WorldWideScience

Sample records for nuclear plant decommissioning

  1. Nuclear power plant decommissioning

    International Nuclear Information System (INIS)

    Yaziz Yunus

    1986-01-01

    A number of issues have to be taken into account before the introduction of any nuclear power plant in any country. These issues include reactor safety (site and operational), waste disposal and, lastly, the decommissioning of the reactor inself. Because of the radioactive nature of the components, nuclear power plants require a different approach to decommission compared to other plants. Until recently, issues on reactor safety and waste disposal were the main topics discussed. As for reactor decommissioning, the debates have been academic until now. Although reactors have operated for 25 years, decommissioning of retired reactors has simply not been fully planned. But the Shippingport Atomic Power Plant in Pennysylvania, the first large scale power reactor to be retired, is now being decommissioned. The work has rekindled the debate in the light of reality. Outside the United States, decommissioning is also being confronted on a new plane. (author)

  2. Decommissioning of nuclear power plants

    International Nuclear Information System (INIS)

    Friske, A.; Thiele, D.

    1988-01-01

    The IAEA classification of decommissioning stages is outlined. The international development hitherto observed in decommissioning of nuclear reactors and nuclear power stations is presented. The dismantling, cutting and decontamination methods used in the decommissioning process are mentioned. The radioactive wastes from decommissioning are characterized, the state of the art of their treatment and disposal is given. The radiation burdens and the decommissioning cost in a decommissioning process are estimated. Finally, some evaluation of the trends in the decommissioning process of nuclear power plants is given. 54 refs. (author)

  3. Decommissioning of nuclear power plants

    International Nuclear Information System (INIS)

    Vollradt, J.

    1977-01-01

    A survey of the main questions of decommissioning of nuclear power plants will be given in the sight of German utilities (VDEW-Working group 'Stillegung'). The main topics are: 1) Definitions of decommissioning, entombment, removal and combinations of such alternatives; 2) Radioactive inventory (build up and decay); 3) Experience up to now; 4) Possibilities to dismantle are given by possibility to repair nuclear power plants; 5) Estimated costs, waste, occupational radiation dose; 6) German concept of decommissioning. (orig./HK) [de

  4. Costs of Decommissioning Nuclear Power Plants

    International Nuclear Information System (INIS)

    Neri, Emilio; French, Amanda; Urso, Maria Elena; Deffrennes, Marc; Rothwell, Geoffrey; ); Rehak, Ivan; Weber, Inge; ); Carroll, Simon; Daniska, Vladislav

    2016-01-01

    While refurbishments for the long-term operation of nuclear power plants and for the lifetime extension of such plants have been widely pursued in recent years, the number of plants to be decommissioned is nonetheless expected to increase in future, particularly in the United States and Europe. It is thus important to understand the costs of decommissioning so as to develop coherent and cost-effective strategies, realistic cost estimates based on decommissioning plans from the outset of operations and mechanisms to ensure that future decommissioning expenses can be adequately covered. This study presents the results of an NEA review of the costs of decommissioning nuclear power plants and of overall funding practices adopted across NEA member countries. The study is based on the results of this NEA questionnaire, on actual decommissioning costs or estimates, and on plans for the establishment and management of decommissioning funds. Case studies are included to provide insight into decommissioning practices in a number of countries. (authors)

  5. EPRI nuclear power plant decommissioning technology program

    International Nuclear Information System (INIS)

    Kim, Karen S.; Bushart, Sean P.; Naughton, Michael; McGrath, Richard

    2011-01-01

    The Electric Power Research Institute (EPRI) is a non-profit research organization that supports the energy industry. The Nuclear Power Plant Decommissioning Technology Program conducts research and develops technology for the safe and efficient decommissioning of nuclear power plants. (author)

  6. Commercialization of nuclear power plant decommissioning technology

    International Nuclear Information System (INIS)

    Williams, D.H.

    1983-01-01

    The commercialization of nuclear power plant decommissioning is presented as a step in the commercialization of nuclear energy. Opportunities for technology application advances are identified. Utility planning needs are presented

  7. Evaluating decommissioning costs for nuclear power plants

    International Nuclear Information System (INIS)

    MacDonald, R.R.

    1980-01-01

    An overview is presented of the economic aspects of decommissioning of large nuclear power plants in an attempt to put the subject in proper perspective. This is accomplished by first surveying the work that has been done to date in evaluating the requirements for decommissioning. A review is presented of the current concepts of decommissioning and a discussion of a few of the uncertainties involved. This study identifies the key factors to be considered in the econmic evaluation of decommissioning alternatives and highlights areas in which further study appears to be desirable. 12 refs

  8. Modelling of nuclear power plant decommissioning financing.

    Science.gov (United States)

    Bemš, J; Knápek, J; Králík, T; Hejhal, M; Kubančák, J; Vašíček, J

    2015-06-01

    Costs related to the decommissioning of nuclear power plants create a significant financial burden for nuclear power plant operators. This article discusses the various methodologies employed by selected European countries for financing of the liabilities related to the nuclear power plant decommissioning. The article also presents methodology of allocation of future decommissioning costs to the running costs of nuclear power plant in the form of fee imposed on each megawatt hour generated. The application of the methodology is presented in the form of a case study on a new nuclear power plant with installed capacity 1000 MW. © The Author 2015. Published by Oxford University Press. All rights reserved. For Permissions, please email: journals.permissions@oup.com.

  9. Radiological characterization of nuclear plants under decommissioning

    International Nuclear Information System (INIS)

    Mincarini, M.

    1989-01-01

    In the present work a description of major problems encountered in qualitative and quantitative radiological characterization of nuclear plants for decommissioning and decontamination purpose is presented. Referring to several nuclear plant classes activation and contamination processes, direct and indirect radiological analysis and some italian significant experience are descripted

  10. Nuclear power plant decommissioning costs in perspective

    International Nuclear Information System (INIS)

    Rothwell, Geoffrey; Deffrennes, Marc; Weber, Inge

    2016-01-01

    At the international level, actual experience is limited in the completion of nuclear power plant decommissioning projects. Cost data for decommissioning projects are thus largely unavailable, with few examples of analyses or comparisons between estimates and actual costs at the project level. The Nuclear Energy Agency (NEA) initiated a project to address this knowledge gap and in early 2016 published the outcomes in the report on Costs of Decommissioning Nuclear Power Plants. The study reviews decommissioning costs and funding practices adopted by NEA member countries, based on the collection and analysis of survey data via a questionnaire. The work was carried out in co-operation with the International Atomic Energy Agency (IAEA) and the European Commission (EC). (authors)

  11. MODELLING OF NUCLEAR POWER PLANT DECOMMISSIONING FINANCING

    Czech Academy of Sciences Publication Activity Database

    Bemš, J.; Knápek, J.; Králík, T.; Hejhal, M.; Kubančák, Ján; Vašíček, J.

    2015-01-01

    Roč. 164, č. 4 (2015), s. 519-522 ISSN 0144-8420 Institutional support: RVO:61389005 Keywords : nuclear power plant * methodology * future decommissioning costs Subject RIV: BG - Nuclear, Atomic and Molecular Physics, Colliders Impact factor: 0.894, year: 2015

  12. Waste from decommissioning of nuclear power plants

    International Nuclear Information System (INIS)

    Nielsen, P.O.

    1992-05-01

    This report is based on the assumption that all twelve nuclear power plants will be shut down no later than A.D. 2010, as was decided by the parliament after the referendum on the future of nuclear power in Sweden. The recent 'Party agreement on the energy policy' of January 15, 1991 does, indeed, leave the door open for an extension of the operational period for the nuclear reactors. This will, however, not change the recommendations and conclusions drawn in this report. The report consists of two parts. Part 1 discusses classification of waste from decommissioning and makes comparisons with the waste arising from reactor operation. Part 2 discusses the documentation required for decommissioning waste. Also this part of the report draws parallels with the documentation required by the authorities for the radioactive waste arising from operation of the nuclear power plants. To some extent these subjects depend on the future use of the nuclear power plant sites after decommissioning of the plants. The options for future site use are briefly discussed in an appendix to the report. There are many similarities between the waste from reactor operations and the waste arising from dismantling and removal of decommissioned nuclear power plants. Hence it seems natural to apply the same criteria and recommendations to decommissioning waste as those presently applicable to reactor waste. This is certainly true also with respect to documentation, and it is strongly recommended that the documentation requirements on decommissioning waste are made identical, or at least similar, to the documentation requirements for reactor waste in force today. (au)

  13. Nuclear power plant decommissioning: an unresolved problem

    International Nuclear Information System (INIS)

    Pollock, C.

    1987-01-01

    In 1984, the Critical Mass Energy Project asserted that at least 11 US reactors had gone through one-third of their operating lives without collecting any decommissioning funds and that nationwide only $600 million had been collected. This lack of financial planning prompted 10 states to require mandatory periodic deposits into external accounts: California, Colorado, Connecticut, Maine, Massachusetts, Mississippi, New Hampshire, Pennsylvania, Vermont, and Wisconsin. Setting aside decommissioning funds is essential in every country that uses nuclear power. Regardless of a nation's future energy plans, existing plants must eventually be scrapped. Just as today's cities would not be habitable without large fleets of garbage trucks and extensive landfills, the international nuclear industry is not viable without a sound decommissioning strategy. Thirty years after the first nuclear plant started producing electricity, such a strategy has yet to be formulated. More than 500 reactors, including those currently under construction, will have to be decommissioned. Preparing to safely retire these plants requires aggressive, well-funded research and development programs, policy makers willing to tackle unpleasant, long-term problems, and robust retirement accounts funded by today's utility customers

  14. Safety problems in decommissioning nuclear power plants

    International Nuclear Information System (INIS)

    Auler, I.; Bardtenschlager, R.; Gasch, A.; Majohr, N.

    1975-12-01

    The safety problems at decommissioning are illustrated by the example of a LWR with 1300 MW electric power after 40 years of specified normal operation. For such a facility the radioactivity in the form of activation and contamination one year after being finally taken out of service is in the order of magnitude of 10 7 Ci, not counting the fuel assemblies. The dose rates occurring during work on the reactor vessel at nozzle level may amount to some 10 4 rem/h. After a rough estimation the accumulated dose for the decommissioning personnel during total dismantling will be about 1200 rem. During performance of the decommissioning activities the problems are mainly caused by direct radiation of the active components and systems and by the release of radioactive particles, aerosols and liquids if these components are crushed. The extent of later dismantling problems may be reduced by selecting appropriate materials as well as considering the requirements for dismantling in design and arrangement of the components already in the design stage of new facilities. Apart from plant design also the concept for the disposal of the radioactive waste from decommissioning will provide important boundary conditions. E.g. the maximum size of the pieces to be stored in the ultimate storage place will very much influence the dose expenditure for handling these parts. For complete dismantling of nuclear power plants an ultimate store must be available where large amounts of bulky decommissioning waste, containing relatively low activity, can be stored. The problems and also the cost for decommissioning may be considerably reduced by delaying complete disposal of the radioactive material >= 40 years and during this period, keeping the radioactivity enclosed within the plant in the form of a safe containment. (orig./HP) [de

  15. Discussion on management of decommissioning funds for nuclear power plants

    International Nuclear Information System (INIS)

    Wang Hailiang

    2013-01-01

    Decommissioning funding is one of the major issues with regard to the policy and management of nuclear power. This paper describes current status of decommissioning of nuclear power plants in some foreign countries and narrates the practices in these countries on the estimation of decommissioning cost, the retrieval and management of decommissioning funds, and the guarantee of fund sufficiency. Based on a brief analysis of the status of decommissioning funding management for nuclear power plants in China, suggestions on tasks or activities needed to be carried out at present in the field of decommissioning funding are proposed. (authors)

  16. Decommissioning project of commercial nuclear power plant

    International Nuclear Information System (INIS)

    Karigome, S.

    2008-01-01

    Decommissioning project of commercial nuclear power plant in Japan was outlined. It is expected that the land, after the decommissioning of commercial nuclear power plants, will serve as sites for new plants. Steps will be taken to reduce the amount of wastes generated and to recycle/reuse them. Wastes with a radioactivity concentration below the 'clearance level' need not be dealt with as radioactive material, and may be handled in the same way as conventional wastes. The Tokai-1 power station, a 166 MWe carbon dioxide cooled reactor which closed down in 1998, is being decommissioned and the first ten years as 'safe storage' to allow radioactivity to decay. Non-reactor grade components such as turbines were already removed, heat exchanger dismantling started and the reactor will be dismantled, the buildings demolished and the site left ready for reuse. All radioactive wastes will be classified as low-level wastes in three categories and will be buried under the ground. The total cost will be 88.5 billion yen -34.7 billion for dismantling and 53.8 billion for waste treatment including the graphite moderator. (T. Tanaka)

  17. Decommissioning planning of Swedish nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Hedin, Gunnar; Bergh, Niklas [Westinghouse Electric Sweden AB, Vaesteraes (Sweden)

    2013-07-01

    The technologies required for the decommissioning work are for the most part readily proven. Taken into account that there will be many more years before the studied reactor units will undergo decommissioning, the techniques could even be called conventional at that time. This will help bring the decommissioning projects to a successful closure. A national waste fund is already established in Sweden to finance amongst others all dismantling and decommissioning work. This will assure that funding for the decommissioning projects is at hand when needed. All necessary plant data are readily available and this will, combined with a reliable management system, expedite the decommissioning projects considerably. Final repositories for both long- and short-lived LILW respectively is planned and will be constructed and dimensioned to receive the decommissioning waste from the Swedish NPP:s. Since the strategy is set and well thought-through, this will help facilitate a smooth disposal of the radioactive decommissioning waste. (orig.)

  18. Decommissioning and back working of Greifswald nuclear power plant

    International Nuclear Information System (INIS)

    Rittscher, D.; Leushacke, D.F.; Meyer, R.

    1998-01-01

    At Nuclear Power Plant Greifswald, the Energiewerke Nord are carrying out the presently world's largest decommissioning project. This requires the gathering up of experience from the operation of the nuclear power plants at Greifswald, the decommissioning of other nuclear power plants, waste management, project management and licensing procedures for the decommissioning of nuclear power plants. That confirmed that the back working of nuclear plants is not a technical problem but a challenge for project management and logistics. It shows that the dismantling and disposal of nuclear plants is an ordinary process in our economic life. (orig.) [de

  19. Decommissioning of nuclear power plant

    International Nuclear Information System (INIS)

    Sato, Tadamichi

    2002-01-01

    On nuclear energy facilities, an abolished one is often difficult to reuse, and is difficult to subdivide because of its strong structure and its inclusion of many apparatus and constructions containing radioactive materials in them. And, it is required to consider radiation management under dismantling operation and radioactive wastes forming at its subdivision. Abolishment of nuclear power station is a measure carrying out subdivision removing of a facility ended its role to a condition unnecessary for its radiation administration, and is defined as all of measures to be done after unused condition before reaching green field condition. Here were described on basic principle on abolishment measure in Japan, processing and disposition of subdivided wastes, and system preparation. (G.K.)

  20. Development of a decommissioning plan for nuclear power plant 'Krsko'

    International Nuclear Information System (INIS)

    Tankosic, Djurica; Fink, Kresimir

    1991-01-01

    Nuclear Power Plant 'Krsko' (NEK), is the only nuclear power plant in Yugoslavia, is a two-loop, Westinghouse-design, pressurized water reactor rated at 632 MWe. When NEK applied for an operating license in 1981, it did not have to explain how the plant would be decommissioned and decommissioning provisions were not part of the licensing process. Faced with mounting opposition to nuclear power and a real threat that the plant would be shut down, the plant management developed a Mission Plan for resolving the decommissioning problem. The Mission Plan calls for a preliminary decommissioning plan to be prepared and submitted to the local regulatory body before the end of 1992

  1. Innovative Nuclear Power Plant Building Arrangement in Consideration of Decommissioning

    OpenAIRE

    Won-Jun Choi; Myung-Sub Roh; Chang-Lak Kim

    2017-01-01

    A new concept termed the Innovative Nuclear Power Plant Building Arrangement (INBA) strategy is a new nuclear power plant building arrangement method which encompasses upfront consideration of more efficient decommissioning. Although existing decommissioning strategies such as immediate dismantling and differed dismantling has the advantage of either early site restoration or radioactive decommissioning waste reduction, the INBA strategy has the advantages of both strategies. In this research...

  2. Public attitudes toward nuclear power plant decommissioning

    International Nuclear Information System (INIS)

    Lough, W.T.

    1987-01-01

    A public workshop was conducted with a group of citizens to obtain the concerns and preferences of the group with respect to decommissioning. Seventeen concerns about decommissioning were identified and prioritized. The participants were most concerned about the potential health and safety effects from decommissioning. The potential impacts from the lost tax base and loss of employment were also rated highly. The estimated increase in electric utility rates was not a major concern. The participants were split fairly evenly on preferences about the methods of decommissioning. However, nine of the ten participants preferred power plant life extension over decommissioning by any method. Finally, the participants were given an evaluation questionnaire about the workshop. In general, they concluded that the process was effective, and they felt like they were a part of the Commission's planning process

  3. Nuclear power plant decommissioning. The nature of problems

    Energy Technology Data Exchange (ETDEWEB)

    Yunus, Yaziz

    1986-04-01

    A number of issues have to be taken into account before the introduction of any nuclear power plant in any country. These issues include reactor safety (site and operational), waste disposal and, lastly, the decommissioning of the reactor inself. Because of the radioactive nature of the components, nuclear power plants require a different approach to decommission compared to other plants. Until recently, issues on reactor safety and waste disposal were the main topics discussed. As for reactor decommissioning, the debates have been academic until now. Although reactors have operated for 25 years, decommissioning of retired reactors has simply not been fully planned. But the Shippingport Atomic Power Plant in Pennysylvania, the first large-scale power reactor to be retired, is now being decommissioned. The work has rekindled the debate in the light of reality. Outside the United States, decommissioning is also being confronted on a new plane.

  4. Knowledge management for the decommissioning of nuclear power plants

    International Nuclear Information System (INIS)

    Kirschnick, F.; Engelhardt, S.

    2004-01-01

    This paper describes background, objectives and select conceptual components of knowledge management for the decommissioning of nuclear power plants. The concept focuses on the transfer of personal practice experience within and between nuclear power plants. The conceptual insights embrace aspects of knowledge content, structure, KM processes, organization, cooperation, culture, persuasion, leadership, technology, infrastructure, business impact and resilience. Key challenges are discussed, and related advice is provided for KM practitioners with similar endeavours in the field of nuclear power plant decommissioning. (author)

  5. Radiation protection in connection with the decommissioning of nuclear plants

    International Nuclear Information System (INIS)

    1997-04-01

    This document presents the SSI preliminary views and position concerning the decommissioning of nuclear plants. To prevent the exposure of the decommissioning personnel and the general public to unacceptable levels of radiation and to protect the environment and future generations, it is SSI's task to formulate and issue the necessary terms and regulations with which the reactor licensees must comply during the decommissioning work. The views and principles presented here are the basis of SSI's continued work on guidelines and regulations for the decommissioning of nuclear plants

  6. Nuclear power plant decommissioning: state-of-the-art review

    International Nuclear Information System (INIS)

    Williams, D.H.

    1984-01-01

    A brief orientation to the state-of-the-art of nuclear power plant decommissioning discusses the related areas of experience, tools and techniques, and planning. There have been 68 nuclear reactor decommissionings to date, including 9 power plants, some of which were mothballed. The picture suggests that the term art may be misapplied since decommissioning is now more of a mature commercial industrial than a research and development endeavor. It also suggests that the nuclear industry has shown foresight by preparing for it before a crisis situation developed. Some of this has already influenced operators of coal power plants, especially where hazardous materials may be involved. 33 references, 1 table

  7. Safe decommissioning of mobile nuclear power plant

    International Nuclear Information System (INIS)

    Paliukhovich, V.M.

    2002-01-01

    The paper addresses some issues for ensuring radiation safety during the process of decommissioning the 630 kW 'Pamir-630D' mobile nuclear power plant (MNPP). That nuclear power plant consisted of a gas cooled reactor (weight of 76.5t), gas turbine-driven set (76t), two control units (2'20t), and an auxiliary unit (20t). The reactor and turbine-driven set were supposed to be put on transport platforms and carried by tractors. The control and auxiliary units were set on track beds. The 'Pamir-630D' was constructed and tested in an appropriate building. The set-up time was no greater than six hours after all units of the MNPP had reached the site. The 'Pamir-630D' was ready to be moved to another site in 30 hours after the shut down. Service lifetime of 'Pamir-630D' was 10 years: 7 years of storage and 3 years of operation. Operational lifetime was no less than 10000 hours (non-stop operational period was no longer than 2000 hours). Dose rate at the boundary of the restrictive area was no more than 6.5 mR/h at the time of reactor operation and no greater than 300 mR/h on the side surface and 1000 mR/h on the end surface of the biological shielding of the reactor, 24 hours after shut down. (author)

  8. Program change management during nuclear power plant decommissioning

    International Nuclear Information System (INIS)

    Bushart, Sean; Kim, Karen; Naughton, Michael

    2011-01-01

    Decommissioning a nuclear power plant is a complex project. The project involves the coordination of several different departments and the management of changing plant conditions, programs, and regulations. As certain project Milestones are met, the evolution of such plant programs and regulations can help optimize project execution and cost. This paper will provide information about these Milestones and the plant departments and programs that change throughout a decommissioning project. The initial challenge in the decommissioning of a nuclear plant is the development of a definitive plan for such a complex project. EPRI has published several reports related to decommissioning planning. These earlier reports provided general guidance in formulating a Decommissioning Plan. This Change Management paper will draw from the experience gained in the last decade in decommissioning of nuclear plants. The paper discusses decommissioning in terms of a sequence of major Milestones. The plant programs, associated plans and actions, and staffing are discussed based upon experiences from the following power reactor facilities: Maine Yankee Atomic Power Plant, Yankee Nuclear Power Station, and the Haddam Neck Plant. Significant lessons learned from other sites are also discussed as appropriate. Planning is a crucial ingredient of successful decommissioning projects. The development of a definitive Decommissioning Plan can result in considerable project savings. The decommissioning plants in the U.S. have planned and executed their projects using different strategies based on their unique plant circumstances. However, experience has shown that similar project milestones and actions applied through all of these projects. This allows each plant to learn from the experiences of the preceding projects. As the plant transitions from an operating plant through decommissioning, the reduction and termination of defunct programs and regulations can help optimize all facets of

  9. Nuclear decommissioning

    Energy Technology Data Exchange (ETDEWEB)

    Lawton, H.

    1987-02-01

    Sufficient work has now been done, on a world-wide basis, to justify confidence that full decommissioning of nuclear installations, both plant and reactors, can be carried out safely and efficiently. Projects in several countries should confirm this in the next few years. In the UK, good progress has been made with the WAGR and supporting development work is finding solutions to resolve uncertainties. Estimates from several sources suggest that decommissioning costs can be kept to an acceptable level.

  10. Nuclear decommissioning

    International Nuclear Information System (INIS)

    Lawton, H.

    1987-01-01

    Sufficient work has now been done, on a world-wide basis, to justify confidence that full decommissioning of nuclear installations, both plant and reactors, can be carried out safely and efficiently. Projects in several countries should confirm this in the next few years. In the UK, good progress has been made with the WAGR and supporting development work is finding solutions to resolve uncertainties. Estimates from several sources suggest that decommissioning costs can be kept to an acceptable level. (author)

  11. Decommissioning of building part of nuclear power plant

    International Nuclear Information System (INIS)

    Sochor, R.

    1988-01-01

    The characteristics are discussed using literature data of building work during decommissioning or reconstruction of nuclear power plants. The scope of jobs associated with power plant decommissioning is mainly given by the size of contaminated parts, intensity of radioactivity, the volume of radioactive wastes and the possible building processes. Attention is devoted to the cost of such jobs and the effect of the plant design on cost reduction. (Z.M.). 6 refs

  12. Guidelines for estimating nuclear power plant decommissioning costs

    International Nuclear Information System (INIS)

    LaGuardia, T.S.; Williams, D.H.

    1989-01-01

    The objectives of the study were: (1) To develop guidelines to facilitate estimating the cost of nuclear power plant decommissioning alternatives on a plant-specific basis and to facilitate comparing estimates made by others. The guidelines are expressed in a form that could be readily adapted by technical specialists from individual utilities or by other uses. (2) To enhance the industry's credibility with decision-makes at the state and federal levels during rate/regulatory processes involving decommissioning costs. This is accomplished by providing a detailed, systematic breakdown of how decommissioning cost estimates are prepared. (3) To increase the validity, realism, and accuracy of site-specific decommissioning cost estimates. This is accomplished by pulling together the experiences and practices of several nuclear utilities and consultants in conducting past decommissioning cost estimates

  13. Decommissioning and equipment replacement of nuclear power plants under uncertainty

    International Nuclear Information System (INIS)

    Takashima, Ryuta; Naito, Yuta; Kimura, Hiroshi; Madarame, Haruki

    2007-01-01

    This study examines the optimal timing for the decommissioning and equipment replacement of nuclear power plants. We consider that the firm has two options of decommissioning and equipment replacement, and determines to exercise these options under electricity price uncertainty. This problem is formulated as two optimal stopping problems. The solution of this model provides the value of the nuclear power plant and the threshold values for decommissioning and replacement. The dependence of decommissioning and replacement strategies on uncertainty and each cost is shown. In order to investigate the probability of events for decommissioning and replacement, Monte Carlo calculations are performed. We also show the probability distribution and the conditional expected time for each event. (author)

  14. Aspects related to the decommissioning of the nuclear power plants

    International Nuclear Information System (INIS)

    Goicea, Andrei; Andrei, Veronica

    2003-01-01

    All power plants, either coal, gas or nuclear, at the end of their life needs to be decommissioned and demolished and thus, to made the site available for other uses. The first generation nuclear power plants were designed for a life of about 30 years and some of them proved capable of continuing well beyond this term. Newer plants have been designed for a 40 to 60 years operating life. To date, other 90 commercial power reactors have been retired from operation. For nuclear power plants and nuclear facilities in general the decommissioning process consists of some or all of the following activities: the safe management of nuclear materials held in the facility, cleaning-up of radioactivity (decontamination), plant dismantling, progressive demolition of the plant and site remediation. Following the decommissioning, the regulatory controls covering facility end, partially or totally, and the safe site is released for appropriate alternative use. Cernavoda NPP is a young plant and it can benefit from the continuously developing experience of the decommissioning process at the international level. The current experience allows the most metallic parts of a nuclear power to be decontaminated and recycled and makes available proven techniques and equipment to dismantle nuclear facilities safely. As experience is gained, decommissioning costs for nuclear power plants, including disposal of associated wastes, are reducing and thus, contribute in a smaller fraction to the total cost of electricity generation. The new specific Romanian regulations establish a funding system for decommissioning and provisions for long-term radioactive waste management. In the near future a decommissioning plan will be made available for Cernavoda NPP. Since the plant has only 7 years operation, that plan can be improved in order to benefit from international experience that is growing. (authors)

  15. Funding nuclear-power-plant decommissioning. Final report

    International Nuclear Information System (INIS)

    Burns, R.E.; Henderson, J.S.; Pollard, W.; Pryor, T.; Chen, Y.M.

    1982-10-01

    The report is organized according to the steps that one might go through when analyzing funding of decommissioning costs. The first step in analyzing decommissioning costs might be to review the present regulatory framework within which decommissioning cost decisions must be made. A description is presented of the present NRC regulations that address the decommissioning of a nuclear power plant. A description is also presented of recent public utility commission activities concerning funding the costs of decommissioning. Possible future trends in NRC regulation are also discussed. The estimation of decommmissioning costs is analyzed. A description of each of the possible decommissoining options is presented. The options of decommissioning include immediate dismantlement, various types of safe storage, and entombment. A discussion is presented of cost estimations for each decommissioning option for nuclear units containing pressurized water reactors and boiling water reactors. A description is included of the various methods of collecting funds for decommissioning as well as a discussion of their possible regulatory treatment. Material is presented which will provide the reader with background information that might assist state utility commissioners or their staffs in choosing or evaluating one of the financial mechanisms for covering decommissioning costs

  16. Decommissioning of nuclear power plants: policies, strategies and costs

    International Nuclear Information System (INIS)

    Lund, I.

    2004-01-01

    As many nuclear power plants will reach the end of their lifetime during the next 20 years or so, decommissioning is an increasingly important topic for governments, regulators and industries. From a governmental viewpoint, particularly in a deregulated market, one essential aspect is to ensure that money for the decommissioning of nuclear installations will be available at the time it is needed, and that no 'stranded' liabilities will be left to be financed by the taxpayers rather than by the electricity consumers. For this reason, there is governmental interest in understanding decommissioning costs, and in periodically reviewing decommissioning cost estimates from nuclear installation owners. Robust cost estimates are key elements in designing and implementing a coherent and comprehensive national decommissioning policy including the legal and regulatory bases for the collection, saving and use of decommissioning funds. From the industry viewpoint, it is essential to assess and monitor decommissioning costs in order to develop a coherent decommissioning strategy that reflects national policy and assures worker and public safety, whilst also being cost effective. For these reasons, nuclear power plant owners are interested in understanding decommissioning costs as best as possible and in identifying major cost drivers, whether they be policy, strategy or 'physical' in nature. National policy considerations will guide the development of national regulations that are relevant for decommissioning activities. Following these policies and regulations, industrial managers responsible for decommissioning activities will develop strategies which best suit their needs, while appropriately meeting all government requirements. Decommissioning costs will be determined by technical and economic conditions, as well as by the strategy adopted. Against this backdrop, the study analyses the relationships among decommissioning policy as developed by governments, decommissioning

  17. Factors influencing the decommissioning of large-scale nuclear plants

    International Nuclear Information System (INIS)

    Large, J.H.

    1988-01-01

    The decision-making process involving the decommissioning of the UK graphite moderated, gas-cooled nuclear power stations is complex. There are timing, engineering, waste disposal, cost and lost generation capacity factors to consider and the overall decision of when and how to proceed with decommissioning may include political and public tolerance dimensions. For the final stage of decommissioning the nuclear industry could either completely dismantle the reactor island leaving a green-field site or, alternatively, the reactor island could be maintained indefinitely with additional super- and substructure containment. At this time the first of these options, or deferred decommissioning, prevails and with this the nuclear industry has expressed considerable confidence that the technology required will become available with passing time, that acceptable radioactive waste disposal methods and facilities will be available and that the eventual costs of decommissioning will not escalate without restraint. If the deferred decommissioning strategy is wrong and it is not possible to completely dismantle the reactor islands a century into the future, then it may be too late to effect sufficient longer term containment to maintain the reactor hulks in a reliable condition. With respect to the final decommissioning of large-scale nuclear plant, it is concluded that the nuclear industry does not know quite how to do it, when it will be attempted and when it will be completed, and they do not know how much it will eventually cost. (author)

  18. Evaluation of nuclear facility decommissioning projects. Status report. Humboldt Bay Power Plant Unit 3, SAFSTOR decommissioning

    International Nuclear Information System (INIS)

    Baumann, B.L.; Haffner, D.R.; Miller, R.L.; Scotti, K.S.

    1986-06-01

    This document explains the purpose of the US Nuclear Regulatory Commission's (NRC) Evaluation of Nuclear Facility Decommissioning Projects (ENFDP) program and summarizes information concerning the decommissioning of the Humboldt Bay Power Plant (HBPP) Unit 3 facility. Preparations to put this facility into a custodial safe storage (SAFSTOR) mode are currently scheduled for completion by June 30, 1986. This report gives the status of activities as of June 1985. A final summary report will be issued after completion of this SAFSTOR decommissioning activity. Information included in this status report has been collected from the facility decommissioning plan, environmental report, and other sources made available by the licensee. This data has been placed in a computerized data base system which permits data manipulation and summarization. A description of the computer reports that can be generated by the decommissioning data system (DDS) for Humboldt Bay and samples of those reports are included in this document

  19. Nuclear decommissioning

    International Nuclear Information System (INIS)

    Lawton, H.

    1987-01-01

    Sufficient work has now been done, on a world-wide basis, to justify confidence that full decommissioning of nuclear installations, both plant and reactors, can be carried out safely and efficiently. Projects in several countries should confirm this in the next few years. In the United Kingdom, good progress has been made with the Windscale Advanced Gas-cooled Reactor and supporting development work is finding solutions to resolve uncertainties. Estimates from several sources suggest that decommissioning costs can be kept to an acceptable level. (author)

  20. Decommissioning nuclear power plants. Policies, strategies and costs

    International Nuclear Information System (INIS)

    2003-01-01

    The decommissioning of nuclear power plants is a topic of increasing interest to governments and the industry as many nuclear units approach retirement. It is important in this context to assess decommissioning costs and to ensure that adequate funds are set aside to meet future financial liabilities arising after nuclear power plants are shut down. Furthermore, understanding how national policies and industrial strategies affect those costs is essential for ensuring the overall economic effectiveness of the nuclear energy sector. This report, based upon data provided by 26 countries and analysed by government and industry experts, covers a variety of reactor types and sizes. The findings on decommissioning cost elements and driving factors in their variance will be of interest to analysts and policy makers in the nuclear energy field. (author)

  1. Cost estimation of the decommissioning of nuclear fuel cycle plants

    International Nuclear Information System (INIS)

    Barbe, A.; Pech, R.

    1991-01-01

    Most studies conducted to date on the cost of decommissioning nuclear facilities pertain to reactors. Few such studies have been performed on the cost of decommissioning nuclear fuel cycle plants, particularly spent fuel reprocessing plants. Present operators of these plants nevertheless need to assess such costs, at least in order to include the related expenses in their short-, medium- or long-term projections. They also need to determine now, for example, suitable production costs that the plant owners will have to propose to their customers. Unlike nuclear reactors for which a series effect is involved (PWRs, BWRs, etc.) and where radioactivity is relatively concentrated, industrial-scale reprocessing plants are large, complex installations for which decommissioning is a long and costly operation that requires a special approach. Faced with this problem, Cogema, the owner and operator of the La Hague and Marcoule reprocessing plants in France, called on SGN to assess the total decommissioning costs for its plants. This assessment led SGN to development by SGN engineers of a novel methodology and a computerized calculation model described below. The resulting methodology and model are applicable to other complex nuclear facilities besides reprocessing plants, such as laboratories and nuclear auxiliaries of reactor cores. (author)

  2. Construction times and the decommissioning of nuclear power plants

    International Nuclear Information System (INIS)

    Erramuspe, H.J.

    1988-01-01

    The construction and the decommissioning periods of nuclear power plants (NPP), are studied, due to their importance in the generation costs. With reference to the construction periods of these plants, a review is made of the situation and technical improvements made in different countries, with the purpose of shortening them. In regard to the decommissioning of NPP, the present and future situations are reviewed in connection with different stages of decommissioning and their related problems, as the residual radioactivity of different components, and the size of the final wastes to be disposed of. The possibilities of plant life extensions are also revised in connection with these problems. Finally, the expected decommissioning costs are analyzed. (Author) [es

  3. Innovative nuclear power plant building arragement in consideration of decommissioning

    International Nuclear Information System (INIS)

    Choi, Won Jun; Roh, Myung Sub; Kim, Chang Lak

    2017-01-01

    A new concept termed the Innovative Nuclear Power Plant Building Arrangement (INBA) strategy is a new nuclear power plant building arrangement method which encompasses upfront consideration of more efficient decommissioning. Although existing decommissioning strategies such as immediate dismantling and differed dismantling has the advantage of either early site restoration or radioactive decommissioning waste reduction, the INBA strategy has the advantages of both strategies. In this research paper, the concept and the implementation method of the INBA strategy will be described. Two primary benefits will be further described: (1) early site restoration; and (2) radioactive waste reduction. Several other potential benefits will also be identified. For the estimation of economic benefit, the INBA strategy, with two primary benefits, will be compared with the immediate dismantling strategy. The effect of a short life cycle nuclear power plant in combination with the INBA strategy will be reviewed. Finally, some of the major impediments to the realization of this strategy will be discussed

  4. Innovative nuclear power plant building arragement in consideration of decommissioning

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Won Jun; Roh, Myung Sub; Kim, Chang Lak [Dept. of Nuclear Power Plant Engineering, KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

    2017-04-15

    A new concept termed the Innovative Nuclear Power Plant Building Arrangement (INBA) strategy is a new nuclear power plant building arrangement method which encompasses upfront consideration of more efficient decommissioning. Although existing decommissioning strategies such as immediate dismantling and differed dismantling has the advantage of either early site restoration or radioactive decommissioning waste reduction, the INBA strategy has the advantages of both strategies. In this research paper, the concept and the implementation method of the INBA strategy will be described. Two primary benefits will be further described: (1) early site restoration; and (2) radioactive waste reduction. Several other potential benefits will also be identified. For the estimation of economic benefit, the INBA strategy, with two primary benefits, will be compared with the immediate dismantling strategy. The effect of a short life cycle nuclear power plant in combination with the INBA strategy will be reviewed. Finally, some of the major impediments to the realization of this strategy will be discussed.

  5. Innovative Nuclear Power Plant Building Arrangement in Consideration of Decommissioning

    Directory of Open Access Journals (Sweden)

    Won-Jun Choi

    2017-04-01

    Full Text Available A new concept termed the Innovative Nuclear Power Plant Building Arrangement (INBA strategy is a new nuclear power plant building arrangement method which encompasses upfront consideration of more efficient decommissioning. Although existing decommissioning strategies such as immediate dismantling and differed dismantling has the advantage of either early site restoration or radioactive decommissioning waste reduction, the INBA strategy has the advantages of both strategies. In this research paper, the concept and the implementation method of the INBA strategy will be described. Two primary benefits will be further described: (1 early site restoration; and (2 radioactive waste reduction. Several other potential benefits will also be identified. For the estimation of economic benefit, the INBA strategy, with two primary benefits, will be compared with the immediate dismantling strategy. The effect of a short life cycle nuclear power plant in combination with the INBA strategy will be reviewed. Finally, some of the major impediments to the realization of this strategy will be discussed.

  6. A study on the optimization of plant life extension and decommissioning for the improvement of economy in nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Shin, Jae In; Jung, K. J.; Chung, U. S.; Baik, S. T.; Park, S. K.; Lee, D. G.; Kim, H. R.; Park, B. Y

    2001-01-01

    Fundamental concepts on the life extension of the nuclear power plant and decommissioning optimization were established from the domestic abroad information and case analyses. Concerning the decommissioning of the nuclear power plant, the management according to decommissioning stages was analyzed by the investigation of the standard of the decommissioning(decontamination dismantling) regulation. Moreover, basics were set for the decommissioning of domestic nuclear power plants and research reactors from the analyses on the decommissioning technology and precedence.

  7. Nuclear power plants life extension and decommissioning its economic aspects

    International Nuclear Information System (INIS)

    Watanabe, Yoshiaki

    1994-06-01

    In USA where the development of nuclear power was started early, the life of nuclear power plants expires successively around the turn of century, and the serious hindrance to electric power supply is feared. Therefore, the research for extending 40 year approved period of operation is in progress. By the extension of life of nuclear power plants, huge cost reduction is estimated as compared with the construction of new plants. However, due to the rise of the cost for the life extension, there were the cases of forced decommissioning. In this book, the present state of the life extension of nuclear power stations, the economical assessment and analysis of the life extension by DOE, the economical assessment by MIDAS method of Electric Power Research Institute, the economical assessment by cost-benefit method of Northern States Power Co., the assessment of the long term operation possibility of nuclear power stations, the economical assessment system for the life extension in Japan, the present state of the decommissioning of nuclear power stations and that in USA, Canada and Europe, the assessment of the decommissioning cost by OECD/NEA, and the decommissioning cost for thermal power stations are described. (K.I.)

  8. BN-350 nuclear power plant. Regulatory aspects of decommissioning

    International Nuclear Information System (INIS)

    Shiganakov, S.; Zhantikin, T.; Kim, A.

    2002-01-01

    Full text: The BN-350 reactor is a fast breeder reactor using liquid sodium as a coolant [1]. This reactor was commissioned in 1973 and operated for its design life of 20 years. Thereafter, it was operated on the basis of annual licenses, and the final shutdown was initially planned in 2003. In 1999, however, the Government of the Republic of Kazakhstan adopted Decree on the Decommissioning of BN-350 Reactor. This Decree establishes the conception of the reactor plant decommissioning. The conception envisages three stages of decommissioning. The first stage of decommissioning aims at putting the installation into a state of long term safe enclosure. The main goal is an achievement of nuclear-and radiation-safe condition and industrial safety level. The completion criteria for the stage are as follows: spent fuel is removed and placed in long term storage; radioactive liquid metal coolant is drained from the reactor and processed; liquid and solid radioactive wastes are reprocessed and long-term stored; systems and equipment, that are decommissioned at the moment of reactor safe store, are disassembled; radiation monitoring of the reactor building and environment is provided. The completion criteria of the second stage are as follows: 50 years is up; a decision about beginning of works by realization of dismantling and burial design is accepted. The goal of the third stage is partial or total dismantling of equipment, buildings and structure and burial. Since the decision on the decommissioning of BN-350 Reactor Facility was accepted before end of scheduled service life (2003), to this moment 'The Decommissioning Plan' (which in Kazakhstan is called 'Design of BN-350 reactor Decommission') was not worked out. For realization of the Governmental Decree and for determination of activities by the reactor safety provision and for preparation of its decommission for the period till Design approval the following documents were developed: 1. Special Technical Requirements

  9. Technology and costs for decommissioning of Swedish nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-06-01

    The decommissioning study for the Swedish nuclear power plants has been carried out during 1992 to 1994 and the work has been led by a steering group consisting of people from the nuclear utilities and SKB. The study has been focused on two reference plants, Oskarshamn 3 and Ringhals 2. Oskarshamn 3 is a boiling water reactor (BWR) and Ringhals 2 is a pressurized water reactor (PWR). Subsequently, the result from these plants have been translated to the other Swedish plants. The study gives an account of the procedures, costs, waste quantities and occupational doses associated with decommissioning of the Swedish nuclear power plants. Dismantling is assumed to start immediately after removal of the spent fuel. No attempts at optimization, in terms of technology or costs, have been made. The nuclear power plant site is restored after decommissioning so that it can be released for use without restriction for other industrial activities. The study shows that a reactor can be dismantled in about five years, with an average labour force of about 150 persons. The maximum labour force required for Oskarshamn 3 has been estimated to about 300 persons. This peak load occurred the first years but is reduced to about 50 persons during the demolishing of the buildings. The cost of decommissioning Oskarshamn 3 has been estimated to be about MSEK 940 in January 1994 prices. The decommissioning of Ringhals 2 has been estimated to be MSEK 640. The costs for the other Swedish nuclear power plants lie in the range MSEK 590-960. 17 refs, 21 figs, 15 tabs.

  10. Technology and costs for decommissioning of Swedish nuclear power plants

    International Nuclear Information System (INIS)

    1994-06-01

    The decommissioning study for the Swedish nuclear power plants has been carried out during 1992 to 1994 and the work has been led by a steering group consisting of people from the nuclear utilities and SKB. The study has been focused on two reference plants, Oskarshamn 3 and Ringhals 2. Oskarshamn 3 is a boiling water reactor (BWR) and Ringhals 2 is a pressurized water reactor (PWR). Subsequently, the result from these plants have been translated to the other Swedish plants. The study gives an account of the procedures, costs, waste quantities and occupational doses associated with decommissioning of the Swedish nuclear power plants. Dismantling is assumed to start immediately after removal of the spent fuel. No attempts at optimization, in terms of technology or costs, have been made. The nuclear power plant site is restored after decommissioning so that it can be released for use without restriction for other industrial activities. The study shows that a reactor can be dismantled in about five years, with an average labour force of about 150 persons. The maximum labour force required for Oskarshamn 3 has been estimated to about 300 persons. This peak load occurred the first years but is reduced to about 50 persons during the demolishing of the buildings. The cost of decommissioning Oskarshamn 3 has been estimated to be about MSEK 940 in January 1994 prices. The decommissioning of Ringhals 2 has been estimated to be MSEK 640. The costs for the other Swedish nuclear power plants lie in the range MSEK 590-960. 17 refs, 21 figs, 15 tabs

  11. Decommissioning process of nuclear power plants and legislative base

    International Nuclear Information System (INIS)

    Bachovsky, J.

    2003-01-01

    The present paper contains some considerations about applicability and completeness of existing Regulation No. 10 in the field of decommissioning of nuclear power plants. No pretence exists for comprehensiveness, representativeness, or even applicability of these considerations. This paper presents personal views of the author and not official position of Risk Engineering Ltd

  12. Nuclear decommissioning

    International Nuclear Information System (INIS)

    Anon.

    1987-01-01

    The paper on nuclear decommissioning was presented by Dr H. Lawton to a meeting of the British Nuclear Energy Society and Institution of Nuclear Engineers, 1986. The decommissioning work currently being undertaken on the Windscale advanced gas cooled reactor (WAGR) is briefly described, along with projects in other countries, development work associated with the WAGR operation and costs. (U.K.)

  13. Decommissioning nuclear power plants: a case for external funding

    International Nuclear Information System (INIS)

    Hendren, C.B.

    1987-01-01

    In deciding how to finance the decommissioning of nuclear power plants, there are five basic criteria for choosing between internal and external funding methods: (1) the desire for financial assurance, (2) the cost of the assurance, (3) the degree of equity in the recovery program, (4) the program's ability to respond to changes, and (5) the program's adaptability to different utilities. To fulfill its obligations to protect long-term public interests, the Missouri Public Service Commission decided it had to assure, to the maximum extent possible, that sufficient decommissioning funds were available when needed. For this reason, it chose the external funding method. In an external fund, the money currently collected from ratepayers to cover decommissioning costs is placed in an independent trust fund comprised of low-risk investments. The funds and the interest they accrue are available to the utility only at the time of decommissioning (and only for that purpose), thus assuring a certain amount of money will be on-hand to cover decommissioning costs as they arise. Such a fund may prove critical to the financial well-being of the utility, particularly if one considers that the utility would need additional generating facilities to replace the capacity lost through the retirement of its nuclear plant. 3 references

  14. Technical and economic aspects of nuclear power plant decommissioning

    International Nuclear Information System (INIS)

    Glauberman, H.; Manion, W.J.

    1977-01-01

    Nuclear power plants may be decommissioned by one of three primary methods - mothballing, entombing, or dismantling, or by using combinations such as mothballing or entombing for a period of time followed by dismantling. Mothballing or entombing both result in an end-product which requires surveillance and maintenance for a significant period to ensure protection of public health and safety. This paper discusses costs for each of the decommissioning methods, including factors that will influence the method selected as well as the total costs. Decommissioning costs have been estimated for an 1100-MW(e) light-water reactor within one year after shutdown following forty years of operation. The basic economic parameters for each decommissioning method were developed using unit cost factors based on known costs of previously decommissioned reactors. Decommissioning cost estimates range from less than four million dollars for mothballing to about forty million dollars for complete dismantling. Estimated cost of entombment is about ten million dollars. Subsequent annual cost of surveillance and maintenance for a reactor facility using the mothballing or entombment method could be as high as US $200,000. Although some tooling development will be needed for removing highly activated reactor vessel segments and internals, technology is currently available and has been demonstrated on prior decommissionings, e.g. the BONUS and HALLUM reactor entombments and the Elk River Reactor complete dismantling. Costs associated with decommissioning are significant; however, allowance for them either as a one-time construction period sinking fund, or annual depreciation type operating allowance, will have little effect on construction or on operating costs. (author)

  15. Technical and economic aspects of nuclear power plant decommissioning

    International Nuclear Information System (INIS)

    Glauberman, H.; Manion, W.J.

    1977-01-01

    Nuclear power plants may be decommissioned by one of three primary methods, namely, mothballing, entombing, or dismantling or by using combinations such as mothballing or entombing for a period of time followed by dismantling. Mothballing or entombing both result in an end-product which require surveillance and maintenance for a significant period of time to ensure protection of public health and safety. This paper discusses costs for each of the decommissioning methods, including factors that will influence the method selected as well as the total costs. Decommissioning costs have been estimated for a 1100 MW(e) light water reactor within one year after shutdown following forty years of operation. The basic economic parameters for each decommissioning method were developed using unit cost factors based on known costs of previously decommissioned reactors. Decommissioning cost estimates range from less than four million dollars for mothballing to about forty million dollars for complete dismantling. Estimated cost of entombment is about ten million dollars. Subsequent annual cost of surveillance and maintenance for a reactor facility using the mothballing or entombment method could be as high as $200,000. Although some tooling development will be needed for the removal of the highly activated reactor vessel segments and internals, technology is currently available and has been demonstrated on prior decommissionings, e.g., the BONUS and HALLUM reactor entombments and the Elk River Reactor complete dismantling. Costs associated with decommissioning are significant; however, allowance for them either as a one-time construction period sinking fund or annual depreciation type operating allowance will have little impact on either construction or operating costs

  16. Recent Trends in the Adequacy of Nuclear Plant Decommissioning Funding

    International Nuclear Information System (INIS)

    Williams, D. G.

    2002-01-01

    Concerned about the potential cost and sufficiency of funds to decommission the nation's nuclear power plants, the Congress asked the U.S. General Accounting Office (GAO) to assess the adequacy, as of December 31, 1997, of electric utilities'; funds to eventually decommission their plants. GAO's report (GAO/RCED-99-75) on this issue addressed three alternative assumption scenarios--baseline (most likely), optimistic, and pessimistic; and was issued in May 1999. This paper updates GAO's baseline assessment of fund adequacy in 1997, and extends the analysis through 2000. In 2000, we estimate that the present value cost to decommission the nation's nuclear plants is about $35 billion; utility fund balances are about $29 billion. Both our two measures of funding adequacy for utilities are on average not only much above ideal levels, but also overall have greatly improved since 1997. However, certain utilities still show less than ideal fund balances and annual contributions. We suggest that the range of these results among the individual utilities is a more important policy measure to assess the adequacy of decommissioning funding than is the funding adequacy for the industry as a whole

  17. The decommissioning of the Barnwell nuclear fuel plant

    International Nuclear Information System (INIS)

    McNeil, J.

    1999-01-01

    The decommissioning of the Barnwell Nuclear Fuel Plant is nearing completion. The owner's objective is to terminate the plant radioactive material license associated with natural uranium and transuranic contamination at the plant. The property is being released for commercial-industrial uses, with radiation exposure from residual radioactivity not to exceed 0.15 millisieverts per year. Historical site assessments have been performed and the plant characterized for residual radioactivity. The decommissioning of the uranium hexafluoride building was completed in April, 1999. Most challenging from a radiological control standpoint is the laboratory building that contained sixteen labs with a total of 37 glove boxes, many of which had seen transuranics. Other facilities being decommissioned include the separations building and the 300,000-gallon underground high-level waste tanks. This decommissioning in many ways is the most significant project of this type yet undertaken in South Carolina. Many innovations have been made to reduce the time and costs associated with the project. (author)

  18. Technology and costs for decommissioning the Swedish nuclear power plants

    International Nuclear Information System (INIS)

    1986-05-01

    The study shows that, from the viewpoint of radiological safety, a nuclear power plant can be dismantled immediately after it has been shut down and the fuel has been removed, which is estimated to take about one year. Most of the equipment that will be used in decommissioning is already available and is used routinely in maintenance and rebuilding work at the nuclear power plants. Special equipment need only be developed for dismantlement of the reactor vessel and for demolishing of heavy concrete structures. The dismantling of a nuclear power plant can be accomplished in about five years, with an average labour force of about 200 men. The maximum labour force required for Ringhals 1 has been estimated at about 500 men during the first years, when active systems are being dismantled in a number of fronts in the plant. During the last years when the buildings are being demolished, approximately 50 men are required. In order to limit the labour requirement and the dose burden to the personnel, the material is taken out in as large pieces as possible. The cost of decommissioning a boiling water reactor (BWR) of the size of Ringhals 1 has been estimated to be about MSEK 540 in January 1986 prices, and for a pressurized water reactor (PWR, Ringhals 2) about MSEK 460. The cost for the other Swedish nuclear power plants lie in the range of MSEK 410-760. These are the direct cost for the decommissioning work, to which must be added the costs of transportation and disposal of the decommissioning waste, about 100 000 m/sup3/. These costs have been estimated to be about MSEK 600 for the 12 Swedish reactors. (author)

  19. Development of recycling techniques for nuclear power plant decommissioning waste

    International Nuclear Information System (INIS)

    Ishikura, Takeshi; Oguri, Daiichiro; Abe, Seiji; Ohnishi, Kazuhiko

    2003-01-01

    Recycling of concrete and metal waste will provide solution to reduce waste volume, contributing to save the natural resources and to protect the environment. Nuclear Power Engineering Corporation has developed techniques of concrete and metal recycling for decommissioning waste of commercial nuclear power plants. A process of radioactive concrete usage for mortar solidification was seen to reduce concrete waste volume by 2/3. A concrete reclamation process for high quality aggregate was confirmed that the reclaimed aggregate concrete is equivalent to ordinary concrete. Its byproduct powder was seen to be utilized various usage. A process of waste metal casting to use radioactive metal as filler could substantially decrease the waste metal volume when thinner containers are applied. A pyro-metallurgical separation process was seen to decrease cobalt concentration by 1/100. Some of these techniques are finished of demonstration tests for future decommissioning activity. (author)

  20. Methodology for cost estimate in projects for nuclear power plants decommissioning

    International Nuclear Information System (INIS)

    Salij, L.M.

    2008-01-01

    The conceptual approaches to cost estimating of nuclear power plants units decommissioning projects were determined. The international experience and national legislative and regulatory basis were analyzed. The possible decommissioning project cost classification was given. It was shown the role of project costs of nuclear power plant units decommissioning as the most important criterion for the main project decisions. The technical and economic estimation of deductions to common-branch fund of decommissioning projects financing was substantiated

  1. Planning for decommissioning of Ignalina Nuclear Power Plant Unit-1

    International Nuclear Information System (INIS)

    Poskas, P.; Poskas, R.; Zujus, R.

    2002-01-01

    In accordance to Ignalina NPP Unit 1 Closure Law, the Government of Lithuania approved the Ignalina NPP Unit 1 Decommissioning Program until 2005. For enforcement of this program, the plan of measures for implementation of the program was prepared and approved by the Minister of Economy. The plan consists of two parts, namely technical- environmental and social-economic. Technical-environmental measures are mostly oriented to the safe management of spent nuclear fuel and operational radioactive waste stored at the plant and preparation of licensing documents for Unit 1 decommissioning. Social-economic measures are oriented to mitigate the negative social and economic impact on Lithuania, inhabitants of the region, and, particularly, on the staff of Ignalina NPP by means of creating favorable conditions for a balanced social and economic development of the region. In this paper analysis of planned radioactive waste management technologies, licensing documents for decommissioning, other technical-environmental and also social-economic measures is presented. Specific conditions in Lithuania important for defining the decommissioning strategy are highlighted. (author)

  2. Selected problems of minimization and management of radioactive wastes from nuclear power plant decommissioning. Part 2

    International Nuclear Information System (INIS)

    Kyrs, M.; Moravec, A.

    1988-06-01

    The processing prior to storage of radioactive wastes produced in nuclear power plant decommissioning is described as are the types of containers employed for waste transport and/or disposal. Data are summarized on exposure of personnel to radioactivity resulting from nuclear power plant decommissioning activities, and accessible data are collected on the costs of nuclear power plant decommissioning and of waste management. Potential directions of research in this field under Czechoslovak conditions are specified. (author)

  3. A study on the optimization of plant life extension and decommissioning for the improvement of economy in nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Shin, Jae In; Jung, K. J.; Chung, U. S.; Baik, S. T.; Park, S. K.; Lee, D. G.; Kim, H. R.; Park, B. Y

    2000-01-01

    Fundamentals on the plan, the national policy, the safety securities for the life extension of the nuclear power plant was established from the domestic/abroad documents and case studies in relation with the life extension and decommissioning of the nuclear power plant. Concerning the decommissioning of the nuclear power plant, the management according to decommissioning stages was analyzed by the investigation of the domestic/abroad standard of the decommissioning (decontamination. dismantling) technology and regulation. Moreover, the study on the cost estimation method has been carried out for the decommissioning of the nuclear power plant. (author)

  4. Alternatives and costs for the decommissioning of Angra Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Carajilescov, Pedro; Moreira, Joao Manoel Losada; Maiorino, Jose Rubens, E-mail: pedro.carajilescov@ufabc.edu.br [Universidade Federal do ABC (UFABC), Santo Andre, SP (Brazil)

    2013-07-01

    The decommissioning of a nuclear reactor requires several actions involving legal basis, decommissioning strategies, planning, dismantling, packing, transport and storage of a large volume of radioactive materials, qualified personnel and financial resources. The paper discusses the several aspects of these actions for the decommissioning of Angra nuclear Power Plants, based on the international experiences. The main phases of the decommissioning process, the Brazilian regulation and cost estimations are also presented. Finally, two alternatives for the decommissioning of the plants, based on logistic aspects, are discussed. (author)

  5. Alternatives and costs for the decommissioning of Angra Nuclear Power Plants

    International Nuclear Information System (INIS)

    Carajilescov, Pedro; Moreira, Joao Manoel Losada; Maiorino, Jose Rubens

    2013-01-01

    The decommissioning of a nuclear reactor requires several actions involving legal basis, decommissioning strategies, planning, dismantling, packing, transport and storage of a large volume of radioactive materials, qualified personnel and financial resources. The paper discusses the several aspects of these actions for the decommissioning of Angra nuclear Power Plants, based on the international experiences. The main phases of the decommissioning process, the Brazilian regulation and cost estimations are also presented. Finally, two alternatives for the decommissioning of the plants, based on logistic aspects, are discussed. (author)

  6. Economic Evaluation of Decommissioning Cost of Nuclear Power Plant in the National Electricity Plan in Korea

    International Nuclear Information System (INIS)

    Lee, Man Ki; Nam, Ji Hee

    2008-01-01

    Decommissioning cost of a nuclear power plant includes the costs related with dismantling a nuclear power plant, disposal of a spent fuel and of a low/medium radioactive waste. The decommissioning cost is different from the other expenditures in that it is occurred after the reactor finishes its commercial operation. In this respect, the electricity act was enforced to secure provisions for decommissioning a nuclear power plant during its commercial operation. The purpose of this study is to provide economic evaluation and economic cost for a decommissioning when the cost of a decommissioning is provided as one of input to the national electricity plan. Therefore, this study does not deal with whether the estimated amount of a decommissioning cost is just or not. This study focuses how to transfer the estimated decommissioning cost given in the electricity act to the economic cost, which can be used in the national electricity plan

  7. The regulatory framework for safe decommissioning of nuclear power plants in Korea

    International Nuclear Information System (INIS)

    Sangmyeon Ahn; Jungjoon Lee; Chanwoo Jeong; Kyungwoo Choi

    2013-01-01

    We are having 23 units of nuclear power plants in operation and 5 units of nuclear power plants under construction in Korea as of September 2012. However, we don't have any experience on shutdown permanently and decommissioning of nuclear power plants. There are only two research reactors being decommissioned since 1997. It is realized that improvement of the regulatory framework for decommissioning of nuclear facilities has been emphasized constantly from the point of view of IAEA's safety standards. It is also known that IAEA will prepare the safety requirement on decommissioning of facilities; its title is the Safe Decommissioning of Facilities, General Safety Requirement Part 6. According to the result of IAEA's Integrated Regulatory Review Service (IRRS) mission to Korea in 2011, it was recommended that the regulatory framework should require decommissioning plans for nuclear installations to be constructed and operated and these plans should be updated periodically. In addition, after the Fukushima nuclear disaster in Japan in March of 2011, preparedness for early decommissioning caused by an unexpected severe accident became important issues and concerns. In this respect, it is acknowledged that the regulatory framework for decommissioning of nuclear facilities in Korea need to be improved. First of all, we focus on identifying the current status and relevant issues of regulatory framework for decommissioning of nuclear power plants compared to the IAEA's safety standards in order to achieve our goal. And then the plan is established for improvement of regulatory framework for decommissioning of nuclear power plants in Korea. It is expected that if the things will go forward as planned, the revised regulatory framework for decommissioning could enhance the safety regime on the decommissioning of nuclear power plants in Korea in light of international standards. (authors)

  8. The Community's research and development programme on decommissioning of nuclear power plants

    International Nuclear Information System (INIS)

    1982-01-01

    The programme, adopted by the Council of the European Communities, seeks to promote a number of research and development projects as well as the identification of guiding principles. The projects concern the following subjects: long-term integrity of buildings and systems; decontaminations for decommissioning purposes; dismantling techniques; treatment of specific waste materials (steel, concrete and graphite); large transport containers for radioactive waste arising from decommissioning of nuclear power plants in the Community; and influence of nuclear power plant design features on decommissioning

  9. Decommissioning of nuclear power plants and research reactors. Safety guide

    International Nuclear Information System (INIS)

    1999-01-01

    Radioactive waste is produced in the generation of nuclear power and the use of radioactive materials in industry, research and medicine. The importance of the safe management of radioactive waste for the protection of human health and the environment has long been recognized, and considerable experience has been gained in this field. The IAEA's Radioactive Waste Safety Standards Programme aimed at establishing a coherent and comprehensive set of principles and requirements for the safe management of waste and formulating the guidelines necessary for their application. This is accomplished within the IAEA Safety Standards Series in an internally consistent set of publications that reflect an international consensus. The publications will provide Member States with a comprehensive series of internationally agreed publications to assist in the derivation of, and to complement, national criteria, standards and practices. The Safety Standards Series consists of three categories of publications: Safety Fundamentals, Safety Requirements and Safety Guides. With respect to the Radioactive Waste Safety Standards Programme, the set of publications is currently undergoing review to ensure a harmonized approach throughout the Safety Standards Series. This Safety Guide addresses the subject of decommissioning of nuclear power plants and research reactors. It is intended to provide guidance to national authorities and operating organizations for the planning and safe management of the decommissioning of such installations. This Safety Guide has been prepared through a series of Consultants and Technical Committee meetings. It supersedes former Safety Series publications Nos 52, 74 and 105

  10. Decommissioning of nuclear power plants and research reactors. Safety guide

    International Nuclear Information System (INIS)

    2004-01-01

    Radioactive waste is produced in the generation of nuclear power and the use of radioactive materials in industry, research and medicine. The importance of the safe management of radioactive waste for the protection of human health and the environment has long been recognized, and considerable experience has been gained in this field. The IAEA's Radioactive Waste Safety Standards Programme aimed at establishing a coherent and comprehensive set of principles and requirements for the safe management of waste and formulating the guidelines necessary for their application. This is accomplished within the IAEA Safety Standards Series in an internally consistent set of publications that reflect an international consensus. The publications will provide Member States with a comprehensive series of internationally agreed publications to assist in the derivation of, and to complement, national criteria, standards and practices. The Safety Standards Series consists of three categories of publications: Safety Fundamentals, Safety Requirements and Safety Guides. With respect to the Radioactive Waste Safety Standards Programme, the set of publications is currently undergoing review to ensure a harmonized approach throughout the Safety Standards Series. This Safety Guide addresses the subject of decommissioning of nuclear power plants and research reactors. It is intended to provide guidance to national authorities and operating organizations for the planning and safe management of the decommissioning of such installations. This Safety Guide has been prepared through a series of Consultants and Technical Committee meetings. It supersedes former Safety Series publications Nos 52, 74 and 105

  11. Decommissioning of nuclear power plants and research reactors. Safety guide

    International Nuclear Information System (INIS)

    2001-01-01

    Radioactive waste is produced in the generation of nuclear power and the use of radioactive materials in industry, research and medicine. The importance of the safe management of radioactive waste for the protection of human health and the environment has long been recognized, and considerable experience has been gained in this field. The IAEA's Radioactive Waste Safety Standards Programme aimed at establishing a coherent and comprehensive set of principles and requirements for the safe management of waste and formulating the guidelines necessary for their application. This is accomplished within the IAEA Safety Standards Series in an internally consistent set of publications that reflect an international consensus. The publications will provide Member States with a comprehensive series of internationally agreed publications to assist in the derivation of, and to complement, national criteria, standards and practices. The Safety Standards Series consists of three categories of publications: Safety Fundamentals, Safety Requirements and Safety Guides. With respect to the Radioactive Waste Safety Standards Programme, the set of publications is currently undergoing review to ensure a harmonized approach throughout the Safety Standards Series. This Safety Guide addresses the subject of decommissioning of nuclear power plants and research reactors. It is intended to provide guidance to national authorities and operating organizations for the planning and safe management of the decommissioning of such installations. This Safety Guide has been prepared through a series of Consultants and Technical Committee meetings. It supersedes former Safety Series publications Nos 52, 74 and 105

  12. Design of a requirements system for decommissioning of a nuclear power plant based on systems engineering

    Energy Technology Data Exchange (ETDEWEB)

    Park, Hee Seong; Park, Seung Kook; Jin, Hyung Gon; Song, Chan Ho; Choi, Jong won [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    The nuclear industry has required an advanced system that can manage decommissioning information ever since the Korean government decide to decommission the Gori No.1 nuclear power plant. The D and D division at KAERI has been developing a system that can secure the reliability and sustainability of the decommissioning project based on the engineering system of the KRR-2 (Korean Research Reactor-2). To establish a decommissioning information system, a WBS that needs to be managed for the decommissioning of an NPP has been extracted, and requirements management research composed of system engineering technology has progressed. This paper propose a new type of system based on systems engineering technology. Even though a decommissioning engineering system was developed through the KRR-2, we are now developing an advanced decommissioning information system because it is not easy to apply this system to a commercial nuclear power plant. An NPP decommissioning is a project requiring a high degree of safety and economic feasibility. Therefore, we have to use a systematic project management at the initial phase of the decommissioning. An advanced system can manage the decommissioning information from preparation to remediation by applying a previous system to the systems engineering technology that has been widely used in large-scale government projects. The first phase of the system has progressed the requirements needed for a decommissioning project for a full life cycle. The defined requirements will be used in various types of documents during the decommissioning preparation phase.

  13. Decommissioning nuclear facilities

    International Nuclear Information System (INIS)

    Harmon, K.M.; Jenkins, C.E.; Waite, D.A.; Brooksbank, R.E.; Lunis, B.C.; Nemec, J.F.

    1976-01-01

    This paper describes the currently accepted alternatives for decommissioning retired light water reactor fuel cycle facilities and the current state of decommissioning technology. Three alternatives are recognized: Protective Storage; Entombment; and Dismantling. Application of these alternatives to the following types of facilities is briefly described: light water reactors; fuel reprocessing plants, and mixed oxide fuel fabrication plants. Brief descriptions are given of decommissioning operations and results at a number of sites, and recent studies of the future decommissioning of prototype fuel cycle facilities are reviewed. An overview is provided of the types of operations performed and tools used in common decontamination and decommissioning techniques and needs for improved technology are suggested. Planning for decommissioning a nuclear facility is dependent upon the maximum permitted levels of residual radioactive contamination. Proposed guides and recently developed methodology for development of site release criteria are reviewed. 21 fig, 32 references

  14. Research and development towards decommissioning of Fukushima Daiichi Nuclear Power Plants

    International Nuclear Information System (INIS)

    Minato, Kazuo

    2013-01-01

    Towards the decommissioning of Fukushima Daiichi Nuclear Power Plants, science-based research and development is important and useful, as well as technology and engineering development. Research and development activities based on radiation chemistry, radiochemistry, thermodynamics, etc., have contributed to safe and efficient decommissioning of the plants. (author)

  15. Ethical guidance in connection with decommissioning of nuclear power plants

    International Nuclear Information System (INIS)

    Braakenhielm, Carl Reinhold

    2006-01-01

    Decommissioning of nuclear plants is guided by three different moral obligations. There is, first, the obligation to collect and to preserve the financial, technical and scientific resources necessary for the future decommissioning of nuclear power plants. There is, secondly, the obligation of the responsible authorities in charge later in the present century to protect dismantling personnel, the general public and the environment from excessive risks and, particularly, harmful levels of radiation. And, thirdly, we in the present generation and the next one implementing different decommissioning programmes are morally responsible for doing it in such a way that future generations of human beings are protected. The main purpose of this paper is to discuss some ethical questions in connection with the third type of obligation. The author suggests some of the ethical principles involved. These principles are indirectly relevant for the other two obligations. Needless to say, one of the reasons for the collection and preservation of resources for D and D programmes in the first place is our obligation to protect future generations. How these resources are collected and preserved is primarily an entangled web of financial, technical and political issues - albeit that usual legal and ethical considerations apply. The main point of departure will be a paper delivered by Kenneth Arrow at the IEA World Congress in 1995, 'Inter-generational equity and the rate of discount in long-term social investment'. In this article Arrow discusses the ethical arguments for and against so-called 'pure time preference'. He concludes that the present generation has an obligation to protect future generations, but the present generation also has certain obligation towards itself. But how do we strike a proper balance between the obligation to ourselves and the obligations to future generations? This paper is designed to provide a tentative answer to this question. The argument of the author

  16. Cost effective decommissioning and dismantling of nuclear power plants

    International Nuclear Information System (INIS)

    Wasinger, Karl

    2012-01-01

    As for any large and complex project, the basis for cost effective decommissioning and dismantling of nuclear power plants is established with the development of the project. Just as its construction, dismantling of a nuclear power plant is similarly demanding. Daily changing situations due to the progress of construction - in the present case progress of dismantling - result in significant logistical challenges for project managers and site supervisors. This will be aggravated by the fact that a considerable amount of the removed parts are contaminated or even activated. Hence, not only occupational health, safety and environmental protection is to be assured, employees, public and environment are to be adequately protected against the adverse effect of radioactive radiation as well. Work progress and not least expenses involved with the undertaking depend on adherence to the planned course of actions. Probably the most frequent cause of deviation from originally planned durations and costs of a project are disruptions in the flow of work. For being enabled to counteract in a timely and efficient manner, all required activities are to be comprehensively captured with the initial planning. The effect initial activities may have on subsequent works until completion must particularly be investigated. This is the more important the larger and more complex the project actually are. Comprehensive knowledge of all the matters which may affect the progress of the works is required in order to set up a suitable work break-down structure; such work break-down structure being indispensable for successful control and monitoring of the project. In building the related organizational structure of the project, all such stakeholders not being direct part of the project team but which may potentially affect the progress of the project are to be considered as well. Cost effective and lost time injury free dismantling of decommissioned nuclear power plants is based on implementing

  17. An Intuitive Robot Teleoperation System for Nuclear Power Plant Decommissioning

    International Nuclear Information System (INIS)

    Lee, Chang-hyuk; Gu, Taehyeong; Lee, Kyung-min; Ye, Sung-Joon; Bang, Young-bong

    2017-01-01

    A robot teleoperation system consists of a master device and a slave robot. The master device senses human intention and delivers it to the salve robot. A haptic device and an exoskeletal robot are widely used as the master device. The slave robot carries out operations delivered by the master device. It should guarantee enough degree of freedom (DOF) to perform the instructed operation and mobility in the environment inside the nuclear plant, such as flat surfaces and stairs. A 7-DOF robotic arm is commonly used as the slave device. This paper proposed a robot teleoperation system for nuclear power plant decommissioning. It discussed an experiment that was performed to validate the system's usability. The operator wearing the exoskeletal master device at the master site controlled the slave robot enabling it to move on a flat surface, climb/descend stairs, and move obstacles. The proposed robot teleoperation system can also be used in hazardous working environments where the use of such robots would be beneficial to human health and safety. In the future, research studies on the protection against radiation that damages the slave robot should be conducted.

  18. Development of an integrated cost model for nuclear plant decommissioning

    International Nuclear Information System (INIS)

    Amos, G.; Roy, R.

    2003-01-01

    A need for an integrated cost estimating tool for nuclear decommissioning and associated waste processing and storage facilities for Intermediate Level Waste (ILW) was defined during the authors recent MSc studies. In order to close the defined gap a prototype tool was developed using logically derived CER's and cost driver variables. The challenge in developing this was to be able to produce a model that could produce realistic cost estimates from the limited levels of historic cost data that was available for analysis. The model is an excel based tool supported by 3 point risk estimating output and is suitable for producing estimates for strategic or optional cost estimates (±30%) early in the conceptual stage of a decommissioning project. The model was validated using minimal numbers of case studies supported by expert opinion discussion. The model provides an enhanced approach for integrated decommissioning estimates which will be produced concurrently with strategic options analysis on a nuclear site

  19. Safety problems in decommissioning of nuclear power plants

    International Nuclear Information System (INIS)

    1975-12-01

    The safety problems in decommissioning are presented by the example of light water reactors with an electric power of 1300 MW and 40 years of preceding specified operation. In such a plant the radioactivity in the form of activation and contamination is of the order of 10 7 Ci one year after final shut-down. The fuel elements are not taken into account. During the work at the reactor vessel dose rates of some 10 4 rem/h may occur at the flange level. According to a rough estimation the dose accumulated by the decommissioning personnel during dismantling of the radioactive components amounts to 1200 rem. During the decommissioning work the problems are caused predominantly by the direct radiation from the radioactive components and systems as well as from the release of radioactive particles, aerosols and liquids on cutting them up. In designing new plants the extent of later decommissioning problems can be reduced above all by selection of suitable materials and by decommissioning-minded design and arrangement of the components and parts of the plant. (orig./RW) [de

  20. Brazilian nuclear power plants decommissioning plan for a multiple reactor site

    Energy Technology Data Exchange (ETDEWEB)

    Monteiro, Deiglys B.; Moreira, Joao M.L.; Maiorino, Jose R., E-mail: deiglys.monteiro@ufabc.edu.br, E-mail: joao.moreira@ufabc.edu.br, E-mail: joserubens.maiorino@ufabc.edu.br [Universidade Federal do ABC (CECS/UFABC), Santo Andre, SP (Brazil). Centro de Engenharia, Modelagem e Ciencias Aplicadas. Programa de Pos-Graduacao em Energia e Engenharia da Energia

    2015-07-01

    Actually, Brazil has two operating Nuclear Power Plants and a third one under construction, all at Central Nuclear Almirante Alvaro Alberto - CNAAA. To comply with regulatory aspects the power plants operator, Eletronuclear, must present to Brazilian Nuclear Regulatory Agency, CNEN, a decommissioning plan. Brazilian experience with decommissioning is limited because none of any nuclear reactor at the country was decommissioned. In literature, decommissioning process is well described despite few nuclear power reactors have been decommissioned around the world. Some different approach is desirable for multiple reactors sites, case of CNAAA site. During the decommissioning, a great amount of wastes will be produced and have to be properly managed. Particularly, the construction of Auxiliary Services on the site could be a good choice due to the possibility of reducing costs. The present work intends to present to the Eletronuclear some aspects of the decommissioning concept and decommissioning management, storage and disposal de wastes, based on the available literature, regulatory standards of CNEN and international experience as well as to suggest some solutions to be implemented at CNAAA site before starts the decommissioning project in order to maximize the benefits. (author)

  1. Brazilian nuclear power plants decommissioning plan for a multiple reactor site

    International Nuclear Information System (INIS)

    Monteiro, Deiglys B.; Moreira, Joao M.L.; Maiorino, Jose R.

    2015-01-01

    Actually, Brazil has two operating Nuclear Power Plants and a third one under construction, all at Central Nuclear Almirante Alvaro Alberto - CNAAA. To comply with regulatory aspects the power plants operator, Eletronuclear, must present to Brazilian Nuclear Regulatory Agency, CNEN, a decommissioning plan. Brazilian experience with decommissioning is limited because none of any nuclear reactor at the country was decommissioned. In literature, decommissioning process is well described despite few nuclear power reactors have been decommissioned around the world. Some different approach is desirable for multiple reactors sites, case of CNAAA site. During the decommissioning, a great amount of wastes will be produced and have to be properly managed. Particularly, the construction of Auxiliary Services on the site could be a good choice due to the possibility of reducing costs. The present work intends to present to the Eletronuclear some aspects of the decommissioning concept and decommissioning management, storage and disposal de wastes, based on the available literature, regulatory standards of CNEN and international experience as well as to suggest some solutions to be implemented at CNAAA site before starts the decommissioning project in order to maximize the benefits. (author)

  2. Conceptual basic and status of nuclear power plant decommissioning effort in the Russian Federation

    International Nuclear Information System (INIS)

    Glazounov, V.; Khamyanov, L.

    1998-01-01

    Decommissioning of nuclear power plants, although a usual phase in nuclear facility life cycle still has significant peculiarities due to radioactive contamination of NPP equipment and structural elements. This paper deals with the phases in decommissioning process, as follows: NPP shutdown, meaning end of commercial operation; NPP unit mothballing, radiation review of the unit to justify particular concept of decommissioning; extended hold-up, which means maintaining of contaminated equipment in the isolated zone under radiologically safe conditions; unit dismantling and burial. Status of NPP decommissioning effort in Russia is described

  3. The decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Niel, J.Ch.; Rieu, J.; Lareynie, O.; Delrive, L.; Vallet, J.; Girard, A.; Duthe, M.; Lecomte, C.; Rozain, J.P.; Nokhamzon, J.G.; Davoust, M.; Eyraud, J.L.; Bernet, Ph.; Velon, M.; Gay, A.; Charles, Th.; Leschaeva, M.; Dutzer, M.; Maocec, Ch.; Gillet, G.; Brut, F.; Dieulot, M.; Thuillier, D.; Tournebize, F.; Fontaine, V.; Goursaud, V.; Birot, M.; Le Bourdonnec, Th.; Batandjieva, B.; Theis, St.; Walker, St.; Rosett, M.; Cameron, C.; Boyd, A.; Aguilar, M.; Brownell, H.; Manson, P.; Walthery, R.; Wan Laer, W.; Lewandowski, P.; Dorms, B.; Reusen, N.; Bardelay, J.; Damette, G.; Francois, P.; Eimer, M.; Tadjeddine, A.; Sene, M.; Sene, R.

    2008-01-01

    This file includes five parts: the first part is devoted to the strategies of the different operators and includes the following files: the decommissioning of nuclear facilities Asn point of view, decommissioning of secret nuclear facilities, decommissioning at the civil Cea strategy and programs, EDF de-construction strategy, Areva strategy for decommissioning of nuclear facilities; the second one concerns the stakes of dismantling and includes the articles as follow: complete cleanup of buildings structures in nuclear facilities, decommissioning of nuclear facilities and safety assessment, decommissioning wastes management issues, securing the financing of long-term decommissioning and waste management costs, organizational and human factors in decommissioning projects, training for the decommissioning professions: the example of the Grenoble University master degree; the third part is devoted to the management of dismantling work sites and includes the different articles as follow: decommissioning progress at S.I.C.N. plant, example of decommissioning work site in Cea Grenoble: Siloette reactor decommissioning, matters related to decommissioning sites, decommissioning of french nuclear installations: the viewpoint of a specialist company, specificities of inspections during decommissioning: the Asn inspector point of view; the fourth part is in relation with the international approach and includes as follow: IAEA role in establishing a global safety regime on decommissioning, towards harmonization of nuclear safety practices in Europe: W.E.N.R.A. and the decommissioning of nuclear facilities, EPA superfund program policy for decontamination and decommissioning, progress with remediation at Sellafield, progress and experiences from the decommissioning of the Eurochemic reprocessing plant in Belgium, activities of I.R.S.N. and its daughter company Risk-audit I.r.s.n./G.r.s. international in the field of decommissioning of nuclear facilities in eastern countries

  4. United States nuclear regulatory commission program for inspection of decommissioning nuclear power plants

    International Nuclear Information System (INIS)

    Harris, P.W.

    2001-01-01

    The United States Nuclear Regulatory Commission (USNRC or Commission) has been inspecting decommissioning commercial nuclear power plants in the United States (U.S.) since the first such facility permanently shutdown in September 1967. Decommissioning inspections have principally focused on the safe storage and maintenance of spent reactor fuel; occupational radiation exposure; environmental radiological releases; the dismantlement and decontamination of structures, systems, and components identified to contain or potentially contain licensed radioactive material; and the performance of final radiological survey of the site and remaining structures to support termination of the USNRC-issued operating license. Over the last 5 years, USNRC inspection effort in these areas has been assessed and found to provide reasonable confidence that decommissioning can be conducted safely and in accordance with Commission rules and regulations. Recently, the staff has achieved a better understanding of the risks associated with particular decommissioning accidents 1 and plans to apply these insights to amendments proposed to enhance decommissioning rules and regulations. The probabilities, scenarios, and conclusions resulting from this effort are being assessed as to their applicability to the inspection of decommissioning commercial power reactors. (author)

  5. United States nuclear regulatory commission program for inspection of decommissioning nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Harris, P.W. [U.S. Nuclear Regulatory Commission, Washington, DC (United States)

    2001-07-01

    The United States Nuclear Regulatory Commission (USNRC or Commission) has been inspecting decommissioning commercial nuclear power plants in the United States (U.S.) since the first such facility permanently shutdown in September 1967. Decommissioning inspections have principally focused on the safe storage and maintenance of spent reactor fuel; occupational radiation exposure; environmental radiological releases; the dismantlement and decontamination of structures, systems, and components identified to contain or potentially contain licensed radioactive material; and the performance of final radiological survey of the site and remaining structures to support termination of the USNRC-issued operating license. Over the last 5 years, USNRC inspection effort in these areas has been assessed and found to provide reasonable confidence that decommissioning can be conducted safely and in accordance with Commission rules and regulations. Recently, the staff has achieved a better understanding of the risks associated with particular decommissioning accidents 1 and plans to apply these insights to amendments proposed to enhance decommissioning rules and regulations. The probabilities, scenarios, and conclusions resulting from this effort are being assessed as to their applicability to the inspection of decommissioning commercial power reactors. (author)

  6. Engineering and planning for decommissioning of nuclear power plants

    International Nuclear Information System (INIS)

    Gans, G.M. Jr.

    1982-01-01

    With the publication of NUREG-0586, ''Draft Generic Environmental Impact Statement on Decommissioning of Nuclear Facilities'' in January, 1981 the Nuclear Regulatory Commission staff has put the industry on notice that the termination of operating licenses and the final disposal of physical facilities will require the early consideration of several options and approaches and the preparation of comprehensive engineering and planning documents for the selected option at the end of useful life. This paper opens with a discussion of the options available and the principal aspects of decommissioning. The major emphasis of the composition is the nature of documents, the general approach to be followed, and special considerations to be taken into account when performing the detailed engineering and planning for decommissioning, as the end of life approaches and actual physical disposal is imminent. The author's main point of reference is on-going work by Burns and Roe, with Nuclear Energy Services, under contract to the Department of Energy's Richland Office, to perform the engineering and planning for the decommissioning of the Shippingport Atomic Power Station in Pennsylvania

  7. The Communities' research and development programme on decommissioning of nuclear power plants

    International Nuclear Information System (INIS)

    1981-01-01

    This is the first progress report of the European Community's programme (1979-1983) of research on the decommissioning of nuclear power plants. It shows the status of the programme on 31 December 1980. The programme seeks to promote a number of research and development projects as well as the identification of guiding principles. The projects concern the following subjects: long-term integrity of buildings and systems; decontamination for decommissioning purposes; dismantling techniques; treatment of specific waste materials: steel, concrete and graphite; large transport containers for radioactive was produced in the dismantling of nuclear power plants; estimation of the quantities of radioactive wastes arising from decommissioning of nuclear power plants in the Community; influence of nuclear power plant design features on decommissioning

  8. Nuclear decommissioning and society

    International Nuclear Information System (INIS)

    Pasqualetti, M.J.

    1990-01-01

    Links between decommissioning in general, reactor decommissioning in particular, and the public are indexed. The established links are recognised and others, such as jobs, are discussed. Finally the links with policy, such as political geography, and wider issues of the environment and public concern over waste disposal are considered. Decommissioning is a relatively new field where public opinion must now be considered but it has implications both for existing nuclear power plants and those planned for the future, especially in their siting. This book looks especially at the situation in the United Kingdom. There are twelve papers, all indexed separately. (UK)

  9. Decommissioning nuclear facilities

    International Nuclear Information System (INIS)

    Buck, S.

    1996-01-01

    Nuclear facilities present a number of problems at the end of their working lives. They require dismantling and removal but public and environmental protection remain a priority. The principles and strategies are outlined. Experience of decommissioning in France and the U.K. had touched every major stage of the fuel cycle by the early 1990's. Decommissioning projects attempt to restrict waste production and proliferation as waste treatment and disposal are costly. It is concluded that technical means exist to deal with present civil plant and costs are now predictable. Strategies for decommissioning and future financial provisions are important. (UK)

  10. Situation and perspective of the decommissioning of nuclear power plants in Germany

    International Nuclear Information System (INIS)

    Kuroda, Yuji

    2012-01-01

    After the Fukushima Daiichi nuclear power plant accident that occurred in 2011, Germany has decided to go back to the phasing out of nuclear energy, with eight reactors shut down. In accordance with this, the number of operating nuclear plants has reduced to 9 from 17. On the other hand, the number of closed reactors is now 27, and the country has become the world's third largest country after the United Kingdom and the United States in the decommissioning field. In this paper, it is described the current situation and perspectives of the decommissioning in Germany, with the history of phasing out of nuclear energy. At first, the basic framework of regulatory regime and funding system are introduced. Then, experience of operations at decommissioning plants and status of radiation waste management are explained. Although the work on decommissioning is steadily proceeding in the country, establishing of final repository of high level waste is still remaining as the most important issue. (author)

  11. Decommissioning strategy and schedule for a multiple reactor nuclear power plant site

    Energy Technology Data Exchange (ETDEWEB)

    Monteiro, Deiglys Borges; Moreira, Joao M.L.; Maiorino, Jose Rubens, E-mail: deiglys.monteiro@ufabc.edu.br, E-mail: joao.moreira@ufabc.edu.br, E-mail: joserubens.maiorino@ufabc.edu.br [Universidade Federal do ABC (CECS/UFABC), Santo Andre, SP (Brazil). Centro de Engenharia, Modelagem e Ciencias Aplicadas

    2015-07-01

    The decommissioning is an important part of every Nuclear Power Plant life cycle gaining importance when there are more than one plant at the same site due to interactions that can arise from the operational ones and a decommissioning plant. In order to prevent undesirable problems, a suitable strategy and a very rigorous schedule should implemented and carried. In this way, decommissioning tasks such as fully decontamination and dismantling of activated and contaminated systems, rooms and structures could be delayed, posing as an interesting option to multiple reactor sites. The present work aims to purpose a strategy and a schedule for the decommissioning of a multiple reactor site highlighting the benefits of delay operational tasks and constructs some auxiliary services in the site during the stand by period of the shutdown plants. As a case study, will be presented a three-reactor site which the decommissioning process actually is in planning stage and that should start in the next decade. (author)

  12. Decommissioning strategy and schedule for a multiple reactor nuclear power plant site

    International Nuclear Information System (INIS)

    Monteiro, Deiglys Borges; Moreira, Joao M.L.; Maiorino, Jose Rubens

    2015-01-01

    The decommissioning is an important part of every Nuclear Power Plant life cycle gaining importance when there are more than one plant at the same site due to interactions that can arise from the operational ones and a decommissioning plant. In order to prevent undesirable problems, a suitable strategy and a very rigorous schedule should implemented and carried. In this way, decommissioning tasks such as fully decontamination and dismantling of activated and contaminated systems, rooms and structures could be delayed, posing as an interesting option to multiple reactor sites. The present work aims to purpose a strategy and a schedule for the decommissioning of a multiple reactor site highlighting the benefits of delay operational tasks and constructs some auxiliary services in the site during the stand by period of the shutdown plants. As a case study, will be presented a three-reactor site which the decommissioning process actually is in planning stage and that should start in the next decade. (author)

  13. 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

  14. A Human Factors Study on an Information Visualization System for Nuclear Power Plants Decommissioning Engineering

    Energy Technology Data Exchange (ETDEWEB)

    Yang, Chih Wei; Yang, Li Chen [Institute of Nuclear Energy Research, Atomic Energy Council, Longtan (China)

    2014-08-15

    Most nuclear power plants (NPPs) in the world have an operating life of up to 40 years. The utility should prepare a comprehensive decommissioning plan with purpose to document and to display how decommissioning activities can be safely performed. In the past, most studies related to NPPs decommissioning planning put emphasis on technical issues, little attention have been given to human factors in decommissioning activities. In fact, human factors are a critical factor to successful NPPs decommissioning. NPPs decommissioning will face potential risks. These risks include not only dismantling and moving large equipment but also treating with the radioactive materials. Using information visualization system, such as virtual reality (VR) technology, for staff training can improve decommissioning work safety and economy. Therefore, this study presents a study using VR to solve real world problems in the nuclear plant decommissioning. Then appropriate cases for introducing VR systems are summarized and future prospects are given. This study assesses availability and performance of the work training system by using heuristic evaluation and actual experiment. In the result, block type of radiation visibility was found relatively better both in performance and person's preference than other types. The results presented in this paper illustrate the VR applications a NPP decommissioning perspective.

  15. A Human Factors Study on an Information Visualization System for Nuclear Power Plants Decommissioning Engineering

    International Nuclear Information System (INIS)

    Yang, Chih Wei; Yang, Li Chen

    2014-01-01

    Most nuclear power plants (NPPs) in the world have an operating life of up to 40 years. The utility should prepare a comprehensive decommissioning plan with purpose to document and to display how decommissioning activities can be safely performed. In the past, most studies related to NPPs decommissioning planning put emphasis on technical issues, little attention have been given to human factors in decommissioning activities. In fact, human factors are a critical factor to successful NPPs decommissioning. NPPs decommissioning will face potential risks. These risks include not only dismantling and moving large equipment but also treating with the radioactive materials. Using information visualization system, such as virtual reality (VR) technology, for staff training can improve decommissioning work safety and economy. Therefore, this study presents a study using VR to solve real world problems in the nuclear plant decommissioning. Then appropriate cases for introducing VR systems are summarized and future prospects are given. This study assesses availability and performance of the work training system by using heuristic evaluation and actual experiment. In the result, block type of radiation visibility was found relatively better both in performance and person's preference than other types. The results presented in this paper illustrate the VR applications a NPP decommissioning perspective

  16. Environmental Audit. A vital part of decommissioning nuclear plants

    International Nuclear Information System (INIS)

    Perry, T.E.; Dutton, L.M.

    1998-01-01

    NNC has undertaken an environmental audit of the Hunterston A nuclear power station in Scotland. The station has closed and is now in the process of being decommissioned. The purpose of the environmental audit was to ensure that the environmental risks and potential liabilities, particularly those related to non-radioactive issues, were adequately identified and managed. The background, methodology and principal findings of the audit are described. (author)

  17. Stade. Decommissioning and dismantling of the nuclear power plant - from the nuclear power plant to the green lawn. 3. ed.

    International Nuclear Information System (INIS)

    2008-01-01

    The nuclear power plant Stade (KKS) was shutdown in 2003 and is being dismantled since 2005. The contribution covers the following issues: What means decommissioning and dismantling? What was the reason for decommissioning? What experiences on the dismantling of nuclear power plants are available? What is the dismantling procedure? What challenges for the power plant personal result from dismantling? What happens with the deconstruction material? What happens with the resulting free area (the ''green lawn'')? What is the legal frame work for dismantling?

  18. The European community's programme of research on the decommissioning of nuclear power plants: objectives, scope and implementation

    International Nuclear Information System (INIS)

    Huber, B.

    1984-01-01

    The European Community's research activities on the decommissioning of nuclear installations are aimed at developing effective techniques and procedures for ensuring the protection of man and his environment against the potential hazards from nuclear installations that have been withdrawn from service. The first five-year (1979-1983) programme of research on the decommissioning of nuclear power plants has comprised seven R and D projects concerning the following areas: maintaining disused plants in safe condition; surface decontamination for decommissioning purposes; dismantling techniques; treatment of the main waste materials arising in decommissioning, i.e. steel, concrete and graphite; large containers for decommissioning waste; arisings and characteristics of decommissioning waste; plant design features facilitating decommissioning. The research work was carried out by organizations and companies in the Member States under 51 research contracts, most of them cost-sharing. The Commission is now launching a new five-year (1984-1988) programme of research on the decommissioning of nuclear installations. (author)

  19. License stewardship and other approaches to commercial nuclear power plant decommissioning

    International Nuclear Information System (INIS)

    Daly, P.T.; Moloney, B.P.

    2011-01-01

    This paper addresses the challenge of how our industry could arrange itself to deliver decommissioning of Nuclear Power Plants (NPPs) safely, in good time and affordably. There is a growing wealth of experience across the world in safe decommissioning techniques. Most - arguably all - of the techniques required to perform the full decommissioning of NPPs have been demonstrated on full-scale projects. Waste processing and disposal challenges remain in many countries, where the major issues are societal acceptance and political will. Interim storage possibilities have been identified in most countries. In decommissioning, the outstanding significant issues lie now in the domain of affordability and risk management. This paper will illustrate approaches to decommissioning with examples from the US and UK, to explore how the industry can achieve configurations to deliver lower risk and improved affordability for utilities. Different configurations, or models, will be used to illustrate the approaches taken. (orig.)

  20. Stakeholder involvement in the decommissioning of Trojan and Maine Yankee nuclear power plants

    International Nuclear Information System (INIS)

    Watson, Bruce A.; Orlando, Dominick A.

    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 the decommissioning planning, the conduct of decommissioning operations, the volume of low-level radioactive waste, 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 its 10 CFR Part 50 license. Maine Yankee elected to reduce the 10 CFR Part 50 license to only the requirements for the ISFSI. 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, stakeholder and public input resulted in the licensee entering into an agreement with a citizen group and resulted in State legislation that lowered the dose limit below the NRC radiological criteria of 0.25 milli-Sievert/year (mSv/yr) (25 mrem/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) that were well below the NRC DCGL screening values. This contributed to

  1. Decommissioning nuclear installations

    International Nuclear Information System (INIS)

    Dadoumont, J.

    2010-01-01

    When a nuclear installation is permanently shut down, it is crucial to completely dismantle and decontaminate it on account of radiological safety. The expertise that SCK-CEN has built up in the decommissioning operation of its own BR3 reactor is now available nationally and internationally. Last year SCK-CEN played an important role in the newly started dismantling and decontamination of the MOX plant (Mixed Oxide) of Belgonucleaire in Dessel, and the decommissioning of the university research reactor Thetis in Ghent.

  2. Decommissioning of units 1 - 4 at Kozloduy nuclear power plant in Bulgaria

    International Nuclear Information System (INIS)

    Dishkova, Denitsa

    2014-01-01

    Nuclear safety and security are absolute priorities for the European Union countries and this applies not only to nuclear power plants in operation but also to decommissioning. In terms of my technical background and my working experience in the field of licensing and environmental impact assessment during the decommissioning of Units 1 to 4 at Kozloduy Nuclear Power Plant (KNPP) in Bulgaria, I decided to present the strategy for decommissioning of Units 1 to 4 at KNPP which was selected and followed to achieve safe and effective decommissioning process. The selected strategy in each case must meet the legislative framework, to ensure safe management of spent fuel and radioactive waste, to provide adequate funding and to lead to positive socio-economic impact. The activities during the decommissioning generate large volume of waste. In order to minimize their costs and environmental impact it should be given a serious consideration to the choice, the development and the implementation of the most adequate process for treatment and the most appropriate measurement techniques. The licensing process of the decommissioning activities is extremely important and need to cope with all safety concerns and ensure optimal waste management. (authors)

  3. Electricite de France Strategy for its nuclear power plants' decommissioning programme

    International Nuclear Information System (INIS)

    Knockaert, J.M.; Gatineau, J.P.

    1992-01-01

    Although final shutdown of the first large PWR Power Stations should not occur before 2015, Electricity of France is nevertheless directly concerned by the decommissioning of its nuclear plants. The shutdown programme of the gas-graphite units is in progress and the medium-power PWR plant (300 MWe) installed at Chooz in the Ardennes will be finally shutdown at the end of 1991. This solution requires EDF to have a policy available which enables it to simultaneously run the double operation 'Plant shutdown-decommissioning' and 'New constructions-increasing available power' from both the technical and financial viewpoints. (author)

  4. Technology, safety, and costs of decommissioning a reference nuclear fuel reprocessing plant

    International Nuclear Information System (INIS)

    Schneider, K.J.; Jenkins, C.E.; Rhoads, R.E.

    1977-09-01

    Safety and cost information were developed for the conceptual decommissioning of a fuel reprocessing plant with characteristics similar to the Barnwell Nuclear Fuel Plant. The main process building, spent fuel receiving and storage station, liquid radioactive waste storage tank system, and a conceptual high-level waste-solidification facility were postulated to be decommissioned. The plant was conceptually decommissioned to three decommissioning states or modes; layaway, protective storage, and dismantlement. Assuming favorable work performance, the elapsed time required to perform the decommissioning work in each mode following plant shutdown was estimated to be 2.4 years for layaway, 2.7 years for protective storage, and 5.2 years for dismantlement. In addition to these times, approximately 2 years of planning and preparation are required before plant shutdown. Costs, in constant 1975 dollars, for decommissioning were estimated to be $18 million for layaway, $19 million for protective storage and $58 million for dismantlement. Maintenance and surveillance costs were estimated to be $680,000 per year after layaway and $140,000 per year after protective storage. The combination mode of protective storage followed by dismantlement deferred for 10, 30, and 100 years was estimated to cost $64 million, $67 million and $77 million, respectively, in nondiscounted total 1975 dollars. Present values of these costs give reduced costs as dismantlement is deferred. Safety analyses indicate that radiological and nonradiological safety impacts from decommissioning activities should be small. The 50-year radiation dose commitment to the members of the public from airborne releases from normal decommissioning activities were estimated to be less than 11 man-rem

  5. Technology, safety, and costs of decommissioning a reference nuclear fuel reprocessing plant

    Energy Technology Data Exchange (ETDEWEB)

    Schneider, K.J.; Jenkins, C.E.; Rhoads, R.E.

    1977-09-01

    Safety and cost information were developed for the conceptual decommissioning of a fuel reprocessing plant with characteristics similar to the Barnwell Nuclear Fuel Plant. The main process building, spent fuel receiving and storage station, liquid radioactive waste storage tank system, and a conceptual high-level waste-solidification facility were postulated to be decommissioned. The plant was conceptually decommissioned to three decommissioning states or modes; layaway, protective storage, and dismantlement. Assuming favorable work performance, the elapsed time required to perform the decommissioning work in each mode following plant shutdown was estimated to be 2.4 years for layaway, 2.7 years for protective storage, and 5.2 years for dismantlement. In addition to these times, approximately 2 years of planning and preparation are required before plant shutdown. Costs, in constant 1975 dollars, for decommissioning were estimated to be $18 million for layaway, $19 million for protective storage and $58 million for dismantlement. Maintenance and surveillance costs were estimated to be $680,000 per year after layaway and $140,000 per year after protective storage. The combination mode of protective storage followed by dismantlement deferred for 10, 30, and 100 years was estimated to cost $64 million, $67 million and $77 million, respectively, in nondiscounted total 1975 dollars. Present values of these costs give reduced costs as dismantlement is deferred. Safety analyses indicate that radiological and nonradiological safety impacts from decommissioning activities should be small. The 50-year radiation dose commitment to the members of the public from airborne releases from normal decommissioning activities were estimated to be less than 11 man-rem.

  6. Study on the Operating Strategy of HVAC Systems for Nuclear Decommissioning Plant

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Sung-hwan; Han, Sung-heum; Lee, Jae-gon [KHNP CRI, Daejeon (Korea, Republic of)

    2016-10-15

    According as Kori nuclear power plant unit 1 was determined to be defueled in 2017, various studies on nuclear plant decommissioning have been performed. In nuclear decommissioning plant, HVAC systems with large fan and electric coil have to be operated for long periods of time to support various types of work from defueled phase to final dismantling phase. So, in view of safety and utility costs, their overall operating strategy need to be established prior to defueled phase. This study presents HVAC system operating strategy at each decommissioning phase, that is, defueled plant operating phase, SSCs(systems, structures, components) decontamination and dismantling phases. In defueled plant operating phase, all fuel assemblies in reactor vessel are transferred to spent fuel pool(SFP) permanently. In defueled plant operation phase, reduction of the operating system trains is more practicable than the introduction of new HVAC components with reduced capacity. And, based on the result of the accident analyses for this phase, HVAC design bases such as MCR habitability requirement can be mitigated. According to these results, associated SSCs also can be downgraded. In similar approach, at each phase of plant decommissioning, proper inside design conditions and operating strategies should be re-established.

  7. Safe and effective nuclear power plant life cycle management towards decommissioning

    International Nuclear Information System (INIS)

    2002-08-01

    The objective of this publication is to promote and communicate the need for a longer-term perspective among senior managers and policy or strategy makers for decisions that have the potential to affect the life cycle management of a nuclear power plant including decommissioning. The following sections provide practical guidance in the subject areas that might have the potential to have such an impact. The publication should be used as an aid to help strategic planning take place in an informed way through the proper consideration of any longer-term decisions to enforce recognition of the point that decommissioning is a part of the whole life cycle of a nuclear power plant. The guidance contained in this publication is relevant to all life cycle stages of a nuclear power plant, with particular emphasis on how these decisions have the potential to impact effective decommissioning. The intended users of this publication are: Strategic decision makers within a Utility through all the various life cycle stages; The senior representatives of the owners of a nuclear power plant. This publication is divided into two basic sections. Section 2 provides guidance on the topics considered generic inputs to plant life cycle management and Section 3 provides guidance on the topics that contribute to effective decommissioning

  8. Decommissioning of nuclear power stations

    International Nuclear Information System (INIS)

    Gregory, A.R.

    1988-01-01

    In the United Kingdom the Electricity Boards, the United Kingdom Atomic Energy Authority (UKAEA) and BNFL cooperate on all matters relating to the decommissioning of nuclear plant. The Central Electricity Generating Board's (CEGB) policy endorses the continuing need for nuclear power, the principle of reusing existing sites where possible and the building up of sufficient funds during the operating life of a nuclear power station to meet the cost of its complete clearance in the future. The safety of the plant is the responsibility of the licensee even in the decommissioning phase. The CEGB has carried out decommissioning studies on Magnox stations in general and Bradwell and Berkeley in particular. It has also been involved in the UKAEA Windscale AGR decommissioning programme. The options as to which stage to decommission to are considered. Methods, costs and waste management are also considered. (U.K.)

  9. Nuclear power plant decommissioning and radioactive waste management in the U.K.. A regulatory perspective

    International Nuclear Information System (INIS)

    Ross, W.M.

    1993-01-01

    Effective control of the decommissioning and radioactive waste management of nuclear power plant in United Kingdom are introduced. The Government established the legislative framework and national strategy, operators provided the necessary skills and equipment for implementation, and the regulators used the legislative controls to ensure a safe system of work is achieved and maintained

  10. Financing strategies for nuclear power plant decommissioning. Report for July 1979-July 1980

    International Nuclear Information System (INIS)

    1980-07-01

    The report analyzes several alternatives for financing the decommissioning of nuclear power plants from the point of view of assurance, cost, equity, and other criteria. Sensitivity analyses are performed on several important variables and possible impacts on representative companies' rates are discussed and illustrated

  11. Financial and accounting alternatives for the recovery of nuclear plant decommissioning costs

    International Nuclear Information System (INIS)

    Collins, P.A.

    1980-01-01

    Compared are 12 different methods of financing the decommissioning of nuclear power plants. The basic financing alternatives are presented first in their simple version where income taxes are zero. Then the effects of the present income tax laws are added and their effect determined

  12. Dismantling and decommissioning of Jose Cabrera nuclear power plant

    International Nuclear Information System (INIS)

    Rodriguez, A.

    2009-01-01

    With the start of the dismantling works at the Jose Cabrera nuclear power plant now in sight, this is an appropriate moment to look back and consider recent history. The first time that the issue of nuclear power plant dismantling was dealt with was in 1975, at a conference in Paris entitled Nuclear Energy Maturity. Up until then the entire question had been one of design, construction and operation, but since that moment and it has been quite a while since that conference dismantling has begun to be seen as just another activity in the nuclear cycle, a final activity that will sooner or later affect all the facilities, an activity different from its predecessors and with the ultimate objective of restoring the sites for whatever use might be determined. During the 1960s and 1970s, the construction of nuclear power plants was widespread across the entire world. It was the baby boom of nuclear energy and now, forty or fifty years later, we are seeing the arrival of the end of the service lifetime of these plants and are faced with the corresponding general process of dismantling these installations. The dismantling of nuclear power plants has ceased to be an emerging issue and is now consolidated as a regular activity in the nuclear industry, albeit an activity that lacks adequate financing or specific regulation in certain countries. Fortunately this is not the case in Spain, since economic provisions have been planned and the regulatory framework developed. In view of the above, the dismantling of the nuclear power plants is an industrial activity involving specific technologies that implies new professional and business opportunities that should be absorbed and seized by society. In Spain the path followed in this direction has been a long one, as is underlined by the experiences of dismantling the Argos (Barcelona, 1998- 2004) and Arbi (Bilbao, 2002-2005) research reactors, the Andujar Uranium Mill (Jaen, 1991-1995), the Vandellos I nuclear power plant

  13. Development of Soil Derived Concentration Guidance Levels for Decommissioning at Overseas Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Sohn, Wook; Yoon, Suk Bon; Kim, Jeongju [KHNP CRI, Daejeon (Korea, Republic of)

    2016-10-15

    In Korea, the criteria are expected to be given in terms of dose as in US and Spain. However, since dose cannot be measured, corresponding measurable concentration limits, so-called Derived Concentration Guidance Levels (DCGLs), should be developed for each radionuclide which is expected to be present in the site. Also, as they serve as a goal of decommissioning and direct dismantling and decontamination methods applicable to the site, DCGLs should be developed in the early phase of decommissioning. This paper describes how each overseas nuclear power plant developed its site-specific Soil DCGLs: what kind of post closure use of the site (scenario) was assumed and how the site-specific Soil DCGLs were calculated based on the scenario assumed for each plant. Through this, it is intended to derive lessons learned which will be instructive for future decommissioning of domestic nuclear power plants including Kori Unit 1. It is very important to have as good under-standing as possible of characteristics of the site by collection of relevant information and data in order to apply a scenario which is most foreseeable and plausible for a site to be decommissioned and to provide site-specific inputs to the calculation of the Soil DCGLs. These efforts will help to have not-overly conservative values for the Soil DCGLs, thus thereby reducing the costs and time needed for performing the decommissioning.

  14. Safety analysis of disposal of decommissioning waste from the Olkiluoto nuclear power plant - PURKU-93

    International Nuclear Information System (INIS)

    Vieno, T.; Meszaros, F.; Nordman, H.; Taivassalo, V.

    1993-12-01

    Decommissioning waste from the Olkiluoto nuclear power plant will be disposed of at the depth between 60 and 100 meters in the bedrock at the power plant site. The existing VLJ repository for low and medium level operating waste will be extended with three new silos for the decommissioning waste of the TVO I and II reactors and the spent fuel interim store at the Olkiluoto site. Besides dismantling waste also used fuel boxes, control rods and other activated metal components accumulated during the operation of the reactors will be disposed of in the repository. The safety analysis is based on the detailed decommissioning plan of the Olkiluoto power plants and the comprehensive safety analysis carried out for the Final Safety Analysis Report of the VLJ repository. (58 refs., 31 figs., 38 tabs.)

  15. Analysis of the Possibility of Required Resources Estimation for Nuclear Power Plant Decommissioning Applying BIM

    Energy Technology Data Exchange (ETDEWEB)

    Jung, Insu [Korea Institute of construction Technology, Goyang (Korea, Republic of); Kim, Woojung [KHNP-Central Research Institute, Daejeon (Korea, Republic of)

    2014-05-15

    Estimation of decommissioning cost, decommissioning strategy, and decommissioning quantity at the time when entering into any decommissioning plans are some elements whose inputs are mandatory for nuclear power plant decommissioning. Ways to estimate decommissioning of required resources in the past have imposed great uncertainty since they analyze required resources at the construction stage, analyzing and consulting decommissioning required resources of overseas nuclear power plants. This study aims at analyzing whether required resources for decommissioning nuclear power plants can be estimated, applying BIM. To achieve this goal, this study analyzed the status quo of BIM such as definition, characteristics, and areas applied, and made use of them when drawing out study results by examining types and features of the tools realizing BIM. In order to review how BIM could be used for decommissioning nuclear power plants, the definition, characteristics and applied areas of BIM were discussed. BIM designs objects of the structures (walls, slabs, pillars, stairs, windows and doors, etc.) by 3D technology and endows attribute (function, structure and usage) information for each object, thereby providing visualized information of structures for participants in construction projects. Major characteristics of BIM attribute information are as follows: - Geometry: The information of objects is represented by measurable geometric information - Extensible object attributes: Objects include pre-defined attributes, and allow extension of other attributes. Any model that includes these attributes forms relationships with other various attributes in order to perform analysis and simulation. - All information including the attributes are integrated to ensure continuity, accuracy and accessibility, and all information used during the life cycle of structures are supported. This means that when information of required resources is added as another attributes other than geometric

  16. Decommissioning a nuclear power plant: the tax effects

    International Nuclear Information System (INIS)

    Foyt, W.W.

    1982-01-01

    The tax treatment of decommissioning costs is as important a consideration as construction costs. The principles also apply to offshore operations and pipeline systems having a negative salvage value. Estimates place the cost at somewhere between 15 and 100% of construction costs, depending on how the decommissioning is done. It is essential to find an accurate way to project decommissioning costs and to decide how they should be reported for tax purposes. The Internal Revenue Service (IRS) does not plan to apply Section 167, which deals with negative net salvage. Utility customers will ultimately provide the funds, but current IRS rulings count these funds as ordinary income and do not allow matching the additional revenue with decommissioning expenses

  17. Decommissioning a nuclear reactor

    International Nuclear Information System (INIS)

    Montoya, G.M.

    1991-01-01

    The process of decommissioning a facility such as a nuclear reactor or reprocessing plant presents many waste management options and concerns. Waste minimization is a primary consideration, along with protecting a personnel and the environment. Waste management is complicated in that both radioactive and chemical hazardous wastes must be dealt with. This paper presents the general decommissioning approach of a recent project at Los Alamos. Included are the following technical objectives: site characterization work that provided a thorough physical, chemical, and radiological assessment of the contamination at the site; demonstration of the safe and cost-effective dismantlement of a highly contaminated and activated nuclear-fuelded reactor; and techniques used in minimizing radioactive and hazardous waste. 12 figs

  18. Spanish regulatory experience in the decommissioning program of Vandellos 1 Nuclear Power Plant

    International Nuclear Information System (INIS)

    Revilla, J.L.

    2003-01-01

    Nuclear facilities are subject to a system of prior authorization by the competent authorities before they come into service and to subsequent regulation and control during their operating life. All the facilities that stop operating, for technical or financial reasons or because they are compelled to, remain subject to this regulatory control system as long as the competent authorities consider that their residual radioactivity represents a potential source of radiological hazard to the individuals affected or entails an unacceptable environmental risk. The decommissioning of nuclear facilities is the final stage of their life cycle. This stage is part of a general strategy of environmental restoration, which must necessarily be followed after the suspension of certain industrial activities that have to some extent affected the environment. In Spain the decommissioning of facilities is considered a further step or stage of their life cycle in which, in principle, the whole regulatory framework in force during the previous stages of their life - siting, construction, operation, etc. - remains applicable. The law setting up the Spanish Nuclear Safety Council (CSN) states that one of its functions is to issue reports to the Ministry of Economy in advance of the resolutions adopted by that Ministry on the granting of licences for the decommissioning of nuclear and radioactive facilities. However, the old regulations on nuclear and radioactive facilities, in force up to the end of 1999, included no specific references that might serve as a regulatory framework for licensing the decommissioning process of such facilities. All facility decommissioning projects initiated in Spain up to that date, including Vandellos 1 Nuclear Power Plant Decommissioning Plan, were licensed according to an approach worked out specifically for each one. (authors)

  19. Strategically oriented project management of the decommissioning of nuclear power plants

    International Nuclear Information System (INIS)

    Kemmeter, Sascha; Woempener, Andreas

    2013-01-01

    Due to the politically induced change of the energy sector in Germany, the operators of nuclear power plants had to react and to deal with completely new conditions concerning the decommissioning of their plants on short notice. Therefore the operators have to devise new strategies for controlling their decommissioning and dismantling projects in a short amount of time and most often similarly for several plants. Two fundamental procedures are possible for the successful controlling of these dismantling projects: a centralized or a decentralized management organization. How these project control processes can be realized in an optimal way, is, next to other economic specifications of the dismantling of nuclear power plants, the topic of a new research project of the Chair of Management Accounting at the University Duisburg-Essen. In that process, results and experiences from other research and practical projects concerning general large-scale projects are being used. Selected findings have been compiled and are being discussed in this paper. (orig.)

  20. The decommissioning of the Latina nuclear power plant

    International Nuclear Information System (INIS)

    Bolla, G.; Macci, E.; Craik, J.F.D.; Walkden, P.

    2001-01-01

    Over the past year, a revised decommissioning programme, drawing upon the combined experience of the two companies, has been developed for the Latina NPP. This has been achieved despite a very demanding time-scale. Theoretical and practical experiences from both Sogin and BNFL's operations in North America and Europe have been used to quantify liabilities and progress the planning process to the point where Sogin have been able to define their funding requirements for Latina with their stakeholders. The project has demonstrated, based on real experience and data, that the Latina NPP can be decommissioned economically for a known cost within the timescale set by the Italian Government. (author)

  1. Comparison of Planning, Management and Organizational Aspects of Nuclear Power Plants A1 and V1 Decommissioning

    Energy Technology Data Exchange (ETDEWEB)

    Stubna, M.; Michal, V., E-mail: Marian.Stubna@vuje.sk, E-mail: V.Michal@iaea.org [VUJE, Inc. Trnava (Slovakia); Daniska, V., E-mail: Daniska@decom.sk [DECOM, Inc. Trnava (Slovakia); Sirota, J., E-mail: Sirota.Jan@javys.sk [JAVYS, Inc. Bratislava, (Slovakia)

    2013-08-15

    This contribution deals with planning, management and organizational aspects of decommissioning of NPP shut down due to the accident (prototype NPP A1) and NPP shut down after normal operation (NPP V1). The A1 and V1 NPPs are located very close in Bohunice nuclear site however both plants have very different technology and operational history. The preparation of A1 NPP decommissioning strategy and relevant decommissioning plans was long term process, because the plant was shut down after the accident in 1977 and decommissioning was implemented first time in Slovakia with many specific difficulties. The decommissioning planning of V1 NPP was shorter and easier, because the plant was shut down after normal operation, there were lessons learned from the A1 NPP decommissioning planning, available legislation, available financing etc. Development of decommissioning strategies, preparation and planning for decommissioning, development of legislation for decommissioning, management of decommissioning projects and other aspects are described and compared. Lessons learned are formulated on the basis of analysis of past, ongoing and planned decommissioning activities in Slovakia. (author)

  2. Nuclear installations: decommissioning and dismantling

    International Nuclear Information System (INIS)

    Anon.

    1995-01-01

    This document is a compilation of seven talks given during the 1995 EUROFORUM conference about decommissioning and dismantling of Nuclear installations in the European Community. The first two papers give a detailed description of the legal, financial and regulatory framework of decommissioning and dismantling of nuclear facilities in the European Union and a review of the currently available decommissioning techniques for inventory, disassembly, decontamination, remote operations and management of wastes. Other papers describe some legal and technical aspects of reactor and plants dismantling in UK, Germany, Spain and France. (J.S.)

  3. Ecological aspects of decommissioning of the Chornobyl Nuclear Power Plant

    International Nuclear Information System (INIS)

    Oskolkov, B.Ya.; Nosovskij, A.V.

    2001-01-01

    During the development of Design of ChNPP Decommissioning, it is necessary to consider all the real ecological conditions of its existence and, taking into account the economic potential, to define the achievable and expedient final result, i.e. the final ecological goal. The final goal of ChNPP decommissioning from the point of view of ecology is the termination of the unfavorable influence of the object on the ecosystem of the location area and renovation of the natural conditions of the environment up to the starting level, i.e. like it was prior to the NPP construction or to the level of accepted for the society at present considering the minimization of the problems for the future generations. For the Chornobyl NPP this result is practically unachievable

  4. Investigations on the decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Goertz, R.; Bastek, H.; Doerge, W.; Kruschel, K.P.

    1985-01-01

    The study discusses and evaluates safety and licensing related aspects associated with the decommissioning of nuclear power plants. Important decommissioning projects and experiences with relevance to decommissioning are analyzed. Recent developments in the field of decommissioning techniques with the potential of reducing the occupational dose to decommissioning workers are described and their range of application is discussed. The radiological consequences of the recycling of scrap metal arising during decommissioning are assessed. The results may be used to evaluate present licensing practices and may be useful for future licensing procedures. Finally the environmental impact of radionuclide release via air and water pathways associated with decommissioning activities is estimated. (orig.) [de

  5. Law on the Decommissioning of unit 1 at the state enterprise of the Republic of Lithuania Ignalina Nuclear Power Plant

    International Nuclear Information System (INIS)

    2000-01-01

    This law regulates the legal principles for the decommissioning of unit 1 at the Ignalina Nuclear Power Plant. The main deadlines for the government in the preparation for the decommissioning are set in the law. All preparatory works should be finished before the year 2005

  6. The Community's research and development programme on decommissioning of nuclear power plants. Fourth annual progress report (year 1983)

    International Nuclear Information System (INIS)

    Anon.

    1985-01-01

    This is the fourth progress report of the European Community's program. (1979-83) of research on decommissioning of nuclear power plants. It covers the year 1983 and follows the 1980, 1981 and 1982 reports (EUR 7440, EUR 8343, EUR 8962). The present report describes the further progress of research and contains a large amount of results. For a majority of the 51 research contracts composing the 1979-83 programme, work was completed by the end of 1983; the conclusions drawn from this work are in this report. The European Community's program deals with the following fields: long-term integrity of buildings and systems; decontamination for decommissioning purposes; dismantling techniques; treatment of specific wastes materials (steel, concrete and graphite); large transport containers for radioactive waste produced in the dismantling of nuclear power plants; estimation of the quantities of radioactive waste arising from the decommissioning of nuclear power plants in the Community; influence of nuclear power plant design features on decommissioning

  7. Preliminary study of the environmental radiological assessment for the Garigliano nuclear power plant decommissioning

    International Nuclear Information System (INIS)

    Esposito, A.M.; Sabbarese, C.; Sirignano, C.; Visciano, L.; D'Onofrio, A.D.; Lubritto, C.; Terrasi, F.

    2002-01-01

    In the last few years many nuclear installations in the world have been stopped either because they reached the end of production lifetime, or for operation problems or, like in Italy, for political decisions. This stop started the decommissioning procedure. It consists in the dismantling of the nuclear installation with appropriate controls and limitations of environmental and radiological impact which arises from these operations. The evaluation of risk and the actions needed for the population safeguard are generally inspired to the recommendations of the International Commission on Radiological Protection (ICRP), but each country faces the problem with different evaluation methodologies and calculations. That is due to different laws and environmental, social and economical context where nuclear installations are located. For this, the decommissioning operations must be separately evaluated for each nuclear installation. In this paper, we present the work carried out so far about the decommissioning of the Nuclear Power Plant of Garigliano (Caserta, Italy), which is managed by SoGIN (Societa di Gestione degli Impianti Nucleari). This Nuclear Power Plant began its activity in 1964 by using a boiling water reactor with a production of 160 MW electric power. In 1979 this nuclear installation was stopped for maintenance and operation has not been resumed until the referendum in 1986, after which all Italian nuclear plants were stopped. Now, the Nuclear Power Plant of Garigliano has the reactor isolated respect to the remaining part and all components and pipes have been drained and sealed. The underground tanks of radioactive wastes have been evacuated and decontaminated. The radioactive wastes have been completely conditioned with cementification in drums suitable to prevent outside release

  8. Costs of decommissioning nuclear power plants as reported to the public to date

    International Nuclear Information System (INIS)

    Strasma, J.D.

    1982-01-01

    This paper attempts to determine what information has been available to the public, in the United States, concerning the cost of decommissioning nuclear power plants. The search was conducted in the Television News Index and Abstracts, in the annual indexes to The Reader's Digest, and in two computer-based bibliographic retrieval systems, Lockheed's DIALOG Magazine Index and the New York Times Information Bank. Fewer than ten articles appeared in widely read places, with none at all in the Reader's Digest and none on the evening TV news, from 1974 to date. The cost of decommissioning nuclear power plants was reported in various ways, with a wide range of estimates and relatively little actual experience. Costs were given in dollars of different years, in percentages of construction costs, in cost per KWH as per month to the consumer, etc., making the range of reported costs seem even wider than it really was. It is not surprising that the public fears that decommissioning costs will be alarmingly high. The public debate on energy policy might be more rational with better information on decommissioning costs. 16 references

  9. Methods of control of inaccuracy in calculation of nuclear power plant decommissioning parameters - 16383

    International Nuclear Information System (INIS)

    Ondra, Frantisek; Daniska, Vladimir; Rehak, Ivan; Necas, Vladimir

    2009-01-01

    The aim of the article is a development of analytical methodology for evaluation of input data inaccuracies impact on calculation of cost and other output decommissioning parameters. This methodology is based on analytical model calculations using the OMEGA code and taking into account the probability of input data inaccuracies occurrence also. To achieve about mentioned aim, the article identifies possible sources of input data inaccuracies and analyzes their level of impact on output parameters. Then the methodology for calculation of input parameters inaccuracies impact is developed, based on analytical model calculation. The model calculation takes into consideration output parameters impact on cost and other decommissioning output parameters in analytical way. The methodology used in model calculations is original, more over it implements the international standardized structure (IAEA, OECD/NEA, EC) [6] of decommissioning cost for the first time. A probabilistic occurrence of input data inaccuracies is taken into consideration and implemented in the methodology developed. A correction factors matrix for evaluation of input data inaccuracies impact on decommissioning output parameters is set up. The matrix contains parameters based on model calculations using the proposed methodology. Finally the methodology for application of correction factor matrix is proposed and tested; the methodology is used for calculation of contingency in the standardized structure which reflected the level of input data inaccuracies. The cost for individual decommissioning projects for common nuclear power plants are in the range 300 - 500 mil. EUR. Contingencies are from 10% to 30%, depending on the level of detailed during preparation of decommissioning projects. A implementation about mentioned methodology in the OMEGA code improves the accuracy of contingency. Consequently it makes calculated contingency more trustworthy and makes calculated decommissioning cost closer to reality

  10. 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.

  11. Evaluation of the electric power production cost growth due to decommissioning of nuclear power plants

    International Nuclear Information System (INIS)

    Basso, G.

    1982-01-01

    The increase of production cost for electric power generated by nuclear plants, due to their decommissioning and the end of operating life, is analysed in respect to (a) waiting time from indefinite shut-down date to the start of dismantlement, (b) financing method, (c) interest and inflation rates. The analysis shows that the additional cost is always small for those solutions which have higher probability to be adopted

  12. Quality Assurance in the Vandellos 1 Nuclear Power Plant Dismantling and Decommissioning Project

    International Nuclear Information System (INIS)

    Soto Lanuza, A.

    2000-01-01

    General description of the Quality Assurance System established and implemented for the efficient development of the current activities specified in the Dismantling and Decommissioning Plan for Vandellos I Nuclear Power Plant. Aspects related to the Quality organization, scope and applicability on the established Quality Assurance Manual, availability of requirements and recommendations on quality as well as actions to be taken for the correct verification on the quality and practical application of the Manual should be described. (Author)

  13. Decommissioning costs of WWER-440 nuclear power plants. Interim report: Data collection and preliminary evaluations

    International Nuclear Information System (INIS)

    2002-11-01

    Based on the interest in decommissioning costs within Member States, especially in WWER- 440 operating countries that face the complex decision about continued operation vs. decommissioning in the near future, the IAEA launched the task to prepare a technical document on decommissioning costs of WWER-440 nuclear power plants. The main objectives of this publication were to present the decommissioning costs of WWER-440 NPPs in a uniform manner, i.e. using the cost item and cost group system of the Interim Technical Document on Nuclear Decommissioning 'A Proposed Standardised List of Items for Costing Purposes' developed jointly by the EC, the IAEA and the OECD Nuclear Energy Agency (NEA), and providing, as such, a basis for understanding decommissioning costs differences. Member States operating WWER-440 NPPs or having such units under shutdown or even under decommissioning conditions have been requested to provide cost estimates and other input data in order to facilitate understanding of their cost figures. Both decommissioning options, i.e. immediate decommissioning and safe enclosure, have been considered. In the aforementioned joint Interim Technical Document, cost items related to activities that are carried out with a similar emphasis, whether or not tied to a similar time schedule for decommissioning, or that are based on overall activities that cannot be categorised in a specific time period, are grouped as follows: pre-decommissioning actions; facility shutdown activities; procurement of general equipment and material; dismantling activities; waste processing, storage and disposal; site security, surveillance and maintenance; site restoration, cleanup and landscaping; project management, engineering and site support; research and development; fuel and nuclear material; other costs. Before starting implementation of the study, agreement was obtained on general financial, technical and social boundary conditions that should be used in order to facilitate

  14. Environmental Problems Associated With Decommissioning The Chernobyl Nuclear Power Plant Cooling Pond

    International Nuclear Information System (INIS)

    Farfan, E. B.; Jannik, G. T.; Marra, J. C.; Oskolkov, B. Ya.; Bondarkov, M. D.; Gaschak, S. P.; Maksymenko, A. M.; Maksymenko, V. M.; Martynenko, V. I.

    2009-01-01

    Decommissioning of nuclear power plants and other nuclear fuel cycle facilities has been an imperative issue lately. There exist significant experience and generally accepted recommendations on remediation of lands with residual radioactive contamination; however, there are hardly any such recommendations on remediation of cooling ponds that, in most cases, are fairly large water reservoirs. The literature only describes remediation of minor reservoirs containing radioactive silt (a complete closure followed by preservation) or small water reservoirs resulting in reestablishing natural water flows. Problems associated with remediation of river reservoirs resulting in flooding of vast agricultural areas also have been described. In addition, the severity of environmental and economic problems related to the remedial activities is shown to exceed any potential benefits of these activities. One of the large, highly contaminated water reservoirs that require either remediation or closure is Karachay Lake near the MAYAK Production Association in the Chelyabinsk Region of Russia where liquid radioactive waste had been deep well injected for a long period of time. Backfilling of Karachay Lake is currently in progress. It should be noted that secondary environmental problems associated with its closure are considered to be of less importance since sustaining Karachay Lake would have presented a much higher radiological risk. Another well-known highly contaminated water reservoir is the Chernobyl Nuclear Power Plant (ChNPP) Cooling Pond, decommissioning of which is planned for the near future. This study summarizes the environmental problems associated with the ChNPP Cooling Pond decommissioning

  15. Quality assurance program application during the decommissioning phase of the Shoreham Nuclear Plant

    International Nuclear Information System (INIS)

    Patch, R.L.

    1993-01-01

    The application of Quality Assurance (QA) requirements for operating nuclear power plants has evolved over the last 30 years. QA programs started as good management practices and evolved to a process that is implemented integral to very detailed Probabilistic Risk Assessments (PRAs). QA programs for controlling activities during decommissioning of nuclear power plants are still in their infancy. Regulatory guidance is currently being developed, and much of what exists is in the form of draft guidance documents. In determining where to apply QA controls during decommissioning, a series of questions must be asked: Is there an existing regulatory commitment? (Safety related or safety significant activity); Are there any postulated accidents which need to be prevented or mitigated; What are the unacceptable risks; Are there other key factors, such as human performance issues and Industrial Safety Programs, to be considered? Which QA controls are needed and to what extent they should be applied must be evaluated on a case by case basis. How much QA to apply is usually a risk evaluation in itself. Can you afford not to apply a specific control? Can you afford to apply costly and rigorous quality control programs? These questions had to be answered at the Shoreham Nuclear Power Station (SNPS) in order to develop and implement an acceptable and effective Quality Assurance program. Exploring the SNPS open-quotes lessons learnedclose quotes on how to apply a quality assurance program during decommissioning is what the following discussion is about

  16. Environmental Problems Associated With Decommissioning The Chernobyl Nuclear Power Plant Cooling Pond

    Energy Technology Data Exchange (ETDEWEB)

    Farfan, E. B.; Jannik, G. T.; Marra, J. C.; Oskolkov, B. Ya.; Bondarkov, M. D.; Gaschak, S. P.; Maksymenko, A. M.; Maksymenko, V. M.; Martynenko, V. I.

    2009-11-09

    Decommissioning of nuclear power plants and other nuclear fuel cycle facilities has been an imperative issue lately. There exist significant experience and generally accepted recommendations on remediation of lands with residual radioactive contamination; however, there are hardly any such recommendations on remediation of cooling ponds that, in most cases, are fairly large water reservoirs. The literature only describes remediation of minor reservoirs containing radioactive silt (a complete closure followed by preservation) or small water reservoirs resulting in reestablishing natural water flows. Problems associated with remediation of river reservoirs resulting in flooding of vast agricultural areas also have been described. In addition, the severity of environmental and economic problems related to the remedial activities is shown to exceed any potential benefits of these activities. One of the large, highly contaminated water reservoirs that require either remediation or closure is Karachay Lake near the MAYAK Production Association in the Chelyabinsk Region of Russia where liquid radioactive waste had been deep well injected for a long period of time. Backfilling of Karachay Lake is currently in progress. It should be noted that secondary environmental problems associated with its closure are considered to be of less importance since sustaining Karachay Lake would have presented a much higher radiological risk. Another well-known highly contaminated water reservoir is the Chernobyl Nuclear Power Plant (ChNPP) Cooling Pond, decommissioning of which is planned for the near future. This study summarizes the environmental problems associated with the ChNPP Cooling Pond decommissioning.

  17. ENVIRONMENTAL PROBLEMS ASSOCIATED WITH DECOMMISSIONING THE CHERNOBYL NUCLEAR POWER PLANT COOLING POND

    Energy Technology Data Exchange (ETDEWEB)

    Farfan, E.

    2009-09-30

    Decommissioning of nuclear power plants and other nuclear fuel cycle facilities has been an imperative issue lately. There exist significant experience and generally accepted recommendations on remediation of lands with residual radioactive contamination; however, there are hardly any such recommendations on remediation of cooling ponds that, in most cases, are fairly large water reservoirs. The literature only describes remediation of minor reservoirs containing radioactive silt (a complete closure followed by preservation) or small water reservoirs resulting in reestablishing natural water flows. Problems associated with remediation of river reservoirs resulting in flooding of vast agricultural areas also have been described. In addition, the severity of environmental and economic problems related to the remedial activities is shown to exceed any potential benefits of these activities. One of the large, highly contaminated water reservoirs that require either remediation or closure is Karachay Lake near the MAYAK Production Association in the Chelyabinsk Region of Russia where liquid radioactive waste had been deep well injected for a long period of time. Backfilling of Karachay Lake is currently in progress. It should be noted that secondary environmental problems associated with its closure are considered to be of less importance since sustaining Karachay Lake would have presented a much higher radiological risk. Another well-known highly contaminated water reservoir is the Chernobyl Nuclear Power Plant (ChNPP) Cooling Pond, decommissioning of which is planned for the near future. This study summarizes the environmental problems associated with the ChNPP Cooling Pond decommissioning.

  18. The use of modern engineered polymer coatings and products in decommissioning of nuclear facilities and plant

    International Nuclear Information System (INIS)

    Christie, K.; Harris, C.W.; Morris, O.P.; Atkinson, P.

    2014-01-01

    During decommissioning of nuclear plant, problems can arise whereby leaks and cracks appear which may require repair or remediation. Following clean-up processes radionuclides may be exposed in concrete or structures such ponds which require sealing to prevent atmospheric release and to obtain a reduction in operator dose. There are a number of polymer based products on the market which with care and skillful selection can be utilised to aid decommissioning and to add reassurance to regulators that radionuclide release cannot occur. Choosing between them is difficult due to the fact that the standard coating tests cannot reliably distinguish between the various products since these modern polymers are all significantly tougher than previous generations of coating technologies. There is therefore a need to develop new bespoke tests which replicate the likely failure modes of the plant and which demonstrate which products are likely to perform well in real life situations. (authors)

  19. Die Energiewerke Nord GmbH. From operator of a decommissioned Russian nuclear power plant to one of Europe's leading decommissioning companies

    International Nuclear Information System (INIS)

    Philipp, Marlies

    2011-01-01

    EWN GmbH is a state-owned company with these duties: - decommissioning and demolition of the Greifswald and Rheinsberg nuclear power stations; - safe operation of the Zwischenlager Nord interim store; - development of the 'Lubminer Heide' industrial and commercial estate. Other projects for which EWN GmbH uses its know-how: - disposal of 120 decommissioned Russian nuclear submarines in Murmansk; - decommissioning and dismantling of the Juelich, NRW, AVR experimental reactor; - demolition of nuclear plants; running the Central Decontamination Operations Department at Karlsruhe, BW. Since 2008, EWN GmbH has held 25% of the shares of Deutsche Gesellschaft zum Bau- und Betrieb von Endlagern fuer Abfallstoffe mbH (DBE), a firm building and operating nuclear repositories. (orig.)

  20. Decommissioning Work Modeling System for Nuclear Facility Decommissioning Design

    International Nuclear Information System (INIS)

    Park, S. K.; Cho, W. H.; Choi, Y. D.; Moon, J. K.

    2012-01-01

    During the decommissioning activities of the KRR-1 and 2 (Korea Research Reactor 1 and 2) and UCP (Uranium Conversion Plant), all information and data, which generated from the decommissioning project, were record, input and managed at the DECOMMIS (DECOMMissioning Information management System). This system was developed for the inputting and management of the data and information of the man-power consumption, operation time of the dismantling equipment, the activities of the radiation control, dismantled waste management and Q/A activities. When a decommissioning is planed for a nuclear facility, an investigation into the characterization of the nuclear facility is first required. The results of such an investigation are used for calculating the quantities of dismantled waste volume and estimating the cost of the decommissioning project. That is why, the DEFACS (DEcommissioning FAcility Characterization DB System) was established for the management of the facility characterization data. The DEWOCS (DEcommissioning WOrk-unit productivity Calculation System) was developed for the calculation of the workability on the decommissioning activities. The work-unit productivities are calculated through this system using the data from the two systems, DECOMMIS and DEFACS. This result, the factors of the decommissioning work-unit productivities, will be useful for the other nuclear facility decommissioning planning and engineering. For this, to set up the items and plan for the decommissioning of the new objective facility, the DEMOS (DEcommissioning work Modeling System) was developed. This system is for the evaluation the cost, man-power consumption of workers and project staffs and technology application time. The factor of the work-unit productivities from the DEWOCS and governmental labor cost DB and equipment rental fee DB were used for the calculation the result of the DEMOS. And also, for the total system, DES (Decommissioning Engineering System), which is now

  1. About the burial of nuclear power plants, damaged or in the process of decommissioning

    International Nuclear Information System (INIS)

    Elbrond, J.

    1994-01-01

    Some underground mining methods leave deep empty holes in the earth's surface behind them. In this paper it is described how to use such mining methods for the burial of damaged nuclear power plants and for the decommissioning by burial of nuclear reactors. The design of a new power plant should be integrated with that of an escapeway - an underground arrangement for burial. The described mining methods are block caving for catastrophy burial, and various stoping methods for planned burial and decommissioning. Blind shaft sinking by full face boring machines for burial and decommissioning of the reactor vessel is also described. All the described activities of mining and shaft sinking are well known. The total costs of burial by these methods are estimated using standard mining industry cost data. These include the costs for normal mine ventilation and groundwater control. However, the estimates of the cost and duration do not include the capital and operational costs of the pre- and post burial activities of ventilation and groundwater control related to the radioactivity. (author)

  2. Russian conceptions of plant life management and decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Bugaenko, S.E.; Butorin, S.L.

    2000-01-01

    Plant life management (PLIM) of nuclear power plant is the concept and practice to provide profitability of safe operation of nuclear electricity-generating installations. Therefore, application of the PLIM technology is a unique possibility for the nuclear power not only to preserve its presence at the generated electricity market but also to enlarge it there at the first quarter of the third millennium. PLIM is considered as the concept and procedure covering the whole life cycle of NPP, consisting of three main phases: pre-operation, operation, post-operation. When considering the list of the main standard works for PLIM, one can notice that the structure of a full volume of works can be presented as the sum of two constituents: specific for a particular power unit and universal one. A specific constituent implies realising the PLIM process at a particular power unit, and universal one implies development scientific-methodological, technological and normative basis supporting PLIM process. The concept of decommissioning NPP power units was developed and adopted in 1991, and nowadays is renewed. Its main principles and provisions correspond to a general approach to decommissioning nuclear power plants which was adopted in international practice and recommended in the IAEA documents. Elimination of NPP power unit is adopted in it as the basic option

  3. Investigation Study on Gamma Ray Imaging Technology for Nuclear Power Plant Decommissioning

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Sang Guk; Jeong, Woo Tae [Machinery and Materials Laboratory, Korea Hydro and Nuclear Power Co., Daejeon (Korea, Republic of)

    2014-10-15

    The gamma ray imaging system provides an estimated dose-rate of the source at 30 cm above. The gamma detector is a terbium activated glass scintillator. The system is capable of producing a color two dimensional image of a radiation field superimposed on a black and white visual image. The system used in US power plants consists of a portable sensor head that contains both gamma ray and visual imaging systems and a portable control computer. The gamma ray imaging system has been successfully used as an ALARA tool for identifying source terms and determining the adequacy of existing shielding. Because the control system can be positioned away from the camera, the radiation exposure to personnel can be reduced without extensive shielding requirements. The gamma ray imaging system has been used to date in the decommissioning of Maine Yankee, Big Rock point,Trojan, San Onofre1, and Millstone 1. The equipment has also been used at normal refueling outages at a number of commercial nuclear power plants and at several Department of Energy Decommissioning sites. This paper is intended to review the applicability of gamma ray imaging system as decommissioning tool. In order to review the actual applicability, we are going to introduce applications for US power plants.

  4. Decommissioning of nuclear reprocessing plants French past experience and approach to future large scale operations

    International Nuclear Information System (INIS)

    Jean Jacques, M.; Maurel, J.J.; Maillet, J.

    1994-01-01

    Over the years, France has built up significant experience in dismantling nuclear fuel reprocessing facilities or various types of units representative of a modern reprocessing plant. However, only small or medium scale operations have been carried out so far. To prepare the future decommissioning of large size industrial facilities such as UP1 (Marcoule) and UP2 (La Hague), new technologies must be developed to maximize waste recycling and optimize direct operations by operators, taking the integrated dose and cost aspects into account. The decommissioning and dismantling methodology comprises: a preparation phase for inventory, choice and installation of tools and arrangement of working areas, a dismantling phase with decontamination, and a final contamination control phase. Detailed description of dismantling operations of the MA Pu finishing facility (La Hague) and of the RM2 radio metallurgical laboratory (CEA-Fontenay-aux-Roses) are given as examples. (J.S.). 3 tabs

  5. Nuclear energy in Bulgaria. Improvement, decommission and new plant

    International Nuclear Information System (INIS)

    Hakata, Tadakuni

    2001-01-01

    Author stayed in Bulgaria at total of 14 months among four years from 1996 to perform a lot of exchange on regulation, research, technology, and so on relating to nuclear safety by widely visiting Kozrodoi nuclear power station, engineering companies, universities, and so on, at center of the Bulgaria Committee of Nuclear Energy Peaceful Application. On a base of knowledge obtained by their experiences, here were introduced on past, present and future subjects remained in Bulgaria, an old Russian satellite nations in East Europe and on present state of nuclear power generation and so on. As exchange with Kozrodoi power station was not a main object of his international cooperation, because of its many subjects its introduction became a main subject. Here were introduced on the newest information such as closure and new construction plan of WWER-440, innovation of energy sector, and so on, furthermore, added some informations obtained from Dr. D.Popov, present quasi-professor of Sophia Technical Collage. (G.K.)

  6. Vinca nuclear decommissioning program

    International Nuclear Information System (INIS)

    Pesic, M.; Subotic, K.; Sotic, O.; Plecas, I.; Ljubenov, V.; Peric, A.

    2002-01-01

    In this paper a preliminary program for the nuclear decommissioning in The Vinca Institute of Nuclear Sciences is presented. Proposed Projects and Activities, planned to be done in the next 10 years within the frames of the Program, should improve nuclear and radiation safety and should solve the main problems that have arisen in the previous period. Project of removal of irradiated spent nuclear fuel from the RA reactor, as a first step in all possible decommissioning strategies and the main activity in the first two-three years of the Program realization, is considered in more details. (author)

  7. Comparing the costs of decommissioning nuclear power plants in USA and in Germany

    International Nuclear Information System (INIS)

    Vollradt, J.; Essmann, J.; Paul, R.; Petrasch, P.

    1991-01-01

    Decommissioning and, in particular, disposing of nuclear power plants is still a subject of controversial debate, increasingly so also under economic aspects. This article contains a discussion of the allegation that new findings had caused the costs of decommissioning in the US to rise sharply in the past few years and, as a consequence, it had to be expected that also the present cost estimates made in the Federal Republic of Germany would have to be corrected upward drastically in the very near future and that nuclear power might well become economically non-viable as a result of this development. These allegations cannot be assessed in detail on scientific grounds, as they obviously constitute biased reports with extrapolations and conversions whose parameters cannot be verified. However, a comparison of unbiased American and German studies shows that the costs of decommissioning have risen in the US over the past twelve years, while their absolute level is still clearly below the high cost level in Germany. Upon examination of the causes it is seen that stricter criteria were applied and different boundary conditions assumed in Germany from the outset. Consequently, no major corrections were or are necessary. In view of the different boundary conditions existing in the two countries, the studies conducted there are meaningful and correct. (orig.) [de

  8. Cutting Technology for Decommissioning of the Reactor Pressure Vessels in Nuclear Power Plants

    International Nuclear Information System (INIS)

    Jeong, Kwan Seong; Kim, Geun Ho; Moon, Jei Kwon; Choi, Byung Seon

    2012-01-01

    Lots of nuclear power plants have been decommissioned during the last 2 decades. An essential part of this work is the dismantling of the Reactor Pressure Vessel and its Internals. For this purpose a wide variety of different cutting technologies have been developed, adapted and applied. A detailed introduction to Plasma Arc cutting, Contact Arc Metal cutting and Abrasive Water Suspension Jet cutting is given, as it turned out that these cutting technologies are particularly suitable for these type of segmentation work. A comparison of these technologies including gaseous emissions, cutting power, manipulator requirements as well as selected design approaches are given. Process limits as well as actual limits of application are presented

  9. The decommissioning of WWER type nuclear power plants. Final report on an IAEA regional technical co-operation project

    International Nuclear Information System (INIS)

    2000-01-01

    Numerous WWER-440 nuclear power plants are in operation in central and eastern Europe and a small number have already been shut down. In addition to reactors already shut down, many other reactors will reach the end of their design lifetime in a few years and become candidates for decommissioning. It is unfortunate that little consideration was devoted to decommissioning of WWER-440 reactors at the plant design and construction stage, and little emphasis was placed on planning for decommissioning. It is within this context that the IAEA launched a regional technical co-operation project in 1994 with the aim of providing guidance on planning and management of decommissioning for WWERs. The project, which had a duration of four years (1995-1998), included the organization of workshops and scientific visits to countries having WWERs and other countries where active decommissioning projects were under way. Eventually, participants suggested the consolidation of expert guidance and collective opinions into a TECDOC, which was drafted by both designated participants from project recipient countries and invited experts. The TECDOC has the aim of serving as a stimulus for all concerned parties in central and eastern European countries to initiate concrete decommissioning planning, including assessment of existing and required resources for the eventual implementation of decommissioning plans. In addition, the regional technical co-operation project has managed to bring together in this TECDOC a number of good practices that could be useful in WWER-440 decommissioning

  10. DEACTIVATION AND DECOMMISSIONING ENVIRONMENTAL STRATEGY FOR THE PLUTONIUM FINISHING PLANT COMPLEX, HANFORD NUCLEAR RESERVATION

    International Nuclear Information System (INIS)

    Hopkins, A.M.; Heineman, R.; Norton, S.; Miller, M.; Oates, L.

    2003-01-01

    Maintaining compliance with environmental regulatory requirements is a significant priority in successful completion of the Plutonium Finishing Plant (PFP) Nuclear Material Stabilization (NMS) Project. To ensure regulatory compliance throughout the deactivation and decommissioning of the PFP complex, an environmental regulatory strategy was developed. The overall goal of this strategy is to comply with all applicable environmental laws and regulations and/or compliance agreements during PFP stabilization, deactivation, and eventual dismantlement. Significant environmental drivers for the PFP Nuclear Material Stabilization Project include the Tri-Party Agreement; the Resource Conservation and Recovery Act of 1976 (RCRA); the Comprehensive Environmental Response, Compensation and Liability Act of 1980 (CERCLA); the National Environmental Policy Act of 1969 (NEPA); the National Historic Preservation Act (NHPA); the Clean Air Act (CAA), and the Clean Water Act (CWA). Recent TPA negotiation s with Ecology and EPA have resulted in milestones that support the use of CERCLA as the primary statutory framework for decommissioning PFP. Milestones have been negotiated to support the preparation of Engineering Evaluations/Cost Analyses for decommissioning major PFP buildings. Specifically, CERCLA EE/CA(s) are anticipated for the following scopes of work: Settling Tank 241-Z-361, the 232-Z Incinerator, , the process facilities (eg, 234-5Z, 242, 236) and the process facility support buildings. These CERCLA EE/CA(s) are for the purpose of analyzing the appropriateness of the slab-on-grade endpoint Additionally, agreement was reached on performing an evaluation of actions necessary to address below-grade structures or other structures remaining after completion of the decommissioning of PFP. Remaining CERCLA actions will be integrated with other Central Plateau activities at the Hanford site

  11. Recommended values for the distribution coefficient (Kd) to be used in dose assessments for decommissioning the Zion Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Sullivan, T. [Brookhaven National Lab. (BNL), Upton, NY (United States)

    2014-09-24

    ZionSolutions is in the process of decommissioning the Zion Nuclear Power Plant. The site contains two reactor Containment Buildings, a Fuel Building, an Auxiliary Building, and a Turbine Building that may be contaminated. The current decommissioning plan involves removing all above grade structures to a depth of 3 feet below grade. The remaining underground structures will be backfilled. The remaining underground structures will contain low amounts of residual licensed radioactive material. An important component of the decommissioning process is the demonstration that any remaining activity will not cause a hypothetical individual to receive a dose in excess of 25 mrem/y as specified in 10CFR20 SubpartE.

  12. Recommended values for the distribution coefficient (Kd) to be used in dose assessments for decommissioning the Zion Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Sullivan T.

    2014-06-09

    ZionSolutions is in the process of decommissioning the Zion Nuclear Power Plant. The site contains two reactor Containment Buildings, a Fuel Building, an Auxiliary Building, and a Turbine Building that may be contaminated. The current decommissioning plan involves removing all above grade structures to a depth of 3 feet below grade. The remaining underground structures will be backfilled. The remaining underground structures will contain low amounts of residual licensed radioactive material. An important component of the decommissioning process is the demonstration that any remaining activity will not cause a hypothetical individual to receive a dose in excess of 25 mrem/y as specified in 10CFR20 SubpartE.

  13. Decommissioning costs of light water nuclear power plants in Germany from 1977 to date

    International Nuclear Information System (INIS)

    Adler, J.; Petrasch, P.

    1993-01-01

    This study presents decommissioning costs of NPP's in Germany. In 1977, a similar study had been carried out by NIS Ingenieurgesellschaft for the Commission of the European Communities. The experience gained during the last 15 years from the decommissioning of nuclear installations, as well as the developments made in calculating costs were the reasons to update the 1977 study. The cost estimates were carried out for the German LWRs, Biblis A (PWR) and Brunsbuettel (BWR) taken as reference plants. For the calculations, the software programme STILLKO 2 (owned by the German VDEW) was used. Not only have cost calculations been carried out, but also data have been obtained relating to manpower, occupational radiation exposure, masses of material to be dismantled and radioactive waste generated. The results enable a direct comparison with those of the 1977 study and show the most important differences. In a separate chapter, costs for single items are presented so that comparison with decommissioning costs from other EC countries may be possible. (authors). 24 refs., 14 figs., 17 tabs., 3 appendices

  14. Collection and characterization of emissions from metal cutting in Caorso nuclear power plant decommissioning

    International Nuclear Information System (INIS)

    Cesari, F.G.; Terzi, L.A.; Giostri, A.; Bernini, C.; Sirito, E.; Sirito, M.

    2005-01-01

    The Caorso's Nuclear Power Plant (BWR, 870 MWe) has just started the decommissioning process, with the intent to reach, by almost ten years, the 'green field' conditions for the site. The plant has fully worked for a very short period of time, by 1981 to 1986, being shut down after 1987 Italy's poll that abrogated nuclear power use. The dismantling of the components and of the structural materials has already begun in the Turbine Building. The University of Bologna, on indication of the NPP's management, has started an experimental campaign to test the cutting processes and its filtering plant. The starting phase is the qualification of the cutting methods chosen by Caorso's management, oxyfuel and plasma cuttings. This campaign is set over no contaminated material, or, better, material with a contamination under the level of free release, and is now running in the University Labs. Next phase are filtering tests. This part of the qualifying campaign is set to highlight the kind of trouble that can emerge in the cutting processes, not yet taking into account radioactivity. Caorso's BWR is a plant designed and built in the 70s. Possible decommissioning problems weren't considered during the design phase so the cutting processes will be quite difficult, even on the conventional side. The final phase is settled in the plant. Cutting tests, following indications made by previous campaigns, will be conducted in the Turbine Building, where tests can be conducted on a low level of radioactivity (only some little part of it has a contamination level over the free release limit of 1 Bq/cm 2 ). The intent is to develop an extensive cutting procedure, with the obvious option of remote control, able to face difficulties connected with cutting processes in a nuclear plant like Caorso. This means handling with radioactivity and with not airy narrow rooms, fulfilled with pipes. (authors)

  15. Safety in nuclear power plant operation, including commissioning and decommissioning. A code of practice

    International Nuclear Information System (INIS)

    1978-01-01

    Safe operation of a nuclear power plant postulates satisfactory siting, design, construction and commissioning, together with proper management and operation of the plant. This Code of Practice deals with the safety aspects of management, commissioning, operation and decommissioning of the plant. It forms part of the Agency's programme, referred to as the NUSS programme, for establishing Codes of Practice and Safety Guides relating to land-based stationary thermal neutron power plants. It has been prepared for the use of those responsible for the operation of stationary nuclear power plants, the main function of which is the generation of electrical and/or thermal power, and for the use of those responsible for regulating the operation of such plants. It is not intended for application to reactors used solely for experimental or research purposes. The provisions in the Code are designed to provide assurance that operational activities are carried out without undue radiological hazard to the general public and to persons on the site. It should be understood that the provisions in the Code set forth minimum requirements which shall be met in order to achieve safe operation of a nuclear power plant

  16. Prospective needs for decommissioning commercial nuclear facilities

    International Nuclear Information System (INIS)

    Stevens, G.H.; Yasui, M.; Laraia, M.

    1992-01-01

    The answers to the questions: How many reactors will face the end of their operating lifetime over the next few decades? To what extent are the issues of decommissioning urgent? The answers will lead us to those issues that should be tackled now in order to complete smoothly the decommissioning of commercial nuclear power plants. The prospective needs for decommissioning of nuclear power plants are illustrated from the viewpoint of reactor age, and some of the issues to be tackled, in particular by governments, in this century are discussed, to prepare for the future decommissioning activities. (author) 18 refs.; 2 figs.; 2 tabs

  17. International measures for supporting the Ukraine in decommissioning Chernobyl nuclear power plant

    International Nuclear Information System (INIS)

    Wolf, J.

    2006-01-01

    The destruction of Block 4 of the Ukranian nuclear power plant in Chernobyl on 26 April 1986 was the largest and most momentous accident in the civil use of nuclear energy. Its far-reaching and lasting ecological, heath-related and economic effects confronted the then Soviet and later the Ukraine with grave problems. Particularly after the dissolution of the Eastern Bloc and the emergence of information about the safety shortcomings of RBMK-type (Chernobyl-type) reactors the Western states pressed for the decommissioning of these reactors. At the G7 summit in Naples in 1994 the Ukraine was offered an action plan of support if it were willing to close down Chernobyl nuclear power plant. This initiative led to the signing on 20 December 1995 of a Memorandum of Understanding on the Closure of Chernobyl Nuclear Power Plant between the G7 states, the European Commission and the Ukraine. It contained an assurance by President Kuchma that Chernobyl nuclear power plant would be closed by the year 2000

  18. Chemical mode control in nuclear power plant decommissioning during operation of technologies in individual radioactive waste processing plants

    International Nuclear Information System (INIS)

    Horvath, J.; Dugovic, L.

    1999-01-01

    Sewage treatment of nuclear power plant decommissioning is performed by system of sewage concentration in evaporator with formation of condensed rest, it means radioactive waste concentrate and breeding steam. During sewage treatment plant operation department of chemical mode performs chemical and radiochemical analysis of sewage set for treatment, chemical and radiochemical analysis of breeding steam condensate which is after final cleaning on ionization filter and fulfilling the limiting conditions released to environment; chemical and radiochemical analysis of heating steam condensate which is also after fulfilling the limiting conditions released to environment. Condensed radioactive concentrate is stored in stainless tanks and later converted into easy transportable and chemically stable matrix from the long term storage point of view in republic storage Mochovce. The article also refer to bituminous plant, vitrification plant, swimming pool decontamination plant of long term storage and operation of waste processing plant Bohunice

  19. Direction for the Estimation of Required Resources for Nuclear Power Plant Decommissioning based on BIM via Case Study

    Energy Technology Data Exchange (ETDEWEB)

    Jung, Insu [Korea Institute of Construction Technology, Goyang (Korea, Republic of); Kim, Woojung [KHNP-Central Research Institute, Daejeon (Korea, Republic of)

    2014-05-15

    Ways to estimate decommissioning of required resources in the past have imposed great uncertainty since they analyze required resources at the construction stage, analyzing and consulting decommissioning required resources of overseas nuclear power plants. As demands on efficient management and use of complicated construction information increased these days, demands on the introduction of Building Information Modeling (herein after referred to as BIM) technology has increased. In the area of quotation, considerable effects are expected as to the accuracy and reliability predicting construction costs through the characteristics that can automatically estimate quantities by using attribute information of BIM model. BIM-based estimation and quotation of required resources is more accurate than the existing 2D-based quotations and have many advantages such as reviews over constructability and interference. It can be desirable to estimate decommissioning required resources in nuclear power plants using BIM as well as using tools that are compatible with usual international/industrial standards. As we looked into the cases where required resources were estimated, using BIM in Korea and abroad, they dealt with estimation of required resources, estimation of construction cost and process management at large. In each area, methodologies, classification systems, BIM, and realization tests have been used variably. Nonetheless, several problems have been reported, and among them, it is noticeable that although BIM standard classification system exists, no case was found that has used standard classification system. This means that no interlink among OBS (Object Breakdown Structure), WBS (Work Breakdown Structure) and CBS (Cost Breakdown Structure) was possible. Thus, for nuclear power plant decommissioning, decommissioning method and process, etc. shall be defined clearly in the stage of decommissioning strategy establishment, so that classification systems must be set up

  20. Direction for the Estimation of Required Resources for Nuclear Power Plant Decommissioning based on BIM via Case Study

    International Nuclear Information System (INIS)

    Jung, Insu; Kim, Woojung

    2014-01-01

    Ways to estimate decommissioning of required resources in the past have imposed great uncertainty since they analyze required resources at the construction stage, analyzing and consulting decommissioning required resources of overseas nuclear power plants. As demands on efficient management and use of complicated construction information increased these days, demands on the introduction of Building Information Modeling (herein after referred to as BIM) technology has increased. In the area of quotation, considerable effects are expected as to the accuracy and reliability predicting construction costs through the characteristics that can automatically estimate quantities by using attribute information of BIM model. BIM-based estimation and quotation of required resources is more accurate than the existing 2D-based quotations and have many advantages such as reviews over constructability and interference. It can be desirable to estimate decommissioning required resources in nuclear power plants using BIM as well as using tools that are compatible with usual international/industrial standards. As we looked into the cases where required resources were estimated, using BIM in Korea and abroad, they dealt with estimation of required resources, estimation of construction cost and process management at large. In each area, methodologies, classification systems, BIM, and realization tests have been used variably. Nonetheless, several problems have been reported, and among them, it is noticeable that although BIM standard classification system exists, no case was found that has used standard classification system. This means that no interlink among OBS (Object Breakdown Structure), WBS (Work Breakdown Structure) and CBS (Cost Breakdown Structure) was possible. Thus, for nuclear power plant decommissioning, decommissioning method and process, etc. shall be defined clearly in the stage of decommissioning strategy establishment, so that classification systems must be set up

  1. Disposal of Steam Generators from Decommissioning of PWR Nuclear Power Plants

    International Nuclear Information System (INIS)

    Walberg, Mirko; Viermann, Joerg; Beverungen, Martin; Kemp, Lutz; Lindstroem, Anders

    2008-01-01

    Amongst other materials remarkable amounts of radioactively contaminated or activated scrap are generated from the dismantling of Nuclear Power Plants. These scrap materials include contaminated pipework, fittings, pumps, the reactor pressure vessel and other large components, most of them are heat exchangers. Taking into account all commercial and technical aspects an external processing and subsequent recycling of the material might be an advantageous option for many of these components. The disposal of steam generators makes up an especially challenging task because of their measures, their weight and compared to other heat exchangers high radioactive inventory. Based on its experiences from many years of disposal of smaller components of NPP still in operation or under decommissioning GNS and Studsvik Nuclear developed a concept for disposal of steam generators, also involving experiences made in Sweden. The concept comprises transport preparations and necessary supporting documents, the complete logistics chain, steam generator treatment and the processing of arising residues and materials not suitable for recycling. The first components to be prepared, shipped and treated according to this concept were four steam generators from the decommissioning of the German NPP Stade which were removed from the plant and shipped to the processing facility during the third quarter of 2007. Although the plant had undergone a full system decontamination, due to the remaining contamination in a number of plugged tubes the steam generators had to be qualified as industrial packages, type 2 (IP-2 packages), and according to a special requirement of the German Federal Office for Radiation Protection a license for a shipment under special arrangement had to be applied for. The presentation gives an overview of the calculations and evidences required within the course of the IP-2 qualification, additional requirements of the competent authorities during the licensing procedure as

  2. Management of very low level waste from decommissioning of the A-1 Jaslovske Bohunice nuclear power plant in Slovakia

    International Nuclear Information System (INIS)

    Burclova, J.; Konecny, L.; Mrskova, A.

    2000-01-01

    Efforts were made to accelerate decommissioning, particularly of the nuclear power plant A1 of the HWGCR type. Progress made and current developments in this subject area are reviewed. Radioactive waste categories are described along with release criteria. An overview is provided on contaminated scrap and the sorting of contaminated soil and concrete. (author)

  3. Nuclear power plant decommissioning. January 1972-September 1988 (Citations from the NTIS data base). Report for January 1972-September 1988

    International Nuclear Information System (INIS)

    1988-10-01

    This bibliography contains citations concerning nuclear power plant phase-out and decommissioning. Included are case histories of the dismantling process, hazardous-waste management, site monitoring, and economic aspects of the phase-out. (Contains 178 citations fully indexed and including a title list.)

  4. Development of Heavy-Duty and High-Precision Hydraulic Manipulator for Inspection, Maintenance and Decommission of Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Sung Uk; Seo, Yong-chil; Jung, Kyung Min; Kim, Chang-hoi; Choi, Byung-seon; Moon, Jei-kwon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2016-10-15

    Robotic manipulators have been used for inspection, maintenance and decommission of nuclear power plants because nuclear power plants have high radiation and human workers cannot easily access the plants. And also, to inspecting, maintaining and decommissioning nuclear power plants require various manipulators. Only one manipulator cannot response to many required tasks. The existing manipulators that was used at nuclear power plants can only operate only focused specific task and cannot be used at several tasks. The actuators used at manipulators are varied and many companies sell actuators depending on power, torque and speed. However, the commercial product is not standardized. Therefore, the development of manipulator is time consuming and expensive. The essential item of a manipulator is an actuator module. If actuator module is standardized, it’s easier to develop a manipulator and also maintain a manipulator. Recently, manipulator having high-radiation, high-duty and high-precision is necessary to inspection, maintain and decommissioning of nuclear power plants. Hydraulic actuator has been used to development high-duty manipulator. But control performance of a hydraulic actuator is not better than that of an electric actuator so that hydraulic manipulator cannot easily satisfy the required precision. In this paper, we developed high-duty and high-precision actuator modules and hydraulic manipulator using the developed actuator modules. The developed hydraulic manipulator have a payload of 250kg and a precision of ±1mm. Four modularized hydraulic actuator modules were developed for inspection, maintenance and decommission. Using the developed actuator modules, the manipulator for decommissioning is easily developed. And also, various manipulators having different kinematic structure for specific tasks will be easily developed by using hydraulic modules.

  5. Development of Heavy-Duty and High-Precision Hydraulic Manipulator for Inspection, Maintenance and Decommission of Nuclear Power Plants

    International Nuclear Information System (INIS)

    Lee, Sung Uk; Seo, Yong-chil; Jung, Kyung Min; Kim, Chang-hoi; Choi, Byung-seon; Moon, Jei-kwon

    2016-01-01

    Robotic manipulators have been used for inspection, maintenance and decommission of nuclear power plants because nuclear power plants have high radiation and human workers cannot easily access the plants. And also, to inspecting, maintaining and decommissioning nuclear power plants require various manipulators. Only one manipulator cannot response to many required tasks. The existing manipulators that was used at nuclear power plants can only operate only focused specific task and cannot be used at several tasks. The actuators used at manipulators are varied and many companies sell actuators depending on power, torque and speed. However, the commercial product is not standardized. Therefore, the development of manipulator is time consuming and expensive. The essential item of a manipulator is an actuator module. If actuator module is standardized, it’s easier to develop a manipulator and also maintain a manipulator. Recently, manipulator having high-radiation, high-duty and high-precision is necessary to inspection, maintain and decommissioning of nuclear power plants. Hydraulic actuator has been used to development high-duty manipulator. But control performance of a hydraulic actuator is not better than that of an electric actuator so that hydraulic manipulator cannot easily satisfy the required precision. In this paper, we developed high-duty and high-precision actuator modules and hydraulic manipulator using the developed actuator modules. The developed hydraulic manipulator have a payload of 250kg and a precision of ±1mm. Four modularized hydraulic actuator modules were developed for inspection, maintenance and decommission. Using the developed actuator modules, the manipulator for decommissioning is easily developed. And also, various manipulators having different kinematic structure for specific tasks will be easily developed by using hydraulic modules

  6. A study on people's awareness about the restarting and decommissioning of nuclear power plants

    International Nuclear Information System (INIS)

    Goto, Manabu; Sakai, Yukimi

    2015-01-01

    In this study, we conducted two questionnaire surveys targeting a total of 918 respondents living in the cities of Kyoto, Osaka and Kobe, in order to elucidate people's awareness of three things: 1) restart of nuclear power plants; 2) extension of the operation period of aging plants; and 3) decommissioning. The results are as follows: 1) People who think that electrical power companies voluntarily take higher safety measures trust the power companies and do not oppose the restart of the nuclear power plants, as compared to people who think that power companies only meet the requirements set by the nuclear regulatory agency. 2) When people were given information about aging measures and conforming to new regulatory standards, their anxiety toward the operation of aging plants was reduced. 3) People thought that decommissioning work was important for society. However, a small number of people thought it was a job worthwhile doing. (author)

  7. Decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Lunning, W.H.

    1977-01-01

    Collaborative studies are in progress in the U.K. between the U.K.A.E.A., the Generating Boards and other outside bodies, to identify the development issues and practical aspects of decommissioning redundant nuclear facilities. The various types of U.K.A.E.A. experimental reactors (D.F.R., W.A.G.R , S.G.H.W.R.) in support of the nuclear power development programme, together with the currently operating commercial 26 Magnox reactors in 11 stations, totalling some 5 GW will be retired before the end of the century and attention is focussed on these. The actual timing of withdrawal from service will be dictated by development programme requirements in the case of experimental reactors and by commercial and technical considerations in the case of electricity production reactors. Decommissioning studies have so far been confined to technical appraisals including the sequence logic of achieving specific objectives and are based on the generally accepted three stage progression. Stage 1, which is essentially a defuelling and coolant removal operation, is an interim phase. Stage 2 is a storage situation, the duration of which will be influenced by environmental pressures or economic factors including the re-use of existing sites. Stage 3, which implies removal of all active and non-active waste material and returning the site to general use, must be the ultimate objective. The engineering features and the radioactive inventory of the system must be assessed in detail to avoid personnel or environmental hazards during Stage 2. These factors will also influence decisions on the degree of Stage 2 decommissioning and its duration, bearing in mind that for Stage 3 activation may govern the waste disposal route and the associated radiation man-rem exposure during dismantling. Ideally, planning for decommissioning should be considered at the design stage of the facility. An objective of present studies is to identify features which would assist decommissioning of future systems

  8. Nuclear decommissioning in Italy

    International Nuclear Information System (INIS)

    Tripputi, I.

    2005-01-01

    in the oil market, both in terms of barrel cost and in terms of security of supplies, and the severe black-outs that have plagued also Italy (the major one in September 2003 lasting in some areas for about 24 hours), have started a widespread discussion about energy alternatives and strategic energy plans. In this frame an increasing number of politicians and scientists are calling for a reconsideration of nuclear energy as a viable option also for Italy in a new energy mix. It is clear that public acceptance of nuclear energy is strictly connected not only to the demonstration of high safety standards of future plants, but also to the solution of radioactive waste disposal and of plant decommissioning. This is the link that could make the SOGIN mission even more strategic for the country

  9. Technical and legal aspects of the decommissioning of nuclear installations

    International Nuclear Information System (INIS)

    Rowden, M.A.; Fowler, S.E.

    1983-01-01

    Many of the plants licensed at the start of nuclear power programmes will require decommissioning in the 1990's and this issue should now be confronted by the nuclear industry, its regulators and governments. This paper deals with the United States programme and experience in the decommissioning of nuclear installations and describes alternative decommissioning methods including safety and financial aspects. (NEA) [fr

  10. Safety culture and organisational issues specific to the transitional phase from operation to decommissioning of the Ignalina Nuclear Power Plant

    International Nuclear Information System (INIS)

    Medeliene, D.

    2005-01-01

    The PHARE project Support to State Nuclear Power Safety Inspectorate for safety culture and organisational issues specific to the pre-shutdown phase of Ignalina Nuclear Power Plant was aimed at providing assistance to VATESI in their task to oversee that the Ignalina Nuclear Power Plant's management and staff are able to provide an acceptable level of reactor safety taking into account possible safety culture related problems that may occur due to the decision of an early closure of both units. Safety culture is used as a concept to characterise the attitudes, behaviour and perceptions of people that are important in ensuring the safety of nuclear power facility. Since the Chernobyl accident, the International Atomic Energy Agency (IAEA) has been active in creating guidance for ensuring that an adequate safety culture can be created and maintained. The transition from operation to decommissioning introduces uncertainty for both the organisation and individuals. This creates new challenges that need to be dealt with. Although safety culture and organisational issues have to be addressed during the entire life cycle of a nuclear power plant, owing to these special challenges, it should be especially highlighted during the transitional period from operation to decommissioning. Nuclear safety experts from Sweden, Finland, Italy, the UK and Germany, as well as Lithuanian specialists, participated in the project, and it proved to be a most effective way to share experience. The aim of this brochure is to provide information about: the importance of safety culture issues during the transitional phase from operation to decommissioning of Ignalina Nuclear Power Plant; the purpose, activities and results of this PHARE project; recommendations that are provided by western experts concerning the management of safety culture issues specific to the pre-decommissioning phase of Ignalina Nuclear Power Plant. (author)

  11. Technical and economical problems of decommissioning nuclear power plants (NPP) in Russia

    International Nuclear Information System (INIS)

    Vaneev, M.

    2001-01-01

    The introduction per new century has brought to atomic Engineering many new problems. One of them, which has got a serious urgency, we now shall consider. It is a problem of decommissioning NPP in Russia. By 2014 all maintained nowadays NPP in Russian Federation will develop the regular service life. And all of them on idea should be removed from operation. But, as we understand, in today's difficult economic conditions, to it NPP the procedure of prolongation of service life will be applied, and where it is impossible by virtue of the various reasons, the procedure of translation NPP in nuclear - safe condition and in a mode of a long storage under supervision, before acceptance of the decision about a method and way of financing of a decommissioning will be applied. Possible the following variants will be: use platforms of the old NPP for construction new NPP, or using as burial place NPP. The variant of a decommissioning up to a condition 'green grass' is represented unprofitable because of its dearness. The similar decommissioning was carried out in Japan. Was removed from operation research reactor of a type WWR. The expenses for this method of a decommissioning considerably surpass expenses for a method of a burial place NPP basically because of high cost of dismantle and transportation in long-term storehouses of the 1 contour equipment. The most urgent problem of decommissioning NPP, which developed their regular service life - is financing this final stage of a exploitation cycle of the block. I shall remind, that the financing is carried out from uniform fund of decommissioning. The formation of this fund occurs by deduction 1.3 % of cost of the put electric power to the consumers by all maintained NPP of Russia. The expenditure of this fund is carried on time on some tens years. They are spent for 3 basic stages: preparation to decommissioning NPP, long endurance under supervision, dismantle and burial the NPP equipment. Nowadays on faculty NPP MPEI

  12. Factors relevant to the decommissioning of land-based nuclear reactor plants

    International Nuclear Information System (INIS)

    1980-01-01

    This document applies to all classes of land-based nuclear fission reactors, including those reactors used for the production of electricity or heat, for testing, for research, and for the production of radionuclides. The document covers the technical and administrative aspects related to the conduct of decommissioning, and to the associated radiation protection of man and his environment both during and after decommissioning. The document is intended to provide assistance to those responsible for planning or implementing the decommissioning of a land-based nuclear reactor. The user of this report is further encouraged to review past experience gained with nuclear facilities and the published technical data cited in the section entitled Bibliography

  13. Cost effective decommissioning and dismantling of nuclear power plants; Kosteneffizienz bei Stilllegung und Rueckbau von Kernkraftwerken

    Energy Technology Data Exchange (ETDEWEB)

    Wasinger, Karl [AREVA NP GmbH, Offenbach (Germany)

    2012-10-15

    As for any large and complex project, the basis for cost effective decommissioning and dismantling of nuclear power plants is established with the development of the project. Just as its construction, dismantling of a nuclear power plant is similarly demanding. Daily changing situations due to the progress of construction - in the present case progress of dismantling - result in significant logistical challenges for project managers and site supervisors. This will be aggravated by the fact that a considerable amount of the removed parts are contaminated or even activated. Hence, not only occupational health, safety and environmental protection is to be assured, employees, public and environment are to be adequately protected against the adverse effect of radioactive radiation as well. Work progress and not least expenses involved with the undertaking depend on adherence to the planned course of actions. Probably the most frequent cause of deviation from originally planned durations and costs of a project are disruptions in the flow of work. For being enabled to counteract in a timely and efficient manner, all required activities are to be comprehensively captured with the initial planning. The effect initial activities may have on subsequent works until completion must particularly be investigated. This is the more important the larger and more complex the project actually are. Comprehensive knowledge of all the matters which may affect the progress of the works is required in order to set up a suitable work break-down structure; such work break-down structure being indispensable for successful control and monitoring of the project. In building the related organizational structure of the project, all such stakeholders not being direct part of the project team but which may potentially affect the progress of the project are to be considered as well. Cost effective and lost time injury free dismantling of decommissioned nuclear power plants is based on implementing

  14. Strategically oriented project management of the decommissioning of nuclear power plants; Strategieorientiertes Projektmanagement der Stilllegung von Kernkraftwerken

    Energy Technology Data Exchange (ETDEWEB)

    Kemmeter, Sascha [Conscore GmbH, Duesseldorf (Germany); Woempener, Andreas [Duisburg-Essen Univ., Duisburg (Germany). Lehrstuhl fuer ABWL und Controlling

    2013-12-15

    Due to the politically induced change of the energy sector in Germany, the operators of nuclear power plants had to react and to deal with completely new conditions concerning the decommissioning of their plants on short notice. Therefore the operators have to devise new strategies for controlling their decommissioning and dismantling projects in a short amount of time and most often similarly for several plants. Two fundamental procedures are possible for the successful controlling of these dismantling projects: a centralized or a decentralized management organization. How these project control processes can be realized in an optimal way, is, next to other economic specifications of the dismantling of nuclear power plants, the topic of a new research project of the Chair of Management Accounting at the University Duisburg-Essen. In that process, results and experiences from other research and practical projects concerning general large-scale projects are being used. Selected findings have been compiled and are being discussed in this paper. (orig.)

  15. Ethics of nuclear decommissioning

    International Nuclear Information System (INIS)

    Surrey, John

    1992-01-01

    What to do with the numerous reactors that reach the end of their operating lives over the next 30 years involves ethical issues of an intergenerational kind. This essay examines various nuclear decommissioning options in the light of the ethical issues. Prompt dismantlement seems preferable to other options involving postponed dismantlement, entombment of some kind or doing nothing. It would avoid bequeathing future generations with the disamenity of entombed reactors or responsibility for dismantling other disused reactors. The choice of option also depends on the health risks through time and whether a sufficient decommissioning fund exists to avoid handing down debt and constrained choice. There is a strong case for supporting research and development from public funds to develop the technology and reduce both the health risks and the costs, especially if dismantlement is left to a future generation. (author)

  16. An overview of reactor vessel internals segmentation for nuclear plant decommissioning

    International Nuclear Information System (INIS)

    Litka, T.J.

    1994-01-01

    Several nuclear plants have undergone reactor vessel (RV) internals segmentation as part of or in preparation for decommissioning the plant. In addition, several other nuclear facilities are planning for similar work efforts. The primary technology used for segmentation of RV internals, whether in-air or underwater is Plasma Arc Cutting (PAC). Metal Disintegration Machining (MDM) is also used for difficult to make cuts. PAC and MDM are deployed by various means including Long Handled Tools (LHTs), fixtures, tracks, and multi-axis manipulators. These enable remote cutting due to the radiation and/or underwater environment. A Boiling Water Reactor (BWR), a Pressurized Water Reactor (PWR), and a High Temperature Gas Reactor (HTGR) have had their internals removed and segmented using PAC and MDM. The cutting technology used for each component, location of cut, cut geometry and environment had to be determined well before the actual cutting operations. This allowed for the design, fabrication, and testing of the delivery systems. The technologies, selection process, and methodology for RV internals segmentation will be discussed in this paper

  17. Topical Session on Funding Issues in Connection with Decommissioning of Nuclear Power Plants - 9 November 2004

    International Nuclear Information System (INIS)

    2006-01-01

    Set up by the Radioactive Waste Management Committee (RWMC), the WPDD brings together senior representatives of national organisations who have a broad overview of Decommissioning and Dismantling (D and D) issues through their work as regulators, implementers, R and D experts or policy makers. These include representatives from regulatory authorities, industrial decommissioners from the NEA Co-operative Programme on Exchange of Scientific and Technical Information on Nuclear Installation Decommissioning Projects (CPD), and cross-representation from the other NEA Committees. The EC is a member of the WPDD and the IAEA is participating as an observer. This broad participation provides good possibilities for the co-ordination efforts amongst activities in the international programmes. At its fifth meeting, in Paris, 8-10 November 2004, the WPDD held a topical session on the 'Funding Issues in Connection with Decommissioning of Nuclear Power Plants'. This report documents the topical session on Funding. An agenda of the Topical session can be found in Appendix 1. The topical session was meant to provide an exchange of information and experience on the following issues: Ethical Values; Actual Experiences of Fund Setting and Management; Uncertainties in Funding. At the end of each session time was allotted for a plenary discussion. The Rapporteur reviewed the main points and the lessons learnt at the end of the whole Topical Session. The Topical Session is documented as follows. A summary of the presentations, the country reports, the discussions and the key issues and lessons learnt is given in the main part of this report. The agenda of the Topical session can be found in Appendix 1 and the full papers supporting each presentation are given in Appendix 2. The national presentations on 'Actual experiences of Fund Setting and Management' in session 2 can be found in Appendix 3 and the national presentations on 'Uncertainties in Funding' in session 3 can be found in

  18. 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)

  19. Standard for design criteria for decommissioning of nuclear fuel reprocessing plants

    International Nuclear Information System (INIS)

    Graham, H.B.

    1976-01-01

    This paper was developed by the ANSI Standards Committee N46. Deactivation or shutdown followed by continued operation on the same site does not constitute decommissioning. It is felt that abandonment with entombment of the highly radioactive parts of the plant is the only economically feasible alternative

  20. Application of wire sawing method to decommissioning of nuclear power plant. Cutting test with turbine pedestal of thermal power plant

    International Nuclear Information System (INIS)

    Hasegawa, Hideki; Uchiyama, Noriyuki; Sugiyama, Kazuya; Yamashita, Yoshitaka; Watanabe, Morishige

    1995-01-01

    It is very important to reduce radioactive waste volume, and to reduce radiation dose to workers and to the public during dismantling of the activated concrete in the decommissioning stage of a nuclear power plant. For the above, we studied a dismantling method which can separate activated concrete from non-activated concrete safely and effectively. Considering the state of legal regulation about radioactive waste disposal, and the state of developing of decommissioning technologies, we come to a conclusion that wire sawing method is feasible as a concrete cutting method. This study was carried out to evaluate the availability of the wire sawing method to dismantling of concrete structures of nuclear power plants. This study consists of concrete cutting rate test and concrete block cutting test. The former is to obtain data about cutting rate with various steel ratios while the latter is to obtain data about working time and man hour of the whole work with wire sawing. Thirty-six year old turbine pedestal of a thermal power plant was selected as a test piece to simulate actual decommissioning work of nuclear power plant, taking its massive concrete volume and age. Taking account of the handling in the building, the wire sawing machine with motor driven was used in this study considering that it did not produce exhaust gas. The concrete cutting rate test was performed with parameter of steel ratio in the concrete, wire tension and cutting direction. In the concrete block cutting test, imaging the actual cutting situation, cubic blocks which side was approximately 1 meter were taken out, and a large block to be cut and to be taken out is a section of 1m x 1.5m x 10m. Test results are shown below. The difference of cutting rate was mainly caused by the difference of reinforcement steel ratio. Working time data of installation, removal of machines and cutting were obtained. Data on secondary waste (dust, drainage and sludge) and environmental effect (noise and

  1. Preparation for decommissioning of the Kozloduy Nuclear Power Plant units 1 and 2

    International Nuclear Information System (INIS)

    Delcheva, T.; Ribarski, V.; Demireva, E.

    2006-01-01

    The first decommissioning strategy of units 1 and 2 of Kozloduy NPP (KNPP) stipulated 3 phases: a 5 year phase including the post operation activities and preparation of the safe enclosure (SE); a 35 years SE period, followed by deferred dismantling. 'Updated Decommissioning Strategy for Units 1-4 of Kozloduy NPP' was issued in June 2006. The Updated Strategy is based on the so called 'Continuous Dismantling' Concept. The updated Strategy starts preparatory work earlier and then moves into dismantling work without a significant gap. The aim is to achieve a more optimal distribution of the dismantling activities along the time, saving jobs and the existing knowledge of the plant personnel during the decommissioning, and ensuring smooth and more effective use of financial and human resources and of the available infrastructure for waste treatment. This paper gives general information about the updated strategy and activities required for its implementation. (author)

  2. A study of a decommissioning activities classification structure for decommissioning of the project management of a nuclear power plant

    International Nuclear Information System (INIS)

    Park, Hee Seong; Park, Seung Kook; Jin, Hyung Gon; Song, Chan Ho; Ha, Jei Hyun; Moon, Jei kwon

    2015-01-01

    Decommissioning activities and requirements that was established in the planning stage should be organized systematically in the course of dismantling the NPP. The work breakdown structure is essential to ensuring that all the project scope is identified, estimated and executed. The project manager needs to ensure that a WBS is established early in the project and maintained throughout the project life cycle. A project management system is ongoing under the circumstance of having no experience dismantling the NPP. The system related to the NPP decommissioning should have technical criteria as well as regulatory requirements in the full scale of decommissioning stage. In the dismantling stage, decommissioning plan document should include the results of radiation/radioactivity characterization, evaluation of the amount of dismantled waste, calculation of the expose dose rate, evaluation of decommissioning cost and schedule after shutdown

  3. A study of a decommissioning activities classification structure for decommissioning of the project management of a nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Park, Hee Seong; Park, Seung Kook; Jin, Hyung Gon; Song, Chan Ho; Ha, Jei Hyun; Moon, Jei kwon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-05-15

    Decommissioning activities and requirements that was established in the planning stage should be organized systematically in the course of dismantling the NPP. The work breakdown structure is essential to ensuring that all the project scope is identified, estimated and executed. The project manager needs to ensure that a WBS is established early in the project and maintained throughout the project life cycle. A project management system is ongoing under the circumstance of having no experience dismantling the NPP. The system related to the NPP decommissioning should have technical criteria as well as regulatory requirements in the full scale of decommissioning stage. In the dismantling stage, decommissioning plan document should include the results of radiation/radioactivity characterization, evaluation of the amount of dismantled waste, calculation of the expose dose rate, evaluation of decommissioning cost and schedule after shutdown.

  4. Safety analysis of disposal of decommissioning wastes from Loviisa nuclear power plant

    International Nuclear Information System (INIS)

    Vieno, T.; Nordman, H.; Rasilainen, K.; Suolanen, V.

    1987-12-01

    The repository for decommissioning wastes from the Loviisa nuclear power plant consisting of two 445 MWe PWR units is planned to be excavated at the depth of 90-130 meters in the bedrock of the power plant site. The reactor vessels weighing each about 215 tons will be transferred each in one piece into the repository. They are emplaced in an upright position in big holes excavated in the bottom of repository caverns. The reactor vessel internals are then emplaced inside the vessels. Finally, the vessels will be filled with concrete and the lids will be emplaced and sealed. Steam generators and pressurizers will also be disposed of uncutted. Other decommissioning wastes will be cut into smaller pieces and emplaced in concrete or wooden containers. The repository will be situated on the small island on which the power plant is located. The groundwater on the island contains two zones of different salinity: an upper zone of fresh, flowing groundwater and a lower zone of saline, stagnant groundwater where the repository will be situated. Three groundwater scenarios have been considered in the safety analysis: a scenario based on the present site conditions, an altered scenario where the repository is assumed to be situated in a zone of fresh, flowing groundwater and a distruptive event scenario with an intensive groundwater flow through the repository. The obtained results of the analysis show clear safety margins. In the basic scenario the maximum annul dose rate is 6x10 -14 Sv/a via the local sea pathways, 6x10 -11 Sv/a via the lake pathways and 4x10 -8 Sv/a via a well bored in the vicinity of the repository. In the altered groundwater scenario the maximum annual dose rate is 4x10 -10 Sv/a via the sea pathways, 3x10 -7 Sv/a via the lake pathways and 1x10 -5 Sv/a via the well pathway. In the unlikely disruptive event scenario the corresponding dose rates are 8x10 -10 Sv/a (sea), 7x10 -7 Sv/a (lake) and 2x10 -4 Sv/a (well)

  5. VGH Mannheim: legitimacy of the decommissioning license for a nuclear power plant; VGH Mannheim: Rechtmaessigkeit der Stilllegungsgenehmigung fuer ein Kernkraftwerk

    Energy Technology Data Exchange (ETDEWEB)

    Anon.

    2015-03-16

    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.

  6. The community's research and development programme on decommissioning of nuclear power plants. Third annual progress report (year 1982)

    International Nuclear Information System (INIS)

    1984-01-01

    This is the third progress report of the European Community's programme (1979-83) of research on the decommissioning of nuclear power plants. It covers the year 1982 and follows the 1980 and 1981 reports (EUR 7440, EUR 8343). Since 1982 was a very active year of research under the programme, this report contains a large amount of results. Besides, the work programmes of some additional research contracts, awarded through 1982, are described

  7. Decommissioning Technology Development for Nuclear Research Facilities

    International Nuclear Information System (INIS)

    Lee, K. W.; Kang, Y. A.; Kim, G. H.

    2007-06-01

    It is predicted that the decommissioning of a nuclear power plant would happen in Korea since 2020 but the need of partial decommissioning and decontamination for periodic inspection and life extension still has been on an increasing trend and its domestic market has gradually been extended. Therefore, in this project we developed following several essential technologies as a decommissioning R and D. The measurement technology for in-pipe radioactive contamination was developed for measuring alpha/beta/gamma emitting nuclides simultaneously inside a in-pipe and it was tested into the liquid waste transfer pipe in KRR-2. And the digital mock-up system for KRR-1 and 2 was developed for choosing the best scenarios among several scenarios on the basis of various decommissioning information(schedule, waste volume, cost, etc.) that are from the DMU and the methodology of decommissioning cost estimation was also developed for estimating a research reactor's decommissioning cost and the DMU and the decommissioning cost estimation system were incorporated into the decommissioning information integrated management system. Finally the treatment and management technology of the irradiated graphites that happened after decommissioning KRR-2 was developed in order to treat and manage the irradiated graphites safely

  8. Decommissioning Technology Development for Nuclear Research Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Lee, K. W.; Kang, Y. A.; Kim, G. H. (and others)

    2007-06-15

    It is predicted that the decommissioning of a nuclear power plant would happen in Korea since 2020 but the need of partial decommissioning and decontamination for periodic inspection and life extension still has been on an increasing trend and its domestic market has gradually been extended. Therefore, in this project we developed following several essential technologies as a decommissioning R and D. The measurement technology for in-pipe radioactive contamination was developed for measuring alpha/beta/gamma emitting nuclides simultaneously inside a in-pipe and it was tested into the liquid waste transfer pipe in KRR-2. And the digital mock-up system for KRR-1 and 2 was developed for choosing the best scenarios among several scenarios on the basis of various decommissioning information(schedule, waste volume, cost, etc.) that are from the DMU and the methodology of decommissioning cost estimation was also developed for estimating a research reactor's decommissioning cost and the DMU and the decommissioning cost estimation system were incorporated into the decommissioning information integrated management system. Finally the treatment and management technology of the irradiated graphites that happened after decommissioning KRR-2 was developed in order to treat and manage the irradiated graphites safely.

  9. Decommissioning of nuclear power facilities

    International Nuclear Information System (INIS)

    Nosovskij, A.V.; Vasil'chenko, V.N.; Klyuchnikov, A.A.; Yashchenko, Ya.V.

    2005-01-01

    This is the first manual in Ukraine giving the complete review of the decommissioning process of the nuclear power facilities including the issues of the planning, design documentation development, advanced technology description. On the base of the international and domestic experience, the issues on the radwaste management, the decontamination methods, the equipment dismantling, the remote technology application, and also the costs estimate at decommissioning are considered. The special attention to the personnel safety provision, population and environment at decommissioning process is paid

  10. Decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    1975-01-01

    Present concepts on stages of, designing for and costs of decommissioning, together with criteria for site release, are described. Recent operations and studies and assessments in progress are summarized. Wastes from decommissioning are characterized

  11. A special information campaign on decommissioning of unit 1 at the Ignalina Nuclear Power Plant started in Lithuania

    International Nuclear Information System (INIS)

    Vitkiene, E.

    2000-01-01

    A lack of understanding is felt in Lithuania of the importance of informing the public about nuclear energy, its safety and decisions related with nuclear energy in general. our swedish colleagues have noticed this flaw in our work and a joined decision has been taken to start a series of publicity projects. It was decided to work along three lines: a series of programmes on the national TV, support to the media of the town of Visaginas and creating an Internet page on the Ignalina Nuclear Power Plant decommissioning

  12. Study into the applicabilities of lasers for the dismantling of decommissioned nuclear power plant

    International Nuclear Information System (INIS)

    Haferkamp, H.; Bach, F.W.; Vinke, T.; Kinzel, A.; Mack, N.; Kuboschek, M.; Grobe, K.

    1989-01-01

    The project was intended to screen current laser technology for potential applications of laser beams in the dismantling of decommissioned nuclear power plant. As with CO 2 , Nd-YAG, or excimer lasers, developments clearly proceed towards higher output power. The market survey shows the CO 2 -laser to be the most efficient at present, with a great number of laser units available on the market in the range up to 5 kW, and some in the range up to 15 kW. The CO 2 -laser has exclusively been used so far for cutting work in steel plates thicker than 10 mm. Characteristic conditions of application include the high output power of more than 2 kW, long beam lengths, oxygen supply at strongly increased working pressure, sometimes from external sources. The maximum cutting work achieved in the laboratory was 110 mm in structural steel, 90 mm in austenitic steel, and 160 mm in concrete, all under conditions of easy access to the material. It remains to be examined whether steel cutting work at constrained positions will allow separation of wall thicknesses of more than 10 mm. Laser beam cutting under water is feasible in principle but has not been much studied yet. There also are only few sampling results of measurements of dust and aerosol quantities resulting from laser beam cutting work. (orig.) [de

  13. A technology-assessment methodology for electric utility planning: With application to nuclear power plant decommissioning

    International Nuclear Information System (INIS)

    Lough, W.T.

    1987-01-01

    Electric utilities and public service commissions have not taken full advantage of the many proven methodologies and techniques available for evaluating complex technological issues. In addition, evaluations performed are deficient in their use of (1) methods for evaluating public attitudes and (2) formal methods of analysis for decision making. These oversight are substantiated through an examination of the literature relevant to electric utility planning. The assessment process known as technology assessment or TA is proposed, and a TA model is developed for route in use in utility planning by electric utilities and state regulatory commissions. Techniques to facilitate public participation and techniques to aid decision making are integral to the proposed model and are described in detail. Criteria are provided for selecting an appropriate technique on a case-by-case basis. The TA model proved to be an effective methodology for evaluating technological issues associated with electric utility planning such as decommissioning nuclear power plants. Through the use of the nominal group technique, the attitudes of a group of residential ratepayers were successfully identified and included in the decision-making process

  14. Evolution of radiation protection of overall decommissioning and Dismantling of a Nuclear Power Plants

    International Nuclear Information System (INIS)

    Ortiz, M. T.; Ondaro, M.; Irun, I.; Just, J.

    2000-01-01

    From the point of view of Radiological Protection, the overall Decommissioning and Dismantling (D and D) Plan of a Nuclear Power Plant cannot be considered in isolation without considering the evolution of the radiological characteristics of the installation and the site itself from previous, during and final states. This experience of D and D is the first in Spain and in other European countries due to several aspects: 1) the reference reactor technology, 2) total grass power, and 3) management of a great amount of materials to be released. Three decommissioning alternatives were studied: Indefinite maintenance in shutdown state, Stage 1. Stage 2 for the defuelled reactor vessel and contents, with decontamination of most of the rest of the site. Immediate dismantling to Stage 3. Stage 2 was the alternative selected with the release of 80% of the site, keeping the remaining 20% of the site as a regulated area, housing the reactor vessel in a new structure and removing the radioactive waste. The above, along with the fact that this is a specific type of natural uranium-graphite-gas plant (NUGG) and that ownership of the facility has been transferred for dismantling (from HIFRENSA to ENRESA), implies a series of preliminary considerations that, for the purposes of this article, are compiled in the following aspects: a) Preliminary phase prior to transfer, b) Preparatory phase, and c) Dismantling phase. This paper describes aspects under the D and D experiences at CN-V1 NPP, now in progress, from the point of view of the radiological aspects in relation with the continuous updating of the source term. Operative Radiological nuclide vectors, applicable in the Radiation Protection tasks, are also commented to prevent and evaluate several risks during the execution of the works. Finally, there is a description of the results obtained from the work performed to decay the three actual nuclide vectors, to evaluate and obtain activity calculations for the release of the

  15. Joint US/Russian study on the development of a decommissioning strategy plan for RBMK-1000 unit No. 1 at the Leningrad Nuclear Power Plant

    International Nuclear Information System (INIS)

    1997-12-01

    The objective of this joint U.S./Russian study was to develop a safe, technically feasible, economically acceptable strategy for decommissioning Leningrad Nuclear Power Plant (LNPP) Unit No. 1 as a representative first-generation RBMK-1000 reactor. The ultimate goal in developing the decommissioning strategy was to select the most suitable decommissioning alternative and end state, taking into account the socioeconomic conditions, the regulatory environment, and decommissioning experience in Russia. This study was performed by a group of Russian and American experts led by Kurchatov Institute for the Russian efforts and by the Pacific Northwest National Laboratory for the U.S. efforts and for the overall project

  16. Joint U.S./Russian Study on the Development of a Preliminary Cost Estimate of the SAFSTOR Decommissioning Alternative for the Leningrad Nuclear Power Plant Unit #1

    Energy Technology Data Exchange (ETDEWEB)

    SM Garrett

    1998-09-28

    The objectives of the two joint Russian/U.S. Leningrad Nuclear Power Plant (NPP) Unit #1 studies were the development of a safe, technically feasible, economically acceptable decom missioning strategy, and the preliminary cost evaluation of the developed strategy. The first study, resulting in the decommissioning strategy, was performed in 1996 and 1997. The preliminary cost estimation study, described in this report, was performed in 1997 and 1998. The decommissioning strategy study included the analyses of three basic RBM.K decommission- ing alternatives, refined for the Leningrad NPP Unit #1. The analyses included analysis of the requirements for the planning and preparation as well as the decommissioning phases.

  17. Preliminary nuclear decommissioning cost study

    International Nuclear Information System (INIS)

    Sissingh, R.A.P.

    1981-04-01

    The decommissioning of a nuclear power plant may involve one or more of three possible options: storage with surveillance (SWS), restricted site release (RSR), and unrestricted site use(USU). This preliminary study concentrates on the logistical, technical and cost aspects of decommissioning a multi-unit CANDU generating station using Pickering GS as the reference design. The procedure chosen for evaluation is: i) removal of the fuel and heavy water followed by decontamination prior to placing the station in SWS for thiry years; ii) complete dismantlement to achieve a USU state. The combination of SWS and USU with an interim period of surveillance allows for radioactive decay and hence less occupational exposure in achieving USU. The study excludes the conventional side of the station, assumes waste disposal repositories are available 1600 km away from the station, and uses only presently available technologies. The dismantlement of all systems except the reactor core can be accomplished using Ontario Hydro's current operating, maintenance and construction procedures. The total decommissioning period is spread out over approximately 40 years, with major activities concentrated in the first and last five years. The estimated dose would be approximately 1800 rem. Overall Pickering GS A costs would be $162,000,000 (1980 Canadian dollars)

  18. Uranium hexafluoride production plant decommissioning

    International Nuclear Information System (INIS)

    Santos, Ivan

    2008-01-01

    The Institute of Energetic and Nuclear Research - IPEN is a research and development institution, located in a densely populated area, in the city of Sao Paulo. The nuclear fuel cycle was developed from the Yellow Cake to the enrichment and reconversion at IPEN. After this phase, all the technology was transferred to private enterprises and to the Brazilian Navy (CTM/SP). Some plants of the fuel cycle were at semi-industrial level, with a production over 20 kg/h. As a research institute, IPEN accomplished its function of the fuel cycle, developing and transferring technology. With the necessity of space for the implementation of new projects, the uranium hexafluoride (UF 6 ) production plant was chosen, since it had been idle for many years and presented potential leaking risks, which could cause environmental aggression and serious accidents. This plant decommission required accurate planning, as this work had not been carried out in Brazil before, for this type of facility, and there were major risks involving gaseous hydrogen fluoride aqueous solution of hydrofluoric acid (HF) both highly corrosive. Evaluations were performed and special equipment was developed, aiming to prevent leaking and avoid accidents. During the decommissioning work, the CNEN safety standards were obeyed for the whole operation. The environmental impact was calculated, showing to be not relevant.The radiation doses, after the work, were within the limits for the public and the area was released for new projects. (author)

  19. Methodology for environmental radiological assessment applied to the decommissioning of the Italian Nuclear Power Plants

    International Nuclear Information System (INIS)

    Petraglia, A.; Sabbarese, C.; Terrasi, F.; D'Onofrio, A.; Visciano, L.; Alfieri, S.; Esposito, A.M.; Migliore, G.; Mancini, F.; Napier, B.

    2006-01-01

    The present study is the second part of a program of characterization of the sites surrounding the Italian Nuclear Power Plants (NPPs) which are currently involved in decommissioning activities. In the first phase of the project an analysis of the Garigliano NPP was carried out and the reference groups of the population were established on the basis of a socio-economical survey of the site. A field campaign was carried out aiming to assess the 'zero level' due to the natural and past anthropogenic radioactivity [1, 2]. In the second part the study was extended to the other three Italian NPPs, namely Latina, Trino and Caorso. The radiological doses due to the planned and accidental releases during the decommissioning phases were calculated on the basis of environmental parameters related to the area of interest. These parameters include climatological, hydrological, geo morphological data. The implementation of transport and diffusion specific models of radionuclides in the environment was another step for the dose calculation using specific evaluation software. The current software (V.A.D.O.S.C.A.) specially built and used in the past for Italian NPPs has been replaced by the framework F.R.A.M.E.S.-GenII 2.0 which is a calculation code updated in the transport model and in the reference laws, and running under new computer operating systems. This code has been used to design the possible scenarios for each site by using conceptual calculation models which contain local input data and adequate dispersion models. The input data consist of (a) way and amount of radionuclide release in planned and accidental cases, (b) reference groups of population and their food habits, (c) climatic data of the area understudy. The dispersion models are implemented by considering releases in water (canal, river, sea) and in atmosphere. In order to allow a simplified, efficient and friendly utilisation of the Frames-GenII code, it has been enriched with a routine, D.S.A.-Reader, which

  20. Annex I.D. Social aspects of the decommissioning and reuse of the Greifswald nuclear power plant, Germany

    International Nuclear Information System (INIS)

    2006-01-01

    The German reunification caused enormous economic and social impacts in the regions previously part of the German Democratic Republic. The Greifswald nuclear power plant complex and the surrounding region were not exceptions in this respect. The entity Energiewerke Nord GmbH (EWN) is the legal successor of the former operator of the Greifswald complex, the Kombinat Bruno Leuschner, and accepted responsibility for the nuclear power plant sites at Greifswald and Rheinsberg after Germany's reunification in 1989. Shortly after the reunification, the operation of the units already completed, as well as all construction work, were completely stopped. Serious efforts were undertaken to restart the more modern units in Greifswald or to use the site for new nuclear and/or conventional power plants. However, the decision was firm to decommission all of the operation and construction activities, mainly because of a lack of political acceptance of the safety margin for the operation of these types of reactor design and the lack of a secured financial basis. Therefore EWN was faced with a formidable task: to safely and efficiently shut down and decommission both nuclear sites with all six nuclear power plants under the above mentioned boundary conditions. Initially difficulties were encountered with the massive personnel reductions that were required, from a total of over 13 600 persons (5600 operational staff and 8000 construction staff) to only about 1400 employees - a staffing reduction of about 90%. In addition, this occurred in combination with the introduction of a market based economy and the imposition of the laws and procedures of the Federal Republic of Germany on the reunified country. This had almost shocking social impacts for this region of Germany. EWN has now achieved successful restructuring of the company and has reached the optimal staffing for its execution of the decommissioning task

  1. Financial precautions for the decommissioning and dismantling of nuclear facilities

    International Nuclear Information System (INIS)

    Lukes, R.; Salje, P.; Feldmann, F.J.

    1978-01-01

    Starting from the fact that the disposal of nuclear-technical plants requires considerable means, the article asks if the financial guarantee for decommissioning and disposal should be requested before giving the licence. He shows the possibilities to ensure financial provisions and to describe their advantages and disadvantages. Planned decommissioning is dealt with separately from unplanned, decommissioning. (UN) [de

  2. Actuator Module of Robot Manipulator for Nuclear Power Plants Inspection, Maintenance and Decommission

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Sung Uk; Jung, Kyung Min; Seo, Young Chil; Choi, Byung Seon; Moon, Jei Kwon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-10-15

    For nuclear facility decommissioning, there are many different electrical manipulators to remotely dismantle a nuclear facility. Various manipulators will be necessary for inspection, maintenance and decommission. Only one manipulator cannot response to many required tasks. Therefore, several manipulators are necessary, depending on the payload capacity, their number of axes and their dexterity. Each manipulator was developed for a specific task. The actuators used at manipulator are varied and many companies sell actuators depending on power, torque and speed. However, the commercial product is not standardized. Therefore, the development of the manipulator is time consuming and expensive. The essential item of the manipulators is the actuator module. If actuator module is standardized, it is easier to develop manipulator. In this paper, we developed two electrical actuator modules to standardize the actuator module and easily develop a manipulator using the proposed actuator modules. The electrical actuator module has a motor, gear and rotary sensor, and is also waterproof. The electrically driven manipulator being used in the proposed actuator modules will be shown. Two modularized electrical actuator modules were developed for inspection, maintenance and decommission. Using the two developed actuator modules, the manipulator inspecting the welding area of reactor vessel is easily developed. Various modularized electrical actuator modules will be developed in terms of size and power.

  3. Decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Schneider, K.J.

    1979-01-01

    The Symposium was jointly sponsored by OECD/NEA and IAEA and was attended by more than 225 participants from 26 countries. Forty one papers were presented in eight sessions which covered the following topics: national and international policies and planning; engineering considerations relevant to decommissioning; radiological release considerations and waste classifications; decommissioning experience; and decontamination and remote operations. In addition, a panel of decommissioning experts discussed questions from the participants

  4. Report on the CSNI workshop on nuclear power plant transition from operation into decommissioning: human factors and organisation considerations

    International Nuclear Information System (INIS)

    2000-01-01

    The Senior Expert Group of the Committee on the Safety of Nuclear Installations (CSNI) proposed to Principal Working Group 1 (PWG1) of CSNI that a workshop be held to identify and discuss issues related to the impact of human factors and organisational aspects on decommissioning. This workshop was held in May 1999 in conjunction with the Joint NEA/IAEA/EC workshop on The Regulatory Aspects of Decommissioning. The workshop goals, as stated in the NEA Research Strategies for Human Performance, were 'to convene an information exchange meeting with interested Member countries in order to discuss areas of concern in this respect and identify possible areas that merit further research and their priorities'. The workshop highlighted a comparative lack of developed work in this area concerning the way in which organisational weaknesses can manifest themselves and how best to prevent or mitigate their effects. Eight key issues were identified and discussed by the participants. For each of the eight issues discussed by working groups, the potential risks of failing to address the Issue were identified. These potential risks formed a focal point for generating discussion about current experience and for drawing out gaps in current knowledge and understanding. From this base, participants then focused on specific types of information and questions that need further research in order to improve understanding and successful implementation of the transition from operations to decommissioning. The eight issues and suggested high priority needs are: - Creating a system to share international experience: Establish improved methods for obtaining and sharing information and experience on a regular basis in order to identify organisational and human factors issues, good practices and lessons learned as regulators and utilities deal with decommissioning. - Organisational memory and competence: Identify effective approaches to retain expertise during the transition from operations to

  5. Problems and necessary conditions of the safe shut down and decommissioning of Chernobyl nuclear power plant

    International Nuclear Information System (INIS)

    Umanets, M.

    1996-01-01

    The paper discusses the following issues: current situation in the nuclear power complex of Ukraine; Analyses of the current safety status at nuclear power units in Ukraine; analysis of violations in the NPPs performance; situation at Chernobyl nuclear power plant

  6. Development of decontamination technology for the decommissioned Bohunice A-1 nuclear power plant

    International Nuclear Information System (INIS)

    Krejci, F.; Majersky, D.; Solcanyi, M.; Sekely, S.; Kucharik, D.

    1991-01-01

    The main results of investigation into the decontamination technology for the equipment and buildings of the decommissioned A-1 nuclear power plant, achieved by the Nuclear Power Plants Research Institute in Trnava over the 1988-1990 period, are summarized. Mobile decontamination and recirculation equipment has been developed for pre-disassembling decontamination. A solution containing formic acid (19 g/l), EDTA-Na 4 (6 g/l) and thiourea (0.5 g/l) was used for decontamination of low-alloy steels; for materials from the steam generators and turbo-compressors, the decontamination factor (DF) of this solution was 30 to 150 per decontamination cycle. For high-alloy steels, a two-stage process comprising the use of an oxidation solution and a reduction solution appeared suitable. The oxidation solution contained potassium permanganate (0.6 g/l) and nitric acid (0.4 g/l), whereas the reduction solution, viz. Citrox 21, contained citric acid (0.5 g/l), oxalic acid (1.0 g/l) and EDTA-NA 4 (2.5 g/l). The DF is 10 to 50 in one oxidation-reduction cycle and 50-100 in two cycles. For the post-disassembling chemical decontamination, the contaminated material was cut into pieces 70 to 80 cm long, freed from grease and decontaminated chemically by submerging in the solution while applying treatment by ultrasound. A technology of electrochemical decontamination has also been developed. It appeared particularly suitable for structural materials of the primary coolant circuit comprising austenitic stainless steels and low-alloy steels after pre-disassembling chemical decontamination with remainders of the corrosion layer, and for structural materials of the secondary coolant circuit after chemical post-disassembling decontamination. Research in the field of decontamination of the building parts and of the outer surfaces of the structural materials concentrated mainly on the use of decontamination foams. Foaming solutions have been developed for the decontamination of PESL floors and

  7. Decommissioning of the MZFR nuclear power plant at the Karlsruhe Nuclear Research Center

    International Nuclear Information System (INIS)

    Demant, W.; Engelhardt, G.

    1991-01-01

    The MZFR multipurpose research reactor was permanently shut down on May 3, 1984. The envisaged decommissioning concept provides for disposal in five steps. The first two steps are devoted to preparatory work on dismantling and simplification of the systems needed for dismantling. In the third step the reactor auxiliary systems in the auxiliary building and in the fourth step the reactor systems in the reactor building will be dismantled. In the fifth step remote dismantling of the reactor pressure vessel and demolition of the building will take place. The scheduled date of completion is the year 2001. (author)

  8. Decommissioning of nuclear facilities: a growing activity in the world

    International Nuclear Information System (INIS)

    Anasco, Raul

    2001-01-01

    Nuclear power plants and nuclear facilities are no different from normal buildings and factories. Eventually, they become worn-out or old fashioned, too expensive to maintain or remodel. Decommissioning a nuclear facility is different from retiring other types because of the radioactivity involved. The most important consideration in nuclear decommissioning is to protect workers and the public from exposure to harmful levels of radiation. General criteria and strategies for the decommissioning of nuclear facilities are described as well as the present decommissioning activities of the Argentine CNEA (author)

  9. Economic impact associated with the decommissioning process of Vandellos I Nuclear Power Plant; Informe final. Impacto economico del desmantelamiento de la central nuclear Vandellos I

    Energy Technology Data Exchange (ETDEWEB)

    Rodriguez Silva, M.

    2005-07-01

    This economic study examines the economic impact associated with the decommissioning process of the Vandellos I Nuclear Power Plant, measured in terms of the global income that generated the ending of the Nuclear Power Plant activity, on the territory. To this end, we will take into account the total investment that has been necessary to complete the process of decommissioning. The economic impact is calculated using the Input- Output methodology. Briefly, the Input-Output model defines a group of accounting relationships that reflect the links taking place within the production system. The Input-Output model is based on the assumption that given an increase (decrease) in the final demand of one sector, this sector should produce more (less) to satisfy this new demand. At the same time, this will lead to demand more (less) intermediate consumption goods from the remainder sectors of the economy. Then, these sectors should produce more (less) and use more (less) intermediate inputs, and so on. Therefore, an increase (decrease) in the final demand of one sector multiplies the effect throughout the economy, following the interdependency relationships that exist among the productive activities. We will start by collecting an exhaustive economic information. This information covers the whole decommissioning process and the whole economic and productive activity of the province of Tarragona. Next, this information is used with the objective of building an Input-Output table of the province that will serve as a base to establish the global economic impact of Vandellos I. The incomes and employment generation has been evaluated in the province of Tarragona that, following the main assumptions, correspond to the global effects of the decommissioning. In addition, we have evaluated the income and employment generation within the region where the nuclear power plant is located. The total income impacts show a high multiplier effect due to the investment carried out during the

  10. Technology, safety, and costs of decommissioning a reference nuclear fuel reprocessing plant

    International Nuclear Information System (INIS)

    Schneider, K.J.; Jenkins, C.E.; Rhoads, R.E.

    1977-09-01

    Volume 2 comprises six appendices on: facility description; residual radioactivity inventory estimates; description and contamination levels of reference site; derivation of residual contamination levels; decommissioning mode detail; and decommissioning safety assessment details

  11. Hungarian Experience in Decommissioning Planning for the Paks Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Danko, G.; Takats, F. [Golder Associates, Budapest (Hungary)

    2013-08-15

    Preparations for the decommissioning planning, and the legal background are described in the first part, followed by a review of possible decommissioning strategies and the present reference scenario. Specific issues of financing the future decommissioning and the anticipated radioactive wastes and their activities are described in the latter part of the report. (author)

  12. Waste management considerations in nuclear facility decommissioning

    International Nuclear Information System (INIS)

    Elder, H.K.; Murphy, E.S.

    1981-01-01

    Decommissioning of nuclear facilities involves the management of significant quantities of radioactive waste. This paper summarizes information on volumes of waste requiring disposal and waste management costs developed in a series of decommissioning studies performed for the U.S. Nuclear Regulatory Commission by the Pacific Northwest Laboratory. These studies indicate that waste management is an important cost factor in the decommissioning of nuclear facilities. Alternatives for managing decommissioning wastes are defined and recommendations are made for improvements in waste management practices

  13. Evaluation of Nuclear Facility Decommissioning Projects program

    International Nuclear Information System (INIS)

    Baumann, B.L.

    1983-01-01

    The objective of the Evaluation of Nuclear Facility Decommissioning Projects (ENFDP) program is to provide the NRC licensing staff with data which will allow an assessment of radiation exposure during decommissioning and the implementation of ALARA techniques. The data will also provide information to determine the funding level necessary to ensure timely and safe decommissioning operations. Actual decommissioning costs, methods and radiation exposures are compared with those estimated by the Battelle-PNL and ORNL NUREGs on decommissioning. Exposure reduction techniques applied to decommissioning activities to meet ALARA objectives are described. The lessons learned concerning various decommissioning methods are evaluated

  14. Decommissioning of an uranium hexafluoride pilot plant

    International Nuclear Information System (INIS)

    Santos, Ivan; Abrao, Alcidio; Carvalho, Fatima M.S.; Ayoub, Jamil M.S.

    2009-01-01

    The Institute of Nuclear and Energetic Researches has completed fifty years of operation, belongs to the National Commission for Nuclear Energy, it is situated inside the city of Sao Paulo. The IPEN-CNEN/SP is a Brazilian reference in the nuclear fuel cycle, researches in this field began in 1970, having dominance in the cycle steps from Yellow Cake to Uranium Hexafluoride technology. The plant of Uranium Hexafluoride produced 35 metric tonnes of this gas by year, had been closed in 1992, due to domain and total transference of know-how for industrial scale, demand of new facilities for the improvement of recent researches projects. The Institute initiates decommissioning in 2002. Then, the Uranium Hexafluoride pilot plant, no doubt the most important unit of the fuel cycle installed at IPEN-CNEN/SP, beginning decommissioning and dismantlement (D and D) in 2005. Such D and D strategies, planning, assessment and execution are described, presented and evaluated in this paper. (author)

  15. Feedback experience from the decommissioning of Spanish nuclear facilities

    International Nuclear Information System (INIS)

    Santiago, J.L.

    2008-01-01

    The Spain has accumulated significant experience in the field of decommissioning of nuclear and radioactive facilities. Relevant projects include the remediation of uranium mills and mines, the decommissioning of research reactors and nuclear research facilities and the decommissioning of gas-graphite nuclear power plants. The decommissioning of nuclear facilities in Spain is undertaken by ENRESA, who is also responsible for the management of radioactive wastes. The two most notable projects are the decommissioning of the Vandellos I nuclear power plant and the decommissioning of the CIEMAT nuclear research centre. The Vandellos I power plant was decommissioned in about five years to what is known as level 2. During this period, the reactor vessel was confined, most plant systems and components were dismantled, the facility was prepared for a period of latency and a large part of the site was restored for subsequent release. In 2005 the facility entered into the phase of dormancy, with minimum operating requirements. Only surveillance and maintenance activities are performed, among which special mention should be made to the five-year check of the leak tightness of the reactor vessel. After the dormancy period (25 - 30 years), level 3 of decommissioning will be initiated including the total dismantling of the remaining parts of the plant and the release of the whole site for subsequent uses. The decommissioning of the CIEMAT Research Centre includes the dismantling of obsolete facilities such as the research reactor JEN-1, a pilot reprocessing plant, a fuel fabrication facility, a conditioning plant for liquid and a liquid waste storage facility which were shutdown in the early eighties. Dismantling works have started in 2006 and will be completed by 2009. On the basis of the experience gained in the above mentioned sites, this paper describes the approaches adopted by ENRESA for large decommissioning projects. (author)

  16. Decommissioning of nuclear facilities: Feasibility, needs and costs

    International Nuclear Information System (INIS)

    DeLaney, E.G.; Mickelson, J.R.

    1985-01-01

    The Nuclear Energy Agency's Working Group on Decommissioning is preparing a study entitled ''Decommissioning of Nuclear Facilities: Feasibility, Needs and Costs.'' The study addresses the economics, technical feasibility and waste management aspects of decommissioning larger commercial reactors and nuclear support facilities. Experience on decommissioning small reactors and fuel cycle facilities shows that current technology is generally adequate. Several major projects that are either underway or planned will demonstrate decommissioning of the larger and more complex facilities. This experience will provide a framework for planning and engineering the decommissioning of the larger commercial reactors and fuel cycle facilities. Several areas of technology development are desired for worker productivity improvement, occupational exposure reduction, and waste volume reduction. In order to assess and plan for the decommissioning of large commercial nuclear facilities, projections have been made of the capacity of these facilities that may be decommissioned in the future and the radioactive waste that would be produced from the decommissioning of these facilities. These projections through the year 2025 are based on current data and the OECD reactor capacity forecast through the year 2000. A 25-year operating lifetime for electrical power generation was assumed. The possibilities of plant lifetime extension and the deferral of plant dismantlement make this projection very conservative

  17. Preliminary study on recycling of metallic waste from decommissioning of nuclear power plant for cask

    International Nuclear Information System (INIS)

    Ohe, Koichiro; Kato, Osamu; Saegusa, Toshiari

    1999-01-01

    Preliminary study was made on technology required to recycle of metallic waste from decommissioning for spent fuel storage cask and on quantity of the cask which can be produced by the metallic waste. The technical and institutional issues for the recycling were studied. The metallic waste from decommissioning may be technically used to a certain degree for manufacturing the casks. However, there were some technical issues to be solved. For example, the manufacturing factories should be established. The radioactive waste from the factories with radiation control should be handled and treated carefully. Quality of the cask should be properly controlled. The 'Clearance Levels' which allows to recycle decommissioning waste have been hardly enacted in Japan. Technical and economic evaluation on recycling of metallic waste from decommissioning for spent fuel storage cask should be conducted again after progress in recycling of radioactive waste of which radioactivity is below the 'Clearance Levels' in Japan. (author)

  18. Project and feedback experience on nuclear facility decommissioning

    Energy Technology Data Exchange (ETDEWEB)

    Santiago, J.L. [ENRESA (Spain); Benest, T.G. [United Kingdom Atomic Energy Authority, Windscale, Cumbria (United Kingdom); Tardy, F.; Lefevre, Ph. [Electricite de France (EDF/CIDEN), 69 - Villeurbanne (France); Willis, A. [VT Nuclear Services (United Kingdom); Gilis, R.; Lewandowski, P.; Ooms, B.; Reusen, N.; Van Laer, W.; Walthery, R. [Belgoprocess (Belgium); Jeanjacques, M. [CEA Saclay, 91 - Gif sur Yvette (France); Bohar, M.P.; Bremond, M.P.; Poyau, C.; Mandard, L.; Boissonneau, J.F.; Fouquereau, A.; Pichereau, E.; Binet, C. [CEA Fontenay aux Roses, 92 (France); Fontana, Ph.; Fraize, G. [CEA Marcoule 30 (France); Seurat, Ph. [AREVA NC, 75 - Paris (France); Chesnokov, A.V.; Fadin, S.Y.; Ivanov, O.P.; Kolyadin, V.I.; Lemus, A.V.; Pavlenko, V.I.; Semenov, S.G.; Shisha, A.D.; Volkov, V.G.; Zverkov, Y.A. [Russian Research Centre Kurchatov Inst., Moscow (Russian Federation)

    2008-11-15

    This series of 6 short articles presents the feedback experience that has been drawn from various nuclear facility dismantling and presents 3 decommissioning projects: first, the WAGR project that is the UK demonstration project for power reactor decommissioning (a review of the tools used to dismantle the reactor core); secondly, the dismantling project of the Bugey-1 UNGG reactor for which the dismantling works of the reactor internals is planned to be done underwater; and thirdly, the decommissioning project of the MR reactor in the Kurchatov Institute. The feedback experience described concerns nuclear facilities in Spain (Vandellos-1 and the CIEMAT research center), in Belgium (the Eurochemic reprocessing plant), and in France (the decommissioning of nuclear premises inside the Fontenay-aux-roses Cea center and the decommissioning of the UP1 spent fuel reprocessing plant at the Marcoule site). (A.C.)

  19. Project and feedback experience on nuclear facility decommissioning

    International Nuclear Information System (INIS)

    Santiago, J.L.; Benest, T.G.; Tardy, F.; Lefevre, Ph.; Willis, A.; Gilis, R.; Lewandowski, P.; Ooms, B.; Reusen, N.; Van Laer, W.; Walthery, R.; Jeanjacques, M.; Bohar, M.P.; Bremond, M.P.; Poyau, C.; Mandard, L.; Boissonneau, J.F.; Fouquereau, A.; Pichereau, E.; Binet, C.; Fontana, Ph.; Fraize, G.; Seurat, Ph.; Chesnokov, A.V.; Fadin, S.Y.; Ivanov, O.P.; Kolyadin, V.I.; Lemus, A.V.; Pavlenko, V.I.; Semenov, S.G.; Shisha, A.D.; Volkov, V.G.; Zverkov, Y.A.

    2008-01-01

    This series of 6 short articles presents the feedback experience that has been drawn from various nuclear facility dismantling and presents 3 decommissioning projects: first, the WAGR project that is the UK demonstration project for power reactor decommissioning (a review of the tools used to dismantle the reactor core); secondly, the dismantling project of the Bugey-1 UNGG reactor for which the dismantling works of the reactor internals is planned to be done underwater; and thirdly, the decommissioning project of the MR reactor in the Kurchatov Institute. The feedback experience described concerns nuclear facilities in Spain (Vandellos-1 and the CIEMAT research center), in Belgium (the Eurochemic reprocessing plant), and in France (the decommissioning of nuclear premises inside the Fontenay-aux-roses Cea center and the decommissioning of the UP1 spent fuel reprocessing plant at the Marcoule site). (A.C.)

  20. When a plant shuts down: The psychology of decommissioning

    International Nuclear Information System (INIS)

    Schulz, J.; Crawford, A.C.

    1993-01-01

    Within the next decade, 10 to 25 nuclear plants in the United States may be taken off line. Many will have reached the end of their 40-year life cycles, but others will be retired because the cost of operating them has begun to outweigh their economic benefit. Such was the case at Fort St. Vrain, the first decommissioning of a US commercial plant under new Nuclear Regulatory Commission (NRC) regulations. Two major problems associated with decommissioning plants have been obvious: (1) the technical challenges and costs of decommissioning, and (2) the cost of maintaining and finally decommissioning a plant after a safe storage (SAFSTOR) period of approximately 60 years. What has received little attention is the challenge that affects not only the people who make a plant work, but the quality of the solutions to these problems: how to maintain effective organizational performance during the process of downsizing and decommissioning and/or SAFSTOR. The quality of technical solutions for closing a plant, as well as how successfully the decommissioning process is held within or below budget, will depend largely on how effectively the nuclear organization functions as a social unit. Technical and people issues are bound together. The difficulty is how to operate a plant effectively when plant personnel have no sense of long-term security. As the nuclear power industry matures and the pace for closing operating plants accelerates, the time has come to prepare for the widespread decommissioning of plants. The industry would be well served by conducting a selective, industry-wide evaluation of plants to assess its overall readiness for the decommissioning process. A decommissioning is not likely to be trouble free, but with a healthy appreciation for the human side of the process, it will undoubtedly go more smoothly than if approached as a matter of dismantling a machine

  1. A state-of-the art on decommissioning of nuclear facilities in Japan

    International Nuclear Information System (INIS)

    Park, Seung Kook; Kim, Hee Reyoung; Chung, Un Soo; Jung, Ki Jung

    2002-05-01

    While proceeding the KRR-1 and 2 decommissioning project, we are carried out study for the state of the art on decommissioning of nuclear facilities in Japan. Also, we are studied for the research reactors and commercial power plant that has the object of decommissioning, and for the government and the organization related on decommissioning operation. We are investigated for decommissioning activities of nuclear facilities achieved by JAERI, and collected the information and data for decommissioning techniques and computational system through the JPDR(Japan Power Demonstration Reactor) decommissioning activities. Such techniques are applying for Tokai Power Station began the decommissioning project from last year, and for Fugen Nuclear Power Station to be planned the decommissioning from 2003. Recent techniques for decommissioning was acquired by direct contact. The status of the treatment for decommissioning waste and the disposal facility for the very low-level radioactive concrete wastes was grasped

  2. Some studies related to decommissioning of nuclear reactors

    International Nuclear Information System (INIS)

    Bergman, C.; Menon, S.

    1990-02-01

    Decommissioning of large nuclear reactors has not yet taken place in the Nordic countries. Small nuclear installations, however, have been dismantled. This NKA-programme has dealt with some interesting and important factors which have to be analysed before a large scale decommissioning programme starts. Prior to decommissioning, knowledge is required regarding the nuclide inventory in various parts of the reactor. Measurements were performed in regions close to the reactor tank and the biological shield. These experimental data are used to verify theoretical calculations. All radioactive waste generated during decommissioning will have to be tansported to a repository. Studies show that in all the Nordic countries there are adequate transport systems with which decommissioning waste can be transported. Another requirement for orderly decommissioning planning is that sufficient information about the plant and its operation history must be available. It appears that if properly handled and sorted, all such information can be extracted from existing documentation. (authors)

  3. BNFL nuclear decommissioning liabilities management program

    International Nuclear Information System (INIS)

    Colquhoun, A.P.

    1995-01-01

    The objective of this paper is to describe BNFL's policy and strategy for decommissioning and also to summarize the overall scope of nuclear liabilities in the wider field of waste retrieval and storage, as well as the dismantling and demolition aspects of decommissioning. BNFL's recently established organisational arrangements for discharging all types of these liabilities are explained, together with a review of practical progress in dealing with them. Organisational changes in recent years have amalgamated decommissioning work with operations covering waste storage and retrieval operations. A strategy of minimising residual activity in shutdown plants is pursued, followed by dismantling and demolition on appropriate time scales to minimise risk and cost. Since April 1995, a new BNFL subsidiary, Nuclear Liabilities Management Company Limited has taken responsibility for discharge of BNFL's Waste Retrieval and Decommissioning liabilities on all BNFL sites. NLM has the objectives of optimal and lowest cost management of liabilities and much clearer segregation of physical operations from project specification and planning. The Ministry of Defense (MoD) policy, strategy, work programmes and progress for the Atomic Weapons Establishment (AWE) are also outlined. MoD/AEA has established an equivalent strategy for dealing with its liabilities. (J.S.). 5 refs., 2 figs., 4 appends

  4. Decommissioning of naval nuclear ships

    International Nuclear Information System (INIS)

    Oelgaard, P.L.

    1993-10-01

    During the next decade the two major nuclear powers will each have to decommission more than 100 naval nuclear vessels, in particular submarines. The problems connected with this task is considered in this report. Firstly the size of the task is considered, i.e. the number of nuclear vessels that has to be decommissioned. Secondly the reactors of these vessels, their fuel elements, their power level, the number of reactors per vessel and the amount of radioactivity to be handled are discussed. Thirdly the decommissioning procedures, i.e. The removal of fuel from the vessels, the temporary storage of the reactor fuel near the base, and the cleaning and disposal of the reactor and the primary circuit components are reviewed. Finally alternative uses of the newer submarines are briefly considered. It should be emphasizes that much of the detailed information on which this report is based, may be of dubious nature, and that may to some extent affect the validity of the conclusions of the report. (au)

  5. Decommissioning in British Nuclear Fuels plc

    International Nuclear Information System (INIS)

    Colquhoun, A.

    1988-01-01

    Decommissioning projects at the BNFL Sellafield site have been selected taking the following into account; the need to gain experience in preparation for the decommissioning of the Magnox reactors and for the post Magnox stage; the need to develop larger scale projects; the need to be cost effective and to foster long term safety. The balance between prompt or delayed decommissioning has to consider operator dose uptake and radioactive waste management. The ten year plan for decommissioning at Sellafield is described briefly. Currently decommissioning is of the fuel pond and decanning plant, the Windscale Pile Chimneys, the coprecipitation plant and the uranium recovery plant. (author)

  6. The preliminary planning for decommissioning nuclear facilities in Taiwan

    International Nuclear Information System (INIS)

    Li, K.K.

    1993-01-01

    During the congressional hearing in 1992 for a $7 billion project for approval of the fourth nuclear power plant, the public was concerned about the decommissioning of the operating plants. In order to facilitate the public acceptance of nuclear energy and to secure the local capability for appropriate nuclear backend management, both technologically and financially, it is important to have preliminary planning for decommissioning the nuclear facilities. This paper attempted to investigate the possible scope of decommissioning activities and addressed the important regulatory, financial, and technological aspects. More research and development works regarding the issue of decommissioning are needed to carry out the government's will of decent management of nuclear energy from the cradle to the grave

  7. Managing radioactive wastes of nuclear power plants in operation and site decommissioning phases

    International Nuclear Information System (INIS)

    Ardalani, E.; Khadivi, S.

    2008-01-01

    A large nuclear reactor annually produces about 25-50 tons consumed Uranium. These consumed materials consist of Uranium and also Plutonium and Curium. In total, about three percent of these materials are remained from fission. Existing actinides (Uranium, Plutonium, and Curium) cause long-term and short-term radiation that could have harmful effects on the environment. In order to reduce the diverse effects of radioactive wastes in Nuclear Power Plants, different procedures are employed such as compaction, chemical treatment, vitrification, canning and sealing with concrete and safe storage. In this paper, the harmful effects of nuclear wastes on the environment are introduced and a management procedure is presented to minimize its diverse effects

  8. Decommissioning of nuclear facilities: COGEMA expertise devoted to UP1 reprocessing plant dismantling programme

    International Nuclear Information System (INIS)

    Gay, A.

    2001-01-01

    Over the last past decades, the French nuclear industry has acquired a great experience and know-how in the field of dismantling. Today this experience amounts to more than 200,000 hours. The fundamental aims within dismantling strategy are the same as for all nuclear facilities: minimising doses received by workers, minimising waste volume and adapting waste management to radioactivity levels, minimising costs. French experience is based on technologies which are currently used in nuclear maintenance facilities. Dismantling is a dynamic process especially in the field of decontamination (chemical and mechanical), cleaning, robotics and remote control operations. The strategy for the dismantling of former UP1 reprocessing plant is based on the feedback of experience gained through the dismantling of other facilities such as the AT1 workshop at La Hague. This workshop, a pilot plant for reprocessing of fast-breeder reactor fuels (Rapsodie and Phenix) has to be dismantled to IAEA level 3 (unrestricted site use), excluding civil works structures. Currently conducted by trained shifts, this dismantling project should end in 1999. The experience already acquired proves that chemical rinsings with the use of specific reagents is sufficient to decontaminate the hot cells and that the use of remote operations or robotics is not as important as previously envisaged. The UP1 reprocessing plant of Marcoule operated from 1958 to 1997. End of the operation was pronounced on the 31st of December 1997. 20,000 tons of spent fuels were reprocessed at UP1. The cleaning and dismantling operations at the Marcoule site depend upon the CEA, EDF and COGEMA. The Defence and Industry Ministries asked for a specific structure to be set up. An economic interest group called CODEM was created in May 1996. CODEM decides, finances and supervises dismantling operations, while respecting the constraints of nuclear safety, environmental protection and cost-effectiveness. The cleaning operations of

  9. The decommissioning of nuclear power stations

    International Nuclear Information System (INIS)

    Barker, F.

    1992-01-01

    This report has been commissioned by the National Steering Committee of Nuclear Free Local Authorities to provide: a comprehensive introduction to the technical, social, political, environmental and economic dimensions to nuclear power station decommissioning; an independent analysis of Nuclear Electric's recent change of decommissioning strategy; the case for wider public involvement in decision making about decommissioning; and a preliminary assessment of the potential mechanisms for achieving that essential wider public involvement

  10. Decommissioning of nuclear fuel cycle facilities. Safety guide

    International Nuclear Information System (INIS)

    2001-01-01

    The objective of this Safety Guide is to provide guidance to regulatory bodies and operating organizations on planning and provision for the safe management of the decommissioning of non-reactor nuclear fuel cycle facilities. While the basic safety considerations for the decommissioning of nuclear fuel cycle facilities are similar to those for nuclear power plants, there are important differences, notably in the design and operating parameters for the facilities, the type of radioactive material and the support systems available. It is the objective of this Safety Guide to provide guidance for the shutdown and eventual decommissioning of such facilities, their individual characteristics being taken into account

  11. Insights from a comprehensive evaluation of risk at spent fuel pools at decommissioning nuclear power plants in the U.S

    International Nuclear Information System (INIS)

    Kelly, G.; Palla, R.; Cheok, M.; Parry, G.

    2001-01-01

    Recently, the U.S. Nuclear Regulatory Commission (NRC) undertook the first comprehensive safety assessment (the study) of spent fuel pools at decommissioning nuclear power plants in the United States. Previous NRC studies of spent fuel pools applied only to commercial nuclear operating reactors. The NRC staff made site visits to four decommissioning sites, and determined that the configurations at the decommissioning plants were very different from that assumed in operating reactor spent fuel pool safety assessments previously performed. The safety assessment will help determine the technical basis for rule making for emergency preparedness, security, and indemnification for decommissioning reactors. The scenario investigated by the safety assessment is one where the pool inventory is lost, spent fuel is uncovered, the fuel heats up, rapid oxidation of the zirconium fuel cladding occurs, and a fuel clad zirconium fire commences, which results in significant off-site doses to the public. The assessment investigated a wide range of internal and external initiating events such as loss of pool cooling, seismic, fire, loss-of-offsite-power, heavy load drop, tornado missile, aircraft impact, and loss of inventory events. The assessment developed conditional recovery probabilities for extended recovery periods. Comparison to the U.S. NRC Safety Goals is made. (author)

  12. Decommissioning and demolition of the Greifswald nuclear power station

    International Nuclear Information System (INIS)

    Sterner, H.; Leushacke, D.; Rittscher, D.

    1995-01-01

    The unexpected decision to decommission the plants in Greifswald makes the management and disposal of fuels and plant waste a major issue to be solved as a precondition for decommissioning and dismantling. The decisive point in waste management is the existence of an interim store or repository of sufficient capacity to accept both the nuclear fuel and the plant waste and the considerable volumes of radioactive residues arising in dismantling. Current major activities include planning for decommissioning and demolition, and drafting of the licensing documents; removal of the fuel elements from the reactor units; construction of the northern interim store for fuel elements and residues. (orig./HP)

  13. Nuclear decommissioning planning, execution and international experience

    CERN Document Server

    2012-01-01

    A title that critically reviews the decommissioning and decontamination processes and technologies available for rehabilitating sites used for nuclear power generation and civilian nuclear facilities, from fundamental issues and best practices, to procedures and technology, and onto decommissioning and decontamination case studies.$bOnce a nuclear installation has reached the end of its safe and economical operational lifetime, the need for its decommissioning arises. Different strategies can be employed for nuclear decommissioning, based on the evaluation of particular hazards and their attendant risks, as well as on the analysis of costs of clean-up and waste management. This allows for decommissioning either soon after permanent shutdown, or perhaps a long time later, the latter course allowing for radioactivity levels to drop in any activated or contaminated components. It is crucial for clear processes and best practices to be applied in decommissioning such installations and sites, particular where any ...

  14. Socio-economic impact of nuclear reactor decommissioning at Vandellos I NPP

    International Nuclear Information System (INIS)

    Liliana Yetta Pandi

    2013-01-01

    Currently nuclear reactors in Indonesia has been outstanding for more than 30 years, the possibility of nuclear reactors will be decommissioned. Closure of the operation or decommissioning of nuclear reactors will have socio-economic impacts. The socioeconomic impacts occur to workers, local communities and wider society. In this paper we report on socio-economic impacts of nuclear reactors decommissioning and lesson learned that can be drawn from the socio-economic impacts decommissioning Vandellos I nuclear power plant in Spain. Socio-economic impact due to decommissioning of nuclear reactor occurs at installation worker, local community and wider community. (author)

  15. Decommission of nuclear ship 'MUTSU'

    International Nuclear Information System (INIS)

    Tateyama, Takeshi

    1996-01-01

    The nuclear-powered ship 'MUTSU' was decommissioned by removing the reactor room in June 1995, which was hoisted and transported by a floating crane to a shore storage room at Sekinehama, Aomori Prefecture. This work was carried out in three stages: extraction of the spent fuel assemblies and neutron sources, dismantling of the machinery in the reactor auxiliary room, and separation and transportation of the reactor together with the secondary shielding structure and surrounding hull. IHI mainly conducted the third stage work. The separation work of the reactor room structure using a semisubmersible barge is outlined. Stress analysis and design of the reactor room for lifting work is also described. (author)

  16. Decommissioning of four small nuclear waste storage buildings and an evaporation plant

    International Nuclear Information System (INIS)

    Hedvall, R.H.; Ellmark, C.; Stocker, P.

    2008-01-01

    A small-scale decommissioning concept was applied with staff from an earlier project wish strong knowledge of radiation protection, minimized radiation doses and environmental pollution. The project was therefore initiated with less than 10 people involved using standard hand held equipment. The aim of the decommissioning project was to set free as much material as possible, i.e. remove waste from the regulatory control regime and also free the remaining structures and buildings for conventional demolition and subsequent reuse of the property. Complete decommissioning will be concluded at the end of 2008 when all waste is taken case of. This is the fourth in a series of important decommissioning projects in Studsvik since the 1980s. Some of the conclusions are: 1) Obtain a group with well-known personnel that have been working together before for the entire project For a project larger than this, project management assistant would have made follow-up more efficient. Experts in instrumentation and statistics are also important. Also important is knowledge about practical decisions that would make the project more efficient in terms of time. Interviews and historical facts are important when choosing which nuclides are of most interest for measurements (but be critic). 2) Be sure all authoritative requirements are followed, like setting up a work environment plan at the entrance to the site and placing a fence around the work site. 3) Check all individual radiation exposures before project start and do whole body measurements both before and after the project. Urine samples should be taken if alpha contamination is a risk. 4) Calculate for unwanted and 'not what you expected' situations in the time schedule. 5) Be aware of contaminations and radiation sources outside the actual area. They might have to be moved. 6) Calculate and order bins and containers for waste storage well in advance. Stay informed of the updated amount of waste and keep it in locked storage. 7

  17. Hematite nuclear fuel cycle facility decommissioning

    International Nuclear Information System (INIS)

    Hayes, K.

    2004-01-01

    Westinghouse Electric Company LLC ('Westinghouse') acquired a nuclear fuel processing plant at Hematite, Missouri ('Hematite', the 'Facility', or the 'Plant') in April 2000. The plant has subsequently been closed, and its operations have been relocated to a newer, larger facility. Westinghouse has announced plans to complete its clean-up, decommissioning, and license retirement in a safe, socially responsible, and environmentally sound manner as required by internal policies, as well as those of its parent company, British Nuclear Fuels plc. ('BNFL'). Preliminary investigations have revealed the presence of environmental contamination in various areas of the facility and grounds, including both radioactive contamination and various other substances related to the nuclear fuel processing operations. The disparity in regulatory requirements for radiological and nonradiological contaminants, the variety of historic and recent operations, and the number of previous owners working under various contractual arrangements for both governmental and private concerns has resulted in a complex project. This paper discusses Westinghouse's efforts to develop and implement a comprehensive decontamination and decommissioning (D and D) strategy for the facility and grounds. (author)

  18. Decontamination and decommissioning project for the nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Park, J. H.; Paik, S. T.; Park, S. W. (and others)

    2007-02-15

    The final goal of this project is to complete the decommissioning of the Korean Research Reactor no.1 and no. 2(KRR-1 and 2) and uranium conversion plant safely and successfully. The goal of this project in 2006 is to complete the decontamination of the inside reactor hall of the KRR-2 which will be operating as a temporary storage for the radioactive waste until the construction and operation of the national repository site. Also the decommissioning work of the KRR-1 and auxiliary facilities is being progress. As the compaction of decommissioning project is near at hand, a computer information system was developed for a systematically control and preserve a technical experience and decommissioning data for the future reuse. The nuclear facility decommissioning, which is the first challenge in Korea, is being closed to the final stages. We completed the decommissioning of all the bio-shielding concrete for KRR-2 in 2005 and carried out the decontamination and waste material grouping of the roof, wall and bottom of the reactor hall of the KRR-2. The decommissioning for nuclear facility were demanded the high technology, remote control equipment and radioactivity analysis. So developed equipment and experience will be applied at the decommissioning for new nuclear facility in the future.

  19. The decommissioning of nuclear facilities; Le demantelement des installations nucleaires de base

    Energy Technology Data Exchange (ETDEWEB)

    Niel, J.Ch.; Rieu, J.; Lareynie, O.; Delrive, L.; Vallet, J.; Girard, A.; Duthe, M.; Lecomte, C.; Rozain, J.P.; Nokhamzon, J.G.; Davoust, M.; Eyraud, J.L.; Bernet, Ph.; Velon, M.; Gay, A.; Charles, Th.; Leschaeva, M.; Dutzer, M.; Maocec, Ch.; Gillet, G.; Brut, F.; Dieulot, M.; Thuillier, D.; Tournebize, F.; Fontaine, V.; Goursaud, V.; Birot, M.; Le Bourdonnec, Th.; Batandjieva, B.; Theis, St.; Walker, St.; Rosett, M.; Cameron, C.; Boyd, A.; Aguilar, M.; Brownell, H.; Manson, P.; Walthery, R.; Wan Laer, W.; Lewandowski, P.; Dorms, B.; Reusen, N.; Bardelay, J.; Damette, G.; Francois, P.; Eimer, M.; Tadjeddine, A.; Sene, M.; Sene, R

    2008-11-15

    This file includes five parts: the first part is devoted to the strategies of the different operators and includes the following files: the decommissioning of nuclear facilities Asn point of view, decommissioning of secret nuclear facilities, decommissioning at the civil Cea strategy and programs, EDF de-construction strategy, Areva strategy for decommissioning of nuclear facilities; the second one concerns the stakes of dismantling and includes the articles as follow: complete cleanup of buildings structures in nuclear facilities, decommissioning of nuclear facilities and safety assessment, decommissioning wastes management issues, securing the financing of long-term decommissioning and waste management costs, organizational and human factors in decommissioning projects, training for the decommissioning professions: the example of the Grenoble University master degree; the third part is devoted to the management of dismantling work sites and includes the different articles as follow: decommissioning progress at S.I.C.N. plant, example of decommissioning work site in Cea Grenoble: Siloette reactor decommissioning, matters related to decommissioning sites, decommissioning of french nuclear installations: the viewpoint of a specialist company, specificities of inspections during decommissioning: the Asn inspector point of view; the fourth part is in relation with the international approach and includes as follow: IAEA role in establishing a global safety regime on decommissioning, towards harmonization of nuclear safety practices in Europe: W.E.N.R.A. and the decommissioning of nuclear facilities, EPA superfund program policy for decontamination and decommissioning, progress with remediation at Sellafield, progress and experiences from the decommissioning of the Eurochemic reprocessing plant in Belgium, activities of I.R.S.N. and its daughter company Risk-audit I.r.s.n./G.r.s. international in the field of decommissioning of nuclear facilities in eastern countries

  20. Regulation for the decommissioning of nuclear power plants in U.S.A

    International Nuclear Information System (INIS)

    Oishi, Yuichi

    2001-01-01

    Since beginning of operation in nuclear reactor for practical power generation for the first one in Japan in 1966, the rector already passed more than 30 years are found and some investigations on its abolition method and its countermeasure accompanied with its permanent operation finishing of the reactor for future have been progressed by government and the relative organizations. The Japan Engineering and Inspection Corporation, under trust of the Ministry of Economy and Industry, has carried out some surveys on abolition measure regulation in the world. On the regulation in U.S.A. as a part of the surveys, abstract of the survey results performed before 1999 was introduced. Items in the survey were regulation system, definition and configuration of the abolition measure, legal procedures on the measure, and the last radiation survey and evaluating method. In U.S.A., as contents on legal procedure and document to be proposed are in detail and concretely regulated, the abolition measure activity can be progressed in standard according to the legal regulation, difference between every plants is thought to be very small. And, in spite of being regulated in details, participation of regulation agency on the procedures is less than that under operation, and there are some exempted items automatically. This is to say, it is a method to be processed under check of the abolition measure activity by NRC through its notice, inspection and approval, under agreeing with desires of applicants. (G.K.)

  1. Governments' role in decommissioning nuclear power facilities

    International Nuclear Information System (INIS)

    Guindon, S.; Wendling, R.D.; Gordelier, S.; Soederberg, O.; Averous, J.; Orlando, D.

    2005-01-01

    Many nuclear power plants will reach the end of their operating lives over the next 20 years; some may be life-extended, others may not. This development will precipitate enhanced industrial and regulatory activities in the area of decommissioning. We are also witnessing in many countries a significant shift in the role of government itself: new pressures on governments, such as enhanced attention on environmental impact/mitigation and strategies to implement market-oriented approaches in a variety of sectors, including the energy sector are driving the public policy agenda. The paper will examine the range of policy issues, drawing from recent NEA studies on decommissioning policies and the recent NEA study on Government and Nuclear Energy and, strategies and costs, and other current trends and developments in the nuclear industry and in the nuclear policy fields. The paper will reflect on issues to be addressed during the conference and draw conclusions on the appropriate role of government in this area. Decommissioning policy is very specific and focused: it is not a high level policy/political issue in most instances and rarely gets the same attention as the issue surrounding the future of nuclear energy itself and public concerns regarding safety, waste and economics. One reason why decommissioning does not get the same attention as for example disposal of spent nuclear fuel might be the fact that technology is available for decommissioning, while technology for disposal of spent nuclear fuel is under development. High profile or not, it will remain an important issue for governments and industry alike particularly because of the cost and long lead times involved. In some instances, governments are the owners of the facilities to be decommissioned. In addition, decommissioning factors into issues surrounding the economics of nuclear energy and the sustainability of the nuclear option. Based on results of the Tarragona Seminar (Spain, September 2-4, 2003) and

  2. Decommissioning of nuclear facilities: 'it can and has been done'

    International Nuclear Information System (INIS)

    2009-01-01

    Considerable international experience gained over the last 20 years demonstrates that nuclear facilities can be safely dismantled and decommissioned once a decision is made to cease operations and permanently shut them down. The term decommissioning is used to describe all the management and technical actions associated with ceasing operation of a nuclear installation and its subsequent dismantling to facilitate its removal from regulatory control (de-licensing). These actions involve decontamination of structures and components, dismantling of components and demolition of buildings, remediation of any contaminated ground and removal of the resulting waste. Worldwide, of the more than 560 commercial nuclear power plants that are or have been in operation, about 120 plants have been permanently shut down and are at some stage of decommissioning. About 10% of all shutdown plants have been fully decommissioned, including eight reactors of more than 100 MWe. A larger number of various types of fuel cycle and research facilities have also been shut down and decommissioned, including: facilities for the extraction and enrichment of uranium, facilities for fuel fabrication and reprocessing, laboratories, isotope production facilities and particle accelerators. This brochure looks at decommissioning across a spectrum of nuclear facilities and shows worldwide examples of successful projects. Further information can be found in NEA publications and on a number of web-sites

  3. Financing the Decommissioning of Nuclear Facilities

    International Nuclear Information System (INIS)

    2016-01-01

    Decommissioning of both commercial and R and D nuclear facilities is expected to increase significantly in the coming years, and the largest of such industrial decommissioning projects could command considerable budgets. It is important to understand the costs of decommissioning projects in order to develop realistic cost estimates as early as possible based on preliminary decommissioning plans, but also to develop funding mechanisms to ensure that future decommissioning expenses can be adequately covered. Sound financial provisions need to be accumulated early on to reduce the potential risk for residual, unfunded liabilities and the burden on future generations, while ensuring environmental protection. Decommissioning planning can be subject to considerable uncertainties, particularly in relation to potential changes in financial markets, in energy policies or in the conditions and requirements for decommissioning individual nuclear installations, and such uncertainties need to be reflected in regularly updated cost estimates. This booklet offers a useful overview of the relevant aspects of financing the decommissioning of nuclear facilities. It provides information on cost estimation for decommissioning, as well as details about funding mechanisms and the management of funds based on current practice in NEA member countries. (authors)

  4. Decommissioning of Salaspils nuclear reactor

    International Nuclear Information System (INIS)

    Abramenkovs, A.; Malnachs, J.; Popelis, A.

    2002-01-01

    In May 1995, the Latvian Government decided to shut down the Research Reactor Salaspils (SRR) and to dispense with nuclear energy in future. The reactor has been out of operation since July 1998. A conceptual study for the decommissioning of SRR has been carried out by Noell-KRC-Energie- und Umwelttechnik GmbH from 1998-1999. he Latvian Government decided on 26 October 1999 to start the direct dismantling to 'green field' in 2001. The results of decommissioning and dismantling performed in 1999-2001 are presented and discussed. The main efforts were devoted to collecting and conditioning 'historical' radioactive waste from different storages outside and inside the reactor hall. All radioactive material more than 20 tons were conditioned in concrete containers for disposal in the radioactive waste depository 'Radons' in the Baldone site. Personal protective and radiation measurement equipment was upgraded significantly. All non-radioactive equipment and material outside the reactor buildings were free-released and dismantled for reuse or conventional disposal. Weakly contaminated material from the reactor hall was collected and removed for free-release measurements. The technology of dismantling of the reactor's systems, i.e. second cooling circuit, zero power reactors and equipment, is discussed in the paper. (author)

  5. Nuclear energy. First experiences with decommissioning in Germany

    International Nuclear Information System (INIS)

    Sokoll, Joerg

    2015-01-01

    After the Fukushima disaster in 2011 the German parliament changed the national atomic energy law by way of its thirteenth amendment. In contrast to the initial ''nuclear phaseout'' the new phaseout of nuclear energy foresees a large number of decommissionings which will occur in part successively and in part simultaneously and will extend over a period of eleven years. Eight generating units were already decommissioned in 2011 or have not been ramped up again since then. By 2020 the last units will have been decommissioned and the phaseout of nuclear energy will have been completed, at least in terms of power plant operation. However the subsequent dismantling operations will keep German operators busy for decades to come. This article reports on first practical experiences in decommissioning.

  6. The cost of decommissioning nuclear facilities

    International Nuclear Information System (INIS)

    1993-01-01

    This report sets out the results of a National Audit Office investigation to determine the extent of the potential Government liability for nuclear decommissioning, how this is to be financed and the possible implications for the taxpayer. Further effort are needed to improve the nuclear industry's estimates, improve efficiency and face up to the costs of decommissioning. This should also ensure that the full cost of nuclear energy is identified. (author)

  7. Organization and management for decommissioning of large nuclear facilities

    International Nuclear Information System (INIS)

    2000-01-01

    For nuclear facilities, decommissioning is the final phase in the life-cycle after siting, design, construction, commissioning and operation. It is a complex process involving operations such as detailed surveys, decontamination and dismantling of plant equipment and facilities, demolition of buildings and structures, and management of resulting waste and other materials, whilst taking into account aspects of health and safety of the operating personnel and the general public, and protection of the environment. Careful planning and management is essential to ensure that decommissioning is accomplished in a safe and cost effective manner. Guidance on organizational aspects may lead to better decision making, reductions in time and resources, lower doses to the workers and reduced impact on public health and the environment. The objective of this report is to provide information and guidance on the organization and management aspects for the decommissioning of large nuclear facilities which will be useful for licensees responsible for discharging these responsibilities. The information contained in the report may also be useful to policy makers, regulatory bodies and other organizations interested in the planning and management of decommissioning. In this report, the term 'decommissioning' refers to those actions that are taken at the end of the useful life of a nuclear facility in withdrawing it from service with adequate regard for the health and safety of workers and members of the public and for the protection of the environment. The term 'large nuclear facilities' involves nuclear power plants, large nuclear research reactors and other fuel cycle facilities such as reprocessing plants, fuel conversion, fabrication and enrichment plants, as well as spent fuel storage and waste management plants. Information on the planning and management for decommissioning of smaller research reactors or other small nuclear facilities can be found elsewhere. The report covers

  8. Quality management in nuclear facilities decommissioning

    International Nuclear Information System (INIS)

    Garonis, Omar H.

    2002-01-01

    Internationally, the decommissioning organizations of nuclear facilities carry out the decommissioning according to the safety requirements established for the regulatory bodies. Some of them perform their activities in compliance with a quality assurance system. This work establishes standardization through a Specifications Requirement Document, for the management system of the nuclear facilities decommissioning organizations. It integrates with aspects of the quality, environmental, occupational safety and health management systems, and also makes these aspects compatible with all the requirements of the nuclear industry recommended for the International Atomic Energy Agency (IAEA). (author)

  9. Regulatory aspects of nuclear reactor decommissioning

    International Nuclear Information System (INIS)

    Ross, W.M.

    1990-01-01

    The paper discusses the regulatory aspects of decommissioning commercial nuclear power stations in the UK. The way in which the relevant legislation has been used for the first time in dealing with the early stages of decommissioning commercial nuclear reactor is described. International requirements and how they infit with the UK system are also covered. The discussion focusses on the changes which have been required, under the Nuclear Site Licence, to ensure that the licensee carries out of work of reactor decommissioning in a safe and controlled manner. (Author)

  10. Methodology and technology of decommissioning nuclear facilities

    International Nuclear Information System (INIS)

    1986-01-01

    The decommissioning and decontamination of nuclear facilities is a topic of great interest to many Member States of the International Atomic Energy Agency (IAEA) because of the large number of older nuclear facilities which are or soon will be retired from service. In response to increased international interest in decommissioning and to the needs of Member States, the IAEA's activities in this area have increased during the past few years and will be enhanced considerably in the future. A long range programme using an integrated systems approach covering all the technical, regulatory and safety steps associated with the decommissioning of nuclear facilities is being developed. The database resulting from this work is required so that Member States can decommission their nuclear facilities in a safe time and cost effective manner and the IAEA can effectively respond to requests for assistance. The report is a review of the current state of the art of the methodology and technology of decommissioning nuclear facilities including remote systems technology. This is the first report in the IAEA's expanded programme and was of benefit in outlining future activities. Certain aspects of the work reviewed in this report, such as the recycling of radioactive materials from decommissioning, will be examined in depth in future reports. The information presented should be useful to those responsible for or interested in planning or implementing the decommissioning of nuclear facilities

  11. Decommissioning and dismantling of nuclear installations

    International Nuclear Information System (INIS)

    Pelzer, N.

    1993-01-01

    The German law governing decommissioning and dismantling of nuclear installations can be called to be embryonic as compared to other areas of the nuclear regulatory system, and this is why the AIDN/INLA regional meeting organised by the German national committee in July 1992 in Schwerin has been intended to elaborate an assessment of the current legal situation and on this basis establish proposals for enhancement and development, taking into account the experience reported by experts from abroad. The proceedings comprise the paper of the opening session, 'Engineering and safety aspects of the decommissioning of nuclear installations', and the papers and discussions of the technical sessions entitled: - Comparative assessment of the regulatory regimes. - Legislation governing the decommissioning of nuclear installations in Germany. - Analysis of the purpose and law making substance of existing regulatory provisions for the decommissioning of nuclear installations. All seventeen papers of the meeting have been prepared for separate retrieval from the database. (orig./HSCH) [de

  12. Final generic environmental impact statement on decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    1988-08-01

    This final generic environmental impact statement was prepared as part of the requirement for considering changes in regulations on decommissioning of commercial nuclear facilities. Consideration is given to the decommissioning of pressurized water reactors, boiling water reactors, research and test reactors, fuel reprocessing plants (FRPs) (currently, use of FRPs in the commercial sector is not being considered), small mixed oxide fuel fabrication plants, uranium hexafluoride conversion plants, uranium fuel fabrication plants, independent spent fuel storage installations, and non-fuel-cycle facilities for handling byproduct, source and special nuclear materials. Decommissioning has many positive environmental impacts such as the return of possibly valuable land to the public domain and the elimination of potential problems associated with increased numbers of radioactively contaminated facilities with a minimal use of resources. Major adverse impacts are shown to be routine occupational radiation doses and the commitment of nominally small amounts of land to radioactive waste disposal. Other impacts, including public radiation doses, are minor. Mitigation of potential health, safety, and environmental impacts requires more specific and detailed regulatory guidance than is currently available. Recommendations are made as to regulatory decommissioning particulars including such aspects as decommissioning alternatives, appropriate preliminary planning requirements at the time of commissioning, final planning requirements prior to termination of facility operations, assurance of funding for decommissioning, environmental review requirements. 26 refs., 7 figs., 68 tabs

  13. Decommissioning engineering systems for nuclear facilities and knowledge inheritance for decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Tachibana, Mitsuo

    2016-01-01

    Information on construction, operation and maintenance of a nuclear facility is essential in order to plan and implement the decommissioning of the nuclear facility. A decommissioning engineering system collects these information efficiently, retrieves necessary information rapidly, and support to plan the reasonable decommissioning as well as the systematic implementation of dismantling activities. Then, knowledge of workers involved facility operation and dismantling activities is important because decommissioning of nuclear facility will be carried out for a long period. Knowledge inheritance for decommissioning has been carried out in various organizations. This report describes an outline of and experiences in applying decommissioning engineering systems in JAEA and activities related to knowledge inheritance for decommissioning in some organizations. (author)

  14. Policy on the decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    1988-08-01

    This Regulatory Policy Statement describes the policy of the Atomic Energy Control Board (AECB) on the decommissioning of those facilities defined as nuclear facilities in the Atomic Energy Control (AEC) Regulations. It is intended as a formal statement, primarily for the information of licensees, or potential licensees, of the regulatory process and requirements generally applicable to the decommissioning of nuclear facilities licensed and regulated by the AECB pursuant to the authority of the AEC Act and Regulations

  15. Russian nuclear-powered submarine decommissioning

    International Nuclear Information System (INIS)

    Bukharin, O.; Handler, J.

    1995-01-01

    Russia is facing technical, economic and organizational difficulties in dismantling its oversized and unsafe fleet of nuclear powered submarines. The inability of Russia to deal effectively with the submarine decommissioning crisis increases the risk of environmental disaster and may hamper the implementation of the START I and START II treaties. This paper discusses the nuclear fleet support infrastructure, the problems of submarine decommissioning, and recommends international cooperation in addressing these problems

  16. Reserves for nuclear power plant decommissioning and radwaste disposal in Germany. An analysis and evaluation from the angle of energy policy

    International Nuclear Information System (INIS)

    Buerger, V.

    1998-01-01

    The study, which is the first of its kind in Germany, presents a comprehensive survey of total reserves set up by the German nuclear industry for liabilities and costs for nuclear power plant decommissioning and resulting radwaste disposal, which is a legal and foreseeable responsibility but uncertain in amount. The study looks into the various ways the earmarked money was invested and analyses the funds with respect to their efficiency and reliability to provide financial security for the given tasks and purpose. The question put in this context is: Are the reserves set up so far in line with official cost estimates, i.e. will they cover estimated costs, or do they even exceed the estimated amounts? The conclusions drawn and explained in this document are: The reserves for nuclear decommissioning have been used by the nuclear power plant operators and electricity companies as a significant capital source. Some of the capital accrued is being increasingly used at present to cover expenses arising for restructuring of business and diversification into new business segments of interest in the open national and European electricity markets. Companies such as RWE, Preussen Elektra, and Bayernwerk, which until deregulation of the energy sector were just power supply companies, have been transformed into conglomerate companies and international players in the markets, like RWE Holding, VEBA, and VIAG. It can be safely assumed that the companies would not have been able to reach the important positions they currently hold in the German economy without tapping the reserves for nuclear decommissioning. (orig./CB) [de

  17. Criteria, standards and policies regarding decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Detilleux, E.; Lennemann, W.L.

    1977-01-01

    At the end of this century, there will probably be around 2500 operating nuclear power reactors, along with all the other nuclear fuel cycle facilities supporting their operation. Eventually these facilities, one by one, will be shut down and it will be necessary to dispose of them as with any redundant industrial facility or plant. Some parts of a nuclear fuel cycle facility can be dismantled by conventional methods, but those parts which have become contaminated with radioactive nuclear products or induced radioactivity must be subject to rigid controls and restrictions and handled by special dismantling and disposal procedures. In many cases, the resulting quantity of radioactive waste is likely to be relatively large and dismantling quite costly. Decommissioning nuclear facilities is a multifaceted problem involving planners, design engineers, operators, waste managers and regulatory authorities. Preparation for decommissioning should begin as early as site selection and plant design. The corner stone for the preparation of a decommissioning programme is the definition of its extent, meeting the requirements for public and environmental protection during the period that the radioactive material is of concern. The paper discusses the decontamination and decommissioning experience at the Eurochemic fuel reprocessing plant, the implications and the knowledge gained from this experience. It includes the results of technical reviews made by the Nuclear Energy Agency of OECD and the International Atomic Energy Agency regarding decommissioning nuclear facilities. The paper notes the special planning that should be arranged between those responsible for the nuclear facility and competent public authorities who should jointly make a realistic determination of the eventual disposition of the nuclear facility, even before it is built. Recommendations cover the responsibilities of nuclear plant entrepreneurs, designers, operators, and public and regulatory authorities

  18. Progress in Decommissioning the Humboldt Bay Power Plant - 13604

    Energy Technology Data Exchange (ETDEWEB)

    Rod, Kerry [PG and E Utility, Humboldt Bay Power Plant, 1000 King Salmon Ave. Eureka, CA 95503 (United States); Shelanskey, Steven K. [Anata Management Solutions, 5180 South Commerce Dr,, Suite F Murray, UT 84107 (United States); Kristofzski, John [CH2MHILL, 295 Bradley Blvd. Suite 300, Richland WA 99353 (United States)

    2013-07-01

    Decommissioning of the Pacific Gas and Electric (PG and E) Company Humboldt Bay Power Plant (HBPP) Unit 3 nuclear facility has now, after more than three decades of SAFSTOR and initial decommissioning work, transitioned to full-scale decommissioning. Decommissioning activities to date have been well orchestrated and executed in spite of an extremely small work site with space constricted even more by other concurrent on-site major construction projects including the demolition of four fossil units, construction of a new generating station and 60 KV switchyard upgrade. Full-scale decommissioning activities - now transitioning from Plant Systems Removal (PG and E self-perform) to Civil Works Projects (contractor performed) - are proceeding in a safe, timely, and cost effective manner. As a result of the successful decommissioning work to date (approximately fifty percent completed) and the intense planning and preparations for the remaining work, there is a high level of confidence for completion of all HBPP Unit 3 decommissions activities in 2018. Strategic planning and preparations to transition into full-scale decommissioning was carried out in 2008 by a small, highly focused project team. This planning was conducted concurrent with other critical planning requirements such as the loading of spent nuclear fuel into dry storage at the Independent Spent Fuel Storage Installation (ISFSI) finishing December 2008. Over the past four years, 2009 through 2012, the majority of decommissioning work has been installation of site infrastructure and removal of systems and components, known as the Plant System Removal Phase, where work scope was dynamic with significant uncertainty, and it was self-performed by PG and E. As HBPP Decommissioning transitions from the Plant System Removal Phase to the Civil Works Projects Phase, where work scope is well defined, a contracting plan similar to that used for Fossil Decommissioning will be implemented. Award of five major work scopes

  19. Progress in Decommissioning the Humboldt Bay Power Plant - 13604

    International Nuclear Information System (INIS)

    Rod, Kerry; Shelanskey, Steven K.; Kristofzski, John

    2013-01-01

    Decommissioning of the Pacific Gas and Electric (PG and E) Company Humboldt Bay Power Plant (HBPP) Unit 3 nuclear facility has now, after more than three decades of SAFSTOR and initial decommissioning work, transitioned to full-scale decommissioning. Decommissioning activities to date have been well orchestrated and executed in spite of an extremely small work site with space constricted even more by other concurrent on-site major construction projects including the demolition of four fossil units, construction of a new generating station and 60 KV switchyard upgrade. Full-scale decommissioning activities - now transitioning from Plant Systems Removal (PG and E self-perform) to Civil Works Projects (contractor performed) - are proceeding in a safe, timely, and cost effective manner. As a result of the successful decommissioning work to date (approximately fifty percent completed) and the intense planning and preparations for the remaining work, there is a high level of confidence for completion of all HBPP Unit 3 decommissions activities in 2018. Strategic planning and preparations to transition into full-scale decommissioning was carried out in 2008 by a small, highly focused project team. This planning was conducted concurrent with other critical planning requirements such as the loading of spent nuclear fuel into dry storage at the Independent Spent Fuel Storage Installation (ISFSI) finishing December 2008. Over the past four years, 2009 through 2012, the majority of decommissioning work has been installation of site infrastructure and removal of systems and components, known as the Plant System Removal Phase, where work scope was dynamic with significant uncertainty, and it was self-performed by PG and E. As HBPP Decommissioning transitions from the Plant System Removal Phase to the Civil Works Projects Phase, where work scope is well defined, a contracting plan similar to that used for Fossil Decommissioning will be implemented. Award of five major work scopes

  20. The role of the visitors' centre during the decommissioning of the Greifswald nuclear power plant and the impact on the public

    International Nuclear Information System (INIS)

    Brauer, D.

    1993-01-01

    In the Energiewerke Nord (EWN) GmbH, the former Nuclear Power Plant (NPP) Greifswald have been the units 1 to 5 shut down finally. The units 6 to 8 are in different stages of construction, but it will not be continued. The current situation, tasks and perspectives at the Greifswald NPP site are briefly described. The main tasks are the post-operation, the decommissioning and the establishment of an industrial area. Considering the situation at the Greifswald site the particularities and necessities and the influence of the Visitors' centre on the neighbouring villages, communities, population and the impact on the public are discussed. (author)

  1. Stakeholder involvement in decommissioning nuclear facilities

    International Nuclear Information System (INIS)

    2007-01-01

    Significant numbers of nuclear facilities will need to be decommissioned in the coming decades. In this context, NEA member countries are placing increasing emphasis on the involvement of stakeholders in the associated decision procedures. This study reviews decommissioning experience with a view to identifying stakeholder concerns and best practice in addressing them. The lessons learnt about the end of the facility life cycle can also contribute to better foresight in siting and building new facilities. This report will be of interest to all major players in the field of decommissioning, in particular policy makers, implementers, regulators and representatives of local host communities

  2. Accidental safety analysis methodology development in decommission of the nuclear facility

    Energy Technology Data Exchange (ETDEWEB)

    Park, G. H.; Hwang, J. H.; Jae, M. S.; Seong, J. H.; Shin, S. H.; Cheong, S. J.; Pae, J. H.; Ang, G. R.; Lee, J. U. [Seoul National Univ., Seoul (Korea, Republic of)

    2002-03-15

    Decontamination and Decommissioning (D and D) of a nuclear reactor cost about 20% of construction expense and production of nuclear wastes during decommissioning makes environmental issues. Decommissioning of a nuclear reactor in Korea is in a just beginning stage, lacking clear standards and regulations for decommissioning. This work accident safety analysis in decommissioning of the nuclear facility can be a solid ground for the standards and regulations. For source term analysis for Kori-1 reactor vessel, MCNP/ORIGEN calculation methodology was applied. The activity of each important nuclide in the vessel was estimated at a time after 2008, the year Kori-1 plant is supposed to be decommissioned. And a methodology for risk analysis assessment in decommissioning was developed.

  3. Development of the Decommissioning Technology for Nuclear Facilities

    International Nuclear Information System (INIS)

    Lee, K. W.; Kim, G. N.; Kim, S. G.

    2010-04-01

    The evaluation technology of decommissioning process must be developed and will be used for the ALARA planning tool of decommissioning process and demonstrated for tools of decommissioning equipment. Also, this technology can be used for tools workplaces with high work difficulty such as large-scale chemical plant, under water and space. The monitoring system for high alpha radioactive contamination measurement will be use in the high radioactivity decommissioning sites such as hot-cell or glove box. Also, it will be use in the general nuclear facilities as the radiation monitoring unit. The preparation technology of the radiation sensor for high radioactive contamination measurement will be transferred to the company for the industrialization. The remote monitoring system can prevent the workers exposure using the optical fiber to separate the sensor and electronics

  4. AECL's strategy for decommissioning Canadian nuclear facilities

    International Nuclear Information System (INIS)

    Joubert, W.M.; Pare, F.E.; Pratapagiri, G.

    1992-01-01

    The Canadian policy on decommissioning of nuclear facilities as defined in the Atomic Energy Control Act and Regulations is administered by the Atomic Energy Control Board (AECB), a Federal Government agency. It requires that these facilities be decommissioned according to approved plans which are to be developed by the owner of the nuclear facility during its early stages of design and to be refined during its operating life. In this regulatory environment, Atomic Energy of Canada (AECL) has developed a decommissioning strategy for power stations which consists of three distinctive phases. After presenting AECL's decommissioning philosophy, its foundations are explained and it is described how it has and soon will be applied to various facilities. A brief summary is provided of the experience gained up to date on the implementation of this strategy. (author) 3 figs.; 1 tab

  5. Criteria, standards and policies regarding decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Detilleux, E.; Lennemann, W.

    1977-01-01

    The paper discusses the decontamination and decommissioning experiences encountered at the Eurochemic fuel reprocessing plant, their implications and the knowledge gained from these experiences. It includes the results of technical reviews made by the Nuclear Energy Agency of OECD and the International Atomic Energy Agency regarding decommissioning nuclear facilities. The conlusions which are presented should weigh heavily in the considerations of the national authorities involved in regulating nuclear power programmes. The paper notes the special planning that should be arranged between those responsible for the nuclear facility and competent public authorities who jointly should make a realistic determination of the eventual disposition of the nuclear facility, even before it is built. Recommendations cover the responsibilities of nuclear plant entrepreneurs, designers, operators, and public and regulatory authorities [fr

  6. Decontamination and decommissioning of the West Valley Reprocessing Plant

    International Nuclear Information System (INIS)

    Daugherty, H.F.; Keel, R.

    1986-11-01

    This report presents the decontamination and decommissioning (D and D) activities at the West Valley Nuclear Fuel Reprocessing Plant through September 1, 1986. The topics addressed are: D and D of areas for reuse by the Liquid Waste Treatment System (LWTS); D and D of areas for reuse as High Level Waste (HLW) canister storage; and technologies developed in D and D work

  7. Nuclear data requirements for fission reactor decommissioning

    International Nuclear Information System (INIS)

    Kocherov, N.P.

    1993-01-01

    The meeting was attended by 13 participants from 8 Member States and 2 International Organizations who reviewed the status of the nuclear data libraries and computer codes used to calculate the radioactive inventory in the reactor unit components for the decommissioning purposes. Nuclides and nuclear reactions important for determination of the radiation fields during decommissioning and for the final disposal of radioactive waste from the decommissioned units were identified. Accuracy requirements for the relevant nuclear data were considered. The present publication contains the text of the reports by the participants and their recommendations to the Nuclear Data Section of the IAEA. A separate abstract was prepared for each of these reports. Refs, figs and tabs

  8. 78 FR 64028 - Decommissioning of Nuclear Power Reactors

    Science.gov (United States)

    2013-10-25

    ... NUCLEAR REGULATORY COMMISSION [NRC-2012-0035] Decommissioning of Nuclear Power Reactors AGENCY... the NRC's regulations relating to the decommissioning process for nuclear power reactors. The revision... Commission (NRC) is issuing Revision 1 of regulatory guide (RG) 1.184 ``Decommissioning of Nuclear Power...

  9. Decontamination and Decommissioning at Small Nuclear Facilities: Facilitating the Submission of Decommissioning Funding Plans

    International Nuclear Information System (INIS)

    Minor, D.A.; Grumbles, A.

    2009-01-01

    This paper describes the efforts of the Washington State Department of Health to ensure that small nuclear facilities have the tools each needs to submit Decommissioning Funding Plans. These Plans are required by both the U.S. Nuclear Regulatory Commission (NRC) and in some states - in the case of Washington state, the Washington State Department of Health is the regulator of radioactive materials. Unfortunately, the guidance documents provided by the U.S. NRC pertain to large nuclear facilities, such as nuclear fuel fabrication plants, not the small nuclear laboratory nor small nuclear laundry that may also be required to submit such Plans. These small facilities are required to submit Decommissioning Funding Plans by dint of their nuclear materials inventory, but have only a small staff, such as a Radiation Safety Officer and few authorized users. The Washington State Department of Health and Attenuation Environmental Company have been working on certain tools, such as templates and spreadsheets, that are intended to assist these small nuclear facilities prepare compliant Decommissioning Funding Plans with a minimum of experience and effort. (authors)

  10. Decontamination and Decommissioning Project for the Nuclear Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Park, J. H.; Paik, S. T.; Park, S. W. and others

    2006-02-15

    The final goal of this project is to complete safely and successfully the decommissioning of the Korean Research Reactor no.1 (KRR-1) and the Korean Research Reactor no.2 (KRR-2), and uranium conversion plant (UCP). The dismantling of the reactor hall of the KRR-2 was planned to complete till the end of 2004, but it was delayed because of a few unexpected factors such as the development of a remotely operated equipment for dismantling of the highly radioactive parts of the beam port tubes. In 2005, the dismantling of the bio-shielding concrete structure of the KRR-2 was finished and the hall can be used as a temporary storage space for the radioactive waste generated during the decommissioning of the KRR-1 and KRR-2. The cutting experience of the shielding concrete by diamond wire saw and the drilling experience by a core boring machine will be applied to another nuclear facility dismantling. An effective management tool of the decommissioning projects, named DECOMIS, was developed and the data from the decommissioning projects were gathered. This system provided many information on the daily D and D works, waste generation, radiation dose, etc., so an effective management of the decommissioning projects is expected from next year. The operation experience of the uranium conversion plant as a nuclear fuel cycle facility was much contributed to the localization of nuclear fuels for both HWR and PWR. It was shut down in 1993 and a program for its decontamination and dismantling was launched in 2001 to remove all the contaminated equipment and to achieve the environment restoration. The decommissioning project is expected to contribute to the development of the D and D technologies for the other domestic fuel cycle facilities and the settlement of the new criteria for decommissioning of the fuel cycle related facilities.

  11. Solid Waste from the Operation and Decommissioning of Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Brown, Marilyn Ann [Georgia Inst. of Technology, Atlanta, GA (United States); D' Arcy, Daniel [Georgia Inst. of Technology, Atlanta, GA (United States); Lapsa, Melissa Voss [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Sharma, Isha [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Li, Yufei [Georgia Inst. of Technology, Atlanta, GA (United States)

    2017-01-05

    This baseline report examines the solid waste generated by the U.S. electric power industry, including both waste streams resulting from electricity generation and wastes resulting from the decommissioning of power plants. Coal and nuclear plants produce large volumes of waste during electricity generation, and this report describes the policies and procedures for handling these materials. Natural gas and oil-fired power plants face similar waste challenges. Renewables considered in this baseline report include hydropower, wind and solar.

  12. The planning of decommissioning activities within nuclear facilities - Generating a Baseline Decommissioning Plan

    International Nuclear Information System (INIS)

    Meek, N.C.; Ingram, S.; Page, J.

    2003-01-01

    BNFL Environmental Services has developed planning tools to meet the emerging need for nuclear liabilities management and decommissioning engineering both in the UK and globally. It can provide a comprehensive baseline planning service primarily aimed at nuclear power stations and nuclear plant. The paper develops the following issues: Decommissioning planning; The baseline decommissioning plan;The process; Work package; Compiling the information; Deliverables summary; Customer Benefits; - Planning tool for nuclear liability life-cycle management; - Robust and reliable plans based upon 'real' experience; - Advanced financial planning; - Ascertaining risk; - Strategy and business planning. The following Deliverables are mentioned:1. Site Work Breakdown Structure; 2. Development of site implementation strategy from the high level decommissioning strategy; 3. An end point definition for the site; 4. Buildings, operational systems and plant surveys; 5. A schedule of condition for the site; 6. Development of technical approach for decommissioning for each work package; 7. Cost estimate to WBS level 5 for each work package; 8. Estimate of decommissioning waste arisings for each work package; 9. Preparation of complete decommissioning programme in planning software to suit client; 10. Risk modelling of work package and overall project levels; 11. Roll up of costs into an overall cost model; 12. Cash flow, waste profiling and resource profiling against the decommissioning programme; 13. Preparation and issue of Final Report. Finally The BDP process is represented by a flowchart listing the following stages: [Power Station project assigned] → [Review project and conduct Characterisation review of power station] → [Identify work packages] → [Set up WBS to level 3] → [Assign work packages] → [Update WBS to level 4] →[Develop cost model] → [Develop logic network] → [Develop risk management procedure] ] → [Develop project strategy document]→ [Work package

  13. The brief introduction to decommissioning of nuclear reactor projects

    International Nuclear Information System (INIS)

    Zhao Shixin

    1991-01-01

    The basic concept and procedure of the decommissioning of nuclear reactor project and the three stages of decommissioning defined by IAEA are introduced. The main work of decommissioning of nuclear reactor are as following: (1) the documentary and technological preparation; (2) the site preparation of decommissioning project; (3) the dismantling of equipment piping system and components; (4) the decontamination of the piping system before and after decomminssioning; (5) the storage and disposal of the operational and decommissioning waste

  14. The brief introduction to decommissioning of nuclear reactor projects

    Energy Technology Data Exchange (ETDEWEB)

    Shixin, Zhao [Beijing Inst. of Nuclear Engineering (China)

    1991-08-01

    The basic concept and procedure of the decommissioning of nuclear reactor project and the three stages of decommissioning defined by IAEA are introduced. The main work of decommissioning of nuclear reactor are as following: (1) the documentary and technological preparation; (2) the site preparation of decommissioning project; (3) the dismantling of equipment piping system and components; (4) the decontamination of the piping system before and after decomminssioning; (5) the storage and disposal of the operational and decommissioning waste.

  15. Regulatory experience in nuclear power station decommissioning

    International Nuclear Information System (INIS)

    Ross, W.M.; Waters, R.E.; Taylor, F.E.; Burrows, P.I.

    1995-01-01

    In the UK, decommissioning on a licensed nuclear site is regulated and controlled by HM Nuclear Installations Inspectorate on behalf of the Health and Safety Executive. The same legislative framework used for operating nuclear power stations is also applied to decommissioning activities and provides a continuous but flexible safety regime until there is no danger from ionising radiations. The regulatory strategy is discussed, taking into account Government policy and international guidance for decommissioning and the implications of the recent white paper reviewing radioactive waste management policy. Although each site is treated on a case by case basis as regulatory experience is gained from decommissioning commercial nuclear power stations in the UK, generic issues have been identified and current regulatory thinking on them is indicated. Overall it is concluded that decommissioning is an evolving process where dismantling and waste disposal should be carried out as soon as reasonably practicable. Waste stored on site should, where it is practical and cost effective, be in a state of passive safety. (Author)

  16. The Ministry of Dilemmas [decommissioning nuclear submarines

    International Nuclear Information System (INIS)

    Peden, W.

    1995-01-01

    A consultant for Greenpeace, the anti-nuclear campaigners, looks at the United Kingdom Government's problems with decommissioning of its nuclear submarine fleet as the vessels become obsolete, and at the transport and storage of spent fuels from the submarine's propulsion reactors. It is argued that no proper plans exist to decommission the vessels safely. The Ministry of Defence sites such as Rosyth and Devonport are immune from inspection by regulatory bodies, so there is no public knowledge of any potential radioactive hazards from the stored out-of-service carcasses, floating in dock, awaiting more active strategies. The author questions the wisdom of building new nuclear submarines, when no proper program exists to decommission existing vessels and their operational waste. (U.K.)

  17. The decommissioning plan of the Nuclear Ship MUTSU

    International Nuclear Information System (INIS)

    Adachi, M.; Matsuo, R.; Fujikawa, S.; Nomura, T.

    1995-01-01

    This paper describes the review about the decommissioning plan and present state of the Nuclear Ship Mutsu. The decommissioning of the Mutsu is carried out by Removal and Isolation method. The procedure of the decommissioning works is presented in this paper. The decommissioning works started in April, 1992 and it takes about four years after her last experimental voyage. (author)

  18. U.S. nuclear decommission trust planning: Romancing a millstone?

    International Nuclear Information System (INIS)

    Rohrbach, J.

    1995-01-01

    Nuclear utilities face unknown financial liabilities for plant decommissioning that exceed the value of present trust fund collections. The situation is a strong bet to get worse than better. Will cost escalation experienced in construction recur in decomissioning? If so, then many Nuclear Decommissioning Trusts (NDTs) are underfunded in real terms. The full consequence of an unfunded liability recognized in the later years of operation will be a ratcheting of collection rates to catch up to the revised decommission estimate. NDT planning should incorporate a conservative set of assumptions based on US experience. An NDT should be treated as a trust fund and not a pay-more-as-you-go fund. Levelization of payments will provide some added earnings and more cash in the NDT fund should a reactor not reach its expected life of 40 years. Facing up to the problem and potential remedial action now is imperative

  19. Quality Assurance in the Vandellos 1 Nuclear Power Plant Dismantling and Decommissioning Project; La garantia de calidad en el proyecto de desmantelamiento y clausura de la Central Nuclear de Vandellos I

    Energy Technology Data Exchange (ETDEWEB)

    Soto Lanuza, A

    2000-07-01

    General description of the Quality Assurance System established and implemented for the efficient development of the current activities specified in the Dismantling and Decommissioning Plan for Vandellos I Nuclear Power Plant. Aspects related to the Quality organization, scope and applicability on the established Quality Assurance Manual, availability of requirements and recommendations on quality as well as actions to be taken for the correct verification on the quality and practical application of the Manual should be described. (Author)

  20. State-of-the-art review on technology for measuring and controlling very low level radioactivity in relation to the decommissioning of nuclear power plants

    International Nuclear Information System (INIS)

    Hulot, M.; Chapuis, A.M.; Garbay, H.; Jager, W.; Kroeger, J.

    1986-01-01

    Information in relation to the measurement devices for very low radioactivity, applied in the decommissioning of electronuclear power plants, is scarce and scattered. However, some realistic information can be obtained from the specialists working on nuclear plant dismantling sites. In practice, the in situ measurements deal with two or three radionuclides only. The other containments must be determined on some samples in laboratories by means of radioanalysis and spectrometry technologies. These technologies are briefly described. One of the problems concerns the detection threshold of the measuring instruments. This threshold varies in relation with the detector efficiency, the background and the measurement duration. The application of this concept of threshold to various types of instrument is studied. Tables and graphs are given that sum up the various possibilities of detection for the usual detectors according to their effective area. The possibility of reducing the number of monitoring points using statistical methods is presented

  1. Atmospheric discharges from nuclear facilities during decommissioning: German experiences

    Energy Technology Data Exchange (ETDEWEB)

    Braun, H.; Goertz, R.; Weil, L.

    1997-08-01

    In Germany, a substantial amount of experience is available with planning, licensing and realization of decommissioning projects. In total, a number of 18 nuclear power plants including prototype facilities as well as 6 research reactors and 3 fuel cycle facilities have been shut down finally and are at different stages of decommissioning. Only recently the final {open_quotes}green field{close_quotes} stage of the Niederaichbach Nuclear Power Plant total dismantlement project has been achieved. From the regulatory point of view, a survey of the decommissioning experience in Germany is presented highlighting the aspects of production and retention of airborne radioactivity. Nuclear air cleaning technology, discharge limits prescribed in licences and actual discharges are presented. As compared to operation, the composition of the discharged radioactivity is different as well as the off-gas discharge rate. In practically all cases, there is no significant amount of short-lived radionuclides. The discussion further includes lessons learned, for example inadvertent discharges of radionuclides expected not to be in the plants inventory. It is demonstrated that, as for operation of nuclear power plants, the limits prescribed in the Ordinance on Radiological Protection can be met using existing air cleaning technology, Optimization of protection results in public exposures substantially below the limits. In the frame of the regulatory investigation programme a study has been conducted to assess the airborne radioactivity created during certain decommissioning activities like decontamination, segmentation and handling of contaminated or activated parts. The essential results of this study are presented, which are supposed to support planning for decommissioning, for LWRs, Co-60 and Cs-137 are expected to be the dominant radionuclides in airborne discharges. 18 refs., 2 figs., 1 tab.

  2. Impact of nuclear power plant construction relative to decommissioning fossil fuel plants in order to reduce CO{sub 2} emissions using a modified Nordhaus Vensim DICE model

    Energy Technology Data Exchange (ETDEWEB)

    Tokuhiro, A.; Colpetzer, J., E-mail: tokuhio@uidaho.edu, E-mail: colp8921@vandals.uidaho.edu [Univ. of Idaho, Idaho Falls, ID (United States)

    2014-07-01

    The current levels of CO{sub 2} emissions and high levels accumulating in the atmosphere have climate scientists concerned. The Dynamic Integrated Climate Economy Model or 'DICE' is a model that is used to simulate climate change and evaluate factors to address global warming. The model was developed by Nordhaus and collaborators. The DICE model uses current economic and environmental data to predict potential climate change as a result of an increase in CO{sub 2} in the atmosphere. The authors recreated the Fiddaman DICE model using Vensim and modified it to evaluate the use of nuclear power plants (NPPs) as a means to counter climate change, as characterize by temperature increases in the atmosphere and oceans and the associated cost of damages. The amount of GHG emissions from a NPP are about 6% per MWe, as that from a fossil-fueled power plant (FFPP). Based on this fact, a model was developed to simulate construction of NPPs with subsequent decommissioning of FFPPs with an equivalent power output. The study looked at extended periods into the future; that is, up to year 2300. Based on the results produced from this study it can be concluded that using NPPs in the U.S. to address climate change will provide a small benefit, but ultimately will not be enough to reduce CO{sub 2} emissions nor atmospheric CO{sub 2} to mitigate global warming. The amount of CO{sub 2} in the atmosphere is predicted to be 1055 parts per million even in the best case scenario by year 2300. This far exceeds the often quoted 350 ppm concentration. The results may have policy ramifications as well as significance with respect to the seriousness of continuing increase in CO{sub 2} concentration. The paper will discuss results and implications. (author)

  3. Radiation environmental monitoring and assessment of plant-221 site ten years after decommissioning

    International Nuclear Information System (INIS)

    Li Yang; Gu Zhijie; Pan Wei; Ren Xiaona; Hu Xiaolin; She Haiqiang

    2011-01-01

    More than 10 years have passed since nuclear facility decommissioning practice for Plant-221 finished. Environmental radiation monitoring and post assessment of the decommissioning site of Plant-221 was carried out during 2003-2006, which was organized by Department of Environmental Protection and executed by China Institute for Radiation Protection, Environmental Radiation Monitoring station of Qinghai Province, etc. It shows that the decommissioning practice for Plant-221 complied with relevant limits for decommissioning, and its environmental radiation situation has not had significant change in general after 10 years, and the potential impact to the public and the environmental is acceptable. (authors)

  4. Policy and systems analysis for nuclear installation decommissioning

    International Nuclear Information System (INIS)

    Gu Jiande

    1995-01-01

    On the basis of introducing into principal concept for nuclear installation decommissioning, form policy, sciences point of view, the author analyses present problems in the policy, the administrative and programme for decommissioning work in China. According to the physical process of decommissioning, the author studied engineering economics, derived method and formulas to estimate decommissioning cost. It is pointed out that basing on optimization principle for radiation protection and analysing cost-benefit for decommissioning engineering, the corresponding policy decision can be made

  5. Full system chemical decontamination used in nuclear decommissioning

    International Nuclear Information System (INIS)

    Elder, George; Rottner, Bernard; Braehler, Georg

    2012-01-01

    The decommissioning of nuclear power stations at the end of the operational period of electricity generation offers technical challenges in the safe dismantling of the facility and the minimization of radioactive waste arising from the decommissioning activities. These challenges have been successfully overcome as demonstrated by decommissioning of the first generation of nuclear power plants. One of the techniques used in decommissioning is that of chemical decontamination which has a number of functions and advantages as given here: 1. Removal of contamination from metal surfaces in the reactors cooling systems. 2. Reduction of radioactive exposure to decommissioning workers 3. Minimization of metal waste by decontamination and recycling of metal components 4. Control of contamination when dismantling reactor and waste systems 5. Reduction in costs due to lower radiation fields, lower contamination levels and minimal metal waste volume for disposal. One such chemical decontamination technology was developed for the Electric Power Research Institute (EPRI) by Bradtec (Bradtec is an ONET Technologies subsidiary) and is known as the EPRI DFD system. This paper gives a description of the EPRI DFD system, and highlights the experience using the system. (orig.)

  6. Civil engineering design for decommissioning of nuclear installations

    International Nuclear Information System (INIS)

    Paton, A.A.; Benwell, P.; Irwin, T.F.; Hunter, I.

    1984-01-01

    This report describes the work carried out by Taylor Woodrow Construction Limited (TWC) in a study aimed at identifying features which may be incorporated at the design stage of future nuclear power plants to facilitate their eventual decommissioning and, in so doing, promote economic and radiological benefits at teh decommissioning stage. For the purposes of this study, decommissioning of a nuclear facility means those measures taken at the end of the facility's operating life to remove it from the site and restore the site to green field conditions, and, while so doing, ensure the continued protection of the public from any residual radioactivity or other potential hazards present in or emanating from the facility. The overall decommissioning process involves eventual dismantling and demolition and may also include, where possible and appropriate, the intermediate steps of renewal and refurbishing. The work has been carried out in a number of sequential stages consisting principally of a literature review, identification of problems likely to arise in decommissioning, generation of possible solutions to the problems, first assessment of the feasibility of these solutions, closer investigation of promising solutions and, finally, preparation of conclusions and recommendations. (author)

  7. Decommissioning of nuclear facilities in Europe and the experience of TUV SUD

    International Nuclear Information System (INIS)

    Hummel, Lothar; Kim, Duill; Ha, Taegun; Yang, Kyunghwa

    2012-01-01

    Many commercial nuclear facilities of the first generation will be taken out of operation in the near future. As of January 2012, total 19 prototype and commercial nuclear reactors have been decommissioned or are under dismantling in Germany. Most of decommissioning projects were successfully performed and a great deal of experience has been accumulated. Selecting a decommissioning strategy is a very important step at the beginning of the decision making process. According to IAEA requirements immediate dismantling is chosen as a preferred option in many countries today. It is associated with less uncertainty, positive political and social effect, and it can make use of existing operational experience and know-how. The availability of funds and final repository is of high importance for a decommissioning strategy selection. The time frame for the dismantling of nuclear facilities depends on the type, size and complexity of the individual project. TUV SUD, which is supervising most of nuclear power plants in Germany, has accumulated lots of experience by taking parts in decommissioning projects. It direct dismantling is chosen, actual light water reactor in Germany decommissioned to green field in approx. 10 years. The activities of TUV SUD cover from establishing the decommissioning concept to the clearance of the sites. This provides an overview of decommissioning projects of nuclear facilities in Europe, including a detail illustration of the German situation. Finally, some recommendations are suggested for the first decommissioning project based on the lessons and experiences derived from many decommissioning works in Europe

  8. Preliminary plan for decommissioning - repository for spent nuclear fuel

    International Nuclear Information System (INIS)

    Hallberg, Bengt; Tiberg, Liselotte

    2010-06-01

    The final disposal facility for spent nuclear fuel is part of the KBS-3 system, which also consists of a central facility for interim storage and encapsulation of the spent nuclear fuel and a transport system. The nuclear fuel repository will be a nuclear facility. Regulation SSMFS 2008:1 (Swedish Radiation Safety Authority's regulations on safety of nuclear facilities) requires that the licensee must have a current decommissioning plan throughout the facility lifecycle. Before the facility is constructed, a preliminary decommissioning plan should be reported to the Swedish Radiation Safety Authority. This document is a preliminary decommissioning plan, and submitted as an attachment to SKB's application for a license under the Nuclear Activities Act to construct, own and operate the facility. The final disposal facility for spent nuclear fuel consists of an above ground part and a below ground part and will be built near Forsmark and the final repository for radioactive operational waste, SFR. The parts above and below ground are connected by a ramp and several shafts, e.g. for ventilation. The below ground part consists of a central area, and several landfill sites. The latter form the repository area. The sealed below ground part constitutes the final repository. The decommissioning is taking place after the main operation has ended, that is, when all spent nuclear fuel has been deposited and the deposition tunnels have been backfilled and plugged. The decommissioning involves sealing of the remaining parts of the below ground part and demolition of above ground part. When decommissioning begins, there will be no contamination in the facility. The demolition is therefore performed as for a conventional plant. Demolition waste is sorted and recycled whenever possible or placed in landfill. Hazardous waste is managed in accordance with current regulations. A ground investigation is performed and is the basis for after-treatment of the site. The timetable for the

  9. Scenarios for dealing with large components in the process of decommissioning nuclear power plants and the possibility of their implementation in the Slovak Republic

    International Nuclear Information System (INIS)

    Hornacek, M.; Necas, V.

    2014-01-01

    The subject of this presentation is a general assessment of the strategies of dismantling of large components in view of the experience gained from projects implemented as well as the identification of the factors determining the choice of the appropriate disassembly procedure. The paper also deals with the possibilities of removing the steam generator used in nuclear power plant Bohunice V1, which is currently in the process of decommissioning. Different scenarios for dismantling, storage respectively storing into the repository are analyzed. The is also studied the impact of declining of the activity of natural decay and application of decontamination technologies (before or dismantling decontamination) on quantities of materials releasable into the environment respectively leviable in the corresponding storage system. (authors)

  10. Decommissioning of excess nuclear facilities

    International Nuclear Information System (INIS)

    Dickson, H.W.; Jacobs, D.J.; Auxier, J.A.

    1978-01-01

    The Department of Energy (DOE) is reviewing the radiological status of over 100 sites previously utilized by the Manhattan Engineering District (MED) and/or the Atomic Energy Commission (AEC) for handling uranium and thorium ores. Many of these sites have been returned to the control of private industry or to public use. Recent radiological surveys indicate that radiation levels at some of the sites exceed certain existing radiological health guidelines, some requiring remedial action. To assess the need for remedial action and to arrive at radiation levels acceptable for unrestricted use of these sites in the future, provisional radiological criteria for decontamination and decommissioning of property contaminated with radium have been developed. These criteria give due consideration to the level of risk, to consistency with existing guidelines, to achievability, enforceability, variability of natural background, flexibility in their application, and the achievement of levels as low as reasonably achievable. Based upon analyses of exposure pathways, numerical criteria have been derived for external gamma radiation, radon daughters levels in structures, radium concentrations in soil and surface contamination levels. In addition, a monitoring program has been designed to evaluate compliance with these decommissioning criteria. (author)

  11. Y-12 Plant Decontamination and Decommissioning Program

    International Nuclear Information System (INIS)

    1992-01-01

    The Decontamination and Decommissioning (D and D) Program at the Oak Ridge Y-12 Plant is part of the Environmental Restoration (ER) and Waste Management (WM) Programs (ERWM). The objective of the ER Program is to provide Y-12 the capability to meet applicable environmental regulations through facility development activities and site remedial actions. The WM Program supports the ER program. The D and D Program provides collective management of sites within the Plant which are in need of decontamination and decommissioning efforts, prioritizes those areas in terms of health, safety, and environmental concerns, and implements the appropriate level of remedial action. The D and D Program provides support to identifiable facilities which formerly served one or more of the many Plant functions. Program activities include (1) surveillance and maintenance of facilities awaiting decommissioning; (2) planning safe and orderly facility decommissioning; and (3) implementing a program to accomplish facility disposition in a safe, cost effective, and timely manner. In order to achieve the first objective, a formal plan which documents the surveillance and maintenance needs for each facility has been prepared. This report provides this documentation for the Y-12 facilities currently included in the D and D Program, as well as those planned for future inclusion in the Program, and includes projected resource requirements for the planning period of FY 1993 through FY 2000

  12. Idea: an integrated set of tools for sustainable nuclear decommissioning projects

    International Nuclear Information System (INIS)

    Detilleux, M.; Centner, B.; Vanderperre, S.; Wacquier, W.

    2008-01-01

    Decommissioning of nuclear installations constitutes an important challenge and shall prove to the public that the whole nuclear life cycle is fully mastered by the nuclear industry. This could lead to an easier public acceptance of the construction of new nuclear power plants. When ceasing operation, nuclear installations owners and operators are looking for solutions in order to assess and keep decommissioning costs at a reasonable level, to fully characterise waste streams (in particular radiological inventories of difficult-to-measure radionuclides) and to reduce personnel exposure during the decommissioning activities taking into account several project, site and country specific constraints. In response to this need, Tractebel Engineering has developed IDEA (Integrated DEcommissioning Application), an integrated set of computer tools, to support the engineering activities to be carried out in the frame of a decommissioning project. IDEA provides optimized solutions from an economical, environmental, social and safety perspective. (authors)

  13. Regulatory procedures for the decommissioning of nuclear installations

    International Nuclear Information System (INIS)

    Woods, P.B.; Basu, P.K.

    1988-01-01

    The basic safety legislation under which operational safety at nuclear installations is regulated does not change when the plant is decommissioned. In the United Kingdom the relevant nuclear safety legislation is embodied in several Acts of Parliament or international conventions. These are listed and described. The potential risk in decommissioning is from radiation exposure of the workers and to a lesser extent of the public and environment. The regulations try to ensure this risk is reduced to acceptable levels. This objective can be achieved if the project is adequately planned, there is reliable information about the plant, the risks are identified and assessed, the quality assurance is good and personnel are trained, and the radioactive wastes produced are managed and disposed of suitably. (U.K.)

  14. Strategy selection for the decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    2004-01-01

    As modern nuclear power programmes mature and large, commercial nuclear power plants and fuel cycle facilities approach the end of their useful life by reason of age, economics or change of policy on the use of nuclear power, new challenges associated with decommissioning and dismantling come to the fore. Politicians and the public may expect there to be a 'right answer' to the choice of strategy for a particular type of facility, or even all facilities. Both this seminar and wider experience show that this is not the case. Local factors and national political positions have a significant input and often result in widely differing strategy approaches to broadly similar decommissioning projects. All facility owners represented at the seminar were able to demonstrate a rational process for strategy selection and compelling arguments for the choices made. In addition to the papers that were presented, these proceedings include a summary of the discussions that took place. (author)

  15. Architecture for a new age of nuclear waste and decommissioning

    International Nuclear Information System (INIS)

    Barrie, D.

    1995-01-01

    Plans to decommission the Trawsfynydd Nuclear Reactor and bury the remaining structure, restoring the site to its previous natural appearance, are set out in this booklet. The ''Poweto Change'' project is a cooperative venture, drawing together architects, engineers, artists and the local communities of Trawsfynydd and Blaenaum Ffestiniog. Plans for reusing parts of the power plants structures to recreate a media centre are discussed and illustrated. (author)

  16. European Nuclear Decommissioning Training Facility II

    International Nuclear Information System (INIS)

    Demeulemeester, Y.

    2005-01-01

    SCK-CEN co-ordinates a project called European Nuclear Decommissioning Training Facility II (EUNDETRAF II) in the Sixth Framework Programme on Community activities in the field of research, technological development and demonstration for the period 2002 to 2006. This was a continuation of the FP5 project EUNDETRAF. EUNDETRAF II is a consortium of main European decommissioners, such as SCK-CEN, EWN (Energie Werke Nord, Greifswald Germany), Belgatom (Belgium), SOGIN Societa Gestione Impiantio Nucleari, Italy), Universitaet Hannover (Germany), RWE NUKEM (United Kingdom), DECOM Slovakia Slovakia), CEA Centre d'Energie Atomique, France), UKAEA (United Kingdom's Atomic Energy Agency, United Kingdom) and NRG (Nuclear Research and consultancy Group, Netherlands). The primary objective of this project is to bring together this vast skill base and experience; to consolidate it for easy assimilation and to transfer to future generations by organising a comprehensive training programme.Each training course has a one-week theoretical and a one-week practical component. The theoretical part is for a broader audience and consists of lectures covering all the main aspects of a decommissioning. The practical part of the course includes site visits and desk top solutions of anticipated decommissioning problems. Due to operational constraints and safety considerations, the number of participants to this part of the course is strictly limited. The partners intend to organise altogether two two-week EUNDETRAF II training courses over a period of three years. Another goal is to disseminate the existing theory as well as the practical know-how to personnel of the third countries. Finally it is important to bring together the principal decommissioning organisations undertaking various decommissioning activities. The project creates a forum for regular contacts to exchange information and experiences for mutual benefit of these organisations as well as to enhance skill base in Europe to

  17. Nuclear Decommissioning R and D: a successful history that goes on. Evolution of R and D for nuclear decommissioning

    International Nuclear Information System (INIS)

    Laraia, Michele; )

    2017-01-01

    Research and Development (R and D) in Nuclear Decommissioning date back to the 1980's and 1990's. At that time, decommissioning was a relatively new, sporadic activity; technologies were mostly imported from the non-nuclear field and adapted to nuclear uses (a trend that continues to this day and should not be looked down). R and D were first applied to a laboratory scale, and later on expanded to prototype and pilot installations. The European Commission launched a series of multi-year R and D programmes, ultimately covering the full-scale decommissioning of nuclear power plants and other large installations. Certain installations (especially the BR-3 reactor at Mol, Belgium), were used to test and compare different technologies and assign a ranking based on various factors. In parallel, the US Department of Energy was active in a number of R and D activities, culminating in a number of topical publications until around the year 2000 and the explosive growth of the decommissioning market. In Japan in early 1990's the decommissioning of the Japan Power Demonstration Reactor (JPDR) was used to test almost all dismantling techniques being available at that time: the spin-offs of JPDR work were still flowing into the nuclear community until recently. It has to be also highlighted that the Chernobyl accident boosted a spate of decommissioning R and D aimed at solving practical problems in the aftermath of that severe accident. Although R and D in this field peaked around the year 2000, R and D efforts have continued to this day. While decommissioning is not 'rocket science' and it can be safely stated that this industry has reached maturity, there are areas (e.g. management of secondary waste, access, characterization and dismantling in 'difficult' environments) that require further efforts to optimize processes and reduce the still high costs. The IAEA has contributed to these advances in various ways. For example, some 50 topical reports on the decommissioning of

  18. An international contribution to decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Lazo, T.

    1995-01-01

    Nuclear power plants and fuel cycle facilities must be retired from service when they have completed their design objective, become obsolete or when they no longer fulfill current safety, technical or economic requirements. Decommissioning is defined as the set of technical and administrative operations that provides adequate protection of workers and public against radiation risks, minimizes impact on the environment and involves manageable costs. A traditional definition of the stages of decommissioning has been proposed by the IAEA and is largely used worldwide. A number of factors have to be considered when selecting the optimum strategy, which include the national nuclear policy, characteristics of the facility, health and safety, environmental protection, radioactive waste management, future use of the site, improvements of the technology that may be achieved in the future, costs and availability of funds and various social considerations. The paper describes the current situation of nuclear facilities and the associated forthcoming requirements and problems of decommissioning. This task requires a complete radionuclide inventory, decontamination methods, disassembly techniques and remote operations. Radiation safety presents three aspects: nuclear safety, protection of workers and protection of the public. An appropriate delay to initiate decommissioning after shutdown of a facility may considerably reduce workers exposures and costs. Decommissioning also generates significant quantities of neutron-activated and surface contaminated materials which require a specific management. A vigorous international cooperation and coordinated research programs have been encouraged by the NEA for a minimization of costs and efforts and to provide a basis for consensus of opinions on policies, strategies and criteria. (J.S.). 19 refs., 5 figs., 3 tabs

  19. 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)

  20. Technology and costs for decommissioning Swedish nuclear power plants; Teknik och kostnader foer rivning av svenska kaernkraftverk

    Energy Technology Data Exchange (ETDEWEB)

    Hedin, Gunnar; Gustavsson, Boerje [Westinghouse Electric Sweden AB, Vaesteraas (Sweden); Carlsson, Jan [Swedish Nuclear Fuel and Waste Management Co., Stockholm (Sweden)

    2004-06-01

    SKB has already performed three studies on available technology and approximate costs for decommissioning Swedish NPPs (years 1986, 1994 and 2000). The present report is an update of the year 2000 report with emphasis on areas that have been studied since the publication of that report. The report also gives a review of the technologies that have been chosen for decommissioning the Swedish reactors. The cost-estimation has also been updated and indexed to the present monetary situation. Areas in need for further studies are pointed in the report.

  1. General principles underlying the decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    1988-03-01

    Previous statements on the use of the term 'decommissioning' by the International Atomic Energy Agency, the Atomic Energy Control Board, and the Advisory Committee on Nuclear Safety are reviewed, culminating in a particular definition for its use in this paper. Three decommissioning phases are identified and discussed, leading to eight general principles governing decommissioning including one related to financing

  2. Decommissioning of nuclear facilities using current criteria

    International Nuclear Information System (INIS)

    Shum, E.Y.; Swift, J.J.; Malaro, J.C.

    1991-01-01

    When a licensed nuclear facility ceases operation, the US Nuclear Regulatory Commission (NRC) is responsible for ensuring that the facility and its site are decontaminated to an acceptable level so that it is safe to release that facility and site for unrestricted public use. Currently, the NRC is developing decommissioning criteria based on reducing public doses from residual contamination in soils and structures at sites released for unrestricted use to as low as is reasonably achievable (ALARA). Plans are to quantify ALARA in terms of an annual total effective dose equivalent (TEDE) to an average member of the most highly exposed population group. The NRC is working on a regulatory guidance document to provide a technical basis for translating residual contamination levels to annual dose levels. Another regulatory guide is being developed to provide guidance to the licensee on how to conduct radiological surveys to demonstration compliance with the NRC decommissioning criteria. The methods and approaches used in these regulatory guides on the decommissioning of a nuclear facility are discussed in the paper

  3. Green Vinca - Vinca Institute nuclear decommissioning program

    International Nuclear Information System (INIS)

    Pesic, M.; Subotic, K.; Ljubenov, V.; Sotic, O.

    2003-01-01

    Current conditions related to the nuclear and radiation safety in the Vinca Institute of Nuclear Sciences, Belgrade, Serbia and Montenegro are the result of the previous nuclear programs in the former Yugoslavia and strong economic crisis during the previous decade. These conditions have to be improved as soon as possible. The process of establishment and initialisation of the Vinca Institute Nuclear Decommissioning (VIND) Program, known also as the 'Green Vinca' Program supported by the Government of the Republic Serbia, is described in this paper. It is supposed to solve all problems related to the accumulated spent nuclear fuel, radioactive waste and decommissioning of RA research reactor. Particularly, materials associated to the RA reactor facility and radioactive wastes from the research, industrial, medical and other applications, generated in the previous period, which are stored in the Vinca Institute, are supposed to be proper repackaged and removed from the Vinca site to some other disposal site, to be decided yet. Beside that, a research and development program in the modern nuclear technologies is proposed with the aim to preserve experts, manpower and to establish a solid ground for new researchers in field of nuclear research and development. (author)

  4. Decommissioning three nuclear reactors at Los Alamos National Laboratory

    International Nuclear Information System (INIS)

    Montoya, G.M.; Salazar, M.

    1992-01-01

    Three nuclear reactors, including the historic water boiler reactor, were decommissioned at Los Alamos National Laboratory (LANL). The decommissioning of the facilities involved removing the reactors and their associated components. Planning for the decommissioning operation included characterizing the facilities, estimating the costs of decommissioning operations, preparing environmental documentation, establishing systems to track costs and work progress, and preplanning to correct health and safety concerns in each facility

  5. Practical decommissioning experience with nuclear installations in the European Community

    International Nuclear Information System (INIS)

    Skupinski, E.

    1993-01-01

    Initiated by the Commission of the European Communities (CEC), this seminar was jointly organized by Kernkraftwerke RWE Bayernwerk GmbH (KRB) and the CEC at Gundremmingen-Guenzburg (D), where the former KRB-A BWR is presently being dismantled. The meeting aimed at gathering a limited number of European experts for the presentation and discussion of operations, the results and conclusions on techniques and procedures presently applied in the dismantling of large-scale nuclear installations in the European Community. Besides the four pilot dismantling projects of the presently running third R and D programme (1989-93) of the European Community on decommissioning of nuclear installations (WAGR, BR-3 PWR, KRB-A BWR and AT-1 FBR fuel reprocessing), the organizers selected the presentation of topics on the following facilities which have a significant scale and/or representative features and are presently being dismantled: the Magnox reprocessing pilot plant at Sellafield, the HWGCR EL4 at Monts d'Arree, the operation of an on-site melting furnace for G2/G3 GCR dismantling waste at Marcoule, an EdF confinement conception of shut-down LWRs for deferred dismantling, and the technical aspects of the Greifswald WWER type NPPs decommissioning. This was completed by a presentation on the decommissioning of material testing reactors in the United Kingdom and by an overview on the conception and implementation of two EC databases on tools, costs and job doses. The seminar concluded with a guided visit of the KRB-A dismantling site. This meeting was attended by managers concerned by the decommissioning of nuclear installations within the European Community, either by practical dismantling work or by decision-making functions. Thereby, the organizers expect to have contributed to the achievement of decommissioning tasks under optimal conditions - with respect to safety and economics - by making available a complete and updated insight into on-going dismantling projects and by

  6. Plan for reevaluation of NRC policy on decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    1978-12-01

    The present decommissioning regulations contained in Sections 50.33(f) and 50.82 of 10 CFR part 50 require applicants for power reactor operating licenses to demonstrate that they can obtain the funds needed to meet both operating costs and estimated costs of shutdown and decommissioning. The development of detailed, specific decommissioning plans for nuclear power plants is not currently required until the licensee seeks to terminate his operating license. Recognizing that the current generation of large commercial reactors and supporting nuclear facilities would substantially increase the need for future decommissionings, the NRC staff began an in-depth review and reevaluation of NRC's regulatory approach to decommissioning in 1975. The Nuclear Regulatory Commission is now considering development of a more explicit overall policy for nuclear facility decommissioning and amending its regulations in 10 CFR Parts 30, 40, 50, and 70 to include more specific guidance on decommissioning criteria for production and utilization facility licensees and byproduct, source, and special nuclear material licensees. In response to comments from the public and states, and to information gained during the initial stage of execution of the plan, several modifications of the plan are now required. The revised overall report sets forth in detail the current NRC staff plan for the development of an overall NRC policy on decommissioning of nuclear facilities

  7. The Preliminary Decommissioning Plan of the Dalat Nuclear Research Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Lam, Pham Van; Vien, Luong Ba; Vinh, Le Vinh; Nghiem, Huynh Ton; Tuan, Nguyen Minh; Phuong, Pham Hoai [Nuclear Research Institute, Da Lat (Viet Nam)

    2013-08-15

    Recently, after 25 years of operation, a preliminary decommissioning plan for the Dalat Nuclear Research Reactor (DNRR) has been produced but as yet it has not been implemented due to the continued operations of the reactor. However, from the early phases of facility design and construction and during operation, the aspects that facilitate decommissioning process have been considered. This paper outlines the DNRR general description, the organization that manages the facility, the decommissioning strategy and associated project management, and the expected decommissioning activities. The paper also considers associated cost and funding, safety and environmental issues and waste management aspects amongst other considerations associated with decommissioning a nuclear research reactor. (author)

  8. Decommissioning and cutting methods in the nuclear field

    Energy Technology Data Exchange (ETDEWEB)

    Bensoussan, E. [Protem SAS, 26 - Etoile sur Rhone (France)

    2008-07-01

    A few states started in the early forties/fifties the first development of nuclear technologies. Some of them now own a great amount of nuclear installations which entirely fulfill their assignment. In some cases, the life time of the nuclear power plants which were scheduled for approximately 30 years have been extended by more than 50%, the other ones as well as fuel production and enrichment plants, experimental or research reactors, will have to be dismantled in the near future. The decommissioning of those installations is definitely one of the twenty first century challenge. It is differently managed depending on the countries and their energetic and development policies, their financial consideration, the availability of qualified engineers or specialized companies to handle such projects. The final aim of decommissioning is to recover the geographic site in its original condition. A real cooperation is existing in between the people involved in different countries through different types of conferences and meetings during which the main subjects are: - The safety of the operators during all the phases of decommissioning operations. - Restrictions and dimensioning of the required equipment - Storage and waste management - Elaboration of procedures for recording all different steps and processes. Some of the techniques are described in this paper without being exhaustive. (author)

  9. Decommissioning and cutting methods in the nuclear field

    International Nuclear Information System (INIS)

    Bensoussan, E.

    2008-01-01

    A few states started in the early forties/fifties the first development of nuclear technologies. Some of them now own a great amount of nuclear installations which entirely fulfill their assignment. In some cases, the life time of the nuclear power plants which were scheduled for approximately 30 years have been extended by more than 50%, the other ones as well as fuel production and enrichment plants, experimental or research reactors, will have to be dismantled in the near future. The decommissioning of those installations is definitely one of the twenty first century challenge. It is differently managed depending on the countries and their energetic and development policies, their financial consideration, the availability of qualified engineers or specialized companies to handle such projects. The final aim of decommissioning is to recover the geographic site in its original condition. A real cooperation is existing in between the people involved in different countries through different types of conferences and meetings during which the main subjects are: - The safety of the operators during all the phases of decommissioning operations. - Restrictions and dimensioning of the required equipment - Storage and waste management - Elaboration of procedures for recording all different steps and processes. Some of the techniques are described in this paper without being exhaustive. (author)

  10. Progress and experiences from the decommissioning of the eurochemic reprocessing plant

    International Nuclear Information System (INIS)

    Gillis, R.; Lewandowski, P.; Ooms, B.; Reusen, N.; Van Laer, W.; Walthery, R.

    2008-01-01

    The Eurochemic reprocessing facility at Dessel in Belgium, was constructed from 1960 to 1966. After shutdown, the plant was decontaminated from 1975 to 1979 to keep safe standby conditions at reasonable cost. When it was decided in 1986 not to resume reprocessing in Belgium, the main Belgoprocess activities changed to processing and storage of radioactive waste and to decontamination and decommissioning of obsolete nuclear facilities. The industrial decommissioning was started in 1990. This document presents the project: overview of decommissioning activities and equipment used, automation in decontamination, ensuring health and safety during the operations, release of decontaminated materials, current situation of the decommissioning activities and quality assurance program. (A.L.B.)

  11. Decommissioning of nuclear installations - regulations - financing - responsibility - insurance

    International Nuclear Information System (INIS)

    Hubert, E.H.; Andersson, C.; Deprimoz, J.; Mayoux, J.C.; Richard, M.; Sartorelli, C.; Nocera, F.

    1983-01-01

    This paper highlights three aspects of decommissioning of nuclear installations which relate, more or less directly, to legal options already applied or advocated. It reviews the regulatory conditions for decommissioning a nuclear installation and indicates legal provisions for financing decommissioning expenditures. It also describes the legal provisions to determine liabilities in case of nuclear damage and the assistance which insurers may provide to cover the consequences of such liabilities. (NEA) [fr

  12. Unrestricted re-use of decommissioned nuclear laboratories

    Energy Technology Data Exchange (ETDEWEB)

    Cornelissen, R; Noynaert, L; Harnie, S; Marien, J

    1996-09-18

    A decommissioning strategy was developed by the Belgian Nuclear Research Centre SCK/CEN. In this strategy decommissioning works are limited to the radioactive parts of the nuclear installation. After obtaining an attestation for unrestricted reuse of the building after removal of all radioactivity, the building can be used for new industrial purposes outside the nuclear field. The decommissioning activities according to this strategy have been applied in four buildings. The results are described.

  13. Decommissioning of the LURE Nuclear Facility

    International Nuclear Information System (INIS)

    Pauwels, N.; Horodynski, J.M.; Robert, P.; Tadjeddine, A.

    2013-01-01

    With the goal of obtaining the decommissioning of the LURE nuclear facility, three of its accelerators were dismantled and another was modified to be below the thresh- old of 'Installation Nucleaire de Base' status. Operations were carried out with the strategy of mechanical dismantling with no cutting process. As the civil engineering radioactivity level was low, a great majority of it has been left in place with no process- ing, but compensatory measures have been taken for public and environmental protection. The overall result of these operations is a gain in both cost and operating time. They also contribute to a significant decrease in the risks, including radiological ones. The radiological impact after decommissioning remains acceptable. (authors)

  14. Experience gained in the management of radioactive waste from maintenance, decontamination and partial decommissioning of a reprocessing plant and conclusions resulting for the management of radioactive wastes from nuclear power plants

    International Nuclear Information System (INIS)

    Hild, W.

    1983-01-01

    After a short description of the historical background of Eurochemic, its main tasks and the various operational phases, a detailed description of the waste management principles applied is presented. The practical experience in the waste treatment is reported for both the operational phase of the reprocessing plant and its decontamination and partial decommissioning after shutdown. Based on this experience and the presented data, an assessment of the practical operations is made and conclusions are drawn. Finally, recommendations are formulated both for the general waste management policy and the practical waste treatment processes in nuclear power reactors. (author)

  15. Computer System Analysis for Decommissioning Management of Nuclear Reactor

    International Nuclear Information System (INIS)

    Nurokhim; Sumarbagiono

    2008-01-01

    Nuclear reactor decommissioning is a complex activity that should be planed and implemented carefully. A system based on computer need to be developed to support nuclear reactor decommissioning. Some computer systems have been studied for management of nuclear power reactor. Software system COSMARD and DEXUS that have been developed in Japan and IDMT in Italy used as models for analysis and discussion. Its can be concluded that a computer system for nuclear reactor decommissioning management is quite complex that involved some computer code for radioactive inventory database calculation, calculation module on the stages of decommissioning phase, and spatial data system development for virtual reality. (author)

  16. Financing of nuclear power plant decommissioning. A study from the point of view of German and European economic law

    International Nuclear Information System (INIS)

    Jasper, M.

    2008-01-01

    The contribution outlines legal problems from the view of national and European law. It presents alternative funding models and investigates their legal applicability. For example, funds may be established with obligatory contributions by nuclear power plant operators. A model of this type was proposed by the EU Commission. The authors discuss whether the EU Commission has the right at all to make this proposal, and what legal problems may arise in Germany, e.g. the right of property of public utilities. Other funding models are presented and investigated as well. (orig.)

  17. Waste minimization fundamental principles used in radioactive waste management plan for decommissioning of a CANDU - 600 nuclear power plant

    International Nuclear Information System (INIS)

    Barariu, Gheorghe; Georgescu, Roxana Cristiana; Sociu, Florin

    2009-01-01

    The objectives of waste minimization are to limit the generation and spread of radioactive contamination and to reduce the amount of wastes for storage and disposal, thereby limiting any consequent environmental impact, as well as the total costs associated with contaminated material management. This objective will be achieved by: reviewing the sources and characteristics of radioactive materials arising from Decontamination and Decommissioning (D and D) activities; reviewing waste minimization principles and current practical applications, together with regulatory, technical, financial and political factors influencing waste minimization practices; and reviewing current trends in improving waste minimization practices during Decontamination and Decommissioning. The main elements of a waste minimization strategy can be grouped into four areas: source reduction, prevention of contamination spread, recycle and reuse, and waste management optimization. For sustaining this objective, the following principles and procedures of wastes management are taken into account: safety and environment protection principles; principles regarding the facility operation; quality assurance procedures; procedures for material classification and releasing. (authors)

  18. Waste management practices in decommissioning nuclear facilities

    International Nuclear Information System (INIS)

    Dickson, H.W.

    1979-01-01

    Several thousand sites exist in the United States where nuclear activities have been conducted over the past 30 to 40 years. Questions regarding potential public health hazards due to residual radioactivity and radiation fields at abandoned and inactive sites have prompted careful ongoing review of these sites by federal agencies including the Department of Energy (DOE) and the Nuclear Regulatory Commission (NRC). In some instances, these reviews are serving to point out poor low-level waste management practices of the past. Many of the sites in question lack adequate documentation on the radiological conditions at the time of release for unrestricted use or were released without appropriate restrictions. Recent investigations have identified residual contamination and radiation levels on some sites which exceed present-day standards and guidelines. The NRC, DOE, and Environmental Protection Agency are all involved in developing decontamination and decommissioning (D and D) procedures and guidelines which will assure that nuclear facilities are decommissioned in a manner that will be acceptable to the nuclear industry, various regulatory agencies, other stakeholders, and the general public

  19. Radionuclide metrology research for nuclear site decommissioning

    Science.gov (United States)

    Judge, S. M.; Regan, P. H.

    2017-11-01

    The safe and cost-effective decommissioning of legacy nuclear sites relies on accurate measurement of the radioactivity content of the waste materials, so that the waste can be assigned to the most appropriate disposal route. Such measurements are a new challenge for the science of radionuclide metrology which was established largely to support routine measurements on operating nuclear sites and other applications such as nuclear medicine. In this paper, we provide a brief summary of the international measurement system that is established to enable nuclear site operators to demonstrate that measurements are accurate, independent and fit for purpose, and highlight some of the projects that are underway to adapt the measurement system to meet the changing demands from the industry.

  20. Study on archive management for nuclear facility decommissioning projects

    International Nuclear Information System (INIS)

    Huang Ling; Gong Jing; Luo Ning; Liao Bing; Zhou Hao

    2011-01-01

    This paper introduces the main features and status of the archive management for nuclear facility decommissioning projects, and explores and discusses the countermeasures in its archive management. Taking the practice of the archive management system of a reactor decommissioning project as an example, the paper illustrates the establishment of archive management system for the nuclear facility decommissioning projects. The results show that the development of a systematic archive management principle and system for nuclear decommissioning projects and the construction of project archives for the whole process from the design to the decommissioning by digitalized archive management system are one effective route to improve the complete, accurate and systematic archiving of project documents, to promote the standardization and effectiveness of the archive management and to ensure the traceability of the nuclear facility decommissioning projects. (authors)

  1. Investment management for nuclear decommissioning trusts

    International Nuclear Information System (INIS)

    Stimes, P.C.; Flaherty, R.T.

    1990-01-01

    According to Nuclear Regulatory Commission estimates, and assuming a 4 percent annual inflation rate, minimum decommissioning requirements for a single reactor could total almost $350 million after 30 years. Consequently, reducing customer contributions to decommissioning funds is a potentially rewarding activity. In fact, improving the after-tax return earned on an NDT fund by as little as one percentage point can reduce customer contributions to the fund by 15% over its life. Unfortunately, many electric utilities are headed in the wrong direction and are unlikely to achieve satisfactory results. The main problem is the prevalence of the conventional wisdom, most of which has been appropriated from the area of pension fund management. This is an area which is familiar to most utility managements, but which has only superficial similarity to the issue of NDT investing. The differences are pronounced: NDTs, unlike pensions, are fully taxable at corporate income tax rates. In addition, NDT managers should be concerned with protecting the inflation-adjusted or real value of fund investments at a single, future decommissioning date. Pension managers, on the other hand, may be concerned with satisfying nominal contractual obligations spread over an extended future time horizon. In view of the large stakes involved in the management of NDTs, the authors summarize five key tenets of the conventional wisdom in this area and demonstrate where they feel they are in error

  2. A radical approach to decommissioning and nuclear liabilities management

    International Nuclear Information System (INIS)

    Pooley, D.

    1996-01-01

    UKAEA Government Division has been set up primarily to manage and eventually eliminate the nuclear liabilities left from the many national nuclear programmes in which UKAEA has been involved. It is no longer primarily a nuclear plant or decommissioning operator but has developed a radical approach to decommissioning. It targets best value for money, alongside meeting safety and environmental requirements, by major use of contractors for its work, including using them as managing agents for big projects. In its first year of operation it made considerable progress in setting out the mission, goals, performance measures and operational principles for such an organization, as well as in reducing costs on a wide front from those expected, in increasing competition for future projects, and in keeping individual projects under good control. It also made major physical progress with specific decommissioning projects. For the future it has established a programme of continuous performance improvement which will bring further benefits and provide a benchmark for all organizations in the business of liabilities management. (author)

  3. A radical approach to decommissioning and nuclear liabilities management

    International Nuclear Information System (INIS)

    Pooley, D.

    1995-01-01

    UKAEA Government Division has been set up primarily to manage and eventually eliminate the nuclear liabilities left from the many national nuclear programmes in which UKAEA has been involved. It is no longer primarily a nuclear plant or decommissioning operator but has developed a radical approach to decommissioning. It targets best value for money, alongside meeting safety and environmental requirements, by major use of contractors for its work, including as managing agents for big projects. In its first year of operation it made considerable progress in setting out the mission, goals, performance measures and operational principles for such an organisation, as well as reducing costs on a wide front from those expected in increasing competition for future projects, and in keeping individual projects under good control. It also made major physical progress with specific decommissioning projects. For the future it has established a programme of continuous performance improvement which will bring further benefits and provide a benchmark for all organisations in the business of liabilities management. (author)

  4. Decommissioning of nuclear facilities in Korea

    International Nuclear Information System (INIS)

    Hahn, Pil Soo

    2003-01-01

    In 1996, it was concluded that the first Korea research reactor (KRR-1) and the second Korea research reactor (KRR-2) would be shut down and decommissioned. The main reason for the decommissioning was that the facilities became old and has become surrounded by the urbanised community. And many difficulties, including the higher cost, were faced according to the enhanced regulations. Another reason was the introduction of a new research reactor 'HANARO' in 1995. A project to decommission the reactors was launched on January of 1997 with a goal of release of the site and buildings for unrestricted use by 2008. All the radioactive wastes generated are to be transported to the national repository, planned by the Korea Hydro and Nuclear Power Company (KHNP), and the final evaluation of the residual radioactivity will be made before the clearance of the site. As a first step of the project, a decommissioning plan, including the assessment of the environmental impact and the quality assurance program, was prepared and submitted to the government in 1998. It was approved, after its safety evaluation, by the Korea Institute of Nuclear Safety (KINS) in November of 2000. After some preparative works such as documentation of procedures, the decontamination and dismantling works for the laboratories and hot cells of KRR-2 were started in September, 2001 and finished in December, 2002. The spent fuels that had been generated from the reactors were transferred to the United States in 1998 and no spent fuel remained at the site. All the liquid waste, both operational and decommissioning, was very low in its radioactivity and was treated in a natural evaporation facility of 200 m3/year capacity, developed by KAERI. Especially the laundry waste was treated in a membrane filtering unit for the removal of surfactants before being introduced to the natural evaporator. The solid wastes were segregated and packed in the container of 4 m3, designed according to the ISO-1496, and also in

  5. Analysis of the risk assessment of a waste repository for radioactive waste from the decommissioning of nuclear power plants

    International Nuclear Information System (INIS)

    Weil, L.

    1984-09-01

    A review of decommissioning experiences and concepts is presented. The radioactive inventory of LWR of modern design at final shutdown is estimated on the basis of activation analysis and empirical data on contamination. In combination with existing types of waste packages and deposition techniques these results allow a prediction of the necessary repository volume for the decommissioning wastes in the Federal Republic of Germany. The essential element of this investigation is the development of a model for the quantitative analysis of the accident 'water intrusion' in the repository. Based on the fundamental chemical and physical processes governing nuclide migration a transport equation is obtained which can be restricted to one dimension due to the thickness and the low permeability of the geological layers above the repository. The radiological consequences are evaluated. The long-lived activation product Ni-59 turns out to be critical radionuclide. Despite a number of conservatisms in the model the evaluated doses are acceptable. The results clearly support the long term safety of the 'Konrad' mine as a low-level waste repository. (orig./HP) [de

  6. The European Community's research and development programme on the decommissioning of nuclear installations

    International Nuclear Information System (INIS)

    Skupinski, E.

    1988-01-01

    The Commission of the European Communities (CEC) continued with a second research programme on the decommissioning of nuclear installations (1984-88), after having completed a first programme on the decommissioning of nuclear power plants (1979-83). The programme, which has about 70 research contracts with organisations or private firms in the member states, includes the development and testing of advanced techniques, such as decontamination and dismantling, and the consideration of the radioactive waste arising therefrom. Work is done at laboratory scale or in the context of large-scale decommissioning operations. The paper will give an overview on the technical content and on some selected results. (author)

  7. Methodology for evaluating radiological consequences of the management of very low-level solide waste arising from decommissioning of nuclear power plants

    International Nuclear Information System (INIS)

    Smith, G.M.; Hemming, C.R.; Clark, J.M.; Chapuis, A.M.; Garbay, H.

    1985-01-01

    In this report a methodology is described, and illustrated by examples, for the evaluation of individual doses and collective dose commitments arising as a result of various management modes for very low-level solid wastes arising from the decommissioning of nuclear power plants. Estimates have been made of the masses of materials activated and contaminated to within three concentration limits, 0.37, 3.7 and 37 Bq g-1, at three times after reactor shutdown, 5 y, 25 y and 100 y. The disposal options considered are shallow land burial, at a municipal landfill site or at the reactor site, and disposal on the seabed in coastal waters or the deep ocean. It is assumed that there is no special treatment to reduce or eliminate the potential radiological hazard. Consideration has also been given to the radiological impact of recycling of contaminated steel. The radiological impacts of all the management options for the wastes considered were found to be small. It may therefore be acceptable to allow such very low-level wastes to be disposal of without special restrictions provided that the level and type of activity of the wastes can be verified. In addition the health detriment cost associated with all the management options is small, so it is likely that other factors such as transport and engineering costs will be more important in final decisions about the management of these wastes

  8. Nuclear facility decommissioning and site remedial actions

    International Nuclear Information System (INIS)

    Knox, N.P.; Webb, J.R.; Ferguson, S.D.; Goins, L.F.; Owen, P.T.

    1990-09-01

    The 394 abstracted references on environmental restoration, nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the eleventh in a series of reports prepared annually for the US Department of Energy's Remedial Action Programs. Citations to foreign and domestic literature of all types -- technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions -- have been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy's Remedial Action Programs. Major sections are (1) Surplus Facilities Management Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Programs, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Grand Junction Remedial Action Program, (7) Uranium Mill Tailings Management, (8) Technical Measurements Center, (9) Remedial Action Program, and (10) Environmental Restoration Program. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication title. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, subject category, and keywords. This report is a product of the Remedial Action Program Information Center (RAPIC), which selects and analyzes information on remedial actions and relevant radioactive waste management technologies

  9. Nuclear facility decommissioning and site remedial actions

    Energy Technology Data Exchange (ETDEWEB)

    Knox, N.P.; Webb, J.R.; Ferguson, S.D.; Goins, L.F.; Owen, P.T.

    1990-09-01

    The 394 abstracted references on environmental restoration, nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the eleventh in a series of reports prepared annually for the US Department of Energy's Remedial Action Programs. Citations to foreign and domestic literature of all types -- technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions -- have been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy's Remedial Action Programs. Major sections are (1) Surplus Facilities Management Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Programs, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Grand Junction Remedial Action Program, (7) Uranium Mill Tailings Management, (8) Technical Measurements Center, (9) Remedial Action Program, and (10) Environmental Restoration Program. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication title. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, subject category, and keywords. This report is a product of the Remedial Action Program Information Center (RAPIC), which selects and analyzes information on remedial actions and relevant radioactive waste management technologies.

  10. Nuclear facility decommissioning and site remedial actions

    International Nuclear Information System (INIS)

    Owen, P.T.; Knox, N.P.; Ferguson, S.D.; Fielden, J.M.; Schumann, P.L.

    1989-09-01

    The 576 abstracted references on nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the tenth in a series of reports prepared annually for the US Department of Energy's Remedial Action Programs. Citations to foreign and domestic literature of all types--technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions--have been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy's Remedial Action Programs. Major sections are (1) Surplus Facilities Management Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Program, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Uranium Mill Tailings Management, (7) Technical Measurements Center, and (8) General Remedial Action Program Studies. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication description. Indexes are provided for author, corporate affiliation, title work, publication description, geographic location, subject category, and keywords

  11. Nuclear facility decommissioning and site remedial actions

    Energy Technology Data Exchange (ETDEWEB)

    Owen, P.T.; Knox, N.P.; Ferguson, S.D.; Fielden, J.M.; Schumann, P.L.

    1989-09-01

    The 576 abstracted references on nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the tenth in a series of reports prepared annually for the US Department of Energy's Remedial Action Programs. Citations to foreign and domestic literature of all types--technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions--have been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy's Remedial Action Programs. Major sections are (1) Surplus Facilities Management Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Program, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Uranium Mill Tailings Management, (7) Technical Measurements Center, and (8) General Remedial Action Program Studies. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication description. Indexes are provided for author, corporate affiliation, title work, publication description, geographic location, subject category, and keywords.

  12. Methods for reducing occupational exposures during the decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    1987-01-01

    The decommissioning and decontamination of nuclear facilities is a topic of great interest to many Member States of the International Atomic Energy Agency (IAEA) because of the large number of older facilities which have been or soon will be retired from service. This report is a review of the current state of knowledge concerning methods for reducing occupational exposures during the decommissioning of nuclear facilities. This report focuses on water cooled nuclear power plants but, in addition, other major nuclear facilities are briefly discussed to determine how they differ from nuclear power plants in this regard. The information presented should be useful to those responsible for or interested in designing or constructing nuclear facilities or in the planning or implementing of the decommissioning of such installations. 59 refs, 1 tab

  13. Decommissioning of nuclear facilities. Feasibility, needs and costs

    International Nuclear Information System (INIS)

    1986-01-01

    Reactor decommissioning activities generally are considered to begin after operations have ceased and the fuel has been removed from the reactor, although in some countries the activities may be started while the fuel is still at the reactor site. The three principal alternatives for decommissioning are described. The factors to be considered in selecting the decommissioning strategy, i.e. a stage or a combination of stages that comprise the total decommissioning programme, are reviewed. One presents a discussion of the feasibility of decommissioning techniques available for use on the larger reactors and fuel cycle facilities. The numbers and types of facilities to be decommissioned and the resultant waste volumes generated for disposal will then be projected. Finally, the costs of decommissioning these facilities, the effect of these costs on electricity generating costs, and alternative methods of financing decommissioning are discussed. The discussion of decommissioning draws on various countries' studies and experience in this area. Specific details about current activities and policies in NEA Member Countries are given in the short country specific Annexes. The nuclear facilities that are addressed in this study include reactors, fuel fabrication facilities, reprocessing facilities, associated radioactive waste storage facilities, enrichment facilities and other directly related fuel cycle support facilities. The present study focuses on the technical feasibility, needs, and costs of decommissioning the larger commercial facilities in the OECD member countries that are coming into service up to the year 2000. It is intended to inform the public and to assist in planning for the decommissioning of these facilities

  14. Nuclear data in the problem of fission reactor decommissioning

    International Nuclear Information System (INIS)

    Manokhin, V.N.; Kulagin, N.T.

    1993-01-01

    This report presents a review of the works published in Russia during last several years and devoted to the problem of nuclear data and calculations of nuclear facilities activation for fission reactor decommissioning. 6 refs

  15. Decommissioning of the Plutonium Purification and Residues Recovery Plant

    International Nuclear Information System (INIS)

    Hunt, J. G.

    2006-01-01

    British Nuclear Group is continuing to build on BNFL's successful record of decommissioning redundant nuclear facilities. Challenging radiological conditions and complex technical problems have been overcome to reduce the hazard associated with the UK's nuclear legacy. The former Plutonium Purification and Residues Recovery Plant at Sellafield operated from 1954 through to 1987. This is the only plant to have experienced an uncontrolled criticality incident in the UK, in August 1970 during operations. The plant comprised of two mirror image cells approximately 6.5 m x 13.5 m x 16 m, constructed of bare brick. The cell structure provided secondary containment, the process vessels and pipes within the cell providing primary containment. The plant utilized a solvent extraction process to purify the plutonium stream. Surrounding the two process cells to the north, east and south is an annulus area that housed the operational control panels, feed and sample glove-boxes, and ancillary equipment. The building was ventilated by an unfiltered extract on the process cells and a filtered extract from the vessels and glove-boxes. During the long operational lifetime of the plant, the primary containment deteriorated to such an extent that the process cells eventually became the main containment, with levels of radioactive contamination in excess of 14,256 pCi alpha. This led to significant aerial effluent discharges towards the end of the plant's operational life and onerous working conditions during decommissioning. Implementation of a phased decommissioning strategy from 1991 has led to: - A reduction of approximately 60% in the Sellafield site's aerial alpha discharges following installation of a new ventilation system, - Removal of 12 plutonium contaminated glove-boxes and sample cabinets from the building, - Disposal of the approximately 500 m 2 of asbestos building cladding, - Removal of over 90% of the active pipes and vessels from the highly contaminated process cells

  16. Decommissioning and deactivation of nuclear facilities

    International Nuclear Information System (INIS)

    Anasco, Roberto; Harriague, Santiago; Hey, Alfredo M.; Fabbri, Silvio; Garonis, Omar H.

    2003-01-01

    The National Atomic Energy Commission (CNEA) is responsible for the decommissioning and deactivation of all relevant nuclear facilities in Argentina. A D and D Subprogram was created in 2000, within Technology Branch of the CNEA, in order to fulfill this responsibility. The D and D Subprogram has organized its activities in four fields: Planning; Technology development; Human resources development and training; International cooperation. The paper describes the work already done in those 4 areas, as well as the nuclear facilities existing in the country. Planning is being developed for the decommissioning of research reactors, beginning with RA-1, as well as for the Atucha I nuclear power station. An integral Management System has been developed, compatibilizing requirements from ISO 9001, ISO 14001, the national norm for Safety and Occupational Health (equivalent to BS 8800), and IAEA 50-SG Q series. Technology development is for the time being concentrated on mechanical decontamination and concrete demolition. A review has been made of technologies already developed both by CNEA and Nucleoelectrica Argentina S.A. (the nuclear power utility) in areas of chemical and electrochemical decontamination, cutting techniques and robotics. Human resources development has been based on training abroad in the areas of decontamination, cutting techniques, quality assurance and planning, as well as on specific courses, seminars and workshops. An IAEA regional training course on D and D has been given on April 2002 at CNEA's Constituyentes Atomic Center, with the assistance of 22 university graduates from 13 countries in the Latin American and Caribbean Region, and 11 from Argentina. CNEA has also given fellowships for PhD and Master thesis on the subject. International cooperation has been intense, and based on: - IAEA Technical Cooperation Project and experts missions; - Cooperation agreement with the US Department of Energy; - Cooperation agreement with Germany

  17. Communications programme for the RA nuclear reactor decommission

    International Nuclear Information System (INIS)

    Milanovic, S.; Antic, D.

    2002-01-01

    During the decommissioning of the RA research nuclear reactor at the VINCA Institute of Nuclear Sciences, an adequate number of radiation and contamination surveys should be conduced to assure radiological safety of the workers, the public and the environment. Public would like to know more about the nuclear and radiological safety. The communications programme defines the ways to informing the public, its representatives and the information media about the health and safety aspects of the activities during the RA nuclear reactor decommission. (author)

  18. Managing LLRW from decommissioning of nuclear facilities - a Canadian perspective

    Energy Technology Data Exchange (ETDEWEB)

    Donders, R E [Atomic Energy of Canada Ltd., Chalk River, ON (Canada). Chalk River Nuclear Labs.; Hardy, D G [Frontenac Consulting Services, Deep River, ON (Canada); De, P L [Low-Level Radioactive Waste Management Office, Gloucester, ON (Canada)

    1994-03-01

    In Canada, considerable experience has been gained recently in decommissioning nuclear facilities and managing the resulting waste. This experience has raised important issues from both the decommissioning and waste management perspectives. This paper focuses on the waste management aspects of decommissioning. Past experience is reviewed, preliminary estimates of waste volumes and characteristics are provided, and the major technical and regulatory issues are discussed. (author). 5 refs., 1 tab., 2 figs.

  19. Nuclear reactor decommissioning: an analysis of the regulatory environments

    International Nuclear Information System (INIS)

    Cantor, R.

    1986-08-01

    In the next several decades, the electric utility industry will be faced withthe retirement of 50,000 megawatts (mW) of nuclear capacity. Responsibility for the financial and technical burdens this activity entails has been delegated to the utilities operating the reactors. However, the operators will have to perform the tasks of reactor decommissioning within the regulatory environment dictated by federal, state and local regulations. The purpose of this study was to highlight some of the current and likely trends in regulations and regulatory practices that will significantly affect the costs, technical alternatives and financing schemes encountered by the electric utilities and their customers. To identify significant trends and practices among regulatory bodies and utilities, a reviw of these factors was undertaken at various levels in the regulatory hierarchy. The technical policies were examined in reference to their treatment of allowed technical modes, restoration of the plant site including any specific recognition of the residual radioactivity levels, and planning requirements. The financial policies were examined for specification of acceptable financing arrangements, mechanisms which adjust for changes in the important parameters used to establish the fund, tax and rate-base treatments of the payments to and earnings on the fund, and whether or not escalation and/or discounting were considered in the estimates of decommissioning costs. The attitudes of regulators toward financial risk, the tax treatment of the decommissioning fund, and the time distribution of the technical mode were found to have the greatest effect on the discounted revenue requirements. Under plausible assumptions, the cost of a highly restricted environment is about seven times that of the minimum revenue requirement environment for the plants that must be decommissioned in the next three decades

  20. Decommissioning of nuclear facilities: Decontamination, disassembly and waste management

    International Nuclear Information System (INIS)

    1983-01-01

    The term 'decommissioning', as used within the nuclear industry, means the actions taken at the end of a facility's useful life to retire the facility from service in a manner that provides adequate protection for the health and safety of the decommissioning workers, the general public, and for the environment. These actions can range from merely closing down the facility and a minimal removal of radioactive material coupled with continuing maintenance and surveillance, to a complete removal of residual radioactivity in excess of levels acceptable for unrestricted use of the facility and its site. This latter condition, unrestricted use, is the ultimate goal of all decommissioning actions at retired nuclear facilities. The purpose of this report is to provide an information base on the considerations important to decommissioning, the methods available for decontamination and disassembly of a nuclear facility, the management of the resulting radioactive wastes, and the areas of decommissioning methodology where improvements might be made. Specific sections are devoted to each of these topics, and conclusions are presented concerning the present status of each topic. A summary of past decommissioning experience in Member States is presented in the Appendix. The report, with its discussions of necessary considerations, available operational methods, and waste management practices, together with supporting references, provides an appreciation of the activities that comprise decommissioning of nuclear facilities. It is anticipated that the information presented in the report should prove useful to persons concerned with the development of plans for the decommissioning of retired nuclear facilities

  1. Training practices to support decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Bourassa, J.; Clark, C.R.; Kazennov, A.; Laraia, M.; Rodriguez, M.; Scott, A.; Yoder, J.

    2006-01-01

    Adequate numbers of competent personnel must be available during any phase of a nuclear facility life cycle, including the decommissioning phase. While a significant amount of attention has been focused on the technical aspects of decommissioning and many publications have been developed to address technical aspects, human resource management issues, particularly the training and qualification of decommissioning personnel, are becoming more paramount with the growing number of nuclear facilities of all types that are reaching or approaching the decommissioning phase. One of the keys to success is the training of the various personnel involved in decommissioning in order to develop the necessary knowledge and skills required for specific decommissioning tasks. The operating organisations of nuclear facilities normally possess limited expertise in decommissioning and consequently rely on a number of specialized organisations and companies that provide the services related to the decommissioning activities. Because of this there is a need to address the issue of assisting the operating organisations in the development and implementation of human resource management policies and training programmes for the facility personnel and contractor personnel involved in various phases of decommissioning activities. The lessons learned in the field of ensuring personnel competence are discussed in the paper (on the basis of information and experiences accumulated from various countries and organizations, particularly, through relevant IAEA activities). Particularly, the following aspects are addressed: transition of training from operational to decommissioning phase; knowledge management; target groups, training needs analysis, and application of a systematic approach to training (SAT); content of training for decommissioning management and professional staff, and for decommissioning workers; selection and training of instructors; training facilities and tools; and training as

  2. Nuclear energy. First experiences with decommissioning in Germany; Kernenergie. Erste Erfahrungen aus den Stilllegungen in Deutschland

    Energy Technology Data Exchange (ETDEWEB)

    Sokoll, Joerg [Arthur D. Little, Frankfurt am Main (Germany). Energy/Utilities

    2015-05-15

    After the Fukushima disaster in 2011 the German parliament changed the national atomic energy law by way of its thirteenth amendment. In contrast to the initial ''nuclear phaseout'' the new phaseout of nuclear energy foresees a large number of decommissionings which will occur in part successively and in part simultaneously and will extend over a period of eleven years. Eight generating units were already decommissioned in 2011 or have not been ramped up again since then. By 2020 the last units will have been decommissioned and the phaseout of nuclear energy will have been completed, at least in terms of power plant operation. However the subsequent dismantling operations will keep German operators busy for decades to come. This article reports on first practical experiences in decommissioning.

  3. Decommissioning of Nuclear Facilities: Training and Human Resource Considerations

    International Nuclear Information System (INIS)

    2008-01-01

    One of the cornerstones of the success of nuclear facility decommissioning is the adequate competence of personnel involved in decommissioning activities. The purpose of this publication is to provide methodological guidance for, and specific examples of good practices in training as an integral part of human resource management for the personnel performing decommissioning activities. The use of the systematic methodology and techniques described in this publication may be tailored and applied to the development of training for all types of nuclear facilities undergoing decommissioning. Examples of good practices in other aspects of human resources, such as knowledge preservation, management of the workforce and improvement of human performance, are also covered. The information contained in this publication, and the examples provided in the appendices and enclosed CD-ROM, are representative of the experience of decommissioning of a wide variety of nuclear facilities.

  4. The Creative Application of Science, Technology and Work Force Innovations to the Decontamination and Decommissioning of the Plutonium Finishing Plant at the Hanford Nuclear Reservation

    International Nuclear Information System (INIS)

    Charboneau, S.; Klos, B.; Heineman, R.; Skeels, B.; Hopkins, A.

    2006-01-01

    The Plutonium Finishing Plant (PFP) consists of a number of process and support buildings for handling plutonium. Building construction began in the late 1940's to meet national priorities and became operational in 1950 producing refined plutonium salts and metal for the United States nuclear weapons program The primary mission of the PFP was to provide plutonium used as special nuclear material for fabrication into a nuclear device for the war effort. Subsequent to the end of World War II, the PFP's mission expanded to support the Cold War effort through plutonium production during the nuclear arms race. PFP has now completed its mission and is fully engaged in deactivation, decontamination and decommissioning (D and D). At this time the PFP buildings are planned to be reduced to ground level (slab-on-grade) and the site remediated to satisfy national, Department of Energy (DOE) and Washington state requirements. The D and D of a highly contaminated plutonium processing facility presents a plethora of challenges. PFP personnel approached the D and D mission with a can-do attitude. They went into D and D knowing they were facing a lot of challenges and unknowns. There were concerns about the configuration control associated with drawings of these old process facilities. There were unknowns regarding the location of electrical lines and the condition and contents of process piping containing chemical residues such as strong acids and caustics. The gloveboxes were highly contaminated with plutonium and chemical residues. Most of the glovebox windows were opaque with splashed process chemicals that coated the windows or etched them, reducing visibility to near zero. Visibility into the glovebox was a serious worker concern. Additionally, all the gloves in the gloveboxes were degraded and unusable. Replacing gloves in gloveboxes was necessary to even begin glovebox clean-out. The sheer volume of breathing air needed was also an issue. These and other challenges and PFP

  5. Use of data processing tools in decommissioning nuclear facilities

    International Nuclear Information System (INIS)

    Petrasch, P.; Lukacs, G.

    1995-01-01

    With the present level of electronic data processing technology, no project of the scale of nuclear reactor decommissioning could be carried out without the use of data processing systems. On the contrary, a reactor decommissioning project requires essential support not only for the technical but also the economic side through the use of proper data processing programs, and not only general applications in the area of personal computers such as MS-EXCEL or MS Project, but also special data processing systems designed for the reactor decommissioning tasks. Various data processing supports are required depending upon the progress of a reactor decommissioning project. (orig./DG) [de

  6. Economical problems in connection with the decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Dangelmaier, P.

    1977-01-01

    Discussed are: Basic questions of financing, to bring in the decommissioning costs with reference to the various types of enterprises, questions of taxes, use of the accumulated liquid means, the economy of nuclear facilities taking into account the decommissioning expenses. (HP) [de

  7. The regulatory process for the decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    1990-01-01

    The objective of this publication is to provide general guidance to Member States for regulating the decommissioning of nuclear facilities within the established nuclear regulatory framework. The Guide should also be useful to those responsible for, or interested in, the decommissioning of nuclear facilities. The Guide describes in general terms the process to be used in regulating decommissioning and the considerations to be applied in the development of decommissioning regulations and guides. It also delineates the responsibilities of the regulatory body and the licensee in decommissioning. The provisions of this Guide are intended to apply to all facilities within the nuclear fuel cycle and larger industrial installations using long lived radionuclides. For smaller installations, however, less extensive planning and less complex regulatory control systems should be acceptable. The Guide deals primarily with decommissioning after planned shutdown. Most provisions, however, are also applicable to decommissioning after an abnormal event, once cleanup operations have been terminated. The decommissioning planning in this case must take account of the abnormal event. 28 refs, 1 fig

  8. Structure and function design for nuclear facilities decommissioning information database

    International Nuclear Information System (INIS)

    Liu Yongkuo; Song Yi; Wu Xiaotian; Liu Zhen

    2014-01-01

    The decommissioning of nuclear facilities is a radioactive and high-risk project which has to consider the effect of radiation and nuclear waste disposal, so the information system of nuclear facilities decommissioning project must be established to ensure the safety of the project. In this study, by collecting the decommissioning activity data, the decommissioning database was established, and based on the database, the decommissioning information database (DID) was developed. The DID can perform some basic operations, such as input, delete, modification and query of the decommissioning information data, and in accordance with processing characteristics of various types of information data, it can also perform information management with different function models. On this basis, analysis of the different information data will be done. The system is helpful for enhancing the management capability of the decommissioning process and optimizing the arrangements of the project, it also can reduce radiation dose of the workers, so the system is quite necessary for safe decommissioning of nuclear facilities. (authors)

  9. Decommissioning of nuclear facilities by the United States Department of Energy Oak Ridge Field Office

    International Nuclear Information System (INIS)

    DeLozier, M.F.P.

    1992-01-01

    The Oak Ridge Field Office of the United States Department of Energy is projecting one of the largest decommissioning efforts in the nation during the next ten to twenty years. The nuclear facilities are varied with respect to the types of contaminants and types of structures and equipment involved. The facilities planned for decommissioning include 26 ORNL facilities (e.g., OGR, HRE, MSRE), 70 facilities at Oak Ridge K25 site, and the Y-12 plant at Oak Ridge. Innovative technologies are required to decommission the facilities and dispose of the waste generated. (R.P.)

  10. Safety Oversight of Decommissioning Activities at DOE Nuclear Sites

    International Nuclear Information System (INIS)

    Zull, Lawrence M.; Yeniscavich, William

    2008-01-01

    The Defense Nuclear Facilities Safety Board (Board) is an independent federal agency established by Congress in 1988 to provide nuclear safety oversight of activities at U.S. Department of Energy (DOE) defense nuclear facilities. The activities under the Board's jurisdiction include the design, construction, startup, operation, and decommissioning of defense nuclear facilities at DOE sites. This paper reviews the Board's safety oversight of decommissioning activities at DOE sites, identifies the safety problems observed, and discusses Board initiatives to improve the safety of decommissioning activities at DOE sites. The decommissioning of former defense nuclear facilities has reduced the risk of radioactive material contamination and exposure to the public and site workers. In general, efforts to perform decommissioning work at DOE defense nuclear sites have been successful, and contractors performing decommissioning work have a good safety record. Decommissioning activities have recently been completed at sites identified for closure, including the Rocky Flats Environmental Technology Site, the Fernald Closure Project, and the Miamisburg Closure Project (the Mound site). The Rocky Flats and Fernald sites, which produced plutonium parts and uranium materials for defense needs (respectively), have been turned into wildlife refuges. The Mound site, which performed R and D activities on nuclear materials, has been converted into an industrial and technology park called the Mound Advanced Technology Center. The DOE Office of Legacy Management is responsible for the long term stewardship of these former EM sites. The Board has reviewed many decommissioning activities, and noted that there are valuable lessons learned that can benefit both DOE and the contractor. As part of its ongoing safety oversight responsibilities, the Board and its staff will continue to review the safety of DOE and contractor decommissioning activities at DOE defense nuclear sites

  11. From conception to decommissioning-servicing nuclear power

    International Nuclear Information System (INIS)

    Burbridge, R.N.

    1988-01-01

    In any utility, or integrated group of utilities, there is a need for an identified body charged with being the guardians of the design database. This is essential with nuclear stations. Within the CEGB (Central Electricity Generating Board), the Generation Development and Construction Division (GDCD) acts as that guardian and performs the triple role of Client (specifying the requirements and procuring new stations), of Architect-Engineer (defining systems and plant layouts and performing effective project management), and of Consultant (for servicing operating stations). Long-term plant developments are pursued until they can be securely incorporated into station proposals. Planning Inquiries for new stations are supported technically until the proposed station is approved and the proposal becomes a project which is managed to be completed on programme and within budget to the required standards. Once complete and commissioned, the station is handed over to the operators and the designers and constructors take on their role of Independent Assessors of proposed design changes. At the end of its life, the decommissioning of the station becomes another project requiring effective management. Nuclear power requires servicing from conception to decommissioning. 1 fig

  12. Methodologies for and Results of Planning later Decommissioning of Nuclear Facilities

    International Nuclear Information System (INIS)

    Auler, I.; Paul, R.; Petrasch, P.

    1996-01-01

    Cost and success of decommissioning and dismantling nuclear power plants or other nuclear facilities are very much related to the chosen strategy and their implementation in practice. The strategy to be developed depends on the specific boundary conditions in a certain country and plant. Inadequate planning and equipment considered too late cause delays in the project performance and improvisations with financial and radiological consequences. For the development of a decommissioning strategy for a nuclear power plant broad experience from past D and D-projects is very important. That experience is very helpful in assessing the importance of the many factors which determine the success or failure of strategic decisions Tools for the systematic recording and investigation of the needed measures and expenditures are available, eg. the decommissioning cost program STILLKO-2, which has been established as standard tool. (author)

  13. 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

  14. Nuclear decommissioning: A problem that won't go away

    International Nuclear Information System (INIS)

    Lenssen, N.

    1999-01-01

    The problem of shutdown reactors is growing steadily. As of the beginning of 1999, 94 reactors have been shutdown, only 429 were in operation, meaning that one out of 5.5 reactors ever built was permanently closed. Yet only a handful of these have actually been dismantled. Some countries as Japan and USA, have announced their policies that hey plan to dismantle their reactors in a decade or two after closure. Other countries like Canada or France intend to wait several decades. At the extreme United Kingdom decided to wait more than 100 years. This old shutdown reactors could become a near permanent fixture in some countries. The problem is that, the longer the reactors run, the more radioactive their interiors become, the more difficult, dangerous and expensive is to dismantle the plants, to store and bury the residual radioactive waste. Despite some early real experience with the cost of decommissioning plants, it still remains uncertain just what those costs will be and who will pay. Estimates of the dismantling cost have ranged from 10% of the initial capital investment up to 40% and even 100%. Thus, decommissioning could become the largest remaining expense facing the nuclear industry and the governments who have supported it, particularly if efforts to confine radioactive waste fail. The challenge facing the human societies is to keep nuclear waste including the shuttered plants in isolation for the many millennia that make up the hazardous life of these materials. In this light, no matter what becomes of nuclear power, the nuclear age will continue for a very long time

  15. Decontamination and decommissioning of nuclear facilities: a literature search

    International Nuclear Information System (INIS)

    Sande, W.E.; Freeman, H.D.; Hanson, M.S.; McKeever, R.

    1975-05-01

    is bibliography includes 429 unclassified references to the decontamination and decommissioning of nuclear facilities. The references are arranged in chronological order and cover the period from 1944 through 1974. Subject and author indexes are e provided. (U.S.)

  16. Decommissioning of Swedish nuclear power reactors. Technology and costs

    International Nuclear Information System (INIS)

    1994-06-01

    The main topics discussed are planning, technology and costs of decommissioning nuclear power reactors. Oskarshamn-3 (BWR) and Ringhals-4 (PWR) have been used as reference reactors. 29 refs, figs, tabs

  17. Addressing Uncertainties in Cost Estimates for Decommissioning Nuclear Facilities

    International Nuclear Information System (INIS)

    Benjamin, Serge; Descures, Sylvain; Du Pasquier, Louis; Francois, Patrice; Buonarotti, Stefano; Mariotti, Giovanni; Tarakonov, Jurij; Daniska, Vladimir; Bergh, Niklas; Carroll, Simon; AaSTRoeM, Annika; Cato, Anna; De La Gardie, Fredrik; Haenggi, Hannes; Rodriguez, Jose; Laird, Alastair; Ridpath, Andy; La Guardia, Thomas; O'Sullivan, Patrick; ); Weber, Inge; )

    2017-01-01

    The cost estimation process of decommissioning nuclear facilities has continued to evolve in recent years, with a general trend towards demonstrating greater levels of detail in the estimate and more explicit consideration of uncertainties, the latter of which may have an impact on decommissioning project costs. The 2012 report on the International Structure for Decommissioning Costing (ISDC) of Nuclear Installations, a joint recommendation by the Nuclear Energy Agency (NEA), the International Atomic Energy Agency (IAEA) and the European Commission, proposes a standardised structure of cost items for decommissioning projects that can be used either directly for the production of cost estimates or for mapping of cost items for benchmarking purposes. The ISDC, however, provides only limited guidance on the treatment of uncertainty when preparing cost estimates. Addressing Uncertainties in Cost Estimates for Decommissioning Nuclear Facilities, prepared jointly by the NEA and IAEA, is intended to complement the ISDC, assisting cost estimators and reviewers in systematically addressing uncertainties in decommissioning cost estimates. Based on experiences gained in participating countries and projects, the report describes how uncertainty and risks can be analysed and incorporated in decommissioning cost estimates, while presenting the outcomes in a transparent manner

  18. Decommissioning considerations at a time of nuclear renaissance

    International Nuclear Information System (INIS)

    Devgun, Jas S.

    2007-01-01

    At a time of renaissance in the nuclear power industry, when it is estimated that anywhere between 60 to 130 new power reactors may be built worldwide over the next 15 years, why should we focus on decommissioning? Yet it is precisely the time to examine what decommissioning considerations should be taken into account as the industry proceeds with developing final designs for new reactors and the construction on the new build begins. One of the lessons learned from decommissioning of existing reactors has been that decommissioning was not given much thought when these reactors were designed three or four decades ago. Even though decommissioning may be sixty years down the road from the time they go on line, eventually all reactors will be decommissioned. It is only prudent that new designs be optimized for eventual decommissioning, along with the other major considerations. The overall objective in this regard is that when the time comes for decommissioning, it can be completed in shorter time frames, with minimum generation of radioactive waste, and with better radiological safety. This will ensure that the tail end costs of the power reactors are manageable and that the public confidence in the nuclear power is sustained through the renaissance and beyond. (author)

  19. R and D and Innovation Needs for Decommissioning Nuclear Facilities

    International Nuclear Information System (INIS)

    Farr, Harvey; LaGuardia, Thomas S.

    2014-01-01

    Nuclear decommissioning activities can greatly benefit from research and development (R and D) projects. This report examines applicable emergent technologies, current research efforts and innovation needs to build a base of knowledge regarding the status of decommissioning technology and R and D. This base knowledge can be used to obtain consensus on future R and D that is worth funding. It can also assist in deciding how to collaborate and optimise the limited pool of financial resources available among NEA member countries for nuclear decommissioning R and D. (authors)

  20. Relative evaluation on decommissioning accident scenarios of nuclear facilities

    International Nuclear Information System (INIS)

    Jeong, Kwan-Seong; Choi, Byung-Seon; Moon, Jei-Kwon; Hyun, Dong-Jun; Kim, Geun-Ho; Kim, Tae-Hyoung; Jo, Kyung-Hwa; Seo, Jae-Seok; Jeong, Seong-Young; Lee, Jung-Jun

    2012-01-01

    Highlights: ► This paper suggests relative importance on accident scenarios during decommissioning of nuclear facilities. ► The importance of scenarios can be performed by using AHP and Sugeno fuzzy method. ► The AHP and Sugeno fuzzy method guarantee reliability of the importance evaluation. -- Abstract: This paper suggests the evaluation method of relative importance on accident scenarios during decommissioning of nuclear facilities. The evaluation method consists of AHP method and Sugeno fuzzy integral method. This method will guarantee the reliability of relative importance evaluation for decommissioning accident scenarios.

  1. Docommissioning of nuclear power plants

    International Nuclear Information System (INIS)

    Essmann, J.

    1981-01-01

    The German utilities operating nuclear power plants have long concerned themselves with aspects of decommissioning and for this purpose an engineering company was given a contract to study the entire spectrum of decommissioning. The results of this study have been available in autumn 1980 and it is possible to discuss all the aspects of decommissioning on a new basis. Following these results no change in the design concept of LWR nuclear power plants in operation or under construction is necessary because the techniques, necessary for decommissioning, are fully available today. The technical feasibility of decommissioning for power plants of Biblis A and KRB type has been shown in detail. The calculations of the quantity of waste produced during removal of a nuclear power plant could be confirmed and it could be determined with high procedure. The radiation dose to the decommissioning personnel is in the range of the radiation protection regulations and is in the same range as the radiation dose to the personnel within a yearly inservice inspection. (AF)

  2. Validity evaluation of internal exposure in nuclear facility decommission

    International Nuclear Information System (INIS)

    Wang Xiaoli; Chen Dahua; You Zeyun

    2012-01-01

    During nuclear facility decommission under construction, it is very important for workers to wear respirator to avoid harm of Am aerosols. So the protection effect of respirator is very important. The protection effect of respirator was calculated and evaluated according to the data achieved from engineering practice. The result shows that the protection effect is better than target management value and the respirator is effective to protect workers from harm of Am aerosols. The respirator is applied to other nuclear facility decommission. (authors)

  3. Calculating the Unit Cost Factors for Decommissioning Cost Estimation of the Nuclear Research Reactor

    International Nuclear Information System (INIS)

    Jeong, Kwan Seong; Lee, Dong Gyu; Jung, Chong Hun; Lee, Kune Woo

    2006-01-01

    The estimated decommissioning cost of nuclear research reactor is calculated by applying a unit cost factor-based engineering cost calculation method on which classification of decommissioning works fitted with the features and specifications of decommissioning objects and establishment of composition factors are based. Decommissioning cost of nuclear research reactor is composed of labor cost, equipment and materials cost. Labor cost of decommissioning costs in decommissioning works are calculated on the basis of working time consumed in decommissioning objects. In this paper, the unit cost factors and work difficulty factors which are needed to calculate the labor cost in estimating decommissioning cost of nuclear research reactor are derived and figured out.

  4. Technology, safety, and costs of decommissioning reference nuclear research and test reactors: sensitivity of decommissioning radiation exposure and costs to selected parameters

    International Nuclear Information System (INIS)

    Konzek, G.J.

    1983-07-01

    Additional analyses of decommissioning at the reference research and test (R and T) reactors and analyses of five recent reactor decommissionings are made that examine some parameters not covered in the initial study report (NUREG/CR-1756). The parameters examined for decommissioning are: (1) the effect on costs and radiation exposure of plant size and/or type; (2) the effects on costs of increasing disposal charges and of unavailability of waste disposal capacity at licensed waste disposal facilities; and (3) the costs of and the available alternatives for the disposal of nuclear R and T reactor fuel assemblies

  5. Decommissioning of nuclear power stations in community countries carried out and projected

    International Nuclear Information System (INIS)

    Cregut, A.; Gregory, A.R.

    1984-01-01

    The decommissioning of large plants such as nuclear power stations merits an approach requiring the introduction of measures and procedures allowing them to be dealt with efficiently; this efficiency would imply concern for optimum economy of operations while respecting the safety and protection rules inherent in nuclear energy. Consequently, plant owners require: the tactical and policy elements to guide them in their decisions and choices; efficient tools, equipment and processes which meet their needs; information gained from experience of decommissioning already carried out which would provide them with a verified background knowledge when dealing with problems. Since decommissioning experience to date has not made it possible to draw up codes and guidelines, it is important to review the work carried out by Community countries in particular on the decommissioning of nuclear power plants. The following paper does not claim to be exhaustive or to make value judgements. Its aim is to list the nuclear power stations shut down in Community countries, to outline the decommissioning levels selected in each case and to underline some interesting aspects of the technical options. In conclusion it will review what appeared to be the difficulties common to the various projects. (author)

  6. Technology, safety and costs of decommissioning a reference boiling water reactor power station: Comparison of two decommissioning cost estimates developed for the same commercial nuclear reactor power station

    International Nuclear Information System (INIS)

    Konzek, G.J.; Smith, R.I.

    1990-12-01

    This study presents the results of a comparison of a previous decommissioning cost study by Pacific Northwest Laboratory (PNL) and a recent decommissioning cost study of TLG Engineering, Inc., for the same commercial nuclear power reactor station. The purpose of this comparative analysis on the same plant is to determine the reasons why subsequent estimates for similar plants by others were significantly higher in cost and external occupational radiation exposure (ORE) than the PNL study. The primary purpose of the original study by PNL (NUREG/CR-0672) was to provide information on the available technology, the safety considerations, and the probable costs and ORE for the decommissioning of a large boiling water reactor (BWR) power station at the end of its operating life. This information was intended for use as background data and bases in the modification of existing regulations and in the development of new regulations pertaining to decommissioning activities. It was also intended for use by utilities in planning for the decommissioning of their nuclear power stations. The TLG study, initiated in 1987 and completed in 1989, was for the same plant, Washington Public Supply System's Unit 2 (WNP-2), that PNL used as its reference plant in its 1980 decommissioning study. Areas of agreement and disagreement are identified, and reasons for the areas of disagreement are discussed. 31 refs., 3 figs., 22 tabs

  7. Comparing nuclear decommissioning in the UK and France

    International Nuclear Information System (INIS)

    Walls, J.; Garcier, R.

    2008-01-01

    In this paper we will compare the decommissioning policies in the UK and France. Both countries have a long nuclear history and decommissioning has taken place since the 1960. However, the proposed decommissioning of Magnox and AGR sites in the UK and of UNGG sites in France brings decommissioning efforts to a new level. Whilst we explore in detail the approaches and methodologies adopted in each country we remain sensitive to the effects that political and economic history play in shaping the policy response. In this paper we draw upon interviews conducted with a range of key stakeholders including: national regulators, companies involved in decommissioning, local politicians and community representatives. We also analyse key academic and non academic literature. (authors)

  8. Regulations and financing for decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Kumakura, Osamu

    1981-01-01

    The purpose of this report is to survey the French legislation concerning the decommissioning of nuclear facilities and the method of financing for it. There is no clause in French regulations, which states any specific criterion or licensing procedure for the proper decommissioning. The legal problems in this domain are treated within the general regulation system on atomic energy. The decommissioning of nuclear facilities is carried out in accordance with the licensing procedure for constructing nuclear facilities or the permission procedure for operating them, according to the ''Decree on nuclear installations, 1963''. The works for the final shut-down and decommissioning are regarded as the modification to the safety report or the general operation instructions, and new permit is required. In the case that the radioactivity of substances after decommissioning is above the criteria of the Decree, 1963, the new license is required. In the case of below the criteria, the facilities are governed by the ''Act on installations classified for environmental protection, 1976''. The ''Decree on general radiation protection, 1966'', the ''Decree on radiation protection of workers in nuclear installations, 1975'', the ''Ministerial order on transport of dangerous materials, 1945'', and two ministerial orders on radioactive effluent discharge, 1974, are applied to the decommissioning works. (Kako, I.)

  9. On Younger Stakeholders and Decommissioning of Nuclear Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Tyszkiewicz, Bogumila; Labor, Bea

    2009-08-15

    based on a proper understanding of the values and value functions of younger citizens. Such information must thus be an integral part of the knowledge base to be used when plans and processes are being developed for dismantling and decommissioning of nuclear power plants and other older nuclear facilities. In the present project, empirical data have been collected and compiled in a survey of the values of younger citizens with regard to decommissioning and dismantling of older nuclear facilities. The survey constitutes a stratified sample from three towns in Poland. They are Lublin, Olsztyn and Gdansk. A total of 780 students in the age group 14-19 years participated in the Survey. The results are compared to those from a similar study in the County of Kalmar in Sweden in the year 2006. The results include some major lesson learned. These may be summarised as follows: - Younger citizens tend to base their values regarding decommissioning on safety, and environmental aspects. Aspects like future economic growth and technological processes are less influential on the values. - Younger citizens tend to express a lack of information and debate as a basis of their value functions. Likewise, they tend to express interest in the topic and are open to become more included in the processes. - Younger citizens have suggestions on how more information can be made accessible to the general public. - Younger citizens need to be better included in the stakeholder process. This can be achieved by allowances from the Swedish Nuclear Waste Fund to support groups of younger citizens to follow the Swedish process of research, development and demonstration of a concept for the management of spent nuclear fuel. Less than fully accessible information campaigns about nuclear power and associated nuclear waste may result in differences in confidence levels between different groups of stakeholders. By finding out more about the values of different stakeholders it will be possible for the

  10. On Younger Stakeholders and Decommissioning of Nuclear Facilities

    International Nuclear Information System (INIS)

    Tyszkiewicz, Bogumila; Labor, Bea

    2009-08-01

    based on a proper understanding of the values and value functions of younger citizens. Such information must thus be an integral part of the knowledge base to be used when plans and processes are being developed for dismantling and decommissioning of nuclear power plants and other older nuclear facilities. In the present project, empirical data have been collected and compiled in a survey of the values of younger citizens with regard to decommissioning and dismantling of older nuclear facilities. The survey constitutes a stratified sample from three towns in Poland. They are Lublin, Olsztyn and Gdansk. A total of 780 students in the age group 14-19 years participated in the Survey. The results are compared to those from a similar study in the County of Kalmar in Sweden in the year 2006. The results include some major lesson learned. These may be summarised as follows: - Younger citizens tend to base their values regarding decommissioning on safety, and environmental aspects. Aspects like future economic growth and technological processes are less influential on the values. - Younger citizens tend to express a lack of information and debate as a basis of their value functions. Likewise, they tend to express interest in the topic and are open to become more included in the processes. - Younger citizens have suggestions on how more information can be made accessible to the general public. - Younger citizens need to be better included in the stakeholder process. This can be achieved by allowances from the Swedish Nuclear Waste Fund to support groups of younger citizens to follow the Swedish process of research, development and demonstration of a concept for the management of spent nuclear fuel. Less than fully accessible information campaigns about nuclear power and associated nuclear waste may result in differences in confidence levels between different groups of stakeholders. By finding out more about the values of different stakeholders it will be possible for the

  11. EDF decommissioning programme: A global commitment to safety, environment and cost efficiency of nuclear energy

    International Nuclear Information System (INIS)

    Chatry, Jean-Paul

    2002-01-01

    Nowadays, decommissioning of nuclear power plants has become a key issue for nuclear industry in Europe. The phasing out of nuclear energy in Germany, Belgium and Sweden, as well as the early closure of nuclear units in applicant countries in the frame of EU enlargement, has largely contributed to consider decommissioning as the next challenge to face. The situation is slightly different in France: nuclear energy is still considered as a safe, cost-effective and environment friendly energy source and EDF is still working on the development of a new generation of reactor to replace the existing one. Nevertheless, to achieve this objective, it will be necessary to get the support of political decision-makers and the acceptance of public opinion. The increasing mobilisation of EDF for the decommissioning of its already shutdown NPPs shows its willingness to demonstrate its capacity to control the nuclear life cycle from end to end. The successful implementation of its decommissioning programme will not mean the end of nuclear energy as an efficient way to generate electricity but it will constitute a prerequisite for the erection of new nuclear power plants in France

  12. Establishment of the nuclear regulatory framework for the process of decommissioning of nuclear installations in Mexico

    International Nuclear Information System (INIS)

    Salmeron V, J. A.; Camargo C, R.; Nunez C, A.

    2015-09-01

    Today has not managed any process of decommissioning of nuclear installations in the country; however because of the importance of the subject and the actions to be taken to long term, the Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS) in Mexico, accordance with its objectives is developing a National Nuclear Regulatory Framework and defined requirements to ensure the implementation of appropriate safety standards when such activities are performed. In this regard, the national nuclear regulatory framework for nuclear installations and the particular case of nuclear power reactors is presented, as well as a proposed licensing process for the nuclear power plant of Laguna Verde based on international regulations and origin country regulations of the existing reactors in nuclear facilities in accordance with the license conditions of operation to allow to define and incorporate such regulation. (Author)

  13. Decommissioning Operations at the Cadarache Nuclear Research Center

    International Nuclear Information System (INIS)

    Gouhier, E.

    2008-01-01

    Among the different activities of the CEA research center of Cadarache, located in the south of France, one of the most important involves decommissioning. As old facilities close, decommissioning activity increases. This presentation will give an overview of the existing organization and the different ongoing decommissioning and cleanup operations on the site. We shall also present some of the new facilities under construction the purpose of which is to replace the decommissioned ones. Cadarache research center was created on October 14, 1959. Today, the activities of the research center are shared out among several technological R and D platforms, essentially devoted to nuclear energy (fission and fusion) Acting as a support to these R and D activities, the center of Cadarache has a platform of services which groups the auxiliary services required by the nuclear facilities and those necessary to the management of nuclear materials, waste, nuclear facility releases and decommissioning. Many old facilities have shut down in recent years (replaced by new facilities) and a whole decommissioning program is now underway involving the dismantling of nuclear reactors (Rapsodie, Harmonie), processing facilities (ATUE uranium treatment facility, LECA UO 2 facility) as well as waste treatment and storage facilities (INB37, INB 56. In conclusion: other dismantling and cleanup operations that are now underway in Cadarache include the following: - Waste treatment and storage facilities, - Historical VLLW and HLW storage facility, - Fissile material storage building, - Historical spent fuel storage facility. Thanks to the project organization: - Costs and risks on these projects can be reduced. - Engineers and technicians can easily move from one project to another. In some cases, when a new facility is under construction for the purpose of replacing a decommissioned one, some of the project team can integrate the new facility as members of the operation team. Today

  14. Radiological planning and implementation for nuclear-facility decommissioning

    International Nuclear Information System (INIS)

    Valentine, A.M.

    1982-01-01

    The need and scope of radiological planning required to support nuclear facility decommissioning are issues addressed in this paper. The role of radiation protection engineering and monitoring professionals during project implementation and closeout is also addressed. Most of the discussion focuses on worker protection considerations; however, project support, environmental protection and site release certification considerations are also covered. One objective is to identify radiological safety issues that must be addressed. The importance of the issues will vary depending on the type of facility being decommissioned; however, by giving appropriate attention to these issues difficult decommissioning projects can be accomplished in a safer manner with workers and the public receiving minimal radiation exposures

  15. Standard Guide for Preparing Characterization Plans for Decommissioning Nuclear Facilities

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2009-01-01

    1.1 This standard guide applies to developing nuclear facility characterization plans to define the type, magnitude, location, and extent of radiological and chemical contamination within the facility to allow decommissioning planning. This guide amplifies guidance regarding facility characterization indicated in ASTM Standard E 1281 on Nuclear Facility Decommissioning Plans. This guide does not address the methodology necessary to release a facility or site for unconditional use. This guide specifically addresses: 1.1.1 the data quality objective for characterization as an initial step in decommissioning planning. 1.1.2 sampling methods, 1.1.3 the logic involved (statistical design) to ensure adequate characterization for decommissioning purposes; and 1.1.4 essential documentation of the characterization information. 1.2 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate saf...

  16. The assessment system based on virtual decommissioning environments to reduce abnormal hazards from human errors for decommissioning of nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, Kwan Seong; Moon, Jei Kwon; Choi, Byung Seon; Hyun, Dong jun; Lee, Jong Hwan; Kim, Ik June; Kang, Shin Young [KAERI, Daejeon (Korea, Republic of)

    2016-05-15

    Decommissioning of nuclear facilities has to be accomplished by assuring the safety of workers. So, it is necessary that before decommissioning, the exposure dose to workers has to be analyzed and assessed under the principle of ALARA (as low as reasonably achievable). Furthermore, to improve the proficiency of decommissioning environments, method and system need to be developed. To establish the plan of exposure dose to workers during decommissioning of nuclear facilities before decommissioning activities, it is necessary that assessment system is developed. This system has been successfully developed so that exposure dose to workers could be real-time measured and assessed in virtual decommissioning environments. It can be concluded that this system could be protected from accidents and enable workers to improve his familiarization about working environments. It is expected that this system can reduce human errors because workers are able to improve the proficiency of hazardous working environments due to virtual training like real decommissioning situations.

  17. Expertise on the project for the decommissioning of the pilot incineration plant at the Paul Scherrer Institute

    International Nuclear Information System (INIS)

    2012-12-01

    This expertise report published by the Swiss Federal Nuclear Safety Inspectorate ENSI takes a look at the proposed decommissioning of the pilot incineration plant at the Paul Scherrer Institute PSI in Switzerland. Details concerning the operator PSI, the installation, the documentation and criteria used in the expertise are presented. Experience in the decommissioning of nuclear installations is reviewed. Decommissioning variants and the concept proposed are described and details concerning radiation sources and problematical materials such as asbestos are reviewed. The views of the Swiss Federal Nuclear Safety Inspectorate ENSI are presented and proposals for the disposal of radioactive wastes are examined. Finally, the costs incurred are reviewed

  18. Establishment and Evaluation of Decommissioning Plant Inventory DB and Waste Quantity

    International Nuclear Information System (INIS)

    Oh, Jae Yong; Moon, Sang-Rae; Yun, Taesik; Kim, Hee-Geun; Sung, Nak-Hoon; Jung, Seung Hyuk

    2016-01-01

    Korea Hydro and Nuclear Power (KHNP) made a decision for permanent shutdown of Kori-1 and has progressed the strategy determination and R and D for the decommissioning of Kori-1. Decommissioning waste, Structure, System and Components (SSCs) is one of the most important elements. Decommissioning waste quantity is calculated based on Plant Inventory Database (PI DB) with activation and contamination data. Due to the largest portion of waste management and disposal in decommissioning, it is necessary to exactly evaluate waste quantity (applying the regulation, guideline and site-specific characterization) for economic feasibility. In this paper, construction of PI DB and evaluation of waste quantity for Optimized Pressurized Reactor (OPR-1000) are mainly described. Decommissioning waste quantities evaluated are going to be applied to calculation of the project cost. In fact, Ministry of Trade, Industry and Energy (MOTIE) in Korea expected the decommissioning waste quantity in a range of 14,500-18,850 drums, and predicted appropriate liability for decommissioning fund by using waste quantity. The result of this study is also computed by the range of 14,500-18,850 drums. Since there is no site-specific data for the NPP site, this evaluation is the preliminary analysis

  19. Establishment and Evaluation of Decommissioning Plant Inventory DB and Waste Quantity

    Energy Technology Data Exchange (ETDEWEB)

    Oh, Jae Yong; Moon, Sang-Rae; Yun, Taesik; Kim, Hee-Geun [KHNP CRI, Daejeon (Korea, Republic of); Sung, Nak-Hoon; Jung, Seung Hyuk [KONES Corp., Seoul (Korea, Republic of)

    2016-10-15

    Korea Hydro and Nuclear Power (KHNP) made a decision for permanent shutdown of Kori-1 and has progressed the strategy determination and R and D for the decommissioning of Kori-1. Decommissioning waste, Structure, System and Components (SSCs) is one of the most important elements. Decommissioning waste quantity is calculated based on Plant Inventory Database (PI DB) with activation and contamination data. Due to the largest portion of waste management and disposal in decommissioning, it is necessary to exactly evaluate waste quantity (applying the regulation, guideline and site-specific characterization) for economic feasibility. In this paper, construction of PI DB and evaluation of waste quantity for Optimized Pressurized Reactor (OPR-1000) are mainly described. Decommissioning waste quantities evaluated are going to be applied to calculation of the project cost. In fact, Ministry of Trade, Industry and Energy (MOTIE) in Korea expected the decommissioning waste quantity in a range of 14,500-18,850 drums, and predicted appropriate liability for decommissioning fund by using waste quantity. The result of this study is also computed by the range of 14,500-18,850 drums. Since there is no site-specific data for the NPP site, this evaluation is the preliminary analysis.

  20. Approach to long- term regalement of nuclear energy installation decommissioning

    International Nuclear Information System (INIS)

    Dryapachenko, Yi.P.; Rudenko, B. A.; Ozimaj, M.S.

    2001-01-01

    In this report we make an accent on because the rules of nuclear installation decommissioning should provide controllability with compounded operations not one generations of the performers. The strategy should take into account problems of the economic completion, environment and standards of health, script of decommissioning and its execution, and so on. These strategies are bound with the social conditions, with accent on work with the low level wastes

  1. In Situ Decommissioning (ISD) Concepts and Approaches for Excess Nuclear Facilities Decommissioning End State - 13367

    International Nuclear Information System (INIS)

    Serrato, Michael G.; Musall, John C.; Bergren, Christopher L.

    2013-01-01

    The United States Department of Energy (DOE) currently has numerous radiologically contaminated excess nuclear facilities waiting decommissioning throughout the Complex. The traditional decommissioning end state is complete removal. This commonly involves demolishing the facility, often segregating various components and building materials and disposing of the highly contaminated, massive structures containing tons of highly contaminated equipment and piping in a (controlled and approved) landfill, at times hundreds of miles from the facility location. Traditional demolition is costly, and results in significant risks to workers, as well as risks and costs associated with transporting the materials to a disposal site. In situ decommissioning (ISD or entombment) is a viable alternative to demolition, offering comparable and potentially more protective protection of human health and the environment, but at a significantly reduced cost and worker risk. The Savannah River Site (SRS) has completed the initial ISD deployment for radiologically contaminated facilities. Two reactor (P and R Reactors) facilities were decommissioned in 2011 using the ISD approach through the American Recovery and Reinvestment Act. The SRS ISD approach resolved programmatic, regulatory and technical/engineering issues associated with avoiding the potential hazards and cost associated with generating and disposing of an estimated 124,300 metric tons (153,000 m 3 ) of contaminated debris per reactor. The DOE Environmental Management Office of Deactivation and Decommissioning and Facility Engineering, through the Savannah River National Laboratory, is currently investigating potential monitoring techniques and strategies to assess ISD effectiveness. As part of SRS's strategic planning, the site is seeking to leverage in situ decommissioning concepts, approaches and facilities to conduct research, design end states, and assist in regulatory interactions in broad national and international

  2. In Situ Decommissioning (ISD) Concepts and Approaches for Excess Nuclear Facilities Decommissioning End State - 13367

    Energy Technology Data Exchange (ETDEWEB)

    Serrato, Michael G. [Savannah River National Laboratory, Savannah River Nuclear Solutions, Aiken, SC 29808 (United States); Musall, John C.; Bergren, Christopher L. [Savannah River Nuclear Solutions, Aiken, SC 29808 (United States)

    2013-07-01

    The United States Department of Energy (DOE) currently has numerous radiologically contaminated excess nuclear facilities waiting decommissioning throughout the Complex. The traditional decommissioning end state is complete removal. This commonly involves demolishing the facility, often segregating various components and building materials and disposing of the highly contaminated, massive structures containing tons of highly contaminated equipment and piping in a (controlled and approved) landfill, at times hundreds of miles from the facility location. Traditional demolition is costly, and results in significant risks to workers, as well as risks and costs associated with transporting the materials to a disposal site. In situ decommissioning (ISD or entombment) is a viable alternative to demolition, offering comparable and potentially more protective protection of human health and the environment, but at a significantly reduced cost and worker risk. The Savannah River Site (SRS) has completed the initial ISD deployment for radiologically contaminated facilities. Two reactor (P and R Reactors) facilities were decommissioned in 2011 using the ISD approach through the American Recovery and Reinvestment Act. The SRS ISD approach resolved programmatic, regulatory and technical/engineering issues associated with avoiding the potential hazards and cost associated with generating and disposing of an estimated 124,300 metric tons (153,000 m{sup 3}) of contaminated debris per reactor. The DOE Environmental Management Office of Deactivation and Decommissioning and Facility Engineering, through the Savannah River National Laboratory, is currently investigating potential monitoring techniques and strategies to assess ISD effectiveness. As part of SRS's strategic planning, the site is seeking to leverage in situ decommissioning concepts, approaches and facilities to conduct research, design end states, and assist in regulatory interactions in broad national and

  3. Eurochemic reprocessing plant decommissioning. Decontamination of contaminated metal

    International Nuclear Information System (INIS)

    Walthery, R.; Teunckens, L.; Lewandowski, P.

    1998-01-01

    When decommissioning nuclear installations, large quantifies of metal components are produced as well as significant amounts of other radioactive materials, which mostly show low surface contamination. Having been used or having been brought for a while in a controlled area, marks them as 'suspected material'. In view of the very high costs for radioactive waste processing and disposal, alternatives have been considered, and much effort has been spent in recycling through decontamination, melting and unconditional release of metals. In a broader context, recycling of materials can be considered as a first order ecological priority to limit the quantities of radioactive wastes to be disposed of, to reduce the technical and economic problems involved with the management of radioactive wastes, and to make economic use of primary material and conserve natural resources of basic material for future generations. Other evaluations as the environmental impact of recycling compared to non recycling (mining or production of new material) and waste treatment, with the associated risks involved, can also be considered, as well as social and political impacts of recycling. This document gives an overview of the current practices in recycling of materials at the decommissioning of the Eurochemic reprocessing plant in Dessel, Belgium. It deals with the decontamination and measurement techniques in use, and considers related technical and economic aspects and constraints. (author)

  4. Record keeping for the decommissioning of nuclear facilities: Guidelines and experience

    International Nuclear Information System (INIS)

    2002-01-01

    This report covers record keeping for the decommissioning of nuclear facilities. Nuclear facilities include large commercial facilities such as nuclear power plants or chemical nuclear facilities (e.g. for fabrication and reprocessing), but also include smaller facilities such as research reactors and medical, industrial and other research facilities. Special attention may be needed for these small facilities owing to factors such as the low priority given to decommissioning by research teams and the possibility of poorly recorded structural and operational changes. A focus on research reactors is also important because of their widespread distribution. Two IAEA TECDOCs address record keeping for radioactive waste management and disposal facilities, and therefore these areas are not covered in this report. The objective of this report is to provide information, experience and assistance on how to identify, update as needed and maintain records to assist in the decommissioning of nuclear facilities, including for the decommissioning plan. This report is intended to be useful to policy makers, regulators, owners, operators, decommissioning contractors and other interested parties. Record keeping is an integral part of overall QA or quality management programmes, and this is emphasized in this report. This report also indicates the possible consequences of not maintaining adequate records. This report describes the needs and the sources of the records for decommissioning (Section 3) and the process of identifying and selecting these records (Section 4). Section 5 considers the records from the decommissioning process itself and their retention, while Section 6 deals with QA, organization and responsibilities. The Records Management System (RMS) is dealt with in Section 7 and the management of new records in Section 8. A summary of observations is included in Section 9. The report is complemented by an appendix and annexes that describe case histories

  5. Implementation of requirements of environmental management (ISO 14000) for the decommissioning of the heavy water plant

    International Nuclear Information System (INIS)

    Gonzalez, Maria I.; Otero de Eppenstein, Marta; Tosi, Lidia E.; Sabio, Manuel

    2000-01-01

    The National Atomic Energy Commission (CNEA) of Argentina has a project of decommissioning in the heavy water plant (Planta Experimental de Agua Pesada - PEAP). The aim of this project is to get some experience for decommissioning of nuclear plants and to achieve knowledge about the application of the requirements in environmental management. The project is being carried out according to ISO 14001 standards 'Environmental Management Systems'. The objectives were taken from the model without any expectation of achieving the complete implementation or certification of the system. This report is a description of the acts that have been done. (author)

  6. Decommissioning of nuclear facilities involving operations with uranium and thorium

    International Nuclear Information System (INIS)

    Shum, E.Y.; Neuder, S.M.

    1990-01-01

    When a licensed nuclear facility ceases operation, the U.S. Nuclear Regulatory Commission (NRC) ensures that the facility and its site are decontaminated to acceptable levels so they may safely be released for unrestricted public use. Because specific environmental standards or broad federal guidelines governing release of residual radioactive contamination have not been issued, NRC has developed ad hoc cleanup criteria for decommissioning nuclear facilities that involved uranium and thorium. Cleanup criteria include decontamination of buildings, equipment, and land. We will address cleanup criteria and their rationale; procedures for decommissioning uranium/thorium facilities; radiological survey designs and procedures; radiological monitoring and measurement; and cost-effectiveness to demonstrate compliance

  7. European Learning Initiatives for Nuclear Decommissioning and Environmental Remediation

    International Nuclear Information System (INIS)

    Abousahl, Said; )

    2017-01-01

    Situation nuclear decommissioning in the EU: - Demonstration of decommissioning at an industrial scale, as a 'last but feasible step' of the nuclear life-cycle, is essential for the credibility of the nuclear energy option; - Decommissioning market is in expansion, particularly in Europe; - Currently, an industrial experience exist, however... further attention is necessary for: - Development of the most suitable techniques, with respect to safety, efficiency and waste limitation; - Standardisation and harmonisation (incl. cost estimation); - Offering and promoting dedicated education and training opportunities; - Sharing knowledge and experiences. Offering and promoting dedicated Education and Training (E&T) opportunities: JRC organised jointly with the University of Birmingham in April 2015 a seminar on Education and Training in Nuclear Decommissioning, in an attempt to answer to the questions: •What are the E&T needs ? •What are the opportunities, what does already exist ? •How can we attract young talent ? Outcome of the seminar is published in a joint report with orientations on the way forward to support Education and Training in Nuclear Decommissioning in the EU

  8. Incorporating design for decommissioning into the layout of nuclear facilities

    International Nuclear Information System (INIS)

    Collum, B.; Druart, A.

    2008-01-01

    Design for Decommissioning (DfD) is the design of nuclear facilities in a manner that facilitates ultimate decommissioning in as safe, technically efficient and cost effective way as possible. Strictly speaking, (DfD) should need minimal introduction and this paper should ideally be aimed at discussing the finer points of some improvement to a practice that is already widely embedded throughout the nuclear industry. The reality though is quite different. As an industry, we all know what DfD is and indeed we do incorporate it into our designs. However, application is at best patchy and there is little evidence of applying it to the level that will be advocated here. When applied at its highest level, DfD is all about truly designing nuclear facilities with their whole life cycle in mind, such that the decommissioning phase is an integral part of the design of a facility from the very first day. In this way, when a facility comes to the end of its operational life, it can move smoothly to Post Operational Clean Out (POCO) and then through the various phases of decommissioning. Demonstrating from the start that the nuclear industry addresses the challenges posed by decommissioning will help it to gain support from the regulators and the general public for proposals to build new nuclear generating capacity. (author)

  9. Decommissioning of NPPs with spent nuclear fuel present - efforts to amend the German regulatory framework to cope with this situation

    International Nuclear Information System (INIS)

    Brendebach, Boris; Rehs, Bernd

    2016-01-01

    The authorization to operate an installation for the fission of nuclear fuel for the commercial production of electricity was withdrawn for the seven oldest NPPs and NPP Kruemmel in Germany on August 6, 2011 after the events at Japanese Nuclear Power Plant (NPP) Fukushima Daiichi in March 2011. In the meantime, all these NPPs applied for decommissioning. One aspect reflected in the applications for these NPPs is the possibility that spent nuclear fuel elements or fuel rods will still be present in the cooling ponds at least during the first stage of decommissioning, i.a. due to limited availability of spent fuel casks. Although considerable decommissioning experiences are available in Germany, the approach 'decommissioning with fuel elements present' has been the exceptional case so far. The paper highlights the efforts undertaken to strengthen the regulatory framework with respect to decommissioning in Germany taking into account this changed approach. The paper presents a short introduction to the legal and regulatory requirements for decommissioning in Germany. Afterwards, the updates to the Decommissioning Guide, which includes proposals for an appropriate procedure for the decommissioning, safe enclosure and dismantling of facilities or parts thereof as defined in item 7 of the German Atomic Energy Act in respect of the application of the technical rules for planning and preparation of decommissioning measures as well as for licensing and supervision, are highlighted. In addition, the amendments to the Guidelines for the Decommissioning of Nuclear Facilities of the Nuclear Waste Management Commission (ESK), which is complementary to the Decommissioning Guide in a technical sense, are reported as well. (authors)

  10. 77 FR 8902 - Draft Regulatory Guide: Issuance, Availability Decommissioning of Nuclear Power Reactors

    Science.gov (United States)

    2012-02-15

    ... Decommissioning of Nuclear Power Reactors AGENCY: Nuclear Regulatory Commission. ACTION: Draft regulatory guide... draft regulatory guide (DG) DG-1271 ``Decommissioning of Nuclear Power Reactors.'' This guide describes... Regulatory Guide 1.184, ``Decommissioning of Nuclear Power Reactors,'' dated July 2000. This proposed...

  11. Industrial safety in a nuclear decommissioning environment observations and lessons learned

    International Nuclear Information System (INIS)

    Brevig, D.

    2008-01-01

    Decommissioning activities present unusual and unexpected workplace safety challenges that go far beyond the traditional experience of nuclear power plant managers. A blend of state-of-the-art safety program management tools along with new and practical applications are required to ensure high industrial safety performance. The demanding and rigorously applied nuclear safety engineering standards that are accepted as normal and routine in the operation of a nuclear power facility, should transform as an industrial safety standard during the non-operating period of decommissioning. In addition, historical measures of non-nuclear industrial safety injury rates would or should not be acceptable safety behaviors during a nuclear decommissioning project. When complex projects, such as the decommissioning of a nuclear generating facility are undertaken, the workforce brings experience, qualifications, and assumptions to the project. The overall multi-year general schedule is developed, with more schedule details, for example, for the nearest rolling 12-18 months. Methods are established for the selection of contractors to assist in areas that are not normal tasks for the facility workforce, whose normal activity is managing and operating a nuclear generating station. However, it is critical to manage those contractors to the agreed work scope to ensure success is maintained by both parties, e.g. the job gets done, on schedule, on budget, all parties are financially whole when the work is complete, and safely. The purpose of this paper is to provide a perspective of nuclear plant personal safety in the ever changing industrial environment created by the demolition of robust and often radiologically contaminated structures in a nuclear facility decommissioning project. (author)

  12. Industrial safety in a nuclear decommissioning environment observations and lessons learned

    Energy Technology Data Exchange (ETDEWEB)

    Brevig, D. [Independent Consultant, San Clemente (United States)

    2008-07-01

    Decommissioning activities present unusual and unexpected workplace safety challenges that go far beyond the traditional experience of nuclear power plant managers. A blend of state-of-the-art safety program management tools along with new and practical applications are required to ensure high industrial safety performance. The demanding and rigorously applied nuclear safety engineering standards that are accepted as normal and routine in the operation of a nuclear power facility, should transform as an industrial safety standard during the non-operating period of decommissioning. In addition, historical measures of non-nuclear industrial safety injury rates would or should not be acceptable safety behaviors during a nuclear decommissioning project. When complex projects, such as the decommissioning of a nuclear generating facility are undertaken, the workforce brings experience, qualifications, and assumptions to the project. The overall multi-year general schedule is developed, with more schedule details, for example, for the nearest rolling 12-18 months. Methods are established for the selection of contractors to assist in areas that are not normal tasks for the facility workforce, whose normal activity is managing and operating a nuclear generating station. However, it is critical to manage those contractors to the agreed work scope to ensure success is maintained by both parties, e.g. the job gets done, on schedule, on budget, all parties are financially whole when the work is complete, and safely. The purpose of this paper is to provide a perspective of nuclear plant personal safety in the ever changing industrial environment created by the demolition of robust and often radiologically contaminated structures in a nuclear facility decommissioning project. (author)

  13. 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

  14. Decontamination and Decommissioning Experience at a Sellafield Uranium Purification Plant

    International Nuclear Information System (INIS)

    Prosser, J.L.

    2006-01-01

    Built in the 1950's, this plant was originally designed to purify depleted uranyl nitrate solution arising from reprocessing operations at the Primary Separation and Head End Plant (Fig. 1). The facility was used for various purposes throughout its life cycle such as research, development and trial based processes. Test rigs were operated in the building from the 1970's until 1984 to support development of the process and equipment now used at Sellafield's Thermal Oxide Reprocessing Plant (THORP). The extensive decommissioning program for this facility began over 15 years ago. Many challenges have been overcome throughout this program such as decommissioning the four main process cells, which were very highly alpha contaminated. The cells contained vessels and pipeline systems that were contaminated to such levels that workers had to use pressurized suits to enter the cells. Since decommissioning at Sellafield was in its infancy, this project has trialed various decontamination/decommissioning methods and techniques in order to progress the project, and this has provided valuable learning for other decommissioning projects. The project has included characterization, decontamination, dismantling, waste handling, and is now ready for demolition during late 2005, early 2006. This will be the first major facility within the historic Separation Area at Sellafield to be demolished down to base slab level. The lessons learnt from this project will directly benefit numerous decommissioning projects as the cleanup at Sellafield continues. (authors)

  15. Selecting strategies for the decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    2006-01-01

    This status report on Selecting Strategies for the Decommissioning of Nuclear Facilities is based on the viewpoints and materials presented at the Tarragona seminar as well as the experience of the WPDD. It identifies, reviews and analyses factors influencing decommissioning strategies and addresses the challenges associated with balancing these factors in the process of strategy selection. It gives recognition to the fact that, in addition to technical characteristics, there are many other factors that influence the selection of a decommissioning strategy and that cannot be quantified, such as policy, regulatory and socio-economic factors and aspects that reach far into the future. Uncertainties associated with such factors are a challenge to those who have to take decisions on a decommissioning strategy. (author)

  16. CONSIDERATIONS FOR THE DEVELOPMENT OF A DEVICE FOR THE DECOMMISSIONING OF THE HORIZONTAL FUEL CHANNELS IN THE CANDU 6 NUCLEAR REACTOR PART 5 - FUEL CHANEL DECOMMISSIONING

    Directory of Open Access Journals (Sweden)

    Gabi ROSCA FARTAT

    2014-05-01

    Full Text Available As many nuclear power plants are reaching their end of lifecycle, the decommissioning of these installations has become one of the 21st century’s great challenges. Each project may be managed differently, depending on the country, development policies, financial considerations, and the availability of qualified engineers or specialized companies to handle such projects. The principle objective of decommissioning is to place a facility into such a condition that there is no unacceptable risk from the decommissioned facility to public health and safety of the environment. In order to ensure that at the end of its life the risk from a facility is within acceptable bounds, action is normally required. The overall decommissioning strategy is to deliver a timely, cost-effective program while maintaining high standards of safety, security and environmental protection. If facilities were not decommissioned, they could degrade and potentially present an environmental radiological hazard in the future. Simply abandoning or leaving a facility after ceasing operations is not considered to be an acceptable alternative to decommissioning. The final aim of decommissioning is to recover the geographic site to its original condition.

  17. Decommissioning situation and research and development for the decommissioning of the commercial nuclear power station in Japan

    International Nuclear Information System (INIS)

    Yamamoto, Tatsumi.

    1996-01-01

    There are 48 commercial nuclear power stations in operation in Japan as of January 1, 1995, which supplies about 28% (2.2 x 10 8 MWh) of total annual electricity generation in FY 1992. Accordingly, as the nuclear power contributes so much in electricity generation, there is a growing concern in the public toward the safety on decommissioning nuclear power station. It is gravely important to secure the safety throughout the decommissioning. This paper discusses: the decommissioning situation in Japan; the Japanese national policy for decommissioning of commercial nuclear power stations; R and D for decommissioning of commercial nuclear power stations in Japan; and the present conditions of low-level radioactive wastes disposal in Japan

  18. The inherent advantages of delayed dismantling of decommissioning nuclear stations

    International Nuclear Information System (INIS)

    Liederman, J.M.; Saroudis, J.I.

    1985-01-01

    Recent studies in Canada pertaining to the decommissioning of the CANDU 600 MW(e) reactor have led to the development of the option of a ''static state'' condition. This alternative is based on judging risk and benefit to society considering the greatly reduced potential radiation exposure to personnel after 30 to 80 years have elapsed, following the final shutdown of the reactor. After approximately 80 to 120 years have elapsed, the decay in all systems and components (with the exception of the reactor assembly) would be such that radiation fields would be at background levels producing an environment that would be acceptable for Stage 3 decommissiong. This philosophy is based on the current engineering judgement that: - All systems, components, and structures which were associated with the nuclear processes and are radioactive, can be put into a static or storage state, and a containment function maintained at low cost for prolonged periods of between 80 to 120 years. - Between 80 to 120 years after shutdown, most of the radioactivity, except for some long lived radionuclides in the reactor vessel itself and its vault, will have naturally decayed to near releasable limits without any external intervention. - There is a lower overall risk to society in this approach, than dismantling and transporting radioactive materials prematurely. This philosophy is developed taking into consideration radiation protection, financial and risk assessment issues. The Canadian concept of dry storage of spent fuel is part of this philosophy and may be of interest to decommissioned nuclear plants of other types. 4 tables, 5 graphs

  19. The decommissioning of a small nuclear reactor

    International Nuclear Information System (INIS)

    Neset, K.; Christensen, G.C.; Lundby, J.E.; Roenneberg, G.A.

    1990-02-01

    The JEEP II reactor at Kjeller, Norway has been used as a model for a study of the decommissioning of a small research reactor. A radiological survey is given and a plan for volume reducing, packaging, certifying, classifying and shipping of the radioactive waste is described. 23 refs., 4 figs

  20. Development of YAG laser cutting system for decommissioning nuclear equipments

    International Nuclear Information System (INIS)

    Kasai, Takeshi; Nitta, Kazuhiko; Hosoda, Hiroshi.

    1995-01-01

    Technology of remote controlled cutting and reduction of generative secondary products have been required to the cutting system for decommissioning nuclear equipments. At a point of view that laser cutting technology by use of a Nd:YAG laser is effective, we have developed the laser cutting machine and carried out cutting tests for several stainless steel plates. As a result, the stainless steel plate with a thickness of 22mm could be cut by using an optical fiber which can flexibly propagate laser power, and possibility of application of this laser cutting system to decommissioning nuclear equipments was verified. (author)

  1. Development of YAG laser cutting system for decommissioning nuclear equipments

    Energy Technology Data Exchange (ETDEWEB)

    Kasai, Takeshi [Fuji Electric Co. Research and Development Ltd., Yokosuka, Kanagawa (Japan); Nitta, Kazuhiko; Hosoda, Hiroshi

    1995-07-01

    Technology of remote controlled cutting and reduction of generative secondary products have been required to the cutting system for decommissioning nuclear equipments. At a point of view that laser cutting technology by use of a Nd:YAG laser is effective, we have developed the laser cutting machine and carried out cutting tests for several stainless steel plates. As a result, the stainless steel plate with a thickness of 22mm could be cut by using an optical fiber which can flexibly propagate laser power, and possibility of application of this laser cutting system to decommissioning nuclear equipments was verified. (author).

  2. Development of decommissioning, decontamination and reuse technology for nuclear facilities

    International Nuclear Information System (INIS)

    Lee, K. W.; Moon, J. K.; Choi, B. S.

    2012-03-01

    In this project, the foundation of decommissioning technology through the development of core technologies applied to maintenance and decommissioning of nuclear facility was established. First of all, we developed the key technology such as safety assessment technology for decommissioning work needed at the preparatory stage of decommissioning of the highly contaminated facilities and simultaneous measurement technology of the high-level alpha/beta contamination applicable to the operation and decommissioning of the nuclear facilities. Second, we developed a remotely controlled laser ablation decontamination system which is useful for a removal of fixed contaminants and developed a chemical gel decontamination technology for a removal of non-fixed contaminants during the maintenance and decommissioning works of high radiation hot cells which have been used for a recycling or treatment of spent fuels. Third, we developed a volume reduction and self-disposal technology for dismantled concrete wastes. Also, the technology for volume reduction and stabilization of the peculiar wastes(HEPA filter and organic mixed wastes), which have been known to be very difficult to treat and manage, generated from the high radioactive facilities in operation, improvement and repair and under decommissioning was developed. Finally, this research project was developed a system for the reduction of radiotoxicity of several uranium mixtures generated in the front- and back-end nuclear fuel cycles with characteristics of highly enhanced proliferation-resistance and more environmental friendliness, which can make the uranium to be recovered or separated from the mixtures with a high purity level enough for the uranium to be reused and to be classified as C-class level for burial near the surface, and then which result in the much reduction in volume of the uranium mixture wastes

  3. Decommissioning and environmental restoration of nuclear facilities in China

    International Nuclear Information System (INIS)

    Pan Ziqiang

    2000-01-01

    In the beginning of the 1980s, the Scientific and Technological Commission (STC) began the study on the environmental impact of the nuclear industry in China. At the end of the 1980s, the STC initiated the study on the decommissioning of nuclear facilities and environmental restoration. In 1989 the STC completed the project entitled ''Radiological and Environmental Quality Assessment of the Nuclear Industry in China Over the Past Thirty Years''. The status of the environmental pollution of various nuclear facility sites was subsequently analysed. In 1994, the decommissioning and environmental restoration of the first research and manufacture complex for nuclear weapons was completed. The complex is now accessible to the public without restriction and the site has become a town. Some nuclear related facilities, such as uranium mines, are currently being decommissioned. Although uranium mining and milling has a more serious impact on the environment, the technology for decommissioning and environmental restoration in mining and milling installations is not much more complicated than that used for reactor and reprocessing facilities: much has been achieved in the area of mining and milling. (author)

  4. Nuclear and non-nuclear safety aspects in nuclear facilities dismantling. The example of a PWR pilot decommissioning project

    International Nuclear Information System (INIS)

    Massaut, V.; Deboodt, P.; Dadoumont, J.; Valenduc, P.; Denissen, L.

    2002-01-01

    The dismantling of nuclear facilities, and in particular of nuclear power plants, involves new challenges for the nuclear industry. Although the dismantling of various activated and contaminated components is nowadays considered as almost industrial practice, the safety aspects of decommissioning bring some specific features which are not always taken into account in the operation of the plants. Moreover, most of the plants and facilities currently decommissioned are rather old and were never foreseen to be decommissioned. The operations involved in dismantling and decontamination, often imply new or unforeseen situations. On the nuclear, or radiological side, the radioprotection optimisation of the operations involved often requires to model the environment and to analyse different scenarios to tackle the operation. Recent 3-D software (like the Visiplan software) allowing representation of the actual environment and the influence of the various sources present, is really needed to be able to minimise the radiological impact on the operators. The risk of contamination spread, by opening loops and components or by the dismantling process itself, is also an important aspect of the radiological protection study. Nevertheless, the radiological aspects of the safety approach are not the only ones to be dealt with when decommissioning nuclear facilities. Indeed, classical industrial safety aspects are also important: the dismantling can bring handling and transporting risk (heavy loads, difficult ways, uneasy access, etc.) but also the handling of toxic or hazardous materials. For instance, the removal of asbestos in contaminated areas can lead to additional hazard; the presence of alkali metals (like Na or NaK), of toxic metals (like e.g. Beryllium) or of corrosive fluids (acid,...) have to be tackled often in unstructured environment, and sometimes with limited knowledge of the actual situation. This leads to approach the operations following the ASARA principle (As

  5. Decommissioning of the gaseous diffusion plant at BNF plc Capenhurst in the UK

    International Nuclear Information System (INIS)

    Clements, D.W.; Cross, J.R.

    1993-01-01

    Since 1982, a gaseous diffusion plant located at the British Nuclear Fuels plc (BNFL) site at Capenhurst in the United Kingdom, has been undergoing decontamination, decommissioning, and dismantling. By March 1994, the decontamination and decommissioning activities will be complete with 99% of the materials used to construct the plant recycled to the environment as clean material. This paper describes the history of the decontamination, decommissioning, dismantling, and disposal program. Reference is made to the scale of the project and to the special techniques developed, particularly in the areas of size reduction, decontamination, and protection of personnel and the environment. The quantities of material involved that require decontamination and release levels for recycling materials in the U.K. metals market are discussed

  6. Nuclear plant life extension

    International Nuclear Information System (INIS)

    Negin, C.A.

    1989-01-01

    The nuclear power industry's addressing of life extension is a natural trend in the maturation of this technology after 20 years of commercial operation. With increasing emphasis on how plants are operated, and less on how to build them, attention is turning on to maximizing the use of these substantial investments. The first studies of life extension were conducted in the period from 1978 and 1982. These were motivated by the initiation, by the Nuclear Regulatory Commission (NRC), of studies to support decommissioning rulemaking. The basic conclusions of those early studies that life extension is feasible and worth pursuing have not been changed by the much more extensive investigations that have since been conducted. From an engineering perspective, life extension for nuclear plants is fundamentally the same as for fossil plants

  7. Beneficial Re-use of Decommissioned Former Nuclear Facilities

    International Nuclear Information System (INIS)

    Boing, L.E.

    1997-01-01

    With the decision to decommission a nuclear facility, it is necessary to evaluate whether to fully demolish a facility or to re-use the facility in some capacity. This evaluation is often primarily driven by both the past mission of the site and the facility and the site's perceived future mission. In the case where the facility to be decommissioned is located within a large research or industrial complex and represents a significant resource to the site's future mission, it may be a perfect candidate to be re-used in some fashion. However, if the site is a rather remote older facility with little chance of being modified to today's standards for its re-use, the chances for its re-use will be substantially reduced. In this presentation, some specific cases of former nuclear facilities being decommissioned and re-used will be reviewed and some factors required to be considered in making this decision will be reviewed

  8. Changing the Focus of Knowledge Management for Nuclear Decommissioning

    International Nuclear Information System (INIS)

    Radford, R.

    2016-01-01

    Full text: Knowledge Management (KM) has long been a recognized tool for improving the safety, efficiency and effectiveness of nuclear facilities. However, the objectives, tools and mechanisms utilized are often focused on steady-state maintenance of established knowledge and on incremental improvements to current practice. When nuclear facilities transition from routine operations to project-based decommissioning activities there is a need to reconsider the knowledge objectives, methodologies and tools to ensure that KM practices are relevant to the new activities being carried out and provide solutions to the new challenges posed in decommissioning. It is important that the changes required in preparation for and during the decommissioning phase are factored in to knowledge planning to ensure that KM activities are efficient and effective. This transition requires a change in the KM mind-set and a different way of setting new KM objectives. (author

  9. Funding schemes in OECD countries for future decommissioning of nuclear power

    International Nuclear Information System (INIS)

    Stevens, G.H.; Yasui, M.

    1993-01-01

    This paper provides a brief overview of the funding schemes for decommissioning implemented in selected OECD countries. The scope of this paper includes only the schemes for future decommissioning costs of private company's nuclear power plants. Countries such as Finland, Spain and Sweden have an official funding scheme, in which the government fixes the amount of money to be put aside, specifies a funding scheme and control the fund. In Belgium and Usa, the government do the same but leaves the management of the fund to the facility owners or external organization. In Canada, France, Germany, Italy, Japan, Netherlands and UK, there is no official funding scheme

  10. EDF decommissioning programme: A global commitment to safety, environment and cost efficiency of nuclear energy

    International Nuclear Information System (INIS)

    Grenouillet, J.-J.

    2002-01-01

    Nowadays, decommissioning of nuclear power plants has become a key issue for the nuclear industry in Europe. The phasing out of nuclear energy in Germany, Belgium and Sweden, as well as the early closure of nuclear units in applicant countries in the frame of EU enlargement, has largely contributed to consider decommissioning as the next challenge to face. The situation is slightly different in France: Nuclear energy is still considered as a safe, cost-effective and environment friendly energy source and EDF is still working on the development of a new generation of reactors to replace the existing ones. Nevertheless, to achieve this objective, it will be necessary to get the support of political decision-makers and the acceptance of public opinion. (author)

  11. Reasons for immediate decommissioning of all nuclear facilities put forward by union members

    International Nuclear Information System (INIS)

    Scheer, J.

    1988-01-01

    The author presents his arguments against the use of nuclear energy from the health hazard point of view, describing the damaging effects of radioactive radiation as a result of increasing environmental radioactivity due to the operation of nuclear installations, or as a consequence of nuclear accidents. The economic problems resulting from an immediate decommissioning of nuclear power plants - development of electricity demand and costs - are judged to be solvable, and decommissioning, the author says, would create new jobs. Another immediate response to the latest irregularities disclosed in the nuclear waste management industry should be to establish public supervisory bodies consisting of non-biased experts who can be found in ecologic research institutes or in other independent monitoring and measuring institutions. (HSCH) [de

  12. Perspectives of nuclear power plants

    International Nuclear Information System (INIS)

    Vajda, Gy.

    2001-01-01

    In several countries the construction of nuclear power plants has been stopped, and in some counties several plants have been decommissioned or are planned to. Therefore, the question arises: have nuclear power plants any future? According to the author, the question should be reformulated: can mankind survive without nuclear power? To examine this challenge, the global power demand and its trends are analyzed. According to the results, traditional energy sources cannot be adequate to supply power. Therefore, a reconsideration of nuclear power should be imminent. The economic, environmental attractions are discussed as opposite to the lack of social support. (R.P.)

  13. Education in nuclear decommissioning in the north of Scotland

    International Nuclear Information System (INIS)

    Catlow, F.; Reeves, G.M.

    2007-01-01

    This paper describes the work covered and experience gained in the first two years of operation of DERC, a Centre for Decommissioning and Environmental Remediation in the Highlands of Scotland. The Centre is a unique development which was set up to teach nuclear decommissioning as a separate discipline, address the problem of a declining skills base in the field of nuclear technologies and to take advantage of the unique and exceptional innovative, technical and research opportunities offered through the decommissioning of Britain's fast reactor site at Dounreay. The Centre is an offshoot from North Highland College which is a member of UHI, the University in embryo of the Highlands and Islands. The Centre currently supports ten PhD students completing various diverse projects mainly in the field of nuclear environmental remediation. In addition there area number of full and part time MSc students who participate in NTEC (Nuclear Technology Education Consortium) a consortium of British Universities set up specifically to engender interest and skills in nuclear technology at postgraduate level. At undergraduate level, courses are offered in Nuclear Decommissioning and related subjects as part of Electrical and Mechanical degree courses. In addition to our relationship with the United Kingdom Atomic Energy Authority (UKAEA) the Dounreay site licensee, we have links with Rolls-Royce and the Ministry of Defence who also share the Dounreay site and with other stakeholders such as, the UK regulator (HSE/NII), the Scottish Environmental Protection Agency (SEPA), local and international contractors and we liaise with the newly formed Nuclear Decommissioning Authority (NDA), who provide some sponsorship and support. We possess our own equipment and laboratories for taking and analysing soil samples and for conducting environmental surveys. Recently we commissioned an aerial survey of contamination in the locality from natural sources, other background levels such as

  14. Decontamination and decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    1989-06-01

    Since 1973, when the IAEA first introduced the subject of decontamination and decommissioning into its programme, twelve Agency reports reflecting the needs of the Member States on these topics have been published. These reports summarize the work done by various Technical Committees, Advisory Groups, and International Symposia. While the basic technology to accomplish decontamination and decommissioning (D and D) is fairly well developed, the Agency feels that a more rapid exchange of information and co-ordination of work are required to foster technology, reduce duplication of effort, and provide useful results for Member States planning D and D activities. Although the Agency's limited financial resources do not make possible direct support of every research work in this field, the IAEA Co-ordinated Research Programme (CRP) creates a forum for outstanding workers from different Member States brought into closer contact with one another to provide for more effective interaction and, perhaps subsequently, closer collaboration. The first IAEA Co-ordinated Research Programme (CRP) on decontamination and decommissioning was initiated in 1984. Nineteen experts from 11 Member States and two international organizations (CEC, OECD/NEA) took part in the three Research Co-ordination Meetings (RCM) during 1984-87. The final RCM took place in Pittsburgh, USA, in conjunction with the 1987 International Decommissioning Symposium (sponsored by the US DOE and organized in co-operation with the IAEA and OECD/NEA). The present document summarizes the salient features and achievements of the co-ordinated research work performed during the 1984-87 programme period. The document consists of two parts: Part 1, Summary of the three research co-ordination meetings and Part 2, Final submissions by participants on the research work performed during 1984-1987. A separate abstract was prepared for each of the 7 reports presented. Refs, figs and tabs

  15. Cost calculations for decommissioning and dismantling of nuclear research facilities

    International Nuclear Information System (INIS)

    Andersson, I.; Backe, S.; Cato, A.; Lindskog, S.; Efraimsson, H.; Iversen, Klaus; Salmenhaara, S.; Sjoeblom, R.

    2008-07-01

    Today, it is recommended that planning of decommission should form an integral part of the activities over the life cycle of a nuclear facility (planning, building and operation), but it was only in the nineteen seventies that the waste issue really surface. Actually, the IAEA guidelines on decommissioning have been issued as recently as over the last ten years, and international advice on finance of decommissioning is even younger. No general international guideline on cost calculations exists at present. This implies that cost calculations cannot be performed with any accuracy or credibility without a relatively detailed consideration of the radiological prerequisites. Consequently, any cost estimates based mainly on the particulars of the building structures and installations are likely to be gross underestimations. The present study has come about on initiative by the Swedish Nuclear Power Inspectorate (SKI) and is based on a common need in Denmark, Finland, Norway and Sweden. The content of the report may be briefly summarised as follows. The background covers design and operation prerequisites as well as an overview of the various nuclear research facilities in the four participating countries: Denmark, Finland, Norway and Sweden. The purpose of the work has been to identify, compile and exchange information on facilities and on methodologies for cost calculation with the aim of achieving an 80 % level of confidence. The scope has been as follows: 1) to establish a Nordic network 2) to compile dedicated guidance documents on radiological surveying, technical planning and financial risk identification and assessment 3) to compile and describe techniques for precise cost calculations at early stages 4) to compile plant and other relevant data A separate section is devoted in the report to good practice for the specific purpose of early but precise cost calculations for research facilities, and a separate section is devoted to techniques for assessment of cost

  16. Cost calculations for decommissioning and dismantling of nuclear research facilities

    Energy Technology Data Exchange (ETDEWEB)

    Andersson, I. (Studsvik Nuclear AB (Sweden)); Backe, S. (Institute for Energy Technology (Norway)); Cato, A.; Lindskog, S. (Swedish Nuclear Power Inspectorate (Sweden)); Efraimsson, H. (Swedish Radiation Protection Authority (Sweden)); Iversen, Klaus (Danish Decommissioning (Denmark)); Salmenhaara, S. (VTT Technical Research Centre of Finland (Finland)); Sjoeblom, R. (Tekedo AB, (Sweden))

    2008-07-15

    Today, it is recommended that planning of decommission should form an integral part of the activities over the life cycle of a nuclear facility (planning, building and operation), but it was only in the nineteen seventies that the waste issue really surface. Actually, the IAEA guidelines on decommissioning have been issued as recently as over the last ten years, and international advice on finance of decommissioning is even younger. No general international guideline on cost calculations exists at present. This implies that cost calculations cannot be performed with any accuracy or credibility without a relatively detailed consideration of the radiological prerequisites. Consequently, any cost estimates based mainly on the particulars of the building structures and installations are likely to be gross underestimations. The present study has come about on initiative by the Swedish Nuclear Power Inspectorate (SKI) and is based on a common need in Denmark, Finland, Norway and Sweden. The content of the report may be briefly summarised as follows. The background covers design and operation prerequisites as well as an overview of the various nuclear research facilities in the four participating countries: Denmark, Finland, Norway and Sweden. The purpose of the work has been to identify, compile and exchange information on facilities and on methodologies for cost calculation with the aim of achieving an 80 % level of confidence. The scope has been as follows: 1) to establish a Nordic network 2) to compile dedicated guidance documents on radiological surveying, technical planning and financial risk identification and assessment 3) to compile and describe techniques for precise cost calculations at early stages 4) to compile plant and other relevant data A separate section is devoted in the report to good practice for the specific purpose of early but precise cost calculations for research facilities, and a separate section is devoted to techniques for assessment of cost

  17. Status of ANSI standards on decommissioning of nuclear reprocessing facilities

    International Nuclear Information System (INIS)

    Graham, H.B.

    1975-01-01

    A definition of decommissioning is given, and the preparation of ANSI Standard, ''General Design Criteria for Nuclear Reprocessing Facilities'' (N101.3) is discussed. A Eurochemic report, entitled ''The Shutdown of Reprocessing Facilities--Results of Preliminary Studies on the Installations Belonging to Eurochemic,'' was used in the preparation of this standard. (U.S.)

  18. Nuclear decommissioning - practical experience of the private sector

    International Nuclear Information System (INIS)

    Brant, A.W.

    1988-01-01

    There is a growing requirement for decommissioning of redundant nuclear facilities. This has led to a number of opportunities for private sector organisations to carry out the work. This paper, based on two actual projects in the United Kingdom, outlines the input required from private sector contractors in executing such work. (author)

  19. Utility planning for decommissioning

    International Nuclear Information System (INIS)

    Williams, D.H.

    1982-01-01

    Though the biggest impact on a utility of nuclear power plant decommissioning may occur many years from now, procrastination of efforts to be prepared for that time is unwarranted. Foresight put into action through planning can significantly affect that impact. Financial planning can assure the recovery of decommissioning costs in a manner equitable to customers. Decision-making planning can minimize adverse affects of current decisions on later decommissioning impacts and prepare a utility to be equipped to make later decommissioning decisions. Technological knowledge base planning can support all other planning aspects for decommissioning and prepare a utility for decommissioning decisions. Informed project planning can ward off potentially significant pitfalls during decommissioning and optimize the effectiveness of the actual decommissioning efforts

  20. Internationally Standardized Cost Item Definitions for Decommissioning of Nuclear Installations

    International Nuclear Information System (INIS)

    Lucien Teunckens; Kurt Pflugrad; Candace Chan-Sands; Ted Lazo

    2000-01-01

    The European Commission (EC), the International Atomic Energy Agency (IAEA), and the Organization for Economic Cooperation and Development/Nuclear Energy Agency (OECD/NEA) have agreed to jointly prepare and publish a standardized list of cost items and related definitions for decommissioning projects. Such a standardized list would facilitate communication, promote uniformity, and avoid inconsistency or contradiction of results or conclusions of cost evaluations for decommissioning projects carried out for specific purposes by different groups. Additionally, a standardized structure would also be a useful tool for more effective cost management. This paper describes actual work and result thus far

  1. Radiochemical analysis for nuclear waste management in decommissioning

    International Nuclear Information System (INIS)

    Hou, X.

    2010-07-01

    The NKS-B RadWaste project was launched from June 2009. The on-going decommissioning activities in Nordic countries and current requirements and problems on the radiochemical analysis of decommissioning waste were discussed and overviewed. The radiochemical analytical methods used for determination of various radionuclides in nuclear waste are reviewed, a book was written by the project partners Jukka Lehto and Xiaolin Hou on the chemistry and analysis of radionuclide to be published in 2010. A summary of the methods developed in Nordic laboratories is described in this report. The progresses on the development and optimization of analytical method in the Nordic labs under this project are presented. (author)

  2. Radiochemical analysis for nuclear waste management in decommissioning

    Energy Technology Data Exchange (ETDEWEB)

    Hou, X. (Technical Univ. of Denmark, Risoe National Lab. for Sustainable Energy. Radiation Research Div., Roskilde (Denmark))

    2010-07-15

    The NKS-B RadWaste project was launched from June 2009. The on-going decommissioning activities in Nordic countries and current requirements and problems on the radiochemical analysis of decommissioning waste were discussed and overviewed. The radiochemical analytical methods used for determination of various radionuclides in nuclear waste are reviewed, a book was written by the project partners Jukka Lehto and Xiaolin Hou on the chemistry and analysis of radionuclide to be published in 2010. A summary of the methods developed in Nordic laboratories is described in this report. The progresses on the development and optimization of analytical method in the Nordic labs under this project are presented. (author)

  3. Development of 3D Visualization Technology for Medium-and Large-sized Radioactive Metal Wastes from Decommissioning Nuclear Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Lee, A Rim; Park, Chan Hee; Lee, Jung Min; Kim, Rinah; Moon, Joo Hyun [Dongguk Univ., Gyongju (Korea, Republic of)

    2013-10-15

    The most important point of decommissioning nuclear facilities and nuclear power plants is to spend less money and do this process safely. In order to perform a better decommissioning nuclear facilities and nuclear power plants, a data base of radioactive waste from decontamination and decommissioning of nuclear facilities should be constructed. This data base is described herein, from the radioactive nuclide to the shape of component of nuclear facilities, and representative results of the status and analysis are presented. With the increase in number of nuclear facilities at the end of their useful life, the demand of decommissioning technologies will continue to grow for years to come. This analysis of medium-and large-sized radioactive metal wastes and 3D visualization technology of the radioactive metal wastes using the 3D-SCAN are planned to be used for constructing data bases. The data bases are expected to be used on development of the basic technologies for decommissioning nuclear facilities 4 session.

  4. The Practice of Cost Estimation for Decommissioning of Nuclear Facilities

    International Nuclear Information System (INIS)

    Davidova, Ivana; Desecures, Sylvain; Lexow, Thomas; Buonarroti, Stefano; Marini, Giuseppe; Pescatore, Claudio; Rehak, Ivan; Weber, Inge; ); Daniska, Vladimir; Linan, Jorge Borque; Caroll, Simon; Hedberg, Bjoern; De La Gardie, Fredrik; Haenggi, Hannes; Laguardia, Thomas S.; Ridpath, Andy

    2015-01-01

    Decommissioning of both commercial and R and D nuclear facilities is expected to increase significantly in the coming years, and the largest of such industrial decommissioning projects could command considerable budgets. Several approaches are currently being used for decommissioning cost estimations, with an international culture developing in the field. The present cost estimation practice guide was prepared in order to offer international actors specific guidance in preparing quality cost and schedule estimates to support detailed budgeting for the preparation of decommissioning plans, for the securing of funds and for decommissioning implementation. This guide is based on current practices and standards in a number of NEA member countries and aims to help consolidate the practice and process of decommissioning cost estimation so as to make it more widely understood. It offers a useful reference for the practitioner and for training programmes. The remainder of report is divided into the following chapters: - Chapter 2 covers the purpose and nature of decommissioning cost estimates, approaches to cost estimation and the major elements of a cost estimate. - Chapter 3 examines the development of the integrated schedule of the activity-dependent work scope and the determination of the project critical path. - Chapter 4 describes the attributes of a quality assurance programme applicable to cost estimation and the use and cautions of benchmarking the estimate from other estimates or actual costs. - Chapter 5 describes the pyramidal structure of the report, and the scope and content that should be included in the cost study report to ensure consistency and transparency in the estimate underpinnings. - Chapter 6 provides some observations, conclusions and recommendations on the use of this guide

  5. Planning and management for the decommissioning of research reactors and other small nuclear facilities

    International Nuclear Information System (INIS)

    1993-01-01

    Many research reactors and other small nuclear facilities throughout the world date from the original nuclear research programmes in the Member States. Consequently, a large number of these plants have either been retired from service or will soon reach the end of their useful lives and are likely to become significant decommissioning tasks for those Members States. In recognition of this situation and in response to considerable interest shown by Member States, the IAEA has produced this document on planning and management for the decommissioning of research reactors and other small nuclear facilities. While not directed specifically at large nuclear installations, it is likely that much of the information presented will also be of interest to those involved in the decommissioning of such facilities. Current views, information and experience on the planning and management of decommissioning projects in Member States were collected and assessed during a Technical Committee Meeting held by the IAEA in Vienna from 29 July to 2 August 1991. It was attended by 22 participants from 14 Member States and one international organization. 28 refs, 2 figs, 3 tabs

  6. The unit cost factors and calculation methods for decommissioning - Cost estimation of nuclear research facilities

    International Nuclear Information System (INIS)

    Kwan-Seong Jeong; Dong-Gyu Lee; Chong-Hun Jung; Kune-Woo Lee

    2007-01-01

    Available in abstract form only. Full text of publication follows: The uncertainties of decommissioning costs increase high due to several conditions. Decommissioning cost estimation depends on the complexity of nuclear installations, its site-specific physical and radiological inventories. Therefore, the decommissioning costs of nuclear research facilities must be estimated in accordance with the detailed sub-tasks and resources by the tasks of decommissioning activities. By selecting the classified activities and resources, costs are calculated by the items and then the total costs of all decommissioning activities are reshuffled to match with its usage and objectives. And the decommissioning cost of nuclear research facilities is calculated by applying a unit cost factor method on which classification of decommissioning works fitted with the features and specifications of decommissioning objects and establishment of composition factors are based. Decommissioning costs of nuclear research facilities are composed of labor cost, equipment and materials cost. Of these three categorical costs, the calculation of labor costs are very important because decommissioning activities mainly depend on labor force. Labor costs in decommissioning activities are calculated on the basis of working time consumed in decommissioning objects and works. The working times are figured out of unit cost factors and work difficulty factors. Finally, labor costs are figured out by using these factors as parameters of calculation. The accuracy of decommissioning cost estimation results is much higher compared to the real decommissioning works. (authors)

  7. Radioactive Waste Management and Nuclear Facility Decommissioning Progress in Iraq - 13216

    Energy Technology Data Exchange (ETDEWEB)

    Al-Musawi, Fouad; Shamsaldin, Emad S.; Jasim, Hadi [Ministry of Science and Technology (MoST), Al-Jadraya, P.O. Box 0765, Baghdad (Iraq); Cochran, John R. [Sandia National Laboratories1, New Mexico, Albuquerque New Mexico 87185 (United States)

    2013-07-01

    Management of Iraq's radioactive wastes and decommissioning of Iraq's former nuclear facilities are the responsibility of Iraq's Ministry of Science and Technology (MoST). The majority of Iraq's former nuclear facilities are in the Al-Tuwaitha Nuclear Research Center located a few kilometers from the edge of Baghdad. These facilities include bombed and partially destroyed research reactors, a fuel fabrication facility and radioisotope production facilities. Within these facilities are large numbers of silos, approximately 30 process or waste storage tanks and thousands of drums of uncharacterised radioactive waste. There are also former nuclear facilities/sites that are outside of Al-Tuwaitha and these include the former uranium processing and waste storage facility at Jesira, the dump site near Adaya, the former centrifuge facility at Rashdiya and the former enrichment plant at Tarmiya. In 2005, Iraq lacked the infrastructure needed to decommission its nuclear facilities and manage its radioactive wastes. The lack of infrastructure included: (1) the lack of an organization responsible for decommissioning and radioactive waste management, (2) the lack of a storage facility for radioactive wastes, (3) the lack of professionals with experience in decommissioning and modern waste management practices, (4) the lack of laws and regulations governing decommissioning or radioactive waste management, (5) ongoing security concerns, and (6) limited availability of electricity and internet. Since its creation eight years ago, the MoST has worked with the international community and developed an organizational structure, trained staff, and made great progress in managing radioactive wastes and decommissioning Iraq's former nuclear facilities. This progress has been made, despite the very difficult implementing conditions in Iraq. Within MoST, the Radioactive Waste Treatment and Management Directorate (RWTMD) is responsible for waste management and the

  8. Radioactive Waste Management and Nuclear Facility Decommissioning Progress in Iraq - 13216

    International Nuclear Information System (INIS)

    Al-Musawi, Fouad; Shamsaldin, Emad S.; Jasim, Hadi; Cochran, John R.

    2013-01-01

    Management of Iraq's radioactive wastes and decommissioning of Iraq's former nuclear facilities are the responsibility of Iraq's Ministry of Science and Technology (MoST). The majority of Iraq's former nuclear facilities are in the Al-Tuwaitha Nuclear Research Center located a few kilometers from the edge of Baghdad. These facilities include bombed and partially destroyed research reactors, a fuel fabrication facility and radioisotope production facilities. Within these facilities are large numbers of silos, approximately 30 process or waste storage tanks and thousands of drums of uncharacterised radioactive waste. There are also former nuclear facilities/sites that are outside of Al-Tuwaitha and these include the former uranium processing and waste storage facility at Jesira, the dump site near Adaya, the former centrifuge facility at Rashdiya and the former enrichment plant at Tarmiya. In 2005, Iraq lacked the infrastructure needed to decommission its nuclear facilities and manage its radioactive wastes. The lack of infrastructure included: (1) the lack of an organization responsible for decommissioning and radioactive waste management, (2) the lack of a storage facility for radioactive wastes, (3) the lack of professionals with experience in decommissioning and modern waste management practices, (4) the lack of laws and regulations governing decommissioning or radioactive waste management, (5) ongoing security concerns, and (6) limited availability of electricity and internet. Since its creation eight years ago, the MoST has worked with the international community and developed an organizational structure, trained staff, and made great progress in managing radioactive wastes and decommissioning Iraq's former nuclear facilities. This progress has been made, despite the very difficult implementing conditions in Iraq. Within MoST, the Radioactive Waste Treatment and Management Directorate (RWTMD) is responsible for waste management and the Iraqi Decommissioning

  9. Decommissioning of fuel PIE caves at Berkeley Nuclear Laboratories

    International Nuclear Information System (INIS)

    Brant, A.W.

    1990-01-01

    This paper describes the first major contract awarded to private industry to carry out decommissioning of a facility with significant radiation levels. The work required operatives to work in pressurised suits, entry times were significantly affected by sources of radiation in the Caves, being as low as thirty minutes per day initially. The Caves at Berkeley Nuclear Laboratories carry out post irradiation examination of fuel elements support units and reactor core components from CEGB power stations. The decommissioning work is part of an overall refurbishment of the facility to allow the receipt of AGR Fuel Stringer Component direct from power stations. The paper describes the decommissioning and decontamination of the facility from the remote removal and clean up work carried out by the client to the hands-on work. It includes reference to entry times, work patterns, interfaces with the client and the operations of the laboratory. Details of a specially adapted size reduction method are given. (Author)

  10. Factors relevant to the recycling or reuse of components arising from the decommissioning and refurbishment of nuclear facilities

    International Nuclear Information System (INIS)

    1988-01-01

    The decommissioning and decontamination of nuclear facilities is a topic of great interest to many Member States of the International Atomic Energy Agency (IAEA) because of the large number of older nuclear facilities which are or soon will be retired from service. To assist in the development of the required decommissioning expertise, the IAEA is developing reports and recommendations which will eventually form an integrated information base covering in a systematic way the wide range of topics associated with decommissioning. This information is required so that Member States can decommission their nuclear facilities in a safe, timely and cost effective manner and the IAEA can effectively respond to requests for assistance. One area which warrants more detailed analyses is an assessment of the factors important to the recycling or reuse of components arising from the refurbishment or decommissioning of nuclear plants, the topic of the present report. The document provides an up to date review of the engineering, social, scientific and administrative factors relevant to the safe recycling or reuse of components arising from decommissioning or refurbishment of nuclear facilities. This report should be of interest to owners, operators, policy makers and regulators involved with nuclear facilities, especially those in developing countries. Refs, figs and tabs

  11. Assuring the availability of funds for decommissioning nuclear reactors

    International Nuclear Information System (INIS)

    1990-08-01

    The general requirements for applications for license termination and decommissioning nuclear power, research, and test reactors are contained in 10 CFR Part 50, ''Domestic Licensing of Production and Utilization Facilities.'' On June 27, 1988, the Commission published amendments to 10 CFR Part 50 (53 FR 24018) concerning specific criteria for decommissioning nuclear facilities. Amended 10 CFR 50.33(k), 50.75, and 50.82(b) require operating license applicants and existing licensees to submit information on how reasonable assurance will be provided that funds are available to decommission the facility. Amended section 50.75 establishes requirements for indicating how this assurance will be provided, namely the amount of funds that must provided, including updates, and the methods to be used for assuring funds. This regulatory guide has been developed in conjunction with the rule amendments and was published for public comment in May 1989. This version incorporates, where appropriate, the public comments received. Its purpose is to provide guidance to applicants and licensees of nuclear power, research, and test reactors concerning methods acceptable to the NRC staff for complying with requirements in the amended rule regarding the amount of funds for decommissioning. It also provides guidance on the content and form of the financial assurance mechanisms indicated in the rule amendments. 9 refs

  12. The Relevance of Metal Recycling for Nuclear Industry Decommissioning Programmes

    Energy Technology Data Exchange (ETDEWEB)

    O' Sullivan, P.J., E-mail: nea@nea.fr [OECD Nuclear Energy Agency, Paris (France)

    2011-07-15

    The large amount of scrap metal arising from the decommissioning of nuclear facilities may present significant problems in the event that the facility owners seek to implement a management strategy based largely or fully on disposal in dedicated disposal facilities. Depending on whether disposal facilities currently exist or need to be developed, this option can be very expensive. Also, public reluctance to accept the expansion of existing disposal facilities, or the siting of new ones, mean that the disposal option should be used only after a wide consideration of all available management options. A comparison of health, environmental and socio-economic impacts of the recycling of lightly contaminated scrap metal, as compared with equivalent impacts associated with the production of replacement material, suggests that recycling has significant overall advantages. With present-day technologies, a large proportion of the metal waste from decommissioning can be decontaminated to clearance levels because most of the contamination is on or near the surface of the metal. In purely economic terms, it makes little sense for lightly contaminated scrap metal from decommissioning, which tends to be of high quality, to be removed from the supply chain and replaced with metal from newly-mined ore. In many countries, the metal recycling industry remains reluctant to accept metal from decommissioning. In Germany, the recycling industry and the decommissioning industry have worked together to develop an approach whereby such material is accepted for melting and the recycled material and is then used for certain defined end uses. Sweden also uses dedicated melting facilities for the recycling of metal from the nuclear industry. Following this approach, the needs of the decommissioning industry are being met in a way that also addresses the needs of the recycling industry. (author)

  13. Waste Management Strategy for Dismantling Waste to Reduce Costs for Power Plant Decommissioning - 13543

    Energy Technology Data Exchange (ETDEWEB)

    Larsson, Arne; Lidar, Per [Studsvik Nuclear AB, SE-611 82 Nykoeping (Sweden); Bergh, Niklas; Hedin, Gunnar [Westinghouse Electric Sweden AB, Fredholmsgatan 2, SE-721 63, Vaesteraas (Sweden)

    2013-07-01

    Decommissioning of nuclear power plants generates large volumes of radioactive or potentially radioactive waste. The proper management of the dismantling waste plays an important role for the time needed for the dismantling phase and thus is critical to the decommissioning cost. An efficient and thorough process for inventorying, characterization and categorization of the waste provides a sound basis for the planning process. As part of comprehensive decommissioning studies for Nordic NPPs, Westinghouse has developed the decommissioning inventories that have been used for estimations of the duration of specific work packages and the corresponding costs. As part of creating the design basis for a national repository for decommissioning waste, the total production of different categories of waste packages has also been predicted. Studsvik has developed a risk based concept for categorization and handling of the generated waste using six different categories with a span from extremely small risk for radiological contamination to high level waste. The two companies have recently joined their skills in the area of decommissioning on selected market in a consortium named 'ndcon' to further strengthen the proposed process. Depending on the risk for radiological contamination or the radiological properties and other properties of importance for waste management, treatment routes are proposed with well-defined and proven methods for on-site or off-site treatment, activity determination and conditioning. The system is based on a graded approach philosophy aiming for high confidence and sustainability, aiming for re-use and recycling where found applicable. The objective is to establish a process where all dismantled material has a pre-determined treatment route. These routes should through measurements, categorization, treatment, conditioning, intermediate storage and final disposal be designed to provide a steady, un-disturbed flow of material to avoid

  14. Waste Management Strategy for Dismantling Waste to Reduce Costs for Power Plant Decommissioning - 13543

    International Nuclear Information System (INIS)

    Larsson, Arne; Lidar, Per; Bergh, Niklas; Hedin, Gunnar

    2013-01-01

    Decommissioning of nuclear power plants generates large volumes of radioactive or potentially radioactive waste. The proper management of the dismantling waste plays an important role for the time needed for the dismantling phase and thus is critical to the decommissioning cost. An efficient and thorough process for inventorying, characterization and categorization of the waste provides a sound basis for the planning process. As part of comprehensive decommissioning studies for Nordic NPPs, Westinghouse has developed the decommissioning inventories that have been used for estimations of the duration of specific work packages and the corresponding costs. As part of creating the design basis for a national repository for decommissioning waste, the total production of different categories of waste packages has also been predicted. Studsvik has developed a risk based concept for categorization and handling of the generated waste using six different categories with a span from extremely small risk for radiological contamination to high level waste. The two companies have recently joined their skills in the area of decommissioning on selected market in a consortium named 'ndcon' to further strengthen the proposed process. Depending on the risk for radiological contamination or the radiological properties and other properties of importance for waste management, treatment routes are proposed with well-defined and proven methods for on-site or off-site treatment, activity determination and conditioning. The system is based on a graded approach philosophy aiming for high confidence and sustainability, aiming for re-use and recycling where found applicable. The objective is to establish a process where all dismantled material has a pre-determined treatment route. These routes should through measurements, categorization, treatment, conditioning, intermediate storage and final disposal be designed to provide a steady, un-disturbed flow of material to avoid interruptions. Bottle

  15. Decommissioning of Australian nuclear facilities - a regulatory perspective

    International Nuclear Information System (INIS)

    Diamond, T.V.; Mabbott, P.E.; Lawrence, B.R.

    2000-01-01

    Decommissioning has been a key political, economic and technical issue for the nuclear industry in recent years as older nuclear facilities have been retired. The management of decommissioning is an important part of nuclear safety as the potential exists for occupational exposures that are several times those expected during normal operation. It involves pre-planning and preparatory measures, procedures and instructions, technical and safety assessments, technology for handling large volumes of radioactive material, cost analyses, and a complex decision process. A challenge for the Commonwealth Government regulatory body, the Australian Radiation Protection and Nuclear Safety Agency (ARPANSA), is to allow the Commonwealth entities that operate nuclear facilities ample freedom to address the above, at the same time ensuring that international best practice is invoked to ensure safety. Accordingly, ARPANSA has prepared a regulatory guideline, first drafted by the Nuclear Safety Bureau in March 1997, that documents the process and the criteria that it uses when assessing an application from an operating organisation for a decommissioning licence. Copyright (2000) Australasian Radiation Protection Society Inc

  16. Development of the Decontamination and Decommissioning Technology for Nuclear Facilities

    International Nuclear Information System (INIS)

    Lee, K. W.; Moon, J. K.; Won, C. H.

    2010-04-01

    The research results could be used for a design of a remote ablation decontamination system and ultimately applicable for an decontamination of high radiation facilities such as the DUPIC and PIEF. The evaluation technology of decommissioning process must be developed and will be used for the ALARA planning tool of decommissioning process and demonstrated for tools of decommissioning equipment. Also, this technology can be used for tools workplaces with high work difficulty such as large-scale chemical plant, under water and space. It is expected that the technology for a volume reduction and self-disposal of dismantled concrete wastes can be contributed to the establishment of a management plan for radioactive dismantled concrete wastes through the minimization of final waste volume

  17. Worldwide overview of nuclear submarine decommissioning plans and issues

    International Nuclear Information System (INIS)

    Oelgaard, P.L.

    1995-06-01

    The number of nuclear propelled vessels that have reached the end of their useful life, is increasing. This raises the question of what to do with these vessels. In this paper the order of magnitude of the problem is first discussed, i.e. the number of nuclear ships built and the number already taken out of service. Next the problems of the first stages of decommissioning are discussed, i.e. the removal of the fuel and the preparation of the reactor parts for final disposal, including the amounts of radioactivity involved. Thirdly, the various methods of final disposal are considered, sea disposal, shallow land burial and deep land burial. Finally, the risks involved in nuclear submarine decommissioning are briefly discussed. (au)

  18. Design Lessons Drawn from the Decommissioning of Nuclear Facilities

    International Nuclear Information System (INIS)

    2011-05-01

    This report provides an updated compilation incorporating the most recent lessons learned from decommissioning and remediation projects. It is intended as a 'road map' to those seeking to apply these lessons. The report presents the issues in a concise and systematic manner, along with practical, thought-provoking examples. The most important lessons learned in recent years are organized and examined to enable the intended audience to gauge the importance of this aspect of the planning for new nuclear facilities. These will be of special interest to those seeking to construct nuclear facilities for the first time. In Sections 1 and 2, the current situation in the field of decommissioning is reviewed and the relevance and importance of beneficial design features is introduced. A more detailed review of previous and current lessons learned from decommissioning is given in Section 3 where different aspects of the decommissioning process are analysed. From this analysis beneficial design features have been extracted and identified in Section 4 which includes two comprehensive tables where brief descriptions of the features are summarized and responsibilities are identified. Conclusions and key design features and key recommendations are given in Section 5. Two Annexes are included to provide lessons from past projects and past experience and to record notes and extracts taken from a comprehensive list of publications listed in the References on page 47.

  19. Possibility of applying large-scale point cloud/mixed reality technology in decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Shoji, Kimiaki

    2017-01-01

    After the accident at Tokyo Electric Company's Fukushima No. 1 nuclear power plant, decommissioning projects of nuclear power plants exceeding 40 years since the start of operation began to move in full swing. And four nuclear power plants have already been under decommissioning. Several decommissioning engineering systems (ES) have been developed according to these decommissioning projects. Various problems were clarified and many findings were obtained by these efforts. On the other, advanced information technologies and products such as three-dimensional CAD, CG, 3D laser measurement, computer aided engineering (CAE) and mixed reality (MR) are progressing rapidly. By combining these technologies and products, it has become possible not only to enhance the usefulness of existing 3D CAD data but also to enable high-level digital study that combines reality and virtual models. Furthermore, it can be applied to a wide range of fields such as demolition simulation for dismantling works of nuclear facilities, which is expected to increase in future, human resource development and skill transfer. In this paper, focusing on a video see-through method capable of displaying a virtual object at a correct position of a real image accurately reflecting the positional relationship between the real image and the virtual object, we introduce items that should contribute to the feasibility and usefulness of application to decommissioning of nuclear facilities. (author)

  20. The study on the recycle condition for existence of the decommissioning waste in the nuclear power station

    International Nuclear Information System (INIS)

    Hironaga, Michihiko; Ozaki, Sachio; Hirai, Mitsuyuki; Sakamoto, Hiroyuki; Usui, Tatsuo; Simizu, Yasuo; Ogane, Daisuke

    2000-01-01

    To establish the technique of the recycle for concrete waste, this paper describes the recycle condition for existence of the decommissioning concrete waste in the nuclear power plant and considers the durability of cask yard concrete constructed at about twenty years ago. The authors examine the recycle system of concrete in the power plant. (author)

  1. Nuclear power plants and their insurances

    International Nuclear Information System (INIS)

    Schludi, H.N.

    1984-01-01

    From the commencement of building to the time of decommissioning of nuclear power plants, the insurances provide continuous coverage, i.e. for construction, nuclear liability, nuclear energy hazards insurance, fire insurance, machinery insurance. The respective financial security is quantified. (DG) [de

  2. Cost calculations for decommissioning and dismantling of nuclear research facilities, Phase 1

    International Nuclear Information System (INIS)

    Andersson, Inga; Backe, S.; Iversen, Klaus; Lindskog, S; Salmenhaara, S.; Sjoeblom, R.

    2006-11-01

    Today, it is recommended that planning of decommission should form an integral part of the activities over the life cycle of a nuclear facility. However, no actual international guideline on cost calculations exists at present. Intuitively, it might be tempting to regard costs for decommissioning of a nuclear facility as similar to those of any other plant. However, the presence of radionuclide contamination may imply that the cost is one or more orders of magnitude higher as compared to a corresponding inactive situation, the actual ratio being highly dependent on the level of contamination as well as design features and use of the facility in question. Moreover, the variations in such prerequisites are much larger than for nuclear power plants. This implies that cost calculations cannot be performed with any accuracy or credibility without a relatively detailed consideration of the radiological and other prerequisites. Application of inadequate methodologies especially at early stages has often lead to large underestimations. The goals of the project and the achievements described in the report are as follows: 1) Advice on good practice with regard to: 1a) Strategy and planning; 1b) Methodology selection; 1c) Radiological surveying; 1d) Uncertainty analysis; 2) Techniques for assessment of costs: 2a) Cost structuring; 2b) Cost estimation methodologies; 3) Compilation of data for plants, state of planning, organisations, etc.; 3a) General descriptions of relevant features of the nuclear research facilities; 3b) General plant specific data; 3c) Example of the decommissioning of the R1 research reactor in Sweden; 3d) Example of the decommissioning of the DR1 research reactor in Denmark. In addition, but not described in the present report, is the establishment of a Nordic network in the area including an internet based expert system. It should be noted that the project is planned to exist for at least three years and that the present report is an interim one

  3. Cost calculations for decommissioning and dismantling of nuclear research facilities, Phase 1

    Energy Technology Data Exchange (ETDEWEB)

    Andersson, Inga [StudsvikNuclear AB (Sweden); Backe, S. [Institute for Energy Technology (Norway); Iversen, Klaus [Danish Decommissioning (Denmark); Lindskog, S [Swedish Nuclear Power Inspectorate (Sweden); Salmenhaara, S. [VTT Technical Research Centre of Finland (Finland); Sjoeblom, R. [Tekedo AB (Sweden)

    2006-11-15

    Today, it is recommended that planning of decommission should form an integral part of the activities over the life cycle of a nuclear facility. However, no actual international guideline on cost calculations exists at present. Intuitively, it might be tempting to regard costs for decommissioning of a nuclear facility as similar to those of any other plant. However, the presence of radionuclide contamination may imply that the cost is one or more orders of magnitude higher as compared to a corresponding inactive situation, the actual ratio being highly dependent on the level of contamination as well as design features and use of the facility in question. Moreover, the variations in such prerequisites are much larger than for nuclear power plants. This implies that cost calculations cannot be performed with any accuracy or credibility without a relatively detailed consideration of the radiological and other prerequisites. Application of inadequate methodologies especially at early stages has often lead to large underestimations. The goals of the project and the achievements described in the report are as follows: 1) Advice on good practice with regard to: 1a) Strategy and planning; 1b) Methodology selection; 1c) Radiological surveying; 1d) Uncertainty analysis; 2) Techniques for assessment of costs: 2a) Cost structuring; 2b) Cost estimation methodologies; 3) Compilation of data for plants, state of planning, organisations, etc.; 3a) General descriptions of relevant features of the nuclear research facilities; 3b) General plant specific data; 3c) Example of the decommissioning of the R1 research reactor in Sweden; 3d) Example of the decommissioning of the DR1 research reactor in Denmark. In addition, but not described in the present report, is the establishment of a Nordic network in the area including an internet based expert system. It should be noted that the project is planned to exist for at least three years and that the present report is an interim one

  4. Plan for reevaluation of NRC policy on decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    1978-03-01

    Recognizing that the current generation of large commercial reactors and supporting nuclear facilities would substantially increase future decommissioning needs, the NRC staff began an in-depth review and re-evaluation of NRC's regulatory approach to decommissioning in 1975. Major technical studies on decommissioning have been initiated at Battelle Pacific Northwest Laboratory in order to provide a firm information base on the engineering methodology, radiation risks, and estimated costs of decommissioning light water reactors and associated fuel cycle facilities. The Nuclear Regulatory Commission is now considering development of a more explicit overall policy for nuclear facility decommissioning and amending its regulations in 10 CFR Parts 30, 40, 50, and 70 to include more specific guidance on decommissioning criteria for production and utilization facility licensees and byproduct, source, and special nuclear material licensees. The report sets forth in detail the NRC staff plan for the development of an overall NRC policy on decommissioning of nuclear facilities

  5. Decommissioning alternatives for the West Valley, New York, Fuel Reprocessing Plant

    Energy Technology Data Exchange (ETDEWEB)

    Munson, L F; Nemec, J F; Koochi, A K

    1978-06-01

    The methodology and numerical values of NUREG-0278 were applied to four decommissioning alternatives for the West Valley Fuel Reprocessing Plant. The cost and impacts of the following four alternatives for the process building, fuel receiving and storage, waste tank farm, and auxiliary facilities were assessed: (1) layaway, (2) protective storage, (3) preparation for alternate nuclear use, and (4) dismantlement. The estimated costs are 5.7, 11, 19, and 31 million dollars, respectively. (DLC)

  6. Decommissioning alternatives for the West Valley, New York, Fuel Reprocessing Plant

    International Nuclear Information System (INIS)

    Munson, L.F.; Nemec, J.F.; Koochi, A.K.

    1978-06-01

    The methodology and numerical values of NUREG-0278 were applied to four decommissioning alternatives for the West Valley Fuel Reprocessing Plant. The cost and impacts of the following four alternatives for the process building, fuel receiving and storage, waste tank farm, and auxiliary facilities were assessed: (1) layaway, (2) protective storage, (3) preparation for alternate nuclear use, and (4) dismantlement. The estimated costs are 5.7, 11, 19, and 31 million dollars, respectively

  7. Status of the decommissioning program of the Eurochemic reprocessing plant

    International Nuclear Information System (INIS)

    Detilleux, E.J.

    1976-01-01

    Reprocessing operations at the Eurochemic demonstration plant stopped in December 1974, after 8 years of operation. Immediately thereafter, cleaning and decontamination were begun as the first phase of the decommissioning program. The facility and reprocessing program are described to indicate the magnitude of the problem, and the requirements of the local authorities are reviewed. The technical decommissioning program consists of several phases: (1) plant cleaning and rinsing, (2) establishment of the final fissile-material balance, (3) plant decontamination for access to process equipment, (4) equipment dismantling, and (5) conditioning and storage of newly generated wastes. The two first phases have been completed, and the third one is nearing completion. Some dismantling has been performed, including the plutonium dioxide production unit. Waste-conditioning and surface-storage facilities have been built to meet the dismantling requirements. Since reprocessing may be resumed in the future, decontamination has been performed with ''smooth'' reagents to limit corrosion and dismantling has been limited to subfacilities

  8. Evaluation of nuclear facility decommissioning projects. Project summary report, Elk River Reactor

    International Nuclear Information System (INIS)

    Miller, R.L.; Adams, J.A.

    1982-12-01

    This report summarizes information concerning the decommissioning of the Elk River Reactor. Decommissioning data from available documents were input into a computerized data-handling system in a manner that permits specific information to be readily retrieved. The information is in a form that assists the Nuclear Regulatory Commission in its assessment of decommissioning alternatives and ALARA methods for future decommissionings projects. Samples of computer reports are included in the report. Decommissioning of other reactors, including NRC reference decommissioning studies, will be described in similar reports

  9. Evolution of some important principles on decommissioning of nuclear and radiation facilities

    International Nuclear Information System (INIS)

    Zhao Yamin; Wu Hao

    2004-01-01

    The paper introduces the evolution of some important principles on decommissioning of nuclear and radiation facilities. Decommissioning issue should not be regarded just as an end phase of the facilities operation, but should be taken into consideration as a part of whole operation process. The decommissioning plan and management should be considered in all phases of siting, design, construction and operation. A new term 'Facilitating Decommissioning' is introduced. Three stages principle of decommissioning (storage with surveillance, restricted release and unrestricted release) is being faded. The decommissioning implementation and related regulatory body should pay attention to these principal changes

  10. Decommissioning and dismantling of nuclear research facilities in Switzerland: lessons learned

    International Nuclear Information System (INIS)

    Leibundgut, Fritz

    2017-01-01

    Paul Scherrer Institute is the largest research institute for natural and engineering science in Switzerland. It operated various nuclear facilities from 1960 to 2011: Research reactors DIORIT, SAPHIR and PROTEUS, and an incineration plant for low and medium level radioactive waste. Concerning SAPHIR research reactor: in operation from 1958 to 1993, planning of decommissioning from 1998 to 2000. Decommissioning work started in 2004. Finishing is planned for 2019. Concerning DIORIT research reactor: operation as DIORIT I (20 MWth) from 1960 to 1967, then reconstruction to DIORIT II (30 MWth) and operation from 1970 until 1977. Planning of decommissioning from 1992 to 1994. Decommissioning work started in 1994 and was finished in 2012. Concerning PROTEUS research reactor: in operation from 1966 to 2011. Planning of decommissioning from 2013 to 2014. Starting of decommissioning work is planned for 2017, finishing is planned for the end of 2018 Incineration plant: In operation from 1974 to 2002. Planning of decommissioning from 2011 to 2012. Starting of decommissioning work in 2016. Finishing planned for end of 2019. Treatment of various material categories from dismantling: Concerning aluminum: because of the production of H_2 during solidification in concrete, it was necessary to minimize the surface area. When dismantling research reactors, the aluminum removed was melted in an induction furnace and poured into a 4.5 m"3 concrete container to solidify. Cutting the metal and handling it was largely accomplished remote control, using conventional technology. Concerning Steel/Cast-iron: the storage containers to be filled determined the method used for reducing the size of these materials, and the technique used for handling them. The goal was to optimize the packing density to reduce repository costs. The selected method of reducing the size of components is to cut them up using diamond-tipped tools, like saw blades. Concerning Graphite: for graphite, grinding was the

  11. National policies and regulations for decommissioning nuclear facilities

    International Nuclear Information System (INIS)

    1993-07-01

    This report, though produced as a follow-up to Safety Series No. 105, The Regulatory Process for the Decommissioning of Nuclear Facilities, is not primarily intended as guidance. Rather, its objective is to provide an overview of national decommissioning policies and regulatory practices as part of the background knowledge which is an essential precondition for good decision making. It discusses the reasons for the similarities and differences in national approach using specific examples but without giving preference to any particular scheme; it aims rather to provide factual, general information on the choices that have been or are being made, and why. As many Member States are in a transient situation between the case-by-case approach to decommissioning and the establishment of national policies, strategies and regulations, this seems the right moment to assess existing national practices worldwide and that is the purpose for which the document is issued at this time. The information gathered in this report is based on submissions by Member States which have developed or are in the process of developing decommissioning oriented policies and regulations. 29 refs

  12. General framework and basis of decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Santiago, J. L.; Martin, N.; Correa, C.

    2013-01-01

    This article summarizes the legal framework defining the strategies, the main activities and the basic responsibilities and roles of the various agents involved in the decommissioning of nuclear facilities in Spain. It also describes briefly the most relevant projects and activities already developed and/or ongoing nowadays, which have positioned Spain within the small group of countries having an integrated and proved experience and know how in this particular field. (Author)

  13. A study on the influence of the regulatory requirements of a nuclear facility during decommissioning activities

    Energy Technology Data Exchange (ETDEWEB)

    Park, Hee Seong; Park, Seung Kook; Park, Kook Nam; Hong, Yun Jeong; Park, Jang Jin; Choi, Jong Won [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2016-10-15

    The preliminary decommissioning plan should be written with various chapters such as a radiological characterization, a decommissioning strategy and methods, a design for decommissioning usability, a safety evaluation, decontamination and dismantling activities, radioactive waste management, an environmental effect evaluation, and fire protection. The process requirements of the decommissioning project and the technical requirements and technical criteria should comply with regulatory requirements when dismantling of a nuclear facility. The requirements related to safety in the dismantling of a nuclear facility refer to the IAEA safety serious. The present paper indicates that a decommissioning design and plan, dismantling activities, and a decommissioning project will be influenced by the decommissioning regulatory requirements when dismantling of a nuclear facility. We hereby paved the way to find the effect of the regulatory requirements on the decommissioning of a whole area from the decommissioning strategy to the radioactive waste treatment when dismantling a nuclear facility. The decommissioning requirements have a unique feature in terms of a horizontal relationship as well as a vertical relationship from the regulation requirements to the decommissioning technical requirements. The decommissioning requirements management will be conducted through research that can recognize a multiple relationship in the next stage.

  14. Study on scenario evaluation methodology for decommissioning nuclear facilities using fuzzy logic

    International Nuclear Information System (INIS)

    Matsuhashi, Kazuya; Yanagihara, Satoshi

    2015-01-01

    Since there are many scenarios of the process from start to completion of a decommissioning project, it is important to study scenarios of decommissioning by evaluating such properties as safety, cost, and technology. An optimum scenario with the highest feasibility in accordance with the facility and environmental conditions should be selected on the basis of the results of the study. For analyzing a scenario of decommissioning, we prepared structured work packages by using the work breakdown structures (WBS) method together with qualitative evaluation of the technologies being applied to work packages located at the bottom (the third level) of the WBS. A calculation model was constructed to evaluate the feasibility of a scenario where fuzzy logic is applied to derive a score of technology performance and TOPSIS is applied for getting a feasibility grade of the scenario from technical performance scoring. As a case study, the model was applied to the debris removal scenario of Fukushima Daiichi Nuclear Power Plant to confirm its applicability. Two scenarios, underwater and in-air debris removal cases, were characterized by extracting the work packages with the lowest feasibility and by obtaining total average scores of the scenarios. It is confirmed that the methodology developed is useful for the scenario evaluation of decommissioning nuclear facilities. (author)

  15. Development of simplified decommissioning cost estimation code for nuclear facilities

    International Nuclear Information System (INIS)

    Tachibana, Mitsuo; Shiraishi, Kunio; Ishigami, Tsutomu

    2010-01-01

    The simplified decommissioning cost estimation code for nuclear facilities (DECOST code) was developed in consideration of features and structures of nuclear facilities and similarity of dismantling methods. The DECOST code could calculate 8 evaluation items of decommissioning cost. Actual dismantling in the Japan Atomic Energy Agency (JAEA) was evaluated; unit conversion factors used to calculate the manpower of dismantling activities were evaluated. Consequently, unit conversion factors of general components could be classified into three kinds. Weights of components and structures of the facility were necessary for calculation of manpower. Methods for evaluating weights of components and structures of the facility were studied. Consequently, the weight of components in the facility was proportional to the weight of structures of the facility. The weight of structures of the facility was proportional to the total area of floors in the facility. Decommissioning costs of 7 nuclear facilities in the JAEA were calculated by using the DECOST code. To verify the calculated results, the calculated manpower was compared with the manpower gained from actual dismantling. Consequently, the calculated manpower and actual manpower were almost equal. The outline of the DECOST code, evaluation results of unit conversion factors, the evaluation method of the weights of components and structures of the facility are described in this report. (author)

  16. U.S. nuclear plant decommissioning funding adequacy - by individual funds, utilities, reactors, and industry-wide - assessed by Monte Carlo and baseline trend methods: 1998, 2000, 2001, and 2004

    International Nuclear Information System (INIS)

    Williams, Daniel G.

    2007-01-01

    This paper assesses, over years 1998, 2000, 2001, and 2004 - using varying sets of assumption values - the adequacy of decommissioning funding (year-end) for United States' nuclear electric power plants. I assess each of the 222 individual trust funds and 99 utility owners (as of August 2003), as well as each of the 122 reactors, and industry-wide. Individual trust fund results are the most important because, in general, dollars may not be transferred from one fund to another to strengthen a less-adequately financed fund. Using stochastic (Monte Carlo) analysis (20,000 iterations) to incorporate risk, or uncertainty, in my simulation modeling, I assess funding adequacy for 2004, but with estimated balances and contributions data for 2004. The paper also assesses the baseline (most likely) trends in funding adequacy, using 'point' estimates for years 1998, 2000, 2001, and stochastic medians for 2004. I compute two measures of funding adequacy relative to two respective benchmark levels: (1) adequacy of 'current year' fund balances; and (2), adequacy of 'recent-year' fund contributions. The former is a more 'looking-backward' measure relative to a benchmark (i.e., current balance embodies all past year contributions and rates of return on fund assets); the latter, more 'looking-forward' relative to a forward benchmark. I use decommissioning fund balances data for 2000 and 1998, as reported by the utilities to the U.S. Nuclear Regulatory Commission (NRC), as well as additional balances, yearly contributions, rates of return, and cost escalation data over 1997-2001 obtained in a 2002 survey of owners by the U.S. Government Accountability Office (GAO). The most fundamental conclusion that one should draw from my simulation modeling results - whether using Monte Carlo or baseline trend analysis - is that these decommissioning adequacy percentages for the 222 funds are extremely variable, although a sizable majority of funds are likely above benchmark. Reduced variability

  17. Technology, safety and costs of decommissioning reference nuclear fuel cycle facilities

    International Nuclear Information System (INIS)

    Elder, H.K.

    1986-05-01

    The radioactive wastes expected to result from decommissioning nuclear fuel cycle facilities are reviewed and classified in accordance with 10 CFR 61. Most of the wastes from the MOX plant (exclusive of the lagoon wastes) will require interim storage (11% Class A 49 m 3 ; 89% interim storage, 383 m 3 ). The MOX plant lagoon wastes are Class A waste (2930 m 3 ). All of the wastes from the U-Fab and UF 6 plants are designated as Class A waste (U-Fab 1090 m 3 , UF 6 1259 m 3 )

  18. Policies and Strategies for the Decommissioning of Nuclear and Radiological Facilities

    International Nuclear Information System (INIS)

    2011-01-01

    This publication presents the main elements of policies and strategies for decommissioning activities of nuclear and radiological facilities. It is intended to help in facilitating proper and systematic planning, and safe, timely and cost effective implementation of all decommissioning activities. The policy establishes the principles for decommissioning and the strategy contains the approaches for the implementation of the policy. The publication will be a useful guide for strategic planners, waste managers, operators of facilities under decommissioning, regulators and other stakeholders.

  19. Elecnuc. Nuclear power plants worldwide

    International Nuclear Information System (INIS)

    1998-01-01

    This small folder presents a digest of some useful information concerning the nuclear power plants worldwide and the situation of nuclear industry at the end of 1997: power production of nuclear origin, distribution of reactor types, number of installed units, evolution and prediction of reactor orders, connections to the grid and decommissioning, worldwide development of nuclear power, evolution of power production of nuclear origin, the installed power per reactor type, market shares and exports of the main nuclear engineering companies, power plants constructions and orders situation, evolution of reactors performances during the last 10 years, know-how and development of nuclear safety, the remarkable facts of 1997, the future of nuclear power and the energy policy trends. (J.S.)

  20. 3D based integrated support concept for improving safety and cost-efficiency of nuclear decommissioning projects

    International Nuclear Information System (INIS)

    Szoeke, Istvan

    2016-01-01

    New concepts enabled by emerging computing technologies based on 3D simulation, virtual (VR) and augmented reality (AR), advanced user interfaces (UI), mobile and wearable computing devices, and geographical information systems have great potential for improving nuclear decommissioning strategies. Such techniques offer very effective new opportunities for improving early characterisation and strategical decision making, knowledge management, on-site management of radiological waste, and regulatory compliance. In addition, such methods allow for an effective training of foreseen decommissioning workers to begin during operation and transition phase without disturbance to normal operation of the plant. Improved plant information systems enabled by 3D simulation, advanced user interface, and mobile computing technologies, offer better ways for acquiring and managing the radiological and other plant information that are required for informed decision making in the early planning phase of decommissioning activities. User friendly, realistic management and visualisation of available radiological information, and results of radiological data analyses, allows decision makers to have a better understanding of the radiological conditions expected when decontamination and dismantling work starts, without high need for physical presence in the environment. Such functionalities, combined with capabilities for easy evaluation of possible decommissioning (decontamination, dismantling) options allow decision makers to make informed decisions, and enable a seamless communication (common language) within a multidisciplinary decommissioning planning team. Support systems, enabled by modern information technologies are expected to improve information and knowledge management in decommissioning projects, especially during transition from the operation phase. Traditionally, inefficient transfer of knowledge from the design and operation phase, results in suboptimal work strategies and

  1. Site release in the decommissioning of nuclear installations

    International Nuclear Information System (INIS)

    Revilla, Jose Luis; Sanz, Maria Teresa; Marugan, Inmaculada; Simon, Inmaculada; Martin, Manuel; Solis, Susana; Sterling, Agustina

    2008-01-01

    Spanish regulatory framework for the decommissioning process of a nuclear facility ends up with a decommission statement, which releases the licence-holder of the facility from its responsibilities as an operator. It also establishes -where a restricted site release applies- the appropriate future use restrictions, and the responsible of both maintaining such restrictions and ensuring their compliance. Releasing a site implies eliminating all radiological monitoring. The Regulations, however, did not specify either the radiological conditions to be met for the site to be released, or the possibility of a partial release -with or without restrictions-. In case of restricted site release, the Regulations did not specify either the required criteria for such a release. This paper presents the main features of the Safety Instruction IS-13 'Radiological criteria for the release of nuclear facilities sites' issued recently by the Spanish Nuclear Safety Council as a new specific regulation. This Safety Instruction establishes the requirements and conditions for the release of nuclear facility sites, that is, radiological criteria on the effective dose to the public, partial release of nuclear facility sites and restricted release of nuclear facility sites. (author).

  2. Investigation of the responsibility for decommissioning of the Ranstad plant; Utredning av ansvaret foer Ranstadsverkets avveckling

    Energy Technology Data Exchange (ETDEWEB)

    Svensson, Haakan; Grundfelt, Bertil [Kemakta Konsult AB, Stockholm (Sweden); Froeberg, Magnus [Froeberg och Lundholm Advokatbyraa AB, Stockholm (Sweden)

    2010-11-15

    The issue of decommissioning, including demolition, of the nuclear facility at the Ranstad plant was raised gradually during 2006-2008. It was then found that it was unclear which company or companies that could be responsible for this decommissioning, economically as well as for the implementation. During this time and until the end of 2009, the concerned authorities, notably Swedish Nuclear Power Inspectorate and SSM, collected a large amount of facts as a basis for assessing liability. This material now needed to be systematized and compiled in order to effectively be utilized in such an assessment. SSM also thought that it would be helpful if an independent party with experience in similar issues could contribute to the interpretation of the legal situation. These were the given conditions of the mission which Kemakta Konsult AB, with the assistance of lawyer Magnus Froeberg, were given by SSM in the autumn of 2009. The results are presented in this final report.

  3. Development of a Preliminary Decommissioning Plan Following the International Structure for Decommissioning Costing (ISDC) of Nuclear Installations - 13361

    International Nuclear Information System (INIS)

    Moshonas Cole, Katherine; Dinner, Julia; Grey, Mike; Daniska, Vladimir

    2013-01-01

    The International Structure for Decommissioning Costing (ISDC) of Nuclear Installations, published by OECD/NEA, IAEA and EC is intended to provide a uniform list of cost items for decommissioning projects and provides a standard format that permits international cost estimates to be compared. Candesco and DECOM have used the ISDC format along with two costing codes, OMEGA and ISDCEX, developed from the ISDC by DECOM, in three projects: the development of a preliminary decommissioning plan for a multi-unit CANDU nuclear power station, updating the preliminary decommissioning cost estimates for a prototype CANDU nuclear power station and benchmarking the cost estimates for CANDU against the cost estimates for other reactor types. It was found that the ISDC format provides a well defined and transparent basis for decommissioning planning and cost estimating that assists in identifying gaps and weaknesses and facilitates the benchmarking against international experience. The use of the ISDC can also help build stakeholder confidence in the reliability of the plans and estimates and the adequacy of decommissioning funding. (authors)

  4. Nuclear decommissioning trusts: A case for convertible bonds

    International Nuclear Information System (INIS)

    Nichols, R.W.

    1992-01-01

    Asset-liability management is studied with special emphasis on application of the author's findings to the management of nuclear decommissioning trusts (NDTs). The trust themselves are investment vehicles established to accumulate and build funds to be used to defray future decommissioning costs. Decommissioning, in turn, is the process of dismantling the shell of a nuclear reactor and the surrounding concrete structures, followed by disposal of the radioactive material, the objective being to return the site to a greenfield state i.e. the site is freed up for unrestricted use. Unfortunately, the assets of NDTs are not so easily managed. The liability that the trusts have been established to fund is a highly uncertain moving target for which little historical data is available. This study first develops a framework for selecting portfolios when the investment objective is to invest against a future liability. The challenge then is to build an investment strategy around an uncertain liability, in the presence of taxes and miscellaneous portfolio constraints. The study then explores the viability of convertible bonds for liability-driven investment strategies because of the hybrid debt/equity nature of these instruments

  5. Decommissioning plan of the nuclear-powered ship 'Mutsu'

    International Nuclear Information System (INIS)

    1992-01-01

    The nuclear-powered ship 'Mutsu' is to be decommissioned at Sekinehama Port immediately after finishing the experimental voyage based on the 'Fundamental plan on the research required for the development of nuclear ships in Japan Atomic Energy Research Institute' decided in March, 1985. The decommissioning plan which determines the methods of the works regarding the decommissioning and others is as follows. In order to utilize the ship hull of Mutsu, the reactor room including the reactor and shielding is removed in a lump, and the removal and isolation method of preserving it as it is on land is adopted. The measures for environment preservation and ensuring the safety of residents are taken, and the sufficient work control is carried out for preventing accidents and reducing the radiation exposure of workers. The ship is used as the ship with ordinary propulsion system for ocean research and the research and development of marine reactors. The utilization of Sekinehama and Ominato facilities is investigated. The reactor room removed from Mutsu is exhibited to public, being preserved safely in a building. (K.I.)

  6. The potential benefits and drawbacks of deferring the decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Nash, R.; Pomfret, D.G.

    2000-01-01

    The need to decommission redundant plants or sites at the end of operations is accepted throughout the industry, by the timing of such work requires careful consideration. In a world where political issues dominate, safety and business drivers are often only two of the inputs, and it is therefore imperative that industry is clear in its understanding of the different drivers that affect this issue. Issues are; 1. The formal positions adopted by governments and regulators are often directed at specifically to water reactors. Should other types of facilities be constrained by the same policies? 2. Political drivers can be dominated by short to medium term considerations. Can we encourage long term strategic planning, and ? 3. The failings of the industry (especially accidents) and fear of nuclear weapons can often dominate public perception. Can industry counter these adverse associations? The key benefits relate to better risk management (especially if the radiological inventory was minimised at plant closure). Extending the decommissioning programme does allow dose reductions to take place, especially if short-lived isotopes are involved. Other benefits include more time is allowed for optioneering and planning of the decommissioning processes. This time frame also gives opportunity to develop new or better technologies. With proper control, political strategies can be developed and financial planning can take place. The concern of 'Will there be enough money to fund decommissioning' can become 'A little funding set aside early, and properly managed, can pay for decommissioning in the future'. Savings in dose, impact on the environment, and money can be achieved through a well-managed deferred programme. An extended programme of decommissioning demands the political will and the infrastructure to remain in place over a long period. Tied in to this is the need to keep money available for a long time, and to be able to retain and recover the relevant knowledge

  7. Development of decommissioning technology for nuclear fuel facility

    International Nuclear Information System (INIS)

    Tanimoto, Ken-ichi

    1998-01-01

    There are many kinds of objects for decommissioning and their properties are greatly different in respects of morphology, constituent materials, contamination history, etc. Therefore, the techniques for decontamination and dismantlement are required to have a great applicability. In addition, most of contamination nuclides have long half-life and so, it is desirable to rapidly take measures to stop or close a contaminated facility. In consideration of these characteristics developments of elementary techniques for decontamination have been attempted. This report summarized the present states of decommissioning technology for nuclear fuel facility. The function and performance of each elementary technique were examined through test operation and simulation was made for the important techniques of them aiming at generalization and optimization. For remote handling technology, two operation tools; 'metal splitting saw cutting tool' and 'plasma cutting tool' were produced and utilizations of these tools in combination with a robot for conveyance are under investigation now. (M.N.)

  8. International Experts' Meeting on Decommissioning and Remediation after a Nuclear Accident. Presentations

    International Nuclear Information System (INIS)

    2013-01-01

    Against the backdrop of the accident at TEPCO's Fukushima Daiichi nuclear power plant in March 2011, the Director General of the International Atomic Energy Agency (IAEA) convened the IAEA Ministerial Conference on Nuclear Safety in Vienna, Austria, in June 2011. The Conference adopted a Ministerial Declaration which, inter alia, requested the Director General to prepare a draft Action Plan covering all the relevant aspects relating to nuclear safety, emergency preparedness and response, and radiation protection of people and the environment, as well as the relevant international legal framework. On 22 September 2011, the IAEA General Conference unanimously endorsed the draft IAEA Action Plan on Nuclear Safety approved by the Board of Governors. The Action Plan sets out a comprehensive programme of work, in 12 major areas, to strengthen nuclear safety worldwide. Under one of these areas, headed 'Enhance transparency and effectiveness of communication and improve dissemination of information', the IAEA Secretariat was requested to organize an International Experts' Meeting (IEM) on decommissioning, cleanup and remediation of nuclear facilities and contaminated lands after a nuclear accident. This IEM was organized in response to that request. The IEM focussed on the complex technical, societal, environmental and economic issues that need to be considered for decommissioning and remediation activities after a nuclear accident, specifically after the emergency exposure situation of an accident has been declared ended. The objective of the IEM is to assist Member States to prepare for and to be able to manage the consequences resulting from a nuclear accident. The meeting highlighted the specific short term and long term issues that may need to be addressed during decommissioning of facilities and remediation of the off-site environment affected by a nuclear accident. It is of interest to a wide range of experts, such as decision makers, regulators, operators

  9. Approaches to 'eternal' accompaniment regalement of nuclear energy installation decommissioning

    International Nuclear Information System (INIS)

    Dryapachenko, Ihor; Trofimova, Nina

    2003-01-01

    The stunning rate of events after striking the push button AZ5 in April 26, 1986 while that only rises. Boundless even for the super-power world states the complex of scientific, technological, organizational, economical and social problems became in 1991 unique property of Ukraine. It has added to the operational power reactors (now 13) at practical absence of an infrastructure of a closed fuel cycle. At the same time Ukrainian economics always' will depend on nuclear power engineering. In it are very much positive aspect concerning high technological and scientifically based contents and future non-alternative of the nuclear power industry on a global scale. The errors in an estimation of separate links of such composite model are not killed mutually, but only add. Uncertainty in estimations of natural or public processes will cause to large uncertainty of general forecast. A laborious transaction of the rules production or the legitimated algorithms of the activity realization reach the foreseen controllability. On our view the following logical thesis of such concept should be comprehension that the rules of decommissioning of a nuclear-power plant should provide the controllability with matched activities not one generation of performers. The impressive achievements of scientific-technological revolution of last decades are accompanied 'non-regalement' from the point of view of life on a planet by disastrous effects. The nuclear technologies overtake in this sense with that feature, that the 'half-life' periods of these consequences often much more large than the whole written history of mankind. The most distant consequences of the long-term processing with radioactive materials bound on our view with the human factor. If for 30-100 years beforehand it is possible to count destiny of radiological contamination or green meadows but to provide behavior of the people or society, as a whole is high-gravity even per annum forward. Objectivity of laws of history

  10. Progress and experiences from the decommissioning of the Eurochemic reprocessing plant

    International Nuclear Information System (INIS)

    Gills, R.; Lewandowski, P.; Ooms, B.; Reusen, N.; Van Laer, W.; Walthery, R.

    2007-01-01

    Belgoprocess started the industrial decommissioning of the main process building of the former EUROCHEMIC reprocessing plant in 1990, after completion of a pilot project in which two buildings were emptied and decontaminated to background levels. The remaining structures were demolished and the concrete debris was disposed of as industrial waste and green field conditions restored. The Eurochemic reprocessing plant operated from 1966 to 1974 to process fuel from power reactors and research reactors. The main building is a large concrete structure, comprising a surface area of 55,000 m 2 , concrete volume 12,500 m 3 , and 1,500 Mg of metal components. The building is divided into multiple cells. About 106 individual cell structures have to be dismantled, involving the removal and decontamination of equipment from each cell, the decontamination of the cell walls, ceilings and floors, the dismantling of the ventilation system. Most of the work involves hands-on operations under protective clothing tailored to each specific task. Tool automation and automatic positioning systems are successfully applied. In view of the final demolition of the main process building, the main process building is divided into three parts - each part is isolated from the others. In the middle of 2008, after the removal of the NDA-IPAN/GEA installation, the eastern part will be demolished. The paper presents a status overview of the decommissioning and decontamination activities at the main process building of the former Eurochemic reprocessing plant on the nuclear site of Dessel in Belgium. The specific BELGOPROCESS approach will be highlighted, in which the decommissioning activities are carried out on an industrial scale with special emphasis on cost minimisation, the use of technology on an industrial representative scale and the specific alpha contamination of equipment and building surfaces, requiring that the decommissioning work is done with adequate protective clothing. Also

  11. Progress and experiences from the decommissioning of the Eurochemic reprocessing plant - 16022

    International Nuclear Information System (INIS)

    Walthery, Robert; Lewandowski, Patrick; Ooms, Bart; Reusen, Nancy; Van Laer, Wim

    2009-01-01

    Belgoprocess started the industrial decommissioning of the main process building of the former EUROCHEMIC reprocessing plant in 1990, after completion of a pilot project in which two buildings were emptied and decontaminated to background levels. The remaining structures were demolished and the concrete debris was disposed of as industrial waste and green field conditions restored. The Eurochemic reprocessing plant operated from 1966 to 1974 to process fuel from power reactors and research reactors. The main building is a large concrete structure, comprising a surface area of 55,000 m 2 , concrete volume 12,500 m 3 , and 1,500 Mg of metal components. The building is divided into multiple cells. About 106 individual cell structures have to be dismantled, involving the removal and decontamination of equipment from each cell, the decontamination of the cell walls, ceilings and floors, the dismantling of the ventilation system. Most of the work involves hands-on operations under protective clothing tailored to each specific task. Tool automation and automatic positioning systems are successfully applied. In view of the final demolition of the main process building, the main process building has been divided into three parts - each part is isolated from the others. In September 2008 the eastern part of the building has been demolished. The paper presents a status overview of the decommissioning and decontamination activities at the main process building of the former Eurochemic reprocessing plant on the nuclear site of Dessel in Belgium. The specific BELGOPROCESS strategy will be highlighted, in which the decommissioning activities are carried out on an industrial scale with special emphasis on cost minimisation, the use of technology on an industrial representative scale and the specific alpha contamination of equipment and building surfaces, requiring that the decommissioning work is done with adequate protective clothing. Also specific breathing and cooling air

  12. CONSIDERATIONS FOR THE DEVELOPMENT OF A DEVICE FORTHE DECOMMISSIONING OF THE FUEL CHANNELS IN THECANDU NUCLEAR REACTOR

    Directory of Open Access Journals (Sweden)

    Gabi ROSCA FARTAT

    2013-05-01

    Full Text Available As many nuclear power plants are reaching their end of lifecycle, the decommissioning of theseinstallations has become one of the 21stcentury’s great challenges. Each project may be managed differently,depending on the country, development policies, financial considerations, and the availability of qualifiedengineers or specialized companies to handle such projects. The principle objective of decommissioning is toplace a facility into such a condition that there is no unacceptable risk from the decommissioned facility topublic health and safety of the environment. In order to ensure that at the end of its life the risk from a facility iswithin acceptable bounds, action is normally required. The overall decommissioning strategy is todeliver a timely, cost-effective program while maintaining high standards of safety, security and environmentalprotection. If facilities were not decommissioned, they could degrade and potentially present an environmentalradiological hazard in the future. Simply abandoning or leaving a facility after ceasing operations is notconsidered to be an acceptable alternative to decommissioning. The final aim of decommissioning is torecover the geographic site to its original condition.

  13. Nuclear power plants - Quality assurance

    International Nuclear Information System (INIS)

    1980-01-01

    This International Standard defines principles for the establishment and implementation of quality assurance programmes during all phases of design, procurement, fabrication, construction, commissioning, operation, maintenance and decommissioning of structures, systems and components of nuclear power plants. These principles apply to activities affecting the quality of items, such as designing, purchasing, fabricating, handling, shipping, storing, cleaning, erecting, installing, testing, commissioning, operating, inspecting, maintaining, repairing, refuelling and modifying and eventually decommissioning. The manner in which the principles described in this document will be implemented in different organizations involved in a specific nuclear power project will depend on regulatory and contractual requirements, the form of management applied to a nuclear power project, and the nature and scope of the work to be performed by different organizations

  14. Approaches of Knowledge Management System for the Decommissioning of Nuclear Facilities

    International Nuclear Information System (INIS)

    Iguchi, Y.; Yanagihara, S.; Kato, Y.; Tezuka, M.; Koda, Y.

    2016-01-01

    Full text: The decommissioning of a nuclear facility is a long term project, handling information beginning with design, construction and operation. Moreover, the decommissioning project is likely to be extended because of the lack of the waste disposal site. In this situation, as the transfer of knowledge to the next generation is a crucial issue, approaches of knowledge management (KM) are necessary. For this purpose, the total system of decommissioning knowledge management system (KMS) is proposed. In this system, we should arrange, organize and systematize the data and information of the plant design, maintenance history, trouble events, waste management records etc. The collected data, information and records should be organized by computer support systems. It becomes a base of the explicit knowledge. Moreover, measures of extracting tacit knowledge from retiring employees are necessary. The experience of the retirees should be documented as much as possible through effective questionnaire or interview process. In this way, various KM approaches become an integrated KMS as a whole. The system should be used for daily accumulation of knowledge thorough the planning, implementation and evaluation of decommissioning activities and it will contribute to the transfer of knowledge. (author

  15. Operations quality assurance for nuclear power plants

    International Nuclear Information System (INIS)

    1987-01-01

    This standard covers the quality assurance of all activities concerned with the operation and maintenance of plant equipment and systems in CANDU-based nuclear power plants during the operations phase, the period between the completion of commissioning and the start of decommissioning

  16. Prioritisation process for decommissioning of the Iraq former nuclear complex

    International Nuclear Information System (INIS)

    Jarjies, Adnan; Abbas, Mohammed; Fernandes, Horst M.; Coates, Roger

    2008-01-01

    There are a number of sites in Iraq which have been used for nuclear activities and which contain