Nuclear plant license renewal

International Nuclear Information System (INIS)

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

1991-01-01

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

Nuclear reactor operator licensing

International Nuclear Information System (INIS)

Bursey, R.J.

1978-01-01

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

Sellafield - a nuclear licensed site

International Nuclear Information System (INIS)

Bloom, Phillipa.

1987-01-01

The report is based on the experience gained when visiting the Exhibition Centre at the BNFL Sellafield site and joining the hour-long coach trip round the site. The sights are recorded and a description given of the processes undertaken at Sellafield to reprocess the Magnox fuel and store the spent fuel from AGR reactors. The purpose of the main plant building, and the passage of the spent fuel through the various processes is described. Criticism is made of the safety record at Sellafield and a full and open debate on nuclear power is called for. (UK)

Improving regulatory effectiveness in Federal/State siting actions: Federal/State regulatory permitting actions in selected nuclear power station licensing cases

International Nuclear Information System (INIS)

Baroff, J.

1977-06-01

The Federal/State regulatory permitting actions in 12 case histories of nuclear power station licensing in nine different states are documented. General observations regarding Federal/State siting roles in the siting process are included. Eleven of the case histories are illustrated with a logic network that gives the actions of the utilities in addition to the Federal/State permits

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

Nuclear power plant attempts in Turkey and the first licensed site

International Nuclear Information System (INIS)

Bektur, Y.; Bezdegumeli, U.

2004-01-01

Turkey is currently in a rapid industrialization process with a young population of 71 million. Electricity is an inevitable need for Turkey as a fast developing country. Turkey's average annual growth rates of electricity consumption have been 8% in the last two decades. The installed electricity generating capacity of Turkey reached 36 GW; the annual gross power generation was 140 TWh (23% lignite and coal, 44% natural gas, 25% hydro and 8% others); and the annual gross per capita consumption of electricity was around 2.000 kWh as of end-2003. According to forecasts prepared by the Ministry of Energy and Natural Resources (MENR), Turkey will need about 60 GW of capacity by 2010, and about 100 GW by 2020. This implies power demand growth rates of at least 8% per annum for the coming decade and at least 6% per annum for the following decade. This means that there is a need for rapid build-up of 3 GW new capacities per year for at least several years. Turkey's experience with nuclear power dates back to the 1960s - a research reactor has been operating in Istanbul since 1962 - and successive governments have had plans to introduce commercial nuclear power to the country for three decades or more. Since 1965, four attempts were made for the construction of an NPP in Turkey, but all failed. Turkish Electricity Authority (TEK, reorganized as Electricity Generation Corporation in 2002) was granted a site license for the Akkuyu site in 1976. According to the current long-term energy planning studies made by MENR, nuclear power is an important option to enhance the national energy security and reliability. In the light of this study, the Turkish Government has an intention for commencement of a nuclear power program that envisages the construction of 4500 M We nuclear power installed capacity in the next decade if the private energy sector do not make an attempt

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)

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)

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)

New nuclear plant design and licensing process

International Nuclear Information System (INIS)

Luangdilok, W.

1996-01-01

This paper describes latest developments in the nuclear power reactor technology with emphasis on three areas: (1) the US technology of advanced passive light water reactors (AP600 and S BWR), (2) regulatory processes that certify their safety, and (3) current engineering concerns. The goal is to provide and insight of how the government's regulatory agency guarantees public safety by looking into how new passive safety features were designed and tested by vendors and how they were re-evaluated and retested by the US NRC. The paper then discusses the US 1989 nuclear licensing reform (10 CFR Part 52) whose objectives are to promote the standardization of nuclear power plants and provide for the early and definitive resolution of site and design issues before plants are built. The new licensing process avoids the unpredictability nd escalated construction cost under the old licensing process. Finally, the paper summarizes engineering concerns found in current light water reactors that may not go away in the new design. The concerns are related the material and water chemistry technology in dealing with corrosion problems in water-cooled nuclear reactor systems (PWRs and BWRs). These engineering concerns include core shroud cracking (BWRs), jet pump hold-down beam cracking (BWRs), steam generator tube stress corrosion cracking (PWR)

The site-characterization plan and its role in resolving siting and licensing issues

International Nuclear Information System (INIS)

Hanlon, C.L.

1986-01-01

As required by the Nuclear Waste Policy Act and the Nuclear Regulatory Commission (NRC) in 10 CFR Part 60, the Department of Energy is preparing plans for conducting site characterization at three candidate sites. Prepared according to a detailed annotated outline that is based on the NRC's Regulatory Guide 4.17, these plans will present the information collected to date about the geologic, hydrologic, geochemical, geoengineering, and climatic conditions of each site; describe the design of the repository and the waste package; and discuss the site-characterization program. The most important portions of the plan will be the strategy for resolving siting and licensing issues and the description of the testing and analysis program to be followed in resolving these issues. The issues-resolution strategy consists of identifying issues and the associated information needs; allocating performance goals for various components of the repository system; developing a testing plan to gather the necessary information; gathering and analyzing the information; and documenting the results for use in site selection and licensing. The issues-resolution strategy will allow the Department to define all of the issues that must be resolved in order to demonstrate compliance with applicable regulations and to specify the information needed to resolve these issues. It will provide a consistent framework and establish priorities for the Department's site-characterization effort for the next several years

Licensed reactor nuclear safety criteria applicable to DOE reactors

International Nuclear Information System (INIS)

1991-04-01

The Department of Energy (DOE) Order DOE 5480.6, Safety of Department of Energy-Owned Nuclear Reactors, establishes reactor safety requirements to assure that reactors are sited, designed, constructed, modified, operated, maintained, and decommissioned in a manner that adequately protects health and safety and is in accordance with uniform standards, guides, and codes which are consistent with those applied to comparable licensed reactors. This document identifies nuclear safety criteria applied to NRC [Nuclear Regulatory Commission] licensed reactors. The titles of the chapters and sections of USNRC Regulatory Guide 1.70, Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants, Rev. 3, are used as the format for compiling the NRC criteria applied to the various areas of nuclear safety addressed in a safety analysis report for a nuclear reactor. In each section the criteria are compiled in four groups: (1) Code of Federal Regulations, (2) US NRC Regulatory Guides, SRP Branch Technical Positions and Appendices, (3) Codes and Standards, and (4) Supplemental Information. The degree of application of these criteria to a DOE-owned reactor, consistent with their application to comparable licensed reactors, must be determined by the DOE and DOE contractor

77 FR 34093 - License Renewal for Calvert Cliffs Nuclear Power Plant, LLC's

Science.gov (United States)

2012-06-08

... Nuclear Power Plant, LLC's AGENCY: Nuclear Regulatory Commission. ACTION: Environmental assessment and... Spent Fuel Storage Installation (ISFSI) at the Calvert Cliffs Nuclear Power Plant site near Lusby... Cliffs Nuclear Power Plant, LLC (CCNPP) submitted an application to the NRC to renew NRC License SNM-2505...

Nuclear power plant operator licensing

International Nuclear Information System (INIS)

1997-01-01

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

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

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)

RM - ODP to express nuclear licensing

International Nuclear Information System (INIS)

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

2002-01-01

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

Geological and geotechnical investigations for nuclear power plants sites

International Nuclear Information System (INIS)

Alves, P.R.R.

1984-09-01

This dissertation presents a general methodology for the tasks of geological and geotechnical investigations, to be performed in the proposed sites for construction of nuclear Power Plants. In this work, items dealing with the standards applied to licensing of Nuclear Power Plants, with the selection process of sites and identification of geological and geotechnical parameters needed for the regional and local characterization of the area being studied, were incorporated. This dissertation also provides an aid to the writing of Technical Reports, which are part of the documentation an owner of a Nuclear Power Plant needs to submit to the Comissao Nacional de Energia Nuclear, to fulfill the nuclear installation licensing requirements. Moreover, this work can contribute to the planning of field and laboratory studies, needed to determine the parameters of the area under investigation, for the siting of Nuclear Power Plants. (Author) [pt

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)

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

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

Science.gov (United States)

2012-05-18

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

Off-site preparedness and nuclear-power-plant licensing

International Nuclear Information System (INIS)

Perry, S.W.

1983-01-01

The first year and a half in which off-site emergency preparedness issues have been litigated before the Atomic Safety and Licensing Boards of the NRC have surfaced unique problems of proof for the applicant as well as the staff. These problems seem to be abating as the boards and the parties become more comfortable with the field and its issues, and as FEMA-NRC emergency management expertise gains credibility. Emergency preparedness presentations have also improved as the parties have become more sensitive to the seasonality of the preparedness case, and have increasingly attempted to raise it at a time when a fully developed set of facts is available for the record. Off-site preparedness issues are only now beginning to be raised on appeal to the NRC appeals board, the full commission, and the courts. Helpful guidance on what constitutes an adequate record in this area will undoubtedly be forthcoming in decisions handed down by these bodies in the months ahead

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

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)

Nuclear licensing and supervision in Germany

International Nuclear Information System (INIS)

1996-06-01

The legal instrument for implementing the licensing and supervisory procedure is specified by statutory ordinances, guidelines and provisions. The licensing requirements for nuclear power plants on the final storage of radioactive wastes in the federal republic of germany are described. The nuclear facilities are subject to continuous state supervision after they have been granted. The appendix gives a brief account of the most important ordinances relating to the AtG and extracts from the Nuclear Safety Convention. (HP)

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)

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

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

A nuclear inspector's perspective on decommissioning at UK nuclear sites

International Nuclear Information System (INIS)

Robinson, I.F.

1999-01-01

The legislative framework used to regulate decommissioning of nuclear facilities in the UK is described. Pre-licensing requirements are outlined and the operation of a nuclear site licence is described. Mention is made of safety assessment and the published principles which are NII's view of what constitutes good practice within the nuclear industry. HSE's approach to the regulation of nuclear decommissioning is described before discussing issues associated with optioneering, the timing of decommissioning, occupational doses and public doses. It is noted that the professional approach taken by the nuclear industry within the framework of the existing regulatory requirements has resulted in considerable reductions in occupational dose over the last few years. The de-licensing process is described in the context of terminating a licensee's period of responsibility for safety, and principles by which 'no danger' may be judged are described. Impending new legislation on environmental impact assessment in relation to decommissioning nuclear reactors is mentioned. It is concluded that a powerful and flexible method of regulatory control is in place with regard to nuclear decommissioning. (author)

Proceedings of the CNRA Workshop on New Reactor Siting, Licensing and Construction Experience

International Nuclear Information System (INIS)

2011-01-01

This report documents the proceedings from the 'Workshop on New Reactor Siting, Licensing and Construction Experience', held in Prague, Czech Republic on 15-17 September 2010. A total of 59 specialists from 16 countries and international organisations attended. The Meeting was sponsored by the OECD Nuclear Energy Agency Committee on Nuclear Regulatory Activities and hosted by the State Office for Nuclear Safety (SUJB) in Czech Republic. The objectives of the workshop were to review and discuss recent and past construction experience lessons learned including perspectives from regulatory authorities, as well as vendors, and licensee. The workshop addressed issues associated with project management resources including: a) overall human resources, expertise, experience and organisation available to the licensee, b) capability of each potential vendor (in-house knowledge and skills versus planned subcontracting and subcontractor management). The workshop also discussed the lessons learned in the regulation of site selection, evaluation and site preparation as well as the review of regulatory practices for the licensing of new reactors, including the regulatory body infrastructure, staffing and expertise needed. The workshop provided an excellent opportunity to communicate recent experience on these topics to a wider audience, including participants from OECD member countries as well as New Entrants from non-OECD member countries. The workshop allowed the WGRNR group to introduce and discuss the current programme of work and products under development in order to gain insights from workshop participants on each of the programme of work areas, and get feedback on additional focus areas. The workshop was structured in 4 technical sessions, each followed by ample time for panel discussions. The first technical session was devoted to presentations of the licensing process for new reactors followed by different member countries. The second technical session was

Licensing process in Finland

International Nuclear Information System (INIS)

Tiippana, Petteri

2011-01-01

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

Site Specific Vendor's License

Data.gov (United States)

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

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 the First Nuclear Power Plant. INSAG-26. A report by the International Nuclear Safety Group

International Nuclear Information System (INIS)

2012-01-01

having nuclear power plants of similar design, and the various technical cooperation activities conducted by international organizations, in particular the IAEA. The first major task for the regulatory body will be carrying out a review of the safety evaluation report of the proposed site for the first nuclear power plant. For this, the regulatory body must lay down the safety requirements that could be developed or adopted from IAEA safety standards on the subject. It will also require a set of specialized competences in areas such as seismology, hydrology, geochemistry and geology that is not necessarily nuclear related. In developing the strategy to secure and maintain a technically competent regulatory body, a decision should be made early whether to recruit staff with those competences or to outsource these activities to agencies where competences in such areas may already be available in the country. Notwithstanding this, the regulatory body still requires a core technical group in the key disciplines to be able to understand and compile the information from the site evaluation reports as input to the site licensing process.

The use of on-site Project Officers by a nuclear regulatory body

International Nuclear Information System (INIS)

Beare, J.W.

1977-01-01

In Canada consideration of applications for licensing nuclear installations is entrusted to the Reactor Safety Advisory Committee within the Atomic Energy Control Board (AECB). The licensing procedure is conducted in three stages (site approval, construction licence, operating licence). In order to control construction and operation of nuclear installations Project Officers are assigned to each particular installation. The policy of AECB is to send these officers on site several months before the reactor reaches criticality; and during reactor operation. This system clearly provides great practical advantages. (NEA) [fr

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

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

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

List of Nuclear Materials Licensing Actions Received

Data.gov (United States)

Nuclear Regulatory Commission — A catalog of all Materials Licensing Actions received for review. The catalog lists the name of the entity submitting the license application, their city and state,...

Siting studies for new nuclear power plants in Argentina

International Nuclear Information System (INIS)

Barbaran, Gustavo A.

2008-01-01

This paper is a summary of the thesis prepared by the Group of Prospective and Energy Planning of the National Atomic Energy Commission for the 'Specialization on Applications of Nuclear Technology Course' of the Instituto Balseiro in 2007. It describes the evolution of siting studies through time and the main focus worldwide in this type of studies. Then, it makes a brief review of previous siting studies of nuclear power plants conducted in Argentina. It carries out a description of the methodology to conduct a site evaluation for nuclear power plants according to actual international criteria. Finally, it describes the licensing process that follows every site study. (author) [es

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)

ESPSD, Nuclear Power Plant Siting Database

International Nuclear Information System (INIS)

Slezak, S.

2001-01-01

1 - Description of program or function: This database is a repository of comprehensive licensing and technical reviews of siting regulatory processes and acceptance criteria for advanced light water reactor (ALWR) nuclear power plants. The program is designed to be used by applicants for an early site permit or combined construction permit/operating license (10CFRR522), Sub-parts A and C) as input for the development of the application. The database is a complete, menu-driven, self-contained package that can search and sort the supplied data by topic, keyword, or other input. The software is designed for operation on IBM compatible computers with DOS. 2 - Method of solution: The database is an R:BASE Runtime program with all the necessary database files included

The nuclear licensing and supervisory procedures for nuclear facilities in the Federal Republic of Germany

International Nuclear Information System (INIS)

Franzen, L.F.

1982-02-01

A combined system has been developed in the Federal Republic of Germany: the States execute the Atomic Energy Act on behalf of the Federal Government. Despite these differences, the safety requirements and the safety standard achieved vary only insignificantly, as a result of a world-wide communication and of international cooperation. The legal prerequesites for the German nuclear licensing procedures have been established about 20 years ago, and, by a number of amendments have been adapted to new perceptions and developments. Several supplementary ordinances, due to further developments in nuclear technology, are being prepared. The work on associated technical provision, which had been neglected for a long time, has in recent years been tackled systematically and should, before long, lead to a comprehensive programme of safety standards, which simplifies and expedites the nuclear licensing procedures. Essential features of the licensing procedure are the phased structure and the division into intermediate steps which render it possible to adapt the safety requirements to the advancing state of science and technology. The responsible authorities call in experts for the safety verification of the application documents. It is the task of these experts to make assessments and to conduct quality examinations in the manufacturing plants and at the site, and to carry out recurrent tests. The public is involved by the announcement of the projects, the display of the documents and by the opportunity to raise objections during the licensing procedure. Licenses granted can be contested before the administrative courts. This procedure paves the way for the achievement of a satisfactory balance between private and public interests. (orig./HP)

Impact of New Radiation Safety Standards on Licensing Requirements of Nuclear Power Plant

International Nuclear Information System (INIS)

Strohal, P.; Subasic, D.; Valcic, I.

1996-01-01

As the outcomes of the newly introduced safety philosophies, new and more strict safety design requirements for nuclear installation are expected to be introduced. New in-depth defence measures should be incorporated into the design and operation procedure for a nuclear installation, to compensate for potential failures in protection or safety measures. The new requirements will also apply to licensing of NPP's operation as well as to licensing of nuclear sites, especially for radioactive waste disposal sites. This paper intends to give an overview of possible impacts of new internationally agreed basic safety standards with respect to NPP and related technologies. Recently issued new basic safety standards for radiation protection are introducing some new safety principles which may have essential impact on future licensing requirements regarding nuclear power plants and radioactive waste installations. These new standards recognize exposures under normal conditions ('practices') and intervention conditions. The term interventions describes the human activities that seek to reduce the existing radiation exposure or existing likelihood of incurring exposure which is not part of a controlled practice. The other new development in safety standards is the introduction of so called potential exposure based on the experience gained from a number of radiation accidents. This exposure is not expected to be delivered with certainty but it may result from an accident at a source or owing to an event or sequence of events of a probabilistic nature, including equipment failures and operating errors. (author)

The Licensing of New Nuclear Power Plants in Europe

International Nuclear Information System (INIS)

Raetzke, C.

2008-01-01

After an introduction dealing with the nuclear Renaissance in Europe and the specific situation of Germany and of Italy, the article focuses on the question of licensing processes for new reactors. New nuclear power plant projects involve a substantial investment and electric utilities will only take this decision if the licensing and regulatory risk can be adequately managed. Licensing processes should be predictable and efficient in order to give sufficient assurance to applicants. The article discusses best practice in licensing by giving some examples of suitable licensing processes of other countries. It also highlights international initiatives aimed at harmonizing safety requirements for new reactors and a multinational cooperation in reactor design review. These issues should be carefully considered by any country wanting to get new nuclear started. [it

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

Managing the high level waste nuclear regulatory commission licensing process

International Nuclear Information System (INIS)

Baskin, K.P.

1992-01-01

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

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)

Future of Nuclear Power: NRC emergency preparedness licensing activities agenda

International Nuclear Information System (INIS)

Essig, T.H.

1995-01-01

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

The work of the OECD Nuclear Energy Agency on safety and licensing of nuclear installations

International Nuclear Information System (INIS)

Strohl, P.

1975-01-01

The acceleration of nuclear power programmes in OECD Member countries is reflected in the emphasis given by OECD/NEA to its activities in nuclear safety and regulatory matters. Particular effort is devoted to work on radiation protection and radioactive waste management, safety of nuclear installations and nuclear law development. A Committee on the Safety of Nuclear Installations reviews the state of the art and identifies areas for research and co-ordination of national programmes. A Sub-Committee on Licensing collates information and data on licensing standards and practices of different countries with a view to considering problems of common interest. Comparative studies of various licensing systems and discussions between licensing authorities should help to improve regulatory control of nuclear installations for which there appears to be a need for internationally accepted standards in the long run. (author)

Licensing the First Nuclear Power Plant. INSAG-26. A report by the International Nuclear Safety Group (Russian Edition)

International Nuclear Information System (INIS)

2016-01-01

countries having nuclear power plants of similar design, and the various technical cooperation activities conducted by international organizations, in particular the IAEA. The first major task for the regulatory body will be carrying out a review of the safety evaluation report of the proposed site for the first nuclear power plant. For this, the regulatory body must lay down the safety requirements that could be developed or adopted from IAEA safety standards on the subject. It will also require a set of specialized competences in areas such as seismology, hydrology, geochemistry and geology that is not necessarily nuclear related. In developing the strategy to secure and maintain a technically competent regulatory body, a decision should be made early whether to recruit staff with those competences or to outsource these activities to agencies where competences in such areas may already be available in the country. Notwithstanding this, the regulatory body still requires a core technical group in the key disciplines to be able to understand and compile the information from the site evaluation reports as input to the site licensing process

Licensing and accident reviews for an HNEC

International Nuclear Information System (INIS)

Clark, R.G.

1978-09-01

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

Future of nuclear licensing

International Nuclear Information System (INIS)

Denton, H.R.

1984-01-01

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

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)

Licensing process characteristics of Small Modular Reactors and spent nuclear fuel repository

Energy Technology Data Exchange (ETDEWEB)

Söderholm, Kristiina, E-mail: kristiina.soderholm@fortum.com [Fortum Power (Finland); Tuunanen, Jari, E-mail: jari.tuunanen@fortum.com [Fortum Power (Finland); Amaba, Ben, E-mail: baamaba@us.ibm.com [IBM Complex Systems (United States); Bergqvist, Sofia, E-mail: sofia.bergqvist@se.ibm.com [IBM Rational Software (Sweden); Lusardi, Paul, E-mail: plusardi@nuscalepower.com [NuScale Power (United States)

2014-09-15

Highlights: • We examine the licensing process challenges of modular nuclear facilities. • We compare the features of Small Modular Reactors and spent nuclear fuel repository. • We present the need of nuclear licensing simplification. • Part of the licensing is proposed to be internationally applicable. • Systems engineering and requirements engineering benefits are presented. - Abstract: This paper aims to increase the understanding of the licensing processes characteristics of Small Modular Reactors (SMR) compared with licensing of spent nuclear fuel repository. The basis of the SMR licensing process development lies in licensing processes used in Finland, France, the UK, Canada and the USA. These countries have been selected for this study because of their various licensing processes and recent actions in the new NPP construction. Certain aspects of the aviation industry licensing process have also been studied and selected practices have been investigated as possibly suitable for use in nuclear licensing. Suitable features for SMR licensing are emphasized and suggested. The licensing features of the spent nuclear fuel deep repository along with similar features of SMR licensing are discussed. Since there are similar types of challenges of lengthy licensing time frames, as well as modular features to be taken into account in licensing, these two different nuclear industry fields can be compared. The main SMR features to take into account in licensing are: • Standardization of the design. • Modularity. • Mass production. • Serial construction. Modularity can be divided into two different categories: the first category is simply a single power plant unit constructed of independently engineered modules (e.g. construction process for Westinghouse AP-1000 NPP) and the second one a power plant composed of many reactor modules, which are manufactured in factories and installed as needed (e.g. NuScale Power SMR design). The deep underground repository

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

Application of probabilistic risk assessment in nuclear and environmental licensing processes of nuclear reactors in Brazil

International Nuclear Information System (INIS)

Mata, Jonatas F.C. da; Vasconcelos, Vanderley de; Mesquita, Amir Z.

2015-01-01

The nuclear accident at Fukushima Daiichi, occurred in Japan in 2011, brought reflections, worldwide, on the management of nuclear and environmental licensing processes of existing nuclear reactors. One of the key lessons learned in this matter, is that the studies of Probabilistic Safety Assessment and Severe Accidents are becoming essential, even in the early stage of a nuclear development project. In Brazil, Brazilian Nuclear Energy Commission, CNEN, conducts the nuclear licensing. The organism responsible for the environmental licensing is Brazilian Institute of Environment and Renewable Natural Resources, IBAMA. In the scope of the licensing processes of these two institutions, the safety analysis is essentially deterministic, complemented by probabilistic studies. The Probabilistic Safety Assessment (PSA) is the study performed to evaluate the behavior of the nuclear reactor in a sequence of events that may lead to the melting of its core. It includes both probability and consequence estimation of these events, which are called Severe Accidents, allowing to obtain the risk assessment of the plant. Thus, the possible shortcomings in the design of systems are identified, providing basis for safety assessment and improving safety. During the environmental licensing, a Quantitative Risk Analysis (QRA), including probabilistic evaluations, is required in order to support the development of the Risk Analysis Study, the Risk Management Program and the Emergency Plan. This article aims to provide an overview of probabilistic risk assessment methodologies and their applications in nuclear and environmental licensing processes of nuclear reactors in Brazil. (author)

Application of probabilistic risk assessment in nuclear and environmental licensing processes of nuclear reactors in Brazil

Energy Technology Data Exchange (ETDEWEB)

Mata, Jonatas F.C. da; Vasconcelos, Vanderley de; Mesquita, Amir Z., E-mail: jonatasfmata@yahoo.com.br, E-mail: vasconv@cdtn.br, E-mail: amir@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

2015-07-01

The nuclear accident at Fukushima Daiichi, occurred in Japan in 2011, brought reflections, worldwide, on the management of nuclear and environmental licensing processes of existing nuclear reactors. One of the key lessons learned in this matter, is that the studies of Probabilistic Safety Assessment and Severe Accidents are becoming essential, even in the early stage of a nuclear development project. In Brazil, Brazilian Nuclear Energy Commission, CNEN, conducts the nuclear licensing. The organism responsible for the environmental licensing is Brazilian Institute of Environment and Renewable Natural Resources, IBAMA. In the scope of the licensing processes of these two institutions, the safety analysis is essentially deterministic, complemented by probabilistic studies. The Probabilistic Safety Assessment (PSA) is the study performed to evaluate the behavior of the nuclear reactor in a sequence of events that may lead to the melting of its core. It includes both probability and consequence estimation of these events, which are called Severe Accidents, allowing to obtain the risk assessment of the plant. Thus, the possible shortcomings in the design of systems are identified, providing basis for safety assessment and improving safety. During the environmental licensing, a Quantitative Risk Analysis (QRA), including probabilistic evaluations, is required in order to support the development of the Risk Analysis Study, the Risk Management Program and the Emergency Plan. This article aims to provide an overview of probabilistic risk assessment methodologies and their applications in nuclear and environmental licensing processes of nuclear reactors in Brazil. (author)

Licensing plan for UMTRA project disposal sites

International Nuclear Information System (INIS)

1993-09-01

The Uranium Mill Tailings Remedial Action (UMTRA) Project Office developed a plan to define UMTRA Project licensing program objectives and establish a process enabling the DOE to document completion of remedial actions in compliance with 40 CFR 1 92 and the requirements of the NRC general license. This document supersedes the January 1987 Project Licensing Plan (DOE, 1987). The plan summarizes the legislative and regulatory basis for licensing, identifies participating agencies and their roles and responsibilities, defines key activities and milestones in the licensing process, and details the coordination of these activities. This plan provides an overview of the UMTRA Project from the end of remedial actions through the NRC's acceptance of a disposal site under the general license. The licensing process integrates large phases of the UMTRA Project. Other programmatic UMTRA Project documents listed in Section 6.0 provide supporting information

Decree No. 83/7405 of 18 November 1983 on the licensing procedure for nuclear installations

International Nuclear Information System (INIS)

1983-01-01

This Decree (No. 83/7405) on the licensing procedure for nuclear installations came into force on 19 December 1983 and supersedes Decree No. 7/9141 of 5 December 1974 on the same subject. The general lines of the licensing procedure laid down by this new Decree are similar to that provided by the 1979 Decree; it is also carried out in three stages: site, construction and operating licences are delivered in succession. (NEA) [fr

Report of the Task Force on bonding and perpetual care of nuclear licensed activities

International Nuclear Information System (INIS)

Snellings, D.D. Jr.

1975-01-01

The primary concern was to consider the bonding and perpetual care requirements of state-licensed shallow land burial sites used for the disposal of radioactive wastes. The specific charge of the task force was to examine in detail the requirements for establishing bonding and perpetual care programs for all types of licensed nuclear activities and to report the findings of the task force as guidance to assist states in program development. Goals and recommendations of the task force are discussed

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

Science.gov (United States)

2010-01-01

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

A survey of the underground siting of nuclear power plants

International Nuclear Information System (INIS)

Pinto, S.

1979-12-01

The idea of locating nuclear power plants underground is not new, since in the period of time between the late fifties and the early sixties, four small nuclear plants have been built in Europe in rock cavities. Safety has been, in general, the main motivation for such a siting solution. In the last years several factors such as increasing power transmission costs, decreasing number of suitable sites above ground, increased difficulties in obtaining site approval by the licensing authorities, increasing opposition to nuclear power, increasing concern for extreme - but highly improbable - accidents, together with the possibility of utilizing the waste heat and the urban siting concept have renewed the interest for the underground siting as an alternative to surface siting. The author presents a survey of the main studies carried out on the subject of underground siting. (Auth.)

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

remove the obligation to perform a 'project-EIA' in connection with the licensing procedures. The most important function of the physical plan is to determine how land and water areas should be used. On the one hand, the location and design of plant installations may not deviate from what is prescribed in a detail plan. The plan is legally binding in this negative respect. On the other hand, a plan which points out an area for the purpose of constructing a nuclear power installation is no legal guarantee for acceptance of the site in subsequent decision-making. The location also has to comply with certain special environmental requirements regulated in the Environmental Code. The Government should always decide upon the 'permissibility' on new installations related to nuclear activities (e.g., a new nuclear plant). Basically, the Government decides if the proposed activity on a certain site is allowed or not. A crucial issue concerns the choice of site for the plant. Furthermore, as in physical planning, the government must apply the provisions on efficient management of natural resources, implying, for instance, that certain areas of national interest for other purposes normally must be avoided. In these cases, where the activity requires a license from the Environmental Court according to the Environmental Code, the Court prepares the case for the Government. A nuclear plant is, according to the Environmental Code, an 'environmental hazardous activity'. This means that the plant requires a license from the Environmental Court. The Court normally decides only upon license conditions for emissions etc.; 'best available technology' (BAT) is required according to chapter 2 in the Code. A separate Natura 2000 license is also required. A license is required for a 'nuclear technology activity', including the operation of a nuclear technology installation. The Nuclear Technology Act includes certain basic provisions vaguely prescribing that nuclear technology activities shall

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

International Nuclear Information System (INIS)

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

2013-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2013-07-01

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

HSE policy on decommissioning and radioactive waste management at licensed nuclear sites

International Nuclear Information System (INIS)

Bacon, M.

1997-01-01

In the UK, radioactive waste management and decommissioning on a licensed nuclear is regulated by the Health and Safety Executive. The same legislative framework used for operating nuclear power stations is also applied to radioactive waste management and decommissioning activities. This provides a continuous but flexible safety regime until there is no danger from ionizing radiations. The regulatory policy is discussed, taking into account the implications of the 1995 White Paper reviewing radioactive waste management policy. For both radioactive waste management and decommissioning the key element of HSE policy is the need for strategic planning. This should ensure that problems are not allowed to build up and to demonstrate that, taking into account all factors, the proposed actions are the optimum in terms of safety. There is a presumption in HSE's policy towards disposal of radioactive waste as soon as possible where disposal routes exist. Where long-term storage is necessary passively safe forms are preferred over those requiring continuous monitoring or frequent intervention. (author)

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)

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)

Psychological characteristics of licensed nuclear power plant operators

International Nuclear Information System (INIS)

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

1987-01-01

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

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

Science.gov (United States)

2013-06-20

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

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)

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

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

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

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

Investment issues in nuclear plant license renewal

International Nuclear Information System (INIS)

Eynon, R.T.

1999-01-01

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

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

International Nuclear Information System (INIS)

Young, G.G.

2012-01-01

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

Regulatory requirements for nuclear power plant site selection in Malaysia-a review.

Science.gov (United States)

Basri, N A; Hashim, S; Ramli, A T; Bradley, D A; Hamzah, K

2016-12-01

Malaysia has initiated a range of pre-project activities in preparation for its planned nuclear power programme. Clearly one of the first steps is the selection of sites that are deemed suitable for the construction and operation of a nuclear power plant. Here we outline the Malaysian regulatory requirements for nuclear power plant site selection, emphasizing details of the selection procedures and site characteristics needed, with a clear focus on radiation safety and radiation protection in respect of the site surroundings. The Malaysia Atomic Energy Licensing Board (AELB) site selection guidelines are in accord with those provided in International Atomic Energy Agency (IAEA) and United Stated Nuclear Regulatory Commission (USNRC) documents. To enhance the suitability criteria during selection, as well as to assist in the final decision making process, possible assessments using the site selection characteristics and information are proposed.

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)

Remote sensing for nuclear power plant siting

International Nuclear Information System (INIS)

Siegal, B.S.; Welby, C.W.

1981-01-01

It is shown that satellite remote sensing provides timely and cost-effective information for siting and site evaluation of nuclear power plants. Side-looking airborne radar (SLAR) imagery is especially valuable in regions of prolonged cloud cover and haze, and provides additional assurance in siting and licensing. In addition, a wide range of enhancement techniques should be employed and different types of image should be color-combined to provide structural and lithologic information. Coastal water circulation can also be studied through repetitive coverage and the inherently synoptic nature of imaging satellites. Among the issues discussed are snow cover, sun angle, and cloud cover, and actual site evaluation studies in the Bataan peninsula of the Philippines and Laguna Verde, California

Nuclear power plant licensing and supervision in the Federal Republic of Germany

International Nuclear Information System (INIS)

Gehrhardt, H.J.; Gottschalk, P.A.

1991-01-01

This paper briefly describes nuclear power plant licensing and supervision in the Federal Republic of Germany (FRG). Peculiarities due to the federal structure of the FRG are outlined paying due regard to the long tradition of using consultation by qualified and independent technical experts. The participating authorities, commissions, expert organizations, vendors, utilities and the public as well as their respective competences are mentioned. Also, the hierarchy in nuclear legislation by means of ordinances, administrative regulations, guidelines and technical standards is pointed out. Typical examples are presented. The paper ends in mentioning important items concerning the evaluation of operating experience, recurrent tests, backfitting, lessons learned from the Chernobyl accident, safety research concerning accident management measures, on-site and off-site emergency planning, as well as qualification and occupational training of the responsible shift personnel. (orig.)

Nebraska withdraws its intent to deny site license

International Nuclear Information System (INIS)

Anon.

1993-01-01

The state of Nebraska has withdrawn its notice of intent to deny the US Ecology (USE) license application for the proposed low-level radioactive waste disposal site in Boyd County, near Butte, Neb. On October 4, after review of USE's August 27 submittal of a revision to the boundaries of the proposed site, a letter from the state's Department of Health (DOH) and Department of Environmental Quality (DEQ) to John. H. DeOld, the USE project manager for the Central Interstate Compact's proposed LLW site, noted that open-quotes...we are hereby withdrawing the Notice of Intent to Deny License as a moot, and will conduct a substantive review of the reconfigured site for compliance with the applicable regulations.close quotes

Generic environmental impact statement for license renewal of nuclear plants. Final report

International Nuclear Information System (INIS)

1996-05-01

This GEIS examines the possible environmental impacts that could occur as a result of renewing the licenses of individual nuclear power plants under 10 CFR 54. To the extent possible, it establishes the bounds and significance of these potential impacts. The analysis encompasses all operating light-water reactors. For each type of environmental impact, the GEIS attempts to establish generic findings covering as many plants as possible. While plant and site-specific information is used in developing the generic findings, the NRC does not intend for the GEIS to be a compilation of individual plant environmental impacts statements. This document has three principal objectives: (1) to provide an understanding of the types and severity of environmental impacts that may occur as a result of license renewal, (2) to identify and assess those impacts that are expected to be generic to license renewal, and (3) to support rulemaking (10 CFR 51) to define the number and scope of issues that need to be addressed by the applicants in plant-by-plant license renewal proceedings

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

International Nuclear Information System (INIS)

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

1976-04-01

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

Mock Site Licensing Demonstration Project. Final report

International Nuclear Information System (INIS)

Roop, R.D.

1986-06-01

The Mock Site Licensing Demonstration Project developed the Low-Level Radioactive Waste Siting Simulation, a role-playing exercise designed to facilitate the process of siting and licensing disposal facilities for low-level waste (LLW). This report describes the development, contant, and usefulness of the siting simulation. The simulation was designed by Harvard University's Program on Negotiation; it can be conducted at a workshop or conference, involves 14 or more participants, and requires about eight hours to complete. The simulation consists of two sessions. In the first, participants negotiate the selection of siting criteria, and in the second, a preferred site for a facility is chosen from three candidate sites. The project sponsored two workshops (in Boston, Massachusetts and Richmond, Virginia) in which the simulation was conducted for persons involved in planning for LLW. It is concluded that the siting simulation can be useful in three ways: (1) as a tool for information dissemination, (2) as a vehicle that can foste communication among parties in conflict, and (3) as a step toward consensus building and conflict resolution. The DOE National Low-Level Waste Management Program is now making the siting simulation available for use by states, regional compacts, and other organizations involved in development of LLW disposal facilities

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

Science.gov (United States)

2010-01-01

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

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.

Project licensing plan for UMTRA [Uranium Mill Tailings Remedial Action] sites

International Nuclear Information System (INIS)

1984-07-01

The purpose of the Uranium Mill Tailings Remedial Action (UMTRA) Project Licensing Plan is to establish how a disposal site will be licensed, and to provide responsibilities of participatory agencies as legislated by the Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978 (Public Law 95-604). This Plan has been developed to ensure that the objectives of licensing are met by identifying the necessary institutional controls, participatory agency responsibilities, and key milestones in the licensing process. The Plan contains the legislative basis for and a description of the licensing process (''Process'') for UMTRA sites. This is followed by a discussion of agency responsibilities, and milestones in the Process. The Plan concludes with a generic timeline of this Process. As discussed in Section 2.1, a custodial maintenance and surveillance plan will constitute the basis for a site license. The details of maintenance and surveillance are discussed in the Project Maintenance and Surveillance Plan (AL-350124.0000). 5 refs., 4 figs

Meteorological events in site evaluation for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2005-01-01

This Safety Guide provides recommendations and guidance on conducting hazard assessments of extreme and rare meteorological phenomena. It is of interest to safety assessors and regulators involved in the licensing process as well as to designers of nuclear power plants. This Safety Guide was prepared under the IAEA programme for safety standards for nuclear power plants. It supplements the IAEA Safety Requirements publication on Site Evaluation for Nuclear Facilities which is to supersede the Code on the Safety of Nuclear Power Plants: Siting, Safety Series No. 50-C-S (Rev. 1), IAEA, Vienna (1988). The present Safety Guide supersedes two earlier Safety Guides: Safety Series No. 50-SG-S11A (1981) on Extreme Meteorological Events in Nuclear Power Plant Siting, Excluding Tropical Cyclones and Safety Series No. 50-SG-S11B (1984) on Design Basis Tropical Cyclone for Nuclear Power Plants. The purpose of this Safety Guide is to provide recommendations and guidance on conducting hazard assessments of extreme and rare meteorological phenomena. This Safety Guide provides interpretation of the Safety Requirements publication on Site Evaluation for Nuclear Facilities and guidance on how to fulfil these requirements. It is aimed at safety assessors or regulators involved in the licensing process as well as designers of nuclear power plants, and provides them with guidance on the methods and procedures for analyses that support the assessment of the hazards associated with extreme and rare meteorological events. This Safety Guide discusses the extreme values of meteorological variables and rare meteorological phenomena, as well as their rates of occurrence, according to the following definitions: (a) Extreme values of meteorological variables such as air temperature and wind speed characterize the meteorological or climatological environment. And (b) Rare meteorological phenomena

Selected review of regulatory standards and licensing issues for nuclear power plants

International Nuclear Information System (INIS)

Stevenson, J.D.; Thomas, F.A.

1982-11-01

This report presents a compilation and description of current foreign regulatory standards and licensing issues in the areas of interest associated with Siting, Structural Engineering, Metallurgy and Materials, and Mechanical Engineering. In addition, summary comparisons of the requirements of both the US and foreign nuclear power plant regulatory standards are provided. The selected foreign countries surveyed include Canada, France, Japan, Sweden, United Kingdom of Great Britain and Northern Ireland, and the Federal Republic of Germany

Personality Factors and Nuclear Power Plant Operators: Initial License Success

Science.gov (United States)

DeVita-Cochrane, Cynthia

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

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

Licensing procedure, nuclear codes and standards in the Federal Republic of Germany

International Nuclear Information System (INIS)

Schultheiss, G.F.

1980-01-01

The present paper deals with legal background of licensing in nuclear technology and atomic energy use, licensing procedures for nuclear power plants and with codes, standards and guidelines in the Federal Republic of Germany. (orig./RW)

Review of the Brazilian experience in the licensing of nuclear power plants

International Nuclear Information System (INIS)

Lederman, L.; Laborne, J.J.

1983-01-01

Survey of the licensing of the Brazilian Nuclear Power Plants (NPPs) is presented. The organization and technical expertise of the Comissao Nacional de Energia Nuclear, the Brazilian Regulatory Body, is reviewed with regard to in-house experience, foreign consultants, agreements with regulatory bodies of other countries and research contracts with Brazilian univerisities. The application of the two-stage licensing process and the stage of development of Brazilian nuclear standards is described. Finally, the paper speculates about the future role of probabilistic risk assessment in the Brazilian licensing process

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)

Nuclear law and environmental law in the licensing of nuclear installations

International Nuclear Information System (INIS)

Raetzke, Christian

2013-01-01

Large nuclear installations can have a considerable impact on the environment, both in actual terms, due to the construction and operation of the plant and in potential terms, related to the risk of an accident. A considerable part of the multiple authorisation processes required to develop a large nuclear project is devoted to addressing the possible impact on the environment. Accordingly, environmental protection is not only warranted by requirements and processes arising out of what is generally considered 'environmental law', but also by laws governing the design, siting, construction and operation of nuclear installations. By ensuring prevention and control of radiation releases to the environment, the aspects of nuclear law governing the design, construction, operation and decommissioning of nuclear facilities pertain to the field of environmental protection just like other fields of environmental law. The perception of the public that nuclear energy is 'anti-environmental' and the generally antinuclear stance of environmental non-governmental organisations (NGOs) should not deflect attention from the fact that protection of the environment is one of the main functions of the body of nuclear law. In this article, the general relationship between the law governing civil nuclear installations and environmental law will be analysed. The subsequent chapters will deal with environmental requirements and procedures as part of the authorisation process for a nuclear installation. The role of public participation and the involvement of neighbouring states in the licensing process will also be investigated, as they are today mainly based on environmental law. Some other aspects which may also have some relation to environmental protection, such as waste management, emergency planning, multinational early notification and assistance in the case of an accident and nuclear liability, have been omitted from discussion as they lie outside the focus of this article

Nuclear power plant licensing: opportunities for improvement

International Nuclear Information System (INIS)

1977-06-01

On April 20, 1977, the Commission directed that recently completed licensing actions be reviewed by the staff for the purpose of identifying ways to improve the effectiveness and efficiency of NRC nuclear power plant licensing activities. This report summarizes the results of a study undertaken by an internal ad hoc Study Group established in response to that directive. The Study Group limited its considerations to safety and environmental review activities. The background, scope, assumptions and objectives of the study are discussed. A prime assumption of this study was that improvements in the efficiency should not be permitted to reduce the current quality achieved in the licensing process. This consideration underlies the conclusions and recommendations of the study

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

International Nuclear Information System (INIS)

Avolahti, Jaana

2014-01-01

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

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

Department of Energy interest and involvement in nuclear plant license renewal activities

International Nuclear Information System (INIS)

Bustard, Larry D.; Harrison, Dennis L.

1991-01-01

Recognizing the importance of nuclear license renewal to the nation's energy strategy, the Department of Energy (DOE) initiated a plant lifetime improvement program during 1985 to determine the feasibility of the license renewal option for US nuclear plants. Initial activities of the DOE program focused on determining whether there were technical and economic obstacles that might preclude or limit the successful implementation of the license renewal option. To make this determination, DOE co-sponsored with the Electric Power Research Institute (EPRI) 'pilot-plant' efforts by Virginia Electric Power and Northern States Power. Both pilot-plant efforts concluded that life extension is technically and economically feasible. In parallel with the pilot plant activities, DOE performed national economic studies that demonstrated the economic desirability of life extension. Having demonstrated the feasibility of life extension, DOE, in conjunction with EPRI, selected two lead plants to demonstrate the license renewal process. These lead plants are Yankees Atomic's Yankee Rowe facility and Northern States Power's Monticello facility. DOE also initiated activities to develop the technical and regulatory bases to support the license renewal process in the United States. These include (1) development of a methodology for identifying systems, structures, and components important to license renewal, (2) development of industry reports that describe industry-accepted approaches for license renewal of ten important classes of equipment, (3) development of technical basis to support license renewal, and (4) interaction/negotiation with the NRC through the Nuclear Management Resources Council (NUMARC) regarding appropriate regulatory requirements for license renewal. DOE has recently identified nuclear plant license renewal to be an important element of its National Energy Strategy. This paper summarizes the significant results, conclusions and ongoing activities of the DOE effort

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

Nuclear Energy Center study. Phase II. Site suitability analysis. Final report

International Nuclear Information System (INIS)

Fellows, W.S.; Sharp, J.M.; Benator, B.I.

1978-06-01

A site screening study was conducted to identify a site or sites for detailed, site-specific study as a nuclear energy center. Using technical criteria of water requirements, geotechnical constraints, and projected load center and transmission considerations as well as environmental and institutional considerations, five potential study sites in the State of South Carolina were identified, evaluated against established criteria, and ranked according to their acceptability as potential nuclear energy center study sites. Consideration of what is ''representative'' of a site as well as the ranking score was factored into site recommendations, since the site deemed easiest to license and permit may not be the most desirable site for future study of the technical and institutional feasibility and practicality of a specific site. The sites near Lake Hartwell and the Savannah River Plant (SRP) of the Department of Energy were selected as potential study sites after consideration of the above criteria. Because the Lake Hartwell site offers the opportunity to consider institutional issues which may be more representative of other possible NEC sites, it is recommended that the Lake Hartwell site be studied to establish the feasibility and practicality of the nuclear energy concept on a site-specific basis

The licensing of nuclear power plants in Brazil

International Nuclear Information System (INIS)

Lederman, L.

1980-01-01

In Brazil the governmental organization responsible for the licensing of NPPs is the Comissao Nacional de Energia Nuclear (CNEN), the Brazilian Regulatory Body. A description of CNEN's organization, responsabilities and working methods, as well as the present situation of the Brazilian NPPs undergoing licensing, has recently been presented. In this paper the experience gained by CNEN in the course of licensing Brazilian NPPs Units I and II is discussed. CNEN's present day technical competence and its future trends are analysed with regard to in-house capacity, foreign consultants and research contracts with Brazilian Universities. Finally, the immediate need for a Safety research programm in support of licensing is discussed. Manpower needs and major areas for such a programm are also indicated. (orig./RW)

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

Function and set up of public participation in the nuclear licensing procedure

International Nuclear Information System (INIS)

Wiedemann, H.

1977-01-01

From the point of view of the public utilities, the participation of the public in the nuclear licensing procedure, in the site provision procedure, in constructional planning, and as a joint action brought pursuant to the new 'Nuclear Installations Ordinance' (AtVfO) is discussed. In this context, it is emphasized, that a change, via possibilities existing de lege lator, is not necessary if government and administration are willing to achieve the objectives given by the legislator on the basis of the existing instrumentarium. The target they have to achieve is the enforcing 'general public interest', which has been declared as binding in law and in programmes of the government based on these laws. (HP) [de

Improving regulatory effectiveness in federal/state siting actions: water supplies and the nuclear licensing process

International Nuclear Information System (INIS)

Davenport, F.S.

1977-07-01

The Interstate Conference on Water Problems (ICWP) is a national association of State, intrastate, and interstate officials concerned with water resources administration and related matters. The Conference was established in 1959 as an outgrowth of regional conferences on water problems as recognized in the same year by action of the General Assembly of the States. This report was produced by the Interstate Conference on Water Problems in an effort to provide a compilation and summary of the views of selected States regarding relationships of water supplies to the nuclear power plant licensing process. This publication does not represent the official position of the U.S Water Resources Council, or the U.S. Nuclear Regulatory Commission, nor does it represent the position of any single state or the ICWP

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)

Decommissioning Licensing Process of Nuclear Installations in Spain

International Nuclear Information System (INIS)

Correa Sainz, Cristina

2016-01-01

The Enresa experience related to the decommissioning of nuclear facilities includes the decommissioning of the Vandellos I and Jose Cabrera NPPs. The Vandellos I gas-graphite reactor was decommissioned in about five years (from 1998 to 2003) to what is known as level 2. In February 2010, the decommissioning of Jose Cabrera power plant has been initiated and it is scheduled to be finished by 2018. The decommissioning of a nuclear power plant is a complex administrative process, the procedure for changing from operation to decommissioning is established in the Spanish law. This paper summarizes the legal framework defining the strategies, the main activities and the basic roles of the various agents involved in the decommissioning of nuclear facilities in Spain. It also describes briefly the Licensing documents required to obtain the decommissioning authorization and the Enresa point of view, as licensee, on the licensing decommissioning process. (author)

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

International Nuclear Information System (INIS)

Xu, Shulan; Dverstorp, Bjoern; Norden, Maria

2014-01-01

In 2011 the Swedish Nuclear Fuel and Waste Management Co. (SKB) submitted a license application for construction of a geological repository for spent nuclear fuel at Forsmark. SKB's disposal method, the KBS-3 method, involves disposing of the spent nuclear fuel in cast iron canisters with an outer layer of 5 cm copper. The canisters will be placed in vertical deposition holes at approximately 500 m depths in crystalline bedrock. Each canister is surrounded by a buffer of swelling bentonite clay. The repository is designed to accommodate 6 000 canisters, corresponding to 12 000 tonnes of spent nuclear fuel. The license application is supported by a post-closure safety assessment, SR-Site. Along with other parts of the application, SR-Site is currently being reviewed by the Swedish Radiation Safety Authority (SSM). The main method for review of SKB's licensing documentation is document review carried out by SSM, supported by SSM's external experts. However, SSM's document review is also supported by regulatory modelling, technical reviews of SKB's quality assurance programme and consideration of external review comments partly from two broad national consultations and an international peer review organised by the OECD's Nuclear Energy Agency (NEA, 2012). SSM's review is divided into three main phases: the initial review phase, the main review phase and the reporting phase. The overall goal of the initial review phase is to achieve a broad coverage of SR-Site and its supporting references and in particular to identify the need for complementary information and clarifications to be provided by SKB, as well as to identify critical review issues that require a more comprehensive treatment in the main review phase. SSM completed the initial review phase at the end of 2012. During the initial review phase SSM has identified a number of issues requiring either clarifications, complementary information from SKB or further in-depth review by SSM. Important issues include the

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)

10 CFR 70.20a - General license to possess special nuclear material for transport.

Science.gov (United States)

2010-01-01

... 10 Energy 2 2010-01-01 2010-01-01 false General license to possess special nuclear material for transport. 70.20a Section 70.20a Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) DOMESTIC LICENSING OF... transport. (a) A general license is issued to any person to possess formula quantities of strategic special...

The site of a nuclear power plant and environmental safety; Ydinvoimalaitoksen sijaintipaikka ja ympaeristoen turvallisuus

Energy Technology Data Exchange (ETDEWEB)

Rossi, J. [VTT Energy, Espoo (Finland)

2001-11-01

The purpose of this report is to give the reader a general view of the things associated with the site of a nuclear power plant. In this context the effect of a nuclear power plant and site on environmental safety is considered. Planning, construction and operating a nuclear power plant require several judgements and licenses based on different laws. The location of the planned nuclear facility project and environmental conditions contribute in great detail to the compliance arguments of permits. At first the environmental impacts of the siting project and its alternatives shall be investigated in the Environmental Impact Assessment procedure. Then the decision in principle according to the Nuclear Energy Act can be applied from the Council of State, the decision shall further be confirmed by Parliament. When the decision in principle is considered the overall good of society shall be assessed by means of considering i.a. site alternatives and safety. The safety related basic principle is that operation of a nuclear power plant may not cause danger to the environment, public or property. After the affirmative principle approval the construction license and later on the operation license can be applied from the Council of State, these licenses need to be supported i.a. by building and environmental licenses of separate authorities. Also some international contracts concern realisation of a nuclear power plant siting. The nuclear power plant site shall be suitable for the needs of the electricity production and the transmission system and it shall be technically appropriate for building and operation of a power plant. The site shall be safe enough on the other hand from the view of external events threatening the power plant - although one can be partly prepared for these things in the design of the plant - and on the other hand from the point of public safety. Requirements for the safety of the site are directed in the decision of the Council of State's general

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)

The SLOWPOKE licensing model

Energy Technology Data Exchange (ETDEWEB)

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

1989-08-15

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

Selection/licensing of nuclear power plant operators

International Nuclear Information System (INIS)

Saari, L.M.

1983-07-01

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

Set of rules SOR 2 licensing of nuclear reactors

International Nuclear Information System (INIS)

1976-05-01

This is the set of rules promulgated by the Israel Atomic Energy Commission pursuant to the Supervision of Supplies and Services Law 5718-1957, Order regarding Supervision of Nuclear Reactors (1974) Chapter 3: Permits, to provide for the Licensing of Nuclear Reactors. (B.G.)

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

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)

77 FR 1748 - Atomic Safety and Licensing Board; Calvert Cliffs 3 Nuclear Project, LLC, and UniStar Nuclear...

Science.gov (United States)

2012-01-11

... under represents potential contributions of wind and solar power, the combination alternative depends... Judge Ronald M. Spritzer, Atomic Safety and Licensing Board Panel, Mail Stop T-3F23, U.S. Nuclear..., Atomic Safety and Licensing Board Panel, Mail Stop T-3F23, U.S. Nuclear Regulatory Commission. Fax: (301...

Nuclear Energy Center study. Phase II. Site suitability analysis. Final report

Energy Technology Data Exchange (ETDEWEB)

Fellows, W.S.; Sharp, J.M.; Benator, B.I.

1978-06-01

A site screening study was conducted to identify a site or sites for detailed, site-specific study as a nuclear energy center. Using technical criteria of water requirements, geotechnical constraints, and projected load center and transmission considerations as well as environmental and institutional considerations, five potential study sites in the State of South Carolina were identified, evaluated against established criteria, and ranked according to their acceptability as potential nuclear energy center study sites. Consideration of what is ''representative'' of a site as well as the ranking score was factored into site recommendations, since the site deemed easiest to license and permit may not be the most desirable site for future study of the technical and institutional feasibility and practicality of a specific site. The sites near Lake Hartwell and the Savannah River Plant (SRP) of the Department of Energy were selected as potential study sites after consideration of the above criteria. Because the Lake Hartwell site offers the opportunity to consider institutional issues which may be more representative of other possible NEC sites, it is recommended that the Lake Hartwell site be studied to establish the feasibility and practicality of the nuclear energy concept on a site-specific basis.

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

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

Science.gov (United States)

2012-05-03

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

The importance of environmental education in the process of nuclear and environmental licensing of nuclear facilities

International Nuclear Information System (INIS)

Araujo, Jefferson Borges; Ribeiro, Katia Maria Bruno

2009-01-01

Today, there is a thread with regard to the global environment. To reduce the environmental impact due to spending supplies to meet the basic needs of the global population. Can be considered as the power of these needs and in this context, the environmental impact occurs by the use of fossil fuels and loss of land for use of water resources. To minimize these impacts, governments are establishing appropriate laws towards the use of renewable energy. However it appears that there is still a great distance between the established law and implementation in practice. In this context nuclear energy is an attractive option, both economic and environmental. The facilities that are somehow associated with nuclear power plants are classified as radioactive or nuclear. These facilities are subject to two licensing procedures: Environmental (by IBAMA) and Nuclear (by CNEN). Nuclear installations such as nuclear power plants Angra 1 and 2, deposits and tailings facilities of the nuclear fuel cycle in Rezende that are more the attention of the population. As part of these processes are reports of analysis of safety and environmental impacts and socio-economic (EIA/RIMA RFAS), which are available to the public and then discussed at public hearings, where there is the opportunity for questions on these reports. These questions are mainly related with the social-environmental and economic due to construction and operation of these facilities. This work is a research, discussing the law, identifying the difficulties in the licensing process and presents a discussion on the importance of environmental education at all school levels, for adult audiences and is a connection between the environmental education and process of environmental licensing and nuclear, showing how the popular consciousness more informed can better discuss issues associated with these licenses, understand the advantages and disadvantages and obtain benefits. (author)

Simulator training and licensing examination for nuclear power station operator

International Nuclear Information System (INIS)

Xu Pingsheng

2007-01-01

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

Factors relating to the selection of sites for nuclear power stations in certain industrial countries

International Nuclear Information System (INIS)

1979-08-01

The subject is discussed under the following headings: framework conditions of energy supply (energy supply in general (economics, planning); supply of nuclear energy (objectives, national nuclear industry, technology, development, public conflict)); environmental planning (legal foundations, planning levels, public site-provision investigations, electrical utilities); general and statutory atomic licensing procedure, criteria. (U.K.)

Safety and licensing of nuclear heating plants

International Nuclear Information System (INIS)

Snell, V.G.; Hilborn, J.W.; Lynch, G.F.; McAuley, S.J.

1989-09-01

World attention continues to focus on nuclear district heating, a low-cost energy from a non-polluting fuel. It offers long-term security for countries currently dependent on fossil fuels, and can reduce the burden of fossil fuel transportation on railways and roads. Current initiatives encompass large, centralized heating plants and small plants supplying individual institutions. The former are variants of their power reactor cousins but with enhanced safety features. The latter face the safety and licensing challenges of urban siting and remotely monitored operation, through use of intrinsic safety features such as passive decay heat removal, low stored energy and limited reactivity speed and depth in the control systems. Small heating reactor designs are compared, and the features of the SLOWPOKE Energy System, in the forefront of these designs, are summarized. The challenge of public perception must be met by clearly presenting the characteristics of small heating reactors in terms of scale and transparent safety in design and operation, and by explaining the local benefits

Renewing the licenses of US nuclear plants: An assessment of the socioeconomic impacts

International Nuclear Information System (INIS)

Schweitzer, M.; Saulsbury, J.W.; Schexnayder, S.M.

1993-01-01

In recent years, increased national attention has been focused on the potential effects of renewing, or not renewing, the licenses of nuclear power plants as the oldest of them approach the end of the 40-year operating period allowed by their original licenses. As part of a larger study for the US Nuclear Regulatory commission (NRC), the authors conducted an assessment of the potential socioeconomic impacts to those communities throughout the country in which nuclear power plants are located and which, therefore, are most directly affected by renewal of nuclear power plant licenses. This paper focuses on six key issues that are traditionally considered essential in the assessment of social impacts: Population; housing; tax payments; local public services; land use and development; and economic structure

Conduct of regulatory review and assessment during the licensing process for nuclear power plants

International Nuclear Information System (INIS)

1980-01-01

This Safety Guide was prepared as part of the Agency's programme, referred to as the NUSS programme, for establishing Codes of Practice and Safety Guides relating to nuclear power plants. It supplements the Code of Practice on Governmental Organization for the Regulation of Nuclear Power Plants (IAEA Safety Series No. 50-C-G) and is concerned with the review and assessment by the regulatory body of all information submitted in support of licence applications, in the various phases of the licensing process. The purpose of the Guide is to provide information, recommendations and guidance for the conduct of these activities. The scope of the review and assessment will encompass the safety aspects of siting, construction, commissioning, operation and decommissioning of each nuclear power plant

Licensing and safety of nuclear power plants in Canada

International Nuclear Information System (INIS)

Boyd, F.C.

1981-09-01

An overview of the regulatory framework and licensing process for nuclear power plants in Canada is given along with an outline of the evolution of the safety philosophy followed and some comments on how this philosophy and process could be applied by a country embarking on a nuclear power program

Technology neutral licensing requirements: have we been successful?

International Nuclear Information System (INIS)

Jamieson, T.

2009-01-01

The Canadian Nuclear Safety Commission (CNSC) is Canada's nuclear regulator. In preparation for the licensing of the next generation of nuclear reactors in Canada, the CNSC has made major changes in its processes and procedures associated with all aspects of the licensing life cycle. These include: development of key regulatory documents outlining the CNSC expectations for the design and siting of new reactors; creation of applicant guidelines for completing licensing applications; creation of a comprehensive set of review guides, specifying how topics in applications are to be reviewed; performing pre-project design reviews for proposed new reactor technologies; and streamlining processes wherever possible, such as performing the environmental assessment and license to prepare site activities in parallel. The predicted workload associated with the nuclear renaissance in Canada is real. The CNSC is currently performing: 4 pre-project design reviews (for AECL's ACR-1000 and EC-6, Areva's EPR and Westinghouse's AP-1000), has received applications for 4 new builds (at Darlington, Bruce, Nanticoke and in Alberta) and is in the midst of performing the combined environmental assessment and license to prepare site phases for these sites. This is in addition to the work associated with: the licensing of new uranium mines; oversight of the existing reactor fleet; refurbishments at Bruce/Gentilly/Point Lepreau; license renewal for the NRU reactor; and oversight of our general client base of over 5000 licensees. In this presentation, experience to date with these new processes and procedures will be discussed, including: status of the current new build projects; anticipated new activities; lessons learned, especially the technology neutral approach; application to our other licensed activities, including non-power reactors; and work underway to further develop CNSC methods. Qualifications Needed to Design, Construct and Manufacture Nuclear Systems and Equipment, C. Voutsinos

Completion of decommissioning: Monitoring for site release and license termination

International Nuclear Information System (INIS)

Boing, L.E.

1997-01-01

To request termination of a license upon completion of dismantling or decommissioning activities, documenting any residual radioactivity to show that the levels are environmentally acceptable will be necessary. When the regulators approve the decommissioning plan, they establish what the release criteria for the decommissioned site will be at the time of the site release and license termination. The criteria are numeric guidelines for direct radiation in soils and on surfaces. If the regulatory body finds that the measured on-site values are below the guidelines, the site will be acceptable for unrestricted release (no radiological controls or future use). If areas are found above those values, more decontamination or cleanup of these areas may be required unless the regulatory body grants an exemption

The problem of licensing and safety of nuclear power plants

International Nuclear Information System (INIS)

Silva, R.A. da.

1987-01-01

The historical evolution of licensing process of nuclear power plants is presented. The designs carried out by FURNAS for constructing Angra-1 reactor and its contribution to the Brazilian CNEN in de licensing process, are evaluated. The aims of FURNAS Research Programs are determined and the safety goals are established. (M.C.K.) [pt

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

Science.gov (United States)

2013-06-20

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

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 issues in the context of terrorist attacks on nuclear power plants

International Nuclear Information System (INIS)

Danwitz, T. von

2002-01-01

The terrorist attack on the World Trade Center in September 2001 has prompted enhanced nuclear risk awareness among the German population. But in the current public debate about the safety of nuclear power plants in Germany in times of new dimensions of danger, aspects such as the role of the constitutional law, the German Atomic Energy Act, and the regulatory system governing nuclear power plant licensing in the context of protection and safety have not been addressed. The author therefore discusses the German nuclear power plant licensing law and administrative regime, elaborating on the significance attributed in those bodies of law to risks like terrorist attacks on nuclear power plants. (orig./CB) [de

Department of Energy interest and involvement in nuclear plant license renewal activities

International Nuclear Information System (INIS)

Bustard, L.D.; Harrison, D.L.

1991-01-01

Recognizing the importance of nuclear license renewal to the nation's energy strategy, the Department of Energy (DOE) initiated a plant lifetime improvement program during 1985 to determine the feasibility of the license renewal option for US nuclear plants. Initial activities of the DOE program focused on determining whether there were technical and economic obstacles that might preclude or limit the successful implementation of the license renewal option. To make this determination, DOE cosponsored with the Electric Power Research Institute (EPRI) pilot-plant efforts by Virginia Electric Power and Northern States Power. Both pilot-plant efforts concluded that life extension is technically and economically feasible. In parallel with the pilot-plant activities, DOE performed national economic studies that demonstrated the economic desirability of life extension. Having demonstrated the feasibility of life extension, DOE, in conjunction with EPRI, selected two lead plants to demonstrate the license renewal process. These lead plants are Yankee Atomic's Yankee Rowe facility and Northern States Power's Monticello facility. DOE also initiated activities to develop the technical and regulatory bases to support the license renewal process in the United States. DOE has recently identified nuclear plant license renewal to be an important element of its National Energy Strategy. This paper summarizes the significant results, conclusions, and ongoing activities of the DOE effort. 18 refs

76 FR 81994 - UniStar Nuclear Energy; Combined License Application for Calvert Cliffs Nuclear Power Plant, Unit...

Science.gov (United States)

2011-12-29

... NUCLEAR REGULATORY COMMISSION [Docket No. 52-016; NRC-2008-0250] UniStar Nuclear Energy; Combined License Application for Calvert Cliffs Nuclear Power Plant, Unit 3; Exemption 1.0 Background: UniStar Nuclear Energy (UNE) submitted to the U.S. Nuclear Regulatory Commission (NRC or the Commission ) a...

Status of the Monticello nuclear generating plant lead plant license renewal program

International Nuclear Information System (INIS)

Pickens, T.A.

1992-01-01

In 1988, the Monticello nuclear generating plant was chosen by the US Department of Energy through Sandia National Laboratories and the Electric Power Research Institute to serve as the lead boiling water reactor in the lead plant license renewal program. The purpose of the lead plant license renewal program is to provide insights during the development of and to demonstrate the license renewal regulatory process with the US Nuclear Regulatory Commission (NRC). The work being performed in three phases: (1) preparation of the technical basis for license renewal; (2) development of the technical basis into a formal license renewal application; and (3) review of the application by the NRC. This paper discusses the systems and structures identified as important to license renewal in accordance with 10CFR54 as well as the plant documents and programs that were used in going through the identification process. The systems and structures important to license renewal will then provide insights into how structures and components were identified that are required to be evaluated for aging, the elements of the aging evaluations, and the effective programs used to manage potentially significant aging

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

Science.gov (United States)

2013-07-31

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

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

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

Factors of site selection for nuclear power plants in selected industrial states

International Nuclear Information System (INIS)

Hoffmann, L.; Obermair, G.; Ringler, W.; Romahn, B.; Sanders, H.

1978-01-01

The range of the tasks within the project consists of working out an optimal catalogue of criteria for the site selection for nuclear power plants; establishing a structured documentation system for the criteria and licensing procedures used by selected industrial countries when selecting sites for nuclear power plants; analyzing and evaluating the documented material with the aim of supplying the basis for decisions concerning land use. The tasks are being realized within a technological ring of data (for the period until 1990, reactor types, cooling, power-heat coupling, special sites, block sizes, local concentration) and a set politico-economical ring of data for the following countries: F.R. Germany, Belgium, Switzerland, Great Britain, Sweden, Denmark, Austria, France, Netherlands, USA, Japan, Yougoslavia. (HP) [de

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

Aspects of supervision of the clearance of nuclear fuel production sites in the Hanau area

International Nuclear Information System (INIS)

Hummel, L.; Ibach, T.M.; Lehmann, K.-H.

2002-01-01

Five nuclear fuel production facilities in the Hanau area are shut down and have to be dismantled. The activities and the licenses for these activities are carried out and issued step by step. In charge of the licensing authorities, TUeV Sueddeutschland evaluated clearance limits as far as they were not given by law and carried out the on-site supervision. This includes independent measurements, the control of a safe clearance strategy and the solution of the specific problems that arise by the characteristics of nuclear fuel. These problems were solved, mainly by specific gamma spectrometric measuring and evaluation techniques, such as adapted in situ spectrometry and a conveyor belt device. At the end of this process is a green field or a site with buildings which can be re-used for purposes not subject to the atomic law. (author)

77 FR 51581 - Request for a License To Export Nuclear Grade Graphite

Science.gov (United States)

2012-08-24

... NUCLEAR REGULATORY COMMISSION Request for a License To Export Nuclear Grade Graphite Pursuant to... 27, 2012, graphite for of nuclear grade graphite to the XMAT424, 11006032. nuclear end use. graphite. Shanghai Institute of Applied Physics in China to test various types of nuclear grade graphite material in...

Underground siting of nuclear power plants

International Nuclear Information System (INIS)

Bender, F.

1982-01-01

The symposium gave the opportunity for an international exchange of views on the concepts of underground nuclear power plants, which are presently world wide under consideration. The results of investigations into the advantages and disadvantages with regard to the technical safety aspects of the underground plants in comparison to plants on the surface led to open and sometimes controversal discussions. As a result of the symposium (32 contributions) a general agreement can be stated on the judgement concerning the advantages and the disadvantages of underground nuclear power plants (nnp). The advantages are: increased protection against external events; delayed release of fission products in accident situations, if the closures operate properly. The disadvantages are: increased costs of the construction of underground and restrictions to such sites where either large caverns or deep pits can be constructed, which also requires that certain technical problems must be solved beforehand. Also, additional safety certificates related to the site will be required within the licensing procedures. The importance of these advantages and disadvantages was in some cases assessed very differently. The discussions also showed, that there are a number of topics where some questions have not been finally answered yet. (orig./HP) [de

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)

Licensing operators for commercial nuclear power plants

International Nuclear Information System (INIS)

Hannon, J.N.

1988-01-01

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

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

Science.gov (United States)

2010-01-14

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

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

International Nuclear Information System (INIS)

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

2008-01-01

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

Safety Considerations in the Selection of Nuclear Power Plant Candidate Sites in Johor State, Malaysia

International Nuclear Information System (INIS)

Ramli, A.T.; Basri, N.A.; Abu Hanifah, N.Z.H.

2014-01-01

Nuclear power is considered as one of the best options for future energy development in Malaysia. Since Malaysia has no experience in nuclear energy generation / production, commissioning the first nuclear power plant needs tremendous effort in various aspects. The most obvious challenges are to ensure the nation’s safety and to handle security issues that may arise from a nuclear power plant site. This paper aims to propose a site for nuclear power plant in Johor State, Malaysia as well as listing the possible safety challenges in the process. The site selection uses the Malaysian Atomic Energy Licensing Board (AELB) guideline document as the main reference, supported by documents from International Atomic Energy Agency (IAEA) and from various countries. Only five site characteristics are chosen as study parameters – geological features and seismic data, air dispersion analysis using meteorological data, population distribution, safety zones and emergency supports. This paper concluded that site number 2 (CS2) at Tanjung Tenggaroh, Mersing is the most suitable area for nuclear power plant in Johor state. It has the least possible risks, safety and security issues. (author)

Safety Considerations in the Selection of Nuclear Power Plant Candidate Sites in Johor State, Malaysia

Energy Technology Data Exchange (ETDEWEB)

Ramli, A. T.; Basri, N. A.; Abu Hanifah, N. Z.H., [Department of Physics, Faculty of Science Universiti Teknologi Malaysia Johor (Malaysia)

2014-10-15

Nuclear power is considered as one of the best options for future energy development in Malaysia. Since Malaysia has no experience in nuclear energy generation / production, commissioning the first nuclear power plant needs tremendous effort in various aspects. The most obvious challenges are to ensure the nation’s safety and to handle security issues that may arise from a nuclear power plant site. This paper aims to propose a site for nuclear power plant in Johor State, Malaysia as well as listing the possible safety challenges in the process. The site selection uses the Malaysian Atomic Energy Licensing Board (AELB) guideline document as the main reference, supported by documents from International Atomic Energy Agency (IAEA) and from various countries. Only five site characteristics are chosen as study parameters – geological features and seismic data, air dispersion analysis using meteorological data, population distribution, safety zones and emergency supports. This paper concluded that site number 2 (CS2) at Tanjung Tenggaroh, Mersing is the most suitable area for nuclear power plant in Johor state. It has the least possible risks, safety and security issues. (author)

Regulatory analysis for final rule on nuclear power plant license renewal

International Nuclear Information System (INIS)

1991-12-01

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

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.

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)

The licensing procedure for construction and operation of nuclear power plants

International Nuclear Information System (INIS)

Salvatore, J.E.L.

1980-03-01

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

Reactors licensing: proposal of an integrated quality and environment regulatory structure for nuclear research reactors in Brazil

International Nuclear Information System (INIS)

Serra, Reynaldo Cavalcanti

2014-01-01

A new integrated regulatory structure based on quality and integrated issues has been proposed to be implemented on the licensing process of nuclear research reactors in Brazil. The study starts with a literature review about the licensing process in several countries, all of them members of the International Atomic Energy Agency. After this phase it is performed a comparative study with the Brazilian licensing process to identify good practices (positive aspects), the gaps on it and to propose an approach of an integrated quality and environmental management system, in order to contribute with a new licensing process scheme in Brazil. The literature review considered the following research nuclear reactors: Jules-Horowitz and OSIRIS (France), Hanaro (Korea), Maples 1 and 2 (Canada), OPAL (Australia), Pallas (Holand), ETRR-2 (Egypt) and IEA-R1 (Brazil). The current nuclear research reactors licensing process in Brazil is conducted by two regulatory bodies: the Brazilian National Nuclear Energy Commission (CNEN) and the Brazilian Institute of Environment and Renewable Natural Resources (IBAMA). CNEN is responsible by nuclear issues, while IBAMA by environmental one. To support the study it was applied a questionnaire and interviews based on the current regulatory structure to four nuclear research reactors in Brazil. Nowadays, the nuclear research reactor’s licensing process, in Brazil, has six phases and the environmental licensing process has three phases. A correlation study among these phases leads to a proposal of a new quality and environmental integrated licensing structure with four harmonized phases, hence reducing potential delays in this process. (author)

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

10 CFR 50.55 - Conditions of construction permits, early site permits, combined licenses, and manufacturing...

Science.gov (United States)

2010-01-01

... construction or manufacture, or any defect found in the final design of a facility as approved and released for..., combined licenses, and manufacturing licenses. 50.55 Section 50.55 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES Issuance, Limitations, and Conditions of...

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

International Nuclear Information System (INIS)

Nordlinger, M.S.

1993-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2006-01-01

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

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

Insights from Siting New Nuclear Power Plants in the Central and Eastern United States

International Nuclear Information System (INIS)

Munson, Clifford G.; Kugler, Andrew J.

2011-01-01

The staff of the U.S. Nuclear Regulatory Commission (NRC) has completed its review for four early site permits and for four standard reactor designs. It is currently reviewing applications for fourteen combined license applications and three additional reactor designs. The staff is applying lessons it has learned from the reviews to date to the review work going forward. The licensing process being used by current applicants differs significantly from that used by the current operating fleet. The previous process required two steps. First an applicant had to obtain a construction permit to build the plant. Then, near the end of construction, the applicant had to obtain an operating license. Under the process in Part 52, an applicant can apply for a combined license (COL) that allows construction and (once certain conditions are met) operation of a new plant - a one-step process. An applicant for a COL may reference an early site permit (ESP13), a standard design certification, both, or neither. In addition to developing Part 52, the NRC also revised CFR Part 100 by adding Subpart B, which includes sections 100.21, 'Non-seismic siting criteria', and 100.23, 'Geologic and seismic siting criteria'. The NRC staff also revised the Standard Review Plan (NUREG-0800) and developed Regulatory Guide (RG) 1.206, 'Combined License Applications for Nuclear Power Plants (LWR Edition).' The NRC staff incorporated into the revision of NUREG-0800 and development of RG 1.206 some early lessons learned from its review of the first three ESPs. Staff work begins before the application is received, as the staff interacts with the applicant to identify issues that will require special treatment or specific staff resources. After the application is submitted, if the NRC finds the application acceptable, the safety and environmental reviews begin, proceeding in parallel. The safety review culminates in the issuance of a safety evaluation report (SER) after it

Quality assurance for nuclear power plants licensing aspect

International Nuclear Information System (INIS)

Borovoy, W.F.G.

1976-02-01

For the nuclear industry, specific criteria must be implemented to provide sufficient assurance that nuclear plants will be constructed and operated to conform with design, regulatory and code requirements. In Israel the inspections or audits are performed by the IAEC Licensing Division. Local position on ANSI QA standards as well as the eighteen criteria are shown. Lists of American standards are presented. The responsibility for quality assurance is not shared, but reinforced by each responsible unit in the supply chain. (B.G.)

Nuclear power plant licensing in Canada

International Nuclear Information System (INIS)

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

1997-01-01

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

Nuclear project sites on Shimokita Peninsula in summer 1989

International Nuclear Information System (INIS)

Anon.

1989-01-01

The present report outlines the current progress in the nuclear projects implemented on the Shimokita Peninsula. At Rokkashomura, Japan Nuclear Fuel Industries is building a uranium enrichment plant. The basic work began in October 1988 and was completed by the end of May, and building work on the plant began. The plant building construction has now progressed to 50% for the first unit of 150,000 SUW/year. The site for the low level radioactive waste storage facility is still flat ground. For the reprocessing plant, Japan Nuclear Fuel Service's permit for waste management business is still before STA. Only road construction, unrelated to licensing, is going on. The completion of the safety examination for reprocessing is expected around 1991. At Higashidorimura, a fishery cooperative has rejected the proposal of compensation, and the compensation problem is at a stalemate. Following a zig-zag course in political disturbances, the Nuclear Ship Mutsu entered its port at Sekinehama in January 1988. Corrosion dots were found on some of the fuel assemblies, and Japan Atomic Energy Research Institute plans to carry out the recovery work in this autumn. Site acquisition procedures for building an Ohma nuclear power plant are now under way. (N.K.)

77 FR 22362 - Exemption Requests for Special Nuclear Material License SNM-362, Department of Commerce...

Science.gov (United States)

2012-04-13

... Nuclear Material License SNM-362, Department of Commerce, Gaithersburg, MD AGENCY: Nuclear Regulatory... Commerce, National Institutes of Standards and Technology (NIST) in Gaithersburg, Maryland. NIST requested... within the Department of Commerce. The SNM license was renewed in 1979, 1985, 1991, and 1997. The current...

Decommissioning and decontamination of licensed reactor facilities and demonstration nuclear power plants

International Nuclear Information System (INIS)

Lear, G.; Erickson, P.B.

1975-01-01

Decommissioning of licensed reactors and demonstration nuclear power plants has been accomplished by mothballing (protective storage), entombment, and dismantling or a combination of these three. The alternative selected by a licensee seems to be primarily based on cost. A licensee must, however, show that the decommissioning process provides adequate protection of the health and safety of the public and no adverse impact on the environment. To date the NRC has approved each of the alternatives in the decommissioning of different facilities. The decommissioning of small research reactors has been accomplished primarily by dismantling. Licensed nuclear power plants, however, have been decommissioned primarily by being placed in a mothballed state in which they continue to retain a reactor license and the associated licensee responsibilities

Geoprocessing semiautomated applied to licensing of nuclear facilities

International Nuclear Information System (INIS)

Oliveira, Aline Fabiane Gonçalves de

2017-01-01

In recent decades, Brazilian environmental legislation has undergone considerable evolution. This fact occurs concurrently with changes related to environmental studies, which aim increasingly to guarantee sustainability and environmental balance. Thus, it is important to use technological resources to optimize the environmental studies involved in the licensing processes. The present work sought to analyze and direct the application of geotechnologies (Geoprocessing) in environmental studies of the Local Report (RL) of the Center for the Development of Nuclear Technology (CDTN). The proposal to apply the Geoprocessing tools and the possibilities inherent to the Geographic Information Systems (GIS) technology, as a tool to subsidize the environmental studies in accordance with the requirements of the RL was aimed at contributing to the modernization of the stages involved in the process of Nuclear licensing, such as in the structuring and execution of environmental studies, as well as in the activities of environmental monitoring, always considering the precepts in force in the laws and resolutions and standards in force of the National Nuclear Energy Commission (CNEN) for nuclear licensing. In order to achieve the objective, the ArcGis application was adopted and one of its analytical tools Model Builder. This allowed the macro (schematization) of the methodology from the GIS tools applied, presenting as an advantage the efficiency and optimization of the execution time of the procedures in situations where it is necessary to apply the same routine of tasks, besides being editable, Which provides possibilities for adaptations and improvements. In order to achieve this objective, the applicability of the methodology was highly feasible, the model developed by Model Builder / ArcMap, provided a semi-automated process, and provided a flowchart that depicts the procedure to be performed in order to reach the Final process to make inferences and analyzes with greater

The art and trend of nuclear power plants aging management and licenses renewal activity In USA

International Nuclear Information System (INIS)

Zhong Zhimin; Li Jinsong; Zhang Mengyi

2014-01-01

This paper briefly introduced the history and the art of nuclear power plants licenses renewal in United State. The aims, working scope, methodology, the art and trend of aging management and its role in license renewal process in United State nuclear power plants license renewal process were discussed in details. Furthermore, the aging management current research focus in United State was described. Then, take into account the AP serials Pressurized Water Reactor and nuclear safety requirements in the regulatory and safety guide in China, some suggestions and recommendation on nuclear power plants aging management were introduced, which will be helpful when we developed related aging management works in China. (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)

Safety and licensing requirements in the Republic of South Africa

International Nuclear Information System (INIS)

Simpson, D.M.; Langford, E.L.

1986-01-01

The principles for licensing of nuclear installations in South Africa are based on the control of mortality risk to the operators of an installation and the population resident in the vicinity of the site. This paper describes the development of this safety philosophy, and the nuclear licensing process used in this country. The structure of the nuclear regulatory function is briefly described, including the respective roles of the Atomic Energy Corporation, Licencing Branch and the Council for Nuclear Safety. The development of risk criteria and quantitative release magnitude-probability criteria for radioactive material is outlined. Tasks that have to be undertaken by a potential waste disposal site licensee before a site licence is issued are described. Once the facility is commissioned periodic monitoring procedures will have to be adopted throughout the lifetime of the facility. The scope of typical monitoring activities is outlined and the ongoing analyses to be performed and the records to be kept are discussed

Study of the legal problems raised by the siting of nuclear power stations in artificial islands

International Nuclear Information System (INIS)

Hebert, J.; Guieze, J.L.

1975-01-01

The creation and operation of a nuclear power station on an artificial island in French waters are governed by domestic law and are subject to two types of procedure: the first concerns erection of the artificial island and the second the control of the public authorities over creation and operation of the nuclear power station. At administrative level, the setting up of an artificial island requires that it be attached to a commune as well as permission for occupancy from the maritime authorities. Furthermore, setting up of a nuclear power station on an artificial island is subject to the licensing procedure for large nuclear installations and to delivery of the licenses required for release of gaseous and liquid radioactive effluents. Given the proximity of the high seas and eventually, the borders of other States, siting of a nuclear power station on an artificial island imposes obligations at international level. These requirements, which concern prevention of transfrontier pollution, stem from the London (1972) and Paris (1974) Conventions on marine pollution. The third party liability regime for a nuclear incident caused by an installation sited in territorial seas is that of the 1960 Paris Convention on third party liability in the nuclear field and the 1963 Brussels Supplementary Convention. Another problem likely to be raised is that of the right of innocent passage of ships near such installations [fr

Licensing method for new nuclear power plant: A study on decision making modeling

Energy Technology Data Exchange (ETDEWEB)

Ramli, N; Ohaga, E. O.; Jung, J. C. [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

2012-10-15

This work provides a study on decision making modeling for a licensing method of a new nuclear power plant. SWOT analysis provides the licensing alternatives attributes, then the expectation from either COL or two step licensing method is decided by inputting the output from the Hurwitz mathematical model. From the analysis, COL shows the best candidate for both optimistic and pessimistic conditions.

Licensing method for new nuclear power plant: A study on decision making modeling

International Nuclear Information System (INIS)

Ramli, N; Ohaga, E. O.; Jung, J. C.

2012-01-01

This work provides a study on decision making modeling for a licensing method of a new nuclear power plant. SWOT analysis provides the licensing alternatives attributes, then the expectation from either COL or two step licensing method is decided by inputting the output from the Hurwitz mathematical model. From the analysis, COL shows the best candidate for both optimistic and pessimistic conditions

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

The National Site Licensing of Electronic Resources: An Institutional Perspective

Directory of Open Access Journals (Sweden)

Xiaohua Zhu

2011-06-01

Full Text Available While academic libraries in most countries are struggling to negotiate with publishers and vendors individually or collaboratively via consortia, a few countries have experimented with a different model, national site licensing (NSL. Because NSL often involves government and large-scale collaboration, it has the potential to solve many problems in the complex licensing world. However, not many nations have adopted it. This study uses historical research approach and the comparative case study research method to explore the seemingly low level of adoption. The cases include the Canadian National Site Licensing Project (CNSLP, the United Kingdom’s National Electronic Site Licensing Initiative (NESLI, and the United States, which has not adopted NSL. The theoretical framework guiding the research design and data collection is W. Richard Scott’s institutional theory, which utilizes three supporting pillars—regulative, normative, and cultural-cognitive—to analyze institutional processes. In this study, the regulative pillar and the normative pillar of NSL adoption— an institutional construction and change—are examined. Data were collected from monographs, research articles, government documents, and relevant websites. Based on the analysis of these cases, a preliminary model is proposed for the adoption of NSL. The factors that support a country’s adoption of NSL include the need for new institutions, a centralized educational policy-making system and funding system, supportive political trends, and the tradition of cooperation. The factors that may prevent a country from adopting NSL include decentralized educational policy and funding, diversity and the large number of institutions, the concern for the “Big Deal,” and the concern for monopoly.

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

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)

Legislative and regulatory aspects of nuclear power reactor licensing in the U.S.A

International Nuclear Information System (INIS)

Malsch, M.G.

1976-01-01

An explanation of the origins, statutory basis and development of the present regulatory system in the US. A description of the various actions which must be taken by a license applicant and by the USNRC before a nuclear power plant can be constructed and placed on-line. Account of the current regulatory practices followed by the USNRC in licensing nuclear power reactors. (orig./HP) [de

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

International Nuclear Information System (INIS)

Chandiwala, F.; Evans, W.P.

1999-01-01

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

Australian Radiation Protection and Nuclear Safety Act 1998. Guide to the Australian radiation protection and nuclear safety licensing framework. 1. ed.

International Nuclear Information System (INIS)

1999-03-01

The purpose of this guide is to provide information to Commonwealth entities who may require a license under the Australian Radiation Protection and Nuclear Safety (ARPANS) Act 1998 to enable them to posses, have control of, use, operate or dispose of radiation sources. The guide describes to which agencies and what activities require licensing. It also addresses general administrative and legal matters such as appeal procedures, ongoing licensing requirements, monitoring and compliance. Applicants are advised to consult the Australian Radiation Protection and Nuclear Safety Act 1998 and accompanying Regulations when submitting applications

Australian Radiation Protection and Nuclear Safety Act 1998. Guide to the Australian radiation protection and nuclear safety licensing framework; 1. ed

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-03-01

The purpose of this guide is to provide information to Commonwealth entities who may require a license under the Australian Radiation Protection and Nuclear Safety (ARPANS) Act 1998 to enable them to posses, have control of, use, operate or dispose of radiation sources. The guide describes to which agencies and what activities require licensing. It also addresses general administrative and legal matters such as appeal procedures, ongoing licensing requirements, monitoring and compliance. Applicants are advised to consult the Australian Radiation Protection and Nuclear Safety Act 1998 and accompanying Regulations when submitting applications

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

Aseismic Design Licensings and guidelines for nuclear power plant in Japan

Energy Technology Data Exchange (ETDEWEB)

Yoshizawa, Kazumi [Agency of Natural Resources and Energy, Tokyo (Japan)

1997-03-01

This paper describes Aseismic Design Licensing for Japanese Nuclear Power Plants which includes system, procedures and brief contents concerned application, permit and inspection, and the `Examination Guide for Aseismic Design of the Nuclear Power Reactor Facilities` which focused principals of seismic design loads, load combinations, and allowable limits. (J.P.N.)

Aseismic Design Licensings and guidelines for nuclear power plant in Japan

International Nuclear Information System (INIS)

Yoshizawa, Kazumi

1997-01-01

This paper describes Aseismic Design Licensing for Japanese Nuclear Power Plants which includes system, procedures and brief contents concerned application, permit and inspection, and the 'Examination Guide for Aseismic Design of the Nuclear Power Reactor Facilities' which focused principals of seismic design loads, load combinations, and allowable limits. (J.P.N.)

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

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

International Nuclear Information System (INIS)

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

1982-07-01

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

The role of effective communications in Nuclear Regulatory Commission licensing

International Nuclear Information System (INIS)

Counsil, W.G.

1991-01-01

Communications are essential to the licensing and general regulatory program of the Nuclear Regulatory Commission. This paper attempts to identify and address certain aspects of, and approaches to, maintaining effective and efficient communications. It considers, from the perspective of the high-level radioactive waste repository program, both internal communication within the DOE itself and external communication with the Nuclear Regulatory Commission and interested parties. Many of the points presented are based on lessons learned from electric utility experience with nuclear plants

Changing concepts of geologic structure and the problem of siting nuclear reactors: examples from Washington State

International Nuclear Information System (INIS)

Tabor, R.W.

1986-01-01

The conflict between regulation and healthy evolution of geological science has contributed to the difficulties of siting nuclear reactors. On the Columbia Plateau in Washington, but for conservative design of the Hanford reactor facility, the recognition of the little-understood Olympic-Wallowa lineament as a major, possibly still active structural alignment might have jeopardized the acceptability of the site for nuclear reactors. On the Olympic Peninsula, evolving concepts of compressive structures and their possible recent activity and the current recognition of a subducting Juan de Fuca plate and its potential for generating great earthquakes - both concepts little-considered during initial site selection - may delay final acceptance of the Satsop site. Conflicts of this sort are inevitable but can be accommodated if they are anticipated in the reactor-licensing process. More important, society should be increasing its store of geologic knowledge now, during the current recess in nuclear reactor siting

Geoelectrical monitoring of simulated subsurface leakage to support high-hazard nuclear decommissioning at the Sellafield Site, UK

Energy Technology Data Exchange (ETDEWEB)

Kuras, Oliver, E-mail: oku@bgs.ac.uk [British Geological Survey, Keyworth, Nottingham NG12 5GG (United Kingdom); Wilkinson, Paul B.; Meldrum, Philip I.; Oxby, Lucy S. [British Geological Survey, Keyworth, Nottingham NG12 5GG (United Kingdom); Uhlemann, Sebastian [British Geological Survey, Keyworth, Nottingham NG12 5GG (United Kingdom); ETH-Swiss Federal Institute of Technology, Institute of Geophysics, Sonneggstr. 5, 8092 Zurich (Switzerland); Chambers, Jonathan E. [British Geological Survey, Keyworth, Nottingham NG12 5GG (United Kingdom); Binley, Andrew [Lancaster Environment Centre, Lancaster University, Lancaster LA1 4YQ (United Kingdom); Graham, James [National Nuclear Laboratory, Central Laboratory, Sellafield, Seascale, Cumbria CA20 1PG (United Kingdom); Smith, Nicholas T. [National Nuclear Laboratory, Central Laboratory, Sellafield, Seascale, Cumbria CA20 1PG (United Kingdom); School of Earth, Atmospheric and Environmental Sciences, Williamson Building, University of Manchester, Oxford Road, Manchester M13 9PL (United Kingdom); Atherton, Nick [Sellafield Ltd, Albion Square, Swingpump Lane, Whitehaven CA28 7NE (United Kingdom)

2016-10-01

A full-scale field experiment applying 4D (3D time-lapse) cross-borehole Electrical Resistivity Tomography (ERT) to the monitoring of simulated subsurface leakage was undertaken at a legacy nuclear waste silo at the Sellafield Site, UK. The experiment constituted the first application of geoelectrical monitoring in support of decommissioning work at a UK nuclear licensed site. Images of resistivity changes occurring since a baseline date prior to the simulated leaks revealed likely preferential pathways of silo liquor simulant flow in the vadose zone and upper groundwater system. Geophysical evidence was found to be compatible with historic contamination detected in permeable facies in sediment cores retrieved from the ERT boreholes. Results indicate that laterally discontinuous till units forming localized hydraulic barriers substantially affect flow patterns and contaminant transport in the shallow subsurface at Sellafield. We conclude that only geophysical imaging of the kind presented here has the potential to provide the detailed spatial and temporal information at the (sub-)meter scale needed to reduce the uncertainty in models of subsurface processes at nuclear sites. - Graphical abstract: 3D fractional resistivity change (resistivity change Δρ divided by baseline resistivity ρ{sub 0}) image showing results of Stage 1 silo liquor simulant injection. The black line delineates the preferential flow path; green cylinders show regions of historic contamination found in sediment cores from ERT boreholes. - Highlights: • 4D geoelectrical monitoring at Sellafield detected and tracked simulated silo leaks. • ERT revealed likely pathways of silo liquor simulant flow in the subsurface. • The method can reduce uncertainty in subsurface process models at nuclear sites. • Has been applied in this form at a UK nuclear licensed site for the first time • Study demonstrates value of 4D geophysics for nuclear decommissioning.

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

International Nuclear Information System (INIS)

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

2010-01-01

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

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

The technical-economic problems concerning the search for sites for nuclear electricity generation facilities

International Nuclear Information System (INIS)

Zimmer, H.J.

1976-01-01

An outline of technical-physical fundamentals, of the design and the mode of operation of LWR reactors is followed by a brief description of the licensing procedure. It is pointed out that safety cannot be a criterion for a site because nuclear power plants have to be safe on every site. The problem of nuclear power plants in the vicinity of towns or densely populated areas is dealt with briefly, too. A method is proposed which allows to find a possible site while investing little time on search and evaluation and which stores this site in a site provision plan. The choice of possible sites is made on three levels which are independent of each other. Possible nuclear power plant sites, on the first level, are considered on the basis of the dominating influence of waste heat discharge and network integration. On the second level, macro-sites are determined by examining the realizability of these possible sites by looking at negative criteria, and, on the third level, the 'fine points' planning stage, a pool of potential micro-sites is determined by applying the 'measure of value' analysis. This is followed by citing an analytical method with which the order of priority amongst 8 possible sites in the USA was determined. (orig./HP) [de

Sociological impacts of nuclear generating stations - summary report on the NRC post-licensing studies. Final report 1 Oct 78-4 Jan 82

International Nuclear Information System (INIS)

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

1982-07-01

The Post-Licensing Studies had four objectives. The first was to identify the socioeconomic effects resulting from the construction and operation of each of twelve nuclear power stations. The socioeconomic variables examined included: economic, demographic, housing, government, public response, and social organization characteristics. The second objective was to determine the way in which the identified effects were evaluated by study area groups. The third objective was to identify the determinants of the project-related effects. This task required knowledge of what combination of site, project, or other determinants was responsible for the project-related effects and for the evaluation of the effects. The fourth objective was to make recommendations with respect to assessment methodologies that could best be used to project the socioeconomic effects of the construction and operation of proposed nuclear generating stations. The objectives of the Post-Licensing Studies are met by the twelve individual case studies and by the Summary Report. The case studies identified the nuclear power stations and describe the evaluation of the effects by area residents. The Summary Report describes the collective findings of the individual case studies, compares the findings across sites to identify possible determinants of the effects, and examines the implication of the findings for future siting decisions and for the methodology most appropriate for projective assessments

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

International Nuclear Information System (INIS)

Nagayama, Munehiro

2017-01-01

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

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 requirements for nuclear merchant ships in the Federal Republic of Germany

International Nuclear Information System (INIS)

Schafstall, H.-G.

1978-01-01

The procedure of approval in the Federal Republic of Germany will be discussed, referring to the participated authorities and organizations. Rules and guidelines relevant for licensing are mentioned in the frame of legal positions. After presentation of general aspects of basic licensing requirements more detailed information is given relative to their accomplishment demonstrated on the German Nuclear Contained Ship NCS-80-Project

76 FR 60941 - Policy Regarding Submittal of Amendments for Processing of Equivalent Feed at Licensed Uranium...

Science.gov (United States)

2011-09-30

... Processing of Equivalent Feed at Licensed Uranium Recovery Facilities AGENCY: Nuclear Regulatory Commission... State-licensed uranium recovery site, either conventional, heap leach, or in situ recovery. DATES... Regarding Submittal of Amendments for Processing of Equivalent Feed at Licensed Uranium Recovery Facilities...

Incorporation of severe accidents in the licensing of nuclear power plants

International Nuclear Information System (INIS)

Alvarenga, Marco Antonio Bayout; Rabello, Sidney Luiz

2011-01-01

Severe accidents are the result of multiple faults that occur in nuclear power plants as a consequence from the combination of latent failures and active faults, such as equipment, procedures and operator failures, which leads to partial or total melting of the reactor core. Regardless of active and latent failures related to the plant management and maintenance, aspects of the latent failures related to the plant design still remain. The lessons learned from the TMI accident in the U.S.A., Chernobyl in the former Soviet Union and, more recently, in Fukushima, Japan, suggest that severe accidents must necessarily be part of design-basis of nuclear power plants. This paper reviews the normative basis of the licensing of nuclear power plants concerning to severe accidents in countries having nuclear power plants under construction or in operation. It was addressed not only the new designs of nuclear power plants in the world, but also the design changes in plants that are in operation for decades. Included in this list are the Brazilian nuclear power plants, Angra-1, Angra-2, and Angra-3. This paper also reviews the current status of licensing in Brazil and Brazilian standards related to severe accidents. It also discusses the impact of severe accidents in the emergency plans of nuclear power plants. (author)

Incorporation of severe accidents in the licensing of nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Alvarenga, Marco Antonio Bayout; Rabello, Sidney Luiz, E-mail: bayout@cnen.gov.b, E-mail: sidney@cnen.gov.b [Comissao Nacional de Energia Nuclear (CNEN) Rio de Janeiro, RJ (Brazil)

2011-07-01

Severe accidents are the result of multiple faults that occur in nuclear power plants as a consequence from the combination of latent failures and active faults, such as equipment, procedures and operator failures, which leads to partial or total melting of the reactor core. Regardless of active and latent failures related to the plant management and maintenance, aspects of the latent failures related to the plant design still remain. The lessons learned from the TMI accident in the U.S.A., Chernobyl in the former Soviet Union and, more recently, in Fukushima, Japan, suggest that severe accidents must necessarily be part of design-basis of nuclear power plants. This paper reviews the normative basis of the licensing of nuclear power plants concerning to severe accidents in countries having nuclear power plants under construction or in operation. It was addressed not only the new designs of nuclear power plants in the world, but also the design changes in plants that are in operation for decades. Included in this list are the Brazilian nuclear power plants, Angra-1, Angra-2, and Angra-3. This paper also reviews the current status of licensing in Brazil and Brazilian standards related to severe accidents. It also discusses the impact of severe accidents in the emergency plans of nuclear power plants. (author)

Study of a conceptual nuclear energy center at Green River, Utah: licensing considerations

International Nuclear Information System (INIS)

Dowdle, M.; Russell, R.; Zillman, D.

1982-04-01

This report examines the laws governing the location of a 9-unit nuclear energy center (NEC) near Green River, Utah. The time frame being considered for development of the conceptual NEC is from 1995 to 2013. Accordingly, the report is forced to speculate about some aspects of the plant, its site and its construction. Most of the report examines existing legal requirements for constructing an NEC. Where pertinent, changes in the law are discussed that would affect an NEC that is to be licensed in one or two decades. In general, no insurmountable legal problems exist that would prevent an NEC from being licensed at the Green River location. Several legal requirements pose significant concerns and would have to be faced before an NEC could be built. Among the major legal constraints are radiation protection, regulatory approval of financing, access to water, and local zoning restrictions. Two other constraints that involve legal matters are the wisdom of standardization of the units and the responsibility of the NEC builder to correct socio-economic impacts on the local area

Evaluating physical protection systems of licensed nuclear facilities using systems engineered inspection guidance

International Nuclear Information System (INIS)

Bradley, R.T.; Olson, A.W.; Rogue, F.; Scala, S.; Richard, E.W.

1980-01-01

The Lawrence Livermore National Laboratory (LLNL) and the US Nuclear Regulatory Commission (NRC) Office of Nuclear Regulatory Research (RES) have applied a systems engineering approach to provide the NRC Office of Inspection and Enforcement (IE) with improved methods and guidance for evaluating the physical protection systems of licensed nuclear facilities

Advances and Challenges in the Implementation of DiD in Siting, Design, and Construction of Nuclear Installations in Vietnam

Energy Technology Data Exchange (ETDEWEB)

Nguyen, H.A., E-mail: nhanh@varans.vn [Vietnam Agency for Radiation and Nuclear Safety, Hanoi (Viet Nam)

2014-10-15

Vietnam is embarking on a development of a nuclear power program. The main focus is now on the initial 1000 MWe x 2 units of the nuclear power plant in Ninh Thuan province. Now, the nuclear projects of Vietnam are in the phase of siting approval and investment projects approval. The design assessment will be performed in 2013-2014; the construction and installation will be performed from now until the operating licensing is obtained in 2020-2021. With state of development of a nuclear power program in Vietnam, this paper only focuses on advances and challenges in the implementation of Defence in Depth (DID) in siting, design, and construction of nuclear installations in Vietnam. (author)

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.)

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

Science.gov (United States)

2013-07-05

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

Siting of nuclear facilities. Selections from Nuclear Safety

Energy Technology Data Exchange (ETDEWEB)

Buchanan, J.R.

1976-07-01

The report presented siting policy and practice for nuclear power plants as developed in the U.S. and abroad. Twenty-two articles from Nuclear Safety on this general topic are reprinted since they provide a valuable reference source. The appendices also include reprints of some relevant regulatory rules and guides on siting. Advantages and disadvantages of novel siting concepts such as underground containment, offshore siting, and nuclear energy parks are addressed. Other topics include site criteria, risk criteria, and nuclear ship criteria.

Siting of nuclear facilities. Selections from Nuclear Safety

International Nuclear Information System (INIS)

Buchanan, J.R.

1976-07-01

The report presented siting policy and practice for nuclear power plants as developed in the U.S. and abroad. Twenty-two articles from Nuclear Safety on this general topic are reprinted since they provide a valuable reference source. The appendices also include reprints of some relevant regulatory rules and guides on siting. Advantages and disadvantages of novel siting concepts such as underground containment, offshore siting, and nuclear energy parks are addressed. Other topics include site criteria, risk criteria, and nuclear ship criteria

Licensing procedures for Low-Level Waste disposal facilities

Energy Technology Data Exchange (ETDEWEB)

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.

Nuclear proliferation and civilian nuclear power: report of the Nonproliferation Alternative Systems Assessment Program. Volume VI. Safety and environmental considerations for licensing

International Nuclear Information System (INIS)

1979-12-01

Volume 6 of the Nonproliferation Alternative Systems Assessment Program report addresses safety and environmental considerations in licensing the principal alternative nuclear reactors and fuel cycles in the United States for large-scale commercial nuclear power plants. In addition, this volume examines the safety and environmental considerations for licensing fuel service centers. These centers, which have been proposed for controlling sensitive fuel-cycle facilities and special nuclear materials, would contain a combination of such facilities as reprocessing plants, fabrication plants, and reactors. For this analysis, two fuel service center concepts were selected - one with power-generating capability and one without. This volume also provides estimates of the time required for development of large-scale commercial reactor systems to reach the construction permit application stage and for fuel-cycle facilities to reach the operating license application stage, which is a measure of the relative technical status of alternative nuclear systems

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 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

Licensing and regulatory control of nuclear power plants in the Federal Republic of Germany

International Nuclear Information System (INIS)

Obenhaus, W.

1977-01-01

The lecture is divided into three parts: 1) the legal conception and requirements of the German Atomic Energy Law (with special view on construction and operation of nuclear power plants), 2) the role of the Federation ('Bund') and the 'Laender' in the field of atomic energy and the Radiation Protection Ordinance (especially for licensing and supervision of nuclear power plants), 3) the function, participants, types and sequence of the strongly formalised licensing procedure for nuclear power plants, technical assessment in the frame of this procedure, content of a licence, possibility for altering the licence at a later date, role of administrative courts, continual supervision. (orig./HP) [de

Environmental licensing of nuclear facilities: compatibility of technical competencies

International Nuclear Information System (INIS)

Shu, J.; Paiva, R.L.C. de; Mezrahi, A.; Cardoso, E.M.; Aquino, W.P.; Deppe, A.L.; Menezes, R.M.; Prado, V.; Franco, N.M.F.L.; Nouailhetas, Y.; Xavier, A.M.

1996-01-01

The Brazilian Nuclear Energy Commission (CNEN) has the technical competency for diagnosing environmental radiological impacts, as well as evaluating the safety and requiring adequate control of the facilities which, due to their activities, represent a potential risk of radiological contamination for the environment. The institution is responsible for emission of radioprotection guidelines, controls and surveys in nuclear safety according to the country's regulations and international recommendations. The methodology to assure the limitation of radiation exposure is consequence from shared control over the nuclear activities, in special the nuclear facilities. According to the Federal Constitution of 1988, the nuclear activities must be under exclusive control of the Union in special related to the nuclear policies, economical, laboral and nuclear safety aspects, while the health and environmental controls of these activities are shared by the Federation, Union, States, Federal District and Counties. The controls related to specific aspects have to be harmonized in such a way to be optimized and effective. In this paper the results of compatibilization of nuclear legislation and environmental legislation are presented aiming to optimize the licensing of nuclear facilities. (author)

SKI's engagement in the process for siting a spent nuclear fuel repository

Energy Technology Data Exchange (ETDEWEB)

Paeivioe Jonsson, Josefin; Westerlind, Magnus [Swedish Nuclear Power Inspectorate, Stockholm (Sweden)

2006-09-15

preferred location for the encapsulation plant for spent nuclear fuel was in the municipality of Oskarshamn (in connection to the central interim storage for spent nuclear fuel, CLAB). This led the municipality to initiate a forum for consultations between the municipality, County Administration Board, SKI and SSI (the so-called MKB-Forum in Kalmar County). They emphasised that active regulators, with clear roles and positions, were a prerequisite for the municipality's involvement in the siting process. In 1996 a feasibility study for a repository was launched by SKB and was included in the MKB-Forum's work. SKI's RandD in the field of nuclear waste management aims at maintaining and developing the competence needed for independent assessments of safety. In recent years the research also includes risk communication and decision-making processes. The co-ordination of EIA and decision making processes according to different acts, in particular the Act on Nuclear Activities and the Environmental Code is one big challenge for all actors involved in process for siting a repository for spent nuclear fuel. Many actors will be involved in the parallel licensing process and it requires good planning and good cooperation. The application for construction of an encapsulation plant will be submitted already in 2006 (addressing mainly technical basis and operational safety), but will be updated in 2008 (e.g. coverage of long-term safety for the sealed waste canisters produced in the plant). These applications must be approved according to the Environmental Code and the Act of Nuclear Activities before construction licenses can be given. A final decision from the Swedish Government will most probably address the whole concept of disposal, simultaneously covering both facilities. With an estimated period covering at least two years for technical review by SKI, SSI and the Swedish Environmental Court (for approval according to Environmental Code) and at least one year for

Licensing of nuclear power plants, immediate implementation, constitutional appeal

International Nuclear Information System (INIS)

Winters, K.P.

1980-01-01

The decision relates to part of the licensing procedure of the Muelheim-Kaerlich Nuclear Power Station. The subject of the complaint of unconstitutionality is the immediate execution of the 7th clearance within the framework of the 1st partial permit, which had been confined by the Rhineland-Palatinate Higher Administrative Court in a decision of May 2, 1977 (DVBl. 1977, p. 730). The Federal Constitutional Court regards the complaint of unconstitutionality as being unfounded. The court expresses itself especially on the assessment, under consnitutional aspects, of the material rules and rules of procedure pertaining to the licensing of nuclear power plants and of major changes in such plants. Moreover, the dissenting opinions of Justices Dr. Simon and Professor Heussner are quoted in excerpts. The comment by K.- P. Winters regards as the nucleus of the decision and of the dissenting vote the statements about the guarantee functions procedural rules have in ensuring effective protection of human rights. In his view, these statements of constitutional law are of fundamental significance for problems of atomic law and radiation protection law. (HSCH) [de

Nuclear fuel licensing requirements: present status and future trends

International Nuclear Information System (INIS)

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

2001-01-01

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

Nuclear licensing reform. Hearings before the Subcommittee on Energy and the Environment, House of Representatives, Ninety-Eighth Congress, First Session on H.R. 2511 and H.R. 2512, June 9 and 30, 1983

International Nuclear Information System (INIS)

Anon.

1984-01-01

Two bills (H.R. 2511 and H.R. 2512) amend licensing and siting regulations in the Atomic Energy Act by introducing the concept of one-stop licensing, encouraging standardized design and early site permits, and replacing adjudicatory proceedings with ''hybrid'' hearings. Witnesses speaking for and against the controversial proposals during the two-day hearing included Nunzio Palladino and other Commissioners of the Nuclear Regulatory Commission, Energy Secretary Hodel, and representatives of electric utilities, the nuclear industry, and environmental and public interest groups. Two appendices with additional material submitted for the hearing record follow the test of the two bills and the statements and testimony of 12 witnesses

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

Assessment of specialized educational programs for licensed nuclear reactor operators

International Nuclear Information System (INIS)

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

1986-02-01

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

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

VGH Mannheim: legitimacy of the decommissioning license for a nuclear power plant

International Nuclear Information System (INIS)

Anon.

2015-01-01

The contribution describes the details of the court (VGH) decision on the legitimacy of the decommissioning license for the NPP Obrigheim. Inhabitants of the neighborhood (3 to 4.5 km distance from the NPP) are suspect hazards for life, health and property due to the dismantling of the nuclear power plant in case of an accident during the licensed measures or a terroristic attack with radioactive matter release.

Public information and licensing procedures for nuclear installations. European experience

International Nuclear Information System (INIS)

Mayoux, J.C.; Chevillard, F.; Mutschler, U.; Stubbe, C.

1981-10-01

This paper reviews the licensing procedures for nuclear installations in various European countries and examines the form, content and methods selected for information and consultation of the public. The author stresses the importance of this stage in the procedure, both for the nuclear operator and the public authorities, given the population's concern about the environment. He concludes that, irrespective of its complexity, the nuclear field cannot remain the concern of a few initiates competent to take decisions and that, consequently, this implies creation of new information systems to meet the public's desire to participate more directly in the process. (NEA) [fr

Some inspirations drawn from the SKB license-application report for the construction of the final repository for spent nuclear fuel in Sweden

International Nuclear Information System (INIS)

Xu Guoqing

2014-01-01

The following problems are described in this paper: the current state of nuclear energy and spent fuel in Sweden, the brief process of repository site selection and the concise geological settings of candidate site Forsmark, the option of repository design, the data presented in license-application report on repository, construction, the review work presented by OECD/NEA international peer review team (IRT) and some considerations noted by the author: 1) Why the design of underground engineering, also known as 5 shafts + l ramp, is adopted? 2) Why the timescale for the assessment is one million years? 3) Why the computer codes used in performance assessment at Forsmark candidate repository site are different from those used at Yucca Mountain candidate repository site? 4) How to carry out the public involvement, support from local government and volumtary siting in China? 5) What is the most important in the R and D program of HLW disposal? 6) What shall we do for the future license-application report for the construction of the final repository in China? (author)

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)

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

76 FR 63330 - Policy Regarding Submittal of Amendments for Processing of Equivalent Feed at Licensed Uranium...

Science.gov (United States)

2011-10-12

... Processing of Equivalent Feed at Licensed Uranium Recovery Facilities AGENCY: Nuclear Regulatory Commission... NRC and Agreement State-licensed uranium recovery site. This action is necessary to correct several... read ``(see Page A2 of SECY-99-011, ``Draft Rulemaking Plan: Domestic Licensing of Uranium and Thorium...

The control density of the administrative courts with regard to nuclear licensing

International Nuclear Information System (INIS)

Deppe, V.

1982-01-01

A possibility does not exist to limit the extent of the activities of administrative courts with regard to the control of the nuclear license decision by a shifting of one part of the ultimate decision competence from the jurisdiction to the executive. The responsibility of the administrative courts which is established in the constitution gives them a comprehensive controlling function with regard to nuclear licensing. Their right of ultimate decision, which is established in the constitution, corresponds to a duty of ultimate decision, which is of paramount importance in such a fundamental law relevant area, as it is nuclear law. The legislator has to help the overburdened courts. The courts themselves are bound to their responsibility as it is laid down in the constitution and the Atomic Energy Act to guarantee legal protection so that any form of self-restraint is inadmissable. (orig./HSCH) [de

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

10 CFR 110.26 - General license for the export of nuclear reactor components.

Science.gov (United States)

2010-01-01

... 10 Energy 2 2010-01-01 2010-01-01 false General license for the export of nuclear reactor components. 110.26 Section 110.26 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) EXPORT AND IMPORT OF... Denmark Finland France Germany Greece Indonesia Ireland Italy Japan Latvia Lithuania Luxembourg...

Effects of Californian PRC 25500 on nuclear power plant licensing

International Nuclear Information System (INIS)

Hahn, F.J.

1976-01-01

The California Public Resources Code 25500 established the Energy Resources Conservation and Development Commission on January 7, 1976. This Act mandated that the Commission process applications for new power plants within very specific timeframes. The paper presents the intent and timing of the two-phase licensing procedure and illustrates the effect of this procedure on power plants already into the NRC licensing process and on power plants which are in the beginning of the site selection process

Recruitment training and licensing of operating personnel for nuclear power plants

International Nuclear Information System (INIS)

Palabrica, R.J.

1979-01-01

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

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

International Nuclear Information System (INIS)

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

1990-01-01

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

Public participation in nuclear licensing procedures from the viewpoint of constitutional law

International Nuclear Information System (INIS)

Mutschler, Ulrich

1981-10-01

This paper reviews public participation in the licensing procedure for nuclear installations, in particular in the Federal Republic of Germany. Examples are given of practical experience acquired to date, also in the field of case-law. Finally, the paper stresses the importance of public information in nuclear procedures in view of the growing concerns for the environment. (NEA) [fr

Information to be submitted in support of licensing applications for nuclear power plants

International Nuclear Information System (INIS)

1979-01-01

This Safety Guide was prepared as part of the Agency's programme, referred to as the NUSS programme, for establishing Codes of Practice and Safety Guides relating to nuclear power plants. It supplements the Agency's Safety Series No.50-C-G, entitled ''Governmental Organization for the Regulation of Nuclear Power Plants: A Code of Practice''. It is concerned with the content of documents which should be submitted to the regulatory body by the applicant/licensee in support of licensing applications, with a possible method of classifying these documents and with the scheduling of their submission to the regulatory body at each major stage of the licensing process

Legal questions concerning the licensing procedure of nuclear power plants

International Nuclear Information System (INIS)

Boerner, B.

1978-01-01

The publication contains 4 articles which deal with legal practice and problems of the licensing procedure in the Federal Republic of Germany: 1) Actions brought by joint boards from the constitutional point of view (Burmeister, J.); 2) court review of the assessment of technical and economic questions concerning the licensing of power plant construction (Ossenbuehl, F.); 3) the site plan approval procedure as a legal problem (Friauf, K.H.); 4) legal questions concerning the immediate enforceability (Papier, H.J.). (HP) [de

Nuclear proliferation and civilian nuclear power. Report of the Nonproliferation Alternative Systems Assessment Program. Volume VI. Safety and environmental considerations for licensing

International Nuclear Information System (INIS)

1980-06-01

This volume of the Nonproliferation Alternative Systems Assessment Program report addresses safety and environmental considerations in licensing the principal alternative nuclear reactors and fuel cycles in the United States for large-scale commercial nuclear power plants. In addition, this volume examines the safety and environmental considerations for licensing fuel service centers. These centers, which have been proposed for controlling sensitive fuel-cycle facilities and special nuclear materials, would contain a combination of such facilities as reprocessing plants, fabrication plants, and reactors. For this analysis, two fuel service center concepts were selected - one with power - generating capability and one without

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

International Nuclear Information System (INIS)

Stadie, K.B.; Strohl, P.

1977-01-01

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

License to build

International Nuclear Information System (INIS)

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

2007-01-01

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

Nuclear energy and the nuclear industry

International Nuclear Information System (INIS)

1979-01-01

These notes have been prepared by the Department of Energy to provide information and to answer questions often raised about nuclear energy and the nuclear industry and in the hope that they will contribute to the public debate about the future of nuclear energy in the UK. The subject is dealt with under the headings; contribution of nuclear power, energy forecasts, nuclear fuels and reactor types, cost, thermal reactor strategy, planning margin, safety, nuclear licensing, unlike an atomic bomb, radiation, waste disposal, transport of nuclear materials, emergency arrangements at nuclear sites, siting of nuclear stations, security of nuclear installations, world nuclear programmes, international regulation and non-proliferation, IAEA safeguards arrangements in the UK, INFCE, and uranium supplies. (U.K.)

Nuclear waste

International Nuclear Information System (INIS)

1988-01-01

The Department of Energy has proposed a draft plan for investigating the Yucca Mountain, Nevada, site to determine if it suitable for a waste repository. This fact sheet provides information on the status of DOE's and the Nuclear Regulatory Commission's efforts to streamline what NRC expects will be the largest and most complex nuclear-licensing proceeding in history, including the development of an electronic information management system called the Licensing Support System

Guide to radiological accident considerations for siting and design of DOE nonreactor nuclear facilities

International Nuclear Information System (INIS)

Elder, J.; Graf, J.M.

1984-01-01

DOE Office of Nuclear Safety has sponsored preparation of a guidance document to aid field offices and contractors in their analyses of consequences of postulated major accidents. The guide addresses the requirements of DOE Orders 5480.1A, Chapter V, and 6430.1, including the general requirement that DOE nuclear facilities be sited, designed, and operated in accordance with standards, codes, and guides consistent with those applied to comparable licensed nuclear facilities. The guide includes both philosophical and technical information in the areas of: siting guidelines doses applied to an offsite reference person; consideration also given to an onsite reference person; physical parameters, models, and assumptions to be applied when calculating doses for comparison to siting criteria; and potential accident consequences other than radiological dose to a reference person which might affect siting and major design features of the facility, such as environmental contamination, population dose, and associated public health effects. Recommendations and/or clarifications are provided where this could be done without adding new requirements. In this regard, the guide is considered a valuable aid to the safety analyst, especially where requirements have been subject to inconsistent interpretation or where analysis methods are in transition, such as use of dose model (ICRP 2 or ICRP 30) or use of probabilistic methods of risk analysis in the siting and design of nuclear facilities

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

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)

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

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)

78 FR 37325 - License Renewal of Nuclear Power Plants; Generic Environmental Impact Statement and Standard...

Science.gov (United States)

2013-06-20

... Nuclear Power Plants; Generic Environmental Impact Statement and Standard Review Plans for Environmental... for Nuclear Power Plants, Supplement 1: Operating License Renewal'' (ESRP). The ESRP serves as a guide... published a final rule, ``Revisions to Environmental Review for Renewal of Nuclear Power Plant Operating...

Nuclear power: Siting and safety

International Nuclear Information System (INIS)

Openshaw, S.

1986-01-01

By 2030, half, or even two-thirds, of all electricity may be generated by nuclear power. Major reactor accidents are still expected to be rare occurrences, but nuclear safety is largely a matter of faith. Terrorist attacks, sabotage, and human error could cause a significant accident. Reactor siting can offer an additional, design-independent margin of safety. Remote geographical sites for new plants would minimize health risks, protect the industry from negative changes in public opinion concerning nuclear energy, and improve long-term public acceptance of nuclear power. U.K. siting practices usually do not consider the contribution to safety that could be obtained from remote sites. This book discusses the present trends of siting policies of nuclear power and their design-independent margin of safety

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

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

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)

Judicial problems in connection with preliminary decision and construction design approval in nuclear licensing procedures

International Nuclear Information System (INIS)

Schmieder, K.

1977-01-01

Standardization in nuclear engineering makes two demands on a legal instrument which is to make this standardization possible and which is to promote standardization in the nuclear licensing practice: On the basis of just one licence for a constructional part or a component, its applicability in any number of subsequent facility licensing procedures has to be warranted, and by virtue of its binding effect, standardization has to create a sufficiently big confidence protection with manufacturers, constructioneers and operators to offer sufficiently effective incentives for standardization. The nuclear preliminary decision pursuant to section 7 a of the Atomic Energy Act in the form of the component preliminary decision appears to be unsuitable as a legal instrument for standardization, as the preliminary decision refers exclusively to the construction of a concrete facility. For standardization in reactor engineering, the construction design approval appears to be basically the proper legal instrument on account of its legal structure as well as its economic effect. Its binding effect encouters a limitation with regard to third parties in so far that this limitation could question again the binding effect in a subsequent site-dependent nuclear licence procedure. The legal structure of the extent of the binding effect, which is decisive for the suitability of the construction design approval, lies with the legislator. The following questions have to be regulated: Ought the applicant to have a legal claim on the granting of a construction design approval, or ought it to be at the discretion of the authorities, and secondly, the extent of the binding effect in terms of time on the basis of the fixation of a time limit, or on the basis of the possibility of subsequent conditions to be imposed, or the revocation. (orig./HP) [de

AP1000R licensing and deployment in the United States

International Nuclear Information System (INIS)

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

2012-01-01

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

Site suitability, selection and characterization: Branch technical position--Low-Level Waste Licensing Branch

International Nuclear Information System (INIS)

Siefken, D.; Pangburn, G.; Pennifill, R.; Starmer, R.J.

1982-04-01

The staff provides an expanded interpretation of the site suitability requirements in the proposed rule 10 CFR Part 61, a description of the anticipated site selection process, and a detailed discussion of the site characterization program needed to support a license application and environmental report. The paper provides early-on guidance to prospective applicants in these three subject areas

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

International Nuclear Information System (INIS)

1975-01-01

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

Public regulation of site selection for nuclear power plants. Present procedures and reform proposals: an annotated bibliography

International Nuclear Information System (INIS)

Klema, E.D.; West, R.L.

1977-01-01

Part I of this bibliography contains literature which describes the process of power-plant siting as conducted by the utilities, siting procedures at the point of initiative, analytical tools employed or proposed for site assessment by enterprises in the industry, and the wide range of considerations which the utilities take into account in making site assessments. Part II contains studies and reports on the structure and process of public regulation of power plant siting: the licensing of nuclear facilities by the NRC under terms of the special Government powers in the field of nuclear energy that have evolved since World War II; the steady expansion of regulatory objectives bearing on site approval for nuclear power plants; local government, State, and other Federal agency regulation of siting; survey siting procedures in other countries; the role of regulatory delay in the long lead-time required for construction and operation of nuclear plants. Part III incudes citations on regulatory structure and practice that are unresponsive to the public interest; regulatory decision making's insufficient accessible to public scrutiny and participation; and regulatory procedures that encourage and protect inefficient practices of the regulated industries. Some legal decisions and case studies are included. Part IV, Reform Proposals, includes citations on regulatory reform and reform of siting regulations. Abstracts are provided with 157 of the citations with many more papers cited by title, author, and accession data

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

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

Science.gov (United States)

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

2017-11-01

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

An international comparison of regulatory organizations and licensing procedures for new nuclear power plants

International Nuclear Information System (INIS)

Bredimas, Alexandre; Nuttall, William J.

2008-01-01

This paper considers measures needed to license new nuclear power plants efficiently. We base our analysis on international standards and a comparison of the national regulatory and licensing framework in seven countries (Canada, France, Germany, Japan, Switzerland, the UK and the USA). We split the review into the organization of regulatory responsibilities and the licensing process. We propose a set of considerations that should be incorporated into national solutions. While conscious of the different cultural fundamentals of each region, we hope this paper will help fuel an emerging debate on this highly topical issue

Communities in the nuclear licensing procedure according to Atomic Energy Act, Article 7

International Nuclear Information System (INIS)

Wald, A.

1978-01-01

The legal positions to be taken by communities in administrative procedures as well as in administrative proceedings in court are pointed out. It is discussed to what extent a community can plead the rights of its inhabitants. The nuclear licensing procedure is investigated more closely and compared with other licensing procedures. The legal position of the communities is discussed with special regard to the right of complaint. (HSCH) 891 HP/HSCH 892 MKO [de

NUCLEAR SAFETY DESIGN BASES FOR LICENSE APPLICATION

International Nuclear Information System (INIS)

Garrett, R.J.

2005-01-01

The purpose of this report is to identify and document the nuclear safety design requirements that are specific to structures, systems, and components (SSCs) of the repository that are important to safety (ITS) during the preclosure period and to support the preclosure safety analysis and the license application for the high-level radioactive waste (HLW) repository at Yucca Mountain, Nevada. The scope of this report includes the assignment of nuclear safety design requirements to SSCs that are ITS and does not include the assignment of design requirements to SSCs or natural or engineered barriers that are important to waste isolation (ITWI). These requirements are used as input for the design of the SSCs that are ITS such that the preclosure performance objectives of 10 CFR 63.111 [DIRS 156605] are met. The natural or engineered barriers that are important to meeting the postclosure performance objectives of 10 CFR 63.113 [DIRS 156605] are identified as ITWI. Although a structure, system, or component (SSC) that is ITS may also be ITWI, this report is only concerned with providing the nuclear safety requirements for SSCs that are ITS to prevent or mitigate event sequences during the repository preclosure period

Requests for licensing of new nuclear sources. New nuclear power source in Slovakia

International Nuclear Information System (INIS)

Vidlicka, R.

2010-01-01

Presentation indicates a new NPP licensing process in the Slovak Republic from the point of the Preparatory Stage - Siting, Design Stage and Construction. The presentation lists individual main criteria and legislation requirements. A part of the presentation covers the estimated new NPP construction schedule and the comparison to proceeding in several foreign countries. (author)

Licensing of nuclear power plants. The case of Sweden in an international comparison

International Nuclear Information System (INIS)

Michanek, Gabriel; Soederholm, Patrik

2009-01-01

Efficient power plant licensing procedures are essential for the functioning of deregulated electricity markets. The purpose of this paper is to review and analyse the licensing process for nuclear power plants in Sweden, and in part contrast the Swedish case with the corresponding approaches in a selection of other countries. This approach permits a discussion of how licensing processes can be altered and what the benefits and drawbacks of such changes are. The paper highlights and discusses a number of important legal issues and implications, including, for instance: (a) the role of political versus impartial decision-making bodies; (b) the tension between national policy goals and implementation at the local level; (c) public participation and access to justice; (d) consistency and clarity of the legal system; and (e) the introduction of license time limits. (author)

78 FR 4467 - UniStar Nuclear Energy, Combined License Application for Calvert Cliffs Power Plant, Unit 3...

Science.gov (United States)

2013-01-22

... NUCLEAR REGULATORY COMMISSION [Docket No. 52-016; NRC-2008-0250] UniStar Nuclear Energy, Combined License Application for Calvert Cliffs Power Plant, Unit 3, Exemption 1.0 Background UniStar Nuclear Energy (UNE), on behalf of Calvert Cliffs Nuclear Project, LLC and UniStar Nuclear Operating Services...

A future for nuclear sites beyond their service life. Nuclear site value development

International Nuclear Information System (INIS)

2008-01-01

As the nuclear industry moves into a new development phase, many facilities built in the fifties and sixties are reaching the end of their service life. Dismantling them and rehabilitating the sites on which they stand is a major industrial challenge which will give rise to a number of new projects. AREVA has more than 20 years' experience in these highly technical fields. As more and more sites reach the end of their service life, AREVA considers nuclear site value development as a fully-fledged industrial activity. The group's competencies in this field have been grouped together to form a dedicated entity: the Nuclear Site Value Development Business Unit, created in 2008. Several billion euros are invested in site value development projects which are far-reaching and complex, and often last for several decades. Long before work actually begins, lengthy studies and preparations are required to schedule operations, select the techniques to be used and optimize costs and deadlines. The Nuclear Site Value Development BU is currently working on four major projects involving its own facilities and those of the CEA: - La Hague: dismantling of the first generation of used fuel recycling facilities. Between 1966 and 1998, almost 5,000 tons of used fuel from graphite-moderated gas-cooled reactors, 4,500 tons of light water reactor fuel, as well as fuel from fast reactors and research reactors, were treated at UP2 400, the very first industrial recycling plant on the La Hague site. - Marcoule: first-time dismantling of a recycling plant. 1,000 rooms to be cleaned up, 30,000 tons of waste to be treated, 30 years of work. - Cadarache: first-time dismantling of a Mox fuel fabrication plant. The Cadarache plant was commissioned in 1962 to fabricate fuel for fast reactors; this was followed by MOX fuel for light water reactors, an activity which continued until the plant was shut down in 2003. - Annecy and Veurey: giving a new lease of life to former industrial sites in built

Recycling and disposal of FUSRAP materials from the Ashland 2 site at a licensed uranium mill

International Nuclear Information System (INIS)

Howard, B.; Conboy, D.; Rehmann, M.; Roberts, H.

1999-01-01

During World War II the Manhattan Engineering District (MED) used facilities near Buffalo, N.Y. to extract natural uranium from ores. Some of the byproduct material left from the ores (MED byproduct), containing low levels of uranium, thorium, and radium, was deposited on a disposal site known as Ashland 2, located in Tonawanda, NY. On behalf of the United States Army Corps of Engineers (USACE, or the Corps), ICF Kaiser Engineers (ICFKE) was tasked to provide the best value clean-up results that meet all of the criteria established in the Record of Decision for the site. International Uranium (USA) Corporation (IUC), the operator of the White Mesa Uranium Mill, a Nuclear Regulatory Commission (NRC)-licensed mill near Blanding, Utah, was selected to perform uranium extraction on the excavated materials, therefore giving the best value as it provided beneficial use of the material consistent with the Resource Conservation and Recovery Act (RCRA) intent to encourage recycling and recovery, while also providing the most cost-effective means of disposal. Challenges overcome to complete this project included (1) identifying the best-value location to accept the material; (2) meeting regulatory requirements with IUC obtaining an NRC license amendment to accept and process the material as an alternate feed; (3) excavating and preparing the material for shipment, then shipping the material to the Mill for uranium recovery; and (4) processing the material, followed by disposal of tailings from the process in the Mill's licensed uranium tailings facility. Excavation from Ashland 2 and processing of the Ashland 2 material at the White Mesa Mill resulted in a cleaner environment at Tonawanda, a cost avoidance of up to $16 million, beneficial recovery of source material, and environmentally protective disposal of byproduct material. (author)

License renewal in the United States

International Nuclear Information System (INIS)

Brons, Jack

2002-01-01

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

Potential Nuclear Power Plant Siting Issues in the United Arab Emirates

International Nuclear Information System (INIS)

Al Hanai, Waddah T.

2011-01-01

Based on the need to develop additional sources of electricity to meet future demand and to ensure the rapid growth of its economy, the United Arab Emirates has embarked on a nuclear programme. The Federal Law by Decree No. 6 of 2009, Concerning the Peaceful Uses of Nuclear Energy was signed by the President, last fall. This law created the Federal Authority for Nuclear Regulation (FANR), which is developing the framework of regulations which will guide the UAE programme. This paper reviews the development of the FANR regulation on Siting and the related environmental issues in general and those unique to the area. This will include steps being planned by the Authority to review the license application and the current concepts being looked at for the inspection programme. Among the unique aspects the author will look at are the results from a recent in-depth study performed on dust and sand storms. (author)

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

International Nuclear Information System (INIS)

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

1987-01-01

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

Nuclear site selection studies

International Nuclear Information System (INIS)

Gharib, A.; Zohoorian Izadpanah, A.A.; Iranmanesh, H.

2000-01-01

It is of special importance, especially from the nuclear safety viewpoint, to select suitable sites for different nuclear structures with the considered future activities. Site selection sometimes involves high costs not necessarily for merely selecting of site but for some preliminary measures to be taken so as the site may have the necessary characteristics. The more suitable the natural characteristics of the site for the considered project, the more successful and efficient the project, the lower the project costs and the longer the project operation period. If so, the project will cause the growth of public culture and sustainable socioeconomic development. This paper is the result of the conclusion of numerous massive reports of this activity in the preliminary phase based on theories, practices and the related safety principles on this ground as well as the application of data and information of the past and a glance to the future. The conception of need for a site for medium structures and nuclear research projects and how to perform this process are presented step by step here with a scientific approach to its selection during the investigations. In this study, it is practically described how the site is selected, by determining and defining the characteristics of research and nuclear projects with medium structures and also its fitting to the optimum site. The discovered sites typically involve the best advantages in technical and economic aspects and no particular contrast with the concerned structures

Environmental Standard Review Plan for the review of license renewal applications for nuclear power plants

International Nuclear Information System (INIS)

O'Brien, J.; Kim, T.J.; Reynolds, S.

1991-08-01

The Environmental Standard Review Plan for the Review of License Applications for Nuclear Power Plants (ESRP-LR) is to be used by the NRC staff when performing environmental reviews of applications for the renewal of power reactor licenses. The use of the ESRP-LR provides a framework for the staff to determine whether or not environmental issues important to license renewal have been identified and the impacts evaluated and provides acceptance standards to help the reviewers comply with the National Environmental Policy Act

Current status of LTO licensing programme for Bohunice nuclear power plant

International Nuclear Information System (INIS)

Borak, J.; Kupca, L.

2012-01-01

The objective of long term operation (LTO) licensing programme for Bohunice nuclear power plant is to demonstrate that the relevant structures and components shall perform their functions throughout the entire LTO period during which they shall meet all the relevant safety requirements. All the activities-which should result in utility's request to obtain the licence for LTO-must be performed in line with the relevant legal basis. As of May 2012, the anticipated duration of currently running programme is thirteen months. All relevant documentation, required by the established legal basis, shall be submitted to the licensing authority one year before the Unit 3 design life expiry. (author)

Organization and practices on regulatory review in the licensing process of nuclear power plants in Spain

International Nuclear Information System (INIS)

Trueba, P.

1979-01-01

The actual organisation, practices and experience of the JEN Nuclear Safety Department on the regulatory review in the licensing process of nuclear power plants in Spain, are presented. Topics to be covered are: The structure, organisation, staff and principal functional areas of the NSD, the academic qualifications and work experience of the NSD personnel, recruiting and training, the conduct of the regulatory review during the licensing process and working procedures, the manpower and coverage of the different technical areas, the principal problems and conclusions. (author)

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)

Will nuclear power plant standardization reduce the licensing impact on construction

International Nuclear Information System (INIS)

Allen, J.M.; Bingham, W.G.; Keith, D.G.

1976-01-01

The NRC and the nuclear industry have been pursuing standardization quite vigorously in an effort to reduce the cost and schedule for the design and construction of nuclear power plants. The NRC is currently reviewing standard plant applications submitted under each of four standardization options. In addition, the NRC has published Standard Review Plans and Standard Technical Specifications. Although problems exist in the implementation of standardization and in areas unaffected by standardization, each of these standardization methods has the potential to reduce the licensing impact on construction

Magnox Electric plc's strategy for decommissioning its nuclear licensed sites

International Nuclear Information System (INIS)

2002-02-01

The 1995 White Paper 'Review of Radioactive Waste Management Policy: Final Conclusions', Cm 2919, determined that the Government would ask all nuclear operators to draw up strategies for the decommissioning of their redundant plant and that the Health and Safety Executive (HSE) would review these strategies on a quinquennial basis in consultation with the environment agencies. This review has considered Magnox Electric pie (Magnox Electric) arrangements for the identification of its responsibilities for decommissioning and radioactive waste management, the quantification of the work entailed, the standards and timing of the work, and the arrangements to provide the financial resources to undertake the work. This is the second review by the HSE in response to Cm 2919 of Magnox Electric's nuclear power station decommissioning and radioactive waste management strategies and is based on the situation in April 2000. It reports the Nuclear Installations Inspectorate's (NIl) view that the strategies proposed by Magnox Electric are appropriate. The strategies are considered to be largely consistent with both national and international policy statements and guidance, and are potentially flexible enough to be able to accommodate lessons learned during ongoing decommissioning activities. During the review the Nil has considered whether Magnox Electric has identified all the tasks required to fully decommission its sites. Generally this has been found to be the case. Some additional tasks have been identified due, in part, to the reviewers' noting the changes which have recently taken place in environmental expectations. At this time, on the basis of the information presented, and with the provisos stated below, Magnox Electric's provisioning for final dismantling after 85 years is considered to be reasonable. The Nil expects Magnox Electric to further justify why a shorter timescale is not reasonably practicable before the next review. One of the purposes of this review

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)

Spent Nuclear Fuel Project path forward: nuclear safety equivalency to comparable NRC-licensed facilities

International Nuclear Information System (INIS)

Garvin, L.J.

1995-11-01

This document includes the Technical requirements which meet the nuclear safety objectives of the NRC regulations for fuel treatment and storage facilities. These include requirements regarding radiation exposure limits, safety analysis, design and construction. This document also includes administrative requirements which meet the objectives of the major elements of the NRC licensing process. These include formally documented design and safety analysis, independent technical review, and oppportunity for public involvement

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

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)

Siting of light-water reactor power plants in the Federal Republic of Germany

International Nuclear Information System (INIS)

Kohler, H.A.G.

1975-01-01

The nuclear power plant site requirements formulated for environment protection in Germany allow nuclear power plants to be built at any site provided these requirements are duly taken into account in preparing and monitoring the site and in the design of the proposed power plant. After a brief discussion of light water reactor power plant sites, prevailing practice in site planning, site selection criteria, licensing procedure and used criteria, rules and guidelines, this paper reports on some considerations taken into account by the expert advisers and by the licensing authorities and future site planning. (orig.) [de

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

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)

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

Nuclear Safety Design Base for License Application

International Nuclear Information System (INIS)

R.J. Garrett

2005-01-01

The purpose of this report is to identify and document the nuclear safety design requirements that are specific to structures, systems, and components (SSCs) of the repository that are important to safety (ITS) during the preclosure period and to support the preclosure safety analysis and the license application for the high-level radioactive waste (HLW) repository at Yucca Mountain, Nevada. The scope of this report includes the assignment of nuclear safety design requirements to SSCs that are ITS and does not include the assignment of design requirements to SSCs or natural or engineered barriers that are important to waste isolation (ITWI). These requirements are used as input for the design of the SSCs that are ITS such that the preclosure performance objectives of 10 CFR 63.111(b) [DIRS 173273] are met. The natural or engineered barriers that are important to meeting the postclosure performance objectives of 10 CFR 63.113(b) and (c) [DIRS 173273] are identified as ITWI. Although a structure, system, or component (SSC) that is ITS may also be ITWI, this report is only concerned with providing the nuclear safety requirements for SSCs that are ITS to prevent or mitigate event sequences during the repository preclosure period

Summary and analysis of public comments on NUREG-1317: Regulatory options for nuclear plant license renewal: Final report

International Nuclear Information System (INIS)

Ligon, D.M.; Seth, S.S.

1989-03-01

On August 29, 1988, the US Nuclear Regulatory Commission (NRC) issued an Advance Notice of Proposed Rulemaking on nuclear plant license renewal and solicited public comments on NUREG-1317, ''Regulatory Options for Nuclear Plant License Renewal.'' NUREG-1317 presents a discussion of fifteen topics involving technical, environmental, and procedural issues and poses a set of related questions. As part of its ongoing task for the NRC, The MITRE Corporation has summarized and analyzed the public comments received. Fifty-three written comments were received. Of these, 83 percent were from nuclear industry representatives; the remaining comments represented federal and state agencies, public interest groups, and a private citizen

10 CFR 72.96 - Siting limitations.

Science.gov (United States)

2010-01-01

... REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL... site within which there is a candidate site for a HLW repository. This limitation shall apply until such time as DOE decides that such candidate site is no longer a candidate site under consideration for...

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

Liability for on-site nuclear property damage

International Nuclear Information System (INIS)

Neems, H.J.

2000-01-01

Typically, liability for on-site property addressed in contracts between operator and its suppliers. Nuclear power plant operators ordinarily protect themselves against risk of nuclear damage to on-site property by insurance. Nuclear liability laws do not specifically address liability for nuclear damage to on-site property. Nuclear plant owners should address risk of damage to on-site property when developing risk management program

76 FR 81992 - PPL Bell Bend, LLC; Combined License Application for Bell Bend Nuclear Power Plant; Exemption

Science.gov (United States)

2011-12-29

... License Application for Bell Bend Nuclear Power Plant; Exemption 1.0 Background PPL Bell Bend, LLC... for Nuclear Power Plants.'' This reactor is to be identified as Bell Bend Nuclear Power Plant (BBNPP... based upon the U.S. EPR reference COL (RCOL) application for UniStar's Calvert Cliffs Nuclear Power...

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

Decree-Law no. 49398 of 24 November 1969 - Establishment of a licensing system for nuclear activities of an industrial nature

International Nuclear Information System (INIS)

1969-01-01

This decree-Law lists the nuclear activities subject to licensing in Portugal. These include: research involving use of nuclear laboratories, pilot and industrial facilities; prospecting for and exploration of radioactive ore deposits, including the production of concentrates; import and export of radioactive materials and nuclear fuels, including fabrication of the latter; nuclear reactors and power plants; trade in irradiated fuels and recycling of recovered fuels. The Decree-Law lays down that the licensing procedure for such activities will be fixed by decree. (NEA) [fr

Regulatory challenges related to the licensing of a new nuclear power plant

International Nuclear Information System (INIS)

Maris, M.

2010-01-01

Assuring the safety and security of nuclear power plants is recognized world-wide as a challenge for all stakeholders. Particular attention goes to plants planned to be built in countries with not sufficiently developed industrial and regulatory infrastructure and experience. A construction and commissioning project, which is usually an international undertaking, gives opportunities to all national stakeholders to develop further their organisations and competences. In the present paper the duties of a regulatory body are recalled as well as the human resources and competences needed for the licensing of a new nuclear power plant. The regulatory body and its technical safety organization(s) should be strengthened and the international cooperation should contribute to this in a systematic and coordinated way. In particular, the donor country should support the necessary development of the regulatory competences and of an effective safety assessment process supporting the national licensing process. Appropriate support can be provided by the International Atomic Energy Agency (IAEA) and through other bi-lateral or multi-lateral programmes

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

Prediction of ground motion from underground nuclear weapons tests as it relates to siting of a nuclear waste storage facility at NTS and compatibility with the weapons test program

International Nuclear Information System (INIS)

Vortman, L.J. IV.

1980-04-01

This report assumes reasonable criteria for NRC licensing of a nuclear waste storage facility at the Nevada Test Site where it would be exposed to ground motion from underground nuclear weapons tests. Prediction equations and their standard deviations have been determined from measurements on a number of nuclear weapons tests. The effect of various independent parameters on standard deviation is discussed. That the data sample is sufficiently large is shown by the fact that additional data have little effect on the standard deviation. It is also shown that coupling effects can be separated out of the other contributions to the standard deviation. An example, based on certain licensing assumptions, shows that it should be possible to have a nuclear waste storage facility in the vicinity of Timber Mountain which would be compatible with a 700 kt weapons test in the Buckboard Area if the facility were designed to withstand a peak vector acceleration of 0.75 g. The prediction equation is a log-log linear equation which predicts acceleration as a function of yield of an explosion and the distance from it

Safety of nuclear installations in Slovakia

International Nuclear Information System (INIS)

1998-01-01

In this part next aspects are described: (1) Site selection (Legislation related to site selection; Meeting criteria at Bohunice and Mochovce sites; International agreements); (2) Design preparation and construction (Designing and construction-relevant legislation; Nuclear installation project preparation of nuclear installation at Mochovce site); (3) Operation (Operator licensing procedure; Operation limits and conditions; Maintenance testing and control documentation for management and operation; Technical support of operation; Analysis of events at nuclear installations and Radioactive waste production); (4) Planned safety upgrading activities at nuclear installations

NRC's license renewal regulations

International Nuclear Information System (INIS)

Akstulewicz, Francis

1991-01-01

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

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

Nuclear knowledge portal to support licensing and control nuclear activities in the Brazilian Nuclear Energy Commission

International Nuclear Information System (INIS)

Gomes, Elizabeth; Braga, Fabiane

2004-01-01

importance of keeping the intellectual capital in the organizations that is to work with the knowledge from the collaborators. In Brazil still have many authors that discusses this concept and we adopt for this paper the definition form Cavalcanti where is the concept 'intellectual capital' refers either to the capacity, ability or experience, as well as to the formal education that the collaborators members have and add to the Organization. The 'intellectual capital' is an intangible asset, which belongs to the individual himself, thus it might be utilized by the organizations in order to generate value. The development and preservation of this intellectual capital is made through the implementation of forums of discussion, workshops or knowledge portals where the organization's collaborators share their experiences. Nevertheless, to assimilate and to develop the 'intellectual capital' does not add value to the organization: It is necessary to keep it. And one way to do so is to create desirable and encouraging work environments, to promote a sharing management and to offer programs of profits sharing. The objective of this paper is to describe how Brazilian Nuclear Energy Commission - CNEN has been developing a nuclear knowledge portal, focused in the Radiation and Safety Nuclear area. The Brazilian Nuclear Energy Commission (CNEN) is a federal autarchy created in October 10 of 1956, as a superior agency of planning, guiding, supervision and inspection in nuclear area being also the body entitled to establish standards and regulations on radiological protection, to issue licenses (permissions) and to survey and control the nuclear activities in Brazil. CNEN also develops researches related to the use of nuclear techniques in benefit of the society. The Radiation and Safety Nuclear directorate of CNEN acts, mainly, in the licensing of nuclear and radioactive installations. The people who work at this area recognize the importance of management and sharing the accumulated

Sites in the United States contaminated with radioactivity

International Nuclear Information System (INIS)

Wolbarst, A.B.; Blom, P.F.; Chan, D.

1999-01-01

Over the century that radioactive materials have been mined, processed, produced, and utilized, many sites across the US have become contaminated. Such sites include bases and installations of the Department of Defense, weapons production and research facilities of the Department of Energy, properties under the authority of other Federal agencies, privately-owned and governmental facilities that are licensed by the Nuclear Regulatory Commission and its Agreement States, and sites licensed by or the responsibility of states. This review reports on aspects of work by the Environmental Protection Agency, the Department of Defense, the Department of Energy, the Nuclear Regulatory Commission, and others to identify sites contaminated with radioactive materials. It also describes the principal programs that have been instituted to deal with them

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

76 FR 11522 - In the Matter of Progress Energy Florida, Inc. (Combined License Application, Levy County Nuclear...

Science.gov (United States)

2011-03-02

... NUCLEAR REGULATORY COMMISSION [Docket Nos. 52-029-COL, 52-030-COL] In the Matter of Progress Energy Florida, Inc. (Combined License Application, Levy County Nuclear Power Plant, Units 1 and 2... by the Nuclear Regulatory Commission staff in this case. Mr. Dehmel has not previously performed any...

75 FR 62153 - Notice of the Nuclear Regulatory Commission Issuance of Materials License SUA-1596 for Uranium...

Science.gov (United States)

2010-10-07

... Commission Issuance of Materials License SUA-1596 for Uranium One Americas, Inc. Moore Ranch In Situ Recovery.... SUPPLEMENTARY INFORMATION: The Nuclear Regulatory Commission (NRC) has issued a license to Uranium One Americas, Inc. (Uranium One) for its Moore Ranch uranium in situ recovery (ISR) facility in Campbell County...

Site-Specific Atmospheric Dispersion Characteristics of Korean Nuclear Power Plant Sites

International Nuclear Information System (INIS)

Han, M. H.; Kim, E. H.; Suh, K. S.; Hwang, W. T.; Choi, Y. G.

2001-01-01

Site-specific atmospheric dispersion characteristics have been analyzed. The northwest and the southwest wind prevail on nuclear sites of Korea. The annual isobaric surface averaged for twenty years around Korean peninsula shows that west wind prevails. The prevailing west wind is profitable in the viewpoint of radiation protection because three of four nuclear sites are located in the east side. Large scale field tracer experiments over nuclear sites have been conducted for the purpose of analyzing the atmospheric dispersion characteristics and validating a real-time atmospheric dispersion and dose assessment system FADAS. To analyze the site-specific atmospheric dispersion characteristics is essential for making effective countermeasures against a nuclear emergency

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

Siemens Nuclear Power Corporation methods development for BWR/PWR reactor licensing

International Nuclear Information System (INIS)

Pruitt, D.W.

1992-01-01

This presentation addresses the Siemens Nuclear Power Corporation (SNP) perspective on the primary forces driving methods development in the nuclear industry. These forces are fuel design, computational environment and industry requirement evolution. The first segment of the discussion presents the SNP experience base. SNP develops, manufactures and licenses both BWR and PWR reload fuel. A review of this experience base highlights the accelerating rate at which new fuel designs are being introduced into the nuclear industry. The application of advanced BWR lattice geometries provides an example of fuel design trends. The second aspect of the presentation is the rapid evolution of the computing environment. The final subject in the presentation is the impact of industry requirements on code or methods development

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

Energy Technology Data Exchange (ETDEWEB)

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

2012-07-01

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

Assessment of national systems for obtaining local acceptance of nuclear waste management siting activities

International Nuclear Information System (INIS)

Paige, H.W.; Owens, J.E.

1984-01-01

On behalf of the United States Department of Energy (DOE), International Energy Associates Limited (IEAL) of Washington, D.C. has conducted surveys and analyses of fourteen countries' plans and approaches for dealing with the problems of obtaining local siting acceptance for nuclear waste management facilities. It was determined that the following elements of the formal systems generally facilitate and/or expedite waste management siting decisions: (1) a clear-cut pro-nuclear power position on the part of the government; (2) a willingness on the part of the central government to exert (with prudence and restraint) its pre-emptive rights in nuclear matters; (3) political structures in which the heads of regional or provincial governments are appointed by the central government; (4) national laws that link reactor licensing with a detailed plan for waste management; (5) an established and stable policy with regard to reprocessing. In contrast, it was determined that the following elements of the formal system generally hinder waste management siting activities: (1) historically strong local land used veto laws; (2) the use of national referenda for making nuclear decisions; (3) requirements for public hearings. The informal approaches fall into the following five categories: (1) political: e.g. assertion of will by political leaders, activities to enlist support of local politicians, activities to broaden involvement in decision-making; (2) economic: e.g. emphasis on normal benefits, provision for additional economic benefits; (3) siting: e.g. at or near existing nuclear facilities, on government or utility property, at multiple locations to spread the political burden; (4) timing: e.g. decoupling drilling activities from ultimate repository site decision, deliberate deferral to (long-range) future; (5) education: e.g. creation of special government programmes, enlisting of media support

NRC licensing requirements: DOD options

International Nuclear Information System (INIS)

Pike, W.J.; O'Reilly, P.D.

1982-09-01

This report describes the licensing process (both safety and environmental) that would apply if the Department of Defense (DOD) chooses to obtain licenses from the US Nuclear Regulatory Commission (NRC) for using nuclear energy for power and luminous sources. The specific nuclear energy sources being considered include: small or medium-size nuclear power reactors; radioisotopic thermoelectric generators with 90 Sr or 238 Pu; radioisotopic dynamic electric generators with 90 Sr or 238 Pu; and applications of radioisotopes for luminous sources (lights) with 3 H, 85 Kr, or 147 Pm. The steps of the licensing process are summarized in the following sections, with particular attention given to the schedule and level of effort necessary to support the process

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

Legal issues, authoritative licenses and tasks in relation with nuclear safety in Hungary

International Nuclear Information System (INIS)

Oerdoegh, J.; Voeroess, L.

1998-01-01

After a brief historical overview of nuclear authorities in Hungary, the role and functions of the National Atomic Energy Office are presented. It is the primary authority in this country on nuclear safety, with tasks and functions of licensing, inspection and enforcing safety measures. The organizational structure of NAEO and its position as a Governmental body is shown. Other tasks include the promotion of R and D coordination and international cooperation. (R.P.)

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

Science.gov (United States)

Purdy, Bruce J.; And Others

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

Preliminary Evaluation of Removing Used Nuclear Fuel from Shutdown Sites

Energy Technology Data Exchange (ETDEWEB)

Maheras, Steven J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Best, Ralph E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Ross, Steven B. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Buxton, Kenneth A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); England, Jeffery L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); McConnell, Paul E. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Massaro, Lawrence M. [Federal Railroad Administration (FRA) (United States); Jensen, Philip J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

2014-10-01

This report presents a preliminary evaluation of removing used nuclear fuel (UNF) from 12 shutdown nuclear power plant sites. At these shutdown sites the nuclear power reactors have been permanently shut down and the sites have been decommissioned or are undergoing decommissioning. The shutdown sites are Maine Yankee, Yankee Rowe, Connecticut Yankee, Humboldt Bay, Big Rock Point, Rancho Seco, Trojan, La Crosse, Zion, Crystal River, Kewaunee, and San Onofre. The evaluation was divided into four components: characterization of the UNF and greater-than-Class C low-level radioactive waste (GTCC waste) inventory; a description of the on-site infrastructure and conditions relevant to transportation of UNF and GTCC waste; an evaluation of the near-site transportation infrastructure and experience relevant to shipping transportation casks containing UNF and GTCC waste, including identification of gaps in information; and, an evaluation of the actions necessary to prepare for and remove UNF and GTCC waste. The primary sources for the inventory of UNF and GTCC waste are the U.S. Department of Energy (DOE) RW-859 used nuclear fuel inventory database, industry sources such as StoreFUEL and SpentFUEL, and government sources such as the U.S. Nuclear Regulatory Commission. The primary sources for information on the conditions of site and near-site transportation infrastructure and experience included observations and information collected during visits to the Maine Yankee, Yankee Rowe, Connecticut Yankee, Humboldt Bay, Big Rock Point, Rancho Seco, Trojan, La Crosse, and Zion sites; information provided by managers at the shutdown sites; Facility Interface Data Sheets compiled for DOE in 2005; Services Planning Documents prepared for DOE in 1993 and 1994; industry publications such as Radwaste Solutions; and Google Earth. State and Regional Group representatives, a Tribal representative, and a Federal Railroad Administration representative participated in six of the shutdown site

Impact of offshore nuclear generating stations on recreational behavior at adjacent coastal sites

International Nuclear Information System (INIS)

Baker, E.J.; West, S.G.; Moss, D.J.; Weyant, J.K.

1977-10-01

A multi-faceted investigation was undertaken to project the impact of offshore nuclear power plants on beach visitation at adjacent beaches. Related literature was reviewed concerning human adjustment to natural hazards, risk-taking behavior, and public attitudes toward nuclear power. Approximately 2400 people were interviewed at beaches in three states with respect to: intended avoidance of beaches near a hypothetical floating nuclear plant (FNP), relative importance of proximity to a FNP, when compared to other beach attributes, onshore-offshore preference for coastal nuclear plant location, behavioral impact of NRC licensing of FNPs, relative tourism impact of coastal nuclear plant compared to coastal coal-fired plant, public concerns about nuclear safety, public attitudes toward alternative energy sources, public confidence in sources of information about nuclear power, visual impact of a FNP, and knowledge about nuclear power. Four beach areas near currently operating coastal nuclear power plants were studied to assess impacts on tourism resulting from plant construction. Data suggest that proximity of a FNP is less important than other beach attributes in determining beach attractiveness, probably no more than (and perhaps less than) 5% to 10% of current beach patrons would avoid a beach after FNP siting three miles directly offshore, and impact of a FNP would decrease exponentially as distance away increased

Nuclear knowledge portal for supporting licensing and controlling nuclear activities in the Brazilian Nuclear Energy Commission

International Nuclear Information System (INIS)

Gomes, E.; Braga, F.

2005-01-01

The knowledge economy is pivotal for moving the wealth and development of traditional industrial sectors - abundant in manual labour, raw materials and capital - to areas whose products, processes and services are rich in technology and knowledge. Even in research areas such as nuclear energy, where goods are based on high technology, the ability to transform information into knowledge, and knowledge into decisions and actions, is extremely important. Therefore, the value of products from these areas depends more and more on the degree of innovation, technology and intelligence incorporated by them. Thus, it has become increasingly important and relevant to acquire strategic knowledge and make it available to the organisation. Therefore, the objective of this paper is to present the construction of a Nuclear Knowledge Portal for aiding and streamlining the Licensing and Management activities of the CNEN. (author)

Nuclear knowledge portal to support licensing and control nuclear activities in the Brazilian Nuclear Energy Commission

International Nuclear Information System (INIS)

Gomes, M.E.; Braga, M.F.

2004-01-01

The Knowledge Economy is pivotal for moving the wealth and development of traditional industrial sectors - abundant in manual labor, raw materials and capital - to areas whose products, processes and services are rich in technology and knowledge. Even in research areas such as nuclear energy, where goods are based on high technology, the ability to transform information into knowledge, and knowledge into decisions and actions, is extremely important. Therefore, the value of products from these areas depends more and more on the degree of innovation, technology and intelligence incorporated by them. Thus, it has become increasingly important and relevant to acquire strategic knowledge and make it available to the organization. Therefore, the objective of this article is to present the construction of a Nuclear Knowledge Portal for aiding and streamlining the Licensing and Management activities of the CNEN. (author)

Continental margin neotectonics in South Africa: a nuclear siting approach

International Nuclear Information System (INIS)

Andreoli, M.A.G.; Hambleton-Jones, B.B.; Anderson, N.J.B.; Faurie, J.N.; Raubenheimer, E.; Antoine, L.; Von Veh, M.W.; McMillan, I.K.

1990-01-01

Neotectonic activity in South Africa has only recently received attention despite the fact that a rigorous knowledge of this phenomenon could have a major impact on industrial development within certain areas. Since the early 1980s the Atomic Energy Corporation of South Africa has addressed this specific problem in the process of detailed site investigations for the licensing of six facilities related to the nuclear industry. The data indicates that there is a general correspondence in five selected areas along the South African coast between the development of Quarternary joints/faults and the degree of seismic activity recorded in each geological domain. Finally, the results provide new data that may add to a recent survey of global tectonic stresses. 13 refs., 1 fig

A Strategy for Describing the Biosphere at Candidate Sites for Repositories of Nuclear Waste: Linking Ecosystem and Landscape Modeling

International Nuclear Information System (INIS)

Lindborg, Tobias; Loefgren, Anders; Soederbaeck, Bjoern; Kautsky, Ulrik; Lindborg, Regina; Bradshaw, Clare

2006-01-01

To provide information necessary for a license application for a deep repository for spent nuclear fuel, the Swedish Nuclear Fuel and Waste Management Co. has started site investigations at two sites in Sweden. In this paper, we present a strategy to integrate site-specific ecosystem data into spatially explicit models needed for safety assessment studies and the environmental impact assessment. The site-specific description of ecosystems is developed by building discipline-specific models from primary data and by identifying interactions and stocks and flows of matter among functional units at the sites. The conceptual model is a helpful initial tool for defining properties needed to quantify system processes, which may reveal new interfaces between disciplines, providing a variety of new opportunities to enhance the understanding of the linkages between ecosystem characteristics and the functional properties of landscapes. This type of integrated ecosystem-landscape characterization model has an important role in forming the implementation of a safety assessment for a deep repository

Early Site Permit Demonstration Program: Recommendations for communication activities and public participation in the Early Site Permit Demonstration Program

International Nuclear Information System (INIS)

1993-01-01

On October 24, 1992, President Bush signed into law the National Energy Policy Act of 1992. The bill is a sweeping, comprehensive overhaul of the Nation's energy laws, the first in more than a decade. Among other provisions, the National Energy Policy Act reforms the licensing process for new nuclear power plants by adopting a new approach developed by the US Nuclear Regulatory Commission (NRC) in 1989, and upheld in court in 1992. The NRC 10 CFR Part 52 rule is a three-step process that guarantees public participation at each step. The steps are: early site permit approval; standard design certifications; and, combined construction/operating licenses for nuclear power reactors. Licensing reform increases an organization's ability to respond to future baseload electricity generation needs with less financial risk for ratepayers and the organization. Costly delays can be avoided because design, safety and siting issues will be resolved before a company starts to build a plant. Specifically, early site permit approval allows for site suitability and acceptability issues to be addressed prior to an organization's commitment to build a plant. Responsibility for site-specific activities, including communications and public participation, rests with those organizations selected to try out early site approval. This plan has been prepared to assist those companies (referred to as sponsoring organizations) in planning their communications and public involvement programs. It provides research findings, information and recommendations to be used by organizations as a resource and starting point in developing their own plans

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

International Nuclear Information System (INIS)

1991-07-01

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

Probabilistic safety analysis : a new nuclear power plants licensing method

International Nuclear Information System (INIS)

Oliveira, L.F.S. de.

1982-04-01

After a brief retrospect of the application of Probabilistic Safety Analysis in the nuclear field, the basic differences between the deterministic licensing method, currently in use, and the probabilistic method are explained. Next, the two main proposals (by the AIF and the ACRS) concerning the establishment of the so-called quantitative safety goals (or simply 'safety goals') are separately presented and afterwards compared in their most fundamental aspects. Finally, some recent applications and future possibilities are discussed. (Author) [pt

Licensing and regulatory control of nuclear power plants in the Federal Republic of Germany

International Nuclear Information System (INIS)

Obenhaus, W.

1976-01-01

The paper deals with the legal background, the role of the 'Bund' (Federation) and the 'Laender' (States) in the field of atomic energy and radiation protection law and the licensing procedure for nuclear power plants. (RW) [de

Environmental Impact Appraisal for renewal of special nuclear material license No. SNM-42 (Docket No. 70-27)

International Nuclear Information System (INIS)

1984-03-01

The Babcock and Wilcox Company (B and W) Naval Nuclear Fuel Division (NNFD) facility near Lynchburg, Virginia, produces fuel assemblies and complete fuel modules for reactors used in the US Navy nuclear propulsion program and fuel components for university and other research reactors; and processes scrap material to recover the enriched uranium content. No significant modifications of the production procedures for the US Navy nuclear fuel fabrication have been made since the previous environmental assessment, and none are anticipated during the five-year license renewal period being considered. In 1982 the fabrication of fuel assemblies for university and other research reactors was begun. This environmental assessment provides a review of the past five years of operation and an analysis of future impacts, including the effect of plant changes. The proposed action is the renewal of the license necessary for B and W to continue the existing fuel fabrication operations. Principal operations in the fabrication facility include the processing of highly enriched uranium (> 90% 235 U) into fuel elements and assembling the elements into complete reactor cores for shipment and eventual installation in US Navy facilities. The principal environmental impacts of current operation of the NNFD result from release of radioactive gases to the atmosphere and of radioactively contaminated liquids to the adjacent James River. The actual gaseous and liquid pollutants released during normal operation of the plant have been monitored and documented. The principal subjects addressed in this environmental assessment include water use, pollutant controls, environmental monitoring, and environmental impact of operation and accidents. Other site factors and plant operations necessary for this assessment are described, and aspects of insignificant impacts are identified. 10 figures, 36 tables

Accident consequence analysis models applied to licensing process of nuclear installations, radioactive and conventional industries

International Nuclear Information System (INIS)

Senne Junior, Murillo; Vasconcelos, Vanderley de; Jordao, Elizabete

2002-01-01

The industrial accidents happened in the last years, particularly in the eighty's decade, had contributed in a significant way to call the attention to government authorities, industry and society as a whole, demanding mechanisms for preventing episodes that could affect people's safety and environment quality. Techniques and methods already thoroughly used in the nuclear, aeronautic and war industries were then adapted for performing analysis and evaluation of the risks associated to other industrial activities, especially in the petroleum, chemistry and petrochemical areas. Some models for analyzing the consequences of accidents involving fire and explosion, used in the licensing processes of nuclear and radioactive facilities, are presented in this paper. These models have also application in the licensing of conventional industrial facilities. (author)

Superfund Record of Decision (EPA Region 4): Maxey Flats Nuclear Disposal site, Fleming County, KY. (First remedial action), September 1991. Final report

International Nuclear Information System (INIS)

1991-01-01

The 280-acre Maxey Flats Nuclear Disposal site is an inactive low-level radioactive waste disposal facility in Fleming County, Kentucky. The estimated 663 people who reside within 2.5 miles of the site use the public water supply for drinking purposes. From 1962 to 1977, Nuclear Engineering Company, Inc. (NECO), operated a solid by-product, source, and special nuclear material disposal facility under a license with the State. Several State investigations in the 1970's revealed that leachate contaminated with tritium and other radioactive substances was migrating from the disposal trenches to unrestricted areas. The Record of Decision (ROD) addresses final remediation of soil, debris, and associated leachate. The primary contaminants of concern affecting the soil and debris are VOCs including benzene, TCE, and toluene; metals including arsenic and lead; and radioactive materials. The selected remedial action for the site is included

Geotechnical aspects of site evaluation and foundations for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2003-01-01

This publication is a revision of the former safety standards of IAEA Safety Series No. 50-SG-S8. The scope has been extended to cover not only foundations but also design questions related to geotechnical science and engineering, such as the bearing capacity of foundations, design of earth structures and design of buried structures. Seismic aspects also play an important role in this field, and consequently the Safety Guide on Evaluation of Seismic Hazards for Nuclear Power Plants, Safety Standards Series No. NS-G-3.3, which discusses the determination of seismic input motion, is referenced on several occasions. The present Safety Guide provides an interpretation of the Safety Requirements on Site Evaluation for Nuclear Installations and guidance on how to implement them. It is intended for the use of safety assessors or regulators involved in the licensing process as well as the designers of nuclear power plants, and it provides them with guidance on the methods and procedures for analyses to support the assessment of the geotechnical aspects of the safety of nuclear power plants

Geotechnical aspects of site evaluation and foundations for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2006-01-01

This publication is a revision of the former safety standards of IAEA Safety Series No. 50-SG-S8. The scope has been extended to cover not only foundations but also design questions related to geotechnical science and engineering, such as the bearing capacity of foundations, design of earth structures and design of buried structures Seismic aspects also play an important role in this field, and consequently the Safety Guide on Evaluation of Seismic Hazards for Nuclear Power Plants, Safety Standards Series No. NS-G-3.3, which discusses the determination of seismic input motion, is referenced on several occasions. The present Safety Guide provides an interpretation of the Safety Requirements on Site Evaluation for Nuclear Installations and guidance on how to implement them. It is intended for the use of safety assessors or regulators involved in the licensing process as well as the designers of nuclear power plants, and it provides them with guidance on the methods and procedures for analyses to support the assessment of the geotechnical aspects of the safety of nuclear power plants

A materials engineering view of license renewal at the US Nuclear Regulatory Commission

International Nuclear Information System (INIS)

Banic, M.

1999-01-01

This paper discusses the treatment of license renewal at the US Nuclear Regulatory Commission (NRC) with emphasis on the review process by the staff of the Materials and Chemical Engineering Branch (EMCB). The paper covers the rules governing license renewal, the applications received, the schedule, the approach, and the technical issues. The NRC has a tight schedule of 30-36 months to renew a license. To date, Baltimore Gas and Electric (BG and E) and Duke Power have applied for license renewal. Expecting more applicants, the staff has taken steps to address the public's concern that the effects of aging will be adequately managed and the industry's concern that the reviews will be timely, efficient, and uniform. These steps include identifying aging effects and making the results available in a report and computerized database, approving topical reports and aging management programs for generic use, and reviewing aging management programs according to specific criteria. Materials Engineering staff have a major role because many of the aging issues are materials related. (author)

Technology of geographical information systems applied to the licensing of nuclear sector installations

International Nuclear Information System (INIS)

Oliveira, Aline F.G. De; Barreto, Alberto A.; Carvalho Filho, Carlos A. de; Rodrigues, Paulo Cezar Horta; Moura, Igor Felipe Silva

2017-01-01

The nuclear licensing process involves the preparation of documents such as Local's Report (LR), Preliminary Safety Analysis Report (PSAR), Final Safety Analysis Report (FSAR), Physical Protection Plans, Radiation Protection Plans and Emergency plans that must be submit to the National Nuclear Energy Commission (DRS / CNEN) for approval. This work presents an analysis and a guide for the use of Geoprocessing tools in the updating of environmental studies necessary to update the Local's Report (LR) of the Center for the Development of Nuclear Technology (CDTN). The main purpose is to contribute to streamline the execution of steps involved in the nuclear licensing process, such as structuring and executing environmental studies, planning environmental monitoring activities, etc. To achieve the objective, we search for and obtained available data of high reliability in various organs using a methodological flowchart for data acquisition and treatment. The study was develop using the ArcMap 10.2 application from ArcGis, especially the Model Builder analytic tool. This tool allowed the (macro) schematization of the methodology from the applied GIS tools, which presents as advantages to the efficiency and optimization of the execution time of the procedures in situations where it is necessary to apply the same routine of tasks, besides the fact of being editable, which offers possibilities for adaptations and improvements. (author)

Technology of geographical information systems applied to the licensing of nuclear sector installations

Energy Technology Data Exchange (ETDEWEB)

Oliveira, Aline F.G. De; Barreto, Alberto A.; Carvalho Filho, Carlos A. de; Rodrigues, Paulo Cezar Horta [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil); Moura, Igor Felipe Silva, E-mail: afgo@cdtn.br, E-mail: aab@cdtn.br, E-mail: cacf@cdtn.br, E-mail: igorfelipedx@ufmg.br [Universidade Federal de Minas Gerais (UFMG), Belo Horizonte, MG (Brazil)

2017-07-01

The nuclear licensing process involves the preparation of documents such as Local's Report (LR), Preliminary Safety Analysis Report (PSAR), Final Safety Analysis Report (FSAR), Physical Protection Plans, Radiation Protection Plans and Emergency plans that must be submit to the National Nuclear Energy Commission (DRS / CNEN) for approval. This work presents an analysis and a guide for the use of Geoprocessing tools in the updating of environmental studies necessary to update the Local's Report (LR) of the Center for the Development of Nuclear Technology (CDTN). The main purpose is to contribute to streamline the execution of steps involved in the nuclear licensing process, such as structuring and executing environmental studies, planning environmental monitoring activities, etc. To achieve the objective, we search for and obtained available data of high reliability in various organs using a methodological flowchart for data acquisition and treatment. The study was develop using the ArcMap 10.2 application from ArcGis, especially the Model Builder analytic tool. This tool allowed the (macro) schematization of the methodology from the applied GIS tools, which presents as advantages to the efficiency and optimization of the execution time of the procedures in situations where it is necessary to apply the same routine of tasks, besides the fact of being editable, which offers possibilities for adaptations and improvements. (author)

Analyses of operating license renewal for nuclear power plants in USA

International Nuclear Information System (INIS)

Chiba, Goro

2007-01-01

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

Improved best estimate plus uncertainty methodology, including advanced validation concepts, to license evolving nuclear reactors

International Nuclear Information System (INIS)

Unal, C.; Williams, B.; Hemez, F.; Atamturktur, S.H.; McClure, P.

2011-01-01

Research highlights: → The best estimate plus uncertainty methodology (BEPU) is one option in the licensing of nuclear reactors. → The challenges for extending the BEPU method for fuel qualification for an advanced reactor fuel are primarily driven by schedule, the need for data, and the sufficiency of the data. → In this paper we develop an extended BEPU methodology that can potentially be used to address these new challenges in the design and licensing of advanced nuclear reactors. → The main components of the proposed methodology are verification, validation, calibration, and uncertainty quantification. → The methodology includes a formalism to quantify an adequate level of validation (predictive maturity) with respect to existing data, so that required new testing can be minimized, saving cost by demonstrating that further testing will not enhance the quality of the predictive tools. - Abstract: Many evolving nuclear energy technologies use advanced predictive multiscale, multiphysics modeling and simulation (M and S) capabilities to reduce the cost and schedule of design and licensing. Historically, the role of experiments has been as a primary tool for the design and understanding of nuclear system behavior, while M and S played the subordinate role of supporting experiments. In the new era of multiscale, multiphysics computational-based technology development, this role has been reversed. The experiments will still be needed, but they will be performed at different scales to calibrate and validate the models leading to predictive simulations for design and licensing. Minimizing the required number of validation experiments produces cost and time savings. The use of multiscale, multiphysics models introduces challenges in validating these predictive tools - traditional methodologies will have to be modified to address these challenges. This paper gives the basic aspects of a methodology that can potentially be used to address these new challenges in

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

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

Geology and geotechnic in the implantation of nuclear power plants

International Nuclear Information System (INIS)

Alves, P.R.R.

1984-01-01

It is presented a general methodology for geological and geotechnical investigations to be performed in sites selected for the construction of nucldar power plants. Items dealing with the standards applied to licensing of a nuclear power plants, the selection process of sites and identification of geological and geotechnical parameters needed for the regional and local characterization of the area being studied, were incorporated. It is also provided an aid to the writing of technical reports, which are part of the documentation an owner of a nuclear power plant needs to submit to the Comissao Nacional de Energia Nuclear, to fulfill the nuclear installation licensing requirements. (Author) [pt

Anti-nuclear activities and critics concerning nuclear power plant sites

International Nuclear Information System (INIS)

Rhee, We-Beg

2000-01-01

Korea has dynamic nuclear power expansion programs, operating 16 nuclear units producing 13710 MW in total located on 4 different sites. Last year, nuclear power supplied over 40 % of national total electricity demands. In 1998, Korean government initiated re-designation work investigating circumstance changes to rule out the unnecessary sites in consideration of a long-term power supply. Korean government has determined to expand the Ulchin site and to designate one point of Woolju county as a new candidate site, and ruled out the rest candidate sites at the end of 1998. About such a governmental measure, the two areas show different reactions. Ulchin where nuclear power plant has been operated safely for about 10 years was likely to accept the governmental determination in spite of some opposition and called for several financial supports for local development. WooIju county, however, showed a strong opposition among local environmental groups and autonomous politicians, and they presented a variety of anti-nuclear activities including demonstrations mainly at the neighbouring metropolis, Ulsan city

Site evaluation for nuclear installations. Safety requirements

International Nuclear Information System (INIS)

2003-01-01

This Safety Requirements publication supersedes the Code on the Safety of Nuclear Power Plants: Siting, which was issued in 1988 as Safety Series No. 50-C-S (Rev. 1). It takes account of developments relating to site evaluations for nuclear installations since the Code on Siting was last revised. These developments include the issuing of the Safety Fundamentals publication on The Safety of Nuclear Installations, and the revision of various safety standards and other publications relating to safety. Requirements for site evaluation are intended to ensure adequate protection of site personnel, the public and the environment from the effects of ionizing radiation arising from nuclear installations. It is recognized that there are steady advances in technology and scientific knowledge, in nuclear safety and in what is considered adequate protection. Safety requirements change with these advances and this publication reflects the present consensus among States. This Safety Requirements publication was prepared under the IAEA programme on safety standards for nuclear installations. It establishes requirements and provides criteria for ensuring safety in site evaluation for nuclear installations. The Safety Guides on site evaluation listed in the references provide recommendations on how to meet the requirements established in this Safety Requirements publication. The objective of this publication is to establish the requirements for the elements of a site evaluation for a nuclear installation so as to characterize fully the site specific conditions pertinent to the safety of a nuclear installation. The purpose is to establish requirements for criteria, to be applied as appropriate to site and site-installation interaction in operational states and accident conditions, including those that could lead to emergency measures for: (a) Defining the extent of information on a proposed site to be presented by the applicant; (b) Evaluating a proposed site to ensure that the site

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

International Nuclear Information System (INIS)

Chiba, Goro

2008-01-01

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

Decisions on sites by Laender parliaments

International Nuclear Information System (INIS)

1977-01-01

The Vereinigung Deutscher Elektrizitaetswerke (VDEW, Association of German Electricity Utilities) proposes two independent steps in the licensing procedure for each nuclear power plant constuction project: one first phase in which to establish site guarantees, and one licensing phase for construction and operation of the power plant. The first phase should henceforth proceed with the active participation of the public involved within the framework of a plans approval procedure. The novel aspect would be the binding clarification in this procedure not only of the nuclear aspects of the case, as formerly, but of all public aspects relating to the site. The construction and operating permits, which would constitute phase two, could then be handled in the usual procedure without any need for urgency. (orig.) [de

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

International Nuclear Information System (INIS)

1976-09-01

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

Capability for intrusion detection at nuclear fuel sites

International Nuclear Information System (INIS)

1978-03-01

A safeguards vulnerability assessment was conducted at three separate licensed nuclear processing facilities. Emphasis was placed on: (1) performance of the total intrusion detection system, and (2) vulnerability of the system to compromise by insiders. The security guards were interviewed to evaluate their effectiveness in executing their duties in accordance with the plant's security plan and to assess their knowledge regarding the operation of the security equipment. A review of the training schedule showed that the guards, along with the other plant employees, are required to periodically attend in-plant training sessions. The vulnerability assessments continued with interviews of the personnel responsible for maintaining the security equipment, with discussions of detector false alarm and maintenance problems. The second part of the vulnerability assessments was to evaluate the effectiveness of the intrusion detection systems including the interior and the perimeter sensors, CCTV surveillance devices and the exterior lighting. Two types of perimeter detectors are used at the sites, a fence disturbance sensor and an infrared barrier type detector. Infrared barrier type detectors have a higher probability of detection, especially in conjunction with dedicated CCTV cameras. The exterior lights satisfy the 0.2 footcandle illumination requirement. The interior intrusion detection systems included ultrasonic motion detectors, microwave motion detectors,balanced magnetic switches, and CCTV cameras. Entrance doors to the materials access areas and vital areas are protected with balanced magnetic switches. The interior intrusion detection systems at the three nuclear processing sites are considered satisfactory with the exception of the areas protected with ultrasonic motion detectors

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

International Nuclear Information System (INIS)

1976-09-01

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

Design/licensing of on-site package for core component

International Nuclear Information System (INIS)

Ogasawara, K.; Chohzuka, T.; Shimura, T.; Kikuchi, T.; Fujiwara, R.; Karigome, S.; Takani, M.

1993-01-01

For storage of used core components which are produced from reactors, Tohoku EPCO decided to construct a site bunker at Onagawa site. It was also decided to develop and fabricate one packaging to transport core components from the reactor buildings to the site bunker. The packaging will be used within the power station; therefore, it shall comply with 'The Law for the Business of Electric Power' and relevant Notification. The main requirements of the packaging are as follows: 1) The number of contents, such as channel boxes and control rods, shall be as large as possible. 2) The weight and the outer dimensions of the packaging shall be within the limitation of the reactor building and the site bunker. 3) Materials shall be selected from those which have been already applied for existing packagings and utilized without any problems. 4) It shall be considered during design of trunnions that handling equipment, such as lifting beam, can be used for not only this packaging but also for existing spent fuel packagings. The design of the packaging is completed and has been licensed. The packaging is scheduled to be utilized from November, 1993. (J.P.N.)

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

Practice and trends in nuclear fuel licensing in France (pressurized water reactor fuels)

International Nuclear Information System (INIS)

Roudier, S.; Badel, D.; Beraha, R.; Champ, M.; Tricot, N.; Tran Dai, P.

1994-01-01

The activities of governmental French authorities responsible for safety of nuclear installations are outlined. The main bodies involved in nuclear safety are: the CSSIN (High Council for Nuclear Safety and Information), CINB (Inter-ministerial Commission for Basic Nuclear Installations) and DSIN (Nuclear Installations Safety Directorate). A brief review of the main fuel licensing issues supported by DSIN is given, which includes: 1) formal regularity procedure ensuring the safety of nuclear installations and especially the pressurized water reactors; 2) guidelines for nuclear design and manufacturing requirements related to safety and 3) safety goals and associated limits. The fuel safety documents for reloading as well as the research and development programmes in the field of technical safety are also described. The ongoing experiments in CABRI reactor, aimed at determining the high burnup fuel behaviour under reactivity initiated accidents until 65 GW d/Mt U, are one of these programs

Practice and trends in nuclear fuel licensing in France (pressurized water reactor fuels)

Energy Technology Data Exchange (ETDEWEB)

Roudier, S [Direction de la Surete des Installations Nucleaires, Fontenay-aux-Roses (France); Badel, D; Beraha, R [Direction Regionale de l` Industrie, de la Recherche et de l` Environnement Rhone-Alpes, Lyon (France); Champ, M; Tricot, N; Tran Dai, P [CEA Centre d` Etudes de Fontenay-aux-Roses, 92 (France). Inst. de Protection et de Surete Nucleaire

1994-12-31

The activities of governmental French authorities responsible for safety of nuclear installations are outlined. The main bodies involved in nuclear safety are: the CSSIN (High Council for Nuclear Safety and Information), CINB (Inter-ministerial Commission for Basic Nuclear Installations) and DSIN (Nuclear Installations Safety Directorate). A brief review of the main fuel licensing issues supported by DSIN is given, which includes: (1) formal regularity procedure ensuring the safety of nuclear installations and especially the pressurized water reactors; (2) guidelines for nuclear design and manufacturing requirements related to safety and (3) safety goals and associated limits. The fuel safety documents for reloading as well as the research and development programmes in the field of technical safety are also described. The ongoing experiments in CABRI reactor, aimed at determining the high burnup fuel behaviour under reactivity initiated accidents until 65 GW d/Mt U, are one of these programs.

Expertise and participation of the population in the context of nuclear risk: democracy and environmental licensing of Angra 3 nuclear power plant

Directory of Open Access Journals (Sweden)

Gláucia Silva

2010-01-01

Full Text Available This article discusses the specificity of citizens' "participation" in contexts of decision-making on the acceptance of nuclear risk, demonstrating that such acceptance depends on mediation by professionals who are willing to translate the typical scientific jargon of technical reports and/or produce their own reports, by way of counter-expertise; otherwise, lay people are unable to confer scientific legitimacy to their arguments. The basic empirical references for the current analysis are the recurrent themes from public hearings organized for the licensing of two Brazilian nuclear power plants using German technology, Angra 2 and Angra 3, with emphasis on the latter, now undergoing prior environmental licensing. The forms of "social control" engendered in France serve as a counterpoint for developing the article's argument.

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)

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

Testing, licensing, and code requirements for seismic isolation systems (for nuclear power plants)

International Nuclear Information System (INIS)

Seidensticker, R.W.

1987-01-01

The use of seismic isolation as an earthquake hazard mitigation strategy for nuclear reactor power plants is rapidly receiving interest throughout the world. Seismic isolation has already been used on at least two French PWR plants, was to have been used for plants to be built in Iran, and is under serious consideration for advanced LMR plants (in the US, UK, France, and Japan). In addition, there is a growing use of seismic isolation throughout the world for other critical facilities such as hospitals, emergency facilities, buildings with very high-cost equipment (e.g., computers) and as a strategy to reduce loss of life and expensive equipment in earthquakes. Such a design approach is in complete contrast to the conventional seismic design strategy in which the structure and components are provided with sufficient strength and ductility to resist the earthquake forces and to prevent structural collapses or failure. The use of seismic isolation for nuclear plants can, therefore, be expected to be a significant licensing issue. For isolation, the licensing process must shift away in large measure from the superstructure and concentrate on the behavior of the seismic isolation system. This paper is not intended to promote the advantages of seismic isolation system, but to explore in some detail those technical issues which must be satisfactorily addressed to achieve full licensability of the use of seismic isolation as a viable, attractive and economical alternative to current traditional design approaches. Special problems and topics associated with testing and codes and standards development are addressed. A positive program for approach or strategy to secure licensing is presented

Testing, licensing, and code requirements for seismic isolation systems (for nuclear power plants)

Energy Technology Data Exchange (ETDEWEB)

Seidensticker, R.W.

1987-01-01

The use of seismic isolation as an earthquake hazard mitigation strategy for nuclear reactor power plants is rapidly receiving interest throughout the world. Seismic isolation has already been used on at least two French PWR plants, was to have been used for plants to be built in Iran, and is under serious consideration for advanced LMR plants (in the US, UK, France, and Japan). In addition, there is a growing use of seismic isolation throughout the world for other critical facilities such as hospitals, emergency facilities, buildings with very high-cost equipment (e.g., computers) and as a strategy to reduce loss of life and expensive equipment in earthquakes. Such a design approach is in complete contrast to the conventional seismic design strategy in which the structure and components are provided with sufficient strength and ductility to resist the earthquake forces and to prevent structural collapses or failure. The use of seismic isolation for nuclear plants can, therefore, be expected to be a significant licensing issue. For isolation, the licensing process must shift away in large measure from the superstructure and concentrate on the behavior of the seismic isolation system. This paper is not intended to promote the advantages of seismic isolation system, but to explore in some detail those technical issues which must be satisfactorily addressed to achieve full licensability of the use of seismic isolation as a viable, attractive and economical alternative to current traditional design approaches. Special problems and topics associated with testing and codes and standards development are addressed. A positive program for approach or strategy to secure licensing is presented.

Cleansing and dismantling of CEA-Saclay nuclear licensed facilities

International Nuclear Information System (INIS)

Jeanjacques, Michel; Delaire, Isabelle; Glevarec, Rebecca; Mandard, Lionel; Martin, Jean-Louis; Serrano, Roger

2013-01-01

This summary presents the cleansing and dismantling operations currently realized on the CEA center of Saclay (CEA-Saclay). It was initiated at the beginning of the 2000 years a cleansing and dismantling program of the old Nuclear Licensed Facilities (NLF). Currently this program relates the dismantling operations to the Hot Laboratories (Laboratoires de Haute Activite: LHA) and the old workshops of the Liquid Waste Treatment Plant (Station des Effluents Liquides: STEL), the dismantling preparation of Ulysse reactor and the dismantling studies to the Solid Waste Management Plant (SWMP; Zone de Gestion des Dechets Solides) and the Osiris reactor. (authors)

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)