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...

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...

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...

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...

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...

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...

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)

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)

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

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

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...

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)

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

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...

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)

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...

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.

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)

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

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.

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

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...

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

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

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

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

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

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

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)

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)

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...

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...

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

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

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)

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

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

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.

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)

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

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

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...

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...

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

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

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

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)

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

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...

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...

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)

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

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

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

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.

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...

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)

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

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)

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)

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

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)

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

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...

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

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)

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)

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)

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

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...

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...

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)

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)

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...

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

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.)

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)

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.

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...

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

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...

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)

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

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

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

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)

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...

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)

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...

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...

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)

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 ...

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

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)

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

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...

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

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...

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...

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

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

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

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...

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)

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)

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)

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

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...

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...

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)

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)

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

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...

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

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

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...

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

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.

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.)

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

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)

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

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

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

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

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

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

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

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

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)

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

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.

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

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)

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)

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

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.

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...

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

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

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)

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)

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.

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)

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)

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)

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)

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)

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)

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...

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

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.

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)

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)

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)

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)

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

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...

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...

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

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

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)

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

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

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...

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.

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

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.

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

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

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...

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

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)

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)

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)

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)

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...

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)

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

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.

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

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

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

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

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. ...

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...

Demarcation of the licensing and supervisory procedures for nuclear engineering installations

International Nuclear Information System (INIS)

Schattke, H.

1986-01-01

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

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...

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)

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

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

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

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.

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

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).

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)

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

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)

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)

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

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)

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

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...

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

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

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...

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

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...

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

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...

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...

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

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.

Logistics of radioactive materials: optimization of laws and regulations

International Nuclear Information System (INIS)

Akakiev, B.V.; Makarevich, I.M.; Nesterov, V.P.

2009-01-01

The article considers the problems of the Russian authorization system in the field of radioactive materials (RM) logistics which does not meet the needs of their application in medicine, science and industry. To correct the situation, first of all, it is necessary to revise the licensing system. For optimization of licensing in the field of RM transportation, a radical revision is needed for the Regulations of transportation of dangerous cargoes by automobiles, sanitary regulations, the GOST Dangerous Cargoes, numerous federal codes and norms issued by Rostekhnadzor in recent years. It is also necessary to review and coordinate various sanitary regulations for radiation safety, develop the Agreement on transit transportation of RM between the countries of the CIS [ru

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...

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...

The problems of enforcement of decisions on the deprivation of the driver's license

Directory of Open Access Journals (Sweden)

Oleg Beketov

2017-01-01

Full Text Available УДК 342.9The subject of research is legal regulation and practice the enforcement of punishment on deprivation of the license permitting to drive a variety of vehicles.The purpose of this article to show that even for such well-established for many years, narrow and specific law enforcement procedure as the execution of administrative punishment in the form of deprivation of the license there is is very typical whitespace in legal regulation leading to conflicts and risks of enforcement. Methodology. The analysis of administrative-legal actions of officials of State Traffic Safety Inspectorate and State Technical Supervision Authority, as well as legislation on the enforcement of their decisions on cases of administrative offences.Results. It is possible to identify the main causes of the problem of law enforcement, placing them in order of importance:1. The lack of the necessary normative legal acts, regulating the procedure of interaction of the bodies of Rostekhnadzor with the traffic police authorities, courts (judges, and the rules of procedure of the issuance of the certificate of the tractor operator-the machinist after the end of the period of deprivation, the absence of an approved format (sample medical certificate, etc., i.e. a very significant omissions of administrative-legal regulation.2. The failure of judges to the provisions of part 2 of article 32.5 of the administrative code of submitting to the authorities of state technical control of decisions on deprivation of the right of management by a tractor, self-propelled machine or other types of equipment for execution.3. Insufficient level of interaction of police with the Gostekhnadzor for the execution of administrative punishment in the field of traffic.4. The lack of access of authorities of state technical control for Federal information system, integrated into the necessary parts of the information system of internal Affairs bodies and the State information system on

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

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)

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

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.

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...

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

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

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

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

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

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)

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)

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

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

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)

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)

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...

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

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

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

Licensing of the OPAL reactor during construction and commissioning

International Nuclear Information System (INIS)

Summerfield, M.

2007-01-01

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

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/.

Delivering Regulatory Consents for Decommissioning and Restoration of the Dounreay Nuclear Licensed Site

International Nuclear Information System (INIS)

Crawford, R.W.; Zyda, P.W.

2006-01-01

On behalf of the Nuclear Decommissioning Authority (NDA) the United Kingdom Atomic Energy Authority (UKAEA) has implemented a strategy to translate the near-term Dounreay restoration plan into a suite of land use documents designed to deliver the necessary planning consents to decommission and restore the Dounreay Nuclear Licensed Site. The legal consents and authorizations required to enable UKAEA to commence major projects and progress the decommissioning of the site are highlighted along with the measures taken to secure political, public and regulatory acceptance at the earliest opportunity. The approach taken by UKAEA is explained, focusing particularly on the critical need to secure planning permission and stakeholder approval well before the onset of construction works. The intention is to realize the benefits of forging a close working relationship with the land use regulator, The Highland Council. UKAEA has taken an approach to suitably inform the planning authority, in particular, the production of the Dounreay Planning Framework (DPF) document. This paper describes the role and need for the DPF, focusing on the key purpose of amending the local development plan to secure supportive planning policies and to set a land use context for the subsequent site decommissioning and restoration. This also has the advantage of securing public acceptance through an established legal process. Strategic milestones subsequent to the Highland Council's adoption of the DPF are highlighted, including the submission of phased planning applications and compliance with environmental legislation generally. The paper describes and underscores the need for early engagement of other regulators in the planning process such as the Scottish Environment Protection Agency (SEPA), and the safety regulator, the Nuclear Installations Inspectorate (NII). It describes the linkages amongst land use consents, Best Practicable Environmental Options (BPEO), radioactive substances

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)

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)

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.

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)

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

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

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

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)

Licensing procedures according to the Federal Act Protection Against Nuisances

International Nuclear Information System (INIS)

Schaefer, K.

1977-01-01

On March 1st, 1977 the 9th decree of the Protection Against Nuisances came into force, which, as the first comprehensive and state-uniform regulation contains the principles of the licensing procedure supplementary to legal provisions. The legal provision is based on numerous recent regulations of procedure from which in the meantime an essential stock of regulations relating to the licensing procedure has emerged. In general, two aims are to be achieved by this new regulation: The acceleration and simplification of the licensing procedure as will as the imperative guaranteeing in this procedure of the rights of the neighbouring areas, and of the society in general by a constitutional state. The legal provision provides in part new legal instruments for this. Examples on which the legal provisions are based are presented in the introduction. Subsequent explanations of provisions of the decree are to assist the application of the new act. Relevant regulations of the Federal Act for Protection Against Nuisances, as well as further supplementary provisions are given in the supplement. (orig.) [de

Judicial facts on licensing and supervisory procedures concerning radiation protection law

International Nuclear Information System (INIS)

Rosenhaum, O.

1976-01-01

Some statistical studies on the present licensing and supervision procedures are discussed, viz. on 1) owner of a licence accord. to sect. 3 and 4 of the 1st Radiation Protection Ordinance; 2) special licences according to section 1 of the Radiation Protection Ordinance for the release of radioactive materials in air and water (required in a very few cases only); 3) violations of the regulations were not of a severe nature (mostly from industry). The author condludes that the present regulations proved to be satisfactory. Minor corrections relating to licence-free handling, restriction of the requirements for a licence as well as to prohibition of illegal use of the radiation warning sign are desired. (HP) [de

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)

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

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...

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)

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

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.

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...

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

LMTK1 regulates dendritic formation by regulating movement of Rab11A-positive endosomes.

Science.gov (United States)

Takano, Tetsuya; Urushibara, Tomoki; Yoshioka, Nozomu; Saito, Taro; Fukuda, Mitsunori; Tomomura, Mineko; Hisanaga, Shin-Ichi

2014-06-01

Neurons extend two types of neurites-axons and dendrites-that differ in structure and function. Although it is well understood that the cytoskeleton plays a pivotal role in neurite differentiation and extension, the mechanisms by which membrane components are supplied to growing axons or dendrites is largely unknown. We previously reported that the membrane supply to axons is regulated by lemur kinase 1 (LMTK1) through Rab11A-positive endosomes. Here we investigate the role of LMTK1 in dendrite formation. Down-regulation of LMTK1 increases dendrite growth and branching of cerebral cortical neurons in vitro and in vivo. LMTK1 knockout significantly enhances the prevalence, velocity, and run length of anterograde movement of Rab11A-positive endosomes to levels similar to those expressing constitutively active Rab11A-Q70L. Rab11A-positive endosome dynamics also increases in the cell body and growth cone of LMTK1-deficient neurons. Moreover, a nonphosphorylatable LMTK1 mutant (Ser34Ala, a Cdk5 phosphorylation site) dramatically promotes dendrite growth. Thus LMTK1 negatively controls dendritic formation by regulating Rab11A-positive endosomal trafficking in a Cdk5-dependent manner, indicating the Cdk5-LMTK1-Rab11A pathway as a regulatory mechanism of dendrite development as well as axon outgrowth. © 2014 Takano et al. This article is distributed by The American Society for Cell Biology under license from the author(s). Two months after publication it is available to the public under an Attribution–Noncommercial–Share Alike 3.0 Unported Creative Commons License (http://creativecommons.org/licenses/by-nc-sa/3.0).

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.)

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

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.

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...

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

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

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...

48 CFR 252.227-7006 - License grant-running royalty.

Science.gov (United States)

2010-10-01

... 48 Federal Acquisition Regulations System 3 2010-10-01 2010-10-01 false License grant-running... of Provisions And Clauses 252.227-7006 License grant—running royalty. As prescribed at 227.7009-4(a...—Running Royalty (AUG 1984) (a) The Contractor hereby grants to the Government, as represented by the...

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...

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)

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

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

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.

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)

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

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

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

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

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

HTR-PM Safety requirement and Licensing experience

International Nuclear Information System (INIS)

Li Fu; Zhang Zuoyi; Dong Yujie; Wu Zongxin; Sun Yuliang

2014-01-01

HTR-PM is a 200MWe modular pebble bed high temperature reactor demonstration plant which is being built in Shidao Bay, Weihai, Shandong, China. The main design parameters of HTR-PM were fixed in 2006, the basic design was completed in 2008. The review of Preliminary Safety Analysis Report (PSAR) of HTR-PM was started in April 2008, completed in September 2009. In general, HTR- PM design complies with the current safety requirement for nuclear power plant in China, no special standards are developed for modular HTR. Anyway, Chinese Nuclear Safety Authority, together with the designers, developed some dedicated design criteria for key systems and components and published the guideline for the review of safety analysis report of HTR-PM, based on the experiences from licensing of HTR-10 and new development of nuclear safety. The probabilistic safety goal for HTR-PM was also defined by the safety authority. The review of HTR-PM PSAR lasted for one and a half years, with 3 dialogues meetings and 8 topics meetings, with more than 2000 worksheets and answer sheets. The heavily discussed topics during the PSAR review process included: the requirement for the sub-atmospheric ventilation system, the utilization of PSA in design process, the scope of beyond design basis accidents, the requirement for the qualification of TRISO coating particle fuel, and etc. Because of the characteristics of first of a kind for the demonstration plant, the safety authority emphasized the requirement for the experiment and validation, the PSAR was licensed with certain licensing conditions. The whole licensing process was under control, and was re-evaluated again after Fukushima accident to be shown that the design of HTR-PM complies with current safety requirement. This is a good example for how to license a new reactor. (author)

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

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)

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.

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...

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...

Developing National Regulations in the United Arab Emirates

International Nuclear Information System (INIS)

Kaufer, Barry; Redwine, Kirk; Al Khafili, Helal; Hafidh, Salem

2011-01-01

The Federal Authority for Nuclear Regulation (FANR), in preparing, issuing and implementing regulations is seeking to be consistent with IAEA Safety Standards, to use risk informed and performance-based methodologies, to capitalise on licensing in the country of origin and to follow internationally recognised practices. FANR's intent is to produce high level regulations which are not prescriptive and which focus on the essential aspects of safety. Regulatory guides will also be provided to assist licensees with compliance. This paper discusses an overview of the regulatory framework in the UAE, the planned scope of the proposed regulations, the approach being taken under an internal management system to develop these regulations and regulatory guides in the UAE and. The current status and future plans will also be provided. (authors)

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

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)

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

International Nuclear Information System (INIS)

Heinonen, Jussi

2014-01-01

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

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.

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)

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)

Nuclear regulation in the 1980s - a leadership role

International Nuclear Information System (INIS)

Asselstine, J.K.

1983-01-01

An overview of cooperation between the Nuclear Regulatory Commission (NRC) and the nuclear industry cites the Institute of Nuclear Power Operations (INPO) as a model for other cooperative efforts, both in determining the need for and the appropriateness of regulatory requirements. The author addresses three needs of nuclear regulation that will be significant during the 1980s: to adapt our regulatory program to a changing workload; to address safety issues, and particularly the development of new safety requirements, for nuclear plants; and to modernize and improve the licensing process. Steps to improve licensing procedures could include standardization, the resolution of design issues before the start of construction, redefinition of the hearing process, limitations of later modifications, stable commission decision making authority, and recognition of the commission's authority to consider economic costs in making regulatory decisions

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

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)

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

Licensing process for safety-critical software-based systems

Energy Technology Data Exchange (ETDEWEB)

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

2000-12-01

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

Licensing process for safety-critical software-based systems

International Nuclear Information System (INIS)

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

2000-12-01

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

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...

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...

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.

Licensing of New Nuclear Power Plants in Canada

International Nuclear Information System (INIS)

Schwarz, Garry; Miller, Doug

2011-01-01

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

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)

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

Environmental assessment for final rule on nuclear power plant license renewal

International Nuclear Information System (INIS)

1991-12-01

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

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

48 CFR 252.227-7012 - Patent license and release contract.

Science.gov (United States)

2010-10-01

... 48 Federal Acquisition Regulations System 3 2010-10-01 2010-10-01 false Patent license and release contract. 252.227-7012 Section 252.227-7012 Federal Acquisition Regulations System DEFENSE ACQUISITION REGULATIONS SYSTEM, DEPARTMENT OF DEFENSE CLAUSES AND FORMS SOLICITATION PROVISIONS AND CONTRACT CLAUSES Text...

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)

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

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)

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

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)

Technical guideline technology according to the X-ray regulations

International Nuclear Information System (INIS)

2011-01-01

The guideline covers the required technical knowledge concerning radiation protection and knowledge concerning for the operation of X-ray devices for technical purposes and stray radiation sources requiring licensing, and requirements for the qualification of officially authorized inspectors. The guidelines includes the following chapters: (1) introductory regulations; (2) Volume of the required technical knowledge; (3) Acquirement and certification of the technical knowledge; (4) Actualization of the technical knowledge; (5)Approval of courses and other training measures; (6) Combination of courses and training measures according to the guideline; (7) Requirements for qualification of officially authorized inspectors; (8) Interim regulations.

A new license plate extraction framework based on fast mean shift

Science.gov (United States)

Pan, Luning; Li, Shuguang

2010-08-01

License plate extraction is considered to be the most crucial step of Automatic license plate recognition (ALPR) system. In this paper, a region-based license plate hybrid detection method is proposed to solve practical problems under complex background in which existing large quantity of disturbing information. In this method, coarse license plate location is carried out firstly to get the head part of a vehicle. Then a new Fast Mean Shift method based on random sampling of Kernel Density Estimate (KDE) is adopted to segment the color vehicle images, in order to get candidate license plate regions. The remarkable speed-up it brings makes Mean Shift segmentation more suitable for this application. Feature extraction and classification is used to accurately separate license plate from other candidate regions. At last, tilted license plate regulation is used for future recognition steps.

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...

Licensing systems and inspection of nuclear installations in NEA Member countries. Part 1, Description of licensing systems

International Nuclear Information System (INIS)

1977-01-01

This study provides an assessment of the legislative and regulatory provisions applicable and of the practices followed in the countries concerned and is divided into two separate sections. This document is the first part only. It contains the description of national licensing and inspection systems for nuclear installations in the twenty OECD countries which have specific regulations in this field. Each analysis has been presented following a plan which is as standardised as possible so as to facilitate comparison between the national systems. Part II, which is not included in this document, contains the diagrams illustrating the steps in the licensing procedure and the duties of the bodies involved as well as certain additional documents. It also includes a table showing the sequence of the main steps in the licensing process in the countries covered by this Study

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)

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...

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)

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.

The licensing practice on nuclear power plants in Korea

International Nuclear Information System (INIS)

Moon, S. P.

1994-01-01

The evolution of Korean regulatory system has tightly coupled with development ot Korean nuclear power program. The nuclear power plant licensing has become a major regulatory function of the government when the construction of the Kori NPP Unit 1 started in early 1970s. During this period, domestic laws and regulations applicable to the licensing of NPP were not yet fully developed. Therefore the vendor countries' laws and regulations were applied as mandatory requirement. Beginning in the early 19808, component approach was used and contracts were awarded separately for major components of the plants, thus enabling more domestic industries to participate in the projects. The two-step licensing system was incorporated into the law. In the third phase from 1987, major efforts have been concentrated on the maximum participation of local industries. The overriding priority for selecting suppliers was the condition of higher nuclear technology transfer to Korea. The Korea Institute of Nuclear Safety (KINS) was established in 1990 as an independent regulatory expert organization

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

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)

Licensing schedule for away-from-reactor (AFR) spent fuel storage facilities

International Nuclear Information System (INIS)

Gray, P.L.

1981-08-01

The Nuclear Regulatory Commission has authority to issue licenses for Away-From-Reactor (AFR) installations for the storage of spent nuclear fuel. This report presents a detailed estimate of the time required to prosecute a licensing action. The projected licensing schedule shows that the elapsed time between filing an application and issuance of a license will be about 32 months, assuming intervention. The legal procedural steps will determine the time schedule and will override considerations of technical complexity. A license could be issued in about 14 months in the absence of intervention

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.)

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)

Electronic licensing filing system development and implementation experience

International Nuclear Information System (INIS)

Walderhaug, J.

1993-01-01

The Electronic Licensing Filing System (ELFS) is a microcomputer-based integrated document search and retrieval system for the Nuclear Regulatory Affairs Division of Southern California Edison (SCE). ELFS allows the user access to the current licensing basis of a subject by providing an easily searchable electronic information data base consisting of regulatory correspondence, design-bases documentation, licensing documents [updated final safety and analysis report (UFSAR) and technical specifications], and regulatory guidance or directives [10CFR, generic letters, bulletins, notices, circulars, regulatory guides, policy statements, and selected US Nuclear Regulatory Commission (NRC) regulations]. It is used in the preparation of correspondence and submittals to the NRC, 50.59 safety evaluations, design-bases reconstitution, and commitment tracking and management

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

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.

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

Introduction to Technology Export License of Nuclear Facility

Energy Technology Data Exchange (ETDEWEB)

Seo, Hana; Lee, Chansuh; Shin, Donghoon [Korea Institute of Nuclear Nonproliferation and Control, Daejeon (Korea, Republic of)

2014-05-15

In this regime, the Nuclear Safety and Security Commission (NSSC) has authority on final decision making. And the Korea Institute of Nuclear nonproliferation and Control (KINAC) has missions to review the classification and export licensing technically. In principle, classification and export licensing are applied and reviewed individually. However, the number of application for classification and licensing has increased geometrically in the last three years. This is largely a due to the contract that the Republic of Korea (ROK) has finalized to build the UAE Barakah Nuclear Power Plant (BNPP) and Jordan Research and Training Reactor (JRTR). This circumstance brought an administrative burden for the government and related institutes as well as stakeholders. This article introduces the law related to the 'Technology Export License of Nuclear Facility' which was developed and legislated to improve the efficiency and effectiveness of commodities classification and export licensing. This system could significantly reduce the licensing burden for transferring the technologies. However, the classification and license on this system are still requested when transferring the goods. Therefore, KINAC will continue to figure out the needs for the stakeholders and keep searching for solutions to problems inherent in the industry.

Introduction to Technology Export License of Nuclear Facility

International Nuclear Information System (INIS)

Seo, Hana; Lee, Chansuh; Shin, Donghoon

2014-01-01

In this regime, the Nuclear Safety and Security Commission (NSSC) has authority on final decision making. And the Korea Institute of Nuclear nonproliferation and Control (KINAC) has missions to review the classification and export licensing technically. In principle, classification and export licensing are applied and reviewed individually. However, the number of application for classification and licensing has increased geometrically in the last three years. This is largely a due to the contract that the Republic of Korea (ROK) has finalized to build the UAE Barakah Nuclear Power Plant (BNPP) and Jordan Research and Training Reactor (JRTR). This circumstance brought an administrative burden for the government and related institutes as well as stakeholders. This article introduces the law related to the 'Technology Export License of Nuclear Facility' which was developed and legislated to improve the efficiency and effectiveness of commodities classification and export licensing. This system could significantly reduce the licensing burden for transferring the technologies. However, the classification and license on this system are still requested when transferring the goods. Therefore, KINAC will continue to figure out the needs for the stakeholders and keep searching for solutions to problems inherent in the industry

Licensing process for future applications of advanced-design nuclear reactors

International Nuclear Information System (INIS)

Miller, C.L.

1990-01-01

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

75 FR 53271 - Assessment of Fees for Dairy Import Licenses for the 2011 Tariff-Rate Import Quota Year

Science.gov (United States)

2010-08-31

... costs of administering the licensing system under this regulation. The regulation at 7 CFR 6.33(a) also... directly related to administering the licensing system, and $53,000 represents other miscellaneous costs... / Tuesday, August 31, 2010 / Notices#0;#0; [[Page 53271

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)

15 CFR 303.7 - Issuance of licenses and shipment permits.

Science.gov (United States)

2010-01-01

... 15 Commerce and Foreign Trade 2 2010-01-01 2010-01-01 false Issuance of licenses and shipment permits. 303.7 Section 303.7 Commerce and Foreign Trade Regulations Relating to Commerce and Foreign Trade (Continued) INTERNATIONAL TRADE ADMINISTRATION, DEPARTMENT OF COMMERCE MISCELLANEOUS REGULATIONS WATCHES...

Nuclear Siting and Licensing Act of 1978. Hearings before the Subcommittee on Energy and Power, Committee on Interstate and Foreign Commerce, House of Representatives, Ninety-Fifth Congress

International Nuclear Information System (INIS)

Anon.

1979-01-01

The Subcommittee on Energy and Power conducted hearings on the administration proposal to revise the process by which nuclear power plants are licensed. The purpose of this proposal is to substantially reduce the amount of time needed to license and construct nuclear powerplants. The bill attempts to encourage the early selection of possible sites by separating the process by which such sites are approved fom the process by which plants are licensed. The bill would dispense with the existing requirement that all hearings be adjudicatory, and instead authorize informal hearings on certain issues, principally those which would be conducted pursuant to the National Environmental Policy Act of 1969. The bill would authorize a State which has established a program, consistent with the criteria contained in the act and regulations promulgated by the Nuclear Regulatory Commission, to determine the environmental acceptability of, and/or the need for, a proposed nuclear plant which would be located within its boundaries. Finally, the bill seeks to encourage the use of standardized design and authorizes the NRC to provide funds to intervenors under certain specified conditions

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

The licensing practice on nuclear power plants in Korea

Energy Technology Data Exchange (ETDEWEB)

Moon, S P

1994-12-31

The evolution of Korean regulatory system has tightly coupled with development ot Korean nuclear power program. The nuclear power plant licensing has become a major regulatory function of the government when the construction of the Kori NPP Unit 1 started in early 1970s. During this period, domestic laws and regulations applicable to the licensing of NPP were not yet fully developed. Therefore the vendor countries` laws and regulations were applied as mandatory requirement. Beginning in the early 19808, component approach was used and contracts were awarded separately for major components of the plants, thus enabling more domestic industries to participate in the projects. The two-step licensing system was incorporated into the law. In the third phase from 1987, major efforts have been concentrated on the maximum participation of local industries. The overriding priority for selecting suppliers was the condition of higher nuclear technology transfer to Korea. The Korea Institute of Nuclear Safety (KINS) was established in 1990 as an independent regulatory expert organization. 1 tab., 4 figs.

New Nuclear Safety Regulations

International Nuclear Information System (INIS)

Novosel, N.; Prah, M.; Cizmek, A.

2008-01-01

Beside new Ordinance on the control of nuclear material and special equipment (Official Gazette No. 15/08), from 2006 State Office for Nuclear Safety (SONS) adopted Ordinance on performing nuclear activities (Official Gazette No. 74/06) and Ordinance on special conditions for individual activities to be performed by expert organizations which perform activities in the area of nuclear safety (Official Gazette No. 74/06), based on Nuclear Safety Act (Official Gazette No. 173/03). The Ordinance on performing nuclear activities regulates the procedure of announcing the intention to perform nuclear activity, submitting an application for the issue of a license to perform nuclear activity, and the procedure for adoption a decision on issuing a nuclear activity license. The Ordinance also regulates the contents of the application form for the announcement of the intention to perform nuclear activity, as well as of the application for the issue of a nuclear activity license and the method of keeping a nuclear activity register. The Ordinance on special conditions for individual activities to be performed by expert organizations which perform activities in the area of nuclear safety regulates these mentioned conditions, whereas compliance is established by a decision passed by the SONS. Special conditions for individual activities to be performed by expert organizations which perform activities in the area of nuclear safety are organizational, technical, technological conditions and established system of quality assurance. In 2007, SONS finalized the text of new Ordinance on nuclear safety and protection conditions for location, design, construction, operation and decommissioning of facility in which nuclear activity is performed. This Ordinance regulates nuclear safety and protection conditions for location, design, construction, operation and decommissioning of facility in which nuclear activity is performed. This Ordinance defines facilities in which nuclear activity is

Guidance for regulation of underground repositories for disposal of radioactive wastes

International Nuclear Information System (INIS)

1989-01-01

Deep geological formations are favoured for disposal of high level and alpha bearing wastes from the nuclear fuel cycle: varying depths of emplacement, including shallow land disposal, with or without engineered barriers may be foreseen for low and intermediate level wastes. Most countries will regulate such disposal through licensing actions by a regulatory body whose purpose is to review and analyse the safety of all stages of the disposal programme. This regulatory function may be performed either by a single national authority or a system of authorities. It is the intent of the IAEA that this publication will be used as a guide to develop regulatory requirements for licensing waste disposal facilities. This report updates IAEA Safety Series No. 51. Development of the regulatory process is maturing rapidly in Member States, hence there is a clear need to revise the nearly ten year old text of that publication. The purpose of this report is to provide general guidance for the regulation of underground disposal of low, intermediate and high level radioactive wastes once a fundamental decision to pursue this option has been made. It is intended to reflect the experience of those countries with mature regulatory programmes and to provide some guidance to those countries that wish to develop regulatory programmes. Guidance is given on what issues should be addressed in the licensing review, what decision points are important, and what guidance should be given to the applicant by the regulatory system in the course of the licensing actions. The orientation of the report is on technical factors rather than the social and political aspects that need to be taken into account when regulating the underground disposal of radioactive wastes. The financing aspects are not discussed

15 CFR 738.4 - Determining whether a license is required.

Science.gov (United States)

2010-01-01

... 15 Commerce and Foreign Trade 2 2010-01-01 2010-01-01 false Determining whether a license is required. 738.4 Section 738.4 Commerce and Foreign Trade Regulations Relating to Commerce and Foreign Trade (Continued) BUREAU OF INDUSTRY AND SECURITY, DEPARTMENT OF COMMERCE EXPORT ADMINISTRATION REGULATIONS...

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...

Lessons learned from the licensing process for the Clinch River Breeder Reactor Plant

International Nuclear Information System (INIS)

Dickson, P.W.; Clare, G.H.

1991-01-01

This paper presents the experience of licensing a specific liquid-metal fast breeder reactor (LMFBR), the Clinch River Breader Reactor Plant (CRBRP). It was a success story in that the licensing process was accomplished in a very short time span. The actions of the applicant and the actions of the US Nuclear Regulatory Commission (NRC) in response are presented and discussed to provide guidance to future efforts to license unconventional reactors. The history is told from the perspective of the authors. As such, some of the reasons given for success or lack of success are subjective interpretations. Nevertheless, the authors' positions provided them an excellent viewpoint to make these judgements. During the second phase of the licensing process, they were the CRBRP Technical Director and the Licensing Manager, respectively, for the Westinghouse Electric Corporation, the prime contractor for the reactor plant

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

International Nuclear Information System (INIS)

Smith, L.J.

2001-01-01

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

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

International Nuclear Information System (INIS)

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

2004-01-01

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

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)

9 CFR 102.5 - U.S. Veterinary Biological Product License.

Science.gov (United States)

2010-01-01

... 9 Animals and Animal Products 1 2010-01-01 2010-01-01 false U.S. Veterinary Biological Product... BIOLOGICAL PRODUCTS § 102.5 U.S. Veterinary Biological Product License. (a) Authorization to produce each biological product shall be specified on a U.S. Veterinary Biological Product License, issued by the...

Licensing procedures and siting problems of nuclear power stations in Japan

International Nuclear Information System (INIS)

Saito, Osamu.

1981-10-01

This paper describes the legislative and regulatory framework for nuclear power plant licensing in Japan and the different stages in the licensing procedure. The role and responsibilities of the authorities competent for the different types of nuclear facilities (power generation, ship propulsion and research) are also reviewed. The Annexes to the paper contain charts of the administrative structure for nuclear activities, the licensing procedure and nuclear facilities. (NEA) [fr

The development of radiation protection regulations in Malaysia

International Nuclear Information System (INIS)

Yusoff Ismail

1995-01-01

The paper begins by mentioning the established policy of the Government of Malaysia vis-a-vis protection against ionizing radiations as embodied in the Radioactive Substances Act 1968 and, later, the atomic Energy Licensing Act 1984. Then it turns to on the major events that influences the past, the present and the future development of the radiation protection regulations in Malaysia. it concludes with a vision where future Malaysia is seen drifting towards a consensus effort in radiation protection rendering self regulation the order of the day. (author)

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)

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)

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.

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

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

77 FR 32167 - Revocation of License of Small Business Investment Company

Science.gov (United States)

2012-05-31

... States Small Business Administration hereby revokes the license of Women's Growth Capital Fund I, LLLP, a... SMALL BUSINESS ADMINISTRATION Revocation of License of Small Business Investment Company Pursuant to the authority granted to the United States Small Business Administration by the Wind-Up Order of...

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

Environmental impact studies of projects be licensed under the Atomic Law

International Nuclear Information System (INIS)

Heuel-Fabianek, Burkhard; Lennartz, Reinhard

2009-01-01

The German Law on Environmental Impact Assessment (UVPG) defines projects to be licensed under the Atomic Law that require an environmental impact study (EIS). Since the project concepts as defined in the UVPG are often not the same as those defined in the Atomic Law (AtG), the licensing authority has to decide which project should be subjected to an EIA. Additionally, Article 37 of the EURATOM Treaty obliges every Member State to communicate certain data relating to the impact of emissions of radioactive substances to the Commission. This is independent of the EIA. A licence may only be granted by the competent authorities if an opinion has been received from the Commission pursuant to Article 37. In either case, the licensing authority is the first point of contact for the applicant if the question arises of whether a project has to be subjected to an EIA. A ''voluntary'' EIA should be regarded with caution because of the complexity of such a procedure within the licensing process requiring considerable resources of time and manpower, and the danger of a loss of credibility of the EIA. (orig.)

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

International Nuclear Information System (INIS)

Dverstorpand, Bjoern; Stroemberg, Bo

2014-01-01

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

The use of U.S. NRC licensing practices for VVERs

International Nuclear Information System (INIS)

Popp, D.M.

2000-01-01

The licensing process for the upgraded Temelin I and C and Fuel designs were enhanced with the introduction of U.S. Nuclear Regulatory Commission, NRC practices. Specifically, the use of the NRC Regulatory Guide 1.70, 'Standard Format and Content Guide for Safety Analyses Reports' and NRC NUREG 0800, 'Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants', were beneficial in the development and review of Temelin licensing documentation. These standards have been used for the preparation and review of Safety Analysis Reports in the United States and also in a large number of licensing applications around the world. Both Regulatory Guide 1.70 and NUREG 0800 were developed to provide a predictable and structured approach to licensing. This paper discusses this approach and identifies the benefits to designers, writers of licensing documentation and reviewers of licensing documents. (author)

31 CFR 539.502 - Effect of license.

Science.gov (United States)

2010-07-01

... 31 Money and Finance: Treasury 3 2010-07-01 2010-07-01 false Effect of license. 539.502 Section 539.502 Money and Finance: Treasury Regulations Relating to Money and Finance (Continued) OFFICE OF... otherwise exist under ordinary principles of law in or with respect to any property. ...

31 CFR 598.502 - Effect of license.

Science.gov (United States)

2010-07-01

... 31 Money and Finance: Treasury 3 2010-07-01 2010-07-01 false Effect of license. 598.502 Section 598.502 Money and Finance: Treasury Regulations Relating to Money and Finance (Continued) OFFICE OF... otherwise exist under ordinary principles of law in or with respect to any property. ...

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

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...

28 CFR 25.1 - Purpose and authority.

Science.gov (United States)

2010-07-01

... Instant Criminal Background Check System § 25.1 Purpose and authority. The purpose of this subpart is to establish policies and procedures implementing the Brady Handgun Violence Prevention Act (Brady Act), Public... Instant Criminal Background Check System (NICS) to be contacted by any licensed importer, licensed...

More juridical security for citizens, operators and authorities

International Nuclear Information System (INIS)

Mumm, D.; Schattke, H.

1982-01-01

Since May 1st, 1982, a new ordinance concerning procedures laid down in the Atomic Energy Law has been in force. The revised version aims at providing all those citizens, operators and authorities which are involved in procedures laid down in the Atomic Energy Law with more juridical security, and at giving those administering law clearer instructions how to proceed. This purpose determines the substance of all the new regulations. The new ordinance on procedures avoids the losing of rights by the individual. It takes up recent decisions made by the Federal Constitutional Court, emphasising the now preceding legal protection of third persons in administrative procedures under the Atomic Energy Law. On the other hand, the authority issuing the ordinance points out those cases in which the licensing authorities do not have to involve the public. By doing so, a few insecurities have been removed which were caused by recent justice administered by administrative courts. (orig.) [de

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.

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

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

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...

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

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

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...

The Devil Is in the Details! On Regulating Cannabis Use in Canada Based on Public Health Criteria Comment on "Legalizing and Regulating Marijuana in Canada: Review of Potential Economic, Social, and Health Impacts".

Science.gov (United States)

Rehm, Jürgen; Crépault, Jean-François; Fischer, Benedikt

2016-08-20

This commentary to the editorial of Hajizadeh argues that the economic, social and health consequences of legalizing cannabis in Canada will depend in large part on the exact stipulations (mainly from the federal government) and on the implementation, regulation and practice of the legalization act (on provincial and municipal levels). A strict regulatory framework is necessary to minimize the health burden attributable to cannabis use. This includes prominently control of production and sale of the legal cannabis including control of price and content with ban of marketing and advertisement. Regulation of medical marijuana should be part of such a framework as well. © 2017 The Author(s); Published by Kerman University of Medical Sciences. This is an open-access article distributed under the terms of the Creative Commons Attribution License (http://creativecommons.org/licenses/by/4.0), which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.

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.

76 FR 65742 - Revocation of Customs Broker Licenses

Science.gov (United States)

2011-10-24

... DEPARTMENT OF HOMELAND SECURITY Customs and Border Protection Revocation of Customs Broker Licenses AGENCY: U.S. Customs and Border Protection, U.S. Department of Homeland Security. ACTION: General... U.S. Customs and Border Protection regulations (19 CFR 111.51(b)), the following Customs broker...

On the reform of nuclear licensing procedures for plants and operation

International Nuclear Information System (INIS)

Lecheler, H.

1977-01-01

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

Licensed reactor nuclear safety criteria applicable to DOE reactors

International Nuclear Information System (INIS)

1993-11-01

This document is a compilation and source list of nuclear safety criteria that the Nuclear Regulatory Commission (NRC) applies to licensed reactors; it can be used by DOE and DOE contractors to identify NRC criteria to be evaluated for application to the DOE reactors under their cognizance. The criteria listed are those that are applied to the areas of nuclear safety addressed in the safety analysis report of a licensed reactor. They are derived from federal regulations, USNRC regulatory guides, Standard Review Plan (SRP) branch technical positions and appendices, and industry codes and standards

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

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

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

Case study for a fit-to-purpose regulatory framework: the history and reasons for the evolution-in the French regulation regarding decommissioning

International Nuclear Information System (INIS)

Averous, J.; Chapalain, E.

2005-01-01

Full text: This paper exposes the regulatory approach for the safety of decommissioning in France, from an historical perspective. The first regulatory framework concerning decommissioning was introduced in the end of the 1980's and considered decommissioning as successive important modifications of the facility, which lead to multiple successive licenses. The first feedback from actual decommissioning projects lead the nuclear safety authority to reconsider the regulatory approach of decommissioning. The new approach privileges an integrated approach to the decommissioning projects, with an initial decommissioning license authorizing the complete project, and puts more weight on the responsibility of the licensee, fostering the organization of internal safety commissions which are allowed to authorize minor operations that do not put into question the global facility safety demonstration. This new regulatory approach was implemented in 2003 and new corresponding licensing procedures are already under way. It is thought that the new regulatory framework for decommissioning that has been introduced in 2003 will allow to regulate in a far more efficient way the decommissioning projects to come, while guarantying a high safety level, adapting the regulatory burden to the actual hazards, and allowing the licensee for the needed flexibility. Taking advantage of this new framework, licensees have already filed many decommissioning license applications, and decommissioning project licensing is currently one of the main tasks of the nuclear safety authority in France. Many such licenses, for all types of nuclear facilities, will be granted in the next few years. (authors)

Improvement suggestions on license extension management for civil nuclear safety equipment activities

International Nuclear Information System (INIS)

Sun Xingjian; Liu Hongji; Han Guoli; Jia Fengcai

2013-01-01

Based on the concepts of Clear Requirements, Comprehensive Review, Objective Assessment, Dynamic Management, this paper gives improvement suggestions on license extension management for civil nuclear safety equipment design, manufacture, installation and non-destructive examination activities, which include establishing a relatively unified license extension review standard, combining multi-views and close linking license review and supervision, full utilizing the daily supervision and inspection results, as well as further improving motivation and elimination mechanism. (authors)

What are the impacts of giving up the driver license?

OpenAIRE

Siren, Anu Kristiina; Haustein, Sonja

2013-01-01

Objectives: Driving cessation is a gradual process, where driver’s self-regulation plays an important role. Age-based license renewal procedures may interfere with this process and trigger premature driving cessation. The present study compares drivers aged 69 years at the baseline who either renewed their driver’s license (“renewers”) or did not (“non-renewers”) over a two-year period.Methods: Data were collected by interviewing a sample of older Danish people in 2009 (n = 1,792) and in 2012...

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.

Status report on the HFR conversion and re-licensing project

International Nuclear Information System (INIS)

Wijtsma, F.G.

2003-01-01

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

Proposed Regulations for Medical Examination of the Radiation Worker

International Nuclear Information System (INIS)

Shabon, M.H.

2015-01-01

Owing to the widespread use of ionising radiation and radioactive isotopes and their well recognized adverse effects on human health. General requirements for workers to grant license to use ionizing radiation in Egypt was reported in the executive of Egyptian ionizing radiation regulation in 1962 following ionizing radiation law no. 59 for the year 1960. Egyptian Nuclear and Radiological Regulatory Authority (ENRRA) has enforced law no. 7 in 2010 and its executive regulation in 2011 through requesting certificates of medical examination as a requirement to grant Egyptian license to ionizing radiation worker. A deficiency in medical examination and special investigations for pre-placement and follow up of the radiation worker has been noticed. This paper provides practical guidance to the employers and the appointed doctors about health surveillance and medical examinations of the radiation worker. Past history, present history, clinical examination and investigations are presented. Illnesses and conditions that prevent the person to be classified are also mentioned.

78 FR 53793 - Request To Amend a License To Export Radioactive Waste

Science.gov (United States)

2013-08-30

... NUCLEAR REGULATORY COMMISSION Request To Amend a License To Export Radioactive Waste Pursuant to... total of 5,500 ``Ultimate Foreign XW012/04 radioactive tons of low- Consignee(s).'' No other 11005699 waste). level waste). changes to the existing license which authorizes the export of non-conforming...

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...

10 CFR 150.20 - Recognition of Agreement State licenses.

Science.gov (United States)

2010-01-01

... 10 Energy 2 2010-01-01 2010-01-01 false Recognition of Agreement State licenses. 150.20 Section 150.20 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) EXEMPTIONS AND CONTINUED REGULATORY AUTHORITY... the activities authorized, for an unlimited period of time. (5) Shall comply with all terms and...

What it took to get an NRC license for centralized incineration

International Nuclear Information System (INIS)

DiSalvo, R.; Zielenbach, W.

1987-01-01

In 1982, Battelle joined five other commercial generators of low level radioactive waste in conducting a study of the technical and economic feasibility and the licensability of a central facility for incinerating LLW. The project generated a license application to the USNRC and supporting documentation related to the safety and environmental impacts of the facility. After thorough review, the NRC has issued a Finding of No Significant Impact and the associated license authorization, which is the first of its kind for an incineration facility

Use of limited information in a license application to construct a repository

International Nuclear Information System (INIS)

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

1996-01-01

The purpose of this paper is to provide a rationale for the proposition that the Department of Energy's (DOE's) submittal of a license application (LA) for the construction of a geologic repository to the Nuclear Regulatory Commission (NRC) may be, and arguably must be, based on statutorily-limited site characterization data and design information. The Nuclear Waste Policy Act of 1982 (NWPA), as amended, is the controlling statute for the disposal of spent nuclear fuel in a licensed geologic repository. Applicable NRC regulations for the licensing of such a repository are found for the most part in 10 C.F.R. Part 60

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

International Nuclear Information System (INIS)

Thoma, J.O.

1985-01-01

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

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)

1990 No. 1918. The Nuclear Installations Act 1965 (Repeal and Modifications) Regulations 1990

International Nuclear Information System (INIS)

1990-01-01

These Regulations entered into force on 31 October 1990. They repeal part of Section (1) of the Nuclear Installations Act 1965 to remove the exemption of the United Kingdom Atomic Energy Authority (UKAEA) from licensing under the Act. The Regulations also amend the 1965 Act to ensure that the UKAEA's duties in respect of the safety of premises it occupies will continue to apply whether or not a nuclear site licence has been granted. (NEA) [fr

Guide to the economic regulation of the energy industries in the European Union

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-12-01

This new addition to the series of OXERA Guides to Regulation provides an analysis of the electricity and gas sectors of each of the 15 EU member states, against the backdrop of the liberalisation of the electricity market and the anticipated liberalisation of the gas market. For each country, the guide provides details of: the industry and institutional structure; privatisation status; government policy; level of competition; licensing regimes; price and non-price regulation and; environmental policies. (Author)

78 FR 53793 - Request To Amend a License To Import Radioactive Waste

Science.gov (United States)

2013-08-30

... NUCLEAR REGULATORY COMMISSION Request To Amend a License To Import Radioactive Waste Pursuant to... (Class A total of 5,500 ``Foreign Suppliers.'' No IW022/04 radioactive tons of low- other changes to the existing 11005700 waste). level waste). license which authorizes the import of low-level waste for...

Licensing procedures for Low-Level Waste disposal facilities

International Nuclear Information System (INIS)

Roop, R.D.; Van Dyke, J.W.

1985-09-01

This report describes the procedures applicable to siting and licensing of disposal facilities for low-level radioactive wastes. Primary emphasis is placed on those procedures which are required by regulations, but to the extent possible, non-mandatory activities which will facilitate siting and licensing are also considered. The report provides an overview of how the procedural and technical requirements for a low-level waste (LLW) disposal facility (as defined by the Nuclear Regulatory Commission's Rules 10 CFR Parts 2, 51, and 61) may be integrated with activities to reduce and resolve conflict generated by the proposed siting of a facility. General procedures are described for site screening and selection, site characterization, site evaluation, and preparation of the license application; specific procedures for several individual states are discussed. The report also examines the steps involved in the formal licensing process, including docketing and initial processing, preparation of an environmental impact statement, technical review, hearings, and decisions. It is concluded that development of effective communication between parties in conflict and the utilization of techniques to manage and resolve conflicts represent perhaps the most significant challenge for the people involved in LLW disposal in the next decade. 18 refs., 6 figs

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

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

International Nuclear Information System (INIS)

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

1993-01-01

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

What are the impacts of giving up the driver license?

DEFF Research Database (Denmark)

Siren, Anu Kristiina; Haustein, Sonja

Objectives: Driving cessation is a gradual process, where driver’s self-regulation plays an important role. Age-based license renewal procedures may interfere with this process and trigger premature driving cessation. The present study compares drivers aged 69 years at the baseline who either...... should try to prevent unwarranted mobility loss. Licensing policies signaling that in old age continuing to drive is an exception rather than the rule may work against this goal....... renewed their driver’s license (“renewers”) or did not (“non-renewers”) over a two-year period. Methods: Data were collected by interviewing a sample of older Danish people in 2009 (n = 1,792) and in 2012 (n = 863). The standardized interviews covered respondents’ background information, health and well...

M5TM alloy high burnup behavior and worldwide licensing

International Nuclear Information System (INIS)

Mardon, J.P.; Hoffmann, P.B.; Garner, G.L.

2005-01-01

tests have been performed on M5 fuel rods up to burnups of 65 GWd/tU. These ramp tests demonstrated the improved behavior of highly irradiated M5 fuel rods compared to Zircaloy-4. Regarding licensing, the generic or plant specific authorization for loading M5 alloy has been granted by US, German, Korean, Chinese, South-African, Swedish and Belgian Safety Authorities. Also the French Safety Authority has given its authorization to load first M5 fuel assembly batches, according to French utility first requests. Moreover, the M5 cladding tube licensing in Japan is in progress and supported by the ALPS program devoted to RIA and LOCA aspects for the high burn-ups. Licensing is also now underway in Great Britain and Finland. (author)

Exploitation of BEPU Approach for the Licensing Process

International Nuclear Information System (INIS)

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

2011-01-01

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

Licensing of ANSTO'S OPAL reactor during construction and commissioning

International Nuclear Information System (INIS)

Summerfield, M.W.; Ordonez, J.P.

2006-01-01

Full text: This paper presents a general description of the ongoing licensing activities associated with the construction and commissioning of the Australian Nuclear Science and Technology Organisation's (ANSTO) Open Pool Australian Light-water (OPAL) Reactor at their Lucas Heights site. It addresses the following aspects: The Construction Licence - what it is and what impact it had on the construction of the OPAL Reactor, specifically the various Construction Licence Conditions; The interface between ANSTO, INVAP and ARPANSA during the construction of the OPAL Reactor, particularly in relation to ARPANS Regulation 54; Specific licensing issues that have arisen during the construction and commissioning process and how they have been resolved; The Operating Licence Application - what it is and how it interfaces with the construction and commissioning of the OPAL Reactor. 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 the lessons learnt that may be of benefit to other licensees and regulators. Note that this paper is an update of a presentation given at IGORR10 and follows on from a paper previously presented at PNBC12 in October 2002

License renewal demonstration program: NRC observations and lessons learned

International Nuclear Information System (INIS)

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

1996-12-01

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

Regulatory Reform and License Termination Planning in Decommissioning

International Nuclear Information System (INIS)

Michael J. Meisner

2000-01-01

Decommissioning of commercial nuclear power plants (NPPs) must be safe and cost-effective and consider the needs of a wide range of stakeholders. The creative tension among these objectives has provided opportunities to reform the way these plants are regulated and managed in decommissioning. Enlightened and visionary leaders from the U.S. Nuclear Regulatory Commission (NRC) and industry are seizing these opportunities to create new paradigms for risk-informed regulation; creative stakeholder involvement; and effective, end-state focused, license termination planning

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

International Nuclear Information System (INIS)

Melani, Ai; Chang, Soon Heung

2008-01-01

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

77 FR 21592 - Guidelines for Preparing and Reviewing Licensing Applications for the Production of Radioisotopes

Science.gov (United States)

2012-04-10

... Licensing of Non-Power Reactors: Format and Content,'' for the production of radioisotopes and NUREG-1537, Part 2, ``Guidelines for Preparing and Reviewing Applications for the Licensing of Non-Power Reactors... by searching on http://www.regulations.gov under Docket ID NRC-2011-0135. You may submit comments by...

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)

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

International Nuclear Information System (INIS)

Alonso, A.

1981-01-01

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

Proposed general amendments to the atomic energy control regulations

International Nuclear Information System (INIS)

1986-01-01

Canada's Atomic Energy Control Act defines the powers and responsibilities of the Atomic Energy Control Board (AECB). Among these is to make regulations to control the development, application and use of atomic energy. In these proposed general amendments to the Atomic Energy Control Regulations substantial changes are proposed in the designation of the authority of AECB staff, exemptions from licensing, international safeguards, duties of licensees and atomic radiation workers, security of information, and provision for hearings. The scope of the control of atomic energy has been redefined as relating to matters of health, safety, security, international safeguards, and the protection of the environment

Licensing procedure for nuclear power in Sweden. An international look with lessons for Sweden

International Nuclear Information System (INIS)

Gaahlin, Emil; Nilsson, Isabelle; Pettersson, Maria; Soederholm, Patrik

2011-02-01

In this study we present an in-depth analysis of the existing licensing procedure for nuclear power in Sweden, and the related processes towards different public authorities. In order to put the existing legislation into context we also analyze the legal and political prerequisites for the establishment of nuclear reactors during the 1970s. The purpose of this report is thus to: (a) analyze the legal and political conditions under which the existing nuclear power plants in Sweden were built; and (b) review and analyze the existing licensing procedure for nuclear power in the country. Four main statutes (and several subordinated regulations) apply in connection with the establishment of a new nuclear plant in Sweden, including the adoption of physical plans, a principal governmental decision on the permissibility of the plant and at least five major licenses. Physical planning according to the Planning and Building Act is primarily a municipal responsibility. A plan has to meet certain environmental requirements; not least the 'provisions on efficient management of natural resources' in the Environmental Code, indicating how different kinds of land and water areas should be used and thereby direct the location of different installations. The Swedish rules are complex and vague in many respects, and may therefore imply major uncertainties for a prospective investor. The legal protection is less unclear if an area is of national interest for a specific purpose, such as nature conservation, where it normally would not be possible to locate, say, a nuclear power plant. An area may also be of national interest for nuclear plants, which of course significantly alters the preconditions in favour of the plant project. The physical planning procedure comprises an 'environmental consideration' of the plan, including an 'environmental impact assessment' (EIA), provided the plan is likely to have significant effects on the environment. This 'programmatic EIA' does however not

Building confidence in nuclear waste regulation: how NRC is adapting in response to stakeholder concerns

International Nuclear Information System (INIS)

Kotra, Janet P.

2004-01-01

Increasing public confidence in the U.S. Nuclear Regulatory Commission as an effective and independent regulator is an explicit goal of the Agency. When developing new, site-specific regulations for the proposed geologic repository at Yucca Mountain, Nevada, NRC sought to improve its efforts to inform and involve the public in NRC's decision-making process. To this end, NRC has made, and continues to make significant organizational, process and policy changes. NRC successfully applied these changes as it completed final regulations for Yucca Mountain, when introducing a draft license review plan for public comment, and when responding to public requests for information on NRC's licensing and hearing process. It should be understood, however, that these changes emerged, and continue to be applied, in the context of evolving agency concern for increasing stakeholder confidence reflected in institutional changes within the agency as a whole. (author)

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.

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)

Licensing and decommissioning of nuclear installations in Japan

International Nuclear Information System (INIS)

Shimoyama, Shunji.

1986-01-01

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

Mechanisms of JAK/STAT pathway negative regulation by the short coreceptor Eye Transformer/Latran.

Science.gov (United States)

Fisher, Katherine H; Stec, Wojciech; Brown, Stephen; Zeidler, Martin P

2016-02-01

Transmembrane receptors interact with extracellular ligands to transduce intracellular signaling cascades, modulate target gene expression, and regulate processes such as proliferation, apoptosis, differentiation, and homeostasis. As a consequence, aberrant signaling events often underlie human disease. Whereas the vertebrate JAK/STAT signaling cascade is transduced via multiple receptor combinations, the Drosophila pathway has only one full-length signaling receptor, Domeless (Dome), and a single negatively acting receptor, Eye Transformer/Latran (Et/Lat). Here we investigate the molecular mechanisms underlying Et/Lat activity. We demonstrate that Et/Lat negatively regulates the JAK/STAT pathway activity and can bind to Dome, thus reducing Dome:Dome homodimerization by creating signaling-incompetent Dome:Et/Lat heterodimers. Surprisingly, we find that Et/Lat is able to bind to both JAK and STAT92E but, despite the presence of putative cytokine-binding motifs, does not detectably interact with pathway ligands. We find that Et/Lat is trafficked through the endocytic machinery for lysosomal degradation but at a much slower rate than Dome, a difference that may enhance its ability to sequester Dome into signaling-incompetent complexes. Our data offer new insights into the molecular mechanism and regulation of Et/Lat in Drosophila that may inform our understanding of how short receptors function in other organisms. © 2016 Fisher et al. This article is distributed by The American Society for Cell Biology under license from the author(s). Two months after publication it is available to the public under an Attribution–Noncommercial–Share Alike 3.0 Unported Creative Commons License (http://creativecommons.org/licenses/by-nc-sa/3.0).

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...

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...

An overview of the class I structures license renewal industry report

International Nuclear Information System (INIS)

Renfro, L.J.; Statton, J.A.

1991-01-01

License renewal of a commercial nuclear power plant requires verification that systems, structures and components important to license renewal can perform their intended safety functions throughout the license renewal term. The verification of this continuing performance includes a technical evaluation of the effects of age-related degradation. An industry report (IR) sponsored by the nuclear industry was developed which identifies potentially significant age-related degradation mechanisms that may affect Class I structures and evaluates their impact on the ability of the structures to continue to perform their safety functions. Preventive and/or mitigative options are outlined for managing degradation mechanisms that could significantly affect plant performance during the license renewal period. This paper provides a summary of the IR. (author)

Operator licensing examination standards for power reactors. Interim revision 8

International Nuclear Information System (INIS)

1997-01-01

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

ISO 14000 and the nuclear licensing

International Nuclear Information System (INIS)

Martins, Nadia Soido Falcao

1999-01-01

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

Licensing of non intrusive inspection equipment s for load and passengers vehicles that use X rays with energies up to 9 MeV. Mexican experience

International Nuclear Information System (INIS)

Munoz M, G. A.; Jimenez C, I.

2013-10-01

In the last years and like part of the extensive program of national security, in Mexico have been introduced a great quantity of non intrusive inspection equipment s for load and passengers vehicles that use X rays up to 9 MeV. Due to the great variety of equipment s, the Comision Nacional de Seguridad Nuclear y Salvaguardias (Mexican regulator organ) has established specific guidelines for their licensing and use supervision. In this work the adopted guidelines are exposed in the technical and administrative evaluation for the later licensing of these equipment s. Relative particular questions to the site of these equipment s and the impact in the public opinion that their use can generate are discussed. (author)

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

Regulating nuclear fuel waste

International Nuclear Information System (INIS)

1995-01-01

When Parliament passed the Atomic Energy Control Act in 1946, it erected the framework for nuclear safety in Canada. Under the Act, the government created the Atomic Energy Control Board and gave it the authority to make and enforce regulations governing every aspect of nuclear power production and use in this country. The Act gives the Control Board the flexibility to amend its regulations to adapt to changes in technology, health and safety standards, co-operative agreements with provincial agencies and policy regarding trade in nuclear materials. This flexibility has allowed the Control Board to successfully regulate the nuclear industry for more than 40 years. Its mission statement 'to ensure that the use of nuclear energy in Canada does not pose undue risk to health, safety, security and the environment' concisely states the Control Board's primary objective. The Atomic Energy Control Board regulates all aspects of nuclear energy in Canada to ensure there is no undue risk to health, safety, security or the environment. It does this through a multi-stage licensing process

Spatial service delivery system for smart licensing & enforcement management

Science.gov (United States)

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

2016-06-01

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

Regulation of fuel cycle facilities in the UK

International Nuclear Information System (INIS)