuclear Reactor Regulation

    International Nuclear Information System (INIS)

    Reiman, T.; Norros, L.

    2001-03-01

    A case study to investigate the organisational culture of the regulatory authority was conducted at the Radiation and Nuclear Safety Authority of Finland's (STUK) Nuclear Reactor Regulation (YTO) - department. Organisational culture is defined as a pattern of shared basic assumptions, which are basically unconscious. Objectives of the study were to conceptualise and describe the main characteristics of YTO's organisational culture and to carry out a tentative core task analysis of the inspectors' work. A combination of quantitative and qualitative methods was used in the research. YTO's culture was identified as a hierarchy-focused culture with less emphasis on innovation or social support. However, the ideal values of the personnel emphasised also social support and goal setting. Ambiguous goals were felt by some personnel as increased uncertainty about the meaningfulness of one's job. Also a lack of feedback was mentioned. The core task analysis identified the critical functions of the regulatory practice. These functions specify the three roles of the regulatory authority, the expert role, the public role and the authority role. The culture must support the fulfilment of the requirements of all the three roles. Development needs in YTO's culture were identified and recommendations were made. (au)

  5. 20 CFR 726.103 - Application for authority to self-insure; effect of regulations contained in this part.

    Science.gov (United States)

    2010-04-01

    ... § 726.103 Application for authority to self-insure; effect of regulations contained in this part. As... 20 Employees' Benefits 3 2010-04-01 2010-04-01 false Application for authority to self-insure; effect of regulations contained in this part. 726.103 Section 726.103 Employees' Benefits EMPLOYMENT...

  6. 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

  7. Development of infrastructure for the regulatory authority to implement risk-informed regulation

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    It is important to assure the technical adequacy of probabilistic risk assessment (PRA) to implement risk-informed regulation of nuclear power plants (NPPs). JNES has been conducting various activities, such as development of PRA model, method, and data base, in order to assure the technical adequacy of PRA as development of the infrastructure for the regulatory authority to implement risk-informed regulation. In 2012, JNES updated the reliability data base used in PRA and improved PRA models to enhance the technical bases of PRA. In addition, JNES has been establishing the PRA model for fuel damage in the spent fuel storage pool in NPPs. As for improvement of PRA model for core damage in reactor, JNES conducted the study including feasibility of a simplified reliability model for digital I and C system developed by the digital I and C task group of OECD/NEA CSNI WGRISK by reproducing the sample calculation, and improvement of PRA models of individual NPPs in Japan. JNES is making effort to develop the procedures of internal fire PRA and internal flooding PRA. To improve the internal fire PRA, JNES is participating in OECD/NEA FIRE project to obtain the latest information and to validate and improve the fire propagation analysis codes and the parameters. JNES is establishing a method for analyzing internal influence due to flooding in NPPs, and this method is the base to develop the procedure of internal flooding PRA. (author)

  8. Waste management and licensing

    International Nuclear Information System (INIS)

    Dauk, W.

    1980-01-01

    It is the Court's consideration of the repercussions the regulation on waste management of Sect. 9a of the Atomic Energy Law will have, relating to the licensing of a plant according to Sect. 7 (2) of the Atomic Energy Law which is noteworthy. Overruling its former legal conception, the Administrative Court Schleswig now assumes, together with the public opinion, that the problem of waste management being brought to a point only with the initial operation of a nuclear power station is accordingly to be taken into account in line with the discretion of licensing according to Sect. 7 (2) of the Atomic Energy Law. In addition, the Administrative Court expressed its opinion on the extent to the right of a neighbour to a nuclear power station to file suit. According to the Sections 114 and 42 (2) of the rules of Administrative Courts it is true that a plaintiff cannot take action to set aside the licence because public interests have not been taken into account sufficiently, but he may do so because his own interests have not been included in the discretionary decision. The Administrative Court is reserved when qualifying the regulation on waste management with regard to the intensity of legal control. The Court is not supposed to replace controversial issues of technology and natural sciences on the part of the executive and its experts by its own assessment. According to the proceedings, the judicial review refers to the finding as to whether decisions made by authorities are suited - according to the way in which they were made - to guarantee the safety standard prescribed in Subdivision 3 of Sect. 7 (2) of the Atomic Energy Law. (HSCH) [de

  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. Regulations concerning licensing of nuclear reactor facilities and other nuclear installations, Decree No 7/9141, 6 January 1975

    International Nuclear Information System (INIS)

    1975-01-01

    This Decree lays down the licensing system for nuclear installations in Turkey and also sets up a Nuclear Safety Committee whose duty is to ensure that the requirements of this Decree are met. The Committee is made up of members of the Atomic Energy Commission specialized in reactors, nuclear safety, health physics, reactor physics as well as two experts respectively appointed by the Ministry of Health and Social Welfare and the Ministry of Energy and National Resources. (NEA) [fr

  11. Looking at the licensability of System 80+ in the UK

    International Nuclear Information System (INIS)

    Molnar, C.M.

    1993-01-01

    There are today no internationally-sanctioned nuclear power plant design or licensing guidelines, or acceptance criteria, available for a standard plant design that would have multi-national regulatory acceptability. On the contrary, a diversity of national regulations govern the design and licensing of nuclear power stations around the world. When licensing a nuclear facility in this environment, it is important for all parties (utility, designer and regulator) to recognise consciously that there are numerous solutions available to satisfy varying safety requirements. There is no one right-way - there are only trade-offs justified on safety, performance benefit and cost, which, taken together, fashion designs that conform to national licensing requirements. (Author)

  12. Licensing process for the power increase

    International Nuclear Information System (INIS)

    Perez P, R.; Mamani A, Y.R.; Salgado G, J.R.

    2006-01-01

    The licensing process for the power increase of a nuclear power station is presented, this includes the description of the effective normative framework, the attributions of the one Mexican regulator organism in nuclear matter, the definition and importance of the power level of a nuclear reactor for the safety studies. Also, the types of power increase according to its magnitude, and the regulator process that it includes the scope and the detail of the required information that it should be evaluated by the one regulator organism are discussed. Finally it offers a summary of the experience that one has in Mexico for this type of processes. (Author)

  13. 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.

  14. Important points not mentioned in 'interim report' of nuclear regulation authority

    International Nuclear Information System (INIS)

    Sato, Satoshi

    2014-01-01

    The Nuclear Regulation Authority (NRA) published the investigation and examination report on the unexplained issues raised by the National Diet Investigation Commission; 'Analysis of the TEPCO Fukushima Daiichi NPS Accident-Interim Report' in October 2014. The NRA had analyzed seven unexplained issues raised in the National Diet Investigation Commission report, and compiled the results. The author insisted the report should include related views and lessons learned and not just explain investigated and examined phenomena in order to contribute to ensuring nuclear safety in the world. As an example, the author selected the fifth of seven issues; 'operating status of the Isolation Condenser of Unit 1 (IC)'. The report concluded 'the AC-driven valve was closed since the AC power supply kept working even after DC power supply for the IC rupture detection circuit was lost. The isolation valves (2A and 2B) outside the PCV were closed, but isolation valves (1B and 4B) of the IC (system 'B') in the PCV remained open. However, the operating status (open/close) of isolation valves (1A and 4A) of the IC (system 'A') in the PCV is not clear. It is therefore necessary to continue analyses of this issue.' As related important points not mentioned in the report, the author described five points; (1) timing of functional losses of IC system, (2) obsolete aspect of equipment arrangement design (system separation), (3) single failure vulnerability, (4) rolling out issue of IC system to RCIC system (horizontal deployment) and (5) lessons learned from risk-informed 'black swan event'. (T. Tanaka)

  15. 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

  16. 31 CFR 500.585 - Payments for services rendered by North Korea to United States aircraft authorized.

    Science.gov (United States)

    2010-07-01

    ... North Korea to United States aircraft authorized. 500.585 Section 500.585 Money and Finance: Treasury... TREASURY FOREIGN ASSETS CONTROL REGULATIONS Licenses, Authorizations and Statements of Licensing Policy § 500.585 Payments for services rendered by North Korea to United States aircraft authorized. Payments...

  17. 75 FR 10997 - Cuban Assets Control Regulations; Sudanese Sanctions Regulations; Iranian Transactions Regulations

    Science.gov (United States)

    2010-03-10

    ... specific license, or otherwise exempt, the exportation of such services and software from the United States... services and software. Paragraph (c) of each of these two sections provides that specific licenses may be... Iranian Transactions Regulations to authorize the exportation of certain services and software incident to...

  18. Development of radioactive waste management licensing review assistant

    International Nuclear Information System (INIS)

    Wei-Whua Loa; Suan Chen; Wei-Chu Yu

    1992-01-01

    Regulations on radioactive waste disposal are now in urgent need due to our increasing consumption of electric power from nuclear origin. It is set forth that actually applying the regulations to evaluate the license application of new repositories for interim storage and final disposal of High-Level Waste and Low-Level Waste before the year of 2000. In the mean time, it is expected to establish the basis for the decision on issuing the license. The license review procedure can be very complicated, because too many factors must be taken into consideration. For the time being, licensing review is as much an art as it is a science. The authority usually faces three major problems; (1) the availability of domain expert, (2) maintaining of high quality and consistent reviews, and (3) the documentation of the review process. However, to maintain a more efficient, accurate, and systematic review procedure, and at the same time to reduce costs, the Artificial Intelligence (AI) techniques may be used. An expert system is designed as a radioactive waste management licensing review aid for the staff those are in charge of the license application. Tasks such as completeness checking, functional areas of review distribution, participation confirmation, knowledge acquisition, review comment collection, weighting calculation, and degree of satisfaction are considered. In this paper we will discuss the development of the radioactive waste management licensing review assistant

  19. 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)

  20. 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.)

  1. Organisational culture at the Radiation and Nuclear Safety Authority of Finland's Nuclear Reactor Regulation department

    International Nuclear Information System (INIS)

    Reiman, T.

    2001-01-01

    A case study to investigate the organisational culture of the regulatory authority was conducted at the Radiation and Nuclear Safety Authority of Finland's (STUK) Nuclear Reactor Regulation (YTO) department. Organisational culture is defined as a pattern of shared basic assumptions, which are basically unconscious. Objectives of the study were to conceptualise and describe the main characteristics of YTO's organisational culture and to carry out a tentative core task analysis of the inspectors' work. A combination of quantitative and qualitative methods was used in the research. In the first phase of the research, an organisational culture survey (FOCUS) was administered. It is base on a theory according to which organisations can be categorised into four main culture types, support-, innovation, goal- and rule-culture. It was tailored to better fit this kind of organisation on the basis of document analysis and preliminary interviews. Data was factor analysed and summated scales were formed. YTO's culture was identified as a hierarchy-focused (rule) culture with less emphasis on innovation, support or goals. However, the ideal values of the personnel emphasised also social support and goal setting. Ambiguous goals were felt by some personnel as increased uncertainty about the meaningfulness of one's job. Also a lack of feedback was mentioned as a weakness in YTO's culture. In the second phase of the research, a development workshop was carried out. The themes of the workshop were identified on the basis of the results of the first phase. Main targets for development that were identified in the workshop were human resources, goal setting and knowledge management. The ideal values of the personnel emphasised support and goal cultures. (orig.)

  2. A BWR licensing experience in the USA

    International Nuclear Information System (INIS)

    Powers, J.; Ogura, C.; Arai, K.; Thomas, S.; Mookhoek, B.

    2015-09-01

    The US-Advanced Boiling Water Reactor (A BWR), certified by the United States Nuclear Regulatory Commission (US NRC), is a third generation, evolutionary boiling water reactor design which is the reference for the South Texas Project Units 3 and 4 (STP3-4) Combined License Application (Cola). Nuclear Innovation North America (Nina) is the License Applicant for this new build project, and Toshiba is the selected primary technology contractor. The STP3-4 project has finished the US NRC technical review of the Cola through the final meeting of the Advisory Committee on Reactor Safeguards (ACRS), and the Final Safety Evaluation Report (FSER) is scheduled to be issued by the US NRC in the middle of 2015. The next steps are to support the Mandatory Hearing process, and voting by the NRC commissioners on the motion to grant the Combined License, which is scheduled beginning of 2016 according to US NRC schedule as of March 30, 2015. This paper summarizes the history and progress of the US-A BWR licensing, including the experiences of the Licensee, Nina, and Toshiba as the Epc team worked through the Code of Federal Regulations Title 10 (10-Cfr) Part 52 process, and provides some perspectives on how the related licensing material would also be of value within a 10-Cfr Part 50, two-step process to minimize schedule and financial risks which could arise from ongoing technical developments and regulatory reviews. (Author)

  3. A BWR licensing experience in the USA

    Energy Technology Data Exchange (ETDEWEB)

    Powers, J.; Ogura, C. [Toshiba America Nuclear Energy, Charlotte, North Carolina (United States); Arai, K. [Toshiba Corporation, Yokohama, Kanagawa (Japan); Thomas, S.; Mookhoek, B., E-mail: jim.powers@toshiba.com [Nuclear Innovation North America, Lake Jackson, Texas (United States)

    2015-09-15

    The US-Advanced Boiling Water Reactor (A BWR), certified by the United States Nuclear Regulatory Commission (US NRC), is a third generation, evolutionary boiling water reactor design which is the reference for the South Texas Project Units 3 and 4 (STP3-4) Combined License Application (Cola). Nuclear Innovation North America (Nina) is the License Applicant for this new build project, and Toshiba is the selected primary technology contractor. The STP3-4 project has finished the US NRC technical review of the Cola through the final meeting of the Advisory Committee on Reactor Safeguards (ACRS), and the Final Safety Evaluation Report (FSER) is scheduled to be issued by the US NRC in the middle of 2015. The next steps are to support the Mandatory Hearing process, and voting by the NRC commissioners on the motion to grant the Combined License, which is scheduled beginning of 2016 according to US NRC schedule as of March 30, 2015. This paper summarizes the history and progress of the US-A BWR licensing, including the experiences of the Licensee, Nina, and Toshiba as the Epc team worked through the Code of Federal Regulations Title 10 (10-Cfr) Part 52 process, and provides some perspectives on how the related licensing material would also be of value within a 10-Cfr Part 50, two-step process to minimize schedule and financial risks which could arise from ongoing technical developments and regulatory reviews. (Author)

  4. 7 CFR 400.207 - Representative licensing and certification.

    Science.gov (United States)

    2010-01-01

    ... insurance; (5) Liability insurance; or (6) Fire insurance and allied lines. The Contractor must submit... INSURANCE CORPORATION, DEPARTMENT OF AGRICULTURE GENERAL ADMINISTRATIVE REGULATIONS Agency Sales and Service... policies are issued, which license authorizes the sales of insurance in any one or more of the following...

  5. Regulations for the transport of radioactive material in Italy: the role of the Italian Competent Authority (ANPA)

    International Nuclear Information System (INIS)

    Orsini, A.; Trivelloni, S.

    1995-01-01

    In Italy four Ministries, Industry, Transport, Marine Merchandise and Interior, have the legal responsibility to issue and apply the transport safety regulations for radioactive material. ANPA, the National Agency for Environmental Protection, has the technical duty to issue the approval certificates and to support the various Ministries in authorizing carriers for all modes of transport, in updating the regulations and advising in the case of emergency conditions. ANPA is monitoring the quantity of radioactive material transported in Italy, the radiation doses of workers and public, and verifying the implementation of transport regulations through inspections of the carriers and during storage in transit and handling. (Author)

  6. 19 CFR 0.2 - All other CBP regulations issued under the authority of the Department of Homeland Security.

    Science.gov (United States)

    2010-04-01

    ... 19 Customs Duties 1 2010-04-01 2010-04-01 false All other CBP regulations issued under the authority of the Department of Homeland Security. 0.2 Section 0.2 Customs Duties U.S. CUSTOMS AND BORDER PROTECTION, DEPARTMENT OF HOMELAND SECURITY; DEPARTMENT OF THE TREASURY TRANSFERRED OR DELEGATED AUTHORITY...

  7. 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)

  8. Licensing activities for advanced reactors in NNC

    International Nuclear Information System (INIS)

    Chevalier, A.B.H.; Mustoe, J.; Walters, J.; Ingham, E.L.

    2001-01-01

    NNC has been involved in safety and licensing activities for advanced reactors for many years. Most recently NNC has been involved with national regulators or their representatives for the HTR (High Temperature Reactor) reactor and the possible siting of ITER (International Thermonuclear Experimental Reactor) within Europe. Commonalties between the two activities can be seen, even though one is a fission process and the other based on a completely new technology. Both have the potential to generate power at a very low overall exposure to the public and station staff, but both also need to demonstrate to the regulator the safety of a design which differs from the standard LWR practice. In both concepts passive design features provide a major part of the safety argument, but the detailed assessment and justification of these features in licensing terms still needs to be made. A number of critical safety issues can be identified, which generally apply to any advanced system. These are: Safety categorization, codes and standards; confinement or containment; ALARA; safety code modelling and data; Occupational Exposure; occupational exposures; decommissioning and waste; no evacuation, or no emergency plans. The UK is notable for a flexible licensing regime, which allows a safety case to be built up from first principles, where this is applicable. In addition, experience of licensing gas cooled, water cooled and liquid metal plant, as well as extensive experience outside the UK provides NNC with a unique insight into the different licensing methodologies which can be applied in the licensing process. This paper discusses some possible approaches which could be applied in order to satisfy regulatory demands when addressing the critical issues listed above. (author)

  9. 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

  10. 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

  11. 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

  12. 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

  13. 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

  14. 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

  15. 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

  16. 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

  17. National competent authorities. List no. 17. Regulations for the safe transport of radioactive material. 1985 edition (Safety series no.6 )

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1985-12-01

    Any national or international authority designated or otherwise recognised as such for any purpose in connection with the transport Regulations is known as a competent authority. In the Member States such a body has the responsibility for establishing national legislation to bring the Agency's transport Regulations into effect and for assuring compliance with its requirements. Depending on the national regulatory or institutional framework the functions of the competent authority may be assigned to one or more bodies. To assist Member States in implementing the transport Regulations and carrying out responsibility for compliance assurance, the IAEA continues to maintain this updated list of designated national competent authorities. Member States are annually requested to verify the list for correctness and completeness.

  18. National competent authorities. List no. 1. Regulations for the safe transport of radioactive materials. 1967 edition (Safety series no. 6)

    International Nuclear Information System (INIS)

    1967-04-01

    Any national or international authority designated or otherwise recognised as such for any purpose in connection with the transport Regulations is known as a competent authority. In the Member States such a body has the responsibility for establishing national legislation to bring the Agency's transport Regulations into effect and for assuring compliance with its requirements. Depending on the national regulatory or institutional framework the functions of the competent authority may be assigned to one or more bodies. To assist Member States in implementing the transport Regulations and carrying out responsibility for compliance assurance, the IAEA continues to maintain this updated list of designated national competent authorities. Member States are annually requested to verify the list for correctness and completeness

  19. National competent authorities. List no. 2. Regulations for the safe transport of radioactive materials. 1967 edition (Safety series no. 6)

    International Nuclear Information System (INIS)

    1968-08-01

    Any national or international authority designated or otherwise recognised as such for any purpose in connection with the transport Regulations is known as a competent authority. In the Member States such a body has the responsibility for establishing national legislation to bring the Agency's transport Regulations into effect and for assuring compliance with its requirements. Depending on the national regulatory or institutional framework the functions of the competent authority may be assigned to one or more bodies. To assist Member States in implementing the transport Regulations and carrying out responsibility for compliance assurance, the IAEA continues to maintain this updated list of designated national competent authorities. Member States are annually requested to verify the list for correctness and completeness

  20. National competent authorities. List no. 3. Regulations for the safe transport of radioactive materials. 1967 edition (Safety series no. 6)

    International Nuclear Information System (INIS)

    1970-06-01

    Any national or international authority designated or otherwise recognised as such for any purpose in connection with the transport Regulations is known as a competent authority. In the Member States such a body has the responsibility for establishing national legislation to bring the Agency's transport Regulations into effect and for assuring compliance with its requirements. Depending on the national regulatory or institutional framework the functions of the competent authority may be assigned to one or more bodies. To assist Member States in implementing the transport Regulations and carrying out responsibility for compliance assurance, the IAEA continues to maintain this updated list of designated national competent authorities. Member States are annually requested to verify the list for correctness and completeness

  1. National competent authorities. List no. 5. Regulations for the safe transport of radioactive materials. 1967 edition (Safety series no. 6)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1972-09-01

    Any national or international authority designated or otherwise recognised as such for any purpose in connection with the transport Regulations is known as a competent authority. In the Member States such a body has the responsibility for establishing national legislation to bring the Agency's transport Regulations into effect and for assuring compliance with its requirements. Depending on the national regulatory or institutional framework the functions of the competent authority may be assigned to one or more bodies. To assist Member States in implementing the transport Regulations and carrying out responsibility for compliance assurance, the IAEA continues to maintain this updated list of designated national competent authorities. Member States are annually requested to verify the list for correctness and completeness.

  2. National competent authorities. List no. 4. Regulations for the safe transport of radioactive materials. 1967 edition (Safety series no. 6)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1971-06-01

    Any national or international authority designated or otherwise recognised as such for any purpose in connection with the transport Regulations is known as a competent authority. In the Member States such a body has the responsibility for establishing national legislation to bring the Agency's transport Regulations into effect and for assuring compliance with its requirements. Depending on the national regulatory or institutional framework the functions of the competent authority may be assigned to one or more bodies. To assist Member States in implementing the transport Regulations and carrying out responsibility for compliance assurance, the IAEA continues to maintain this updated list of designated national competent authorities. Member States are annually requested to verify the list for correctness and completeness.

  3. National competent authorities. List no. 4. Regulations for the safe transport of radioactive materials. 1967 edition (Safety series no. 6)

    International Nuclear Information System (INIS)

    1971-06-01

    Any national or international authority designated or otherwise recognised as such for any purpose in connection with the transport Regulations is known as a competent authority. In the Member States such a body has the responsibility for establishing national legislation to bring the Agency's transport Regulations into effect and for assuring compliance with its requirements. Depending on the national regulatory or institutional framework the functions of the competent authority may be assigned to one or more bodies. To assist Member States in implementing the transport Regulations and carrying out responsibility for compliance assurance, the IAEA continues to maintain this updated list of designated national competent authorities. Member States are annually requested to verify the list for correctness and completeness

  4. National competent authorities. List no. 5. Regulations for the safe transport of radioactive materials. 1967 edition (Safety series no. 6)

    International Nuclear Information System (INIS)

    1972-09-01

    Any national or international authority designated or otherwise recognised as such for any purpose in connection with the transport Regulations is known as a competent authority. In the Member States such a body has the responsibility for establishing national legislation to bring the Agency's transport Regulations into effect and for assuring compliance with its requirements. Depending on the national regulatory or institutional framework the functions of the competent authority may be assigned to one or more bodies. To assist Member States in implementing the transport Regulations and carrying out responsibility for compliance assurance, the IAEA continues to maintain this updated list of designated national competent authorities. Member States are annually requested to verify the list for correctness and completeness

  5. National competent authorities. List no. 17. Regulations for the safe transport of radioactive material. 1985 edition (Safety series no.6 )

    International Nuclear Information System (INIS)

    1985-12-01

    Any national or international authority designated or otherwise recognised as such for any purpose in connection with the transport Regulations is known as a competent authority. In the Member States such a body has the responsibility for establishing national legislation to bring the Agency's transport Regulations into effect and for assuring compliance with its requirements. Depending on the national regulatory or institutional framework the functions of the competent authority may be assigned to one or more bodies. To assist Member States in implementing the transport Regulations and carrying out responsibility for compliance assurance, the IAEA continues to maintain this updated list of designated national competent authorities. Member States are annually requested to verify the list for correctness and completeness

  6. National competent authorities. List no. 3. Regulations for the safe transport of radioactive materials. 1967 edition (Safety series no. 6)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1970-06-01

    Any national or international authority designated or otherwise recognised as such for any purpose in connection with the transport Regulations is known as a competent authority. In the Member States such a body has the responsibility for establishing national legislation to bring the Agency's transport Regulations into effect and for assuring compliance with its requirements. Depending on the national regulatory or institutional framework the functions of the competent authority may be assigned to one or more bodies. To assist Member States in implementing the transport Regulations and carrying out responsibility for compliance assurance, the IAEA continues to maintain this updated list of designated national competent authorities. Member States are annually requested to verify the list for correctness and completeness.

  7. National competent authorities. List no. 2. Regulations for the safe transport of radioactive materials. 1967 edition (Safety series no. 6)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1968-08-01

    Any national or international authority designated or otherwise recognised as such for any purpose in connection with the transport Regulations is known as a competent authority. In the Member States such a body has the responsibility for establishing national legislation to bring the Agency's transport Regulations into effect and for assuring compliance with its requirements. Depending on the national regulatory or institutional framework the functions of the competent authority may be assigned to one or more bodies. To assist Member States in implementing the transport Regulations and carrying out responsibility for compliance assurance, the IAEA continues to maintain this updated list of designated national competent authorities. Member States are annually requested to verify the list for correctness and completeness.

  8. National competent authorities. List no. 1. Regulations for the safe transport of radioactive materials. 1967 edition (Safety series no. 6)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1967-04-01

    Any national or international authority designated or otherwise recognised as such for any purpose in connection with the transport Regulations is known as a competent authority. In the Member States such a body has the responsibility for establishing national legislation to bring the Agency's transport Regulations into effect and for assuring compliance with its requirements. Depending on the national regulatory or institutional framework the functions of the competent authority may be assigned to one or more bodies. To assist Member States in implementing the transport Regulations and carrying out responsibility for compliance assurance, the IAEA continues to maintain this updated list of designated national competent authorities. Member States are annually requested to verify the list for correctness and completeness.

  9. 31 CFR 586.510 - Transactions related to telecommunications authorized.

    Science.gov (United States)

    2010-07-01

    ... telecommunications authorized. 586.510 Section 586.510 Money and Finance: Treasury Regulations Relating to Money and... Licensing Policy § 586.510 Transactions related to telecommunications authorized. All transactions with respect to the receipt and transmission of telecommunications involving the FRY (S&M) are authorized. This...

  10. 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)

  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. 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)

  13. 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

  14. 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.

  15. The Swedish radiological environmental protection regulations applied in a review of a license application for a geological repository for spent nuclear fuel.

    Science.gov (United States)

    Andersson, Pål; Stark, Karolina; Xu, Shulan; Nordén, Maria; Dverstorp, Björn

    2017-11-01

    For the first time, a system for specific consideration of radiological environmental protection has been applied in a major license application in Sweden. In 2011 the Swedish Nuclear Fuel & Waste Management Co. (SKB) submitted a license application for construction of a geological repository for spent nuclear fuel at the Forsmark site. The license application is supported by a post-closure safety assessment, which in accordance with regulatory requirements includes an assessment of environmental consequences. SKB's environmental risk assessment uses the freely available ERICA Tool. Environmental media activity concentrations needed as input to the tool are calculated by means of complex biosphere modelling based on site-specific information gathered from site investigations, as well as from supporting modelling studies and projections of future biosphere conditions in response to climate change and land rise due to glacial rebound. SKB's application is currently being reviewed by the Swedish Radiation Safety Authority (SSM). In addition to a traditional document review with an aim to determine whether SKB's models are relevant, correctly implemented and adequately parametrized, SSM has performed independent modelling in order to gain confidence in the robustness of SKB's assessment. Thus, SSM has used alternative stylized reference biosphere models to calculate environmental activity concentrations for use in subsequent exposure calculations. Secondly, an alternative dose model (RESRAD-BIOTA) is used to calculate doses to biota that are compared with SKB's calculations with the ERICA tool. SSM's experience from this review is that existing tools for environmental dose assessment are possible to use in order to show compliance with Swedish legislation. However, care is needed when site representative species are assessed with the aim to contrast them to generic reference organism. The alternative modelling of environmental concentrations resulted in much lower

  16. 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)

  17. 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...

  18. Regulations for the transport of radioactive material in Italy: the role of the Italian Competent Authority (ANPA)

    International Nuclear Information System (INIS)

    Orsini, A.; Trivelloni, S.

    1995-01-01

    In Italy four Ministries, Industry, Transport, Marine Merchandise and Interior, have the legal responsibility to issue and apply the transport safety regulations for radioactive material. ANPA, the National Agency for Environmental Protection, has the technical duty to issue the approval certificates and to support the various Ministries in authorising carriers for all modes of transport, in updating the regulations and advising in the case of emergency conditions. ANPA is monitoring the quantity of radioactive material transported in Italy, the radiation doses of workers and public, and verifying the implementation of transport regulations through inspection of the carriers and during storage in transit and handling. (author)

  19. Development of radioactive waste management licensing review assistant

    International Nuclear Information System (INIS)

    Loa, W.W.; Chen, S.; Yu, W.C.; Peng, C.M.; Huang, C.L.; Lin, C.

    1992-01-01

    Regulations on radioactive waste disposal are now in urgent need due to our increasing consumption of electric power from nuclear origin. It is set forth that actually applying the regulations to evaluate the license application of new repositories for interim storage and final disposal fo High-Level Waste and Low-Level Waste before the year of 2000. In the mean time, it is expected to establish the basis for the decision on issuing the license. The license review procedure can be very complicated because too many factors must be taken into consideration. However, to maintain a more efficient, accurate, and systematic review procedure, and at the same time to reduce costs, the Artificial Intelligence (AI) techniques may be used. An expert system is designed as a radioactive waste management licensing review aid for the staff those are in charge of the license application. Tasks such as completeness checking, functional areas of review distribution, participation confirmation, knowledge acquisition, review comment collection, weighting calculation, and degree of satisfaction are considered. In this paper the authors will discuss the development of the radioactive waste management licensing review assistant

  20. 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

  1. The Texas concurrent characterization, licensing, and development process

    Energy Technology Data Exchange (ETDEWEB)

    Avant, R.V. Jr. [Texas Low-Level Radioactive Waste Disposal Authority, Austin, TX (United States)

    1993-03-01

    The 72nd Texas Legislature specifically delineated a 400-square-mile area in southeast Hudspeth County where siting activities would be limited. The Authority was given unprecedented powers of property access and eminent domain and expanded budget authority to conduct site selection, characterization, and licensing. In the summer of 1991, the Authority identified five general siting areas in the prescribed region, and in the fall of 1991, the Authority narrowed the siting area to one large ranch composed of about 16,000 acres--called the Faskin Ranch. Site characterization began in 1991 and will be complete by September 1993. In September 1991, Authority staff began preparing the license application and included all available information on the Faskin Ranch. At its February meeting, the Authority`s board directed staff to submit the license application to the Texas Water Commission (the new Texas radiation control agency). The license application was submitted on March 2, 1992, and on April 15, 1992, the Commission determined that the application was sufficiently complete to begin review. Discrete technical packages such as groundwater hydrology, surface water hydrology, design, etc., will be submitted to the agency for review on the completion of each package. A schedule has been developed to allow the regulators the maximum time possible to review critical technical areas while minimizing the total review period.

  2. 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...

  3. 14 CFR 385.17 - Authority of the Assistant General Counsel for Regulation and Enforcement.

    Science.gov (United States)

    2010-01-01

    ..., DEPARTMENT OF TRANSPORTATION (AVIATION PROCEEDINGS) ORGANIZATION STAFF ASSIGNMENTS AND REVIEW OF ACTION UNDER ASSIGNMENTS Assignment of Functions to Staff Members § 385.17 Authority of the Assistant General Counsel for...

  4. Exchange of information between nuclear safety authorities: Policy of the French regulator

    International Nuclear Information System (INIS)

    Asty, Michel

    2000-01-01

    Full text: The decree setting up the Nuclear Safety Authority in 1973 entrusted it with international assignments whose objectives are still valid: - develop exchanges of information with foreign counterparts on regulatory systems and practices, on problems encountered in the nuclear safety field and on provisions made, with a view to enhancing its approach, and - becoming better acquainted with the actual operating practice of these Safety Authorities from which lessons could be learned for its own working procedures; - improving its position in the technical discussions with the French operators, since its arguments would be strengthened by practical knowledge of conditions abroad; - make known and explain the French approach and practices in the nuclear safety field and provide information on measures taken to deal with the problems encountered. This approach has several objectives: - promote the circulation of information on French positions on certain issues, such as very low level waste, for instance; - assist some countries wishing to create or modify their Nuclear Safety Authority, such as countries of the former USSR, the Central and Eastern European countries, and emerging countries on other continents; - help, when requested, foreign Safety Authorities required to issue permits for nuclear equipment of French origin; - provide the countries concerned with all relevant information on French nuclear installations located near their frontiers. Examples are given on the way the French Nuclear Safety Authority implements these objectives. (author)

  5. 78 FR 76738 - Updated Statements of Legal Authority for the Export Administration Regulations

    Science.gov (United States)

    2013-12-19

    ... DEPARTMENT OF COMMERCE Bureau of Industry and Security 15 CFR Parts 730, 732, 734, 736, 738, 740... Administration Regulations AGENCY: Bureau of Industry and Security, Commerce. ACTION: Final rule. SUMMARY: This... INFORMATION CONTACT: William Arvin, Regulatory Policy Division, Bureau of Industry and Security, Telephone...

  6. PTIP chromatin regulator controls development and activation of B cell subsets to license humoral immunity in mice

    DEFF Research Database (Denmark)

    Su, Dan; Vanhee, Stijn; Soria, Rebeca

    2017-01-01

    B cell receptor signaling and downstream NF-κB activity are crucial for the maturation and functionality of all major B cell subsets, yet the molecular players in these signaling events are not fully understood. Here we use several genetically modified mouse models to demonstrate that expression...... of the multifunctional BRCT (BRCA1 C-terminal) domain-containing PTIP (Pax transactivation domain-interacting protein) chromatin regulator is controlled by B cell activation and potentiates steady-state and postimmune antibody production in vivo. By examining the effects of PTIP deficiency in mice at various ages during...... ontogeny, we demonstrate that PTIP promotes bone marrow B cell development as well as the neonatal establishment and subsequent long-term maintenance of self-reactive B-1 B cells. Furthermore, we find that PTIP is required for B cell receptor- and T:B interaction-induced proliferation, differentiation...

  7. Systems engineering and the licensing of Small Modular Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Kulesa, T., E-mail: tkulesa@us.ibm.com [IBM, Philidelphia, Pennsylvania (United States); Soderholm, K., E-mail: Kristiina.Soderholm@fortum.com [Fortum Power (Finland); Fechtelkotter, P., E-mail: pfech@us.ibm.com [IBM, Boston, Massacheusets (United States)

    2014-07-01

    Both global warming and the need for dependable sources of energy continue to make nuclear power generation an appealing option. But a history of cost overruns, project delays, and environmental disaster has pushed the industry to innovate and design a more flexible, scalable, and safe source of nuclear energy - the small modular reactor. Innovation in generation technology creates disruption in already complex licensing and regulatory processes. This paper discusses how the application of systems engineering and requirements management can help combat confusion, rework, and efficiency problems across the engineering and compliance life cycle. The paper is based on the PhD Dissertation 'Licensing Model Development for Small Modular Reactors (SMRs) - Focusing on Finnish Regulatory Framework', approved in 2013. The result of the study gives recommendations and tools to develop and optimize the licensing process for SMRs. The most important SMR-specific feature, in terms of licensing, is the modularity of the design. Here the modularity indicates multi-module SMR designs, which creates new challenges in the licensing process. Another feature impacting licensing feasibility is the plan to build many standardized power plants in series and use factory-fabricated modules to optimize the construction costs. SMR licensing challenges are under discussion in many international forums, such as World Nuclear Association Cooperation in Reactor Design Evaluation and Licensing Small Modular Reactor group (WNA CORDEL SMR) group and IAEA INPRO regulators' forum. This paper also presents an application of the new licensing process using Systems Engineering, Requirements Management, and Project Management practices and tools. (author)

  8. Systems engineering and the licensing of Small Modular Reactors

    International Nuclear Information System (INIS)

    Kulesa, T.; Soderholm, K.; Fechtelkotter, P.

    2014-01-01

    Both global warming and the need for dependable sources of energy continue to make nuclear power generation an appealing option. But a history of cost overruns, project delays, and environmental disaster has pushed the industry to innovate and design a more flexible, scalable, and safe source of nuclear energy - the small modular reactor. Innovation in generation technology creates disruption in already complex licensing and regulatory processes. This paper discusses how the application of systems engineering and requirements management can help combat confusion, rework, and efficiency problems across the engineering and compliance life cycle. The paper is based on the PhD Dissertation 'Licensing Model Development for Small Modular Reactors (SMRs) - Focusing on Finnish Regulatory Framework', approved in 2013. The result of the study gives recommendations and tools to develop and optimize the licensing process for SMRs. The most important SMR-specific feature, in terms of licensing, is the modularity of the design. Here the modularity indicates multi-module SMR designs, which creates new challenges in the licensing process. Another feature impacting licensing feasibility is the plan to build many standardized power plants in series and use factory-fabricated modules to optimize the construction costs. SMR licensing challenges are under discussion in many international forums, such as World Nuclear Association Cooperation in Reactor Design Evaluation and Licensing Small Modular Reactor group (WNA CORDEL SMR) group and IAEA INPRO regulators' forum. This paper also presents an application of the new licensing process using Systems Engineering, Requirements Management, and Project Management practices and tools. (author)

  9. The comparison of license management procedure for nuclear power plant in China and United States

    International Nuclear Information System (INIS)

    Yu Zusheng

    2006-01-01

    'Tow steps' license management procedure for nuclear power plant has been performed bas- ted on the requirement of 10CFR Part50-DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES in United States since last century fifties. In order to ulterior reduce the risk of investment and technical for new construction nuclear power plants, new regulations 'One step' license management procedure-10CFR Part52-EARLY SITE PERMITS; STANDARD DESIGN CERTIFICATIONS; AND COMBINED LICENSES FOR NUCLEAR POWER PLANTS issued in 1989. The new regulations has been adopted by new design of nuclear power plant, for example AP1000. ‘The similar tow steps’ license management procedure for nuclear power plant has been performed basted on the requirement of HAFO01/01 Rules for the Implementation of Regulations on the Safety Regulation for Civilian Nuclear Installations of the People's Re- public of China Part One: Application and Issuance of Safety License for Nuclear Power Plant (December 1993) in China since last century nineties. This article introduces and compares the requirements and characteristics of above license management procedure for nuclear power plant in China and United States. (author)

  10. 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.

  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. Introduction of regulatory and licensing procedures of some OECD countries in the field of decommissioning

    International Nuclear Information System (INIS)

    Benedekfi, O.; Zagyvai, P.; Czifrus, S.; Ormai, P.; Danko, G.

    2001-01-01

    In the OECD countries more than 50 nuclear power plants will have to be closed in the beginning of the next century since their licenses expire. For this reason it is very important to establish reasonable regulations in the field of decommissioning. In this poster firstly we define the basic principles related to decommissioning. Then we account on our survey of the situation of the regulatory and licensing procedures in some OECD countries. Finally we compare the results. (authors)

  13. Guidelines for authorities and operators from the EURATOM regulation according to nuclear safety

    International Nuclear Information System (INIS)

    Karpenstein, Ulrich

    2010-01-01

    At 22nd July, 2009 the guideline 2009/71/EURATOM on a community framework for the nuclear security of nuclear installations comes into effect. A lot of regulations of this guideline intervene very deeply in the competencies of the member states. In acknowledgment of the national responsibility for nuclear security, the guideline grants large free space to the member states. Thereby, the guideline aims at a general legal framework and a mutual learning process off.

  14. A Certificate Authority (CA-based cryptographic solution for HIPAA privacy/security regulations

    Directory of Open Access Journals (Sweden)

    Sangram Ray

    2014-07-01

    Full Text Available The Health Insurance Portability and Accountability Act (HIPAA passed by the US Congress establishes a number of privacy/security regulations for e-healthcare systems. These regulations support patients’ medical privacy and secure exchange of PHI (protected health information among medical practitioners. Three existing HIPAA-based schemes have been studied but appear to be ineffective as patients’ PHI is stored in smartcards. Moreover, carrying a smartcard during a treatment session and accessing PHI from different locations results in restrictions. In addition, authentication of the smartcard presenter would not be possible if the PIN is compromised. In this context, we propose an MCS (medical center server should be located at each hospital and accessed via the Internet for secure handling of patients’ PHI. All entities of the proposed e-health system register online with the MCS, and each entity negotiates a contributory registration key, where public-key certificates issued and maintained by CAs are used for authentication. Prior to a treatment session, a doctor negotiates a secret session key with MCS and uploads/retrieves patients’ PHI securely. The proposed scheme has five phases, which have been implemented in a secure manner for supporting HIPAA privacy/security regulations. Finally, the security aspects, computation and communication costs of the scheme are analyzed and compared with existing methods that display satisfactory performance.

  15. Scientific Method and the Regulation of Health and Nutritional Claims by the European Food Safety Authority

    Science.gov (United States)

    Hoad, Darren

    2011-01-01

    The protection of European consumers from the false or misleading scientific and nutritional claims of food manufacturers took a step forward with the recent opinions of the European Food Safety Authority (EFSA). As a risk assessment agency, the EFSA recently assessed and rejected a vast number of food claim forcing the withdrawal of many claims…

  16. Certificate authority collapse: regulating systemic vulnerabilities in the HTTPS value chain

    NARCIS (Netherlands)

    Arnbak, A.M.; van Eijk, N.A.N.M.

    2012-01-01

    Recent breaches and malpractices at several Certificate Authorities (CA’s) have led to a global collapse of trust in these central mediators of Hypertext Transfer Protocol Secure (HTTPS) communications. Given our dependence on secure web browsing, the security of HTTPS has become a top priority in

  17. The gas and electric power markets opening in Europe, the implementation of the regulation authorities

    International Nuclear Information System (INIS)

    2001-12-01

    Because the gas and the electric power are not simple goods, the opening of their market needs a whole reflexion where the governments must be involved. To analyse this opening, this report presents in a first part the traditional organization of the gas and electric power sectors marked by the strong presence of the government and the end of this organization at the end of the years 1980. It details then the new regulation, the operators and the effects of the competition. In a last part it provides propositions for the institutional framework in France. (A.L.B.)

  18. 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

  19. 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.

  20. Television food marketing to children revisited: the Federal Trade Commission has the constitutional and statutory authority to regulate.

    Science.gov (United States)

    Pomeranz, Jennifer L

    2010-01-01

    The evidence reveals that young children are targeted by food and beverage advertisers but are unable to comprehend the commercial context and persuasive intent of marketing. Although the First Amendment protects commercial speech, it does not protect deceptive and misleading speech for profit. Marketing directed at children may fall into this category of unprotected speech. Further, children do not have the same First Amendment right to receive speech as adults. For the first time since the Federal Trade Commission's original attempt to regulate marketing to children in the 1970s (termed KidVid), the political, scientific, and legal climate coalesce to make the time well-suited to reevaluate the FTC's authority for action. This paper analyzes the constitutional authority for the FTC to regulate television food marketing directed at children as deceptive in light of the most robust public health evidence on the subject.

  1. 7 CFR 46.6 - License fees.

    Science.gov (United States)

    2010-01-01

    ... Regulations of the Department of Agriculture AGRICULTURAL MARKETING SERVICE (Standards, Inspections, Marketing Practices), DEPARTMENT OF AGRICULTURE MARKETING OF PERISHABLE AGRICULTURAL COMMODITIES REGULATIONS (OTHER... commission merchants, brokers, and dealers (other than grocery wholesalers and retailers) the annual license...

  2. 7 CFR 46.3 - License required.

    Science.gov (United States)

    2010-01-01

    ... Regulations of the Department of Agriculture AGRICULTURAL MARKETING SERVICE (Standards, Inspections, Marketing Practices), DEPARTMENT OF AGRICULTURE MARKETING OF PERISHABLE AGRICULTURAL COMMODITIES REGULATIONS (OTHER... considered to result in separate firms and, therefore, do not require separate licenses. ...

  3. 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

    practices have been investigated as possibly suitable for use in nuclear licensing. All of the current licensing processes were found to be quite heavy and time-consuming and further streamlining could be possible without compromising safety or the need for public participation in the licensing process. Some examples of the modification possibilities for SMR applications are discussed. A profound discussion on SMR-specific licensing models, and on ways to simplify and harmonize them, will be needed in the near future in Europe too. This would be a natural continuation to the harmonization efforts underway for existing and new large reactors. (author)

  4. The Legal Regulation Of The Substitution Of The Budgetary Credit Release Authority In Exceptional Conditions

    Directory of Open Access Journals (Sweden)

    Ionel Bostan

    2016-03-01

    Full Text Available The purpose of our endeavour is to bring into the light of debates the situation that might exceptionally occur at the level of administrative territorial authority (ATU – villages, cities, municipalities and counties when it is affected the budgetary activity because the mayor/chairman of CC (County Council is unable to exert its mandate, the LC (Local County/CC is dissolved and the secretary position of the ATU is vacant. The discussion is focused on the legislative solution adopted by the Government through the Emergency Order, establishing the possibility according to which the prefect can name a person – by detachment – as secretary of the LC/CC. At the same time, it was also identified the solution for preventing a budgetary obstruction caused by the existence of the deliberative authority dissolution state which consists in the enactment of application in the current financial year of the ultimate budget, updated with the allocated amounts in the current year coming from the state budget or other budgets, respecting the monthly expenditures limit of 1/12 of this total budget.

  5. 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

  6. 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)

  7. Safety performance indicators used by the Russian Safety Regulatory Authority in its practical activities on nuclear power plant safety regulation

    International Nuclear Information System (INIS)

    Khazanov, A.L.

    2005-01-01

    The Sixth Department of the Nuclear, Industrial and Environmental Regulatory Authority of Russia, Scientific and Engineering Centre for Nuclear and Radiation Safety process, analyse and use the information on nuclear power plants (NPPs) operational experience or NPPs safety improvement. Safety performance indicators (SPIs), derived from processing of information on operational violations and analysis of annual NPP Safety Reports, are used as tools to determination of trends towards changing of characteristics of operational safety, to assess the effectiveness of corrective measures, to monitor and evaluate the current operational safety level of NPPs, to regulate NPP safety. This report includes a list of the basic SPIs, those used by the Russian safety regulatory authority in regulatory activity. Some of them are absent in list of IAEA-TECDOC-1141 ('Operational safety performance indicators for nuclear power plants'). (author)

  8. 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)

  9. 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)

  10. 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

  11. The Role of Digital Certificates in EGoverning. The Case of the Romanian Regulation and Surveillance Authority

    Directory of Open Access Journals (Sweden)

    Andra Marin

    2012-08-01

    Full Text Available The implementation of electronic governance related projects implies user authentication,accounts activation and personal data verification. Certain public services, particularly thoseinvolving financial transactions or statements, require a high security level. The use of the PKI technology and, consequently, of digital signatures, constitutes the most viable solution, meeting the required security standards, protecting, on the one hand, the signatory’s identity, and, on the other hand, the integrity of the transmitted message. Due to the use of the digital certificate, the development of online public services is now possible, especially since it meets the requirements of security standards, but also because it is highly trusted by users. This article intends to analyze the impact of the digital certificate on the improvement of communication between state authorities, including specific transactional relations, and also to consider its influence on security improvement of dataflow. The study demonstrates that the digital certificate is closely connected to the information society, directly determining the dynamics of the development of new applications that provide a better interface between the state and its citizens.

  12. License agreement, employee work

    OpenAIRE

    Poncová, Veronika

    2012-01-01

    The rigorous thesis is focused on license agreement and employee work. The aim of the thesis is not only an analysis of the use of a copyrighted work by a person different from the author of the work, but also an analysis of the performance of copyright by a person different from the author of the work. The thesis consists of five chapters. The opening chapter provides a summary of the notion of copyright, its sources at the national and international levels, but also the European Union legis...

  13. Licensing fees in the district heating industry; Gestattungsentgelte in der Fernwaermewirtschaft

    Energy Technology Data Exchange (ETDEWEB)

    Fricke, Norman [Jena Univ. (Germany)

    2009-10-15

    By means of licensing agreements municipalities grant the right to the district heating suppliers to use their properties with or without fees for the construction of district heating pipelines. Contrary to the power industry or gas industry, this type of contract is not regulated by special legal and price-legal regulations. Often an uncertainty exists whether and in which amount the municipalities may require a return for the right of utilization. In particular, this is valid if municipalities make the extension of discontinued licensing agreements dependent on the agreement of higher license fees. The general review under consideration reports on any legal limits of the amount of the licence fees. At the same time, a reference to licence fees in the power sector and gas sector is performed. In addition, the author reports on the law historical and law political background of license fees.

  14. 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)

  15. Design change management in regulation of nuclear fleets: World nuclear association's working groups on Cooperation in Reactor Design Evaluation and Licensing (CORDEL)

    International Nuclear Information System (INIS)

    Swinburn, R.; Borysova, I.; Waddington, J.; Head, J. G.; Raidis, Z.

    2012-01-01

    The 60 year life of a reactor means that a plant will undergo change during its life. To ensure continuing safety, changes must be made with a full understanding of the design intent. With this aim, regulators require that each operating organisation should have a formally designated entity responsible for complete design knowledge in regard to plant safety. INSAG-19 calls such an entity 'Design Authority'. This requirement is difficult to achieve, especially as the number of countries and utilities operating plants increases. Some of these operating organisations will be new, and some will be small. For Gen III plants sold on a turnkey basis, it is even more challenging for the operating company to develop and retain the full knowledge needed for this role. CORDEL's Task Force entitled 'Design Change Management' is investigating options for effective design change management with the aim to support design standardization throughout a fleet's lifetime by means of enhanced international cooperation within industry and regulators. This paper starts with considering the causes of design change and identifies reasons for the increased beneficial involvement of the plant's original vendor in the design change process. A key central theme running through the paper is the definition of responsibilities for design change. Various existing mechanisms of vendor-operator interfaces over design change and how they are managed in different organisational and regulatory environments around the world are considered, with the functionality of Owners Groups and Design Authority being central. The roles played in the design change process by vendors, utilities, regulators, owners' groups and other organisations such as WANO are considered The aerospace industry approach to Design Authority has been assessed to consider what lessons might be learned. (authors)

  16. 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...

  17. Assessment and improvement on system of licensing for work with ionizing radiation in China

    International Nuclear Information System (INIS)

    Sun Xiaobo

    1998-01-01

    The article outlined regulations, authorities and responsibilities for licensing in China. The health departments at provincial level issue the license certificates to the units engaging in the production, use or sale of radioisotopes or apparatus equipped with radiation source or radiation-emitting apparatus, and have the duty of supervising and monitoring the security about radiation work. For the particular dangers of radiation sources, there is deficiency and shortage of the current licensing system, such as ignorance of the importance of keeping detail records about sources, poor communications among every health department, poor actions to prevent illegal and secret radiation work such as secret use and sale. We are going to improve our licensing system by hardware (computer technology) and software (management). (author)

  18. 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

  19. IAEA news: • Newcomer countries face common challenges in nuclear infrastructure development. • Safety and licensing requirements for small modular reactors: IAEA hosts first workshop for regulators. • IAEA reaches milestone in disposal of radioactive sources

    International Nuclear Information System (INIS)

    Kollar, Lenka; Dyck, Elisabeth; Dixit, Aabha; Gaspar, Miklos; Gil, Laura

    2016-01-01

    • Newcomer countries face common challenges in nuclear infrastructure development: Countries embarking on a nuclear power programme need to make sure that the development of their legal, regulatory and support infrastructure keeps pace with the construction of the power plant itself. This is the only way to ensure that the programme proceeds in a safe, secure and sustainable way, concluded participants of a workshop on nuclear power infrastructure development hosted at the IAEA last February. • Safety and licensing requirements for small modular reactors: IAEA hosts first workshop for regulators: A new generation of advanced, prefab nuclear power reactors called small modular reactors (SMRs) could be licensed and hit the market as early as 2020, and the IAEA is helping regulators prepare for their debut. In a series of workshops that began earlier this year, the IAEA is working closely with regulators on approaches to safety and licensing ahead of potential SMR deployment worldwide. • IAEA reaches milestone in disposal of radioactive sources: Successful tests of a promising technology for moving and storing low level radioactive sealed sources are paving the way for a new disposal method for dealing with small volumes of radioactive waste around the world. The method, which involves placing and covering sealed sources in a narrow hole a few hundred metres deep, would allow countries to safely and securely take charge of their own disused radioactive sources. The proof of concept for the technology was tested in Croatia late last year — without the use of actual radioactive material.

  20. CANFLEX-NU fuel licensing status and issues in Korea

    International Nuclear Information System (INIS)

    Geun-Sun Auh; Jun-Sang Park; Sweng-Woong Woo; Yong-Ho Ryu

    1999-01-01

    The CANFLEX-NU Fuel Design Report (FDR) for Wolsung 1,2,3,4 was submitted for licensing review in July 1996. The FDR contains sections of fuel rod design, fuel bundle design, nuclear design and thermal-hydraulic design. Each section describes the design bases, design methodology and design evaluation results showing that the design bases are met. The CANFLEX-NU fuel design is not finalized yet in Korean licensing point of view. For example, among others, new Xc-BL correlation is needed to be developed, fuel rod gap reduction effect is to be considered in the Critical Heat Flux, more information for power ramp defect of fuel rod especially in the end-cap weld region is needed in the fuel rod design, and enough data are not available in irradiated conditions in the fuel rod and bundle designs. The specific detailed technical licensing issues and their backgrounds are explained for the CANFLEX-NU FDR in Korea. The Korean nuclear regulation environment is changing due to the Korean government policy of overall regulation reduction. The contents and timetables of Korean nuclear regulation changes are also explained for new fuel licensing. (author)

  1. German rules and regulations eith special reference to application documents

    International Nuclear Information System (INIS)

    Kraut, A.

    1979-01-01

    Regulations and standards play an essential role in achieving a safe and economic technology and in making the licensing procedure systematic, effective and clear. German rules and regulations applicable to the nuclear field are presented in this paper together with references to the rulemaking organizations. Detailed information is given on those rules and regulations, which prescribe the requirements concerning necessary documents for the nuclear licensing procedure. (author)

  2. 77 FR 60619 - Removal of Obsolete Regulation: Use of the Centennial of Flight Commission Name

    Science.gov (United States)

    2012-10-04

    ... Removal of Obsolete Regulation: Use of the Centennial of Flight Commission Name AGENCY: National... section 1204. 506 entitled ``Delegation of Authority to License the Use of the Centennial of Flight Commission Name.'' Section 506, Delegation of Authority to License the Use of the Centennial of Flight...

  3. 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...

  4. 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...

  5. 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

  6. Licensing of safety critical software for nuclear reactors - Common position of seven European nuclear regulators and authorised technical support organisations - Revision 2013

    International Nuclear Information System (INIS)

    2013-01-01

    This report is the 5th revision of the report. The task force was formed in 1994 as a group of experts on safety critical software. The members come from regulatory authorities and/or their technical support organization. Bo Liwaang, SSM, has been a member since the work started in 1994. For full information of the historical background, previous revisions of the report and objectives, see the Introduction of the report. The conclusions and viewpoints presented in the report are those of the authors and do not necessarily coincide with those of the SSM. The report, without the SSM cover and this page, will be published by or available at the websites of the other participating organizations. Effect on SSM supervisory and regulatory task: The effect of the report is high as it presents a common view on important issues by experts from seven European regulatory organizations, even though the report is not a regulation or guide

  7. Cost and risk reduction using upfront licensing in Canada. Annex 15

    International Nuclear Information System (INIS)

    Snell, V.G.

    2002-01-01

    The paper summarizes the use of 'up-front' licensing in Canada - how licensing requirements are defined, and met - in advance of a project commitment. The approach to licensing in Canada has allowed flexibility in development of new designs. Since licensing was originally risk-based, and current regulatory policy allows cost-benefit considerations as part of the decision making, risk can be and should be used in novel circumstances as a licensing tool. Since the licensing framework is non-prescriptive, innovative approaches to design can be introduced and dispositioned without changing the legal structure. This flexibility has been used in several up-front licensing reviews: a small urban heating reactor, repeat CANDU 6 generating station units, and the single unit CANDU 9 generating station. In the future we expect to apply it to advanced designs, as an essential part of risk reduction and customer confidence in the product. The important lessons learned in Canada include: Up-front licensing is essential to reduce the risk of licensing-related delays once a project has been committed. It requires a significant investment in time and effort from both the designer and the regulator; The most effective scope for up-front licensing is for the regulator to thoroughly assess novel concepts, test the design against changed domestic requirements, and follow-up on known difficult areas; and for the designer to ensure foreign requirements are incorporated. There is little benefit in certifying the design in detail; Although it would be satisfying to have legally-binding certification, in the end there can be no legal obligation on the regulator, and agreement is pursued on the basis of good faith that the regulator will not make arbitrary decisions and that the designer will meet agreed targets or requirements; In almost all circumstances, issues will arise that are beyond the current 'rules', however expressed. Rather than rushing to create new rules, one reaches a

  8. 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

  9. The nuclear licensing procedure

    International Nuclear Information System (INIS)

    Wagner, H.

    1976-01-01

    To begin with, the present nuclear licensing procedure is illustrated by a diagram. The relationship between the state and the Laender, the various experts (GRS - IRS + LRA -, TUEV, DWD, university institutes, firms of consulting engineers, etc), participation of the public, e.g. publication of the relevant documents, questions, objections (made by individuals or by groups such as citizens' initiatives), public discussion, official notice, appeals against the decision, the right of immediate execution of the decision are shortly dealt with. Finally, ways to improve the licensing procedure are discussed, from the evaluation of the documents to be submitted, published, and examined by the authorities (and their experts) up to an improvement of the administrative procedure. An improved licensing procedure should satisfy the well-founded claims of the public for more transparency as well as the equally justifiable claims of industry and utilities in order to ensure that the citizens' legal right to have safe and adequate electric power is guaranteed. The updated energy programme established by the Federal Government is mentioned along with the effectiveness of dealing with nuclear problems on the various levels of a Land government. (orig.) [de

  10. 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

  11. Assessment of the licensing aspects of HTGR in Yugoslavia

    International Nuclear Information System (INIS)

    Varazdinec, Z.

    1990-01-01

    This paper deals not only with the licensing procedure in Yugoslavia, but also reflects the Utility/Owner approach to the assessment of the licensability of the HTGR during the site selection process and especially during bid evaluation process. Besides the description of the existing procedure which was implemented on licensing of LWR program, the assessment of some licensing aspects of HTGR has been presented to describe possible implementation on licensing procedure. (author)

  12. Assessment of the licensing aspects of HTGR in Yugoslavia

    Energy Technology Data Exchange (ETDEWEB)

    Varazdinec, Z [Institut za Elektroprivredu-Zagreb, Zagreb (Yugoslavia)

    1990-07-01

    This paper deals not only with the licensing procedure in Yugoslavia, but also reflects the Utility/Owner approach to the assessment of the licensability of the HTGR during the site selection process and especially during bid evaluation process. Besides the description of the existing procedure which was implemented on licensing of LWR program, the assessment of some licensing aspects of HTGR has been presented to describe possible implementation on licensing procedure. (author)

  13. 75 FR 60830 - Surrender of License of Small Business Investment Company

    Science.gov (United States)

    2010-10-01

    ... Business Administration Rules and Regulations (13 CFR 107.1900) to function as a small business investment... SMALL BUSINESS ADMINISTRATION Surrender of License of Small Business Investment Company Pursuant to the authority granted to the United States Small Business Administration under the Small Business...

  14. 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)

  15. 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

  16. 77 FR 55183 - Effectiveness of Licensing Procedures for Agricultural Commodities to Cuba

    Science.gov (United States)

    2012-09-07

    ...] Effectiveness of Licensing Procedures for Agricultural Commodities to Cuba AGENCY: Bureau of Industry and... Administration Regulations for the export of agricultural commodities to Cuba. BIS will include a description of...), to Cuba. Requirements and procedures associated with such authorization are set forth in Sec. 740.18...

  17. 75 FR 54594 - Effectiveness of Licensing Procedures for Agricultural Commodities to Cuba

    Science.gov (United States)

    2010-09-08

    ...] Effectiveness of Licensing Procedures for Agricultural Commodities to Cuba AGENCY: Bureau of Industry and... Administration Regulations for the export of agricultural commodities to Cuba. BIS will include a description of...), to Cuba. Requirements and procedures associated with such authorization are set forth in section 740...

  18. 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)

  19. Advanced CANDU reactor pre-licensing progress

    International Nuclear Information System (INIS)

    Popov, N.K.; West, J.; Snell, V.G.; Ion, R.; Archinoff, G.; Xu, C.

    2005-01-01

    The Advanced CANDU Reactor (ACR) is an evolutionary advancement of the current CANDU 6 reactor, aimed at producing electrical power for a capital cost and at a unit-energy cost significantly less than that of the current reactor designs. The Canadian Nuclear Safety Commission (CNSC) staff are currently reviewing the ACR design to determine whether, in their opinion, there are any fundamental barriers that would prevent the licensing of the design in Canada. This CNSC licensability review will not constitute a licence, but is expected to reduce regulatory risk. The CNSC pre-licensing review started in September 2003, and was focused on identifying topics and issues for ACR-700 that will require a more detailed review. CNSC staff reviewed about 120 reports, and issued to AECL 65 packages of questions and comments. Currently CNSC staff is reviewing AECL responses to all packages of comments. AECL has recently refocused the design efforts to the ACR-1000, which is a larger version of the ACR design. During the remainder of the pre-licensing review, the CNSC review will be focused on the ACR-1000. AECL Technologies Inc. (AECLT), a wholly-owned US subsidiary of AECL, is engaged in a pre-application process for the ACR-700 with the US Nuclear Regulatory Commission (USNRC) to identify and resolve major issues prior to entering a formal process to obtain standard design certification. To date, the USNRC has produced a Pre-Application Safety Assessment Report (PASAR), which contains their reviews of key focus topics. During the remainder of the pre-application phase, AECLT will address the issues identified in the PASAR. Pursuant to the bilateral agreement between AECL and the Chinese nuclear regulator, the National Nuclear Safety Administration (NNSA) and its Nuclear Safety Center (NSC), NNSA/NSC are reviewing the ACR in seven focus areas. The review started in September 2004, and will take three years. The main objective of the review is to determine how the ACR complies

  20. Technical Memory 2010. Nuclear Regulatory Authority

    International Nuclear Information System (INIS)

    2010-01-01

    The technical memory 2010 of the Nuclear Regulatory Authority of Argentine Republic, compile the papers published in the subject on radiation protection and nuclear safety presented in journals, technical reports, congress or meetings of these subjects by the ARN personnel during 2010. In this edition the documents are presented on: environmental protection; safety transport of radioactive materials; regulations; licensing of medical installations; biological radiation effects; therapeutic uses of ionizing radiation and radioprotection of patients; internal dosimetry; radioactive waste management [es

  1. Technical Memory 2011. Nuclear Regulatory Authority

    International Nuclear Information System (INIS)

    2011-01-01

    The technical memory 2011 of the Nuclear Regulatory Authority of Argentine Republic, compile the papers published in the subject on radiation protection and nuclear safety presented in journals, technical reports, congress or meetings of these subjects by the ARN personnel during 2011. In this edition the documents are presented on: environmental protection; safety transport of radioactive materials; regulations; licensing of medical installations; biological radiation effects; therapeutic uses of ionizing radiation and radioprotection of patients; internal dosimetry; radioactive waste management [es

  2. 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

  3. 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

  4. 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

  5. Regulation of the Nuclear Regulatory Authority of the Slovak Republic No. 431/2011 of 16 November 2011 on the quality management system

    International Nuclear Information System (INIS)

    2012-01-01

    The Regulation lays down details of the requirements for the scope, content, hierarchy, structure and review of the quality management system of subjects seeking for licences and of licensees, requirements for the scope, content, hierarchy, and structure of the quality management system documentation, details of the requirements for quality assurance at nuclear facilities, details of the requirements for quality assurance at selected facilities, and details of the scope of their licensing. The Regulation has the following Annexes: (1) Requirements for the quality management system; (2) Requirements for quality management system documentation; (3) Scope of quality management system documentation to be approved; (4) Requirements for quality assurance programs of nuclear facilities; (5) Requirements for quality plans of selected facilities; (6) Requirements for the quality of selected facilities; (7) Requirements for accompanying technical documentation of selected facilities; (P.A.)

  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. 32 CFR 643.126 - Transportation licenses.

    Science.gov (United States)

    2010-07-01

    ... 32 National Defense 4 2010-07-01 2010-07-01 true Transportation licenses. 643.126 Section 643.126... ESTATE Additional Authority of Commanders § 643.126 Transportation licenses. Installation commanders are... free competitive proposals of all available companies or individuals. (b) DD Form 694 (Transportation...

  8. 36 CFR 271.4 - Commercial license.

    Science.gov (United States)

    2010-07-01

    ... 36 Parks, Forests, and Public Property 2 2010-07-01 2010-07-01 false Commercial license. 271.4... BEARâ SYMBOL § 271.4 Commercial license. (a) The Chief may authorize the commercial manufacture... a use or royalty charge which is reasonably related to the commercial enterprise has been...

  9. 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)

  10. 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.

  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. 48 CFR 52.227-19 - Commercial Computer Software License.

    Science.gov (United States)

    2010-10-01

    ... Software License. 52.227-19 Section 52.227-19 Federal Acquisition Regulations System FEDERAL ACQUISITION... Clauses 52.227-19 Commercial Computer Software License. As prescribed in 27.409(g), insert the following clause: Commercial Computer Software License (DEC 2007) (a) Notwithstanding any contrary provisions...

  13. 14 CFR 1245.108 - License to contractor.

    Science.gov (United States)

    2010-01-01

    ... 14 Aeronautics and Space 5 2010-01-01 2010-01-01 false License to contractor. 1245.108 Section... INTELLECTUAL PROPERTY RIGHTS Patent Waiver Regulations § 1245.108 License to contractor. (a) Each contractor.... The license extends to the contractor's domestic subsidiaries and affiliates, if any, within the...

  14. 48 CFR 1352.239-70 - Software license addendum.

    Science.gov (United States)

    2010-10-01

    ... 48 Federal Acquisition Regulations System 5 2010-10-01 2010-10-01 false Software license addendum... Software license addendum. As prescribed in 48 CFR 1339.107, insert the following clause: Software License....S.C. Section 516). (h) Renewal of Support after Expiration of this Award: Service will not...

  15. 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.

  16. 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)

  17. Licensing of simple digital devices

    International Nuclear Information System (INIS)

    Jackson, T. W.

    2008-01-01

    The inability to guarantee error-free software gave rise to the potential for common-cause failure of digital safety systems in nuclear power plants. To address this vulnerability, the U. S. Nuclear Regulatory Commission (NRC) required a quality software development process and a defense-in-depth and diversity analysis for digital safety systems. As a result of recent interim [NRC] staff guidance in the digital instrumentation and control (I and C) area, licensing of simple digital devices decreases some regulatory burden with respect to demonstrating a quality software development process and defense-in-depth and diversity analysis. This paper defines simple digital devices and addresses the interim staff guidance that applies to such devices. The paper also highlights the technical aspects that affect the licensing of such devices and incorporates licensing experience in the U.S. to date. (authors)

  18. 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

  19. 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

  20. 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...

  1. 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....

  2. Challenges in licensing a sodium-cooled advanced recycling reactor

    International Nuclear Information System (INIS)

    Levin, Alan E.

    2008-01-01

    As part of the Global Nuclear Energy Partnership (GNEP), the U.S. Department of Energy (DOE) has focused on the use of sodium-cooled fast reactors (SFRs) for the destruction of minor actinides derived from used reactor fuel. This approach engenders an array of challenges with respect to the licensing of the reactor: the U.S. Nuclear Regulatory Commission (NRC) has never completed the review of an application for an operating license for a sodium-cooled reactor. Moreover, the current U.S. regulatory structure has been developed to deal almost exclusively with light-water reactor (LWR) designs. Consequently, the NRC must either (1) develop a new regulatory process for SFRs, or (2) reinterpret the existing regulations to apply them, as appropriate, to SFR designs. During the 1980s and 1990s, the NRC conducted preliminary safety assessments of the Sodium Advanced Fast Reactor (SAFR) and the Power Reactor Innovative Small Module (PRISM) designs, and in that context, began to consider how to apply LWR-based regulations to SFR designs. This paper builds on that work to consider the challenges, from the reactor designer's point of view, associated with licensing an SFR today, considering (1) the evolution of SFR designs, (2) the particular requirements of reactor designs to meet GNEP objectives, and (3) the evolution of NRC regulations since the conclusion of the SAFR and PRISM reviews. (author)

  3. The law governing the nuclear licensing procedure in Brazil and in the Federal Republic of Germany

    International Nuclear Information System (INIS)

    Andrade Da Costa Lima, W.

    1984-01-01

    The two first parts of this thesis separately describe the framework of the legal system of the two countries in the field of nuclear energy, whereas the third part goes into details which are explained in order to prepare the subsequent comparative analysis. The comparison covers the structural set-up of the bodies of the national atomic energy provisions, the structure of the various nuclear licensing procedures, the role and competences of experts and their opinions, and the role and competence of jurisdiction. The most profound difference is found in the fact that Brazilian administrative law does not include jurisdiction of an administrative court, and this for constitutional reasons. The civil courts only have competence to examine acts of administration with regard to their legality. The procedure for licensing nuclear installations or equipment is determined by the central licensing authority within the framework of its competency. So far, there have been no attempts in Brazil to seek judicial remedy or to start an action to set aside decisions taken in the nuclear licensing procedure. Furthermore, there are no means in Brazilian law to stop licensing whenever the requirements of Art. 7, section 1, no. I-IV of Lei 6189 are met. The licensing authority has no scope of discretion. Applicants for a licence in Brazil will have no problems in finding out which regulations are applicable to their particular case. The concrete definition of details, however, always is a time-consuming and expensive process. (orig./HSCH) [de

  4. Challenging the FDA's authority to regulate autologous adult stem cells for therapeutic use: Celltex therapeutics' partnership with RNL Bio, substantial medical risks, and the implications of United States v. Regenerative Sciences.

    Science.gov (United States)

    Drabiak-Syed, Katherine

    2013-01-01

    This Article examines the convergence of three corporations that have attempted to capitalize on translating emerging research into clinical procedures by manufacturing and facilitating the process for patients to obtain mesenchymal stem cell (MSC) injections. Although the Food and Drug Administration (FDA) has asserted its authority to regulate somatic cell therapy products like MSCs under the Public Health Service Act and the Food, Drug, and Cosmetic Act, some manufacturers have attempted to circumvent FDA regulation through various mechanisms and argue that their products do not fall within the definition of a biological product or drug. However, scientific knowledge of using MSCs for clinical therapy remains in its infancy, and MSCs pose a number of serious risks to patients. This Article focuses on the development of Celltex, a company based in Sugar Land, Texas that manufactures and facilitates the injection of autologous MSCs; RNL Bio, a company that licenses its operations technology to Celltex; and Regenerative Sciences, a company based in Broomfield, Colorado that was recently involved in litigation with the FDA. Corporate circumvention of intended regulatory oversight exposes patients to potentially inefficacious products that could contribute to serious medical injuries such as viruses, myocardial infarction, cancer, or death.

  5. Licensing experience of the HTR-10 test reactor

    International Nuclear Information System (INIS)

    Sun, Y.; Xu, Y.

    1996-01-01

    A 10MW high temperature gas-cooled test reactor (HTR-10) is now being projected by the Institute of Nuclear Energy Technology within China's National High Technology Programme. The Construction Permit of HTR-10 was issued by the Chinese nuclear licensing authority around the end of 1994 after a period of about one year of safety review of the reactor design. HTR-10 is the first high temperature gas-cooled reactor (HTGR) to be constructed in China. The purpose of this test reactor project is to test and demonstrate the technology and safety features of the advanced modular high temperature reactor design. The reactor uses spherical fuel elements with coated fuel particles. The reactor unit and the steam generator unit are arranged in a ''side-by-side'' way. Maximum fuel temperature under the accident condition of a complete loss of coolant is limited to values much lower than the safety limit set for the fuel element. Since the philosophy of the technical and safety design of HTR-10 comes from the high temperature modular reactor design, the reactor is also called the Test Module. HTR-10 represents among others also a licensing challenge. On the one side, it is the first helium reactor in China, and there are less licensing experiences both for the regulator and for the designer. On the other side, the reactor design incorporates many advanced design features in the direction of passive or inherent safety, and it is presently a world-wide issue how to treat properly the passive or inherent safety design features in the licensing safety review. In this presentation, the licensing criteria of HTR-10 are discussed. The organization and activities of the safety review for the construction permit licensing are described. Some of the main safety issues in the licensing procedure are addressed. Among these are, for example, fuel element behaviour, source term, safety classification of systems and components, containment design. The licensing experiences of HTR-10 are of

  6. 12 CFR 723.20 - How can a state supervisory authority develop and enforce a member business loan regulation?

    Science.gov (United States)

    2010-01-01

    ... state regulation minimizes the risk and accomplishes the overall objectives of NCUA's member business... and enforce a member business loan regulation? 723.20 Section 723.20 Banks and Banking NATIONAL CREDIT UNION ADMINISTRATION REGULATIONS AFFECTING CREDIT UNIONS MEMBER BUSINESS LOANS § 723.20 How can a state...

  7. 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

  8. National competent authorities. List no. 16. Regulations for the safe transport of radioactive materials. 1973 revised edition (as amended) (Safety series no. 6)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1984-10-01

    Any national or international authority designated or otherwise recognised as such for any purpose in connection with the transport Regulations is known as a competent authority. In the Member States such a body has the responsibility for establishing national legislation to bring the Agency's transport Regulations into effect and for assuring compliance with its requirements. Depending on the national regulatory or institutional framework the functions of the competent authority may be assigned to one or more bodies. To assist Member States in implementing the transport Regulations and carrying out responsibility for compliance assurance, the IAEA continues to maintain this updated list of designated national competent authorities. Member States are annually requested to verify the list for correctness and completeness.

  9. National competent authorities. List no. 11. Regulations for the safe transport of radioactive materials. 1973 revised edition (Safety series no. 6)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1979-04-01

    Any national or international authority designated or otherwise recognised as such for any purpose in connection with the transport Regulations is known as a competent authority. In the Member States such a body has the responsibility for establishing national legislation to bring the Agency's transport Regulations into effect and for assuring compliance with its requirements. Depending on the national regulatory or institutional framework the functions of the competent authority may be assigned to one or more bodies. To assist Member States in implementing the transport Regulations and carrying out responsibility for compliance assurance, the IAEA continues to maintain this updated list of designated national competent authorities. Member States are annually requested to verify the list for correctness and completeness.

  10. National competent authorities. List no. 13. Regulations for the safe transport of radioactive materials. 1973 revised edition (as amended) (Safety series no. 6)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1981-10-01

    Any national or international authority designated or otherwise recognised as such for any purpose in connection with the transport Regulations is known as a competent authority. In the Member States such a body has the responsibility for establishing national legislation to bring the Agency's transport Regulations into effect and for assuring compliance with its requirements. Depending on the national regulatory or institutional framework the functions of the competent authority may be assigned to one or more bodies. To assist Member States in implementing the transport Regulations and carrying out responsibility for compliance assurance, the IAEA continues to maintain this updated list of designated national competent authorities. Member States are annually requested to verify the list for correctness and completeness.

  11. National competent authorities. List no. 12. Regulations for the safe transport of radioactive materials. 1973 revised edition (as amended) (Safety series no. 6)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1980-07-01

    Any national or international authority designated or otherwise recognised as such for any purpose in connection with the transport Regulations is known as a competent authority. In the Member States such a body has the responsibility for establishing national legislation to bring the Agency's transport Regulations into effect and for assuring compliance with its requirements. Depending on the national regulatory or institutional framework the functions of the competent authority may be assigned to one or more bodies. To assist Member States in implementing the transport Regulations and carrying out responsibility for compliance assurance, the IAEA continues to maintain this updated list of designated national competent authorities. Member States are annually requested to verify the list for correctness and completeness.

  12. National competent authorities. List no. 10. Regulations for the safe transport of radioactive materials. 1973 revised edition (Safety series no. 6)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1978-04-01

    Any national or international authority designated or otherwise recognised as such for any purpose in connection with the transport Regulations is known as a competent authority. In the Member States such a body has the responsibility for establishing national legislation to bring the Agency's transport Regulations into effect and for assuring compliance with its requirements. Depending on the national regulatory or institutional framework the functions of the competent authority may be assigned to one or more bodies. To assist Member States in implementing the transport Regulations and carrying out responsibility for compliance assurance, the IAEA continues to maintain this updated list of designated national competent authorities. Member States are annually requested to verify the list for correctness and completeness.

  13. National competent authorities. List no. 9. Regulations for the safe transport of radioactive materials. 1973 revised edition (Safety series no. 6)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1977-08-01

    Any national or international authority designated or otherwise recognised as such for any purpose in connection with the transport Regulations is known as a competent authority. In the Member States such a body has the responsibility for establishing national legislation to bring the Agency's transport Regulations into effect and for assuring compliance with its requirements. Depending on the national regulatory or institutional framework the functions of the competent authority may be assigned to one or more bodies. To assist Member States in implementing the transport Regulations and carrying out responsibility for compliance assurance, the IAEA continues to maintain this updated list of designated national competent authorities. Member States are annually requested to verify the list for correctness and completeness.

  14. National competent authorities. List no. 15. Regulations for the safe transport of radioactive materials. 1973 revised edition (as amended) (Safety series no. 6)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1983-10-01

    Any national or international authority designated or otherwise recognised as such for any purpose in connection with the transport Regulations is known as a competent authority. In the Member States such a body has the responsibility for establishing national legislation to bring the Agency's transport Regulations into effect and for assuring compliance with its requirements. Depending on the national regulatory or institutional framework the functions of the competent authority may be assigned to one or more bodies. To assist Member States in implementing the transport Regulations and carrying out responsibility for compliance assurance, the IAEA continues to maintain this updated list of designated national competent authorities. Member States are annually requested to verify the list for correctness and completeness.

  15. National competent authorities. List no. 14. Regulations for the safe transport of radioactive materials. 1973 revised edition (as amended) (Safety series no. 6)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1982-10-01

    Any national or international authority designated or otherwise recognised as such for any purpose in connection with the transport Regulations is known as a competent authority. In the Member States such a body has the responsibility for establishing national legislation to bring the Agency's transport Regulations into effect and for assuring compliance with its requirements. Depending on the national regulatory or institutional framework the functions of the competent authority may be assigned to one or more bodies. To assist Member States in implementing the transport Regulations and carrying out responsibility for compliance assurance, the IAEA continues to maintain this updated list of designated national competent authorities. Member States are annually requested to verify the list for correctness and completeness.

  16. National competent authorities. List no. 13. Regulations for the safe transport of radioactive materials. 1973 revised edition (as amended) (Safety series no. 6)

    International Nuclear Information System (INIS)

    1981-10-01

    Any national or international authority designated or otherwise recognised as such for any purpose in connection with the transport Regulations is known as a competent authority. In the Member States such a body has the responsibility for establishing national legislation to bring the Agency's transport Regulations into effect and for assuring compliance with its requirements. Depending on the national regulatory or institutional framework the functions of the competent authority may be assigned to one or more bodies. To assist Member States in implementing the transport Regulations and carrying out responsibility for compliance assurance, the IAEA continues to maintain this updated list of designated national competent authorities. Member States are annually requested to verify the list for correctness and completeness

  17. National competent authorities. List no. 7. Regulations for the safe transport of radioactive materials. 1973 revised edition (Safety series no. 6)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1975-01-01

    Any national or international authority designated or otherwise recognised as such for any purpose in connection with the transport Regulations is known as a competent authority. In the Member States such a body has the responsibility for establishing national legislation to bring the Agency's transport Regulations into effect and for assuring compliance with its requirements. Depending on the national regulatory or institutional framework the functions of the competent authority may be assigned to one or more bodies. To assist Member States in implementing the transport Regulations and carrying out responsibility for compliance assurance, the IAEA continues to maintain this updated list of designated national competent authorities. Member States are annually requested to verify the list for correctness and completeness.

  18. National competent authorities. List no. 6. Regulations for the safe transport of radioactive materials. 1973 revised edition (Safety series no. 6)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1974-01-01

    Any national or international authority designated or otherwise recognised as such for any purpose in connection with the transport Regulations is known as a competent authority. In the Member States such a body has the responsibility for establishing national legislation to bring the Agency's transport Regulations into effect and for assuring compliance with its requirements. Depending on the national regulatory or institutional framework the functions of the competent authority may be assigned to one or more bodies. To assist Member States in implementing the transport Regulations and carrying out responsibility for compliance assurance, the IAEA continues to maintain this updated list of designated national competent authorities. Member States are annually requested to verify the list for correctness and completeness.

  19. National competent authorities. List no. 11. Regulations for the safe transport of radioactive materials. 1973 revised edition (Safety series no. 6)

    International Nuclear Information System (INIS)

    1979-04-01

    Any national or international authority designated or otherwise recognised as such for any purpose in connection with the transport Regulations is known as a competent authority. In the Member States such a body has the responsibility for establishing national legislation to bring the Agency's transport Regulations into effect and for assuring compliance with its requirements. Depending on the national regulatory or institutional framework the functions of the competent authority may be assigned to one or more bodies. To assist Member States in implementing the transport Regulations and carrying out responsibility for compliance assurance, the IAEA continues to maintain this updated list of designated national competent authorities. Member States are annually requested to verify the list for correctness and completeness

  20. National competent authorities. List no. 8. Regulations for the safe transport of radioactive materials. 1973 revised edition (Safety series no. 6)

    International Nuclear Information System (INIS)

    1976-01-01

    Any national or international authority designated or otherwise recognised as such for any purpose in connection with the transport Regulations is known as a competent authority. In the Member States such a body has the responsibility for establishing national legislation to bring the Agency's transport Regulations into effect and for assuring compliance with its requirements. Depending on the national regulatory or institutional framework the functions of the competent authority may be assigned to one or more bodies. To assist Member States in implementing the transport Regulations and carrying out responsibility for compliance assurance, the IAEA continues to maintain this updated list of designated national competent authorities. Member States are annually requested to verify the list for correctness and completeness

  1. National competent authorities. List no. 10. Regulations for the safe transport of radioactive materials. 1973 revised edition (Safety series no. 6)

    International Nuclear Information System (INIS)

    1978-04-01

    Any national or international authority designated or otherwise recognised as such for any purpose in connection with the transport Regulations is known as a competent authority. In the Member States such a body has the responsibility for establishing national legislation to bring the Agency's transport Regulations into effect and for assuring compliance with its requirements. Depending on the national regulatory or institutional framework the functions of the competent authority may be assigned to one or more bodies. To assist Member States in implementing the transport Regulations and carrying out responsibility for compliance assurance, the IAEA continues to maintain this updated list of designated national competent authorities. Member States are annually requested to verify the list for correctness and completeness

  2. National competent authorities. List no. 7. Regulations for the safe transport of radioactive materials. 1973 revised edition (Safety series no. 6)

    International Nuclear Information System (INIS)

    1975-01-01

    Any national or international authority designated or otherwise recognised as such for any purpose in connection with the transport Regulations is known as a competent authority. In the Member States such a body has the responsibility for establishing national legislation to bring the Agency's transport Regulations into effect and for assuring compliance with its requirements. Depending on the national regulatory or institutional framework the functions of the competent authority may be assigned to one or more bodies. To assist Member States in implementing the transport Regulations and carrying out responsibility for compliance assurance, the IAEA continues to maintain this updated list of designated national competent authorities. Member States are annually requested to verify the list for correctness and completeness

  3. National competent authorities. List no. 9. Regulations for the safe transport of radioactive materials. 1973 revised edition (Safety series no. 6)

    International Nuclear Information System (INIS)

    1977-08-01

    Any national or international authority designated or otherwise recognised as such for any purpose in connection with the transport Regulations is known as a competent authority. In the Member States such a body has the responsibility for establishing national legislation to bring the Agency's transport Regulations into effect and for assuring compliance with its requirements. Depending on the national regulatory or institutional framework the functions of the competent authority may be assigned to one or more bodies. To assist Member States in implementing the transport Regulations and carrying out responsibility for compliance assurance, the IAEA continues to maintain this updated list of designated national competent authorities. Member States are annually requested to verify the list for correctness and completeness

  4. National competent authorities. List no. 6. Regulations for the safe transport of radioactive materials. 1973 revised edition (Safety series no. 6)

    International Nuclear Information System (INIS)

    1974-01-01

    Any national or international authority designated or otherwise recognised as such for any purpose in connection with the transport Regulations is known as a competent authority. In the Member States such a body has the responsibility for establishing national legislation to bring the Agency's transport Regulations into effect and for assuring compliance with its requirements. Depending on the national regulatory or institutional framework the functions of the competent authority may be assigned to one or more bodies. To assist Member States in implementing the transport Regulations and carrying out responsibility for compliance assurance, the IAEA continues to maintain this updated list of designated national competent authorities. Member States are annually requested to verify the list for correctness and completeness

  5. National competent authorities. List no. 14. Regulations for the safe transport of radioactive materials. 1973 revised edition (as amended) (Safety series no. 6)

    International Nuclear Information System (INIS)

    1982-10-01

    Any national or international authority designated or otherwise recognised as such for any purpose in connection with the transport Regulations is known as a competent authority. In the Member States such a body has the responsibility for establishing national legislation to bring the Agency's transport Regulations into effect and for assuring compliance with its requirements. Depending on the national regulatory or institutional framework the functions of the competent authority may be assigned to one or more bodies. To assist Member States in implementing the transport Regulations and carrying out responsibility for compliance assurance, the IAEA continues to maintain this updated list of designated national competent authorities. Member States are annually requested to verify the list for correctness and completeness

  6. National competent authorities. List no. 16. Regulations for the safe transport of radioactive materials. 1973 revised edition (as amended) (Safety series no. 6)

    International Nuclear Information System (INIS)

    1984-10-01

    Any national or international authority designated or otherwise recognised as such for any purpose in connection with the transport Regulations is known as a competent authority. In the Member States such a body has the responsibility for establishing national legislation to bring the Agency's transport Regulations into effect and for assuring compliance with its requirements. Depending on the national regulatory or institutional framework the functions of the competent authority may be assigned to one or more bodies. To assist Member States in implementing the transport Regulations and carrying out responsibility for compliance assurance, the IAEA continues to maintain this updated list of designated national competent authorities. Member States are annually requested to verify the list for correctness and completeness

  7. National competent authorities. List no. 15. Regulations for the safe transport of radioactive materials. 1973 revised edition (as amended) (Safety series no. 6)

    International Nuclear Information System (INIS)

    1983-10-01

    Any national or international authority designated or otherwise recognised as such for any purpose in connection with the transport Regulations is known as a competent authority. In the Member States such a body has the responsibility for establishing national legislation to bring the Agency's transport Regulations into effect and for assuring compliance with its requirements. Depending on the national regulatory or institutional framework the functions of the competent authority may be assigned to one or more bodies. To assist Member States in implementing the transport Regulations and carrying out responsibility for compliance assurance, the IAEA continues to maintain this updated list of designated national competent authorities. Member States are annually requested to verify the list for correctness and completeness

  8. National competent authorities. List no. 12. Regulations for the safe transport of radioactive materials. 1973 revised edition (as amended) (Safety series no. 6)

    International Nuclear Information System (INIS)

    1980-07-01

    Any national or international authority designated or otherwise recognised as such for any purpose in connection with the transport Regulations is known as a competent authority. In the Member States such a body has the responsibility for establishing national legislation to bring the Agency's transport Regulations into effect and for assuring compliance with its requirements. Depending on the national regulatory or institutional framework the functions of the competent authority may be assigned to one or more bodies. To assist Member States in implementing the transport Regulations and carrying out responsibility for compliance assurance, the IAEA continues to maintain this updated list of designated national competent authorities. Member States are annually requested to verify the list for correctness and completeness

  9. National competent authorities. List no. 8. Regulations for the safe transport of radioactive materials. 1973 revised edition (Safety series no. 6)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1976-01-01

    Any national or international authority designated or otherwise recognised as such for any purpose in connection with the transport Regulations is known as a competent authority. In the Member States such a body has the responsibility for establishing national legislation to bring the Agency's transport Regulations into effect and for assuring compliance with its requirements. Depending on the national regulatory or institutional framework the functions of the competent authority may be assigned to one or more bodies. To assist Member States in implementing the transport Regulations and carrying out responsibility for compliance assurance, the IAEA continues to maintain this updated list of designated national competent authorities. Member States are annually requested to verify the list for correctness and completeness.

  10. 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)

  11. 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)

  12. 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)

  13. Cooperation in reactor design evaluation and licensing

    International Nuclear Information System (INIS)

    Kaufer, B.; Wasylyk, A.

    2014-01-01

    In January 2007 the World Nuclear Association (WNA) established the Cooperation in Reactor Design Evaluation and Licensing (CORDEL) Working Group with the aim of stimulating a dialogue between the nuclear industry (including reactor vendors, operators and utilities) and nuclear regulators (national and international organisations) on the benefits and means of achieving a worldwide convergence of reactor safety standards for reactor designs. From the time of its inception to the present, CORDEL has evolved from a group of experts discussing how to achieve international standardisation in nuclear safety design to an established and recognised working group dedicated to analysing and forging common understandings in key areas as input to major decisions on nuclear energy policy. This paper will review the general directions and activities CORDEL plans to undertake during the next five-year period, including its general strategy, activities, priorities and interactions with its customers in order to meet its objectives. (author)

  14. Cooperation in reactor design evaluation and licensing

    Energy Technology Data Exchange (ETDEWEB)

    Kaufer, B.; Wasylyk, A. [World Nuclear Association, London (United Kingdom)

    2014-07-01

    In January 2007 the World Nuclear Association (WNA) established the Cooperation in Reactor Design Evaluation and Licensing (CORDEL) Working Group with the aim of stimulating a dialogue between the nuclear industry (including reactor vendors, operators and utilities) and nuclear regulators (national and international organisations) on the benefits and means of achieving a worldwide convergence of reactor safety standards for reactor designs. From the time of its inception to the present, CORDEL has evolved from a group of experts discussing how to achieve international standardisation in nuclear safety design to an established and recognised working group dedicated to analysing and forging common understandings in key areas as input to major decisions on nuclear energy policy. This paper will review the general directions and activities CORDEL plans to undertake during the next five-year period, including its general strategy, activities, priorities and interactions with its customers in order to meet its objectives. (author)

  15. 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.

  16. Decommissioning licensing procedure

    International Nuclear Information System (INIS)

    Perello, M.

    1979-01-01

    Decommissioning or closure of a nuclear power plant, defined as the fact that takes place from the moment that the plant stops producing for the purpose it was built, is causing preocupation. So this specialist meeting on Regulatory Review seems to be the right place for presenting and discusing the need of considering the decommissioning in the safety analysis report. The main goal of this paper related to the licensing procedure is to suggest the need of a new chapter in the Preliminary Safety Analysis Report (P.S.A.R.) dealing with the decommissioning of the nuclear power plant. Therefore, after a brief introduction the problem is exposed from the point of view of nuclear safety and finally a format of the new chapter is proposed. (author)

  17. 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...

  18. Tast Force report on bonding and perpetual care of nuclear licensed activities

    International Nuclear Information System (INIS)

    Anon.

    1975-01-01

    Potential issues which should be considered prior to the adoption and implementation of a bonding or perpetual care program are examined. The following topics are discussed: problem definition; major processors; factors in setting the amount of a bond; waste handling licensees; ore refineries and mills; former AEC licensed facilities; other specific licenses; authority; states where it is deemed that amendment of existing statutes is necessary to authorize imposition of a bonding requirement for licenses; administration; and recommendations. The following appendices are included: summary of cost estimate to decontaminate the American Nuclear Company; report on 1974 national conference on radiation control workshop no. 3; suggested changes to state regulations; and suggested legislation for licensee bonding and perpetual care trust funds

  19. 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

  20. Licensing of nuclear facilities according to the Bulgarian Act on the Safe Use of Nuclear Energy

    International Nuclear Information System (INIS)

    Stoyanova-Todorova, P.

    2004-01-01

    The new Bulgarian Act on the Safe Use of Nuclear Energy /Nuclear Act/ has replaced the former Act on the Use of Nuclear Energy for Peaceful Purposes. The new Nuclear Act covers the activities involving nuclear energy and sources of ionising radiation mainly by establishing a consistent licensing regime. About 13 regulations specifying the provisions of the Nuclear Act have been recently adopted by the Council of Ministers, the most important one being the Regulation on the Procedure for Issue of Licenses and Permits for the Safe Use of Nuclear Energy. The Chairman of the Nuclear Regulatory Agency (NRA) is authorised by the law to consider any application for issue of a license or a permit under the Bulgarian Nuclear Act. The procedure starts with an application, filed with the NRA, and continues about nine months. The final decision could be for issuing of the license or permit or a refusal for issuing the claimed document. The denial must be grounded and is subject to appeal. The Nuclear Act prescribes the conditions for issuing of two types of licensing documents (authorisations): licenses and permits. From a legal point of view the two types of licensing documents have one and the same nature - they are individual administrative acts according to the Bulgarian law. That is why there is no difference between them in terms of the issuing procedure. The difference between licenses and permits could be explained as follows: while a license is issued for reiterated activities, a permit is issued for non-reoccurring activities, this division being a specific feature of the Bulgarian Nuclear Act. In the field of nuclear facilities usage only one type of license is provided for by the Nuclear Act - a license for operation of a nuclear facility unit. For the rest of the activities issuing of permits is envisaged, those permits being in compliance with the main stages of the authorisation process formulated by the IAEA, following the step-by-step approach - siting, design

  1. Licensing of new fuel for Slovak NPPs

    International Nuclear Information System (INIS)

    Melicharek, M.; Mikulas, B.

    2011-01-01

    With the hope of achieving a six year fuel cycle and to allow for further power uprates a new type of fuel was licensed for NPP Mochovce Unit 1 (EMO1). Slovenske elektrarne, a.s. introduced the idea for the new fuel type to the regulatory authority in the middle of 2010. That's when the first draft of EMO safety report was made. This was the actual start of the licensing process. In case of new fuel regulator has several requirements like extended start up and power test; introducing a fuel behavior monitoring plan; using two independent methods to determine coolant flow though the active zone. In this paper the following issues have been discussed: 1) Engineering and safety reserve factors; 2)Fuel limits; 3) Uncertainties decrease in measurement of coolant flow through the reactor; 4) Determination of heating on fuel assembly; 5) Storage pool issues; 6) Emergency planning; 7) Monitoring of several fuel parameters (K qmax , K rmax , K v .K k and bypass)monitored during campaign

  2. 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)

  3. Radiation protection type testing and licensing of diagnostic X-ray equipment in the GDR

    International Nuclear Information System (INIS)

    Taschner, P.; Poulheim, K.F.; Feldheim, W.

    1987-01-01

    The results of more than 10 years experience in type testing and type licensing of diagnostic X-ray equipment with respect to meeting radiation protection requirements as well as the implications for the conduct of these procedures resulting from the introduction of new radiation protection legislation in 1983 and 1984, are described. At present an updated version of the 'Regulation of 16 December 1977 concerning radiation protection type testing and licensing of sealed radiation sources and equipment emitting ionizing radiation' is being prepared. (author)

  4. Nuclear relevant installations licensing methodology in the Argentine Republic

    International Nuclear Information System (INIS)

    Paganini, C.E.

    1986-01-01

    A review of the requeriments of the Nuclear Installations Advisory Committee on Licensing (CALIN) from the nuclear security point of view, is presented. The methodology applied by the CALIN for the licensing in the Argentine Republic is included as well as codes, standards of applications and the interaction between the licensing Authority and the Responsible Entity during the whole process. Finally, the Atucha II nuclear power plant's licensing, in construction at present, is explained and the standard, of the licensing schedule, is presented graphically. (author) [es

  5. 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)

  6. 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

  7. 31 CFR 595.305 - General license.

    Science.gov (United States)

    2010-07-01

    ... 31 Money and Finance: Treasury 3 2010-07-01 2010-07-01 false General license. 595.305 Section 595.305 Money and Finance: Treasury Regulations Relating to Money and Finance (Continued) OFFICE OF FOREIGN ASSETS CONTROL, DEPARTMENT OF THE TREASURY TERRORISM SANCTIONS REGULATIONS General Definitions...

  8. 31 CFR 595.312 - Specific license.

    Science.gov (United States)

    2010-07-01

    ... 31 Money and Finance: Treasury 3 2010-07-01 2010-07-01 false Specific license. 595.312 Section 595.312 Money and Finance: Treasury Regulations Relating to Money and Finance (Continued) OFFICE OF FOREIGN ASSETS CONTROL, DEPARTMENT OF THE TREASURY TERRORISM SANCTIONS REGULATIONS General Definitions...

  9. 31 CFR 595.308 - License.

    Science.gov (United States)

    2010-07-01

    ... 31 Money and Finance: Treasury 3 2010-07-01 2010-07-01 false License. 595.308 Section 595.308 Money and Finance: Treasury Regulations Relating to Money and Finance (Continued) OFFICE OF FOREIGN ASSETS CONTROL, DEPARTMENT OF THE TREASURY TERRORISM SANCTIONS REGULATIONS General Definitions § 595.308...

  10. 48 CFR 252.227-7007 - License term-running royalty.

    Science.gov (United States)

    2010-10-01

    ... 48 Federal Acquisition Regulations System 3 2010-10-01 2010-10-01 false License term-running... of Provisions And Clauses 252.227-7007 License term—running royalty. As prescribed at 227.7009-4(b), insert the following clause in patent releases, license agreements, and assignments: License Term—Running...

  11. The licensing of shipping containers for radioactive materials

    International Nuclear Information System (INIS)

    Schulz-Forberg, B.

    1987-01-01

    In the Federal Republic of Germany the competent Federal Minister regulated the licensing procedure in a guideline while assigning the PTB the function of competent authority, and stipulating that BAM is to execute design inspection for approval. On completion of design inspection, BAM summarizes the results in a certificate which also states the measures required to be taken in quality monitoring in the manufacturing and maintenance of packagings. A sheet specifies the implemental provisions covering quality-assurance measures in planning, manufacturing, commissioning and operation of shipping items of types B(U) and B(M), and of nuclear safety classes I, II, and III. (orig./DG) [de

  12. U.S. ALMR safety approach and licensing status

    International Nuclear Information System (INIS)

    Hardy, R.W.; Gyorey, G.L.

    1991-01-01

    The Advanced Liquid Metal Cooled Reactor in the United States is based on the PRISM concept originated by General Electric. This concept features a compact modular system suitable for factory fabrication, and a high degree of passive and natural safety characteristics. The safety approach emphasizes accident prevention, backed up by accident mitigation as required. First-round safety evaluations by the U.S. regulators have found that the design provides passive, natural and other desirable features enhancing the safety of the power plant. Licensing review continuing. (author)

  13. Inspection of licensed nuclear power plants in the United States

    International Nuclear Information System (INIS)

    Thornburg, H. D.

    1977-01-01

    Inspection of licensed nuclear power plants in the United States is performed by the Office of Inspection and Enforcement (IE), United States Nuclear Regulatory Commission. IE has several key functions : a) Inspection of licensees and investigation of incidents, occurrences and allegations. b) Detection and correction of safety and security problems. c) Enforcement of rules, regulations, and Commission orders. d) Feedback to the industry and others regarding safety experience. e) Informing the public and others. Major enforcement actions and events involving operating power reactors for the past several years will be summarized. (author)

  14. 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)

  15. 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

  16. Current status of the PBMR licensing project

    International Nuclear Information System (INIS)

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

    2000-01-01

    The CNS is currently reviewing the PBMR conceptual design from a licensibility point of view. The PBMR concept is based on a High Temperature Gas Cooled Reactor - pebble bed reactor type. It is anticipated that the PBMR design will rely on inherent safety characteristics to contain fission products within fuel over the full range of design basis events. This feature combined with the high temperature integrity of the fuel and structural graphite, allows the safe use of a high coolant temperature, which allows consideration of the future development of this reactor for non-electrical applications of nuclear heat for industrial use. The CNS licensing approach requires that the licensing and design basis of the plant should respect prevailing international norms and practices and that a quantitative risk assessment should demonstrate compliance with the CNS fundamental safety standards. The first stage of the licensing process is now ongoing; this is a pre-application phase, which will result in a statement on licensibility being issued. Identification of the specific documentation requirements and information needed is required across every step of the licensing process. Top level regulatory requirements have been established for the PBMR. They include the CNS fundamental safety standard and basic licensing criteria, which describes requirements on licensees of nuclear installations regarding risk assessment and compliance with the safety criteria and define classification of licensing basis events. (author)

  17. 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.

  18. Licensed bases management for advanced nuclear plants

    International Nuclear Information System (INIS)

    O'Connell, J.; Rumble, E.; Rodwell, E.

    2001-01-01

    Prospective Advanced Nuclear Plant (ANP) owners must have high confidence that the integrity of the licensed bases (LB) of a plant will be effectively maintained over its life cycle. Currently, licensing engineers use text retrieval systems, database managers, and checklists to access, update, and maintain vast and disparate licensing information libraries. This paper describes the demonstration of a ''twin-engine'' approach that integrates a program from the emerging class of concept searching tools with a modern Product Data Management System (PDMS) to enhance the management of LB information for an example ANP design. (author)

  19. Licensed bases management for advanced nuclear plants

    Energy Technology Data Exchange (ETDEWEB)

    O' Connell, J [Duke Engineering and Services, Marlborough, MA (United States); Rumble, E; Rodwell, E [EPRI, Palo Alto, CA (United States)

    2001-07-01

    Prospective Advanced Nuclear Plant (ANP) owners must have high confidence that the integrity of the licensed bases (LB) of a plant will be effectively maintained over its life cycle. Currently, licensing engineers use text retrieval systems, database managers, and checklists to access, update, and maintain vast and disparate licensing information libraries. This paper describes the demonstration of a ''twin-engine'' approach that integrates a program from the emerging class of concept searching tools with a modern Product Data Management System (PDMS) to enhance the management of LB information for an example ANP design. (author)

  20. Licensed bases management for advanced nuclear plants

    Energy Technology Data Exchange (ETDEWEB)

    O' Connell, J. [Duke Engineering and Services, Marlborough, MA (United States); Rumble, E.; Rodwell, E. [EPRI, Palo Alto, CA (United States)

    2001-07-01

    Prospective Advanced Nuclear Plant (ANP) owners must have high confidence that the integrity of the licensed bases (LB) of a plant will be effectively maintained over its life cycle. Currently, licensing engineers use text retrieval systems, database managers, and checklists to access, update, and maintain vast and disparate licensing information libraries. This paper describes the demonstration of a ''twin-engine'' approach that integrates a program from the emerging class of concept searching tools with a modern Product Data Management System (PDMS) to enhance the management of LB information for an example ANP design. (author)

  1. Author Details

    African Journals Online (AJOL)

    Naumovski, G. Vol 8, No 2 (2014) - Articles Comment: Convergence of Trademark Law and E-Commerce: Overview of US, EU and China Regulations on Trademarks and Domain Names Abstract PDF. ISSN: 1998-9881. AJOL African Journals Online. HOW TO USE AJOL... for Researchers · for Librarians · for Authors ...

  2. Author Details

    African Journals Online (AJOL)

    Sanie-Jahromi, Fatemeh. Vol 18, No 4 (2017) - Articles Extremely low frequency electromagnetic field in combination with β-Lapachone up-regulates the genes of non-homologous end joining. Abstract PDF. ISSN: 1110-8630. AJOL African Journals Online. HOW TO USE AJOL... for Researchers · for Librarians · for Authors ...

  3. Author Details

    African Journals Online (AJOL)

    Temesgen, Eshetu Yadeta. Vol 5, No 1 (2016) - Articles Laws regulating franchise business in different jurisdictions. Abstract PDF. ISSN: 2305-3739. AJOL African Journals Online. HOW TO USE AJOL... for Researchers · for Librarians · for Authors · FAQ's · More about AJOL · AJOL's Partners · Terms and Conditions of Use ...

  4. Licensing of HTGRs in the United States

    International Nuclear Information System (INIS)

    Fisher, C.R.; Orvis, D.D.

    1981-01-01

    The licensing history of the high-temperature gas-cooled reactor (HTGR) in the United States is given historical perspective. The experience began with the licensing of the Peach Bottom Atomic Power Station and extends to the continuing experience at the Fort St. Vrain Nuclear Generating Station. Additional experience was obtained from the licensing reviews in the mid-1970s of the large HTGR plants that were to be built by Philadelphia Electric Company and Delmarva Power and Light. Also, information was provided by the licensing review of the General Atomic standard plant by the U.S. Nuclear Regulatory Commission (NRC) at about the same time. These experiences are summarized in terms of the principal design criteria that were required by the regulatory authority for each project. These criteria include specification of the design basis accidents that were postulated for the plant safety analysis. Several technical issues raised by the NRC during their review of the large HTGR are presented. (author)

  5. 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)

  6. 14 CFR Section 01 - Authority Under Which Accounting and Reporting Rules and Regulations are Prescribed and Administered

    Science.gov (United States)

    2010-01-01

    ... OFFICE OF THE SECRETARY, DEPARTMENT OF TRANSPORTATION (AVIATION PROCEEDINGS) ECONOMIC REGULATIONS UNIFORM... all documents, papers, and correspondence, now or hereafter existing, and kept or required to be kept... necessary in the public interest. Safety, Economic and Postal Offenses Sec. 901. (a)(1) Any person who...

  7. 14 CFR 399.111 - All operations of federally authorized carriers to be regulated by the Board.

    Science.gov (United States)

    2010-01-01

    ... SECRETARY, DEPARTMENT OF TRANSPORTATION (AVIATION PROCEEDINGS) POLICY STATEMENTS STATEMENTS OF GENERAL POLICY Policies Relating to Federal Preemption of State Economic Regulations § 399.111 All operations of... carriers are subject to the requirements of Title IV of the Act, including certification and tariff-filing...

  8. French regulations

    International Nuclear Information System (INIS)

    Ballereau, P.

    1998-01-01

    In this issue are given the new French regulations relative to radiation protection of temporary personnel, the licensing to release gaseous and liquid wastes and the licensing granted to thirty two laboratories using beta and gamma decay radioisotopes. (N.C.)

  9. 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

  10. 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.

  11. 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)

  12. The Short Selling Regulation in the EU: Assessing the Authorization Granted for ESMA to Prohibit Short Selling

    Directory of Open Access Journals (Sweden)

    Matias Huhtilainen

    2017-07-01

    Full Text Available The paper discusses the renewed short selling regulation (Regulation (EU No 236/2012 in the European Union. The focus is on the provisions that deal with prohibiting short selling in exceptional market circumstances. The Regulation further enforces certain obligations to report and disclose short positions. It is concluded that banning short selling is not an effective tool to contain extreme price volatility. The difference-in-differences regression and repeated measures GLM were used to test whether short selling bans were successful in containing volatility of those Spanish and Italian stocks that were subject to two back-to-back prohibitions during the years 2011-2013. The results are consistent with the majority of previous research, suggesting that the effectiveness of short sale constraints in reducing volatility is limited at best. Furthermore, there are evidence of counterproductive effects: constraints on short selling may actually increase volatility as well as deteriorate liquidity. However, based on theory and previous studies, reporting and disclosure requirements shall be favored provided they improve market efficiency as well as supervisory work of regulatory bodies.This paper discusses the renewed short selling regulation (Regulation (EU No 236/2012 in the European Union. The focus is on the provisions that deal with prohibiting short selling in exceptional market circumstances. The Regulation further enforces certain obligations to report and disclose short positions. It is concluded that banning short selling is not an effective tool to contain extreme price volatility. The difference-in-differences regression and repeated measures GLM were used to test whether short selling bans were successful in containing volatility of those Spanish and Italian stocks that were subject to two back-to-back prohibitions during the years 2011-2013. The results are consistent with the majority of previous research, suggesting that the

  13. Radiation Regulation Bodies in South Africa

    International Nuclear Information System (INIS)

    Mavunda, R.D.

    2010-01-01

    Tthere are two types Regulatory Bodies in South Africa: department of Health - Radiation Control (DoH) and National Nuclear Regulator (NNR). The function DoH include of Promotion and maintenance of health within the framework of National health plan, Protection against injury or disease caused by technological devises, Protection against injury or disease caused by radiation, Promote safe and legal use of such products. The National Nuclear Regulator authorizes Nuclear Installation License, Nuclear Vessel License, Certificate of Registration and Certificate of Exemption. Some of the Electronic Products include licensing electro-medical products, Import or manufactured License conditions, Radiation workers, Report forms, Use and Radio-nuclides. Nuclear Authorization is the process of granting, by the National Nuclear Regulator, a written approval to applicants or / and operating organizations to perform nuclear related activities as detailed in the scope of the authorization. International Trade Administration Commission of South Africa (ITAC) issue license for import and export of all products including electronic X-Ray products and Radio-nuclides

  14. 48 CFR 227.7009 - Patent releases, license agreements, and assignments.

    Science.gov (United States)

    2010-10-01

    ... 48 Federal Acquisition Regulations System 3 2010-10-01 2010-10-01 false Patent releases, license... ACQUISITION REGULATIONS SYSTEM, DEPARTMENT OF DEFENSE GENERAL CONTRACTING REQUIREMENTS PATENTS, DATA, AND COPYRIGHTS Infringement Claims, Licenses, and Assignments 227.7009 Patent releases, license agreements, and...

  15. Radioprotection guidelines to the elaboration of a specific standard for the licensing of radioactive facilities on the practice of oil and gas well logging

    International Nuclear Information System (INIS)

    Gomes, Rogerio dos Santos; Gomes, Joana D'Arc Ramos Lopes; Costa, Mara Lucia de Lara; Miranda, Marcia Valeria F.E. Sa

    2011-01-01

    The regulatory process in oil and gas well logging has shown the need for specific standard for the issuance of a license authorizing the use of sealed sources in well logging activities, in order to guarantee the quality of many factors from the point of view of radiation protection. Currently, have been used only generic radiation protection standards, but are not comprehensive or technically suitable for a well logging licensing purpose. The lack of a specific standard for licensing in radioactive well logging operations in Brazil, weakens the nuclear regulatory body in your aim of regulate and licensing the activity. This work establish, as main objective, a guideline for the future Brazilian radioprotection code in well logging operations, presenting relevant aspects not covered by generic radiation protection standards. (author)

  16. Radioprotection guidelines to the elaboration of a specific standard for the licensing of radioactive facilities on the practice of oil and gas well logging

    International Nuclear Information System (INIS)

    Gomes, Rogerio dos Santos; Gomes, Joana D'Arc Ramos Lopes; Costa, Mara Lucia de Lara; Miranda, Marcia Valeria F.E. Sa

    2011-01-01

    The regulatory process in oil and gas well logging has shown the need for specific standard for the issuance of a license authorizing the use of sealed sources in well logging activities, in order to guarantee the quality of many factors from the point of view of radiation protection. Currently, have been used only generic radiation protection standards, but are not comprehensive or technically suitable for a well logging licensing purpose. The lack of a specific standard for licensing in radioactive well logging operations in Brazil, weakens the nuclear regulatory body in your aim of regulate and licensing the activity. This work establish, as main objective, a guideline for the future Brazilian radioprotection code in well logging operations, presenting relevant aspects not covered by genetic radiation protection standards. (author)

  17. An analysis on the export license criteria for NSG control items in the US and Japan

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Young Rok [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1995-06-01

    Korea has taken steps to join the Nuclear Suppliers Group (NSG) which is a major part of the international nuclear export control regime. In this connection, it is an urgent task to build a new Korean nuclear export control system that includes NSG guidelines and control items. In addition, it is necessary to review the developed supplier countries` experience in the field of export control. The main purpose of this study is to analyze how the US and Japan have controlled the items listed in NSG part 1 and 2 guidelines. To this end, various relevant regulations of the US and Japan were studied. Among those regulations, the US Export Administration Regulation, US 10 CFR 110 and 810, and the Japan`s Export Administration Order are included. Through the review process, this study identified NSG items which are controlled in the export control systems of the US and Japan. Furthermore, this study summarized and compared the export license criteria that must be satisfied before exporting each NSG item in the two countries. The export license criteria consist of permitted destinations, document requirements, and types of license. The results of this study are expected to contribute to establishing an appropriate Korean nuclear export control system and could be used as references to the practical export licensing policies of the US and Japan. 6 tabs., 13 refs., (Author) .new.

  18. An analysis on the export license criteria for NSG control items in the US and Japan

    International Nuclear Information System (INIS)

    Choi, Young Rok

    1995-06-01

    Korea has taken steps to join the Nuclear Suppliers Group (NSG) which is a major part of the international nuclear export control regime. In this connection, it is an urgent task to build a new Korean nuclear export control system that includes NSG guidelines and control items. In addition, it is necessary to review the developed supplier countries' experience in the field of export control. The main purpose of this study is to analyze how the US and Japan have controlled the items listed in NSG part 1 and 2 guidelines. To this end, various relevant regulations of the US and Japan were studied. Among those regulations, the US Export Administration Regulation, US 10 CFR 110 and 810, and the Japan's Export Administration Order are included. Through the review process, this study identified NSG items which are controlled in the export control systems of the US and Japan. Furthermore, this study summarized and compared the export license criteria that must be satisfied before exporting each NSG item in the two countries. The export license criteria consist of permitted destinations, document requirements, and types of license. The results of this study are expected to contribute to establishing an appropriate Korean nuclear export control system and could be used as references to the practical export licensing policies of the US and Japan. 6 tabs., 13 refs., (Author) .new

  19. The options of local authorities for addressing climate change and energy efficiency through environmental regulation of companies

    DEFF Research Database (Denmark)

    Dirckinck-Holmfeld, Kasper

    2015-01-01

    of energy consumption and GHG emissions during inspections. The assessment is based on the triangulation of different data: a) qualitative interviews with environmental officers from seven local authorities taking part in a EU life+ project, Carbon 20; b) a documentary review of political documents...

  20. 7 CFR 46.9 - Termination, suspension, revocation, cancellation of licenses; notices; renewal.

    Science.gov (United States)

    2010-01-01

    ... AGRICULTURAL MARKETING SERVICE (Standards, Inspections, Marketing Practices), DEPARTMENT OF AGRICULTURE MARKETING OF PERISHABLE AGRICULTURAL COMMODITIES REGULATIONS (OTHER THAN RULES OF PRACTICE) UNDER THE..., within four years from the date of the issuance of the license, the license shall be automatically...

  1. 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

  2. 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

  3. 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.

  4. 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...

  5. May compact storage facilities be licensed

    International Nuclear Information System (INIS)

    Gleim, A.; Winter, G.

    1980-01-01

    The authors examine as potential statements fo fact for licensing so-called compact storage facilities for spent fuel elements Sec. 6 to 9c of the German Atomic Energy Act and Sec. 4 of the German Radiation Protection Ordinance. They find that none of these provisions were applicable to compact stroage facilities. In particular, the storage of spent fuel elements was no storage of nuclear fuels licensable under Sec. 6 of the Atomic Energy Act, because Sec. 6 did not cover spent fuel elements. Also in the other wording of the Atomic Energy Act there was no provision, which could be used as a statement of fact for licensing compact storage facilities. Such facilities could not be licensed and, for that reason, were not permitted. (IVR) [de

  6. Licensing of HTGRs in the United States

    Energy Technology Data Exchange (ETDEWEB)

    Fisher, C. R.; Orvis, D. D. [General Atomic Co., San Diego, CA (USA)

    1981-01-15

    The licensing history of the high-temperature gas-cooled reactor (HTGR) in the United States is given historical perspective. The experience began with the licensing of the Peach Bottom Atomic Power Station and extends to the continuing experience at the Fort St. Vrain Nuclear Generating Station. Additional experience was obtained from the licensing reviews in the mid-1970s of the large HTGR plants that were to be built by Philadelphia Electric Company and Delmarva Power and Light. Also, information was provided by the licensing review of the General Atomic standard plant by the U.S. Nuclear Regulatory Commission (NRC) at about the same time. These experiences are summarized in terms of the principal design criteria that were required by the regulatory authority for each project. These criteria include specification of the design basis accidents that were postulated for the plant safety analysis. Several technical issues raised by the NRC during their review of the large HTGR are presented.

  7. Report of the Economy, Sustainable Development and Land Planning Commission aiming at authorizing electricity final user and small companies to go back to the electricity regulated price

    International Nuclear Information System (INIS)

    2010-01-01

    This report first presents the French regulated price system by recalling the legal bases for electricity and natural gas pricing, and by describing the progressive process of the electricity and natural gas market opening in France. It outlines that a reversibility principle has been introduced along with regulated pricing in most of the European Union countries. It also comments the complexity created on this issue by successive laws in France, the consequences of the soon coming law on the new organization of the electricity market. Then, the report comments the proposition which aims at authorizing electricity household users and small companies to go back to the regulated electricity price, thereby perpetuating the reversibility principle, while maintaining a criterion of installed electricity power, including natural gas prices and new consumption sites. A table proposes a comparison between existing texts, the present law project and this Commission proposition

  8. 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)

  9. Regulation

    International Nuclear Information System (INIS)

    Ballereau, P.

    1999-01-01

    The different regulations relative to nuclear energy since the first of January 1999 are given here. Two points deserve to be noticed: the decree of the third august 1999 authorizing the national Agency for the radioactive waste management to install and exploit on the commune of Bures (Meuse) an underground laboratory destined to study the deep geological formations where could be stored the radioactive waste. The second point is about the uranium residues and the waste notion. The judgment of the administrative tribunal of Limoges ( 9. july 1998) forbidding the exploitation of a storage installation of depleted uranium considered as final waste and qualifying it as an industrial waste storage facility has been annulled bu the Court of Appeal. It stipulated that, according to the law number 75663 of the 15. july 1965, no criteria below can be applied to depleted uranium: production residue (possibility of an ulterior enrichment), abandonment of a personal property or simple intention to do it ( future use aimed in the authorization request made in the Prefecture). This judgment has devoted the primacy of the waste notion on this one of final waste. (N.C.)

  10. Allegheny County Dog Licenses

    Data.gov (United States)

    Allegheny County / City of Pittsburgh / Western PA Regional Data Center — A list of dog license dates, dog breeds, and dog name by zip code. Currently this dataset does not include City of Pittsburgh dogs.

  11. Credentialing, Licensing, and Education

    Science.gov (United States)

    ... V W X Y Z Credentialing, Licensing, and Education Share: On This Page The Bottom Line Credentials, ... and practices that chiropractors are allowed to perform. Education and Training Professional organizations in some complementary health ...

  12. Site Specific Vendor's License

    Data.gov (United States)

    Montgomery County of Maryland — This dataset contains information of a site-specific vendor's license which is required if an individual sells or offers to sell goods or services from a stationary...

  13. 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

  14. 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

  15. ITER, On the way to call for the license

    International Nuclear Information System (INIS)

    Alejaidre, C.; Girard, J.P.

    2007-01-01

    Full text of publication follows: All the seven ITER Parties have now ratified the lTER Agreement, which was signed in Paris in November last year. On October 24, 2007 the ITER Agreement enters officially into force. The licensing procedure to start construction shall be launched within the coming months in order to start construction at the beginning of 2009. The Host Party, Europe and the Host State, France have already participated together with the ITER Organization (IO) to a public debate to present the project to the neighboring populations (January to May 2006) and other administrative procedures to prepare the site and the roads for heavy loads. According to host state law on licensing of nuclear facilities, IO will send a set of administrative documents including a safety assessment (called Preliminary Safety Report) and public hearing files including impact studies and risk analysis. The review and public hearing are expected mid-08 to be consistent with the start of nuclear building construction on site. The latest update of the design took into account of inputs from: -An internal design review managed through eight specialist groups including safety and licensing, - Host State regulations (technical and QA), which should be fulfilled as quoted in the ITER agreement, - Site adaptation including land configuration, environmental conditions and external hazards. The ITER designers, in close contact with the Participant Teams, are proceeding with the adaptation of the generic design to comply with these new inputs. The codes and standards for all equipment are also under revision in order to fit with the expected requirements, taking into account the procurement sharing agreement and the French regulations. In the earlier stage of ITER design fusion took benefit from fission knowledge, in the present stage fusion is taking the lead as can be demonstrated by the update of the European mechanical code RCC-MR, now ready and updated to the vacuum vessel design

  16. DESIGN AND LICENSING TRENDS OF THE GENERAL EDUCATIONAL PROGRAMS IN LATVIA

    OpenAIRE

    Mihailovs, Ivans Jānis; Krūmiņa, Aira Aija

    2016-01-01

    The general education program designing and licensing trends in Latvia in the period from 2010 to 2014 are analyzed in the article. Based on the general education program licensing data, it found that there isn’t a trend to license author’s program in primary education, while the secondary level of education author's programs are designed and licensed more often. The fact that primary education is more licensed programs in mathematics, science and technology, but in general secondary educatio...

  17. 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

  18. 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

  19. 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

  20. 75 FR 32983 - Commercial Driver's License (CDL) Standards: Exemption

    Science.gov (United States)

    2010-06-10

    ...-28480] Commercial Driver's License (CDL) Standards: Exemption AGENCY: Federal Motor Carrier Safety... commercial driver's license (CDL) as required by current regulations. FMCSA reviewed NAAA's application for... demonstrate alternatives its members would employ to ensure that their commercial motor vehicle (CMV) drivers...

  1. 78 FR 48158 - Intent To Grant an Exclusive Patent License

    Science.gov (United States)

    2013-08-07

    ... the invention described and claimed in the U.S. patent entitled PROCESS FOR THE BIODEGRADATION OF... notice of its intent to grant an exclusive, royalty-bearing, revocable license to practice the invention... 404.5 and 404.7 of the U.S. Government patent licensing regulations. EPA will negotiate the final...

  2. 23 CFR 635.110 - Licensing and qualification of contractors.

    Science.gov (United States)

    2010-04-01

    ... licensing contractors, who may bid for, be awarded, or perform Federal-aid highway contracts, shall be... competition, to prevent submission of a bid by, or to prohibit the consideration of a bid submitted by, any...) No contractor shall be required by law, regulation, or practice to obtain a license before submission...

  3. 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

  4. 48 CFR 252.227-7005 - License term.

    Science.gov (United States)

    2010-10-01

    ... 48 Federal Acquisition Regulations System 3 2010-10-01 2010-10-01 false License term. 252.227-7005..., DEPARTMENT OF DEFENSE CLAUSES AND FORMS SOLICITATION PROVISIONS AND CONTRACT CLAUSES Text of Provisions And... referred to in the “License Grant” clause of this contract and any and all patents hereafter issued on...

  5. Initiatives in transport cask licensing

    International Nuclear Information System (INIS)

    Patterson, John

    1998-01-01

    The variations in research reactor fuel form, configuration, irradiation characteristics, and transport cask have required a substantial number of transport cask licensing actions associated with foreign research reactor spent fuel transportation. When compounded by limited time for shipment preparations, due to contract timing or delayed receipt of technical data, the number and timing of certifications has adversely impacted the ability of regulatory agencies to support intended shipping schedules. This issue was brought into focus at a april, 1998 meeting among DOE, the US Nuclear Regulatory Commission, and DOE's spent fuel transportation contractors. (author)

  6. Cask development, testing, and licensing

    International Nuclear Information System (INIS)

    Quinn, G.J.; Haelsig, R.T.; Warrant, M.M.

    1986-01-01

    The NuPac 125-B Rail Cask was developed to provide a safe means of transporting the damaged core of Three Mile Island Unit 2 from the TMI site at Middletown, PA, to the Idaho National Engineering laboratory (INEL) at Idaho Falls, ID. The development of the NuPac 125-B Rail Cask posed two engineering and technical management challenges; Licensing Strategy - The NuPac 125-B Rail Cask represented the first irradiated fuel rail cask developed within the United States in the past decade, a decade characterized by changing nuclear regulations, and Accelerated Schedule - The TMI-2 defueling schedule demanded a cask development schedule one-third as long as normally required. These challenges governed the overall development and licensing process for the cask. First, a high degree of conservation was incorporated into the design to allow quick, simplified demonstrations of adequacy to regulatory staff. Second, redundant design techniques were employed in all areas of uncertainty. The testing program eliminated performance uncertainties and validated predictions and predictive models. Drop tests of a quarter-scale model of the cask were conducted, and results were correlated with analytic predictions to verify structural and mechanical performance of the cask. Full-scale tests of the canisters were conducted to verify structural behavior of canister internals which provide criticality control. This paper describes the testing program for the NuPac 125-B Rail Cask, presents results therefrom, and correlates findings with Regulation 10 CFR 71 of the U.S. Nuclear Regulatory Commission

  7. A review of tritium licensing requirements

    International Nuclear Information System (INIS)

    Meikle, A.B.

    1982-12-01

    Present Canadian regulations and anticipated changes to these regulations relevant to the utilization of tritium in fusion facilities and in commercial applications have been reviewed. It is concluded that there are no serious licensing obstacles, but there are a number of requirements which must be met. A license will be required from Atomic Energy Control Board if Ontario Hydro tritium is to be applied by other users. A license is required from the Federal Government to export or import tritium. A licensed container will be required for the storage and shipping of tritium. The containers being designed by AECL and Ontario Hydro and which are currently being tested will adequately store and ship all of the Ontario Hydro tritium but are unnecessarily large for the small quantities required by the commercial tritium users. Also, some users may prefer to receive tritium in gaseous form. An additional, smaller container should be considered. The licensing of overseas fusion facilities for the use of tritium is seen as a major undertaking offering opportunities to Canadian Fusion Fuels Technology Project to undertake health, safety and environmental analysis on behalf of these facilities

  8. 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

  9. 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

  10. 31 CFR 594.307 - Licenses; general and specific.

    Science.gov (United States)

    2010-07-01

    ...) OFFICE OF FOREIGN ASSETS CONTROL, DEPARTMENT OF THE TREASURY GLOBAL TERRORISM SANCTIONS REGULATIONS General Definitions § 594.307 Licenses; general and specific. (a) Except as otherwise specified, the term...

  11. Procedural violation in the licensing procedure and possible legal consequences; Verfahrensmaengel im Konzessionierungsverfahren und etwaige Rechtsfolgen

    Energy Technology Data Exchange (ETDEWEB)

    Meyer-Hetling, Astrid; Probst, Matthias Ernst; Wolkenhauer, Soeren [Kanzlei Becker Buettner Held (BBH), Berlin (Germany)

    2012-07-15

    With respect to paragraph 46 sect. 2 to 4 EnWG (Energy Economy Law) communities are required to provide a publication procedure and competition procedure ('licensing procedure') for the new assignment of easement agreements for the establishment of local power supply systems and natural gas supply systems. The specific design of the selection process legally is regulated only rudimentary. Nevertheless old concessionaires increasingly deny the statutory grid transfer to the new concessionaires relying on supposed errors in the selection process. The unclear legal situation and the inconsistent, sometimes unreasonably strict jurisdiction and jurisprudence of antitrust as well as regulatory authorities resulted to a considerable legal certainty in communities and grid operators. Unless the legislature establishes the necessary legal clarity, the competent courts and authorities are invoked to act moderately in the examination of licensing procedures.

  12. Software licenses: Stay honest!

    CERN Multimedia

    Computer Security Team

    2012-01-01

    Do you recall our article about copyright violation in the last issue of the CERN Bulletin, “Music, videos and the risk for CERN”? Now let’s be more precise. “Violating copyright” not only means the illegal download of music and videos, it also applies to software packages and applications.   Users must respect proprietary rights in compliance with the CERN Computing Rules (OC5). Not having legitimately obtained a program or the required licenses to run that software is not a minor offense. It violates CERN rules and puts the Organization at risk! Vendors deserve credit and compensation. Therefore, make sure that you have the right to use their software. In other words, you have bought the software via legitimate channels and use a valid and honestly obtained license. This also applies to “Shareware” and software under open licenses, which might also come with a cost. Usually, only “Freeware” is complete...

  13. 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

  14. 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

  15. 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.

  16. Cesium-137 in ash from combustion of biofuels. Application of regulations from the Swedish Radiation Safety Authority

    International Nuclear Information System (INIS)

    Sjoeblom, Rolf

    2009-01-01

    The Swedish Radiation Safety Authority, SSM, has issued an ordinance on ash contaminated with Cesium-137. It implies amongst other things that ash containing 0,5 - 10 kBq/kg Cesium-137 (so-called contaminated ash) can be used for geotechnical purposes provided that the content in a near-by well does not exceed 1 Bq/litre and that the increase in a near-by fish producing recipient does not exceed 0,1 Bq/litre. The initial plan with the presently reported work was to provide a compilation of how the ordinance for Cesium-137 can be applied in practical work. It became evident, however, in the course of the work that issues related to the co-variation between potassium and Cesium needed further investigation. As a result, the present report comprises also a compilation of this extended information search. Cesium-137 is present in ash as a result of the accident in a nuclear power reactor in Chernobyl in 1986 during which material having a very small grain size was spread to a high altitude. A few days later, Cesium-137 was deposited during rains over large parts of Sweden. This activity penetrated to a depth of one or a few decimetres during the course of the subsequent few days and weeks, after which it was partially taken up by plants and spread in the ecosystem. Section 2 has the character of a handbook. It provides basic information on radiation, and also about the ordinance and other material from the SSI. Section 3 comprises compilations of relevant international status of knowledge. This regards how potassium and Cesium behave in soil and ash, and also how spreading of Cesium can be modelled. Cesium behaves similarly to Potassium but with the difference that Cesium is bonded much more strongly to mineral soil and ash. Potassium and Cesium appears in soil in four different forms: dissolved in the pore water, exchangeable, non-exchangeable and as bonded to minerals. The amount dissolved in the pore water is the smallest and that bonded to minerals is the largest

  17. 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

  18. ABWR certification work brings US licensing stability nearer

    International Nuclear Information System (INIS)

    Wilkins, D.R.; Quirk, J.F.

    1991-01-01

    The Advanced Boiling Water Reactor (ABWR) is now approaching Final Design Approval by the US Nuclear Regulatory Commission (NRC) and will then proceed on to the certification phase of the NRC's new standard plant licensing process. Successful completion of this will usher in a new era of standardization and reactor licensing stability in the US. (author)

  19. 48 CFR 1852.225-70 - Export Licenses.

    Science.gov (United States)

    2010-10-01

    ... writing, that the Contracting Officer authorizes it to export ITAR-controlled technical data (including... licenses or other approvals, if required, for exports of hardware, technical data, and software, or for the provision of technical assistance. (b) The Contractor shall be responsible for obtaining export licenses, if...

  20. 22 CFR 120.21 - Manufacturing license agreement.

    Science.gov (United States)

    2010-04-01

    ... 22 Foreign Relations 1 2010-04-01 2010-04-01 false Manufacturing license agreement. 120.21 Section... DEFINITIONS § 120.21 Manufacturing license agreement. An agreement (e.g., contract) whereby a U.S. person grants a foreign person an authorization to manufacture defense articles abroad and which involves or...

  1. Secure matching of Dutch car license plates

    NARCIS (Netherlands)

    Sunil, A.B.; Erkiny, Z.; Veugenyz, T.

    2016-01-01

    License plate matching plays an important role in applications like law enforcement, traffic management and road pricing, where the plate is first recognized and then compared to a database of authorized vehicle registration plates. Unfortunately, there are several privacy related issues that should

  2. Is Licensing Public Protection of Professional Protectionism?

    Science.gov (United States)

    Hogan, Daniel B.

    1979-01-01

    Granting of licenses to practice has long been linked to academic credentials, but this system offers more protection to the professions than to the public. There is an immediate need to break the credentials monopoly by opening up alternative routes to obtaining credentials. (Author/MLW)

  3. 14 CFR 1274.942 - Export licenses.

    Science.gov (United States)

    2010-01-01

    ... writing, that the Agreement Officer authorize it to export ITAR-controlled technical data (including... appropriate licenses or other approvals, if required, for exports of hardware, technical data, and software, or for the provision of technical assistance. (b) The Recipient shall be responsible for obtaining...

  4. Use of modeling in repository licensing

    International Nuclear Information System (INIS)

    McGarry, J.M. III; Echols, F.S.

    1995-01-01

    A review of the regulatory history of the Nuclear Regulatory Commission (NRC) regulations applicable to the licensing of a geologic repository, as well as a review of NRC administrative (licensing) decisions and federal case law, support the NRC's use of simplified models, in appropriate circumstances, which provide well-documented and reasonably conservative bounding assumptions, together with the use of expert judgement, natural analogues, and other aids to supplement available information, in reaching its reasonable assurance determination whether the public health and safety will be adequately protected if the Yucca Mountain, Nevada site should be licensed for development as a geologic repository. Specific examples are provided to assist the reader to better understand how such qualitative concepts as open-quote reasonable assurance close-quote, open-quote reasonably conservative close-quote, and open-quote adequate close-quote protection are used in an administrative context to resolve technical issues

  5. Child Day Care Centers, This dataset contains the licensed daycare center locations in MD. Addresses were provided by the Department of Labor Licensing and Regulation (DLLR), and geocoded using Maryland Statewide Addressing Initiative Centerline., Published in 2012, 1:2400 (1in=200ft) scale, Towson University.

    Data.gov (United States)

    NSGIC Education | GIS Inventory — Child Day Care Centers dataset current as of 2012. This dataset contains the licensed daycare center locations in MD. Addresses were provided by the Department of...

  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. Licensing of spent nuclear fuel dry storage in Russia

    International Nuclear Information System (INIS)

    Kislov, A.I.; Kolesnikov, A.S.

    1999-01-01

    The Federal nuclear and radiation safety authority of Russia (Gosatomnadzor) being the state regulation body, organizes and carries out the state regulation and supervision for safety at handling, transport and storage of spent nuclear fuel. In Russia, the use of dry storage in casks will be the primary spent nuclear fuel storage option for the next twenty years. The cask for spent nuclear fuel must be applied for licensing by Gosatomnadzor for both storage and transportation. There are a number of regulations for transportation and storage of spent nuclear fuel in Russia. Up to now, there are no special regulations for dry storage of spent nuclear fuel. Such regulations will be prepared up to the end of 1998. Principally, it will be required that only type B(U)F, packages can be used for interim storage of spent nuclear fuel. Recently, there are two dual-purpose cask designs under consideration in Russia. One of them is the CONSTOR steel concrete cask, developed in Russia (NPO CKTI) under the leadership of GNB, Germany. The other cask design is the TUK-104 cask of KBSM, Russia. Both cask types were designed for spent nuclear RBMK fuel. The CONSTOR steel concrete cask was designed to be in full compliance with both Russian and IAEA regulations for transport of packages for radioactive material. The evaluation of the design criteria by Russian experts for the CONSTOR steel concrete cask project was performed at a first stage of licensing (1995 - 1997). The CONSTOR cask design has been assessed (strength analysis, thermal physics, nuclear physics and others) by different Russian experts. To show finally the compliance of the CONSTOR steel concrete cask with Russian and IAEA regulations, six drop tests have been performed with a 1:2 scale model manufactured in Russia. A test report was prepared. The test results have shown that the CONSTOR cask integrity is guaranteed under both transport and storage accident conditions. The final stage of the certification procedure

  8. Renovation of the exploitation authorization

    International Nuclear Information System (INIS)

    Garcia Delgado, L.

    2009-01-01

    With the current administrative framework, nuclear power plant licenses are granted for the-year periods. The Cofrentes NPP Operating License is valid until March 2011 and its renewal has to be requested before March 2010. Cofrentes NPP is working on an application for renewal until 2021. This work requires assessments of the facility's nuclear Safety-related performance between 1999 and 2008, as well as evaluations and subsequent implementation of new legislation that, when applied, will benefit safety. (Author)

  9. Overview of NORM and activities by a NORM licensed permanent decontamination and waste processing facility

    Energy Technology Data Exchange (ETDEWEB)

    Mirro, G.A. [Growth Resources, Inc., Lafayette, LA (United States)

    1997-02-01

    This paper presents an overview of issues related to handling NORM materials, and provides a description of a facility designed for the processing of NORM contaminated equipment. With regard to handling NORM materials the author discusses sources of NORM, problems, regulations and disposal options, potential hazards, safety equipment, and issues related to personnel protection. For the facility, the author discusses: description of the permanent facility; the operations of the facility; the license it has for handling specific radioactive material; operating and safety procedures; decontamination facilities on site; NORM waste processing capabilities; and offsite NORM services which are available.

  10. 10 CFR 51.80 - Draft environmental impact statement-materials license.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Draft environmental impact statement-materials license. 51...-Regulations Implementing Section 102(2) Draft Environmental Impact Statements-Materials Licenses § 51.80 Draft environmental impact statement—materials license. (a) The NRC staff will either prepare a draft environmental...

  11. 10 CFR 51.97 - Final environmental impact statement-materials license.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Final environmental impact statement-materials license. 51...-Regulations Implementing Section 102(2) Final Environmental Impact Statements-Materials Licenses § 51.97 Final environmental impact statement—materials license. (a) Independent spent fuel storage installation (ISFSI...

  12. 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)

  13. Licensing the Sun

    Science.gov (United States)

    Demski, Jennifer

    2013-01-01

    The University of San Diego (USD) and Point Loma Nazarene University (PLNU) are licensing the sun. Both California schools are generating solar power on campus without having to sink large amounts of capital into equipment and installation. By negotiating power purchasing agreements (PPAs) with Amsolar and Perpetual Energy Systems, respectively,…

  14. 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

  15. European regulation model for herbal medicine: The assessment of the EU monograph and the safety and efficacy evaluation in marketing authorization or registration in Member States.

    Science.gov (United States)

    Qu, Liping; Zou, Wenjun; Wang, YiTao; Wang, Mei

    2018-03-15

    The European Union (EU) has created a regulatory framework for herbal medicinal products (HMPs) since the enforcement of Directive 2004/24/EC. Substantial achievements have been made, with 1719 traditional use marketing registrations (TURs) and 859 well-established use marketing authorizations (WEU-MAs) for HMPs granted by the end of 2016. Apparently, the European regulation model has worked out well and in that the essential feature is the use of EU herbal monographs into those granted WEU-MAs and TURs. A systematic analysis of the European regulation model for HMPs and the EU herbal monograph's part of this model are undertaken to assist understanding of the EU legislation particularly for interested parties those from outside EU area, and afterwards, to help in decision-making in the HMPs registration in European market for pharmaceutical companies, as well as in the establishment of legislation in countries with strong traditional use of herbal remedies. A search of PubMed, ScienceDirect, the European Medicines Agency website and the Heads of Medicines Agencies website was conducted (up to December 2017), and the available information on regulation of HMPs in the EU was collected. The evaluation of applications by National Competent Authorities (NCAs) at a national level together with the assessment of EU monographs by the Committee on Herbal Medicinal Products (HMPC) at the European level constitute the European regulation framework for HMPs. As the scientific opinion about the safety and efficacy of HMPs from HMPC, the EU herbal monographs have been given a constitutional-based meaning to the TURs and WEU-MAs of HMPs and play a supportive function in the marketing procedure in Member States. The European framework has provided a powerful regulation model for harmonization of scientific assessment and facilitation of product marketing. For the pharmaceutical industries particularly those outside the EU, optimal use of the EU herbal monograph in their marketing

  16. 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

  17. 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.

  18. Conformation of an evaluation process for a license renovation solicitude of a nuclear power plant in Mexico; Conformacion de un proceso de evaluacion para una solicitud de renovacion de licencia de una central nuclear en Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Serrano R, M. L., E-mail: mlserrano@cnsns.gob.mx [Comision Nacional de Seguridad Nuclear y Salvaguardias, Dr. Barragan No. 779, Col. Narvarte, 03020 Mexico D. F. (Mexico)

    2012-10-15

    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)

  19. 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

  20. 77 FR 4887 - DOE Patent Licensing Regulations

    Science.gov (United States)

    2012-02-01

    ... administered by the National Nuclear Security Administration (NNSA) for NNSA facilities. The NNSA Deputy... issue a Family Policymaking Assessment for any rule or policy that may affect family well being. This rule will have no impact on family, the autonomy or integrity of the family as an institution...

  1. The Atomic Safety and Licensing Board Panel

    International Nuclear Information System (INIS)

    1998-01-01

    Through the Atomic Energy Act, Congress made is possible for the public to get a full and fair hearing on civilian nuclear matters. Individuals who are directly affected by any licensing action involving a facility producing or utilizing nuclear materials may participate in a formal hearing, on the record, before independent judges on the Atomic Safety and Licensing Board Panel (ASLBP or Panel). Frequently, in deciding whether a license, permit, amendment, or extension should be granted to a particular applicant, the Panel members must be more than mere umpires. If appropriate, they are authorized to go beyond the issues the parties place before them in order to identify, explore, and resolve significant questions involving threats to the public health and safety that come to a board's attention during the proceedings. This brochure explains the purpose of the panel. Also addressed are: type of hearing handled; method of public participation; formality of hearings; high-level waste; other panel responsibilities and litigation technology

  2. 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

  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. 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. Atomic Energy Control Regulations

    International Nuclear Information System (INIS)

    1992-01-01

    This is the consolidated text of the Atomic Energy Control Regulations of 17 March 1960, with amendments to 27 August 1992. The Regulations cover the licensing of nuclear facilities, radiation sources, including uranium mining, radiation protection questions, etc. (NEA)

  6. 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)

  7. 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)

  8. The Public Opinion participation in the Nuclear Facilities Licensing Regime: A study for The Egyptian Nuclear Law and other countries laws

    International Nuclear Information System (INIS)

    Ali, A. M.; Abd El-Moniem, A. E.

    2012-12-01

    This paper deals with the Nuclear Facilities Licensing Regime and the public Opinion participation. It discusses the general conceptual framework such as the importance of public opinion in the licensing process for nuclear facilities. It deals with the transparency principle and the nuclear safety. It also an analysis the Egyptian nuclear law for regulating the nuclear and radiological activities(law No.7) and its provisions that regulate the participation of the public in the licensing process (Article No.12 paragraph No.7 and 16 ) that staled that the regulatory body will set the regulation to involve the public in the licensing and it will also issues publicly a garrulity report about the nuclear safety situation in the state. It also deals with the legal rules for licensing and the participation of public in it many states such as Japan, France and Germany. The paper concluded that the lunch of a nuclear programme should lunch, in parallel, a programme for the public communications because in the absent of such a public programme, the political decisions of nuclear programme might be lose its effectiveness and the programme might be slow dow. (Author)

  9. 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)

  10. 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)

  11. 77 FR 2057 - Aquamac Corporation; Notice of Termination of License by Implied Surrender and Soliciting...

    Science.gov (United States)

    2012-01-13

    ... Corporation; Notice of Termination of License by Implied Surrender and Soliciting Comments and Motions To.... Type of Proceeding: Termination of License by Implied Surrender. b. Project No.: 2927-006. c. Date... authorized, the licensee is in violation of the terms and conditions of the license. l. This notice is...

  12. 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

  13. A new licensing strategy for Canadian mobile earth stations

    Science.gov (United States)

    Amero, Ronald G.

    1990-01-01

    Initiatives presently under consideration by the Department of Communications which will greatly simplify the licensing process for mobile earth stations are addressed. The current licensing approach is reviewed and the limitations of that system identified. A new approach is needed to respond to the needs of mobile satellite users in the 1990's and beyond, one which will have a minimal impact on the user while still respecting the legislative responsibilities of the department under the new Radiocommunication Act and the General Radio Regulations. The objective of this new strategy is to lead to a transparent licensing scheme for the end user, which in turn could lead to license exemption of blanket licenses as soon as possible.

  14. Licensing Air and Transboundary Shipments of Spent Nuclear Fuel

    International Nuclear Information System (INIS)

    Komarov, S.V.; Budu, M.E.; Derganov, D.V.; Savina, O.A.; Bolshinsky, I.M.; Moses, S.D.; Biro, L.

    2016-01-01

    Since 1996 the IAEA TS-R-1 regulation included new requirements applicable to transport of fissile materials by air. The later 2005 and 2009 editions confirmed the validity of those provisions. Despite the fact that the IAEA TS-R-1 allows for air shipments of SNF in Type B and Type C packages, the examples of such shipments are not abundant. Nuclear regulatory bodies and transport safety experts are cautious about air shipments of SNF. Why so? What are the risks? What are the alternatives? In this new regulatory framework, in 2009, two air shipments in Type B packages of Research Reactor (RR) Spent Nuclear Fuel (SNF) from Romania and Libya were performed under the U.S. DOE/NNSA RRRFR Program. The first licensing process of such shipment brought up many questions about package and shipment safety from the licensing experts' side and so the scope of analyses exceeded the requirements of IAEA. Under the thorough supervision of Rosatom and witnessed by DOE and CNCAN, all questions were answered by various strength analyses and risk evaluations. But the progress achieved didn't stop here. In 2010-2011, an energy absorption container (EAC) with titanium spheres as absorbers based on the SKODA VPVR/M cask was designed as the first Type C package in the world destined for RR SNF, currently under approval process. At the same time, intense preparations for the safe removal of the Russian-origin damaged RR SNF from Serbia, Vinca were in progress. The big amount of SNF and its rapidly worsening condition imposed as requirements to organize only one shipment as fast as possible, i.e. using at the maximum extent the entire experience available from other SNF shipments. The long route, several transit countries and means of transport, two different casks, new European regulations and many other issues resulted for the Serbian shipment in one of the most complex SNF shipments’ licensing exercise. This paper shows how the international regulatory framework ensures the

  15. A licensing discussion: SMRs in Canada

    International Nuclear Information System (INIS)

    De Vos, M.

    2013-01-01

    The CNSC (Canadian AECB) is ready to regulate Small Modular Reactors (SMR) facilities in Canada. The CNSC is well situated to engage with proponents of SMR reactors in design reviews or licensing discussions. A risk-informed (graded) approach is possible in many instances for reactors but it is not a relaxation of requirements. The vendor design review process helps reduce regulatory risks by encouraging early engagement.

  16. 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

  17. Open licenses and their compliance with the new private law (new civil code)

    OpenAIRE

    Kráľ, Štefan

    2013-01-01

    Computer programs are widely licensed under open (public, open source, free) licenses. This thesis examines whether the open license (especially GNU GPL) is in compliance with the Czech law and which business models are used to generate profit distributing open computer programs. On the basis of analysis of legislation, case law and doctrinal literature the author assesses whether open licenses are admissible under the new Civil Code. The thesis also provides an overview of commonly used busi...

  18. Environmental policy on the fixed-fee licensing of eco-technology under foreign penetration

    OpenAIRE

    Kim, Seung-Leul; Lee, Sang-Ho

    2016-01-01

    This study investigates environmental policy on the fixed-fee licensing strategy of clean eco-technology by an innovator having foreign ownership. We show that near-zero emission taxes accompanied by non-exclusive licensing regulation can improve social welfare when the cost gap is small or foreign penetration is high. However, when foreign ownership is not high, exclusive licensing regulations with an appropriate emission tax policy may improve social welfare.

  19. 10 CFR 50.10 - License required; limited work authorization.

    Science.gov (United States)

    2010-01-01

    ... retaining walls within an excavation, installation of foundations, or in-place assembly, erection..., subsurface preparation, placement of backfill, concrete, or permanent retaining walls within an excavation... plant emergency operating procedures; (iii) SSCs whose failure could prevent safety-related SSCs from...

  20. Cogeneration plants in Italy: Licensing aspects

    International Nuclear Information System (INIS)

    Buscaglione, A.

    1991-01-01

    This paper focusses on administrative/bureaucratic problems relative to the licensing of cogeneration plants in Italy. The current stumbling block appears to lie in organizational difficulties relative to the coordination of various Government authorized safety committees responsible for the drafting up of suitable legislation governing cogeneration plant fire safety aspects. The author cites the possible environmental benefits in terms of air pollution abatement that could have been had with the timely start-up of a new 7 MW plant (in Lombardia) still awaiting its go-ahead authorization

  1. Licensing of radioactive materials and facilities in the Philippines

    International Nuclear Information System (INIS)

    Mateo, A.J.

    1976-12-01

    The importation, acquisition, possession, use, sale and/ or transfer of radioactive materials need to be regulated and controlled in order to safeguard the importer, possessor, user or seller and the general public as well. The Philippine Atomic Energy Commission pursuant to Republic Act No. 2067, as amended and Republic Act No. 5207, has been charged by the government to control, regulate and license all the radioactive materials and facilities in the Philippines. Licensing and control is accomplished through a system of rules and regulations applicable to all importers, possessors, users or sellers of radioactive materials

  2. Example of establishing the recycling of scrap metal as a waste management option within German regulations

    International Nuclear Information System (INIS)

    Bodenstein, Matthias; Delfs, Johannes; Karschnick, Oliver

    2014-01-01

    The German Atomic Energy Act (Atomgesetz, AtG) specifies the German nuclear licensing and supervising regulations. On that basis the German federal states are responsible for licensing and supervising of nuclear power plants (NPPs) located in that state. The Ministry of Energy, Agriculture, the Environment and Rural Areas (MELUR) is the authority responsible for the state Schleswig-Holstein, in which the NPPs Brokdorf, Brunsbuettel, Kruemmel and the research reactor HZG are located. In the licensing and supervisory procedures the authority may consult authorized experts. In addition to the AtG, the German Radiation Protection Ordinance (Strahlenschutzverordnung, StrlSchV) specifies regulations for clearance according to the 10 μSv-concept. The clearance of metal by recycling / melting is one option within the regulations of the StrlSchV. For a clearance an additional license given by the MELUR is necessary. In that license and the application documents as well as in the supervisory procedures very specific regulations are implemented. This includes regulations for clearance at third parties in foreign countries. In this talk a short introduction to the German regulations focussed on clearance according to the 10 μSv-concept will be given. The specific regulations in the license of clearance will be presented and also the application documents for NPPs in Schleswig-Holstein will be discussed. Furthermore it will be illustrated on what terms the MELUR decided to agree upon the recycling of scrap metal with the aim of clearance according to Radiation Protection 89 in foreign countries along with the German regulatory framework. (authors)

  3. 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)

  4. 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

  5. License to Learn

    DEFF Research Database (Denmark)

    Leone, Maria Isabella; Boccardelli, Paolo; Reichstein, Toke

    2016-01-01

    the technology. Drawing on a sample of 133 licensees and an equal number of matched nonlicensees, we present empirical evidence that thick contracts propel the licensees' likelihood of introducing new inventions. It is also found that thick contracts act as a substitute for licensees' absorptive capacity....... Licensees that are more familiar with the licensed technology are in less need of assistance from the licensors to assimilate and integrate the knowledge. However, this substitution effect is neutralized once the hurdle of invention has been overcome, meaning that the licensees have succeeded to ignite...... the invention process, suggesting the exploitation of the learning curve, triggered by their mutual understanding....

  6. 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

  7. Validation, acceptance and licensing

    International Nuclear Information System (INIS)

    Wene, C.O.

    1992-01-01

    The licensing process requires communication of complex scientific and technical information. In this paper transfer of such information is discussed using concepts and ideas from systems analysis, cybernetics and argumentation theory. A simple model for the decision process is developed. The analysis stresses the need for careful design of the communication channels between the three systems involved: the political system, the judicial-regulatory system and the scientific-technical community. The Dialogue - Scenario project initiated by the Swedish nuclear Inspectorate is briefly presented

  8. Generic environmental impact statement for license renewal of nuclear plants

    International Nuclear Information System (INIS)

    1996-05-01

    Volume 2 of the Generic Environmental Impact Statement for License Renewal of Nuclear Plants contains the appendices. These include: (A) General characterisitics and environmental settings of domestic nuclear plants, (B) Definition of impact initiators, (C) Socioeconomics and case studies, (D) Aquatic organisms and human health, (E) Radiation protection considerations, (F) Methodology for assessing impacts to aquatic ecology and water resources, (G) Postulated accidents, and (H) Environmental statutes and regulations affecting license renewal

  9. 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)

  10. Westinghouse AP1000 licensing maturity

    International Nuclear Information System (INIS)

    Schulz, T.; Vijuk, R.P.

    2005-01-01

    The Westinghouse AP1000 Program is aimed at making available a nuclear power plant that is economical in the U.S deregulated electrical power industry in the near-term. The AP1000 is two-loop 1000 MWe pressurizer water reactor (PWR). It is an up rated version of the AP600. The AP1000 uses passive safety systems to provide significant and measurable improvements in plant simplification, safety, reliability, investment protection and plant costs. The AP1000 uses proven technology, which builds on over 35 years of operating PWR experience. The AP1000 received Final Design Approval by the United States Nuclear Regulatory Commission (U.S. NRC) in September 2004. The AP1000 meets the US utility requirements. The AP1000 and its sister plant the AP600 have gone through a very through and complete licensing review. This paper describes the U.S. NRC review efforts of both the AP600 and the AP1000. The detail of the review and the independent calculations, evaluations and testing is discussed. The AP600 licensing documentation was submitted in 1992. The U.S. NRC granted Final Design Approval in 1999. During the intervening 7 years, the U.S. NRC asked thousands of questions, performed independent safety analysis, audited Westinghouse calculations and analysis, and performed independent testing. The more significant areas of discussion will be described. For the AP1000 Westinghouse first engaged the U.S. NRC in pre-certification discussions to define the extent of the review required, since the design is so similar to the AP600. The AP1000 licensing documentation was submitted in March 2002. The U.S. NRC granted Final Design Approval in September 2004. During the intervening 2 1/2 years, the U.S. NRC asked hundreds of questions, performed independent safety analysis, audited Westinghouse calculations and analysis, and performed independent testing. The more significant areas of discussion will be described. The implications of this review and approval on AP1000 applications in

  11. 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)

  12. Radiation Safety of Accelerator Facility with Regard to Regulation

    International Nuclear Information System (INIS)

    Dedi Sunaryadi; Gloria Doloresa

    2003-01-01

    The radiation safety of accelerator facility and the status of the facilities according to licensee in Indonesia as well as lesson learned from the accidents are described. The atomic energy Act No. 10 of 1997 enacted by the Government of Indonesia which is implemented in Radiation Safety Government Regulation No. 63 and 64 as well as practice-specific model regulation for licensing request are discussed. (author)

  13. 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

  14. Regulatory Approach To and Lessons Learned with Licensing of Service Life Extension at PAKS NPP

    International Nuclear Information System (INIS)

    Petofi, G.

    2012-01-01

    Paks Nuclear Power Plant of Hungary decided to extend the original design lifetime of the plant by 20 years, which expires on December 31, 2012 concerning unit 1. The Hungarian Atomic Energy Authority established the legal environments in order to license the extension using an approach similar to that followed in the United States. The regulation specifies the pre-conditions for the extension, defines the scoping and screening process for the passive and long lived systems, structures and components to be involved in the licensing and the respective methods of treatment and also determines how the active components shall be dealt with during the extended lifetime. The regulatory procedure is a two-step process including the oversight of the preparatory programme of the operator for the extension that started 4 years before the expiry of the lifetime and the licensing process itself, which is currently under way for unit 1 after the submittal of the licensee's application at the end of 2011. The first experiences with the regulatory assessment of the application are available yet and presented in this paper. (author)

  15. 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.

  16. International conference on strengthening of nuclear safety in Eastern Europe. Armenian Nuclear Regulatory Authority

    International Nuclear Information System (INIS)

    Nersesyan, V.

    1999-01-01

    The status of the Armenian Nuclear Regulatory Authority (ANRA) are described in detail with its main task and responsibilities concerning regulations and surveillance of nuclear and radiation safety. The following issues are presented: nuclear legislation; inspection activities; licensing of significant safety related modifications and modernization of NPPs; incidents at NPPs; personnel training; emergency planning; surveillance of nuclear materials; radioactive waste management; and plan of the ANRA perspective development

  17. 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....

  18. 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

  19. Process of licensing nuclear facilities (resume from the Spanish National Report for the Joint Convention, 2005)

    International Nuclear Information System (INIS)

    Prieto, N.

    2007-01-01

    The process of licensing both nuclear and radioactive facilities is governed by the Regulation on Nuclear and Radioactive Facilities (Span. Reglamento de Instalaciones Nucleares y Radiactivas, RINR), approved by Royal Decree 1836/1999, of 3 December. According to the RINR, these authorizations are granted by the Ministry of Industry, Tourism and Trade (Span. Ministerio de Industria, Turismo y Comercio, MITYC), to which the corresponding requests should be addressed, along with the documentation required in each case, The MITYC sends a copy of each request and accompanying documentation to the Nuclear Safety Council (Span. Consejo de Seguridad Nuclear, CSN) for its mandatory report.) The CSN reports are mandatory and binding, both were negative or withholding in nature with respect to the request and, when positive, as regards the conditions established. On receiving the report from the CSN, and following whatever decisions or further reports might be required in each case, the MITYC will adopt the appropriate resolution. System for the licensing of nuclear facilities. According to the definitions included in the RINR, the following are nuclear facilities: - Nuclear power plants. - Nuclear reactors. - Manufacturing facilities using nuclear fuels to produce nuclear substances and those at which nuclear substances are treated. - Facilities for the permanent storage of nuclear substances. In compliance with the RINR, the nuclear facilities require different permits or administrative authorizations for their operation, these being the preliminary or site authorization, the construction permit, the operating permit, the authorization for modification and the dismantling permit. The procedure for the awarding of each of these authorizations is regulated by the Regulation itself and is briefly described below. (author)

  20. 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)

  1. Regulating nuclear and radiation safety in the frame of the Chernobyl shelter Implementation Plan

    Energy Technology Data Exchange (ETDEWEB)

    Bykov, V.; Demchyuk, A.; Kilochitska, T.; Redko, V. [State Nuclear Regulatory Committee of Ukraine, SNRCU, Arsenalna St. 9/11, Kyiv (Ukraine); Bogorinski, P. [GRS/IPSN-RISKAUDIT, Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, Koeln (Germany); Vasilchenko, V.; Erickson, L.; Kadkin, E.; Kondratyev, S.; Kutina, L.; Smyshliaeva, S. [SSTC NRS, Stusa St. 35-37, 03142, Kyiv (Ukraine)

    2003-07-01

    Since 1998 the Shelter Implementation Plan (SIP) has been carried out on the Chernobyl NPP Unit 4 (the object Shelter - OS). The State Nuclear Regulatory Committee of Ukraine (SNRCU) recognizes the exceptional importance of successful and efficient SIP implementation and acts accordingly in regulation, licensing, and inspection. Technical support of the SNRCU in SIP licensing are provided by the State Scientific and Technical Center for Nuclear and Radiation Safety (SSTC) and the SIP Licensing Consultant (LC) representing RISKAUDIT IPSN/GRS International and SCIENTECH, Inc. Support of the SNRCU is also provided by the International Consultative Committee of Regulatory Bodies (ICCRB). ICCRB members represent regulatory authorities from nine European countries, Canada and the U.S. Summarizing the information above, it can be stated that a sound basis has been created for the licensing process for SIP. The approach for using the regulatory base has been determined. It ensures the establishment of safety objectives and gives ChNPP the freedom of optimal choice of specific technical decisions. The License has been issued for OS-related activities and a number of documents have been developed to conduct an effective and high quality authorization process: the Licensing Process; Recommendations on single SSR, Licensing Plan for SIP. The Order of State Safety Supervision for SIP has been approved. Working groups are functioning, whose purposes are to coordinate actions of participants in authorization activities, including ChNPP, SNRCU, and other RA.

  2. Regulating nuclear and radiation safety in the frame of the Chernobyl shelter Implementation Plan

    International Nuclear Information System (INIS)

    Bykov, V.; Demchyuk, A.; Kilochitska, T.; Redko, V.; Bogorinski, P.; Vasilchenko, V.; Erickson, L.; Kadkin, E.; Kondratyev, S.; Kutina, L.; Smyshliaeva, S.

    2003-01-01

    Since 1998 the Shelter Implementation Plan (SIP) has been carried out on the Chernobyl NPP Unit 4 (the object Shelter - OS). The State Nuclear Regulatory Committee of Ukraine (SNRCU) recognizes the exceptional importance of successful and efficient SIP implementation and acts accordingly in regulation, licensing, and inspection. Technical support of the SNRCU in SIP licensing are provided by the State Scientific and Technical Center for Nuclear and Radiation Safety (SSTC) and the SIP Licensing Consultant (LC) representing RISKAUDIT IPSN/GRS International and SCIENTECH, Inc. Support of the SNRCU is also provided by the International Consultative Committee of Regulatory Bodies (ICCRB). ICCRB members represent regulatory authorities from nine European countries, Canada and the U.S. Summarizing the information above, it can be stated that a sound basis has been created for the licensing process for SIP. The approach for using the regulatory base has been determined. It ensures the establishment of safety objectives and gives ChNPP the freedom of optimal choice of specific technical decisions. The License has been issued for OS-related activities and a number of documents have been developed to conduct an effective and high quality authorization process: the Licensing Process; Recommendations on single SSR, Licensing Plan for SIP. The Order of State Safety Supervision for SIP has been approved. Working groups are functioning, whose purposes are to coordinate actions of participants in authorization activities, including ChNPP, SNRCU, and other RA

  3. UK safety and standards for radioactive waste management and decommissioning on nuclear licensed sites

    International Nuclear Information System (INIS)

    Mason, D.J.

    2001-01-01

    This paper discusses the regulation of radioactive waste and decommissioning in the United Kingdom and identifies the factors considered by HM Nuclear Installations Inspectorate in examining the adequacy arrangements for their management on nuclear licensed sites. The principal requirements are for decommissioning to be undertaken as soon as reasonably practicable and that radioactive wastes should be minimised, disposed of or contained and controlled by storage in a passively safe form. However, these requirements have to be considered in the context of major organisational changes in the UK nuclear industry and the non-availability of disposal routes for some decommissioning wastes. The legislative framework used to regulate decommissioning of nuclear facilities in the UK is described. Reference is made to radioactive waste and decommissioning strategies, quinquennial reviews criteria for delicensing and the forthcoming Environmental Impact Assessment Regulations. (author)

  4. 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

  5. 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

  6. 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

  7. 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

  8. 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

  9. 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

  10. 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

  11. IRIS Licensing Status

    International Nuclear Information System (INIS)

    Kling, Charles L.; Carelli, Mario D.

    2006-01-01

    The International Reactor Innovative and Secure (IRIS) nuclear power plant is well into the pre-application review process with the US NRC and has accomplished its first near term goal of obtaining US NRC feedback on the long term testing program. To date, the IRIS team has submitted to the US NRC a number of documents patterned after the Evaluation Model Development and Assessment Process (EMDAP) outlined in Regulatory Guide 1,203. They have covered a detailed description of IRIS, initial safety analysis results, PIRT development for limiting transients, scaling analysis and a description of the test program. The IRIS Safety-by-Desing TM intrinsically eliminates and/or significantly reduces the consequences of traditional LWR accidents. In addition, the fewer passive safety systems are similar in principle to those of the US NRC approved AP1000 design. For these reasons, the IRIS testing program only needs to include those features unique to the IRIS design. NRC feedback was that the planned test program appeared to be complete and could generate sufficient information to support a Design Certification (DC) submittal. The US NRC has also stated that a DC application must include complete information regarding the test program. On this basis the IRIS team has initiated an aggressive program to conduct IRIS testing to support a DC submittal by the end of 2008. Subsequent US NRC review should be expeditious because of the AP1000 precedent, allowing IRIS to obtain its Final Design Approval (FDA) in 2012; thereby, maintaining its goal of deployment in the 2015-2017 time frame. The next steps in the pre-application review process will be to provide the US NRC with a road map of the anticipated IRIS licensing process, a review of current licensing requirements showing that IRIS meets or exceeds all current criteria and information to support the long term goal of redefining the Emergency Planning Zone (EPZ)

  12. 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

    lack of sufficient prerequisites for constructing and using a nuclear facility in a safe manner without causing injury to people, or damage to the environment or property, have arisen in the statement from Radiation and Nuclear Safety Authority STUK or elsewhere during the processing of the application. The Government's decision-in-principle shall be forwarded, without delay, to Parliament for perusal. Parliament may reject the decision-in-principle or decide that it shall remain in force as it stands. In 2000, the Government made a DiP on the disposal of spent fuel from Loviisa and Olkiluoto nuclear power plants in Olkiluoto bedrock. The DiP also stated that the project is allowed to proceed to the construction of the ONKALO underground rock characterization facility in Olkiluoto. From a legal standpoint, the DiP thus included a permit to start a limited construction of the repository. ONKALO may be later used as a part of the actual repository and therefore the regulatory approach to ONKALO construction is the same as is for the rest of the repository. The activities of Posiva, the implementing organisation, to fulfill the DiP are regulated by the Ministry of Employment and Economy (MEE) and Radiation and Nuclear Safety Authority (STUK). The regulatory oversight of Posiva's spent fuel disposal project (including the construction of ONKALO), consists of review and assessment and inspection. Other functions, such as establishing, updating or adopting safety principles, regulations and regulatory guides, are developed in parallel with the RD and D work. Pursuant to the Nuclear Energy Act, the decision-making and licensing system of nuclear facilities is based on a principle whereby safety is continuously reviewed, the assessments being further defined throughout the procedure so that the final safety assessments are only performed at the operating licensing stage. The actual licensing procedure starts after the Government's decision-in-principle. The

  13. Safety culture in nuclear installations - The role of the regulator

    International Nuclear Information System (INIS)

    Karigi, Alice W.

    2002-01-01

    Safety culture is an amalgamation of values, standards, morals and norms of acceptable behavior by the licensees, Radiation workers and the Regulator. The role played by a Regulator in establishing safety culture in a nuclear installation is that related to Authorization, review, assessment, inspection and enforcement. The regulator is to follow the development of a facility or activity from initial selection of the site through design, construction, commissioning, radioactive waste management through to decommissioning and closure. He is to ensure safety measures are followed through out the operation of the facility by laying down in the license conditions of controlling construction of nuclear installations and ensuring competence of the operators. (author)

  14. Safety regulations of radiation sources in industry in the Philippines

    Energy Technology Data Exchange (ETDEWEB)

    Borras, A M [Licensing and Evaluation Section, Nuclear Regulations Licensing and Safeguards Division, Philippine Nuclear Research Institute, Diliman, Quezon City (Philippines)

    1992-12-31

    The Philippine Nuclear Research Institute (PNRI) by virtue of Republic Act 2067, as amended, Republic Act 5207 and Executive Order 128 (1987), was mandated to advance and regulate the safe and peaceful applications of nuclear science and technology in the Philippines. The PNRI was formerly the Philippine Atomic Energy Commission established in 1958. This report aims to share the experiences of the PNRI on licensing and regulating the safe use of radioactive materials in industry, particularly in industrial gamma radiography, nuclear gauges and radioactive tracers. It enumerates the licensing and enforcement procedures. Some common problems encountered in the licensing and enforcement activities and comments of future plans to resolve the problems were also discussed. (Author).

  15. Safety regulations of radiation sources in industry in the Philippines

    International Nuclear Information System (INIS)

    Borras, A.M.

    1991-01-01

    The Philippine Nuclear Research Institute (PNRI) by virtue of Republic Act 2067, as amended, Republic Act 5207 and Executive Order 128 (1987), was mandated to advance and regulate the safe and peaceful applications of nuclear science and technology in the Philippines. The PNRI was formerly the Philippine Atomic Energy Commission established in 1958. This report aims to share the experiences of the PNRI on licensing and regulating the safe use of radioactive materials in industry, particularly in industrial gamma radiography, nuclear gauges and radioactive tracers. It enumerates the licensing and enforcement procedures. Some common problems encountered in the licensing and enforcement activities and comments of future plans to resolve the problems were also discussed. (Author)

  16. New overhead lines are required for the land - and Europe. The new regulation of the TEN-E regulations and their consequences for the Germann planning law and licensing law for high-voltage power lines under special consideration of the regulations of the public relations; Neue Leitungen braucht das Land - und Europa. Die Neuregelung der TEN-E-Leitlinien und deren Konsequenzen fuer das deutsche Planungs- und Genehmigungsrecht fuer Hoechstspannungsleitungen unter besonderer Beruecksichtigung der Vorschriften ueber die Oeffentlichkeitsbeteiligung

    Energy Technology Data Exchange (ETDEWEB)

    Schadtle, Kai [Stuttgart Univ. (Germany). Abt. fuer Rechtswissenschaft

    2013-05-15

    The German energy policy turnaround requires an optimization of the energy infrastructure. The energy policy objectives of the European Union with respect to competitiveness, security of supply and sustainability require a rapid expansion and transformation of the European energy infrastructure. Under this aspect, the author of the contribution under consideration reports on the revision of the TEN-E guidelines and their consequences for the German planning law and licensing law for high-voltage power lines with special consideration of the rules of the public relations. The national legal framework for the development of the German transmission system and the design of the new TEN-E guidelines for the trans-European network development are presented.

  17. Gas reactor international cooperative program interim report: United States/Federal Republic of Germany nuclear licensing comparison

    International Nuclear Information System (INIS)

    1978-09-01

    In order to compare US and FRG Nuclear Licensing, a summary description of United States Nuclear Licensing is provided as a basis. This is followed by detailed information on the participants in the Nuclear Licensing process in the Federal Republic of Germany (FRG). FRG licensing procedures are described and the rules and regulations imposed are summarized. The status of gas reactor licensing in both the U.S. and the FRG is outlined and overall conclusions are drawn as to the major licensing differences. An appendix describes the most important technical differences between US and FRG criteria

  18. Essays on the economics of licensing nuclear power plants

    International Nuclear Information System (INIS)

    Cohen, L.R.

    1979-01-01

    Regulation and licensing of nuclear power plants by the United States Atomic Energy Commission and the United States Nuclear Regulatory Commission are discussed. Chapter 1 overviews the licensing process and issues raised in licensing cases. Based on a sample of plants licensed between 1967 and 1978, a statistical study of the impact of public participation in licensing is performed. The study concludes that public participation has had a major impact on licensing and power-plant costs. The impact is due to a fundamental weakness of the Commissions: their inability to resolve certain issues related to acceptable social risk. The study has important policy implications for reforming the Federal licensing process. Chapter 2 contains an analysis of the Price-Anderson Act, a Federal program for compensating victims of large nuclear accidents. The Price-Anderson Act is placed within the context of generalized federal disaster relief. A model is developed that allows an evaluation programs on the basis of moral hazard and equity principles. Chapter 3 analyzes the Nuclear Regulatory Commission's treatment of its mandatory antitrust review of applicants for nuclear power plants. The main conclusion of the chapter is that the reviews have not addressed the central economic issues of antitrust that are relevant to nuclear power. Instead, the reviews contribute to further cartelization of the electric utility industry. While politically expedient, the reviews are counter-productive to the development of an optimal industry structure

  19. 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

  20. Reassessing Occupational Licensing Of Tour Guides (Opinion Piece

    Directory of Open Access Journals (Sweden)

    Amir SHANI

    2017-06-01

    Full Text Available It is conventionally held that to protect tourists from incompetent and/or unscrupulous tour guides, governments should require guides to be licensed in order to legally practice their profession. Despite the implementation of such regulatory statutes in many countries, it is argued in this opinion paper that the severe drawbacks of licensing demands should be re-evaluated by both policy-makers and tourism scholars. The licensing of guides is not only an ineffective means of quality assurance, with negative consequences for many of those involved, but it also undermines the ethical foundations of a free society. Furthermore, licensing is an archaic practice for ensuring standardization among the members of a profession in a way that is no longer suitable for addressing the challenges of the tourism industry in the 21st century, in which a wide variety of specialized and innovative guided tours are offered to tourists. Although this commentary presents a firm stand against the compulsory licensing of tour guides, it should be seen as an invitation for open discussion among tourism researchers regarding the necessity of licensing tour guides in particular, and of government tourism regulation in general. Moreover, further research is needed to clarify key points on the issue of the professional licensing of tour guides.