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Sample records for decommissioning cost analysis

  1. An analysis of decommissioning costs

    International Nuclear Information System (INIS)

    Teunckens, L.; Loeschhorn, U.; Yanagihara, S.; Wren, G.; Menon, S.

    1992-01-01

    Within the OECD/NEA Cooperative Programme on Decommissioning a Task Group was set up early in 1989 to identify the reasons for the large variations in decommissioning cost estimates. The Task Group gathered cost data from 12 of the 14 projects in the Programme to form the basis of their analysis. They included reactors being decommissioned to various stages as well as fuel cycle facilities. The projects were divided into groups of projects with similar characteristics ('models') to facilitate the analysis of the cost distribution in each group of projects and the cost data was progressively refined by a dialogue between the Task Group and the project managers. A comparative analysis was then performed and project specific discrepancies were identified. The Task Group's report is summarized on the results of the comparative analysis as well as the lessons learnt by the Task Group in the acquisition and analysis of cost data from international decommissioning projects. (author) 5 tabs

  2. Decommissioning Unit Cost Data

    International Nuclear Information System (INIS)

    Sanford, P. C.; Stevens, J. L.; Brandt, R.

    2002-01-01

    The Rocky Flats Closure Site (Site) is in the process of stabilizing residual nuclear materials, decommissioning nuclear facilities, and remediating environmental media. A number of contaminated facilities have been decommissioned, including one building, Building 779, that contained gloveboxes used for plutonium process development but did little actual plutonium processing. The actual costs incurred to decommission this facility formed much of the basis or standards used to estimate the decommissioning of the remaining plutonium-processing buildings. Recent decommissioning activities in the first actual production facility, Building 771, implemented a number of process and procedural improvements. These include methods for handling plutonium contaminated equipment, including size reduction, decontamination, and waste packaging, as well as management improvements to streamline planning and work control. These improvements resulted in a safer working environment and reduced project cost, as demonstrated in the overall project efficiency. The topic of this paper is the analysis of how this improved efficiency is reflected in recent unit costs for activities specific to the decommissioning of plutonium facilities. This analysis will allow the Site to quantify the impacts on future Rocky Flats decommissioning activities, and to develop data for planning and cost estimating the decommissioning of future facilities. The paper discusses the methods used to collect and arrange the project data from the individual work areas within Building 771. Regression and data correlation techniques were used to quantify values for different types of decommissioning activities. The discussion includes the approach to identify and allocate overall project support, waste management, and Site support costs based on the overall Site and project costs to provide a ''burdened'' unit cost. The paper ultimately provides a unit cost basis that can be used to support cost estimates for

  3. DECOST: computer routine for decommissioning cost and funding analysis

    International Nuclear Information System (INIS)

    Mingst, B.C.

    1979-12-01

    One of the major controversies surrounding the decommissioning of nuclear facilities is the lack of financial information on just what the eventual costs will be. The Nuclear Regulatory Commission has studies underway to analyze the costs of decommissioning of nuclear fuel cycle facilities and some other similar studies have also been done by other groups. These studies all deal only with the final cost outlays needed to finance decommissioning in an unchangeable set of circumstances. Funding methods and planning to reduce the costs and financial risks are usually not attempted. The DECOST program package is intended to fill this void and allow wide-ranging study of the various options available when planning for the decommissioning of nuclear facilities

  4. Aagesta-BR3 Decommissioning Cost. Comparison and Benchmarking Analysis

    International Nuclear Information System (INIS)

    Varley, Geoff

    2002-11-01

    equipment. The BR3 work packages described in this report add up to something like 83,000 labour hours plus about MSEK 13 of investments and consumables costs. At Swedish average team labour rates 83,000 hours would equate to about MSEK 52. Adding the investment cost of MSEK 13 gives a total of about MSEK 65. This of course is quite close to the Aagesta figure but it would be wrong to draw immediate, firm conclusions based on these data. Such a comparison should take into account, inter alia: The number and relative sizes of the equipment decontaminated and dismantled at Aagesta and BR3. The assumed productivity in the Aagesta estimate compared to the actual BR3 figures. The physical scale of the Aagesta reactor is somewhat larger than the BR3 reactor, so all other things being equal, one might expect the Aagesta decommissioning cost estimate to be higher than for BR3. Aagesta has better access overall, which should help to constrain costs. The productivity ratio for workers at BR3 on average was high - generally 80 per cent or more, so this is unlikely to be exceeded at Aagesta and might not be equalled, which would tend to push the Aagesta cost up relative to the BR3 situation. There is an additional question of the possible extra work performed at BR3 due to the R and D nature of the project. The BR3 data analysed has tried to strip away any such 'extra' work but nevertheless there may be some residual effect on the final numbers. Analysis and comparison of individual work packages has raised several conclusions, as follows: The constructed cost for Aagesta using BR3 benchmark data is encouragingly close to the Aagesta estimate value but it is not clear that the way of deriving the Aagesta estimate for decontamination was entirely rigorous. The reliability of the Aagesta estimate on these grounds therefore might reasonably be questioned. A significant discrepancy between the BR3 and Aagesta cases appears to exist in respect of the volumes of waste arising from the

  5. Aagesta-BR3 Decommissioning Cost. Comparison and Benchmarking Analysis

    Energy Technology Data Exchange (ETDEWEB)

    Varley, Geoff [NAC International, Henley on Thames (United Kingdom)

    2002-11-01

    25 is equipment. The BR3 work packages described in this report add up to something like 83,000 labour hours plus about MSEK 13 of investments and consumables costs. At Swedish average team labour rates 83,000 hours would equate to about MSEK 52. Adding the investment cost of MSEK 13 gives a total of about MSEK 65. This of course is quite close to the Aagesta figure but it would be wrong to draw immediate, firm conclusions based on these data. Such a comparison should take into account, inter alia: The number and relative sizes of the equipment decontaminated and dismantled at Aagesta and BR3. The assumed productivity in the Aagesta estimate compared to the actual BR3 figures. The physical scale of the Aagesta reactor is somewhat larger than the BR3 reactor, so all other things being equal, one might expect the Aagesta decommissioning cost estimate to be higher than for BR3. Aagesta has better access overall, which should help to constrain costs. The productivity ratio for workers at BR3 on average was high - generally 80 per cent or more, so this is unlikely to be exceeded at Aagesta and might not be equalled, which would tend to push the Aagesta cost up relative to the BR3 situation. There is an additional question of the possible extra work performed at BR3 due to the R and D nature of the project. The BR3 data analysed has tried to strip away any such 'extra' work but nevertheless there may be some residual effect on the final numbers. Analysis and comparison of individual work packages has raised several conclusions, as follows: The constructed cost for Aagesta using BR3 benchmark data is encouragingly close to the Aagesta estimate value but it is not clear that the way of deriving the Aagesta estimate for decontamination was entirely rigorous. The reliability of the Aagesta estimate on these grounds therefore might reasonably be questioned. A significant discrepancy between the BR3 and Aagesta cases appears to exist in respect of the volumes of waste

  6. Trojan Decommissioning Project Cost Performance

    International Nuclear Information System (INIS)

    Michael B. Lackey

    2000-01-01

    The Trojan nuclear plant (Trojan) was an 1160-MW(electric) four-loop pressurized water reactor located in Rainier, Oregon. The plant was permanently shut down in 1993 after ∼17 yr of commercial operation. The early plant closure was an economic decision. The key factors in the closure analysis were escalation of inspection and repair costs associated with steam generator tube cracking and the projected availability of inexpensive replacement power in the Pacific Northwest region of the United States. Since the plant closure, Portland General Electric (PGE) has been actively engaged in decommissioning. The Trojan Decommissioning Project currently has a forecast at completion of $429.7 million (all costs are in millions of 1997 dollars, unless otherwise noted). The cost performance of the Trojan Decommissioning Project to date is addressed, as well as the tools that are in place to provide cost control through completion of decommissioning

  7. Financial aspects of decommissioning (key aspects of decommissioning costing)

    International Nuclear Information System (INIS)

    Danska, V.

    2009-01-01

    In this presentation the following aspects of NPPs decommissioning are discussed: Requirements and purpose of decommissioning costing; Decommissioning costing methodologies; Standardised decommissioning cost structure; Input data for cost estimate process; Waste management in cost estimate process; Grading aspects in cost estimating; Cost control in decommissioning projects; Summary of the cost estimation process; Conclusions and recommendations.

  8. Platform decommissioning costs

    International Nuclear Information System (INIS)

    Rodger, David

    1998-01-01

    There are over 6500 platforms worldwide contributing to the offshore oil and gas production industry. In the North Sea there are around 500 platforms in place. There are many factors to be considered in planning for platform decommissioning and the evaluation of options for removal and disposal. The environmental impact, technical feasibility, safety and cost factors all have to be considered. This presentation considers what information is available about the overall decommissioning costs for the North Sea and the costs of different removal and disposal options for individual platforms. 2 figs., 1 tab

  9. An analysis of decommissioning costs for the AFRRI TRIGA reactor facility

    International Nuclear Information System (INIS)

    Forsbacka, Matt

    1990-01-01

    A decommissioning cost analysis for the AFRRI TRIGA Reactor Facility was made. AFRRI is not at this time suggesting that the AFRRI TRIGA Reactor Facility be decommissioned. This report was prepared to be in compliance with paragraph 50.33 of Title 10, Code of Federal Regulations which requires the assurance of availability of future decommissioning funding. The planned method of decommissioning is the immediate decontamination of the AFRRI TRIGA Reactor site to allow for restoration of the site to full public access - this is called DECON. The cost of DECON for the AFRRI TRIGA Reactor Facility in 1990 dollars is estimated to be $3,200,000. The anticipated ancillary costs of facility site demobilization and spent fuel shipment is an additional $600,000. Thus the total cost of terminating reactor operations at AFRRI will be about $3,800,000. The primary basis for this cost estimate is a study of the decommissioning costs of a similar reactor facility that was performed by Battelle Pacific Northwest Laboratory (PNL) as provided in USNRC publication NUREG/CR-1756. The data in this study were adapted to reflect the decommissioning requirements of the AFRRI TRIGA. (author)

  10. Engineering Evaluation/Cost Analysis for Decommissioning of the Engineering Test Reactor Complex

    Energy Technology Data Exchange (ETDEWEB)

    A. B. Culp

    2006-10-01

    Preparation of this Engineering Evaluation/Cost Analysis is consistent with the joint U.S. Department of Energy and U.S. Environmental Protection Agency Policy on Decommissioning of Department of Energy Facilities Under the Comprehensive Environmental Response, Compensation, and Liability Act, which establishes the Comprehensive Environmental Response, Compensation, and Liability Act non-time-critical removal action (NTCRA) process as an approach for decommissioning.

  11. Engineering Evaluation/Cost Analysis for Decommissioning of the Engineering Test Reactor Complex

    International Nuclear Information System (INIS)

    A. B. Culp

    2006-01-01

    Preparation of this Engineering Evaluation/Cost Analysis is consistent with the joint U.S. Department of Energy and U.S. Environmental Protection Agency Policy on Decommissioning of Department of Energy Facilities Under the Comprehensive Environmental Response, Compensation, and Liability Act, which establishes the Comprehensive Environmental Response, Compensation, and Liability Act non-time-critical removal action (NTCRA) process as an approach for decommissioning

  12. Cost estimation for decommissioning of research reactors

    International Nuclear Information System (INIS)

    Grossi, Pablo Andrade; Tello, Cledola Cassia Oliveira de; Segabinaze, Roberto de Oliveira; Daniska, Vladimir

    2013-01-01

    In the case of research reactors, the limited data that is available tends to provide only overall decommissioning costs, without any breakdown of the main cost elements. In order to address this subject, it is important to collect and analyse all available data of decommissioning costs for the research reactors. The IAEA has started the DACCORD Project focused on data analysis and costing of research reactors decommissioning. Data collection is organized in accordance with the International Structure for Decommissioning Costing (ISDC), developed jointly by the IAEA, the OECD Nuclear Energy Agency and the European Commission. The specific aims of the project include the development of representative and comparative data and datasets for preliminary costing for decommissioning. This paper will focus on presenting a technique to consider several representative input data in accordance with the ISDC structure and using the CERREX (Cost Estimation for Research Reactors in Excel) software developed by IAEA. (author)

  13. Decommissioning Cost Assessment

    International Nuclear Information System (INIS)

    Labor, Bea

    2012-03-01

    The future costs for dismantling, decommissioning and handling of associated radioactive waste of nuclear installations represents substantial liabilities. It is the generations that benefits from the use of nuclear installations that shall carry the financial burden. Nuclear waste programmes have occasionally encountered set-backs related to the trust from society. This has resulted in delayed, redirected or halted activities, which has the common denominator of costs increases. In modern democratic countries, information sharing, knowledge transfer and open communication about costs for the management of radioactive waste are prerequisites for the task to develop modern methods for public participation and thus to develop well-founded and justified confidence for further development of nuclear energy. Nuclear and radiation safety Authorities have a clear role to provide unbiased information on any health, safety, financial and environmental related issues. This task requires a good understanding of the values and opinion of the public, and especially those of the younger generation

  14. Basic Research about Calculation of the Decommissioning Unit Cost based on The KRR-2 Decommissioning Project

    International Nuclear Information System (INIS)

    Song, Chan-Ho; Park, Hee-Seong; Ha, Jea-Hyun; Jin, Hyung-Gon; Park, Seung-Kook

    2015-01-01

    The KAERI be used to calculate the decommissioning cost and manage the data of decommissioning activity experience through systems such as the decommissioning information management system (DECOMMIS), Decommissioning Facility Characterization DB System (DEFACS), decommissioning work-unit productivity calculation system (DEWOCS). Some country such as Japan and The United States have the information for decommissioning experience of the NPP and publish reports on decommissioning cost analysis. These reports as valuable data be used to compare with the decommissioning unit cost. In particular, need a method to estimate the decommissioning cost of the NPP because there is no decommissioning experience of NPP in case of Korea. makes possible to predict the more precise prediction about the decommissioning unit cost. But still, there are many differences on calculation for the decommissioning unit cost in domestic and foreign country. Typically, it is difficult to compare with data because published not detailed reports. Therefore, field of estimation for decommissioning cost have to use a unified framework in order to the decommissioning cost be provided to exact of the decommissioning cost

  15. Basic Research about Calculation of the Decommissioning Unit Cost based on The KRR-2 Decommissioning Project

    Energy Technology Data Exchange (ETDEWEB)

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

    2015-05-15

    The KAERI be used to calculate the decommissioning cost and manage the data of decommissioning activity experience through systems such as the decommissioning information management system (DECOMMIS), Decommissioning Facility Characterization DB System (DEFACS), decommissioning work-unit productivity calculation system (DEWOCS). Some country such as Japan and The United States have the information for decommissioning experience of the NPP and publish reports on decommissioning cost analysis. These reports as valuable data be used to compare with the decommissioning unit cost. In particular, need a method to estimate the decommissioning cost of the NPP because there is no decommissioning experience of NPP in case of Korea. makes possible to predict the more precise prediction about the decommissioning unit cost. But still, there are many differences on calculation for the decommissioning unit cost in domestic and foreign country. Typically, it is difficult to compare with data because published not detailed reports. Therefore, field of estimation for decommissioning cost have to use a unified framework in order to the decommissioning cost be provided to exact of the decommissioning cost.

  16. Guideline to Estimate Decommissioning Costs

    Energy Technology Data Exchange (ETDEWEB)

    Yun, Taesik; Kim, Younggook; Oh, Jaeyoung [KHNP CRI, Daejeon (Korea, Republic of)

    2016-10-15

    The primary objective of this work is to provide guidelines to estimate the decommissioning cost as well as the stakeholders with plausible information to understand the decommissioning activities in a reasonable manner, which eventually contribute to acquiring the public acceptance for the nuclear power industry. Although several cases of the decommissioning cost estimate have been made for a few commercial nuclear power plants, the different technical, site-specific and economic assumptions used make it difficult to interpret those cost estimates and compare them with that of a relevant plant. Trustworthy cost estimates are crucial to plan a safe and economic decommissioning project. The typical approach is to break down the decommissioning project into a series of discrete and measurable work activities. Although plant specific differences derived from the economic and technical assumptions make a licensee difficult to estimate reliable decommissioning costs, estimating decommissioning costs is the most crucial processes since it encompasses all the spectrum of activities from the planning to the final evaluation on whether a decommissioning project has successfully been preceded from the perspective of safety and economic points. Hence, it is clear that tenacious efforts should be needed to successfully perform the decommissioning project.

  17. Approaches to estimating decommissioning costs

    International Nuclear Information System (INIS)

    Smith, R.I.

    1990-07-01

    The chronological development of methodology for estimating the cost of nuclear reactor power station decommissioning is traced from the mid-1970s through 1990. Three techniques for developing decommissioning cost estimates are described. The two viable techniques are compared by examining estimates developed for the same nuclear power station using both methods. The comparison shows that the differences between the estimates are due largely to differing assumptions regarding the size of the utility and operating contractor overhead staffs. It is concluded that the two methods provide bounding estimates on a range of manageable costs, and provide reasonable bases for the utility rate adjustments necessary to pay for future decommissioning costs. 6 refs

  18. 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)

  19. An Analysis of the Authorities' Expected Costs Related to the Decommissioning Programme

    International Nuclear Information System (INIS)

    Lindskog, Staffan; Borg, Lorens; Lichtenberg, Steen

    2002-05-01

    The analysis serves two general aims. These are: (1) To establish a neutral value of the authorities' total expected future costs arising from the decommissioning programme and identify the related uncertainties and their primary sources. The result is measured as a Net Present Value figure (NPV). (2) To test the suggested procedure under development. The analysis procedure follows the basics of the suggested estimate procedure 1. This analysis deals with a programme of an unusually long duration. The timing itself is highly uncertain. In addition, R and D is still to be finished. (I) Costs from January 1 2003 arising from all necessary activities of SKI and SSI and which directly or indirectly relate to the decommissioning programme: They include activities at the power plants after the operating period and until the end of the decommissioning period, and similar activities at CLAB and other communal or shared facilities, as well as related administration, R and D, etc. (II) Any future 'wage inflation'. (III) Events not known today, as well as effects on the programme of minor and medium-scale unplanned events. (IV) Effects of major force majeure events are excluded, for example, a serious nuclear accident in Sweden or elsewhere. (V) Activities and obligations related to nuclear power plants in operation as well as other applications of nuclear materials (e.g. at hospitals) are excluded from the study. (VI) The price level is SEK as at 2002-01-01. (VII) The discount factor as recommended by KAFS and used in the present decommissioning funding is also used here. Hence, it operates at an annual rate of 4% until 2020, and 2.5% thereafter. (VIII) This analysis is limited to the AUB scenario. The parallel GB estimate can be derived from the results of this estimate, subject to minor adjustments. Our basic findings: The total Net Present Value is calculated at Mean Value(M): 2,912 MSEK Standard Deviation (S): 980 MSEK 1. An estimate procedure for the decommissioning

  20. Engineering Evaluation/Cost Analysis (EE/CA) for Decommissioning of TAN-607 Hot Shop Area

    Energy Technology Data Exchange (ETDEWEB)

    J. P. Floerke

    2007-02-05

    Area in a final configuration that will be protective of human health and the environment. Decommissioning the TAN-607 Hot Shop Area is consistent with the joint DOE and U.S. Environmental Protection Agency (EPA) Policy on Decommissioning of Department of Energy Facilities Under the Comprehensive Environmental Response, Compensation and Liability Act, which establishes the CERCLA NTCRA process as the preferred approach for decommissioning surplus DOE facilities. Under this policy, a NTCRA may be taken when DOE determines that the action will prevent, minimize, stabilize, or eliminate a risk to human health and/or the environment. When DOE determines that a CERCLA NTCRA is necessary, DOE is authorized to evaluate, select, and implement the removal action that DOE determines is most appropriate to address the potential risk posed by the release or threat of release. This action is taken in accordance with applicable authorities and in conjunction with EPA and the State of Idaho pursuant to Section 5.3 of the Federal Facility Agreement and Consent Order. In keeping with the joint policy, this engineering evaluation/cost analysis (EE/CA) was developed in accordance with CERCLA as amended by the ''Superfund Amendments and Reauthorization Act of 1986'' and in accordance with the ''National Oil and Hazardous Substances Pollution Contingency Plan.'' This EE/CA is consistent with the remedial action objectives (RAOs) of the Final Record of Decision, Test Area North, Operable Unit 1-10 and supports the overall remediation goals established through the Federal Facility Agreement and Consent Order for Waste Area Group 1. Waste Area Group 1 is located at TAN.

  1. Cost-benefit analysis for U.S. NRC proposed radiological criteria for decommissioning

    International Nuclear Information System (INIS)

    Meck, R.A.

    1995-01-01

    The U.S. Nuclear Regulatory Commission prepared cost-benefit analyses in support of the proposed regulation on radiological criteria for decommissioning. These analyses have been published in the Draft Generic Environmental Impact Statement (GEIS), NUREG-1496, and in the Draft Regulatory Analysis (RA). The method used was to first list the reasonable regulatory alternatives that could be considered. Second, for each regulatory alternative, we analyzed and compared the costs and the incremental radiological and non-radiological impacts to workers and members of the public. The regulatory alternatives for unrestricted use of a site that were analyzed and compared were: no regulatory change; a uniform risk based on total effective dose equivalent (TEDE); use of 'best' available technology; and returning the level of radioactivity attributable to licensed activity to background levels. The analyses were performed for ten types of reference facilities, and each facility was evaluated at low, medium, and high levels of contamination. The reference facilities included: reactors; various uranium and non-fuel cycle facilities; and independent spent fuel storage installations. Since both the radiological and non-radiological benefits were considered, the benefits of the various alternatives were measured in terms of 'Estimated Mortalities Averted.' Conclusions supported by the analyses were that a risk limit, expressed as a 15 mrem/y dose, is reasonable both as a level for protecting public health and safety and with regard to its cost-benefit effects. Further reductions on a site-specific application of the ALARA principle are also supported in the context of accounting for both the radiological and non-radiological effects in both the short and long terms. Restricted release is also supported when the same level of protection is provided in decommissioning those facilities that cannot reasonably meet the unrestricted release criteria. (J.P.N.)

  2. Technical and cost aspects of radioactive wastes from decommissioning

    International Nuclear Information System (INIS)

    Claes, J.; Menon, S.

    2001-01-01

    The OECD Nuclear Energy Agency's Co-operative Programme on Decommissioning was established in 1985 to share the experience and information emerging from on-going decommissioning projects within member countries. The main aim of the programme is to gather and collate such data, which can then provide the basis for planning the future industrial phase of decommissioning of commercial nuclear plants. Starting with 10 decommissioning projects in 1985, today the programme has 35 participating projects from 12 countries. Apart from exchanging valuable information, task groups have been set up for in-depth analysis and studies of areas of common interest, among which are the recycling of material from decommissioning projects and decommissioning costs. This paper will describe the structure and mode of operation of the programme. Some of the results of the work in the task groups will be presented, with particular emphasis on the management of materials from decommissioning and on decommissioning costs. (author)

  3. 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)

  4. Importance of funding in decommissioning cost estimates

    International Nuclear Information System (INIS)

    Mingst, B.C.

    1987-01-01

    Decommissioning cost estimates have been made by several study groups for the decommissioning of pressurized-water and boiling-water nuclear power stations. The results of these studies are comparable when corrected for inflation and the differences in contingency factors applied by the study groups. The estimated dismantling costs differ far less than a factor of 2 in all cases, despite the design differences found in the plants that were studied. An analysis of the different methods available for funding the dismantling of these facilities shows the much stronger effect that the choice of funding methods has on the net cost of decommissioning. The total cost of dismantling may vary more than a factor of 4 from one funding method to another, assuming current or recent historical inflation rates. The funding methods evaluated include sinking funds, deposits, negative-salvage value depreciation, and insurance. These funding methods are taken from the NRC's Notice of Proposed Rulemaking description of acceptable funding methods. The funding analysis for this study was performed using the DECOST-86 computer code. The evaluation of funding options for a nuclear facility, and the appropriate choice of the funding method best for that facility, are found to be more important than detailed engineering studies in determining the net cost of decommissioning during the early portions of the plant's operating lifetime

  5. Cost/risk/benefit analysis report on the decontamination and decommissioning of Z-plant

    International Nuclear Information System (INIS)

    Melvin, J.P.; Sexton, R.A.; Fort, M.L.; Nunn, S.E.

    1979-01-01

    This study was performed to estimate the cost of decontaminating and decommissioning Z-Plant. All of the buildings in the Z-Plant exclusion area except Building 2736-Z, the plutonium storage vault, are included in the study. The study also excludes all underground facilities within the exclusion area which are not contained within a building and all Z-Plant related facilities outside the perimeter fence. The contamination in Z-Plant is primarily 239 Pu which has a half-life of 24,360 years. Because of the long half-life of 239 Pu, it is not practical to consider the isolation of the facility to await reduction of the contamination level by natural decay. Therefore, this study analyzes the costs, risk and benefit of decontaminating Z-Plant to four different levels of residual contamination. The three principle criteria used in the analysis are cost, the risk of offsite dose to the public, and the occupational exposure to onsite personnel

  6. Cost/risk/benefit analysis report on the decontamination and decommissioning of Z-plant

    Energy Technology Data Exchange (ETDEWEB)

    Melvin, J. P.; Sexton, R. A.; Fort, M. L.; Nunn, S. E.

    1979-09-28

    This study was performed to estimate the cost of decontaminating and decommissioning Z-Plant. All of the buildings in the Z-Plant exclusion area except Building 2736-Z, the plutonium storage vault, are included in the study. The study also excludes all underground facilities within the exclusion area which are not contained within a building and all Z-Plant related facilities outside the perimeter fence. The contamination in Z-Plant is primarily /sup 239/Pu which has a half-life of 24,360 years. Because of the long half-life of /sup 239/Pu, it is not practical to consider the isolation of the facility to await reduction of the contamination level by natural decay. Therefore, this study analyzes the costs, risk and benefit of decontaminating Z-Plant to four different levels of residual contamination. The three principle criteria used in the analysis are cost, the risk of offsite dose to the public, and the occupational exposure to onsite personnel.

  7. 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)

  8. R2/R0-WTR decommissioning cost. Comparison and benchmarking analysis

    International Nuclear Information System (INIS)

    Varley, Geoff; Rusch, Chris

    2001-10-01

    SKI charged NAC International with the task of determining whether or not the decommissioning cost estimates of R2/R0 (hereafter simply referred to as R2) and Aagesta research reactors are reasonable. The associated work was performed in two phases. The objective in Phase I was to make global comparisons of the R2 and Aagesta decommissioning estimates with the estimates/actual costs for the decommissioning of similar research reactors in other countries. This report presents the results of the Phase II investigations. Phase II focused on selected discrete work packages within the decommissioning program of the WTR reactor. To the extent possible a comparison of those tasks with estimates for the R2 reactor has been made, as a basis for providing an opinion on the reasonableness of the R2 estimate. The specific WTR packages include: reactor vessel and internals dismantling; biological shield dismantling; primary coolant piping dismantling; electrical equipment removal; waste packaging; transportation and disposal of radioactive concrete and reactor components; project management, licensing and engineering; and removal of ancillary facilities. The specific tasks were characterised and analysed in terms of fundamental parameters including: task definition; labour hours expended; labour cost; labour productivity; length of work week; working efficiency; working environment and impact on job execution; external costs (contract labour, materials and equipment); total cost; waste volumes; and waste packaging and transport costs. Based on such detailed raw data, normalised unit resources have been derived for selected parts of the decommissioning program, as a first step towards developing benchmarking data for D and D activities at research reactors. Several general conclusions emerged from the WTR decommissioning project. Site characterisation can confirm or negate major assumptions, quantify waste volumes, delineate obstacles to completing work, provide an understanding

  9. Decommissioning Cost Estimating -The ''Price'' Approach

    International Nuclear Information System (INIS)

    Manning, R.; Gilmour, J.

    2002-01-01

    Over the past 9 years UKAEA has developed a formalized approach to decommissioning cost estimating. The estimating methodology and computer-based application are known collectively as the PRICE system. At the heart of the system is a database (the knowledge base) which holds resource demand data on a comprehensive range of decommissioning activities. This data is used in conjunction with project specific information (the quantities of specific components) to produce decommissioning cost estimates. PRICE is a dynamic cost-estimating tool, which can satisfy both strategic planning and project management needs. With a relatively limited analysis a basic PRICE estimate can be produced and used for the purposes of strategic planning. This same estimate can be enhanced and improved, primarily by the improvement of detail, to support sanction expenditure proposals, and also as a tender assessment and project management tool. The paper will: describe the principles of the PRICE estimating system; report on the experiences of applying the system to a wide range of projects from contaminated car parks to nuclear reactors; provide information on the performance of the system in relation to historic estimates, tender bids, and outturn costs

  10. Costing for decommissioning: Continuing NEA engagement

    International Nuclear Information System (INIS)

    Gillogly, Mari; Weber, Inge; ); Siemann, Michael; )

    2017-01-01

    On 20-21 September 2016, the International Conference on Financing of Decommissioning of nuclear power plants was held in Stockholm, Sweden. The conference focused on the exchange and sharing of information on current and emerging issues in the financing of nuclear power plant decommissioning and the underlying costs of decommissioning. It aimed at providing a good picture of the variety of financing systems in place to cover the costs of decommissioning of nuclear facilities. As an increasing number of nuclear reactors are expected to be permanently shut-down and enter into the decommissioning phase, the conference highlighted challenges for financing and delivering these decommissioning activities and explored the ways in which they were being addressed. This also included consideration of the implications of potentially under-funded or uncertain decommissioning liabilities. The insights gained in the course of the conference informed future development of work on these issues. The conference addressed a variety of issues from a range of perspectives under three main themes: financing systems - the variety of financing systems in place to provide the financial resources needed for decommissioning, including the arrangements for collecting and developing financial resources during operation and drawing down the assets during decommissioning activities, as well as oversight and reporting issues; decommissioning costing - understanding the cost estimates, quality and interpretation issues in decommissioning costing, the challenges of assurance, comparisons of estimates and actual costs, exploring ways to remedy the current lack of comparable actual cost data, possible benchmarking, etc.; [financial] risk management - effective management of financial assets, risk management strategies, the changing of markets and investment strategies for financial assets, balancing the rates of return and the reduction of risk, implications of the major changes in the energy and

  11. The cost of decommissioning uranium mill tailings

    International Nuclear Information System (INIS)

    Lush, D.L.; Lendrum, C.; Hostovsky, C.; Eedy, W.; Ashbrook, A.

    1986-04-01

    This report identifies several key operations that are commonly carried out during decommissioning of tailings areas in the Canadian environment. These operations are unit costed for a generic site to provide a base reference case. The unit costs have also been scaled to the quantities required for the decommissioning of four Canadian sites and these scaled quantities compared with site-specific engineering cost estimates and actual costs incurred in carrying out the decommissioning activities. Variances in costing are discussed. The report also recommends a generic monitoring regime upon which both short- and longer-term environmental monitoring costs are calculated. Although every site must be addressed as a site-specific case, and monitoring programs must be tailored to fit a specific site, it would appear that for the conventional decommissioning and monitoring practices that have been employed to date, costs can be reasonably estimated when site-specific conditions are taken into account

  12. Brief Assessment of Krsko NPP Decommissioning Costs

    International Nuclear Information System (INIS)

    Skanata, D.; Medakovic, S.; Debrecin, N.

    2000-01-01

    The first part of the paper gives a brief description of decommissioning scenarios and models of financing the decommissioning of NPPs. The second part contains a review of decommissioning costs for certain PWR plants with a brief description of methods used for that purpose. The third part of the paper the authors dedicated to the assessment of decommissioning costs for Krsko NPP. It does not deal with ownership relations and obligations ensuing from them. It starts from the simple point that decommissioning is an structure of the decommissioning fund is composed of three basic cost items of which the first refers to radioactive waste management, the second to storage and disposal of the spent nuclear fuel and the third to decommissioning itself. The assessment belongs to the category of preliminary activities and as such has a limited scope and meaning. Nevertheless, the authors believe that it offers a useful insight into the basic costs that will burden the decommissioning fund of Krsko NPP. (author)

  13. On tentative decommissioning cost analysis with specific authentic cost calculations with the application of the Omega code on a case linked to the Intermediate storage facility for spent fuel in Sweden

    Energy Technology Data Exchange (ETDEWEB)

    Vasko, Marek; Daniska, Vladimir; Ondra, Frantisek; Bezak, Peter; Kristofova, Kristina; Tatransky, Peter; Zachar, Matej [DECOM Slovakia, spol. s.r.o., J. Bottu 2, SK-917 01 Trnava (Slovakia); Lindskog, Staffan [Swedish Nuclear Power Inspectorate, Stockholm (Sweden)

    2007-03-15

    The presented report is focused on tentative calculations of basic decommissioning parameters such as costs, manpower and exposure of personnel for activities of older nuclear facility decommissioning in Sweden represented by Intermediate storage facility for spent fuel in Studsvik, by means of calculation code OMEGA. This report continuously follows up two previous projects, which described methodology of cost estimates of decommissioning with an emphasis to derive cost functions for alpha contaminated material and implementation of the advanced decommissioning costing methodology for Intermediate Storage facility for Spent Fuel in Studsvik. The main purpose of the presented study is to demonstrate the trial application of the advanced costing methodology using OMEGA code for Intermediate Storage Facility for Spent Fuel in Studsvik. Basic work packages presented in report are as follows: 1. Analysis and validation input data on Intermediate Storage Facility for Spent Fuel and assemble a database suitable for standardised decommissioning cost calculations including radiological parameters, 2. Proposal of range of decommissioning calculations and define an extent of decommissioning activities, 3. Defining waste management scenarios for particular material waste streams from Intermediate Storage Facility for Spent Fuel, 4. Developing standardised cost calculation structure applied for Intermediate Storage Facility for Spent Fuel decommissioning calculation and 5. Performing tentative decommissioning calculations for Intermediate Storage Facility for Spent Fuel by OMEGA code. Calculated parameters of decommissioning are presented in structure according to Proposed Standardized List of Items for Costing Purposes. All parameters are documented and summed up in both table and graphic forms in text and Annexes. The presented report documents availability and applicability of methodology for evaluation of costs and other parameters of decommissioning in a form implemented

  14. On tentative decommissioning cost analysis with specific authentic cost calculations with the application of the Omega code on a case linked to the Intermediate storage facility for spent fuel in Sweden

    International Nuclear Information System (INIS)

    Vasko, Marek; Daniska, Vladimir; Ondra, Frantisek; Bezak, Peter; Kristofova, Kristina; Tatransky, Peter; Zachar, Matej; Lindskog, Staffan

    2007-03-01

    The presented report is focused on tentative calculations of basic decommissioning parameters such as costs, manpower and exposure of personnel for activities of older nuclear facility decommissioning in Sweden represented by Intermediate storage facility for spent fuel in Studsvik, by means of calculation code OMEGA. This report continuously follows up two previous projects, which described methodology of cost estimates of decommissioning with an emphasis to derive cost functions for alpha contaminated material and implementation of the advanced decommissioning costing methodology for Intermediate Storage facility for Spent Fuel in Studsvik. The main purpose of the presented study is to demonstrate the trial application of the advanced costing methodology using OMEGA code for Intermediate Storage Facility for Spent Fuel in Studsvik. Basic work packages presented in report are as follows: 1. Analysis and validation input data on Intermediate Storage Facility for Spent Fuel and assemble a database suitable for standardised decommissioning cost calculations including radiological parameters, 2. Proposal of range of decommissioning calculations and define an extent of decommissioning activities, 3. Defining waste management scenarios for particular material waste streams from Intermediate Storage Facility for Spent Fuel, 4. Developing standardised cost calculation structure applied for Intermediate Storage Facility for Spent Fuel decommissioning calculation and 5. Performing tentative decommissioning calculations for Intermediate Storage Facility for Spent Fuel by OMEGA code. Calculated parameters of decommissioning are presented in structure according to Proposed Standardized List of Items for Costing Purposes. All parameters are documented and summed up in both table and graphic forms in text and Annexes. The presented report documents availability and applicability of methodology for evaluation of costs and other parameters of decommissioning in a form implemented

  15. Decommissioning and disposal costs in Switzerland

    International Nuclear Information System (INIS)

    Zurkinden, Auguste

    2003-01-01

    Introduction Goal: Secure sufficient financial resources. Question: How much money is needed? Mean: Concrete plans for decommissioning and waste disposal. - It is the task of the operators to elaborate these plans and to evaluate the corresponding costs - Plans and costs are to be reviewed by the authorities Decommissioning Plans and Costs - Comprise decommissioning, dismantling and management (including disposal) of the waste. - New studies 2001 for each Swiss nuclear power plant (KKB 2 x 380 MWe, KKM 370 MWe, KKG 1020 MWe, KKL 1180 MWe). - Studies performed by NIS (D). - Last developments taken into account (Niederaichbach, Gundremmingen, Kahl). Decommissioning: Results and Review Results: Total cost estimates decreasing (billion CHF) 1994 1998 2001 13.7 13.1 11.8 Lower costs for spent fuel conditioning and BE/HAA/LMA repository (Opalinus Clay) Split in 2025: 5.6 bil. CHF paid by NPP 6.2 billion CHF in Fund Review: Concentrates on disposal, ongoing

  16. CECP, Decommissioning Costs for PWR and BWR

    International Nuclear Information System (INIS)

    Bierschbach, M.C.

    1997-01-01

    1 - Description of program or function: The Cost Estimating Computer Program CECP, designed for use on an IBM personal computer or equivalent, was developed for estimating the cost of decommissioning boiling water reactor (BWR) and light-water reactor (PWR) power stations to the point of license termination. 2 - Method of solution: Cost estimates include component, piping, and equipment removal costs; packaging costs; decontamination costs; transportation costs; burial volume and costs; and manpower staffing costs. Using equipment and consumables costs and inventory data supplied by the user, CECP calculates unit cost factors and then combines these factors with transportation and burial cost algorithms to produce a complete report of decommissioning costs. In addition to costs, CECP also calculates person-hours, crew-hours, and exposure person-hours associated with decommissioning. 3 - Restrictions on the complexity of the problem: The program is designed for a specific waste charge structure. The waste cost data structure cannot handle intermediate waste handlers or changes in the charge rate structures. The decommissioning of a reactor can be divided into 5 periods. 200 different items for special equipment costs are possible. The maximum amount for each special equipment item is 99,999,999$. You can support data for 10 buildings, 100 components each; ESTS1071/01: There are 65 components for 28 systems available to specify the contaminated systems costs (BWR). ESTS1071/02: There are 75 components for 25 systems available to specify the contaminated systems costs (PWR)

  17. 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)

  18. Towards Greater Harmonisation of Decommissioning Cost Estimates

    International Nuclear Information System (INIS)

    O'Sullivan, Patrick; ); Laraia, Michele; ); LaGuardia, Thomas S.

    2010-01-01

    The NEA Decommissioning Cost Estimation Group (DCEG), in collaboration with the IAEA Waste Technology Section and the EC Directorate-General for Energy and Transport, has recently studied cost estimation practices in 12 countries - Belgium, Canada, France, Germany, Italy, Japan, the Netherlands, Slovakia, Spain, Sweden, the United Kingdom and the United States. Its findings are to be published in an OECD/NEA report entitled Cost Estimation for Decommissioning: An International Overview of Cost Elements, Estimation Practices and Reporting Requirements. This booklet highlights the findings contained in the full report. (authors)

  19. 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

  20. Cost Estimation for Research Reactor Decommissioning

    International Nuclear Information System (INIS)

    2013-01-01

    One of the IAEA's statutory objectives is to 'seek to accelerate and enlarge the contribution of atomic energy to peace, health and prosperity throughout the world'. One way this objective is achieved is through the publication of a range of technical series. Two of these are the IAEA Nuclear Energy Series and the IAEA Safety Standards Series. According to Article III.A.6 of the IAEA Statute, the safety standards establish 'standards of safety for protection of health and minimization of danger to life and property.' The safety standards include the Safety Fundamentals, Safety Requirements and Safety Guides. These standards are written primarily in a regulatory style, and are binding on the IAEA for its own programmes. The principal users are the regulatory bodies in Member States and other national authorities. The IAEA Nuclear Energy Series comprises reports designed to encourage and assist R and D on, and application of, nuclear energy for peaceful uses. This includes practical examples to be used by owners and operators of utilities in Member States, implementing organizations, academia, and government officials, among others. This information is presented in guides, reports on technology status and advances, and best practices for peaceful uses of nuclear energy based on inputs from international experts. The IAEA Nuclear Energy Series complements the IAEA Safety Standards Series. The purpose of this publication is to develop a costing methodology and a software tool in order to support cost estimation for research reactor decommissioning. The costing methodology is intended for the preliminary cost estimation stages for research reactor decommissioning with limited inventory data and other input data available. Existing experience in decommissioning costing is considered. As the basis for the cost calculation structure, the costing model uses the International Structure for Decommissioning Costing (ISDC) that is recommended by the IAEA, the Organisation for

  1. 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.

  2. Basic Research on Selecting ISDC Activity for Decommissioning Costing in KRR-2 Decommissioning Project Experience Data

    Energy Technology Data Exchange (ETDEWEB)

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

    2015-10-15

    KAERI is performing research for calculation of expected time of a decommissioning work and evaluation of decommissioning cost and this research calculate a decommissioning work unit productivity based on the experience data of decommissioning activity for KRR-2. The KAERI be used to calculate the decommissioning cost and manage the experience data from the decommissioning activity through the Decommissioning Information Management System (DECOMMIS), Decommissioning Facility Characterization DB System (DEFACS), and Decommissioning Work-unit Productivity Calculation System (DEWOCS). In this paper, the methodology was presented how select the ISDC activities in dismantling work procedures of a 'removal of radioactive concrete'. The reason to select the 'removal of radioactive concrete' is main key activity and generates the amount of radioactive waste. This data will take advantage of the cost estimation after the code for the selected items derived ISDC. There are various efforts for decommissioning costing in each country. In particular, OECD/NEA recommends decommissioning cost estimation using the ISDC and IAEA provides for Cost Estimation for Research Reactors in Excel (CERREX) program that anyone is easy to use the cost evaluation from a limited decommissioning experience in domestic. In the future, for the decommissioning cost evaluation, the ISDC will be used more widely in a strong position. This paper has described a method for selecting the ISDC item from the actual dismantling work procedures.

  3. On Decommissioning Costs of the Ranstad Site

    Energy Technology Data Exchange (ETDEWEB)

    Varley, Geoff (NAC International (United Kingdom))

    2010-08-15

    The main objective of this study has been to extend the review of the future cost to decommission and dismantling the industrial area at the site of the old uranium mine at Ranstad in Sweden. The feedback of experience and actual costs from a decommissioning project in the United Kingdom (A26 in Springfields) has been used to help in the assessment of the reasonableness of the estimated costs for decommissioning of the old uranium mine in Ranstad. A quantitative (albeit subjective) statement about the accuracy of the Ranstad cost estimate has been developed. Also, the factors relevant to the allocation of costs between the Swedish state and the current owners of the old uranium mine site have been evaluated and presented. The study has developed the following main conclusions: - The importance of thorough characterization/radiological mapping to the selection of the optimum decommissioning approach (technique) has been reinforced very strongly. - Thorough characterization has the related consequence of being able to better define the costs of decommissioning, in terms of equipment needed, labour hours required and, importantly, the volumes of different categories of waste requiring different routes (and associated different unit costs) for ultimate disposition. - Uncertainties in the Ranstad decommissioning cost estimate nevertheless remain, in particular relating to the viability of the proposed approach to dismantling and decontaminating the acid proof bricks that line the pools in the Large Leaching Hall; a method that is acknowledged to be not proven. The outcome could have an impact on actual dismantling and decontamination costs, as well as on the costs of ultimate waste disposition. The KB2010 cost estimate report does not offer an alternative in the event that the base plan proves to be unfeasible. - On balance it would appear that the continued presence of RMA at the Ranstad site ultimately will provide a net cost benefit to the program. The extra costs

  4. On Decommissioning Costs of the Ranstad Site

    International Nuclear Information System (INIS)

    Varley, Geoff

    2010-08-01

    The main objective of this study has been to extend the review of the future cost to decommission and dismantling the industrial area at the site of the old uranium mine at Ranstad in Sweden. The feedback of experience and actual costs from a decommissioning project in the United Kingdom (A26 in Springfields) has been used to help in the assessment of the reasonableness of the estimated costs for decommissioning of the old uranium mine in Ranstad. A quantitative (albeit subjective) statement about the accuracy of the Ranstad cost estimate has been developed. Also, the factors relevant to the allocation of costs between the Swedish state and the current owners of the old uranium mine site have been evaluated and presented. The study has developed the following main conclusions: - The importance of thorough characterization/radiological mapping to the selection of the optimum decommissioning approach (technique) has been reinforced very strongly. - Thorough characterization has the related consequence of being able to better define the costs of decommissioning, in terms of equipment needed, labour hours required and, importantly, the volumes of different categories of waste requiring different routes (and associated different unit costs) for ultimate disposition. - Uncertainties in the Ranstad decommissioning cost estimate nevertheless remain, in particular relating to the viability of the proposed approach to dismantling and decontaminating the acid proof bricks that line the pools in the Large Leaching Hall; a method that is acknowledged to be not proven. The outcome could have an impact on actual dismantling and decontamination costs, as well as on the costs of ultimate waste disposition. The KB2010 cost estimate report does not offer an alternative in the event that the base plan proves to be unfeasible. - On balance it would appear that the continued presence of RMA at the Ranstad site ultimately will provide a net cost benefit to the program. The extra costs

  5. A Review of the Decommissioning Costs of the Ranstad Site

    Energy Technology Data Exchange (ETDEWEB)

    Varley, Geoff (NAC International, Norcross, GA (United States))

    2009-08-15

    The main objective of this study has been to review the future cost to decommission and dismantling the industrial area at the site of the old uranium mine at Ranstad in Sweden. Analyses of some detailed comparative empirical information have been used in the context of preliminary 'bench-marking' studies. The estimated costs for decommissioning of the old uranium mine in Ranstad have been compared with actual costs from other relevant decommissioning projects. In this way it has been possible to give a preliminary qualitative statement about the accuracy of the Ranstad cost estimate. The study gives the following lessons learned: 1. The available information suggests that the overall estimated cost may be reasonable, but there are still some points of weakness that need to be elaborated more in detail before a full statement about the adequacy of the forecast cost will be possible. 2. Especially the costs associated with declassification activities warrant further analysis in order to determine there level of accuracy. 3. There exists the possibility that the estimate might be low concerning decontamination, dismantling and planning and institutional work. 4. Further work and analysis is needed in order to develop a more transparent cost estimate in which the stakeholders can have the highest confidence. 5. A new bidding procedure for the conventional demolition may result in lower estimated costs. Hence, it would be beneficial to obtain an updated estimate based on at least more than one quotation. 6. The method of addressing uncertainty and risk should be more connected to the logistics of specific decommissioning activities, in order to be more transparent and clearer in details. There is a need for further study to develop a better estimate. In the short run follow-up work needs to be undertaken to provide a better understanding of what are the major contributors to risk and cost drivers in the planned decommissioning process at the Ranstad

  6. A Review of the Decommissioning Costs of the Ranstad Site

    International Nuclear Information System (INIS)

    Varley, Geoff

    2009-08-01

    The main objective of this study has been to review the future cost to decommission and dismantling the industrial area at the site of the old uranium mine at Ranstad in Sweden. Analyses of some detailed comparative empirical information have been used in the context of preliminary 'bench-marking' studies. The estimated costs for decommissioning of the old uranium mine in Ranstad have been compared with actual costs from other relevant decommissioning projects. In this way it has been possible to give a preliminary qualitative statement about the accuracy of the Ranstad cost estimate. The study gives the following lessons learned: 1. The available information suggests that the overall estimated cost may be reasonable, but there are still some points of weakness that need to be elaborated more in detail before a full statement about the adequacy of the forecast cost will be possible. 2. Especially the costs associated with declassification activities warrant further analysis in order to determine there level of accuracy. 3. There exists the possibility that the estimate might be low concerning decontamination, dismantling and planning and institutional work. 4. Further work and analysis is needed in order to develop a more transparent cost estimate in which the stakeholders can have the highest confidence. 5. A new bidding procedure for the conventional demolition may result in lower estimated costs. Hence, it would be beneficial to obtain an updated estimate based on at least more than one quotation. 6. The method of addressing uncertainty and risk should be more connected to the logistics of specific decommissioning activities, in order to be more transparent and clearer in details. There is a need for further study to develop a better estimate. In the short run follow-up work needs to be undertaken to provide a better understanding of what are the major contributors to risk and cost drivers in the planned decommissioning process at the Ranstad industrial area

  7. Development of computer program for estimating decommissioning cost - 59037

    International Nuclear Information System (INIS)

    Kim, Hak-Soo; Park, Jong-Kil

    2012-01-01

    The programs for estimating the decommissioning cost have been developed for many different purposes and applications. The estimation of decommissioning cost is required a large amount of data such as unit cost factors, plant area and its inventory, waste treatment, etc. These make it difficult to use manual calculation or typical spreadsheet software such as Microsoft Excel. The cost estimation for eventual decommissioning of nuclear power plants is a prerequisite for safe, timely and cost-effective decommissioning. To estimate the decommissioning cost more accurately and systematically, KHNP, Korea Hydro and Nuclear Power Co. Ltd, developed a decommissioning cost estimating computer program called 'DeCAT-Pro', which is Decommission-ing Cost Assessment Tool - Professional. (Hereinafter called 'DeCAT') This program allows users to easily assess the decommissioning cost with various decommissioning options. Also, this program provides detailed reporting for decommissioning funding requirements as well as providing detail project schedules, cash-flow, staffing plan and levels, and waste volumes by waste classifications and types. KHNP is planning to implement functions for estimating the plant inventory using 3-D technology and for classifying the conditions of radwaste disposal and transportation automatically. (authors)

  8. Decommissioning wind energy projects: An economic and political analysis

    International Nuclear Information System (INIS)

    Ferrell, Shannon L.; DeVuyst, Eric A.

    2013-01-01

    Wind energy is the fastest-growing segment of new electrical power capacity in the United States, with the potential for significant growth in the future. To facilitate such growth, a number of concerns between developers and landowners must be resolved, including assurance of wind turbine decommissioning at the end of their useful lives. Oklahoma legislators enlisted the authors to develop an economically-sound proposal to ensure developers complete their decommissioning obligations. Economic analysis of turbine decommissioning is complicated by a lack of operational experience, as few U.S. projects have been decommissioned. This leads to a lack of data regarding decommissioning costs. Politically, the negotiation leading to the finally-enacted solution juxtaposed economic theory against political pragmatism, leading to a different but hopefully sound solution. This article will provide background for the decommissioning issue, chronicle the development of the decommissioning component of the Oklahoma Wind Energy Act, and frame issues that remain for policymakers in regulating wind power development. - Highlights: ► Wind energy is the fastest-growing component of U.S. power generation. ► Decommissioning wind projects is policy concern for wind development. ► Little public information on wind turbine decommissioning costs exists. ► Oklahoma’s solution attempts to account for both costs and risks. ► Additional research is needed to create a more precise policy solution.

  9. 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)

  10. 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

  11. Cost estimation for decommissioning: a review of current practice

    International Nuclear Information System (INIS)

    O'Sullivan, P.; Pescatore, C.

    2009-01-01

    boundary conditions; cost estimation methodologies; and experience gained during the process. Twelve countries provided responses and participated in the analysis: Belgium, Canada, France, Germany, Italy, Japan, the Netherlands, the Slovak Republic, Spain, Sweden, the United Kingdom and the United States. The final report documenting the study is nearing publication. Its main findings are reported in this article. There is no single cost assessment methodology that applies equally at all stages of a decommissioning project. This means that different cost assessment methodologies may need to be used as the project advances. Such methodologies should be continuously updated using cost data from actual decommissioning projects, thus improving the cost assessment, providing better control of uncertainties and contingencies for each major cost category, and facilitating the preparation of an annualized schedule of expenditures for each facility. In the future, risk management may benefit from an approach that uses a deterministic calculation (base case) that feeds into a probabilistic assessment of future costs. Such approaches may be used to gain a better understanding of potential cost and programme requirements. Attention should also be given early on to socio-economic factors, including impacts caused by loss of employment, to help in building public support and acceptance of a decommissioning project. Early meetings with stakeholders may be used to gain agreement on project boundary conditions, strategy, release criteria and measurement protocols, and waste containers used. In view of the very significant impacts that changes and increases in scope may have on cost estimates, it is important that these be identified and controlled immediately, and incorporated into the estimate so that the estimate may continue to provide a viable benchmarking resource. Characterisation is acknowledged to be an important part of cost estimating accuracy, as it affects system and structure

  12. Derivation of the mass factors for decommissioning cost estimation of low contaminated auxiliary systems

    International Nuclear Information System (INIS)

    Poskas, G.

    2015-01-01

    Ignalina NPP was operating two RBMK-1500 reactors. Unit 1 was closed at the end of 2004, and Unit 2 - at the end of 2009. Now they are under decommissioning. Decommissioning has been started from the reactor's periphery, with dismantling of non-contaminated and low contaminated equipment and installations. This paper discusses a methodology for derivation of mass factors for preliminary decommissioning costing at NPP when the number of inventory items is significant, and separate consideration of each inventory item is impossible or impractical for preliminary decommissioning plan, especially when the level of radioactive contamination is very low. The methodology is based on detailed data analysis of building V1 taking into account period and inventory based activities, investment and consumables and other decommissioning approach- related properties for building average mass factors. The methodology can be used for cost estimation of preliminary decommissioning planning of NPP auxiliary buildings with mostly very low level contamination. (authors)

  13. Implementation of the international structure for decommissioning costing; examples and related IAEA projects - 59313

    International Nuclear Information System (INIS)

    Daniska, Vladimir; Laraia, Michele; O'Sullivan, Patrick

    2012-01-01

    In 1999, IAEA, the OECD Nuclear Energy Agency and the European Commission jointly proposed the standardised listing of decommissioning activities [1] to serve as a general basis for presentation of decommissioning costs and for promoting the harmonisation in decommissioning costing. The standardised listing of activities [1] was developed in three hierarchical levels based on analysis of typical decommissioning activities identified in various decommissioning projects. The structure [1] has been currently updated by the same organisations as the International Structure for Decommissioning Costing (ISDC) based on the experience gained over ten years of use of the original standardised listing [2]. First part of the paper presents the revised ISDC. The principle of the three-level original hierarchical structure has been preserved. Re-definition of the content and re-structuring was done to avoid ambiguity and to ensure comprehensiveness. Paper presents two basic approaches for implementation of the ISDC structure in costing - converting the cost data available in specific cost structures, mostly according the work breakdown structures of decommissioning projects into ISDC and implementation of the ISDC as the cost calculation structure. Examples of the second approach are given to show that this approach is feasible and may have several advantages. An ORACLE based costing model with implemented of the extended ISDC for detailed costing and an Excel based costing model for preliminary costing at IAEA for research reactors are given. (authors)

  14. Contingency Cost estimation for Research reactor Decommissioning

    International Nuclear Information System (INIS)

    Jin, Hyung Gon; Hong, Yun Jeong

    2016-01-01

    There are many types of cost items in decommissioning cost estimation, however, contingencies are for unforeseen elements of cost within the defined project scope. Regulatory body wants to reasonable quantification for this issue. Many countries have adopted the breakdown of activity dependent and period-dependent costs to structure their estimates. Period-dependent costs could be broken down into defined time frames to reduce overall uncertainties. Several countries apply this notion by having different contingency factors for different phases of the project. This study is a compilation of contingency cost of research reactor and for each country. Simulation techniques using TRIM, MATLAB, and PSpice can be useful tools for designing detector channels. Thus far TRIM, MATLAB and PSpice have been used to calculate the detector current output pulse for SiC semiconductor detectors and to model the pulses that propagate through potential detector channels. This model is useful for optimizing the detector and the resolution for application to neutron monitoring in the Generation IV power reactors

  15. Contingency Cost estimation for Research reactor Decommissioning

    Energy Technology Data Exchange (ETDEWEB)

    Jin, Hyung Gon; Hong, Yun Jeong [KAERI, Daejeon (Korea, Republic of)

    2016-05-15

    There are many types of cost items in decommissioning cost estimation, however, contingencies are for unforeseen elements of cost within the defined project scope. Regulatory body wants to reasonable quantification for this issue. Many countries have adopted the breakdown of activity dependent and period-dependent costs to structure their estimates. Period-dependent costs could be broken down into defined time frames to reduce overall uncertainties. Several countries apply this notion by having different contingency factors for different phases of the project. This study is a compilation of contingency cost of research reactor and for each country. Simulation techniques using TRIM, MATLAB, and PSpice can be useful tools for designing detector channels. Thus far TRIM, MATLAB and PSpice have been used to calculate the detector current output pulse for SiC semiconductor detectors and to model the pulses that propagate through potential detector channels. This model is useful for optimizing the detector and the resolution for application to neutron monitoring in the Generation IV power reactors.

  16. 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

  17. 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

  18. 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

  19. 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

  20. Prediction of Decommissioning Cost for Kijang Research Reactor Using Power Data of DACCORD

    Energy Technology Data Exchange (ETDEWEB)

    Hong, Yun Jeong; Jin, Hyung Gon; Park, Hee Seong; Park, Seung Kook [KAERI, Daejeon (Korea, Republic of)

    2016-05-15

    There are 3 types of cost estimate that can be used, and each have a different level of accuracy: (i) Order of magnitude estimate: One without detailed engineering data, where an estimate is prepared using scale-up or -down factors and approximate ratios. It is likely that the overall scope of the project has not been well defined. The level of accuracy expected is -30% to +50%. The cost plans to predict referring to abroad examples as decommissioning cost estimation has still not developed and been commercial method for Kijang research reactor. In Kijang research reactor case, overall scope of business isn't yet decided. Then it is supposed to estimate cost with type (i). The IAEA project, entitled 'DACCORD' (Data Analysis and Collection for Costing of Research Reactor Decommissioning) performs decommissioning costing after collecting and analyzing the information related to research reactors around the world for several years. Also decommissioning costing method development tends to increase in the each country. This paper aims to estimate preliminary decommissioning cost based on total decommissioning cost per thermal power rate of research reactor presented in DACCORD project' data which is collected by member state. In this paper, preliminary decommissioning cost is estimated based on total decommissioning cost per thermal power rate of research reactor presented in DACCORD data which is collected by member state. Although there exists a general tendency for costs to increase with increasing thermal power, the limited data available show that decommissioning costs at any given power level can vary widely, with increased variability at higher power levels. Variations in decommissioning cost for the research reactors of the same or similar thermal power are caused by differences in reactor types and design, decommissioning project scopes, country- specific unit workforce costs, and other reactor or project factors. An important factor for the

  1. 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

  2. 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

  3. Parameters of Dismantling Techniques Related to Costs for Decommissioning of Nuclear Facilities

    International Nuclear Information System (INIS)

    Jeong, Kwanseong; Moon, Jeikwon; Choi, Byungseon

    2012-01-01

    Reliable cost estimating is one of the most important elements of decommissioning operation. Reliable cost estimating is one of the most important elements of decommissioning planning. Alternative technologies may be evaluated and compared on their efficiency and effectiveness, and measured against a baseline cost as to the feasibility and benefit derived from the technology. This principle ensures that the cost consideration is economically sound and practical for funding. This paper provides a list with basic review of cutting and dismantling techniques, including some typical characteristics if available, as well as aspects of implementation, parameters of cutting and dismantling techniques in decommissioning costing. This paper gives an overview of the principles of the unit factor approach and its implementation in costing in relation to dismantling activities. In general, proper evaluation of decommissioning costs is important for following issues and relevant measures for achieving the listed aspects are: · Selection of a decommissioning strategy and activities: several decommissioning options should be evaluated: · Support to a cost-benefit analysis to ensure that the principle of optimization and reasonably practicable measures are applied: the extent of evaluated decommissioning options should cover all possible scenarios for dismantling activities; · Estimate of required financial resources for the selected strategy: the selected option should involve the dismantling activities in a structure and extent relevant to real procedure of dismantling activities; · Preparation of the project schedule, workforce requirements and phased funding needs: dismantling activities should be structured according to the tasks of the decommissioning schedule; · Definition of measures for proper management and maintenance of resources for safe and timely decommissioning: the time distribution and safety related parameters of dismantling activities should be known

  4. 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

  5. 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

  6. 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

  7. Optimization of costs versus radiation exposures in decommissioning

    International Nuclear Information System (INIS)

    Konzek, G.J.

    1979-01-01

    The estimated worth of decommissioning optimization planning during each phase of the reactor's life cycle is dependent on many variables. The major variables are tabulated and relatively ranked. For each phase, optimization qualitative values (i.e., cost, safety, maintainability, ALARA, and decommissioning considerations) are estimated and ranked according to their short-term and long-term potential benefits. These estimates depend on the quality of the input data, interpretation of that data, and engineering judgment. Once identified and ranked, these considerations form an integral part of the information data base from which estimates, decisions, and alternatives are derived. The optimization of costs and the amount of occupational radiation exposure reductions are strongly interrelated during decommissioning. Realizing that building the necessary infrastructure for decommissioning will take time is an important first step in any decommissioning plan. In addition, the following conclusions are established to achieve optimization of costs and reduced occupational radiation exposures: the assignment of cost versus man-rem is item-specific and sensitive to the expertise of many interrelated disciplines; a commitment to long-term decommissioning planning by management will provide the conditions needed to achieve optimization; and, to be most effective, costs and exposure reduction are sensitive to the nearness of the decommissioning operation. For a new plant, it is best to start at the beginning of the cycle, update continually, consider innovations, and realize full potential and benefits of this concept. For an older plant, the life cycle methodology permits a comprehensive review of the plant history and the formulation of an orderly decommissioning program based on planning, organization, and effort

  8. 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

  9. On Cost Estimate for Decommissioning of one Isotope Central

    International Nuclear Information System (INIS)

    Marek Vasko et al

    2010-08-01

    The main scope of this study has been to calculate the future cost for decommission and dismantling the Isotope central at the Studsvik site using the OMEGA CODE. Detailed empirical information is used in the study for 'bench-marking' purposes, in such cases when there is a need to supplement and correct field data from the industry. In the present study, data has been retrieved and organized such that the estimated costs for decommissioning of the Isotope Central become transparent and reliable. This approach gives a preliminary qualitative indication about the accuracy of the cost estimate delivered by the industry

  10. On Cost Estimate for Decommissioning of one Isotope Central

    Energy Technology Data Exchange (ETDEWEB)

    Marek Vasko et al

    2010-08-15

    The main scope of this study has been to calculate the future cost for decommission and dismantling the Isotope central at the Studsvik site using the OMEGA CODE. Detailed empirical information is used in the study for 'bench-marking' purposes, in such cases when there is a need to supplement and correct field data from the industry. In the present study, data has been retrieved and organized such that the estimated costs for decommissioning of the Isotope Central become transparent and reliable. This approach gives a preliminary qualitative indication about the accuracy of the cost estimate delivered by the industry

  11. 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.

  12. Technology, safety and costs of decommissioning a reference pressurized water reactor power station: Technical support for decommissioning matters related to preparation of the final decommissioning rule

    International Nuclear Information System (INIS)

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

    1988-07-01

    Preparation of the final Decommissioning Rule by the Nuclear Regulatory Commission (NRC) staff has been assisted by Pacific Northwest Laboratory (PNL) staff familiar with decommissioning matters. These efforts have included updating previous cost estimates developed during the series of studies on conceptually decommissioning reference licensed nuclear facilities for inclusion in the Final Generic Environmental Impact Statement (FGEIS) on decommissioning; documenting the cost updates; evaluating the cost and dose impacts of post-TMI-2 backfits on decommissioning; developing a revised scaling formula for estimating decommissioning costs for reactor plants different in size from the reference pressurized water reactor (PWR) described in the earlier study; defining a formula for adjusting current cost estimates to reflect future escalation in labor, materials, and waste disposal costs; and completing a study of recent PWR steam generator replacements to determine realistic estimates for time, costs and doses associated with steam generator removal during decommissioning. This report presents the results of recent PNL studies to provide supporting information in four areas concerning decommissioning of the reference PWR: updating the previous cost estimates to January 1986 dollars; assessing the cost and dose impacts of post-TMI-2 backfits; assessing the cost and dose impacts of recent steam generator replacements; and developing a scaling formula for plants different in size than the reference plant and an escalation formula for adjusting current cost estimates for future escalation

  13. 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)

  14. Development of Cost Estimation Methodology of Decommissioning for PWR

    International Nuclear Information System (INIS)

    Lee, Sang Il; Yoo, Yeon Jae; Lim, Yong Kyu; Chang, Hyeon Sik; Song, Geun Ho

    2013-01-01

    The permanent closure of nuclear power plant should be conducted with the strict laws and the profound planning including the cost and schedule estimation because the plant is very contaminated with the radioactivity. In Korea, there are two types of the nuclear power plant. One is the pressurized light water reactor (PWR) and the other is the pressurized heavy water reactor (PHWR) called as CANDU reactor. Also, the 50% of the operating nuclear power plant in Korea is the PWRs which were originally designed by CE (Combustion Engineering). There have been experiences about the decommissioning of Westinghouse type PWR, but are few experiences on that of CE type PWR. Therefore, the purpose of this paper is to develop the cost estimation methodology and evaluate technical level of decommissioning for the application to CE type PWR based on the system engineering technology. The aim of present study is to develop the cost estimation methodology of decommissioning for application to PWR. Through the study, the following conclusions are obtained: · Based on the system engineering, the decommissioning work can be classified as Set, Subset, Task, Subtask and Work cost units. · The Set and Task structure are grouped as 29 Sets and 15 Task s, respectively. · The final result shows the cost and project schedule for the project control and risk management. · The present results are preliminary and should be refined and improved based on the modeling and cost data reflecting available technology and current costs like labor and waste data

  15. National and international cost aspects of decommissioning and dismantling

    International Nuclear Information System (INIS)

    Mittler, M.; Lukacs, G.

    1996-01-01

    The German concept applied for the planning of nuclear power plant decommissioning activities and for cost estimates is accepted also internationally as an exemplary scheme. The decommissioning costs essentially are determined by the factor ''time'', and time under the German concept is a factor primarily influenced by the licensing procedure. In other countries, particularly in the USA, the procedure is much more pragmatic, as much more responsibility lies with the supervising and licensing authorities for aspects such as safety and environmental compatibility, and economically efficient use of public funds in particular. (orig./DG)

  16. Offshore Wind Energy Cost Modeling Installation and Decommissioning

    CERN Document Server

    Kaiser, Mark J

    2012-01-01

    Offshore wind energy is one of the most promising and fastest growing alternative energy sources in the world. Offshore Wind Energy Cost Modeling provides a methodological framework to assess installation and decommissioning costs, and using examples from the European experience, provides a broad review of existing processes and systems used in the offshore wind industry. Offshore Wind Energy Cost Modeling provides a step-by-step guide to modeling costs over four sections. These sections cover: ·Background and introductory material, ·Installation processes and vessel requirements, ·Installation cost estimation, and ·Decommissioning methods and cost estimation.  This self-contained and detailed treatment of the key principles in offshore wind development is supported throughout by visual aids and data tables. Offshore Wind Energy Cost Modeling is a key resource for anyone interested in the offshore wind industry, particularly those interested in the technical and economic aspects of installation and decom...

  17. 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)

  18. Cost update: Technology, safety, and costs of decommissioning a reference uranium fuel fabrication plant

    International Nuclear Information System (INIS)

    Miles, T.L.; Liu, Y.

    1994-06-01

    The cost estimates originally developed in NUREG/CR-1266 for commissioning a reference low-enrichment uranium fuel fabrication plant are updated from 1978 to early 1993 dollars. During this time, the costs for labor and materials increased approximately at the rate of inflation, the cost of energy increased more slowly than the rate of inflation, and the cost of low-level radioactive waste disposal increased much more rapidly than the rate of inflation. The results of the analysis indicate that the estimated costs for the immediate dismantlement and decontamination for unrestricted facility release (DECON) of the reference plant have increased from the mid-1978 value of $3.57 million to $8.08 million in 1993 with in-compact low-level radioactive waste disposal at the US Ecoloay facility near Richland, Washington. The cost estimate rises to $19.62 million with out-of-compact radioactive waste disposal at the Chem-Nuclear facility near Barnwell, South Carolina. A methodology and a formula are presented for estimating the cost of decommissioning the reference uranium fuel fabrication plant at some future time, based on these early 1993 cost estimates. The formula contains essentially the same elements as the formula given in 10 CFR 50.75 for escalating the decommissioning costs for nuclear power reactors to some future time

  19. Cost Control Guide For Decommissioning Of Nuclear Installations

    International Nuclear Information System (INIS)

    2013-01-01

    This cost control guide was prepared in response to the request from the OECD/NEA Working Party on Decommissioning and Dismantling (WPDD) - Decommissioning Cost Estimation Group (DCEG) to offer the industry guidance in preparing and implementing cost and schedule controls during decommissioning. The DCEG sent out a survey questionnaire in 2010 soliciting comments from OECD member states on their use of cost controls during decommissioning. While the response was limited, the consensus was to proceed with the preparation of this guide. Cost and schedule control systems have been in use for more than 30 years, and in the last 10 years or so have evolved into a more formalised earned value management system (EVMS). This guide is based on the internationally recognised standard, Earned Value Management Systems (ANSI, 2007). The EVMS is built on a work breakdown structure (WBS) of decommissioning activities, and a defined process for controlling a project. The EVMS not only provides measurement of project status and future performance, but also builds a structure and culture for accountability on project performance. This guide describes the performance metrics used to determine the value earned based on what was planned to be done, what was actually accomplished and what it actually cost. Variances measured monthly at a minimum indicate where potential problems are arising and raise a flag for the project manager to implement corrective actions for the next reporting period. The success of the EVMS programme depends on management commitment to implement a culture change for its employees, and to impose the EVMS on potential future contractors performing decommissioning work at a facility. Formal training is required to ensure all elements of the process are understood and put into action. It is recommended to begin with a small project, and graduate to larger projects as the staff learns how to use the system. The EVMS process has been used internationally for small

  20. Technology, safety and costs of decommissioning a refernce boiling water reactor power station: Technical support for decommissioning matters related to preparation of the final decommissioning rule

    International Nuclear Information System (INIS)

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

    1988-07-01

    Preparation of the final Decommissioning Rule by the Nuclear Regulatory Commission (NRC) staff has been assisted by Pacific Northwest Laboratory (PNL) staff familiar with decommissioning matters. These efforts have included updating previous cost estimates developed during the series of studies of conceptually decommissioning reference licensed nuclear facilities for inclusion in the Final Generic Environmental Impact Statement (FGEIS) on decommissioning; documenting the cost updates; evaluating the cost and dose impacts of post-TMI-2 backfits on decommissioning; developing a revised scaling formula for estimating decommissioning costs for reactor plants different in size from the reference boiling water reactor (BWR) described in the earlier study; and defining a formula for adjusting current cost estimates to reflect future escalation in labor, materials, and waste disposal costs. This report presents the results of recent PNL studies to provide supporting information in three areas concerning decommissioning of the reference BWR: updating the previous cost estimates to January 1986 dollars; assessing the cost and dose impacts of post-TMI-2 backfits; and developing a scaling formula for plants different in size than the reference plant and an escalation formula for adjusting current cost estimates for future escalation

  1. 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.

  2. 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

  3. 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

  4. 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

  5. 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)

  6. Technology, safety, and costs of decommissioning reference light-water reactors following postulated accidents. Appendices

    Energy Technology Data Exchange (ETDEWEB)

    Murphy, E S; Holter, G M

    1982-11-01

    Appendices contain information concerning the reference site description; reference PWR facility description; details of reference accident scenarios and resultant contamination levels; generic cleanup and decommissioning information; details of activities and manpower requirements for accident cleanup at a reference PWR; activities and manpower requirements for decommissioning at a reference PWR; costs of decommissioning at a reference PWR; cost estimating bases; safety assessment details; and details of post-accident cleanup and decommissioning at a reference BWR.

  7. 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)

  8. 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)

  9. Cost Savings through Innovation in Decontamination, Decommissioning, and Dismantlement

    International Nuclear Information System (INIS)

    Yancey, Neal A.

    2003-01-01

    The United States Department of Energy (DOE) continually seeks safer and more cost effective technologies for the decontamination and decommissioning (D and D) of nuclear facilities. The Deactivation and Decommissioning Focus Area (DDFA) of the DOE's Office of Science and Technology (OST) sponsored large-scale demonstration and deployment projects (LSDDPs) to help bring new technologies into the D and D programs. The Idaho National Engineering and Environmental Laboratory (INEEL) LSDDP generated a list of needs defining specific problems where improved technologies could be incorporated into ongoing D and D tasks. The needs fell into 5 major categories--characterization, dismantlement, safety, material dispositioning, and decontamination. Technologies were carefully selected that provide a large benefit for a small investment. The technologies must provide significant improvements in cost, safety, radiation exposure, waste volume reduction, or schedule savings and widely applicable throughout the DOE complex. The LSDDP project provided training for the new technologies and worked with technology suppliers to resolve any questions that arose. Since 1998, 26 technologies have been demonstrated or deployed through the LSDDP for the D and D program at the INEEL. Of the 26 demonstrated and deployed technologies, 14 were in characterization, 3 were in decontamination, 4 were in dismantlement, 3 were in safety, and 2 were in material dispositioning. To promote the use of these technologies at other sites within the DOE complex, the LSDDP team published fact sheets, videos, technology summary reports, articles in INEEL star newspaper, posters, and maintained an internet home page on the project. As a result, additional deployments have taken place at the Hanford, Mound, Fernald, Oak Ridge, Ashtabula, and West Valley. Eight of the 26 technologies evaluated were developed in foreign countries. The technologies demonstrated have been shown to be faster, less expensive, and

  10. Cost update: Technology, safety, and costs of decommissioning reference independent spent fuel storage installations

    International Nuclear Information System (INIS)

    Miles, T.L.

    1994-07-01

    The cost estimates originally developed in NUREG/CR-2210 for decommissioning five conceptual Independent Spent Fuel Storage Installations (ISFSIs) and their supporting ancillaries (hot cell and transporter) are updated from 1981 to 1993 dollars. The costs for labor and materials increased approximately at the rate of inflation, the cost of energy increased more slowly than the rate of inflation, and the cost of low-level radioactive waste disposal increased much more rapidly than the rate of inflation. A methodology and a formula are presented for estimating the cost of decommissioning the ISFSIs at some future time, based on these current cost estimates. The formula contains essentially the same elements as the formula given in 10 CFR 50.75 for escalating the decommissioning costs for nuclear power reactors to some future time

  11. On Decommissioning Cost for Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Varley, Geoff (NAC International (United Kingdom)); Rush, Chris (NAC International (United States))

    2011-01-15

    The two biggest changes in NPP DandD over the last 15 years that are applicable across all countries are: a. Equipment and tools used in NPP DandD have evolved to be available on a more industrial basis, although concerning DandD of the main NPP components, such activity typically is very individual and requires one-of equipment to be developed. b. Regulation of DandD has increased. Earlier regulations were adapting to what emerged from evolving DandD projects. Today regulatory requirements have caught up and have been framed based on the feedback of experience over the last 15 years. In general they impose prescriptive requirements on DandD approaches and execution. In the U.S. access to LLW disposal has been opened up to a majority of states, which will ease the development and timely execution of DandD projects. A newly emerging trend in the U.S. is that segregation of some categories of waste, to facilitate the disposal of some volumes in general landfill rather than in radioactive waste disposal facilities, is being sacrificed, on cost grounds, in favour of mixing waste volumes with the consequence of having to dispose of a larger volume of waste in a LLW facility. Regarding access to information that can be meaningful and sufficiently detailed to support an international benchmarking inter-comparison of NPP DandD cost information: - NAC has established good access to detailed information on actual DandD projects at one U.S. PWR (Trojan) and one U.S. BWR (Rancho Seco). Additional information sources probably can be accessed with additional investigation. - Germany has highly relevant cost estimate and actual NPP DandD experience. Accessibility of the information is not yet fully determined. This will need more extensive, face-to-face interaction with the relevant stakeholders. Utilities and cost estimate service providers offer the opportunity to access relevant information. Specific terms and conditions that would apply and the extent of detail that would be

  12. On Decommissioning Cost for Nuclear Power Plants

    International Nuclear Information System (INIS)

    Varley, Geoff; Rush, Chris

    2011-01-01

    The two biggest changes in NPP DandD over the last 15 years that are applicable across all countries are: a. Equipment and tools used in NPP DandD have evolved to be available on a more industrial basis, although concerning DandD of the main NPP components, such activity typically is very individual and requires one-of equipment to be developed. b. Regulation of DandD has increased. Earlier regulations were adapting to what emerged from evolving DandD projects. Today regulatory requirements have caught up and have been framed based on the feedback of experience over the last 15 years. In general they impose prescriptive requirements on DandD approaches and execution. In the U.S. access to LLW disposal has been opened up to a majority of states, which will ease the development and timely execution of DandD projects. A newly emerging trend in the U.S. is that segregation of some categories of waste, to facilitate the disposal of some volumes in general landfill rather than in radioactive waste disposal facilities, is being sacrificed, on cost grounds, in favour of mixing waste volumes with the consequence of having to dispose of a larger volume of waste in a LLW facility. Regarding access to information that can be meaningful and sufficiently detailed to support an international benchmarking inter-comparison of NPP DandD cost information: - NAC has established good access to detailed information on actual DandD projects at one U.S. PWR (Trojan) and one U.S. BWR (Rancho Seco). Additional information sources probably can be accessed with additional investigation. - Germany has highly relevant cost estimate and actual NPP DandD experience. Accessibility of the information is not yet fully determined. This will need more extensive, face-to-face interaction with the relevant stakeholders. Utilities and cost estimate service providers offer the opportunity to access relevant information. Specific terms and conditions that would apply and the extent of detail that would be

  13. 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

  14. 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.

  15. 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

  16. 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)

  17. 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)

  18. 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

  19. 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

  20. Decommissioning costing approach based on the standardised list of costing items. Lessons learnt by the OMEGA computer code

    International Nuclear Information System (INIS)

    Daniska, Vladimir; Rehak, Ivan; Vasko, Marek; Ondra, Frantisek; Bezak, Peter; Pritrsky, Jozef; Zachar, Matej; Necas, Vladimir

    2011-01-01

    The document 'A Proposed Standardised List of Items for Costing Purposes' was issues in 1999 by OECD/NEA, IAEA and European Commission (EC) for promoting the harmonisation in decommissioning costing. It is a systematic list of decommissioning activities classified in chapters 01 to 11 with three numbered levels. Four cost group are defined for cost at each level. Document constitutes the standardised matrix of decommissioning activities and cost groups with definition of content of items. Knowing what is behind the items makes the comparison of cost for decommissioning projects transparent. Two approaches are identified for use of the standardised cost structure. First approach converts the cost data from existing specific cost structures into the standardised cost structure for the purpose of cost presentation. Second approach uses the standardised cost structure as the base for the cost calculation structure; the calculated cost data are formatted in the standardised cost format directly; several additional advantages may be identified in this approach. The paper presents the costing methodology based on the standardised cost structure and lessons learnt from last ten years of the implementation of the standardised cost structure as the cost calculation structure in the computer code OMEGA. Code include also on-line management of decommissioning waste, decay of radioactively, evaluation of exposure, generation and optimisation of the Gantt chart of a decommissioning project, which makes the OMEGA code an effective tool for planning and optimisation of decommissioning processes. (author)

  1. Technology, safety, and costs of decommissioning a reference large irradiator and reference sealed sources

    Energy Technology Data Exchange (ETDEWEB)

    Haffner, D.R.; Villelgas, A.J. [Pacific Northwest Lab., Richland, WA (United States)

    1996-01-01

    This report contains the results of a study sponsored by the US Nuclear Regulatory Commission (NRC) to examine the decommissioning of large radioactive irradiators and their respective facilities, and a broad spectrum of sealed radioactive sources and their respective devices. Conceptual decommissioning activities are identified, and the technology, safety, and costs (in early 1993 dollars) associated with decommissioning the reference large irradiator and sealed source facilities are evaluated. The study provides bases and background data for possible future NRC rulemaking regarding decommissioning, for evaluation of the reasonableness of planned decommissioning actions, and for determining if adequate funds are reserved by the licensees for decommissioning of their large irradiator or sealed source facilities. Another purpose of this study is to provide background and information to assist licensees in planning and carrying out the decommissioning of their sealed radioactive sources and respective facilities.

  2. Technology, safety, and costs of decommissioning a reference large irradiator and reference sealed sources

    International Nuclear Information System (INIS)

    Haffner, D.R.; Villelgas, A.J.

    1996-01-01

    This report contains the results of a study sponsored by the US Nuclear Regulatory Commission (NRC) to examine the decommissioning of large radioactive irradiators and their respective facilities, and a broad spectrum of sealed radioactive sources and their respective devices. Conceptual decommissioning activities are identified, and the technology, safety, and costs (in early 1993 dollars) associated with decommissioning the reference large irradiator and sealed source facilities are evaluated. The study provides bases and background data for possible future NRC rulemaking regarding decommissioning, for evaluation of the reasonableness of planned decommissioning actions, and for determining if adequate funds are reserved by the licensees for decommissioning of their large irradiator or sealed source facilities. Another purpose of this study is to provide background and information to assist licensees in planning and carrying out the decommissioning of their sealed radioactive sources and respective facilities

  3. Managing the present and future costs of decommissioning

    International Nuclear Information System (INIS)

    Azorsky, T.L.; Fenster, H.L.

    1987-01-01

    The lack of state and federal standards for decommissioning and decontamination (D and D) of nuclear facilities may result in additional costs years after the D and D is complete. Increased costs may result from the application of certain environmental statutes to the facility or from personal injury and property damage, i.e., tort, litigation. Companies that operated facilities that provided a service or product for the government have certain financial protections and certain immunities from suit. Companies operating commercial facilities, however, have little or no protection from future liabilities. Accordingly, this country needs federal standards for D and D, standards that would govern the level of decontamination required and protect companies completing the D and D effort from future liability

  4. 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)

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

    International Nuclear Information System (INIS)

    Cantor, R.

    1984-04-01

    The purpose of this study is to highlight some of the current and likely regulations that will significantly affect the costs, technical alternatives and financing schemes for reactor decommissioning encountered by electric utilities and their customers. The paper includes a general review of the decommissioning literature, as well as information on specific regulations at the federal, state, and utility levels. Available estimated costs for the decommissioning of individual reactors are also presented. Finally, classification of the specific policies into common trends and practices among the various regulatory bodies is used to examine more general regulatory environments and their potential financial implications

  6. Estimating pressurized water reactor decommissioning costs: A user's manual for the PWR Cost Estimating Computer Program (CECP) software

    International Nuclear Information System (INIS)

    Bierschbach, M.C.; Mencinsky, G.J.

    1993-10-01

    With the issuance of the Decommissioning Rule (July 27, 1988), nuclear power plant licensees are required to submit to the US Regulatory Commission (NRC) for review, decommissioning plans and cost estimates. This user's manual and the accompanying Cost Estimating Computer Program (CECP) software provide a cost-calculating methodology to the NRC staff that will assist them in assessing the adequacy of the licensee submittals. The CECP, designed to be used on a personnel computer, provides estimates for the cost of decommissioning PWR plant stations to the point of license termination. Such cost estimates include component, piping, and equipment removal costs; packaging costs; decontamination costs; transportation costs; burial costs; and manpower costs. In addition to costs, the CECP also calculates burial volumes, person-hours, crew-hours, and exposure person-hours associated with decommissioning

  7. Cost update technology, safety, and costs of decommissioning a reference uranium hexafluoride conversion plant

    International Nuclear Information System (INIS)

    Miles, T.L.; Liu, Y.

    1995-08-01

    The purpose of this study is to update the cost estimates developed in a previous report, NUREG/CR-1757 (Elder 1980) for decommissioning a reference uranium hexafluoride conversion plant from the original mid-1981 dollars to values representative of January 1993. The cost updates were performed by using escalation factors derived from cost index trends over the past 11.5 years. Contemporary price quotes wee used for costs that have increased drastically or for which is is difficult to find a cost trend. No changes were made in the decommissioning procedures or cost element requirements assumed in NUREG/CR-1757. This report includes only information that was changed from NUREG/CR-1757. Thus, for those interested in detailed descriptions and associated information for the reference uranium hexafluoride conversion plant, a copy of NUREG/CR-1757 will be needed

  8. 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

  9. 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

  10. Selection of relevant items for decommissioning costing estimation of a PWR using fuzzy logic

    International Nuclear Information System (INIS)

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

    2015-01-01

    The decommissioning is an important part of a nuclear power plant life cycle which may occur by technical, economical or safety reasons. Decommissioning requires carrying out a large number of tasks that should be planned in advance, involves cost evaluations, preparation of plans of activity and actual operational actions. Despite the large number of tasks, only part of them is relevant for cost estimation purpose. The technical literature and international regulatory agencies suggest a variety of methods for decommissioning cost estimation. Most of them require a very detailed knowledge of the plant and data available suitable for plants that are starting their decommissioning but not for those in the planning stage. The present work aims to apply fuzzy logic to sort out relevant items to cost estimation in order to reduce the work effort involved. The scheme uses parametric equations for specific cost items, and is applied to specific parts of the process of nuclear power plant decommissioning. (author)

  11. Selection of relevant items for decommissioning costing estimation of a PWR using fuzzy logic

    Energy Technology Data Exchange (ETDEWEB)

    Monteiro, Deiglys Borges; Busse, Alexander Lucas; Moreira, Joao M.L.; Maiorino, Jose Rubens, E-mail: deiglys.monteiro@ufabc.edu.br, E-mail: alexlucasb@gmail.com, 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

    The decommissioning is an important part of a nuclear power plant life cycle which may occur by technical, economical or safety reasons. Decommissioning requires carrying out a large number of tasks that should be planned in advance, involves cost evaluations, preparation of plans of activity and actual operational actions. Despite the large number of tasks, only part of them is relevant for cost estimation purpose. The technical literature and international regulatory agencies suggest a variety of methods for decommissioning cost estimation. Most of them require a very detailed knowledge of the plant and data available suitable for plants that are starting their decommissioning but not for those in the planning stage. The present work aims to apply fuzzy logic to sort out relevant items to cost estimation in order to reduce the work effort involved. The scheme uses parametric equations for specific cost items, and is applied to specific parts of the process of nuclear power plant decommissioning. (author)

  12. Ratemaking treatment of decommissioning costs by the Federal Energy Regulatory Commission

    International Nuclear Information System (INIS)

    Lenart, R.J.

    1985-01-01

    The Nuclear Regulatory Commission (NRC) has the responsibility for the assurance of funds at the time of decommissioning. The Federal Energy Regulatory Commission (FERC), in conjunction with the State Public Utility Commissions, have the responsibilty to ensure that utilities have just and reasonable rates and an opportunity to collect an appropriate amount of dollars to decommission a nuclear reactor at the conclusion of its service life. Therefore, the Federal Energy Regulatory Commission allows utilities to include nuclear power plant decommissioning costs in rates based on the following ratemaking concepts: (1) that the methodology used by a utility equitably allocates costs between present and future ratepayers who receive service from a nuclear unit; (2) that, given the uncertainty and imprecision that are included in cost estimates for events that will transpire 20-40 years in the future, the FERC chose to err on the low side rather than run the risk of overcharging current customers for future decommissioning expense; and (3) that, as decommissioning experience accumulates, as decommissioning technology improves, and as decommissioning estimates become more refined, utilities would continue to seek revised decommissioning expense allowances from FERC in order to ensure that actual decommissioning costs are recovered over the useful life in which the plant provides service

  13. A model study of cost estimates of decontamination and decommissioning with an emphasis to derive cost functions for alpha contaminated material using OMEGA code

    Energy Technology Data Exchange (ETDEWEB)

    Kristofova, Kristina; Daniska, Vladimir; Ondra, Frantisek; Rehak, Ivan; Vasko, Marek [DECOM SLOVAKIA spol. s.r.o., Trnava (Slovakia)

    2004-12-01

    The presented study is focused on model decommissioning cost calculations for primary circuit of A-1 nuclear power plant in Jaslovske Bohunice. In addition, the survey of advanced decommissioning costing is included together with impact analyses of contamination on particular decommissioning parameters. OMEGA code decommissioning cost calculations for primary circuit of A-1 NPP presented in the study are performed and evaluated under the following conditions: different contamination level of inner and outer surfaces; different waste management scenarios; application and non-application of pre-dismantling decontamination; different start of decommissioning: 2004, 2010, 2020, 2030, 2040; radionuclide composition of primary circuit contamination in A-1 NPP with occurrence of alpha radionuclides and fission products as a consequence of operational accident with damaged fuel cladding; radionuclide composition of primary circuit contamination in V-2 NPP in Jaslovske Bohunice as a representative NPP with an operation without accidents and therefore neither non-alpha contaminants nor fission products are included. The results of all the above mentioned conditions impacts on calculated costs, manpower, exposure and distribution of materials arisen from decommissioning are evaluated in detail within the calculation sensitivity analysis.

  14. A model study of cost estimates of decontamination and decommissioning with an emphasis to derive cost functions for alpha-contaminated material using OMEGA code

    International Nuclear Information System (INIS)

    Kristofova, Kristina; Daniska, Vladimir; Ondra, Frantisek; Rehak, Ivan; Vasko, Marek

    2004-12-01

    The presented study is focused on model decommissioning cost calculations for primary circuit of A-1 nuclear power plant in Jaslovske Bohunice. In addition, the survey of advanced decommissioning costing is included together with impact analyses of contamination on particular decommissioning parameters. OMEGA code decommissioning cost calculations for primary circuit of A-1 NPP presented in the study are performed and evaluated under the following conditions: different contamination level of inner and outer surfaces; different waste management scenarios; application and non-application of pre-dismantling decontamination; different start of decommissioning: 2004, 2010, 2020, 2030, 2040; radionuclide composition of primary circuit contamination in A-1 NPP with occurrence of alpha radionuclides and fission products as a consequence of operational accident with damaged fuel cladding; radionuclide composition of primary circuit contamination in V-2 NPP in Jaslovske Bohunice as a representative NPP with an operation without accidents and therefore neither non-alpha contaminants nor fission products are included. The results of all the above mentioned conditions impacts on calculated costs, manpower, exposure and distribution of materials arisen from decommissioning are evaluated in detail within the calculation sensitivity analysis

  15. Technology, safety and costs of decommissioning a reference boiling water reactor power station. Appendices. Volume 2

    Energy Technology Data Exchange (ETDEWEB)

    Oak, H.D.; Holter, G.M.; Kennedy, W.E. Jr.; Konzek, G.J.

    1980-06-01

    Appendices are presented concerning the evaluations of decommissioning financing alternatives; reference site description; reference BWR facility description; radiation dose rate and concrete surface contamination data; radionuclide inventories; public radiation dose models and calculated maximum annual doses; decommissioning methods; generic decommissioning information; immediate dismantlement details; passive safe storage, continuing care, and deferred dismantlement details; entombment details; demolition and site restoration details; cost estimating bases; public radiological safety assessment details; and details of alternate study bases.

  16. Report on waste burial charges: Escalation of decommissioning waste disposal costs at low-level waste burial facilities

    International Nuclear Information System (INIS)

    1988-07-01

    One of the requirements placed upon nuclear power reactor licensees by the US Nuclear Regulatory Commission (NRC) is for the licensees to periodically adjust the estimate of the cost of decommissioning their plant, in dollars of the current year, as part of the process to provide reasonable assurance that adequate funds for decommissioning will be available when needed. This report, which is scheduled to be revised annually, contains the development of a formula for escalating decommissioning cost estimates that is acceptable to the NRC, and contains values for the escalation of radioactive waste burial costs, by site and by year. The licensees may use the formula, the coefficients, and the burial escalation factors from this report in their escalation analysis, or may use an escalation rate at least equal to the escalation approach presented herein. 4 refs., 2 tabs

  17. Technology, safety and costs of decommissioning nuclear reactors at multiple-reactor stations

    International Nuclear Information System (INIS)

    Wittenbrock, N.G.

    1982-01-01

    Safety and cost information is developed for the conceptual decommissioning of large (1175-MWe) pressurized water reactors (PWR) and large (1155-MWe) boiling water reactors (BWR) at multiple-reactor stations. Three decommissioning alternatives are studied: DECON (immediate decontamination), SAFSTOR (safe storage followed by deferred decontamination), and ENTOMB (entombment). Safety and costs of decommissioning are estimated by determining the impact of probable features of multiple-reactor-station operation that are considered to be unavailable at a single-reactor station, and applying these estimated impacts to the decommissioning costs and radiation doses estimated in previous PWR and BWR decommissioning studies. The multiple-reactor-station features analyzed are: the use of interim onsite nuclear waste storage with later removal to an offsite waste disposal facility, the use of permanent onsite nuclear waste disposal, the dedication of the site to nuclear power generation, and the provision of centralized services

  18. 26 CFR 1.468A-0T - Nuclear decommissioning costs; table of contents.

    Science.gov (United States)

    2010-04-01

    ...) Substantial completion of decommissioning defined. § 1.468A-6TDisposition of an interest in a nuclear power...-abuse provision. § 1.468A-7TManner of and time for making election (temporary). (a) In general. (b... 26 Internal Revenue 6 2010-04-01 2010-04-01 false Nuclear decommissioning costs; table of contents...

  19. Technology, safety, and costs of decommissioning a reference pressurized water reactor power station. Appendices

    International Nuclear Information System (INIS)

    Smith, R.I.; Konzek, G.J.; Kennedy, W.E. Jr.

    1978-05-01

    Detailed appendices are presented under the following headings: reference PWR facility description, reference PWR site description, estimates of residual radioactivity, alternative methods for financing decommissioning, radiation dose methodology, generic decommissioning activities, intermediate dismantlement activities, safe storage and deferred dismantlement activities, compilation of unit cost factors, and safety assessment details

  20. Comparison of standardised decommissioning costing tools on pilot Vienna TRIGA MARK-II research reactor

    International Nuclear Information System (INIS)

    Hornacek, M.; Kristofova, K.; Slugen, V.; Zachar, M.; Stummer, T.

    2017-01-01

    The main purpose of the paper is to compare decommissioning costing code CERREX (Cost Estimation for Research Reactors in Excel) with advanced calculation methodology applied in eOMEGA-RR code. CERREX code was developed in line with the IAEA recommendations for decommissioning costing of research facilities and fully implements the ISDC (International Structure for Decommissioning Costing of Nuclear Installations) structure and costing methodology. In comparison with CERREX, usually applied in preliminary costing, the code eOMEGA-RR incorporates the realistic activity and material flow during decommissioning process (e.g. decontamination, dismantling and waste management). This advanced approach enables to carry out the decommissioning planning and costing more effectively. Moreover, the user-friendly interface helps to perform wide range of sensitivity analyses. In order to meet the above mentioned objectives, the model calculation costing case for TRIGA MARK-II research reactor in Vienna was developed in both calculation codes. The whole process covered four step-by-step procedures to be implemented. At first, inventory database taking into account physical as well as radiological parameters (e.g.: contamination, dose rates, nuclide vectors, limits and conditions) was developed. At second, advanced decommissioning costing case using CERREX and eOMEGA-RR code was created. At third, sensitivity analyses to estimate the impact of changing input parameters on calculated results were performed. Finally, costing results obtained from both cost calculation codes are compared and discussed. (authors)

  1. Case Study to Apply Work Difficulty Factors to Decommissioning Cost Estimates

    Energy Technology Data Exchange (ETDEWEB)

    Yun, Taesik; Jung, Hyejin; Oh, Jaeyoung; Kim, Younggook [KHNP CRI, Daejeon (Korea, Republic of)

    2016-10-15

    This article is prepared as a guideline regarding how to apply the work difficult factor (WDF) when it comes to the estimates of the decommissioning costs. Although several cases of the decommissioning cost estimates have been made for a few commercial nuclear power plants, the different technical, site-specific economic assumptions used make it difficult to interpret those cost estimates and compare them with that of Kori-1. In addition, it is clear that we are supposed to experience difficulties being created in the process of the Kori-1 and the virtual inaccessibility to the limited areas at the pre-decommissioning stage. Estimating decommissioning costs is one of the most crucial processes since it encompasses all the spectrum of decommissioning activities from the planning to the last evaluation on whether the decommissioning has successfully been proceeded from the safety and economic perspectives. Here I suggested the activity dependent costs is only related to WDFs of the incumbent plant planning or undergone to be decommissioned since as a matter of fact, estimating WDFs is the core process to articulately scrutinize the practical costs to apply to Kori-1 project.

  2. 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

  3. Technology, safety and costs of decommissioning reference light water reactors following postulated accidents

    International Nuclear Information System (INIS)

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

    1990-12-01

    The estimated costs for post-accident cleanup at the reference BWR (developed previously in NUREG/CR-2601, Technology, Safety and Costs of Decommissioning Reference Light Water Reactors Following Postulated Accidents) are updated to January 1989 dollars in this report. A simple formula for escalating post-accident cleanup costs is also presented. Accident cleanup following the most severe accident described in NUREG/CR-2601 (i.e., the Scenario 3 accident) is estimated to cost from $1.22 to 1.44 billion, in 1989 dollars, for assumed escalation rates of 4% or 8% in the years following 1989. The time to accomplish cleanup remained unchanged from the 8.3 years originally estimated. No reanalysis of current information on the technical aspects of TMI-2 cleanup has been performed. Only the cost of inflation has been evaluated since the original PNL analysis was completed. 32 refs., 12 tabs

  4. Technical assessment of environmental and cost implications of superconducting super collider decommissioning

    International Nuclear Information System (INIS)

    Chen, S.Y.; Opelka, J.H.; Chambers, W.C.; Stavrou, J.

    1988-07-01

    Potential environmental and cost implications of decommissioning the proposed Superconducting Super Collider (SSC) are examined. One decommissioning alternative is selected for general assessment. That alternative includes removal of the major sources of radioactivity induced during operation and temporary entombment of remaining underground facilities. On the suface, the campus complex would be left in place for future use, but most other aboveground features would be dismantled and removed. Because of the low level of radioactivity that would be induced in SSC components during system operation, potential radiological impacts to the environment from decommissioning would be benign, and the estimated total occupational radiation dose to workers would be less that 5 person-rem. Potential nonradiological impacts of decommissioning are not evaluated because of the lack of site-specific data. The total estimated cost of decommissioning operations is $38 million. Although few current regulations are explicitly applicable, the SSC decommissioning operation should not encounter any difficulty in complying with potentially applicable regulatory constraints. Upon completion of decommissioning, the SSC site surface could be returned to unrestricted use, but it is recommended that a degree of institutional control and environmental monitoring be carried out for a short period following decommissioning. 11 refs., 8 figs., 6 tabs

  5. A Prediction on the Unit Cost Estimation for Decommissioning Activities Using the Experienced Data from DECOMMIS

    Energy Technology Data Exchange (ETDEWEB)

    Park, Seung Kook; Park, Hee Seong; Choi, Yoon Dong; Song, Chan Ho; Moon, Jei Kwon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-05-15

    The KAERI (Korea Atomic Energy Research Institute) has developed the DECOMMIS (Decommissioning Information Management System) and have been applied for the decommissioning project of the KRR (Korea Research Reactor)-1 and 2 and UCP (Uranium Conversion Plant), as the meaning of the first decommissioning project in Korea. All information and data which are from the decommissioning activities are input, saved, output and managed in the DECOMMIS. This system was consists of the web server and the database server. The users could be access through a web page, depending on the input, processing and output, and be modified the permissions to do such activities can after the decommissioning activities have created the initial system-wide data is stored. When it could be used the experienced data from DECOMMIS, the cost estimation on the new facilities for the decommissioning planning will be established with the basic frame of the WBS structures and its codes. In this paper, the prediction on the cost estimation through using the experienced data which were store in DECOMMIS was studied. For the new decommissioning project on the nuclear facilities in the future, through this paper, the cost estimation for the decommissioning using the experienced data which were WBS codes, unit-work productivity factors and annual governmental unit labor cost is proposed. These data were from the KRR and UCP decommissioning project. The differences on the WBS code sectors and facility characterization between new objected components and experienced dismantled components was reduces as scaling factors. The study on the establishment the scaling factors and cost prediction for the cost estimation is developing with the algorithms from the productivity data, now.

  6. 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

  7. Influence of accounting concepts and regulatory rules on the funding of power reactor decommissioning costs

    International Nuclear Information System (INIS)

    Ferguson, J.S.

    1985-01-01

    Under normal circumstances, an evaluation of nuclear plant decommissioning costs by an engineering analyst will not produce the same results as an evaluation by a financial analyst. These analysts should understand evaluations based on each other's bases to ensure that their evaluation techniques are appropriate for the circumstances. The intent of this discussion is to enhance that understanding by describing the accounting and regulatory framework that is applicable to the decommissioning costs of U.S. nuclear power plants, and by explaining why evaluations of decommissioning costs prepared by engineering analysts often look different from evaluations prepared by financial analysts. Of major importance are the financial implications of several methods of funding the decommissioning costs. Since many owners of nuclear plants are subject to revenue rate regulation, financial implications often translate directly to regulatory implications

  8. Decommissioning of the nuclear facilities at Risø National Laboratory. Descriptions and cost assessment

    DEFF Research Database (Denmark)

    Lauridsen, K.

    2001-01-01

    and the costs incurred. Three decommissioning scenarios were considered with decay times of 10, 25 and 40 years for the DR 3 reactor. The assessments conclude, however, that there will not be much to gain by allowing forthe longer decay periods; some operations still will need to be performed remotely....... Furthermore, the report describes some of the legal and licensing framework for the decommissioning and gives an assessment of the amounts of radioactive waste to betransferred to a Danish repository. For a revision of the cost estimate for the decommissioning of the research Reactor DR 3 please consult...

  9. Ringhals Site Study 2013 - An assessment of the decommissioning cost for the Ringhals site

    Energy Technology Data Exchange (ETDEWEB)

    Hansson, Tommy [Ringhals AB, Ringhals (Sweden); Norberg, Thomas [Solvina AB, Goeteborg (Sweden); Knutsson, Andreas; Fors, Patrik; Sandebert, Camilla [Vattenfall AB, Stockholm (Sweden)

    2013-03-15

    This report presents the decommissioning cost for the Ringhals site as of 2013. The objective has been to make a best estimate of the costs within the uncertainties of a budgetary estimate. To achieve this, the decommissioning costs have been assessed with support from TLG Services Inc., utilizing their knowledge and experience from U.S. decommissioning projects incorporated in their cost estimation platform DECCER. The 2013 estimate has included the development of a Ringhals-specific cost estimation method that allows for successive improvement in the future. In-house experiences have been included and the method is based on the present decommissioning strategy according to Ringhals decommissioning plan. Two basic approaches have been used in the cost assessment; a bottom up approach to develop unit cost factors (UCF) for recurrent work; and a specific analogy approach for cost estimating special items. The basic, activity-dependent, costs have been complemented by period-dependent costs, derived, among other things, from SKB's newly developed reference planning and organizational model for a Swedish decommissioning project. Furthermore, collateral costs based on the experiences of Barsebaeck have been included. As a final point, all costs have been adjusted for industrial standard contingencies, as suggested by TLG, to achieve a best estimate. In order to make the cost intelligible a comprehensive description of the assumptions, boundary conditions and general basis of the estimate is included in this report. All costs have been reported both according to the International Structure for Decommissioning Costing (ISDC) of Nuclear Installations published by OECD/NEA and according to the SKB developed EEF structure. Furthermore, common costs have been isolated to a theoretical unit 0 to make the cost for respective unit even more comparable on a national and international scale. The calculations show that the total cost for the decommissioning of the Ringhals

  10. Ringhals Site Study 2013 - An assessment of the decommissioning cost for the Ringhals site

    International Nuclear Information System (INIS)

    Hansson, Tommy; Norberg, Thomas; Knutsson, Andreas; Fors, Patrik; Sandebert, Camilla

    2013-03-01

    This report presents the decommissioning cost for the Ringhals site as of 2013. The objective has been to make a best estimate of the costs within the uncertainties of a budgetary estimate. To achieve this, the decommissioning costs have been assessed with support from TLG Services Inc., utilizing their knowledge and experience from U.S. decommissioning projects incorporated in their cost estimation platform DECCER. The 2013 estimate has included the development of a Ringhals-specific cost estimation method that allows for successive improvement in the future. In-house experiences have been included and the method is based on the present decommissioning strategy according to Ringhals decommissioning plan. Two basic approaches have been used in the cost assessment; a bottom up approach to develop unit cost factors (UCF) for recurrent work; and a specific analogy approach for cost estimating special items. The basic, activity-dependent, costs have been complemented by period-dependent costs, derived, among other things, from SKB's newly developed reference planning and organizational model for a Swedish decommissioning project. Furthermore, collateral costs based on the experiences of Barsebaeck have been included. As a final point, all costs have been adjusted for industrial standard contingencies, as suggested by TLG, to achieve a best estimate. In order to make the cost intelligible a comprehensive description of the assumptions, boundary conditions and general basis of the estimate is included in this report. All costs have been reported both according to the International Structure for Decommissioning Costing (ISDC) of Nuclear Installations published by OECD/NEA and according to the SKB developed EEF structure. Furthermore, common costs have been isolated to a theoretical unit 0 to make the cost for respective unit even more comparable on a national and international scale. The calculations show that the total cost for the decommissioning of the Ringhals site is

  11. Technology, safety, and costs of decommissioning reference nuclear research and test reactors. Main report

    International Nuclear Information System (INIS)

    Konzek, G.J.; Ludwick, J.D.; Kennedy, W.E. Jr.; Smith, R.I.

    1982-03-01

    Safety and Cost Information is developed for the conceptual decommissioning of two representative licensed nuclear research and test reactors. Three decommissioning alternatives are studied to obtain comparisons between costs (in 1981 dollars), occupational radiation doses, potential radiation dose to the public, and other safety impacts. The alternatives considered are: DECON (immediate decontamination), SAFSTOR (safe storage followed by deferred decontamination), and ENTOMB (entombment). The study results are presented in two volumes. Volume 1 (Main Report) contains the results in summary form

  12. 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

  13. 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.

  14. Procedure for estimating facility decommissioning costs for non-fuel-cycle nuclear facilities

    International Nuclear Information System (INIS)

    Short, S.M.

    1988-01-01

    The Nuclear Regulatory Commission (NRC) staff has been reappraising its regulatory position relative to the decommissioning of nuclear facilities over the last several years. Approximately 30 reports covering the technology, safety, and costs of decommissioning reference nuclear facilities have been published during this period in support of this effort. One of these reports, Technology, Safety, and Costs of Decommissioning Reference Non-Fuel-Cycle Nuclear Facilities (NUREG/CR-1754), was published in 1981 and was felt by the NRC staff to be outdated. The Pacific Northwest Laboratory (PNL) was asked by the NRC staff to revise the information provided in this report to reflect the latest information on decommissioning technology and costs and publish the results as an addendum to the previous report. During the course of this study, the NRC staff also asked that PNL provide a simplified procedure for estimating decommissioning costs of non-fuel-cycle nuclear facilities. The purpose being to provide NRC staff with the means to easily generate their own estimate of decommissioning costs for a given facility for comparison against a licensee's submittal. This report presents the procedure developed for use by NRC staff

  15. Comparative analysis of the Oskarshamn 3 and Barsebaeck site decommissioning studies

    International Nuclear Information System (INIS)

    Hansson, Bertil; Joensson, Lars-Olof

    2009-01-01

    Several projects concerning the decommissioning of different types of nuclear facilities have shown that technical methods and equipment are available today for safe dismantling of nuclear facilities of any type or size. However, comparison of individual cost estimates for specific facilities exhibit relatively large variations, and several studies have tried to identify the reasons for these variations. Analysis has shown that decommissioning cost estimates vary depending on a number of factors, including: the boundary conditions and strategy chosen; the cost items taken into account; the origin of the cost estimate; the methodology applied; the political-administrative framework; and the way contingencies are included. In this study, a comparison has been made between two decommissioning studies in the same country, with more or less same decommissioning schedule and with similar overall ideas on cost estimates. However, the two studies had from the start a different focus and different objectives. One study is intended as a reference study for all BWRs in Sweden, while the other focuses on a full site decommissioning. Furthermore, one of the studies is based on direct dismantling and the other on deferred dismantling. A great deal of work therefore had to be devoted in the present study to giving the studies comparable structures and boundary conditions using the OECD/NEA cost estimate structure. The boundary conditions in each of the studies have been thoroughly evaluated qualitatively and quantitatively, and the differences have been explained. In the end, values have been set in the quantitative analysis to verify that the studies could be compared, within the accuracy of what is defined in the industry as a 'budgetary estimate'. Differences still exist relating to what has been included in the studies and to the decommissioning plans and the resulting inventory from site characterization. Such differences must be accepted as long as it is clear what is

  16. Comparative analysis of the Oskarshamn 3 and Barsebaeck site decommissioning studies

    Energy Technology Data Exchange (ETDEWEB)

    Hansson, Bertil (Bewon, Loeddekoepinge (Sweden)); Joensson, Lars-Olof (Barsebaeck Kraft AB, Loeddekoepinge (Sweden))

    2009-01-15

    Several projects concerning the decommissioning of different types of nuclear facilities have shown that technical methods and equipment are available today for safe dismantling of nuclear facilities of any type or size. However, comparison of individual cost estimates for specific facilities exhibit relatively large variations, and several studies have tried to identify the reasons for these variations. Analysis has shown that decommissioning cost estimates vary depending on a number of factors, including: the boundary conditions and strategy chosen; the cost items taken into account; the origin of the cost estimate; the methodology applied; the political-administrative framework; and the way contingencies are included. In this study, a comparison has been made between two decommissioning studies in the same country, with more or less same decommissioning schedule and with similar overall ideas on cost estimates. However, the two studies had from the start a different focus and different objectives. One study is intended as a reference study for all BWRs in Sweden, while the other focuses on a full site decommissioning. Furthermore, one of the studies is based on direct dismantling and the other on deferred dismantling. A great deal of work therefore had to be devoted in the present study to giving the studies comparable structures and boundary conditions using the OECD/NEA cost estimate structure. The boundary conditions in each of the studies have been thoroughly evaluated qualitatively and quantitatively, and the differences have been explained. In the end, values have been set in the quantitative analysis to verify that the studies could be compared, within the accuracy of what is defined in the industry as a 'budgetary estimate'. Differences still exist relating to what has been included in the studies and to the decommissioning plans and the resulting inventory from site characterization. Such differences must be accepted as long as it is clear

  17. Technology, safety and costs of decommissioning a Reference Boiling Water Reactor Power Station. Main report. Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    Oak, H.D.; Holter, G.M.; Kennedy, W.E. Jr.; Konzek, G.J.

    1980-06-01

    Technology, safety and cost information is given for the conceptual decommissioning of a large (1100MWe) boiling water reactor (BWR) power station. Three approaches to decommissioning, immediate dismantlement, safe storage with deferred dismantlement and entombment, were studied to obtain comparisons between costs, occupational radiation doses, potential dose to the public and other safety impacts. It also shows the sensitivity of decommissioning safety and costs to the power rating of a BWR in the range of 200 to 1100 MWe.

  18. Evolution or revolution? Dismantling the FASB standard on decommissioning costs

    International Nuclear Information System (INIS)

    Ferguson, J.S.

    1996-01-01

    The Financial Standards and Accounting Board has issued for comment a draft of proposed financial accounting standards pertaining to nuclear plant decommissioning. This article examines the proposed rules and discusses alternate approaches in those areas in which the author takes issue with the FASB draft

  19. Decommissioning cost recovery in the United States: lessons learned from Connecticut Yankee NPP

    International Nuclear Information System (INIS)

    Joosten, J.

    1999-01-01

    The international audience at ICONE-7 is already familiar with the roles of the owner and the NRC in ensuring the technical and safety performance goals of nuclear plant decommissioning. This paper addresses the role of the economic regulator since the pursuit of technical and safety goals must necessarily carry with them -a price tag- and owners must be concerned with the recovery of those costs. Answers to questions about how to pay and who should pay for decommissioning can very often influence nuclear power plant owner's decision-making. In the United States, most nuclear power plants are privately owned. Nevertheless, their owners are not totally free to determine the plant's economics or profitability. Instead, plant owners must sell their electricity to consumers in a regulated market wherein the price of electricity and terms of sale are controlled by the government. Under this regulatory regime, utilities are generally allowed to recover their investment costs -including decommissioning costs- provided that such costs are prudently, incurred. However, when an owner retires the plant prematurely, the prudence of his actions -up to and including the shutdown- are likely to be challenged. In 1997, for example, the owners of the Connecticut Yankee reactor faced a stiff challenge to the recovery of decommissioning costs when they shut down the plant ten years before license expiration. The Connecticut Yankee case thus provides valuable insights into the role of economic regulation on a nuclear plant's decommissioning strategy. (author)

  20. 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

  1. Waste management strategy for cost effective and environmentally friendly NPP decommissioning

    Energy Technology Data Exchange (ETDEWEB)

    Per Lidar; Arne Larsson [Studsvik Nuclear AB (ndcon partner), Nykoping (Sweden); Niklas Bergh; Gunnar Hedin [Westinghouse Electric Sweden AB (ndcon partner), Vasteraas (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 interruptions. Bottle

  2. Waste management strategy for cost effective and environmentally friendly NPP decommissioning

    International Nuclear Information System (INIS)

    Per Lidar; Arne Larsson; Niklas Bergh; Gunnar Hedin

    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

  3. 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

  4. 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)

  5. 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)

  6. 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

  7. WPDD workshop on: 'safe, efficient, and cost-effective decommissioning'. Workshop Conclusions/Final Stocktaking

    International Nuclear Information System (INIS)

    2005-01-01

    On September 6-10, 2004 a workshop on 'Safe, Efficient, and Cost-Effective Decommissioning' was held in Rome (Italy) to enable international experts on decommissioning to compare and evaluate respective approaches and experiences in decommissioning nuclear power and fuel cycle facilities and to formulate proposals for future international cooperation in the decommissioning arena. The main messages emerging from the workshop are: - Decommissioning is a mature industrial process and many projects have been safely completed with support of local communities. Technical and scientific issues are well-understood and practical experience and associated lessons are being documented to guide future activities. Emphasis is being placed on effective planning with active programmes of community involvement. - Individual countries need to further develop integrated decommissioning and waste management strategies to ensure that long-term solutions will be available for all wastes generated from decommissioning. National systems are evolving to meet national needs, against a framework provided by the international organisations, and these seem increasingly to favour early dismantling regardless of the availability of waste disposal routes. - Realistic and streamlined regulatory programmes are being developed with feed back from industry experience and are placing more responsibility and accountability on licensees. - Accurate decommissioning waste cost calculation methods is needed. Waste volumes may vary from project to project even for similar installations. There though appears to be a strong case for accumulating data and benchmarking costs for similar plants and processes. Further work and experience exchange on cost comparisons between different strategies (for example clearance and recycling/reuse of materials versus direct surface disposal) would be valuable. - International clearance criteria have been established, with individual countries free to adopt them

  8. Constructing Predictive Estimates for Worker Exposure to Radioactivity During Decommissioning: Analysis of Completed Decommissioning Projects - Master Thesis

    Energy Technology Data Exchange (ETDEWEB)

    Dettmers, Dana Lee; Eide, Steven Arvid

    2002-10-01

    An analysis of completed decommissioning projects is used to construct predictive estimates for worker exposure to radioactivity during decommissioning activities. The preferred organizational method for the completed decommissioning project data is to divide the data by type of facility, whether decommissioning was performed on part of the facility or the complete facility, and the level of radiation within the facility prior to decommissioning (low, medium, or high). Additional data analysis shows that there is not a downward trend in worker exposure data over time. Also, the use of a standard estimate for worker exposure to radioactivity may be a best estimate for low complete storage, high partial storage, and medium reactor facilities; a conservative estimate for some low level of facility radiation facilities (reactor complete, research complete, pits/ponds, other), medium partial process facilities, and high complete research facilities; and an underestimate for the remaining facilities. Limited data are available to compare different decommissioning alternatives, so the available data are reported and no conclusions can been drawn. It is recommended that all DOE sites and the NRC use a similar method to document worker hours, worker exposure to radiation (person-rem), and standard industrial accidents, injuries, and deaths for all completed decommissioning activities.

  9. Technology, Safety and Costs of Decommissioning a Reference Uranium Hexafluoride Conversion Plant

    Energy Technology Data Exchange (ETDEWEB)

    Elder, H. K.

    1981-10-01

    Safety and cost information is developed for the conceptual decommissioning of a commercial uranium hexafluoride conversion (UF{sub 6}) plant. Two basic decommissioning alternatives are studied to obtain comparisons between cost and safety impacts: DECON, and passive SAFSTOR. A third alternative, DECON of the plant and equipment with stabilization and long-term care of lagoon wastes. is also examined. DECON includes the immediate removal (following plant shutdown) of all radioactivity in excess of unrestricted release levels, with subsequent release of the site for public use. Passive SAFSTOR requires decontamination, preparation, maintenance, and surveillance for a period of time after shutdown, followed by deferred decontamination and unrestricted release. DECON with stabilization and long-term care of lagoon wastes (process wastes generated at the reference plant and stored onsite during plant operation} is also considered as a decommissioning method, although its acceptability has not yet been determined by the NRC. The decommissioning methods assumed for use in each decommissioning alternative are based on state-of-the-art technology. The elapsed time following plant shutdown required to perform the decommissioning work in each alternative is estimated to be: for DECON, 8 months; for passive SAFSTOR, 3 months to prepare the plant for safe storage and 8 months to accomplish deferred decontamination. Planning and preparation for decommissioning prior to plant shutdown is estimated to require about 6 months for either DECON or passive SAFSTOR. Planning and preparation prior to starting deferred decontamination is estimated to require an additional 6 months. OECON with lagoon waste stabilization is estimated to take 6 months for planning and about 8 months to perform the decommissioning work. Decommissioning cost, in 1981 dollars, is estimated to be $5.91 million for OECON. For passive SAFSTOR, preparing the facility for safe storage is estimated to cost $0

  10. Safety analysis for the 233-S decontamination and decommissioning project

    International Nuclear Information System (INIS)

    Thoren, S.

    1996-08-01

    Decommissioning of the 233-S Plutonium Concentration Facility (REDOX) is a proposed expedited response action that is regulated by the Comprehensive Environmental Response Compensation and Liability Act of 1980 and the Hanford Federal Facility Agreement and Consent Order. Due to progressive physical deterioration of this facility, a decontamination and decommissioning plan is being considered for the immediate future. This safety analysis describes the proposed actions involved in this D ampersand D effort; identifies the radioactive material inventories involved; reviews site specific environmental characteristics and postulates an accident scenario that is evaluated to identify resultant effects

  11. Technology, safety, and costs of decommissioning reference nuclear research and test reactors. Appendices

    International Nuclear Information System (INIS)

    Konzek, G.J.; Ludwick, J.D.; Kennedy, W.E. Jr.; Smith, R.I.

    1982-03-01

    Safety and Cost Information is developed for the conceptual decommissioning of two representative licensed nuclear research and test reactors. Three decommissioning alternatives are studied to obtain comparisons between costs (in 1981 dollars), occupational radiation doses, potential radiation dose to the public, and other safety impacts. The alternatives considered are: DECON (immediate decontamination), SAFSTOR (safe storage followed by deferred decontamination), and EMTOMB (entombment). The study results are presented in two volumes. Volume 2 (Appendices) contains the detailed data that support the results given in Volume 1, including unit-component data

  12. Technology, safety, and costs of decommissioning reference nuclear research and test reactors. Appendices

    Energy Technology Data Exchange (ETDEWEB)

    Konzek, G.J.; Ludwick, J.D.; Kennedy, W.E. Jr.; Smith, R.I.

    1982-03-01

    Safety and Cost Information is developed for the conceptual decommissioning of two representative licensed nuclear research and test reactors. Three decommissioning alternatives are studied to obtain comparisons between costs (in 1981 dollars), occupational radiation doses, potential radiation dose to the public, and other safety impacts. The alternatives considered are: DECON (immediate decontamination), SAFSTOR (safe storage followed by deferred decontamination), and EMTOMB (entombment). The study results are presented in two volumes. Volume 2 (Appendices) contains the detailed data that support the results given in Volume 1, including unit-component data.

  13. Decommissioning Programme Management: reducing risk and cost while accelerating schedules through improved planning, Earned Value Management and safe work execution

    International Nuclear Information System (INIS)

    Hansen, S.E.

    2008-01-01

    CH2M HILL experience includes more than two decades of managing nuclear facilities and providing clean-up and operations support for commercial and government facilities worldwide. Our expertise ranges from decommissioning and defence sector businesses to nuclear technology development and innovation. Our approach places top priority on the safe execution of work while reducing both risk and cost. Our nuclear services include: programme management, nuclear safety analysis, radiological protection, radioactive waste management, nuclear remediation, nuclear materials and waste transportation management, nuclear safeguards and security services, and nuclear decontamination and decommissioning. This paper will discuss our approach which has resulted in a strong track record of accelerating schedules and reducing costs of major nuclear programmes, including Rocky Flats, Idaho, and our work at UKAEA sites. (author)

  14. 77 FR 64361 - Report on Waste Burial Charges: Changes in Decommissioning Waste Disposal Costs at Low-Level...

    Science.gov (United States)

    2012-10-19

    ... Decommissioning Waste Disposal Costs at Low-Level Waste Burial Facilities AGENCY: Nuclear Regulatory Commission... 15, ``Report on Waste Burial Charges: Changes in Decommissioning Waste Disposal Costs at Low-Level... for low-level waste. DATES: Submit comments by November 15, 2012. Comments received after this date...

  15. Technology, safety and costs of decommissioning a reference small mixed oxide fuel fabrication plant. Volume 1. Main report

    Energy Technology Data Exchange (ETDEWEB)

    Jenkins, C. E.; Murphy, E. S.; Schneider, K J

    1979-01-01

    Detailed technology, safety and cost information are presented for the conceptual decommissioning of a reference small mixed oxide fuel fabrication plant. Alternate methods of decommissioning are described including immediate dismantlement, safe storage for a period of time followed by dismantlement and entombment. Safety analyses, both occupational and public, and cost evaluations were conducted for each mode.

  16. Decontamination and decommissioning waste characterization and cost estimates from historical records

    International Nuclear Information System (INIS)

    Hootman, H.E.

    1994-01-01

    There are more than 600 facilities at the Savannah River Site (SRS) that are contaminated with either radioactivity, hazardous chemicals, or asbestos. The more significant facilities can be separated into broad categories for decontamination and decommissioning (D ampersand D) planning such as plutonium facilities, waste tanks, chemical separations canyons, and nuclear reactors. Uncertainties exist in the timing, extent of stabilization, and D ampersand D required for these production facilities. Detailed analyses of the risk, costs, and engineering feasibility are needed to define production facility end states to ensure expected reduction in health and environmental risk. In the meantime, scoping projections are required to satisfy Department of Energy (DOE) requirements for 30 year plans, and to indicate where detailed analysis should be funded

  17. Methodology to collect data on decommissioning costs and occupational radiation exposure

    International Nuclear Information System (INIS)

    Petrasch, P.; Roger, J.

    1993-01-01

    Decommissioning data collection has been, up to now, almost a national matter. The present joint study performed by NIS Ingenieurgesellschaft mbH, Hanau, and the Commissariat a l'energie atomique, Unite de declassement d'installations nucleaires, and coordinated by the Commission of the European Communities, is intended to identify a methodology allowing the collection of data which are useful to manage a decommissioning project, e.g. data on dismantling costs, occupational radiation exposure and waste arisings. A common structure for decommissioning tasks (called working packages) derived from those already in use at the abovementioned organizations has been established and the corresponding first series of data-collection sheets defined in order to cover data from LWRs, GCRs (UNGGs) and nuclear fuel cycle installations. Work focused on the cost of decommissioning tasks. The study is intended to be a first step towards an EC-wide usable data-base for data generated in the various ongoing and future decommissioning projects

  18. Guide for International Peer Reviews of Decommissioning Cost Studies for Nuclear Facilities

    International Nuclear Information System (INIS)

    LaGuardia, Thomas S.; Pescatore, Claudio; )

    2014-01-01

    Peer reviews are a standard co-operative OECD working tool that offer member countries a framework to compare experiences and examine best practices in a host of areas. The OECD Nuclear Energy Agency (NEA) has developed a proven methodology for conducting peer reviews in radioactive waste management and nuclear R and D. Using this methodology, the NEA Radioactive Waste Management Committee's Working Party on Decommissioning and Dismantling (WPDD) developed the present guide as a framework for decommissioning cost reviewers and reviewees to prepare for and conduct international peer reviews of decommissioning cost estimate studies for nuclear facilities. It includes checklists that will help national programmes or relevant organisations to assess and improve decommissioning cost estimate practices in the future. This guide will act as the NEA reference for conducting such international peer reviews. The remainder of this guide is divided into eight chapters. Chapter 2 describes gathering the cost estimate study and underpinning documents, reviewing the study and writing a final report. Chapter 3 provides a detailed checklist approach for the review of the cost study report. Chapter 4 provides checklists to assist in reviewing benchmarked information. Chapter 5 provides comments on the approach and recommendations for use of this guide. Chapters 6 and 7 provide the background material used in developing this guide and Chapter 8 provides a list of the abbreviations and acronyms used in this guide

  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. 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

  1. 26 CFR 1.468A-1T - Nuclear decommissioning costs; general rules (temporary).

    Science.gov (United States)

    2010-04-01

    ... accrual method of accounting that do not elect the application of section 468A are not allowed a deduction... (temporary). 1.468A-1T Section 1.468A-1T Internal Revenue INTERNAL REVENUE SERVICE, DEPARTMENT OF THE...-1T Nuclear decommissioning costs; general rules (temporary). (a) Introduction. Section 468A provides...

  2. Safety analysis factors for environmental restoration and decontamination and decommissioning

    International Nuclear Information System (INIS)

    Ellingson, D.R.

    1993-04-01

    Environmental restoration (ER) and facility decontamination/decommissioning (D ampersand D) operations can be grouped into two general categories. ''Nonstationary cleanup'' or simply ''cleanup'' activities are where the operation must relocate to the site of new contaminated material at the completion of each task (i.e., the operation moves to the contaminated material). ''Stationary production'' or simply ''production'' activities are where the contaminated material is moved to a centralized location (i.e., the contaminated material is moved to the operation) for analysis, sorting, treatment, storage, and disposal. This paper addresses the issue of nonstationary cleanup design. The following are the specific assigned action items: Collect and compile a list of special safety-related ER/D ampersand D design factors, especially ones that don't follow DOE Order 6430.1A requirements. Develop proposal of what makes sense to recommend to designers; especially consider recommendations for short-term projects. Present proposal at the January meeting. To achieve the action items, applicable US Department of Energy (DOE) design requirements, and cleanup operations and differences from production activities are reviewed and summarized; basic safety requirements influencing design are summarized; and finally, approaches, considerations, and methods for safe, cost-effective design of cleanup activities are discussed

  3. Estimating boiling water reactor decommissioning costs. A user's manual for the BWR Cost Estimating Computer Program (CECP) software: Draft report for comment

    International Nuclear Information System (INIS)

    Bierschbach, M.C.

    1994-12-01

    With the issuance of the Decommissioning Rule (July 27, 1988), nuclear power plant licensees are required to submit to the U.S. Regulatory Commission (NRC) for review, decommissioning plans and cost estimates. This user's manual and the accompanying Cost Estimating Computer Program (CECP) software provide a cost-calculating methodology to the NRC staff that will assist them in assessing the adequacy of the licensee submittals. The CECP, designed to be used on a personal computer, provides estimates for the cost of decommissioning BWR power stations to the point of license termination. Such cost estimates include component, piping, and equipment removal costs; packaging costs; decontamination costs; transportation costs; burial costs; and manpower costs. In addition to costs, the CECP also calculates burial volumes, person-hours, crew-hours, and exposure person-hours associated with decommissioning

  4. Pathways and cost-risk-benefit analyses for INEL radioactively contaminated soil areas being evaluated for decontamination and decommissioning

    International Nuclear Information System (INIS)

    Chapin, J.A.

    1980-12-01

    Several radioactively contaminated soil areas exist at the Idaho National Engineering Laboratory; virtually all are contaminated with nuclides of cesium, strontium, and cobalt at low levels of activity. This study develops a method of analysis to determine cost effective alternatives for decommissioning these areas, considering risk to the workers and general public, as well as the benefits to be gained. Because much of the input data to the analysis is highly subjective and detailed radiological characterization of the soil areas is minimal, it was decided that an analysis based on a relative weighting method be employed. The results of this analysis constitute a relative prioritization list of the soil areas being considered for decommissioning as well as the recommended decommissioning alternatives. The results of this analysis indicate that, of the 46 areas considered, 11 should be left in place under protective storage and 16 should be left as is. Nineteen areas were not analyzed because they were either operational or characterization data were not available. These results are based on a maximum exposure to a member of the general population, through realistic exposure pathways, of 5 mrem/yr

  5. Decommissioning of the nuclear facilities at Risoe National Laboratory. Descriptions and cost assessment

    International Nuclear Information System (INIS)

    Lauridsen, Kurt

    2001-02-01

    The report is the result of a project initiated by Risoe National Laboratory in June 2000 on request from the Minister of Research and Information Technology. It describes the nuclear facilities at Risoe National Laboratory to be decommissioned and gives an assessment of the work to be done and the costs incurred. Three decommissioning scenarios were considered with decay times of 10, 25 and 40 years for the DR 3 reactor. The assessments conclude, however, that there will not be much to gain by allowing for the longer decay periods; some operations still will need to be performed remotely. Furthermore, the report describes some of the legal and licensing framework for the decommissioning and gives an assessment of the amounts of radioactive waste to be transferred to a Danish repository. (au)

  6. Decommissioning of the nuclear facilities at Risoe National Laboratory. Descriptions and cost assessment[Denmark

    Energy Technology Data Exchange (ETDEWEB)

    Lauridsen, Kurt [ed.

    2001-02-01

    The report is the result of a project initiated by Risoe National Laboratory in June 2000 on request from the Minister of Research and Information Technology. It describes the nuclear facilities at Risoe National Laboratory to be decommissioned and gives an assessment of the work to be done and the costs incurred. Three decommissioning scenarios were considered with decay times of 10, 25 and 40 years for the DR 3 reactor. The assessments conclude, however, that there will not be much to gain by allowing for the longer decay periods; some operations still will need to be performed remotely. Furthermore, the report describes some of the legal and licensing framework for the decommissioning and gives an assessment of the amounts of radioactive waste to be transferred to a Danish repository. (au)

  7. Technology, safety, and costs of decommissioning a reference pressurized water reactor power station

    International Nuclear Information System (INIS)

    Smith, R.I.; Konzek, G.J.; Kennedy, W.E. Jr.

    1978-05-01

    Safety and cost information was developed for the conceptual decommissioning of a large [1175 MW(e)] pressurized water reactor (PWR) power station. Two approaches to decommissioning, Immediate Dismantlement and Safe Storage with Deferred Dismantlement, were studied to obtain comparisons between costs, occupational radiation doses, potential radiation dose to the public, and other safety impacts. Immediate Dismantlement was estimated to require about six years to complete, including two years of planning and preparation prior to final reactor shutdown, at a cost of $42 million, and accumulated occupational radiation dose, excluding transport operations, of about 1200 man-rem. Preparations for Safe Storage were estimated to require about three years to complete, including 1 1 / 2 years for planning and preparation prior to final reactor shutdown, at a cost of $13 million and an accumulated occupational radiation dose of about 420 man-rem. The cost of continuing care during the Safe Storage period was estimated to be about $80 thousand annually. Accumulated occupational radiation dose during the Safe Storage period was estimated to range from about 10 man-rem for the first 10 years to about 14 man-rem after 30 years or more. The cost of decommissioning by Safe Storage with Deferred Dismantlement was estimated to be slightly higher than Immediate Dismantlement. Cost reductions resulting from reduced volumes of radioactive material for disposal, due to the decay of the radioactive containments during the deferment period, are offset by the accumulated costs of surveillance and maintenance during the Safe Storage period

  8. Cost analysis guidelines

    International Nuclear Information System (INIS)

    Strait, R.S.

    1996-01-01

    The first phase of the Depleted Uranium Hexafluoride Management Program (Program)--management strategy selection--consists of several program elements: Technology Assessment, Engineering Analysis, Cost Analysis, and preparation of an Environmental Impact Statement (EIS). Cost Analysis will estimate the life-cycle costs associated with each of the long-term management strategy alternatives for depleted uranium hexafluoride (UF6). The scope of Cost Analysis will include all major expenditures, from the planning and design stages through decontamination and decommissioning. The costs will be estimated at a scoping or preconceptual design level and are intended to assist decision makers in comparing alternatives for further consideration. They will not be absolute costs or bid-document costs. The purpose of the Cost Analysis Guidelines is to establish a consistent approach to analyzing of cost alternatives for managing Department of Energy's (DOE's) stocks of depleted uranium hexafluoride (DUF6). The component modules that make up the DUF6 management program differ substantially in operational maintenance, process-options, requirements for R and D, equipment, facilities, regulatory compliance, (O and M), and operations risk. To facilitate a consistent and equitable comparison of costs, the guidelines offer common definitions, assumptions or basis, and limitations integrated with a standard approach to the analysis. Further, the goal is to evaluate total net life-cycle costs and display them in a way that gives DOE the capability to evaluate a variety of overall DUF6 management strategies, including commercial potential. The cost estimates reflect the preconceptual level of the designs. They will be appropriate for distinguishing among management strategies

  9. 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

  10. Decommissioning Handbook

    International Nuclear Information System (INIS)

    Cusack, J.G.; Dalfonso, P.H.; Lenyk, R.G.

    1994-01-01

    The Decommissioning Handbook provides technical guidance on conducting decommissioning projects. Information presented ranges from planning logic, regulations affecting decommissioning, technology discussion, health and safety requirements, an developing a cost estimate. The major focus of the handbook are the technologies -- decontamination technologies, waste treatment, dismantling/segmenting/demolition, and remote operations. Over 90 technologies are discussed in the handbook providing descriptions, applications, and advantages/disadvantages. The handbook was prepared to provide a compendium of available or potentially available technologies in order to aid the planner in meeting the specific needs of each decommissioning project. Other subjects presented in the Decommissioning Handbook include the decommissioning plan, characterization, final project configuration based planning, environmental protection, and packaging/transportation. These discussions are presented to complement the technologies presented in the handbook

  11. 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.)

  12. 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

  13. 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

  14. Transuranium contamination in BWRs after fuel accidents and its impact on decommissioning exposures and costs

    Energy Technology Data Exchange (ETDEWEB)

    Lundgren, K.

    1996-12-01

    The theme of the present study is to quantify the amount of transuranium activity in different parts of the plant after various fuel accidents, and which impact such contamination has on radiation exposure and costs for decommissioning the plant. The consequences of four different accident degrees have been treated: Common fuel failures, e.g. in line with recent experiences from Swedish BWRs; Fuel channel obstruction resulting in partial melting of one fuel assembly; Total loss of electric power resulting in partial meltdown of the core, but with primary circuit intact preventing a massive contamination of the containment; A LOCA followed by a core meltdown and melting and penetration of the reactor pressure vessel. The amount of transuranium activity distributed, the form of this activity and the plant contamination are evaluated for these accidents. The costs and exposures have been split up on cleanup activities after the accident and decommissioning. 75 refs.

  15. Transuranium contamination in BWRs after fuel accidents and its impact on decommissioning exposures and costs

    International Nuclear Information System (INIS)

    Lundgren, K.

    1996-12-01

    The theme of the present study is to quantify the amount of transuranium activity in different parts of the plant after various fuel accidents, and which impact such contamination has on radiation exposure and costs for decommissioning the plant. The consequences of four different accident degrees have been treated: Common fuel failures, e.g. in line with recent experiences from Swedish BWRs; Fuel channel obstruction resulting in partial melting of one fuel assembly; Total loss of electric power resulting in partial meltdown of the core, but with primary circuit intact preventing a massive contamination of the containment; A LOCA followed by a core meltdown and melting and penetration of the reactor pressure vessel. The amount of transuranium activity distributed, the form of this activity and the plant contamination are evaluated for these accidents. The costs and exposures have been split up on cleanup activities after the accident and decommissioning. 75 refs

  16. Technology, safety and costs of decommissioning a reference small mixed oxide fuel fabrication plant. Volume 2. Appendices

    Energy Technology Data Exchange (ETDEWEB)

    Jenkins, C. E.; Murphy, E. S.; Schneider, K. J.

    1979-01-01

    Volume 2 contains appendixes on small MOX fuel fabrication facility description, site description, residual radionuclide inventory estimates, decommissioning, financing, radiation dose methodology, general considerations, packaging and shipping of radioactive materials, cost assessment, and safety (JRD)

  17. Decommissioning Handbook

    Energy Technology Data Exchange (ETDEWEB)

    1994-03-01

    The Decommissioning Handbook is a technical guide for the decommissioning of nuclear facilities. The decommissioning of a nuclear facility involves the removal of the radioactive and, for practical reasons, hazardous materials to enable the facility to be released and not represent a further risk to human health and the environment. This handbook identifies and technologies and techniques that will accomplish these objectives. The emphasis in this handbook is on characterization; waste treatment; decontamination; dismantling, segmenting, demolition; and remote technologies. Other aspects that are discussed in some detail include the regulations governing decommissioning, worker and environmental protection, and packaging and transportation of the waste materials. The handbook describes in general terms the overall decommissioning project, including planning, cost estimating, and operating practices that would ease preparation of the Decommissioning Plan and the decommissioning itself. The reader is referred to other documents for more detailed information. This Decommissioning Handbook has been prepared by Enserch Environmental Corporation for the US Department of Energy and is a complete restructuring of the original handbook developed in 1980 by Nuclear Energy Services. The significant changes between the two documents are the addition of current and the deletion of obsolete technologies and the addition of chapters on project planning and the Decommissioning Plan, regulatory requirements, characterization, remote technology, and packaging and transportation of the waste materials.

  18. Technical support to the social cost study of Ignalina NPP decommissioning

    International Nuclear Information System (INIS)

    Vitkiene, E.

    2001-01-01

    Description of Phare project on assessment of social cost related with decommissioning of unit 1 of Ignalina NPP is presented. This is the first project of social guarantees in Visaginas financed by European Commission Project will develop pilot studies aimed at encouraging small and medium size business in Visaginas, creating new jobs, employment of young people. The project will also consult about the activities of the said projects, inform the community about the things being done to mitigate social impact

  19. Decommissioning of the nuclear facilities at Risoe National Laboratory. Descriptions and cost assessment. Danish summary

    International Nuclear Information System (INIS)

    Lauridsen, Kurt

    2001-02-01

    The report gives a brief description of relevant aspects of the decommissioning of all nuclear facilities at Risoe National Laboratory, including the necessary operations to be performed and the associated costs. Together with a more detailed report, written in English, this report is the result of a project initiated by Risoe in the summer of 2000. The English report has undergone an international review, the results of which are summarised in the present report. (au)

  20. Radiochemical analysis of concrete samples for decommission of nuclear reactors

    Energy Technology Data Exchange (ETDEWEB)

    Zapata-Garcia, Daniel; Wershofen, Herbert [Physikalisch-Technische Bundesanstalt (PTB), Bundesallee 100 38116, Braunschweig (Germany); Larijani, Cyrus; Sobrino-Petrirena, Maitane; Garcia-Miranda, Maria; Jerome, Simon M. [National Physical Laboratory (NPL), Hampton Road, Teddington, Middlesex, TW11 0LW (United Kingdom)

    2014-07-01

    Decommissioning of the oldest nuclear power reactors are some of the most challenging technological legacy issues many countries will face in forthcoming years, as many power reactors reach the end of their design lives. Decommissioning of nuclear reactors generates large amounts of waste that need to be classified according to their radioactive content. Approximately 10 % of the contaminated material ends up in different repositories (depending on their level of contamination) while the rest is decontaminated, measured and released into the environment or sent for recycling. Such classification needs to be done accurately in order to ensure that both the personnel involved in decommissioning and the population at large are not needlessly exposed to radiation or radioactive material and to minimise the environmental impact of such work. However, too conservative classification strategies should not be applied, in order to make proper use of radioactive waste repositories since space is limited and the full process must be cost-effective. Implicit in decommissioning and classification of waste is the need to analyse large amounts of material which usually combine a complex matrix with a non-homogeneous distribution of the radionuclides. Because the costs involved are large, it is possible to make great savings by the adoption of best available practices, such as the use of validated methods for on-site measurements and simultaneous determination of more than one radionuclide whenever possible. The work we present deals with the development and the validation of a procedure for the simultaneous determination of {sup 241}Am, plutonium isotopes, uranium isotopes and {sup 90}Sr in concrete samples. Samples are firstly ground and fused with LiBO{sub 2} and Li{sub 2}B{sub 4}O{sub 7}. After dissolution of the fused sample, silicate and alkaline elements are removed followed by radiochemical separation of the target radionuclides using extraction chromatography. Measurement

  1. Study on the Development of Methodology for Cost Calculations and Financial Planning of Decommissioning Operations

    International Nuclear Information System (INIS)

    2001-12-01

    The following study deals with the development of methodology for cost calculations and financial planning of decommissioning operations. It has been carried out by EDF / FRAMATOME / VUJE / SCK-CEN in the frame of the contract B7-032/2000/291058/MAR/C2 awarded by the European Commission. This study consists of 4 parts. The first task objective is to develop a reliable and transparent methodology for cost assessment and financial planning sufficient precise but without long and in depth investigations and studies. This methodology mainly contains: Calculation methods and algorithms for the elaboration of costs items making up the whole decommissioning cost. Estimated or standard values for the parameters and for the cost factors to be used in the above-mentioned algorithms Financial mechanism to be applied as to establish a financial planning. The second part task is the provision of standard values for the different parameters and costs factors described in the above-mentioned algorithms. This provision of data is based on the own various experience acquired by the members of the working team and on existing international references (databases, publications and reports). As decommissioning operations are spreading over several dozens of years, the scope of this task the description of the financial mechanisms to be applied to the different cost items as to establish a complete financial cost. It takes into account the financial schedule issued in task 1. The scope of this task consists in bringing together in a guideline all the information collected before: algorithms, data and financial mechanisms. (A.L.B.)

  2. Guidelines for producing commercial nuclear power plant decommissioning cost estimates

    International Nuclear Information System (INIS)

    La Guardia, T.S.

    1986-01-01

    The guidelines are not intended to be a ''cookbook'' or a ''standard''. Their purpose is to ensure all decomissioning cost elements are properly included and to provide guidance on the detail required. Other methodologies may be used if they accomplish this objective

  3. Decommissioning of Brennilis NPP

    International Nuclear Information System (INIS)

    Baize, Jean-Marc

    1998-01-01

    This EDF press communique give information related to the decommissioning of the Brennilis NPP. The following five items are developed in this report: 1. the level-2 decommissioning operations at the Brennilis NPP; 2. the Brennilis NPP, a pilot operation from the commissioning up to the decommissioning; 3. history of the Brennilis NPP decommissioning; 4. the types of radioactive wastes generated by the Brennilis NPP decommissioning; 5. the Brennilis NPP - a yard management as a function of the wastes. The document contains also seven appendices addressing the following subjects: 1. the share of decommissioning assigned to EDF and the decommissioning steps; 2. the EDF installations in course of decommissioning; 3. the CEA decommissioned installations or in course of decommissioning; 4. regulations; 5. costs; 6. waste management - principles; 7. data on the decommissioning yard

  4. 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)

  5. 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)

  6. The impact of the internalisation of the decommissioning costs at Cernavoda NPP

    International Nuclear Information System (INIS)

    Metes, Mircea; Goicea, Andrei

    2004-01-01

    The 'decommissioning of the nuclear power plant' means to release the site where a nuclear installation has been operated in such manner that this site could be further used, without any restriction, by the present or future generations. This is an important and complex requirement related to sustainable development. The decommissioning is a complicated and costly process; therefore it is imperative to start its preparation as early as possible, to ensure the creation of the necessary financial resources and to carefully schedule all the phases to be performed after the plant's permanently shutdown. The paper presents different possible strategies for the decommissioning, recommended by the International Atomic Energy Agency-Vienna, as well as some elements of the decommissioning experience acquired in the world. Special attention is given to the issue of the financial resources which must be provided by the nuclear power plant, during its operational life, with the corresponding impact on the cost of the electrical energy delivered by the plant. The practice of the internalization of the decommissioning costs is worldwide accepted; it is an approach specific to nuclear sector, proving once more its compatibility with the environmental protection and sustainable development. The sustainable development consists in such solutions that are able to satisfy the needs of the present generation without hampering the ability of the future generations to satisfy their own needs. In the nuclear energy sector, sustainability is provided by the following specific features: (1) Nuclear energy was and shall be in the future an important factor in security of energy supply. Due to the availability of the primary energy resources (fissile and fertile materials), nuclear electricity is and shall be accessible at affordable price on a permanent and reliable basis. (2) Nuclear energy as a part of the energy mix can diminish non-renewable energy consumption, prevent the exhaustion of

  7. Technology, safety and costs of decommissioning a reference boiling water reactor power station. Volume 1. Main report. Technical report, September 1977-October 1979

    International Nuclear Information System (INIS)

    Oak, H.D.; Holter, G.M.; Kennedy, W.E. Jr.; Konzek, G.J.

    1980-06-01

    Technology, safety and cost information is given for the conceptual decommissioning of a large (1100MWe) boiling water reactor (BWR) power station. Three approaches to decommissioning, immediate dismantlement, safe storage with deferred dismantlement and entombment, were studied to obtain comparisons between costs, occupational radiation doses, potential dose to the public and other safety impacts. It also shows the sensitivity of decommissioning safety and costs to the power rating of a BWR in the range of 200 to 1100 MWE

  8. Technology, safety and costs of decommissioning a reference boiling water reactor power station. Volume 1. Main report. Technical report, September 1977-October 1979

    Energy Technology Data Exchange (ETDEWEB)

    Oak, H.D.; Holter, G.M.; Kennedy, W.E. Jr.; Konzek, G.J.

    1980-06-01

    Technology, safety and cost information is given for the conceptual decommissioning of a large (1100MWe) boiling water reactor (BWR) power station. Three approaches to decommissioning, immediate dismantlement, safe storage with deferred dismantlement and entombment, were studied to obtain comparisons between costs, occupational radiation doses, potential dose to the public and other safety impacts. It also shows the sensitivity of decommissioning safety and costs to the power rating of a BWR in the range of 200 to 1100 MWE.

  9. 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

    extensive rework during the decommissioning phase. 3D technologies have the potential for minimising knowledge loss during the transition to decommissioning, and support efficient reconstruction of design and other knowledge supporting more optimised decommissioning strategies. Application of advanced 3D visualisation technologies are applied for planning the manipulation of heavy large components in decommissioning projects. With the decreasing time and cost investment required for application of 3D simulation and AR technology, an increasing number of experts are exploring the possibilities in using such methods for supporting on-site logistics (categorisation, transportation, and temporary storage) of contaminated and activated components during decommissioning. 3D radiological simulation and visualisation technology provides a new more efficient way for explaining complex radiological conditions, work plans, and compliance with regulatory requirements. Advanced support systems based on 3D technologies have successfully been applied in the decommissioning of a number of nuclear installations (e.g. Fugen NPP, Chernobyl NPP, Leningrad NPP, Andreeva Bay branch of Northwest Center for Radioactive Waste Management in NW Russia) for increasing safety and optimising costs. For further details the reader is referred to the literature

  10. Upside, downside: Who should bear the unanticipated costs of nuclear decommissioning?

    International Nuclear Information System (INIS)

    Riddich, L.A.

    1994-01-01

    A great deal of attention is currently being directed to issues surrounding the decommissioning of nuclear generation plants. Chief among these is determining the best way to recover the associated costs. The cost-recovery procedure should be tied to three things: (1) the nature of the business risks created by nuclear power, (2) who bears those risks now, and (3) who has historically been compensated for bearing those risks in the past. Further, and important analogy can be made to past experience with utilities' diversification into other areas of business. It is important for regulators to balance the costs to the customer against the compensation that investors have already received for bearing the risk of nuclear power. Each case will be different, but it is neither fair nor wise to force all costs on customers

  11. 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.

  12. 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)

  13. Technology, Safety and Costs of Decommissioning a Reference Low-Level Waste Burial Ground. Appendices

    International Nuclear Information System (INIS)

    None

    1980-01-01

    Safety and cost information are developed for the conceptual decommissioning of commercial low-level waste (LLW) burial grounds. Two generic burial grounds, one located on an arid western site and the other located on a humid eastern site, are used as reference facilities for the study. The two burial grounds are assumed to have the same site capacity for waste, the same radioactive waste inventory, and similar trench characteristics and operating procedures. The climate, geology. and hydrology of the two sites are chosen to be typical of real western and eastern sites. Volume 2 (Appendices) contains the detailed analyses and data needed to support the results given in Volume 1.

  14. Technology, Safety and Costs of Decommissioning a Reference Low-Level Waste Burial Ground. Main Report

    International Nuclear Information System (INIS)

    Murphy, E. S.; Holter, G. M.

    1980-01-01

    Safety and cost information are developed for the conceptual decommissioning of commercial low-level waste (LLW) burial grounds. Two generic burial grounds, one located on an arid western site and the other located on a humid eastern site, are used as reference facilities for the study. The two burial grounds are assumed to have the same site capacity for waste, the same radioactive waste inventory, and similar trench characteristics and operating procedures. The climate, geology. and hydrology of the two sites are chosen to be typical of real western and eastern sites. Volume 1 (Main Report) contains background information and study results in summary form.

  15. Technology, Safety and Costs of Decommissioning a Reference Low-Level Waste Burial Ground. Main Report

    Energy Technology Data Exchange (ETDEWEB)

    Murphy, E. S.; Holter, G. M.

    1980-06-01

    Safety and cost information are developed for the conceptual decommissioning of commercial low-level waste (LLW) burial grounds. Two generic burial grounds, one located on an arid western site and the other located on a humid eastern site, are used as reference facilities for the study. The two burial grounds are assumed to have the same site capacity for waste, the same radioactive waste inventory, and similar trench characteristics and operating procedures. The climate, geology. and hydrology of the two sites are chosen to be typical of real western and eastern sites. Volume 1 (Main Report) contains background information and study results in summary form.

  16. Deactivation and Decommissioning Planning and Analysis with Geographic Information Systems

    International Nuclear Information System (INIS)

    Bollinger, James S.; Koffman, Larry D.; Austin, William E.

    2008-01-01

    From the mid-1950's through the 1980's, the U.S. Department of Energy's Savannah River Site produced nuclear materials for the weapons stockpile, for medical and industrial applications, and for space exploration. Although SRS has a continuing defense-related mission, the overall site mission is now oriented toward environmental restoration and management of legacy chemical and nuclear waste. With the change in mission, SRS no longer has a need for much of the infrastructure developed to support the weapons program. This excess infrastructure, which includes over 1000 facilities, will be decommissioned and demolished over the forthcoming years. Dis-positioning facilities for decommissioning and deactivation requires significant resources to determine hazards, structure type, and a rough-order-of-magnitude estimate for the decommissioning and demolition cost. Geographic information systems (GIS) technology was used to help manage the process of dis-positioning infrastructure and for reporting the future status of impacted facilities. Several thousand facilities of various ages and conditions are present at SRS. Many of these facilities, built to support previous defense-related missions, now represent a potential hazard and cost for maintenance and surveillance. To reduce costs and the hazards associated with this excess infrastructure, SRS has developed an ambitious plan to decommission and demolish unneeded facilities in a systematic fashion. GIS technology was used to assist development of this plan by: providing locational information for remote facilities, identifying the location of known waste units adjacent to buildings slated for demolition, and for providing a powerful visual representation of the impact of the overall plan. Several steps were required for the development of the infrastructure GIS model. The first step involved creating an accurate and current GIS representation of the infrastructure data. This data is maintained in a Computer Aided Design

  17. 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

  18. Progress on Radiochemical Analysis for Nuclear Waste Management in Decommissioning

    DEFF Research Database (Denmark)

    Hou, Xiaolin; Qiao, Jixin; Shi, Keliang

    With the increaed numbers of nuclear facilities have been closed and are being or are going to be decommissioned, it is required to characterise the produced nuclear waste for its treatment by identification of the radionuclides and qualitatively determine them. Of the radionuclides related...... separation of radionuclides. In order to improve and maintain the Nodic competence in analysis of radionculides in waste samples, a NKS B project on this topic was launched in 2009. During the first phase of the NKS-B RadWaste project (2009-2010), a good achivement has been reached on establishment...... of collaboration, identifing the requirements from the Nordic nuclear industries and optimizing and development of some analytical methods (Hou et al. NKS-222, 2010). In the year 2011, this project (NKS-B RadWaste2011) continued. The major achievements of this project in 2011 include: (1) development of a method...

  19. Technology, safety and costs of decommissioning a reference pressurized water reactor power station. Classification of decommissioning wastes. Addendum 3

    International Nuclear Information System (INIS)

    Murphy, E.S.

    1984-09-01

    The radioactive wastes expected to result from decommissioning of the reference pressurized water reactor power station are reviewed and classified in accordance with 10 CFR 61. The 17,885 cubic meters of waste from DECON are classified as follows: Class A, 98.0%; Class B, 1.2%; Class C, 0.1%. About 0.7% (133 cubic meters) of the waste would be generally unacceptable for disposal using near-surface disposal methods

  20. 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

  1. Review of selected cost drivers for decisions on continued operation of older nuclear reactors. Safety upgrades, lifetime extension, decommissioning

    International Nuclear Information System (INIS)

    1999-05-01

    Lately, the approach to the operation of relatively old NPPs has become an important issue for the nuclear industry for several reasons. First, a large part of operating NPPs will reach the planned end of their lives relatively soon. Replacing these capacities can involve significant investment for the concerned countries and utilities. Second, many operating NPPs while about 30 years old are still in very good condition. Their continued safe operation appears possible and may bring about essential economic gains. Finally, with the costs of new NPPs being rather high at present, continued operation of existing plants and eventually their lifetime extension are viable options for supporting the nuclear share in power generation. This is becoming especially important in view of the growing attention to the issue of global warming and the role of nuclear energy in greenhouse gas mitigation. This report is a review of information related to three cost categories that are part of such cost-benefit analysis: costs of safety upgrades for continued operation of a nuclear unit, costs of lifetime extension and costs of decommissioning. It can serve as a useful reference source for experts and decision makers involved in the economics of operating NPPs

  2. 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.

  3. An Applied Study of Implementation of the Advanced Decommissioning Costing Methodology for Intermediate Storage Facility for Spent Fuel in Studsvik, Sweden with special emphasis to the application of the Omega code

    Energy Technology Data Exchange (ETDEWEB)

    Kristofova, Kristina; Vasko, Marek; Daniska, Vladimir; Ondra, Frantisek; Bezak, Peter [DECOM Slovakia, spol. s.r.o., J. Bottu 2, SK-917 01 Trnava (Slovakia); Lindskog, Staffan [Swedish Nuclear Power Inspectorate, Stockholm (Sweden)

    2007-01-15

    The presented study is focused on an analysis of decommissioning costs for the Intermediate Storage Facility for Spent Fuel (FA) facility in Studsvik prepared by SVAFO and a proposal of the advanced decommissioning costing methodology application. Therefore, this applied study concentrates particularly in the following areas: 1. Analysis of FA facility cost estimates prepared by SVAFO including description of FA facility in Studsvik, summarised input data, applied cost estimates methodology and summarised results from SVAFO study. 2. Discussion of results of the SVAFO analysis, proposals for enhanced cost estimating methodology and upgraded structure of inputs/outputs for decommissioning study for FA facility. 3. Review of costing methodologies with the special emphasis on the advanced costing methodology and cost calculation code OMEGA. 4. Discussion on implementation of the advanced costing methodology for FA facility in Studsvik together with: - identification of areas of implementation; - analyses of local decommissioning infrastructure; - adaptation of the data for the calculation database; - inventory database; and - implementation of the style of work with the computer code OMEGA.

  4. An Applied Study of Implementation of the Advanced Decommissioning Costing Methodology for Intermediate Storage Facility for Spent Fuel in Studsvik, Sweden with special emphasis to the application of the Omega code

    International Nuclear Information System (INIS)

    Kristofova, Kristina; Vasko, Marek; Daniska, Vladimir; Ondra, Frantisek; Bezak, Peter; Lindskog, Staffan

    2007-01-01

    The presented study is focused on an analysis of decommissioning costs for the Intermediate Storage Facility for Spent Fuel (FA) facility in Studsvik prepared by SVAFO and a proposal of the advanced decommissioning costing methodology application. Therefore, this applied study concentrates particularly in the following areas: 1. Analysis of FA facility cost estimates prepared by SVAFO including description of FA facility in Studsvik, summarised input data, applied cost estimates methodology and summarised results from SVAFO study. 2. Discussion of results of the SVAFO analysis, proposals for enhanced cost estimating methodology and upgraded structure of inputs/outputs for decommissioning study for FA facility. 3. Review of costing methodologies with the special emphasis on the advanced costing methodology and cost calculation code OMEGA. 4. Discussion on implementation of the advanced costing methodology for FA facility in Studsvik together with: - identification of areas of implementation; - analyses of local decommissioning infrastructure; - adaptation of the data for the calculation database; - inventory database; and - implementation of the style of work with the computer code OMEGA

  5. 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 ...

  6. Decommissioning handbook

    Energy Technology Data Exchange (ETDEWEB)

    Manion, W.J.; LaGuardia, T.S.

    1980-11-01

    This document is a compilation of information pertinent to the decommissioning of surplus nuclear facilities. This handbook is intended to describe all stages of the decommissioning process including selection of the end product, estimation of the radioactive inventory, estimation of occupational exposures, description of the state-of-the-art in re decontamination, remote csposition of wastes, and estimation of program costs. Presentation of state-of-the-art technology and data related to decommissioning will aid in consistent and efficient program planning and performance. Particular attention is focused on available technology applicable to those decommissioning activities that have not been accomplished before, such as remote segmenting and handling of highly activated 1100 MW(e) light water reactor vessel internals and thick-walled reactor vessels. A summary of available information associated with the planning and estimating of a decommissioning program is also presented. Summarized in particular are the methodologies associated with the calculation and measurement of activated material inventory, distribution, and surface dose level, system contamination inventory and distribution, and work area dose levels. Cost estimating techniques are also presented and the manner in which to account for variations in labor costs as impacting labor-intensive work activities is explained.

  7. Decommissioning handbook

    International Nuclear Information System (INIS)

    Manion, W.J.; LaGuardia, T.S.

    1980-11-01

    This document is a compilation of information pertinent to the decommissioning of surplus nuclear facilities. This handbook is intended to describe all stages of the decommissioning process including selection of the end product, estimation of the radioactive inventory, estimation of occupational exposures, description of the state-of-the-art in re decontamination, remote csposition of wastes, and estimation of program costs. Presentation of state-of-the-art technology and data related to decommissioning will aid in consistent and efficient program planning and performance. Particular attention is focused on available technology applicable to those decommissioning activities that have not been accomplished before, such as remote segmenting and handling of highly activated 1100 MW(e) light water reactor vessel internals and thick-walled reactor vessels. A summary of available information associated with the planning and estimating of a decommissioning program is also presented. Summarized in particular are the methodologies associated with the calculation and measurement of activated material inventory, distribution, and surface dose level, system contamination inventory and distribution, and work area dose levels. Cost estimating techniques are also presented and the manner in which to account for variations in labor costs as impacting labor-intensive work activities is explained

  8. Cost Estimates for the Decontamination and Decommissioning of Eight ORNL Buildings

    International Nuclear Information System (INIS)

    Hogan, M.

    2006-01-01

    The U.S. Department of Energy's Oak Ridge National Laboratory (ORNL) contains a number of buildings that are antiquated and no longer used. These buildings historically were used for the production of atomic weapons and often remain contaminated with radioactive materials. Certain costs and risks are associated with the long-term stewardship of the buildings. One way to reduce these liabilities is to eliminate the buildings that are no longer in use and are not expected to be used in the future. Some of these buildings at ORNL are located in an area known as 'Isotope Circle'. From this area, eight buildings that are expected to be decontaminated and decommissioned (D and D) in the next five to ten years were chosen to have cost estimates completed. The specific facilities are Buildings 3030, 3031, 3118, 3032, 3033, 3033 Annex, 3034, and 3093. There are many challenges for estimating the costs to D and D buildings potentially contaminated with radionuclides. Each building is unique, has various types and levels of contamination, and (as in this case) often lacks up-to-date information. Because of these limitations, order-of- magnitude cost estimates for each of the eight ORNL buildings were completed using parametric cost modeling software known as RACER TM (Remedial Action Cost Engineering and Requirements System). This type of cost estimate is useful for screening technical concepts and is used for budgetary planning. For the eight buildings evaluated in this study, the total cost to D and D was estimated to be nearly $6 M. This value includes the direct cost of approximately $3.5 M to complete D and D and $2.5 M in cost markups. Also, assuming the actual project does not begin until the year 2010, this total cost is escalated to almost $6.7 M, which accounts for expected inflation. Although the cost estimates in this study were expected to have a wide range in accuracy, there are various factors that could impact these estimates in a negative or positive fashion

  9. New techniques for cutting and decontamination for decommissioning of nuclear research reactors with consideration of cost reduction. Final report

    International Nuclear Information System (INIS)

    Bach, W.; Redeker, C.F.; Versemann, R.

    2003-06-01

    In decommissioning of research reactors, specific boundary conditions, such as special materials, nuclides, geometries, spatial circumstances exist. This project aims on the development and adaptation of progressive procedures for decommissioning tasks with respect to economical aspects (cost reduction). Explored are Laser Cutting techniques, especially the cutting of aluminium in atmosphere and under water, remote- and manually controlled; decontamination and removal of concrete and ceramics by a combined diodelaser / cryogenic carbon dioxide thermal shock treatment (dry ice blasting) as well as cutting with the water-abrasive-suspension-jet and the plasma beam. The project will lead to application in the decommissioning of PTB's FRMB (research reactor of Physikalisch Technische Bundesanstalt, Braunschweig, Germany). (orig.) [de

  10. Economic aspects of decommissioning

    International Nuclear Information System (INIS)

    Jenne, C.

    1988-01-01

    Two viewpoints on decommissioning are quoted; the first suggests that decommissioning can be viewed as a technical detail that is of limited relevance whereas the second suggests that decommissioning is a key financial issue. Both are specifically relevant to United Kingdom nuclear power stations. This paper attempts to reconcile the two views. It suggests that decommissioning does raise some important issues for regulation and financing of a privatised industry but, despite this, the economics of nuclear do remain insensitive. The paper begins by examining the significance of decommissioning costs in a number of contexts, including nuclear unit generating costs and financing requirements. It then addresses the degree of uncertainty in the decommissioning cost estimates. With privatisation on the horizon, the paper considers the significance of decommissioning and the associated uncertainty for the investor; this last section considers regulatory issues raised in relation to funding, accounting policy and electricity pricing. (author)

  11. Analysis of soil samples from OMRE decommissioning project

    International Nuclear Information System (INIS)

    Simpson, O.D.; Chapin, J.A.; Hine, R.E.; Mandler, J.W.; Orme, M.P.; Soli, G.A.

    1979-01-01

    In order to establish that the present Organic Moderated Reactor Experiment (OMRE) site does not exceed the criteria for radioactive contamination, samples obtained from the remainder of the facility that was not removed such as soil, concrete pads, various structural materials, and the leach pond area were analyzed to determine their radioactive content. The results of the analyses performed on soil samples are presented. Results of this study indicate that the activity at the OMRE decommissioned area is confined to localized areas (i.e., the leach pond area and reactor area). Comparisons of radionuclide concentrations measured in soil taken from the lip of the leach pond with concentrations in soil obtained outside the Idaho National Engineering Laboratory (INEL) site boundaries indicate that the concentration in the soil at the edge of the leach pond is at background levels. The vertical augering technique was determined to be the best approach for obtaining shallow soil samples at the INEL. Selection of this technique was based on ease of operation and analytical results. Less area is disturbed per sample than with the horizontal trenching and coring techniques. The radionuclide analysis of the samples shows the existence of a few regions in the reactor and leach pond areas that were still above INEL release criteria. These regions have been or are being further decontaminated

  12. 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

  13. 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)

  14. Decommissioning standards

    International Nuclear Information System (INIS)

    Crofford, W.N.

    1980-01-01

    EPA has agreed to establish a series of environmental standards for the safe disposal of radioactive waste through participation in the Interagency Review Group on Nuclear Waste Management (IRG). One of the standards required under the IRG is the standard for decommissioning of radioactive contaminated sites, facilities, and materials. This standard is to be proposed by December 1980 and promulgated by December 1981. Several considerations are important in establishing these standards. This study includes discussions of some of these considerations and attempts to evaluate their relative importance. Items covered include: the form of the standards, timing for decommissioning, occupational radiation protection, costs and financial provisions. 4 refs

  15. 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

  16. Technology, safety and costs of decommissioning a reference boiling water reactor power station. Volume 2. Appendices. Technical report, September 1977-October 1979

    International Nuclear Information System (INIS)

    Oak, H.D.; Holter, G.M.; Kennedy, W.E. Jr.; Konzek, G.J.

    1980-06-01

    Technology, safety and cost information is given for the conceptual decommissioning of a large (1100MWe) boiling water reactor (BWR) power station. Three approaches to decommissioning, immediate dismantlement, safe storage with deferred dismantlement and entombment, were studied to obtain comparisons between costs, occupational radiation doses, potential dose to the public and other safety impacts. It also shows the sensitivity of decommissioning safety and costs to the power rating of a BWR in the range of 200 to 1100 MWE. This volume contains the appendices

  17. Technology, safety and costs of decommissioning a reference boiling water reactor power station. Volume 2. Appendices. Technical report, September 1977-October 1979

    Energy Technology Data Exchange (ETDEWEB)

    Oak, H.D.; Holter, G.M.; Kennedy, W.E. Jr.; Konzek, G.J.

    1980-06-01

    Technology, safety and cost information is given for the conceptual decommissioning of a large (1100MWe) boiling water reactor (BWR) power station. Three approaches to decommissioning, immediate dismantlement, safe storage with deferred dismantlement and entombment, were studied to obtain comparisons between costs, occupational radiation doses, potential dose to the public and other safety impacts. It also shows the sensitivity of decommissioning safety and costs to the power rating of a BWR in the range of 200 to 1100 MWE. This volume contains the appendices.

  18. 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)

  19. Cost Estimating for Decommissioning of a Plutonium Facility--Lessons Learned From The Rocky Flats Building 771 Project

    International Nuclear Information System (INIS)

    Stevens, J. L.; Titus, R.; Sanford, P. C.

    2002-01-01

    The Rocky Flats Closure Site is implementing an aggressive approach in an attempt to complete Site closure by 2006. The replanning effort to meet this goal required that the life-cycle decommissioning effort for the Site and for the major individual facilities be reexamined in detail. As part of the overall effort, the cost estimate for the Building 771 decommissioning project was revised to incorporate both actual cost data from a recently-completed similar project and detailed planning for all activities. This paper provides a brief overview of the replanning process and the original estimate, and then discusses the modifications to that estimate to reflect new data, methods, and planning rigor. It provides the new work breakdown structure and discusses the reasons for the final arrangement chosen. It follows with the process used to assign scope, cost, and schedule elements within the new structure, and development of the new code of accounts. Finally, it describes the project control methodology used to track the project, and provides lessons learned on cost tracking in the decommissioning environment

  20. Report on waste burial charges. Escalation of decommissioning waste disposal costs at low-level waste burial facilities, Revision 4

    International Nuclear Information System (INIS)

    1994-06-01

    One of the requirements placed upon nuclear power reactor licensees by the U.S. Nuclear Regulatory Commission (NRC) is for the licensees to periodically adjust the estimate of the cost of decommissioning their plants, in dollars of the current year, as part of the process to provide reasonable assurance that adequate funds for decommissioning will be available when needed. This report, which is scheduled to be revised periodically, contains the development of a formula for escalating decommissioning cost estimates that is acceptable to the NRC. The sources of information to be used in the escalation formula are identified, and the values developed for the escalation of radioactive waste burial costs, by site and by year, are given. The licensees may use the formula, the coefficients, and the burial escalation factors from this report in their escalation analyses, or they may use an escalation rate at least equal to the escalation approach presented herein. This fourth revision of NUREG-1307 contains revised spreadsheet results for the disposal costs for the reference PWR and the reference BWR and the ratios of disposal costs at the Washington, Nevada, and South Carolina sites for the years 1986, 1988, 1991 and 1993, superseding the values given in the May 1993 issue of this report. Burial cost surcharges mandated by the Low-Level Radioactive Waste Policy Amendments Act of 1985 (LLRWPAA) have been incorporated into the revised ratio tables for those years. In addition, spreadsheet results for the disposal costs for the reference reactors and ratios of disposal costs at the two remaining burial sites in Washington and South Carolina for the year 1994 are provided. These latter results do not include any LLRWPAA surcharges, since those provisions of the Act expired at the end of 1992. An example calculation for escalated disposal cost is presented, demonstrating the use of the data contained in this report

  1. Human resource development for decommissioning

    International Nuclear Information System (INIS)

    Yanagihara, Satoshi

    2016-01-01

    This paper summarized the features of decommissioning work and the methods how to develop human resources. The general flow of decommissioning includes the following steps: (1) evaluation of facility characteristics, (2) planning, (3) decontamination and disassembly of equipment and structures contaminated with radioactivity, (4) radioactivity measurement, (5) treatment and disposal of radioactive waste, and (6) release from legal restrictions (termination of decommissioning). For this purpose, techniques in various fields are required. In the evaluation of facility characteristics, radiation measurement and calculation of activation amount in the core part are required. In decontamination and dismantling, cutting technology (mechanical cutting, thermal cutting, etc.), decontamination technology, and remote control technology are required. In the nuclear power education in the past, the fields related to design, construction, operation, and maintenance among the plant life cycle were the main parts. Much attention was not payed to decommissioning and the treatment/disposal of radioactive waste in the second half of life cycle. As university education, Hokkaido University and Fukui University have lectures on decommissioning. Furthermore, the education and research for students are proceeding at seven universities, with a focus on common reactors including those of Fukushima Daiichi Power Station. It is a key for promoting decommissioning, to incorporate project management, risk analysis, cost evaluation, and decision making into education, and to foster human resources heading toward challenging problems including social problems. (A.O.)

  2. 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.)

  3. Evaluation of cost of radioactive waste management during the Chernobyl NPP decommissioning

    International Nuclear Information System (INIS)

    Gavrish, V.M.; Tkachev, D.A.

    2009-01-01

    The article presents the results of calculations on evaluation of radioactive waste volumes, the required financing, and the labor expenses for management of radioactive waste that may arise during the decommissioning of Chernobyl NPP Units 1, 2, 3

  4. Calculating Program for Decommissioning Work Productivity based on Decommissioning Activity Experience Data

    Energy Technology Data Exchange (ETDEWEB)

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

    2014-10-15

    KAERI is performing research to calculate a coefficient for decommissioning work unit productivity to calculate the estimated time decommissioning work and estimated cost based on decommissioning activity experience data for KRR-2. KAERI used to calculate the decommissioning cost and manage decommissioning activity experience data through systems such as the decommissioning information management system (DECOMMIS), Decommissioning Facility Characterization DB System (DEFACS), decommissioning work-unit productivity calculation system (DEWOCS). In particular, KAERI used to based data for calculating the decommissioning cost with the form of a code work breakdown structure (WBS) based on decommissioning activity experience data for KRR-2.. Defined WBS code used to each system for calculate decommissioning cost. In this paper, we developed a program that can calculate the decommissioning cost using the decommissioning experience of KRR-2, UCP, and other countries through the mapping of a similar target facility between NPP and KRR-2. This paper is organized as follows. Chapter 2 discusses the decommissioning work productivity calculation method, and the mapping method of the decommissioning target facility will be described in the calculating program for decommissioning work productivity. At KAERI, research on various decommissioning methodologies of domestic NPPs will be conducted in the near future. In particular, It is difficult to determine the cost of decommissioning because such as NPP facility have the number of variables, such as the material of the target facility decommissioning, size, radiographic conditions exist.

  5. Calculating Program for Decommissioning Work Productivity based on Decommissioning Activity Experience Data

    International Nuclear Information System (INIS)

    Song, Chan-Ho; Park, Seung-Kook; Park, Hee-Seong; Moon, Jei-kwon

    2014-01-01

    KAERI is performing research to calculate a coefficient for decommissioning work unit productivity to calculate the estimated time decommissioning work and estimated cost based on decommissioning activity experience data for KRR-2. KAERI used to calculate the decommissioning cost and manage decommissioning activity experience data through systems such as the decommissioning information management system (DECOMMIS), Decommissioning Facility Characterization DB System (DEFACS), decommissioning work-unit productivity calculation system (DEWOCS). In particular, KAERI used to based data for calculating the decommissioning cost with the form of a code work breakdown structure (WBS) based on decommissioning activity experience data for KRR-2.. Defined WBS code used to each system for calculate decommissioning cost. In this paper, we developed a program that can calculate the decommissioning cost using the decommissioning experience of KRR-2, UCP, and other countries through the mapping of a similar target facility between NPP and KRR-2. This paper is organized as follows. Chapter 2 discusses the decommissioning work productivity calculation method, and the mapping method of the decommissioning target facility will be described in the calculating program for decommissioning work productivity. At KAERI, research on various decommissioning methodologies of domestic NPPs will be conducted in the near future. In particular, It is difficult to determine the cost of decommissioning because such as NPP facility have the number of variables, such as the material of the target facility decommissioning, size, radiographic conditions exist

  6. NPP Krsko decommissioning concept

    International Nuclear Information System (INIS)

    Novsak, M.; Fink, K.; Spiler, J.

    1996-01-01

    At the end of the operational lifetime of a nuclear power plant (NPP) it is necessary to take measures for the decommissioning as stated in different international regulations and also in the national Slovenian law. Based on these requirements Slovenian authorities requested the development of a site specific decommissioning plan for the NPP KRSKO. In September 1995, the Nuklearna Elektrarna Krsko (NEK) developed a site specific scope and content for decommissioning plan including the assumptions for determination of the decommissioning costs. The NEK Decommissioning Plan contains sufficient information to fulfill decommissioning requirements identified by NRC, IAEA and OECD - NEA regulations. In this paper the activities and the results of development of NEK Decommissioning Plan consisting of the development of three decommissioning strategies for the NPP Krsko and selection of the most suitable strategy based on site specific, social, technical, radiological and economical aspects, cost estimates for the strategies including the costs for construction of final disposal facilities for fuel/high level waste (fuel/HLW) and low/intermediate level waste (LLW/ILW) and scheduling all activities necessary for the decommissioning of the NPP KRSKO are presented. (author)

  7. NPP Krsko decommissioning concept

    International Nuclear Information System (INIS)

    Novsak, M.; Fink, K.; Spiler, J.

    1996-01-01

    At the end of the operational lifetime of a nuclear power plant (NPP) it is necessary to take measures for the decommissioning as stated in different international regulations and also in the national Slovenian law. Based on these requirements Slovenian authorities requested the development of a site specific decommissioning plan for the NPP Krsko. In September 1995, the Nuklearna Elektrarna Krsko (NEK) developed a site specific scope and content for a decommissioning plan including the assumptions for determination of the decommissioning costs. The NEK Decommissioning Plan contains sufficient information to fulfill the decommissioning requirements identified by NRC, IAEA and OECD - NEA regulations. In this paper the activities and results of development of NEK Decommissioning Plan consisting of the development of three decommissioning strategies for the NPP Krsko and selection of the most suitable strategy based on site specific, social, technical, radiological and economic aspects, cost estimates for the strategies including the costs for construction of final disposal facilities for fuel/high level waste (fuel/HLW) and low/intermediate level waste (LLW/ILW) and scheduling of all activities necessary for the decommissioning of the NPP Krsko are presented. (author)

  8. Progress on radiochemical analysis for nuclear waste management in decommissioning

    Energy Technology Data Exchange (ETDEWEB)

    Hou, X. (Technical Univ. of Denmark. Center for Nuclear Technologies (NuTech), Roskilde (Denmark))

    2012-01-15

    This report summarized the progress in the development and improvement of radioanalytical methods for decommissioning and waste management completed in the NKS-B RadWaste 2011 project. Based on the overview information of the analytical methods in Nordic laboratories and requirement from the nuclear industry provided in the first phase of the RadWaste project (2010), some methods were improved and developed. A method for efficiently separation of Nb from nuclear waste especially metals for measurement of long-lived 94Nb by gamma spectrometry was developed. By systematic investigation of behaviours of technetium in sample treatment and chromatographic separation process, an effective method was developed for the determination of low level 99Tc in waste samples. An AMS approachment was investigated to measure ultra low level 237Np using 242Pu for AMS normalization, the preliminary results show a high potential of this method. Some progress on characterization of waste for decommissioning of Danish DR3 is also presented. (Author)

  9. Progress on radiochemical analysis for nuclear waste management in decommissioning

    International Nuclear Information System (INIS)

    Hou, X.

    2012-01-01

    This report summarized the progress in the development and improvement of radioanalytical methods for decommissioning and waste management completed in the NKS-B RadWaste 2011 project. Based on the overview information of the analytical methods in Nordic laboratories and requirement from the nuclear industry provided in the first phase of the RadWaste project (2010), some methods were improved and developed. A method for efficiently separation of Nb from nuclear waste especially metals for measurement of long-lived 94Nb by gamma spectrometry was developed. By systematic investigation of behaviours of technetium in sample treatment and chromatographic separation process, an effective method was developed for the determination of low level 99Tc in waste samples. An AMS approachment was investigated to measure ultra low level 237Np using 242Pu for AMS normalization, the preliminary results show a high potential of this method. Some progress on characterization of waste for decommissioning of Danish DR3 is also presented. (Author)

  10. National waste terminal storage repository in a bedded salt formation for spent unreprocessed fuel. Special study No. 1. Twenty-five-year retrievability, decommissioning cost estimate

    International Nuclear Information System (INIS)

    1978-11-01

    This estimate covers decommissioning costs of facilities for the receipt, handling, and storage in bedded salt of canistered spent fuel assemblies from both BWR and PWR commercial power plants. The estimate includes all decommissioning costs for a repository, based on 25-year retrievability, constructed in accordance with the design shown in Conceptual Design Report (CDR), as modified by Special Study No. 1 (KE Report No. 78-60-RE) and decommissioned in accordance with the program outlined in the Conceptual Design Description Report, KE Report No. 78-58-R. Costs for Operating Contractor personnel on the site at this time are included in this report and not in the Operating Cost Estimate (KE Report 78-63-RE). The operating cost estimates end with the completion of storage room backfilling. The three major elements of decommissioning are: demolition of surface facilities, backfilling of main entries and airways, and shaft liner removal and shaft plugging. EDIT, ECON, and DELOX computer programs and a chart of accounts were furnished by UCC-ND under direction of the Government and the line item-capital-cost estimate was prepared according to the prescribed format. The decommissioning cost estimate referenced herein is in the same format as its companion line item-capital-cost estimate KE Report 78-62-RE

  11. Securing the long-term financing of decommissioning and radioactive waste management - From cost estimates to a comprehensive financing system

    International Nuclear Information System (INIS)

    Aebersold, Michael

    2003-01-01

    One of the most important issues in the area of waste disposal concerns the long-term securing of the necessary financing. Large amounts of money will have to be invested, managed and subsequently spent at the appropriate time, over an extended period of 100 years or more. In an electricity market that is opening up across Europe and is characterised by complicated legal structures, a focus on a handful of major groups and cost pressure due to increased competition, it will be necessary to create the corresponding background conditions. The anticipated costs for decommissioning and disposal will have to be calculated or estimated on the basis of available know-how and criteria. The required funds will then have to be collected and invested on the domestic and international money markets, which given the current situation on the stock markets will by no means be an easy task. But the assurance that enough money will be available is essential for public confidence. Using Switzerland as an example, the author wishes to demonstrate which steps are necessary in order to calculate the potential decommissioning and waste disposal costs based on a defined disposal concept and programme, determine the annual contributions to be paid in by operators, and establish a suitable system for securing the necessary funding. This paper deals with the following issues: 1. Political background and legislative framework in Switzerland; 2. Swiss radioactive waste management policy and programmes; 3. Calculating the decommissioning and waste management costs; 4. Calculating the contributions to the Funds; 5. Financing system

  12. Preparatory activities of the Fugen decommissioning

    International Nuclear Information System (INIS)

    Iguchi, Y.; Tajiri, T.; Kiyota, S.

    2004-01-01

    The Advanced Thermal Reactor Fugen is a 165 MWe, heavy water moderated, light-water cooled, pressure-tube type reactor. In February 1998, the Atomic Energy Commission of Japan introduced a new policy that development and research of decommissioning of Fugen should be promoted in order to carry out the decommissioning smoothly after the shutdown. The Fugen reactor was shut down definitely in March 2003, and Fugen has been preparing for the project, including necessary development of technologies. The development of decommissioning for Fugen is divided into two areas. One area is the development of unique technology for dismantling special components such as the reactor core and the heavy water system. Another area is the improvement and enhancement of existing technologies. Especially the former area requires effort and comprises development of the reactor dismantlement, tritium decontamination of heavy water system and engineering support systems. The activities are as follows: the density and amount of radioactive nuclides in all equipment or concrete including the reactor core need to be evaluated for the decommissioning. To prepare for decommissioning, analysis, measurement and evaluation of the neutron flux density have been executed during reactor operation. Special dismantling process is necessary for the heavy water system and the reactor that are unique to Fugen. Some studies and tests are going on for the safe dismantling based on existing technologies and their combination. Systems engineering approach is necessary in order to optimize the work load, exposure dose, waste mass and cost by selecting appropriate dismantling process at the planning stage of the decommissioning. For this reason, in order to make a decommissioning plan efficiently, we have been developing an Engineering Support System for decommissioning by adopting new information technologies such as three-dimensional computer-aided design system and virtual reality system. Moreover, the

  13. SMART 3D SUBSURFACE CONTAMINANT CHARACTERIZATION AT THE BGRR DECOMMISSIONING PROJECT. ACCELERATED SITE TECHNOLOGY DEPLOYMENT COST AND PERFORMANCE REPORT

    International Nuclear Information System (INIS)

    HEISER, J.; KALB, P.; SULLIVAN, T.; MILIAN, L.

    2001-01-01

    The Brookhaven Graphite Research Reactor (BGRR), which operated from 1951--1968 is currently undergoing decontamination and decommissioning (D and D). As part of this effort, many of the major structures and facilities (e.g., Above Grade Ducts, Cooling Fans, Pile Fan Sump, Transfer Canal and Instruments Houses) are being removed to eliminate contaminants and reduce the footprint of the overall facility. However, a significant cost savings (almost $5M) can potentially be realized if the large concrete Below Grade Ducts (BGD) can be decontaminated and left in place. In order to do this, soils beneath the ducts must be fully characterized to identify areas where contaminants may have leaked, what radioactive and hazardous contaminants remain, and in what concentrations. This information will then be used to evaluate whether discrete areas of localized contaminated soil can be selectively removed or, if the contamination is significant and widespread, and whether the ducts themselves must be removed for complete cleanup. The information generated from this effort is input into the BGRR BGD Characterization Report and an Engineering Evaluation/Cost Analysis (EE/CA) currently being prepared to evaluate potential options for the ducts. This FY01 Department of Energy Accelerated Site Technology Deployment (DOE ASTD) project combined a suite of innovative technologies to provide cost-effective characterization of the soils beneath the BGD and present the data in an easily understandable three-dimensional representation of the contaminant concentrations beneath the ducts. Conventional characterization of the soil would have required sampling a very large area in a tight grid pattern to ensure that all areas of potential contamination were evaluated. It is estimated that using baseline techniques would require approximately 2500 samples (costing ∼$1.6M), depending on the level of precision required by regulators. This massive amount of data would then be difficult to

  14. 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

  15. A Review of the Decommissioning Plan and Cost Estimate for the Studsvik Rock Facility (AM) for the Storage of Low and Intermediate Level Wastes

    International Nuclear Information System (INIS)

    Varley, Geoff

    2004-03-01

    cost may be high. This conclusion is based on correlation analysis of data in other Swedish cost estimates for the R2 research reactor and for Aagesta, compared with the AM cost estimate. It may be helpful to perform a broader analysis of other AB SVAFO decommissioning cost estimates and actual decommissioning projects, to see if there is any consistent correlation between planning resource needs and overall project cost, or indeed if an alternative, nonlinear correlation might apply. The assumptions made for worker utilisation and dismantling efficiency may or may not be appropriate for the AM facility estimate. However, the AB SVAFO report provides insufficient information to facilitate further comment on the reasonableness of the assumptions and related methodology. Dismantling costs were based on information provided by a commercial company, in a non-competitive situation. On one hand there might have been a tendency for the information to introduce conservatism into the AM cost estimate. On the other hand it could be either high or low in terms of estimated resources needed. In any event, the AM cost estimate report is unclear on cleaning and decontamination aspects, not least because statements appear to be inconsistent. In addition, the whole concept of cleaning and decontamination prior to activity mapping might be considered to be an inappropriate approach. If, as is expected, the entire facility will not be contaminated, it is reasonable to ask why the estimate would address an extensive program of cleaning and decontamination. Notwithstanding a number of inadequacies of the AM cost estimate report, the general impression is that the indicated financial requirements probably are sufficient and might even be overstated (conservative). This assertion is predicated on the basis that the basic methodologies applied are reasonable, which remains to be demonstrated. The report is ambiguous in its presentation, which makes it difficult to draw firm conclusions in

  16. Systematic Approach for Decommissioning Planning and Estimating

    International Nuclear Information System (INIS)

    Dam, A. S.

    2002-01-01

    Nuclear facility decommissioning, satisfactorily completed at the lowest cost, relies on a systematic approach to the planning, estimating, and documenting the work. High quality information is needed to properly perform the planning and estimating. A systematic approach to collecting and maintaining the needed information is recommended using a knowledgebase system for information management. A systematic approach is also recommended to develop the decommissioning plan, cost estimate and schedule. A probabilistic project cost and schedule risk analysis is included as part of the planning process. The entire effort is performed by a experienced team of decommissioning planners, cost estimators, schedulers, and facility knowledgeable owner representatives. The plant data, work plans, cost and schedule are entered into a knowledgebase. This systematic approach has been used successfully for decommissioning planning and cost estimating for a commercial nuclear power plant. Elements of this approach have been used for numerous cost estimates and estimate reviews. The plan and estimate in the knowledgebase should be a living document, updated periodically, to support decommissioning fund provisioning, with the plan ready for use when the need arises

  17. Utility financial stability and the availability of funds for decommissioning: An analysis of internal and external funding

    International Nuclear Information System (INIS)

    Siegel, J.J.

    1988-06-01

    The NRC is currently developing final rules in the area of decommissioning nuclear facilities. A part of that rulemaking effort is assuring that funds will be available at the time of decommissioning of power reactors. This report provides an update by considering public comments received on the NRC's proposed rule on decommissioning (published February, 1985) and by analyzing the relative level of assurance of internal and external reserves. In its analysis, the report makes use of specific case utility financial situations. The report concludes that from a financial standpoint, with the exception of PSNH, internal reserves currently provide sufficient assurance of funds for decommissioning. The report also concludes that the NRC should recommend changes in bankruptcy laws, including decommissioning obligations in utility prospectuses, and conduct periodic financial reviews of nuclear utilities due to changing economic conditions

  18. Factor analysis on hazards for safety assessment in decommissioning workplace of nuclear facilities using a semantic differential method

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, Kwan-Seong [Korea Atomic Energy Research Institute, 1045 Daedeok-daero, Yuseong-gu, Daejeon 305-353 (Korea, Republic of)], E-mail: ksjeongl@kaeri.re.kr; Lim, Hyeon-Kyo [Chungbuk National University, 410 Sungbong-ro, Heungduk-gu, Cheongju, Chungbuk 361-763 (Korea, Republic of)

    2009-10-15

    The decommissioning of nuclear facilities must be accomplished according to its structural conditions and radiological characteristics. An effective risk analysis requires basic knowledge about possible risks, characteristics of potential hazards, and comprehensive understanding of the associated cause-effect relationships within a decommissioning for nuclear facilities. The hazards associated with a decommissioning plan are important not only because they may be a direct cause of harm to workers but also because their occurrence may, indirectly, result in increased radiological and non-radiological hazards. Workers need to be protected by eliminating or reducing the radiological and non-radiological hazards that may arise during routine decommissioning activities as well as during accidents. Therefore, to prepare the safety assessment for decommissioning of nuclear facilities, the radiological and non-radiological hazards should be systematically identified and classified. With a semantic differential method of screening factor and risk perception factor, the radiological and non-radiological hazards are screened and identified.

  19. Decommissioning of offshore installations

    Energy Technology Data Exchange (ETDEWEB)

    Oeen, Sigrun; Iversen, Per Erik; Stokke, Reidunn; Nielsen, Frantz; Henriksen, Thor; Natvig, Henning; Dretvik, Oeystein; Martinsen, Finn; Bakke, Gunnstein

    2010-07-01

    and requirements that should be considered in the regulation of decommissioning facilities for offshore installations. These facilities need sound expertise to be able to identify and deal with different types of waste, including hazardous waste such as heavy metals, other hazardous substances, low specific activity (LSA) radioactive material and asbestos. Facilities must be designed to allow safe handling of such waste, with no risk of runoff or infiltration into the soil. In addition, a decommissioning facility should have an effective collection system and an on-site treatment plant for contaminated water, including surface water. Each facility must have a sampling and analysis programme to monitor releases of the most relevant pollutants. The need for an environmental monitoring programme to follow developments in the recipient should also be considered. Other factors that must be closely monitored include noise and releases to air in connection with metal cutting and other operations. Moreover, decommissioning contracts must ensure that the costs of handling hazardous waste are met by the offshore operators. When decommissioning facilities for offshore installations are being sited, other interests must also be taken into account; for example, the use of nearby areas for housing, holiday housing or recreation. In addition, the implications for other sectors such as fisheries and agriculture must be taken into consideration. These are important issues that the municipalities must consider when preparing zoning plans and drawing up environmental impact assessments. In many cases, a regional authority is in a better position than a national one to make overall, cross-sectoral assessments of developments within the region. Nevertheless, the report recommends transferring the authority for regulating decommissioning facilities for offshore installations from the County Governors to the Climate and Pollution Agency. Regulating these facilities requires special

  20. Feasibility studies for decommissioning

    International Nuclear Information System (INIS)

    Hladky, E.

    2000-01-01

    In this presentation author deals with planning of decommission of the NPPs A1, V1 and V2 Bohunice and Mochovce. It was concluded that: Used model for decommissioning parameters assessment has been suitable for elaboration of initial decommissioning plans (feasibility studies); Basic assessment of main decommissioning parameters and basic comparison of various decommissioning options have been possible; Improvement of the model and corresponding software is desirable and works on software improvement began one year ago; V1-NPP initial decommissioning plan should be actualized, because initial decommissioning plan does not correspond by its content and structure to requirements of Act No. 130/98 and Nuclear Regulatory Authority Degree No. 246/99; Strategy of radioactive wastes treatment and conditioning together with technical provisions at Jaslovske Bohunice site was changed in comparison with the assumptions in 1991-92; Considered V1 NPP decommissioning options are necessary to be re-evaluated in accordance with latest development of knowledge and approaches to NPP decommissioning in the world; Specific unit costs are substantially and differentially changed in comparison with the assumptions in 1991-92; Necessity to take into account technical changes resulted from V1 NPP reconstruction. (author)

  1. 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

  2. Cost benefit analysis cost effectiveness analysis

    International Nuclear Information System (INIS)

    Lombard, J.

    1986-09-01

    The comparison of various protection options in order to determine which is the best compromise between cost of protection and residual risk is the purpose of the ALARA procedure. The use of decision-aiding techniques is valuable as an aid to selection procedures. The purpose of this study is to introduce two rather simple and well known decision aiding techniques: the cost-effectiveness analysis and the cost-benefit analysis. These two techniques are relevant for the great part of ALARA decisions which need the use of a quantitative technique. The study is based on an hypothetical case of 10 protection options. Four methods are applied to the data

  3. 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)

  4. Economic analysis vs. capital-recovery requirements of power reactor decommissioning

    International Nuclear Information System (INIS)

    Ferguson, J.S.

    1980-01-01

    As a consultant to electric utilities the author often becomes involved in the development of policy for capital recovery and in the determination of depreciation rates that will implement the policy. Utility capital recovery is controlled by generally accepted depreciation accounting practices and by regulatory commission accounting rules and, as a result, can differ significantly from engineering economics. Those involved with decommissioning of power reactors should be aware of the depreciation accounting and regulatory framework that dictates capital recovery requirements, whether their involvement is related to engineering economics or capital recovery. This presentation defines that framework, points out several significant implications (particularly tax), describes several conforming capital-recovery methods, describes several techniques that have been used with the decommissioning component in economic analysis of alternative energy sources, and discusses why those involved in economic analysis should learn the accounting and regulatory framework for capital recovery

  5. Money Related Decommissioning and Funding Decision Making

    International Nuclear Information System (INIS)

    Goodman, Lynne S.

    2008-01-01

    'Money makes the world go round', as the song says. It definitely influences decommissioning decision-making and financial assurance for future decommissioning. This paper will address two money-related decommissioning topics. The first is the evaluation of whether to continue or to halt decommissioning activities at Fermi 1. The second is maintaining adequacy of financial assurance for future decommissioning of operating plants. Decommissioning costs considerable money and costs are often higher than originally estimated. If costs increase significantly and decommissioning is not well funded, decommissioning activities may be deferred. Several decommissioning projects have been deferred when decision-makers determined future spending is preferable than current spending, or when costs have risen significantly. Decommissioning activity timing is being reevaluated for the Fermi 1 project. Assumptions for waste cost-escalation significantly impact the decision being made this year on the Fermi 1 decommissioning project. They also have a major impact on the estimated costs for decommissioning currently operating plants. Adequately funding full decommissioning during plant operation will ensure that the users who receive the benefit pay the full price of the nuclear-generated electricity. Funding throughout operation also will better ensure that money is available following shutdown to allow decommissioning to be conducted without need for additional funds

  6. 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 )

  7. Safety analysis report for decommissioning of KNPP units 1 and 2

    International Nuclear Information System (INIS)

    Ivanova, A.; Ovcharova, I.

    2008-01-01

    At present units 1 and 2 possess a license for operation in mode „E‟ – storage of the spent fuel in the spent fuel pools. According to the order of BNSA, from the beginning of December 2006 the licenses for operation of KNPP units 1 and 2 have been modified; this does not change the current status – operation of the units in mode „E‟ , but allows for dismantling of the systems and equipment, which are not important for safety and do not contain radioactive substances above the free release levels. The next step is obtaining a licence for Stage 1 decommissioning activities – Safe enclosure (SE) and dismantling in Turbine hall. The development of Decommissioning Safety Analysis Report (DSAR) is one of the documents needed for this license. The specific features of the units and decommitioning options are described

  8. 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

  9. 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

  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

    EDF has 9 NPPs permanently shutdown and under decommissioning. EDF considers that if the nuclear option is to remain open, it is necessary to deal with increasing public concerns for environmental and waste management issues. Therefore EDF has decided to achieve total dismantling of all shutdown reactor in the next 25 years. The Decommissioning Program has been developed including 2 stages of activities. The first stage consists of: 1) Final dismantling of Brennilis in 2015; 2) A dismantling demonstration of a PWR reactor building (Chooz A) before starting replacing the population of PWRs currently in operation; 3) Final dismantling of reactor containment of a GCR (Bugey 1) as a first of its kind. The second stage includes: 1)Dismantling of following 5 GCR (Saint Laurent A1 and A2, Chinon A1, A2 and A3); 2) Final dismantling of Chooz A and Bugey 1 in 2025. The successful implementation relies on the simplification of the regulatory process; availability of treatment, conditioning and disposal facilities and effective nuclear industry. The main issue is availability of time and waste solutions such as opening of a Very Low Waste disposal in 2003 (130 000 tons); opening of a new disposal for graphite and radiferous wastes (17 000 tons) in 2010 and opening in 2007-2008 of a centralized interim storage (BANEDA) facility for long-lived Medium Level Wastes (500 tons including filters, control rods etc)Three investigations are to be carried out for high level radioactive waste before 2006

  11. Decommissioning and Decontamination

    International Nuclear Information System (INIS)

    Massaut, V.

    2000-01-01

    The objectives of SCK-CEN's decommissioning and decontamination programme are (1) to develop, test and optimise the technologies and procedures for decommissioning and decontamination of nuclear installations in order to minimise the waste arising and the distributed dose; (2) to optimise the environmental impact; (3) to reduce the cost of the end-of-life of the installation; (4) to make these new techniques available to the industry; (5) to share skills and competences. The programme and achievements in 1999 are summarised

  12. An evaluation of cost estimates of nuclear power reactor decommissioning in Sweden, Germany and the United States

    Energy Technology Data Exchange (ETDEWEB)

    Andersson, S O; Varley, G; Heibel, R; Rusch, C [NAC International, Zurich (Switzerland)

    1995-11-01

    Nominal base decommissioning cost estimates in Sweden, Germany and the US differ by large amounts. Even after adjustments to normalize the work scopes, significant cost differences remain. Variations in national cost structures, achievable productivity, the extent of preexisting infrastructure and institutional factors all contribute to make up the differences. Exchange rate aberrations are a complication for which appropriate adjustments have to be made in order to achieve a meaningful comparison. Our analyses demonstrate that virtually all these differences between the Swedish, German and US estimates can be explained by these factors. In terms of the overall reasonableness of the Swedish estimate as a basis for making financial provisions, there remain some issues that may warrant further investigation. One is the potential for and financial consequences of a serious interruption to the proposed sea transportation system. Secondly, the limited number of individual system analyses we have performed indicated some significant potential underestimates. For example, dismantling of the reactor pressure vessel costs appear to be underestimated by up to 70 MSEK (about 10 MUSD) per reactor, or up to 900 MSEK for the whole Swedish program of 12 reactors. Overall, the Swedish estimates appear to be built up in a logical and reasonable way. Our analyses indicate that some internal inconsistencies exist and that some specific input data assumptions may not be valid. In summary, the credibility of the estimates would benefit from further refinement of the scenarios and assumptions. 21 refs., 15 figs., 42 tabs.

  13. An evaluation of cost estimates of nuclear power reactor decommissioning in Sweden, Germany and the United States

    International Nuclear Information System (INIS)

    Andersson, S.O.; Varley, G.; Heibel, R.; Rusch, C.

    1995-11-01

    Nominal base decommissioning cost estimates in Sweden, Germany and the US differ by large amounts. Even after adjustments to normalize the work scopes, significant cost differences remain. Variations in national cost structures, achievable productivity, the extent of preexisting infrastructure and institutional factors all contribute to make up the differences. Exchange rate aberrations are a complication for which appropriate adjustments have to be made in order to achieve a meaningful comparison. Our analyses demonstrate that virtually all these differences between the Swedish, German and US estimates can be explained by these factors. In terms of the overall reasonableness of the Swedish estimate as a basis for making financial provisions, there remain some issues that may warrant further investigation. One is the potential for and financial consequences of a serious interruption to the proposed sea transportation system. Secondly, the limited number of individual system analyses we have performed indicated some significant potential underestimates. For example, dismantling of the reactor pressure vessel costs appear to be underestimated by up to 70 MSEK (about 10 MUSD) per reactor, or up to 900 MSEK for the whole Swedish program of 12 reactors. Overall, the Swedish estimates appear to be built up in a logical and reasonable way. Our analyses indicate that some internal inconsistencies exist and that some specific input data assumptions may not be valid. In summary, the credibility of the estimates would benefit from further refinement of the scenarios and assumptions. 21 refs., 15 figs., 42 tabs

  14. Corrosion analysis of decommissioned carbon steel waste water tanks at Brookhaven National Laboratory

    International Nuclear Information System (INIS)

    Soo, P.; Roberts, T.C.

    1995-07-01

    A corrosion analysis was carried out on available sections of carbon steels taken from two decommissioned radioactive waste water tanks at Brookhaven National Laboratory. One of the 100,000 gallon tanks suffered from a pinhole failure in the wall which was subsequently patched. From the analysis it was shown that this leak, and two adjacent leaks were initiated by a discarded copper heating coil that had been dropped into the tank during service. The failure mechanism is postulated to have been galvanic attack at points of contact between the tank structure and the coil. Other leaks in the two tanks are also described in this report

  15. Lessons Learned for Decommissioning Planning

    International Nuclear Information System (INIS)

    Sohn, Wook; Kim, Young-gook; Kim, Hee-keun

    2015-01-01

    The purpose of this paper is to introduce the U.S. nuclear industrial's some key lessons learned especially for decommissioning planning based on which well informed decommissioning planning can be carried out. For a successful decommissioning, it is crucial to carry out a well-organized decommissioning planning before the decommissioning starts. This paper discussed four key factors which should be decided or considered carefully during the decommissioning planning period with introduction of related decommissioning lessons learned of U.S. nuclear industry. Those factors which have been discussed in this paper include the end state of a site, the overall decommissioning strategy, the management of the spent fuels, and the spent fuel pool island. Among them, the end state of a site should be decided first as it directs the whole decommissioning processes. Then, decisions on the overall decommissioning strategy (DECON vs. SAFSTOR) and the management of the spent fuels (wet vs. dry) should follow. Finally, the spent fuel pool island should be given due consideration because its implementation will result in much cost saving. Hopefully, the results of this paper would provide useful inputs to performing the decommissioning planing for the Kori unit 1

  16. Characterization of decommissioned reactor internals: Monte Carlo analysis technique

    International Nuclear Information System (INIS)

    Reid, B.D.; Love, E.F.; Luksic, A.T.

    1993-03-01

    This study discusses computer analysis techniques for determining activation levels of irradiated reactor component hardware to yield data for the Department of Energy's Greater-Than-Class C Low-Level Radioactive Waste Program. The study recommends the Monte Carlo Neutron/Photon (MCNP) computer code as the best analysis tool for this application and compares the technique to direct sampling methodology. To implement the MCNP analysis, a computer model would be developed to reflect the geometry, material composition, and power history of an existing shutdown reactor. MCNP analysis would then be performed using the computer model, and the results would be validated by comparison to laboratory analysis results from samples taken from the shutdown reactor. The report estimates uncertainties for each step of the computational and laboratory analyses; the overall uncertainty of the MCNP results is projected to be ±35%. The primary source of uncertainty is identified as the material composition of the components, and research is suggested to address that uncertainty

  17. New projects related to decommissioning

    International Nuclear Information System (INIS)

    Benbow, R.

    2008-01-01

    The PMU has been established in support of the KNPP Decommissioning Department. All of the Infrastructure Projects associated with Decommissioning have been identified and are being managed through the EBRD Procurement Process. The status of the following projects is presented: Evaluation of the Radiological Inventory for Units 1 to 4; Supply of Size Reduction and Decontamination Workshops; Dismantling Tools and Equipment; Heat Generation Plant; Environmental Assessment for Decommissioning; Decay Storage Site for Transitional RAW ; Information Centres for Decommissioning; Storage Site for Conventional Waste from Decommissioning; Inventory, Treatment an Conditioning of Contaminated Soil; Concrete Core Sampling Analysis; Asbestos Removal Equipment; Demolition Equipment

  18. 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

  19. 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

  20. 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

  1. Compilation and analysis of national and international OPEX for Safe Enclosure prior to decommissioning

    International Nuclear Information System (INIS)

    Dinner, Paul J.C.; Heimlich, Karel

    2016-01-01

    Around the world, a large number of aging nuclear plants are approaching final shutdown. While this is largely driven by plants reaching the end of their design life, economic factors such as low gas prices (in North America) and the smaller unit size of early commercial reactors are important contributors to this trend. In several instances, economic pressures have resulted in a need for a more rapid transition to Safe Enclosure than originally anticipated. Thus plans for this transition taking into account experience with Safe Enclosure periods of varying lengths are being actively prepared in many jurisdictions. The IAEA as well as other national and international authorities have long recognized the importance of the topic of Safe Enclosure and provided guidance, and the IAEA has recently undertaken a study of 'Lessons Learned from Deferred Decommissioning of Nuclear Facilities'. Beginning with preliminary experience from Canadian CANDU reactors in extended shutdown or safe enclosure, this paper aims to compare this experience with the larger pool of experience from the international community to: - classify the main issues or themes, - examine means to mitigate these, and - formulate general measures of 'good practice'. Compilation of this experience represents the first steps towards a comprehensive, searchable database potentially of use to many in the decommissioning community. Tabulation and analysis of the complete list (comprising approximately 70 cases) has provided the 'short list' of issues presented in Table 1. Examples of the most important listed issues are discussed. The authors' objective is to stimulate interest in extending this compilation. In this way it will continue to grow and benefit all those preparing for transition to decommissioning. (authors)

  2. Compilation and analysis of national and international OPEX or safe enclosure prior to decommissioning

    International Nuclear Information System (INIS)

    Dinner, Paul J.C.; Heimlich, Karel

    2016-01-01

    Around the world, a large number of aging nuclear plants are approaching final shutdown. While this is largely driven by plants reaching the end of their design life, economic factors such as low gas prices (in North America) and the smaller unit size of early commercial reactors are important contributors to this trend. In several instances, economic pressures have resulted in a need for a more rapid transition to Safe Enclosure than originally anticipated. Thus plans for this transition taking into account experience with Safe Enclosure periods of varying lengths are being actively prepared in many jurisdictions. The IAEA as well as other national and international authorities have long recognized the importance of the topic of Safe Enclosure and provided guidance [1-7], and the IAEA has recently undertaken a study of 'Lessons Learned from Deferred Decommissioning of Nuclear Facilities' [8]. Beginning with preliminary experience from Canadian CANDU reactors in extended shutdown or safe enclosure, this paper aims to compare this experience with the larger pool of experience from the international community to: - classify the main issues or themes, - examine means to mitigate these, and - formulate general measures of 'good practice'. Compilation of this experience represents the first steps towards a comprehensive, searchable database potentially of use to many in the decommissioning community. Tabulation and analysis of the complete list (comprising approximately 70 cases) has provided the 'short list' of issues presented. Examples of the most important listed issues are discussed. The authors' objective is to stimulate interest in extending this compilation. In this way it will continue to grow and benefit all those preparing for transition to decommissioning. (authors)

  3. NPP Decommissioning: the concept; state of activities

    International Nuclear Information System (INIS)

    Nemytov, S.; Zimin, V.

    2001-01-01

    The main principles of NPP decommissioning concept in Russia are given. The conditions with fulfillment of works on NPP unit pre-decommissioning and decommissioning including: development of the normative documentation, creation of special fund for financing NPP decommissioning activities, deriving the Gosatomnadzor license for decommissioning of shut down NPP units, development of the equipment and technologies for waste and spent fuel management are presented. The decommissioning cost and labour intensity of one WWER-440 unit are shown. The practical works, executed on shut down units at Beloyarsk NPP (Unit1 and 2) and Novo Voronezh NPP (Unit 1 and 2) are outlined

  4. Scheduling for decommissioning projects

    International Nuclear Information System (INIS)

    Podmajersky, O.E.

    1987-01-01

    This paper describes the Project Scheduling system being employed by the Decommissioning Operations Contractor at the Shippingport Station Decommissioning Project (SSDP). Results from the planning system show that the project continues to achieve its cost and schedule goals. An integrated cost and schedule control system (C/SCS) which uses the concept of earned value for measurement of performance was instituted in accordance with DOE orders. The schedule and cost variances generated by the C/SCS system are used to confirm management's assessment of project status. This paper describes the types of schedules and tools used on the SSDP project to plan and monitor the work, and identifies factors that are unique to a decommissioning project that make scheduling critical to the achievement of the project's goals. 1 fig

  5. Decommissioning Facility Characterization DB System

    International Nuclear Information System (INIS)

    Park, S. K.; Ji, Y. H.; Park, J. H.; Chung, U. S.

    2010-01-01

    Basically, 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 and estimating the cost of the decommissioning project. In this paper, it is presented a computer system for the characterization of nuclear facilities, called DEFACS (DEcommissioning FAcility Characterization DB System). This system consists of four main parts: a management coding system for grouping items, a data input system, a data processing system and a data output system. All data is processed in a simplified and formatted manner in order to provide useful information to the decommissioning planner. For the hardware, PC grade computers running Oracle software on Microsoft Windows OS were selected. The characterization data results for the nuclear facility under decommissioning will be utilized for the work-unit productivity calculation system and decommissioning engineering system as basic sources of information

  6. Decommissioning Facility Characterization DB System

    Energy Technology Data Exchange (ETDEWEB)

    Park, S. K.; Ji, Y. H.; Park, J. H.; Chung, U. S. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2010-10-15

    Basically, 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 and estimating the cost of the decommissioning project. In this paper, it is presented a computer system for the characterization of nuclear facilities, called DEFACS (DEcommissioning FAcility Characterization DB System). This system consists of four main parts: a management coding system for grouping items, a data input system, a data processing system and a data output system. All data is processed in a simplified and formatted manner in order to provide useful information to the decommissioning planner. For the hardware, PC grade computers running Oracle software on Microsoft Windows OS were selected. The characterization data results for the nuclear facility under decommissioning will be utilized for the work-unit productivity calculation system and decommissioning engineering system as basic sources of information

  7. A study on the decommissioning methods of nuclear facilities of North Korea

    International Nuclear Information System (INIS)

    Chung, U. S.; Park, J. H.; Park, S. K.; Hong, S. B.; Lee, G. W.

    2012-02-01

    For Korea, it is essential to participate in the decommissioning of North Korean nuclear facilities for Pu-based weapon program and to lead the project for the protection of the environments from the possible spread of nuclear contamination. Before, the studies for the verification of the North Korea nuclear facilities and for the technical preparation of the decommissioning of north Korea were conducted but the depth of the studies was not reached to the evaluation of the decommissioning project by the documentation of a decommissioning plan to the provision of the technical information to the policy decision makers. It is very helpful for understanding the characteristics of the decommissioning projects to formulate a possible dismantling scenario and to make a decommissioning plan. The cost and the periods estimated on the base of this scenario is more exact and the analysis for the selection of different policies will be possible

  8. A Novel and Cost Effective Approach to the Decommissioning and Decontamination of Legacy Glove Boxes - Minimizing TRU Waste and Maximizing LLW Waste - 13634

    Energy Technology Data Exchange (ETDEWEB)

    Pancake, Daniel; Rock, Cynthia M.; Creed, Richard [Argonne National Laboratory, 9700 South Cass Avenue, Lemont, IL 60439 (United States); Donohoue, Tom; Martin, E. Ray; Mason, John A. [ANTECH Corporation 9050 Marshall Court, Westminster, CO, 80031 (United States); Norton, Christopher J.; Crosby, Daniel [Environmental Alternatives, Inc., 149 Emerald Street, Suite R, Keene, NH 03431 (United States); Nachtman, Thomas J. [InstaCote, Inc., 160 C. Lavoy Road, Erie, MI, 48133 (United States)

    2013-07-01

    This paper describes the process of decommissioning two gloveboxes at the Argonne National Laboratory (ANL) that were employed for work with plutonium and other radioactive materials. The decommissioning process involved an initial phase of clearing tools and materials from the glove boxes and disconnecting them from the laboratory infrastructure. The removed materials, assessed as Transuranic (TRU) waste, were packaged into 55 gallon (200 litre) drums and prepared for ultimate disposal at the Waste Isolation Pilot Plant (WIPP) at Carlsbad New Mexico. The boxes were then sampled to determine the radioactive contents by means of smears that were counted with alpha and beta detectors to determine the residual surface contamination, especially in terms of alpha particle emitters that are an indicator of TRU activity. Paint chip samples were also collected and sent for laboratory analysis in order to ascertain the radioactive contamination contributing to the TRU activity as a fixed contamination. The investigations predicted that it may be feasible to reduce the residual surface contamination and render the glovebox structure low level waste (LLW) for disposal. In order to reduce the TRU activity a comprehensive decontamination process was initiated using chemical compounds that are particularly effective for lifting and dissolving radionuclides that adhere to the inner surfaces of the gloveboxes. The result of the decontamination process was a reduction in the TRU surface activity on the inner surfaces of the gloveboxes by four orders of magnitude in terms of disintegrations per unit area (DPA). The next phase of the process involved a comprehensive assay of the gloveboxes using a combination of passive neutron and gamma ray scintillation detectors and a shielded and collimated high purity Germanium (HPGe) gamma ray detector. The HPGe detector was used to obtain gamma ray spectra for a variety of measurement positions within the glovebox. The spectra were used to

  9. A Novel and Cost Effective Approach to the Decommissioning and Decontamination of Legacy Glove Boxes - Minimizing TRU Waste and Maximizing LLW Waste - 13634

    International Nuclear Information System (INIS)

    Pancake, Daniel; Rock, Cynthia M.; Creed, Richard; Donohoue, Tom; Martin, E. Ray; Mason, John A.; Norton, Christopher J.; Crosby, Daniel; Nachtman, Thomas J.

    2013-01-01

    This paper describes the process of decommissioning two gloveboxes at the Argonne National Laboratory (ANL) that were employed for work with plutonium and other radioactive materials. The decommissioning process involved an initial phase of clearing tools and materials from the glove boxes and disconnecting them from the laboratory infrastructure. The removed materials, assessed as Transuranic (TRU) waste, were packaged into 55 gallon (200 litre) drums and prepared for ultimate disposal at the Waste Isolation Pilot Plant (WIPP) at Carlsbad New Mexico. The boxes were then sampled to determine the radioactive contents by means of smears that were counted with alpha and beta detectors to determine the residual surface contamination, especially in terms of alpha particle emitters that are an indicator of TRU activity. Paint chip samples were also collected and sent for laboratory analysis in order to ascertain the radioactive contamination contributing to the TRU activity as a fixed contamination. The investigations predicted that it may be feasible to reduce the residual surface contamination and render the glovebox structure low level waste (LLW) for disposal. In order to reduce the TRU activity a comprehensive decontamination process was initiated using chemical compounds that are particularly effective for lifting and dissolving radionuclides that adhere to the inner surfaces of the gloveboxes. The result of the decontamination process was a reduction in the TRU surface activity on the inner surfaces of the gloveboxes by four orders of magnitude in terms of disintegrations per unit area (DPA). The next phase of the process involved a comprehensive assay of the gloveboxes using a combination of passive neutron and gamma ray scintillation detectors and a shielded and collimated high purity Germanium (HPGe) gamma ray detector. The HPGe detector was used to obtain gamma ray spectra for a variety of measurement positions within the glovebox. The spectra were used to

  10. Assessment of foreign decommissioning technology with potential application to US decommissioning needs

    International Nuclear Information System (INIS)

    Allen, R.P.; Konzek, G.J.; Schneider, K.J.; Smith, R.I.

    1987-09-01

    This study was conducted by the Pacific Northwest Laboratory (PNL) for the US Department of Energy (DOE) to identify and technically assess foreign decommissioning technology developments that may represent significant improvements over decommissioning technology currently available or under development in the United States. Technology need areas for nuclear power reactor decommissioning operations were identified and prioritized using the results of past light water reactor (LWR) decommissioning studies to quantitatively evaluate the potential for reducing cost and decommissioning worker radiation dose for each major decommissioning activity. Based on these identified needs, current foreign decommissioning technologies of potential interest to the US were identified through personal contacts and the collection and review of an extensive body of decommissioning literature. These technologies were then assessed qualitatively to evaluate their uniqueness, potential for a significant reduction in decommissioning costs and/or worker radiation dose, development status, and other factors affecting their value and applicability to US needs

  11. Drilling cost analysis

    International Nuclear Information System (INIS)

    Anand, A.B.

    1992-01-01

    Drilling assumes greater importance in present day uranium exploration which emphasizes to explore more areas on the basis of conceptual model than merely on surface anomalies. But drilling is as costly as it is important and consumes a major share (50% to 60%) of the exploration budget. As such the cost of drilling has great bearing on the exploration strategy as well as on the overall cost of the project. Therefore, understanding the cost analysis is very much important when planning or intensifying an exploration programme. This not only helps in controlling the current operations but also in planning the budgetary provisions for future operations. Also, if the work is entrusted to a private party, knowledge of in-house cost analysis helps in fixing the rates of drilling in different formations and areas to be drilled. Under this topic, various factors that contribute to the cost of drilling per meter as well as ways to minimize the drilling cost for better economic evaluation of mineral deposits are discussed. (author)

  12. Remote Decommissioning Experiences at Sellafield

    International Nuclear Information System (INIS)

    Brownridge, M.

    2006-01-01

    British Nuclear Group has demonstrated through delivery of significant decommissioning projects the ability to effectively deploy innovative remote decommissioning technologies and deliver cost effective solutions. This has been achieved through deployment and development of off-the-shelf technologies and design of bespoke equipment. For example, the worlds first fully remotely operated Brokk was successfully deployed to enable fully remote dismantling, packaging and export of waste during the decommissioning of a pilot reprocessing facility. British Nuclear Group has also successfully implemented remote decommissioning systems to enable the decommissioning of significant challenges, including dismantling of a Caesium Extraction Facility, Windscale Pile Chimney and retrieval of Plutonium Contaminated Material (PCM) from storage cells. The challenge for the future is to continue to innovate through utilization of the supply chain and deploy off-the-shelf technologies which have been demonstrated in other industry sectors, thus reducing implementation schedules, cost and maintenance. (authors)

  13. 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.)

  14. Cost-benefit analyses for decommissioning and dismantling of nuclear power stations

    International Nuclear Information System (INIS)

    Hock, R.

    1988-01-01

    According to ICRP provisions, radiation doses to the population are to be kept as low as possible, on the basis of a justifiable relationship between additional expense for dose reduction and the radiological benefit. The paper examines whether this optimisation principle requires maximum conceivable limits of personal doses as a result of materials recovery from dismantling ought to be reviewed, and whether clearance levels for materials to be recycled have to be reduced. The cost-benefit assessments presented for various options take into account the cost involved for processing and recycling methods as well as the social burden of dose commitments. A comparison in terms of radiological safety is presented for ultimate disposal of material, or meltdown of material subject to appropriate radiological measurement and surveillance. (DG) [de

  15. Shippingport Station Decommissioning Project Start of Physical Decommissioning

    International Nuclear Information System (INIS)

    Crimi, F. P.

    1987-01-01

    The Shippingport Atomic Power Station consists of the nuclear steam supply system and associated radioactive waste processing systems, which are owned by the United States Department of Energy, and the turbine-generator and balance of plant, which is owned by the Duquesne Light Company. The station is located at Shippingport, Pennsylvania on seven acres of land leased by DOE from Duquesne Light Company. The Shippingport Station Decommissioning Project is being performed under contract to the DOE by the General Electric Company and its integrated subcontractor, Morrison-Knudsen Company. as the Decommissioning Operations Contractor. This paper describes the current status of the physical decommissioning work, which started September 1985. The preparations required to start a major decommissioning work effort in a safe and cost effective manner are discussed including the development and implementation of a cost/schedule control system. The detailed plan required to ensure that people, property, and procedures are ready in sufficient time to support the start of physical decommissioning is also discussed. The total estimated cost of the Shippingport Station Decommissioning Project should be $98.3 M, with the Project scheduled for completion in April 1990. As the decommissioning of the first commercial-scale nuclear power plant, the Shippingport Project is expected to set the standard for safe, cost-effective demolition of nuclear plants

  16. Reactor decommissioning

    International Nuclear Information System (INIS)

    Lawton, H.

    1984-01-01

    A pioneering project on the decommissioning of the Windscale Advanced Gas-cooled Reactor, by the UKAEA, is described. Reactor data; policy; waste management; remote handling equipment; development; and recording and timescales, are all briefly discussed. (U.K.)

  17. Radiological impacts of Jackpile-Paguate uranium mines: an analysis of alternatives of decommissioning

    International Nuclear Information System (INIS)

    Momeni, M.H.; Tsai, S.Y.H.; Yang, J.Y.; Gureghian, A.B.; Dungey, C.E.

    1983-03-01

    Potential pathways of radiation exposure and radiation-induced genetic and somatic effects from materials at the mine complex under five alternatives of decommissioning were analyzed using UDAD and PRIM computer codes. The principal pathways of exposure included in the analysis were inhalation of airborne radionuclides, ingestion of food and water containing radionuclides, and extended exposure to gamma and beta radiation from either airborne or ground-deposited radionuclides. The alternatives of decommissioning include (A) No Action (site will be fenced, otherwise left as it is), (B) No Future Use (site will be fenced and all disturbed area will be covered with 30 cm of soil, no grazing on the site); (C1) Grazing Land Use as developed by Anaconda Company (protore, waste piles, and open pits covered with 120 cm of soil, the remainder of the disturbed areas covered with 30 cm of soil, pits backfilled 90 cm above the equilibrium groundwater recovery level, no human habitation or farming allowed on the mine site, but grazing would be allowed); (C2) Grazing Land Use as developed by US Department of the Interior (similar to Alternative C1, but the pits covered with 300 cm of soil above the groundwater recovery level); and (D) Maximum Future Use (similar to Alternative C2, except construction of commercial and industrial facilities, storage, recreation, and further mining would be allowed). Radiation doses from atmospheric transport and ingestion of radionuclides were calculated, and somatic and genetic effects in individuals living within 80 km from the mine complex were predicted. Hydrological flow patterns in the mine area were analyzed to determine the potential for future contamination of surface water and groundwater and to determine the groundwater recovery level after reclamation, thus permitting incorporation of corrective actions into the reclamation procedures

  18. Financial aspects of decommissioning

    International Nuclear Information System (INIS)

    Chirica, T.; Havris, A.

    2003-01-01

    European Commission adopted recently two proposals of Directives designed to pave the way for a Community approach to the safety of nuclear power plants and the processing of radioactive waste. Nuclear safety cannot be guaranteed without making available adequate financial resources. With regard, in particular, to the decommissioning of nuclear facilities, the Directive defines the Community rules for the establishment, management and use of decommissioning funds allocated to a body with legal personality separate from that of the nuclear operator. In order to comply with the acquis communautaire, Romanian Government issued the Emergency Ordinance no. 11/2003 which set up the National Agency for Radioactive Waste (ANDRAD) and soon will be established the financial mechanism for raising the necessary funds. Societatea Nationala 'Nuclearelectrica' S.A. operates, through one of its branches, Cernavoda NPP Unit 1 and has to prepare its decommissioning strategy and to analyze the options to assure the financing for covering the future costs. The purpose of this paper is to clarify the financial systems' mechanisms to the satisfaction of the nuclear operator obligations, according to the disbursement schedule foreseen by decommissioning projects . The availability of cash to pay for all the decommissioning expenditure must be foreseen by setting up assets and establishing a suitable financing plan. The different practices of assets management shall be presented in this paper on the basis of the international experience. Some calculation samples shall be given as an illustration. (author)

  19. Decommissioning: the final folly

    International Nuclear Information System (INIS)

    Dibdin, T.

    1990-01-01

    The Second International Seminar on Decommissioning of Nuclear Facilities held in London is reviewed. Various solutions to the reactor decommissioning, including isolating the reactor core, and turning the surrounding buildings into a theme park, are mentioned. The International Atomic Energy Agency identifies three decommissioning stages. Stage 1, defuelling; Stage 2 dismounting of non-radioactive plant with isolation of the nuclear island and Stage 3, return to a 'green field' site. The real debate is about waste management and timing of the stages - whether to defer Stage 3 for a century or so, or even whether to attempt Stage 3 at all. Cost estimation is also discussed. In the United Kingdom, the timing of completion of the deep repository for high level waste will affect the timing. (UK)

  20. Revised Analyses of Decommissioning Reference Non-Fuel-Cycle Facilities

    International Nuclear Information System (INIS)

    Bierschbach, M.C.; Haffner, D.R.; Schneider, K.J.; Short, S.M.

    2002-01-01

    that contaminated components either be: (1) decontaminated to restricted or unrestricted release levels or (2) packaged and shipped to an authorized disposal site. This study considers unrestricted release only. The new decommissioning criteria of July 1997 are too recent for this study to include a cost analysis of the restricted release option, which is now allowed under these new criteria. The costs of decommissioning facility components are generally estimated to be in the range of $140 to $27,000, depending on the type of component, the type and amount of radioactive contamination, the remediation options chosen, and the quantity of radioactive waste generated from decommissioning operations. Estimated costs for decommissioning the example laboratories range from $130,000 to $205,000, assuming aggressive low-level waste (LLW) volume reduction. If only minimal LLW volume reduction is employed, decommissioning costs range from $150,000 to $270,000 for these laboratories. On the basis of estimated decommissioning costs for facility components, the costs of decommissioning typical non-fuel-cycle laboratory facilities are estimated to range from about $25,000 for the decommissioning of a small room containing one or two fume hoods to more than $1 million for the decommissioning of an industrial plant containing several laboratories in which radiochemicals and sealed radioactive sources are prepared. For the reference sites of this study, the basic decommissioning alternatives are: (1) site stabilization followed by long-term care and (2) removal of the waste or contaminated soil to an authorized disposal site. Cost estimates made for decommissioning three reference sites range from about $130,000 for the removal of a contaminated drain line and hold-up tank to more than $23 million for the removal of a tailings pile that contains radioactive residue from ore-processing operations in which tin slag is processed for the recovery of rare metals. Total occupational

  1. Revised Analyses of Decommissioning Reference Non-Fuel-Cycle Facilities

    Energy Technology Data Exchange (ETDEWEB)

    MC Bierschbach; DR Haffner; KJ Schneider; SM Short

    2002-12-01

    facility, DECON requires that contaminated components either be: (1) decontaminated to restricted or unrestricted release levels or (2) packaged and shipped to an authorized disposal site. This study considers unrestricted release only. The new decommissioning criteria of July 1997 are too recent for this study to include a cost analysis of the restricted release option, which is now allowed under these new criteria. The costs of decommissioning facility components are generally estimated to be in the range of $140 to $27,000, depending on the type of component, the type and amount of radioactive contamination, the remediation options chosen, and the quantity of radioactive waste generated from decommissioning operations. Estimated costs for decommissioning the example laboratories range from $130,000 to $205,000, assuming aggressive low-level waste (LLW) volume reduction. If only minimal LLW volume reduction is employed, decommissioning costs range from $150,000 to $270,000 for these laboratories. On the basis of estimated decommissioning costs for facility components, the costs of decommissioning typical non-fuel-cycle laboratory facilities are estimated to range from about $25,000 for the decommissioning of a small room containing one or two fume hoods to more than $1 million for the decommissioning of an industrial plant containing several laboratories in which radiochemicals and sealed radioactive sources are prepared. For the reference sites of this study, the basic decommissioning alternatives are: (1) site stabilization followed by long-term care and (2) removal of the waste or contaminated soil to an authorized disposal site. Cost estimates made for decommissioning three reference sites range from about $130,000 for the removal of a contaminated drain line and hold-up tank to more than $23 million for the removal of a tailings pile that contains radioactive residue from ore-processing operations in which tin slag is processed for the recovery of rare metals. Total

  2. Decommissioning of multiple-reactor stations: facilitation by sequential decommissioning

    International Nuclear Information System (INIS)

    Moore, E.B.; Smith, R.I.; Wittenbrock, N.G.

    1982-01-01

    Reductions in cost and radiation dose can be achieved for decommissionings at multiple reactor stations because of factors not necessarily present at a single reactor station: reactors of similar design, the opportunity for sequential decommissioning, a site dedicated to nuclear power generation, and the option of either interim or permanent low-level radioactive waste storage facilities onsite. The cost and radiation dose reductions occur because comprehensive decommissioning planning need only be done once, because the labor force is stable and need only be trained once, because there is less handling of radioactive wastes, and because central stores, equipment, and facilities may be used. The cost and radiation dose reductions are sensitive to the number and types of reactors on the site, and to the alternatives selected for decommissioning. 3 tables

  3. 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)

  4. Development of decommissioning system engineering technology

    International Nuclear Information System (INIS)

    Lee, K. W.; Kim, S. K.; Seo, B. K.

    2012-02-01

    In the decommissioning planning stage, it is important to select the optimized decommissioning process considering the cost and safety. Especially the selection of the optimized decommissioning process is necessary because it affects to improve worker's safety and decommissioning work efficiency. The decommissioning process evaluation technology can provide the optimized decommissioning process as constructing various decommissioning scenarios and it can help to prevent the potential accidents as delivering the exact work procedures to workers and to help workers to perform decommissioning work skillfully. It's necessary to measure the radioactive contamination in the highly contaminated facilities such as hot-cells or glove-boxes to be decommissioned for decommissioning planning. These facilities are very high radiation level, so it is difficult to approach. In this case the detector system is preferable to separate the sensor and electronics, which have to locate in the facility outside to avoid the electric noise and worker's radiation exposure. In this project, we developed the remote detection system for radiation measurement and signal transmission in the high radiation area. In order to minimize worker's exposure when decommissioning highly activated nuclear facilities, it is necessary to develop the remote handling tool to perform the dismantling work remotely. Especially, since cutting, measuring, and decontamination works should be performed remotely in the highly activated area, the remote handling tool for conducting these works should be developed. Therefore, the multi-purpose dismantling machine that can measuring dose, facility cutting, and remote handling for maintenance and decommissioning of highly activated facility should be needed

  5. Decommissioning Plan for European Spallation Source

    Directory of Open Access Journals (Sweden)

    Ene Daniela

    2017-01-01

    Full Text Available This paper is a survey of the European Spallation Source initial decommissioning plan developed in compliance with Swedish Regulatory Authority requirements. The report outlines the decommissioning strategy selected and the baseline plan for decommissioning. Types and quantities of radioactive waste estimated to be generated at the final shut-down of the facility are further provided. The paper ends up with the analysis of the key elements of the decommissioning plan and the recommendations to the ESS management team..

  6. The System Cost Model: A tool for life cycle cost and risk analysis

    International Nuclear Information System (INIS)

    Hsu, K.; Lundeen, A.; Shropshire, D.; Sherick, M.

    1996-01-01

    In May of 1994, Lockheed Idaho Technologies Company (LITCO) in Idaho Falls, Idaho and subcontractors began development of the System Cost Model (SCM) application. The SCM estimates life cycle costs of the entire US Department of Energy (DOE) complex for designing; constructing; operating; and decommissioning treatment, storage, and disposal (TSD) facilities for mixed low-level, low-level, and transuranic waste. The SCM uses parametric cost functions to estimate life cycle costs for various treatment, storage, and disposal modules which reflect planned and existing waste management facilities at DOE installations. In addition, SCM can model new TSD facilities based on capacity needs over the program life cycle. The user can provide input data (default data is included in the SCM) including the volume and nature of waste to be managed, the time period over which the waste is to be managed, and the configuration of the waste management complex (i.e., where each installation's generated waste will be treated, stored, and disposed). Then the SCM uses parametric cost equations to estimate the costs of pre-operations (designing), construction, operations and maintenance, and decommissioning these waste management facilities. The SCM also provides transportation costs for DOE wastes. Transportation costs are provided for truck and rail and include transport of contact-handled, remote-handled, and alpha (transuranic) wastes. A complement to the SCM is the System Cost Model-Risk (SCM-R) model, which provides relative Environmental, Safety, and Health (ES and H) risk information. A relative ES and H risk basis has been developed and applied by LITCO at the INEL. The risk basis is now being automated in the SCM-R to facilitate rapid risk analysis of system alternatives. The added risk functionality will allow combined cost and risk evaluation of EM alternatives

  7. Decommissioning licensing procedure

    International Nuclear Information System (INIS)

    Perello, M.

    1979-01-01

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

  8. The waste management implications of decommissioning

    International Nuclear Information System (INIS)

    Passant, F.H.

    1988-01-01

    Decommissioning policy can only be framed in the light of radioactive waste management policy. What can be done with the waste materials, how and when, will determine the overall decommissioning plans and costs. In this paper the waste management options and their costs are reviewed for the decommissioning of the Central Electricity Generating Boards civil nuclear power stations. The paper concentrates on the decommissioning of Magnox stations, although comparative information on waste volumes and costs are given for the AGR programme and a typical PWR. (author)

  9. Decommissioning - The worldwide challenge

    International Nuclear Information System (INIS)

    McKeown, John

    2002-01-01

    Full text: Whatever the future may hold for nuclear power, there are closed or ageing nuclear facilities in many countries around the world. While these may be in safe care and maintenance at present, a sustainable long term solution is required. Facilities need to be decommissioned, contaminated land remediated, and wastes conditioned for safe storage or disposal. Practical nuclear site restoration has been demonstrated internationally. This experience has revealed generic challenges in dealing with old, often experimental, facilities. These include: Facilities not designed for ease of decommissioning; Records of plant construction and operation, and of the materials utilised and wastes produced, not to modern standards; Fuels and wastes stored for long periods in less than optimal conditions, leading to deterioration and handling problems; The historic use of experimental fuels and materials, giving rise to unique waste streams requiring unique waste management solutions; The application of modern safety and environmental standards to plant which dates from the 1940s, 50s and 60s, requiring investment before decommissioning can even commence. These problems can be tackled, as examples from UKAEA's own programme will illustrate. But two fundamental issues must be recognised and considered. First, the costs of decommissioning older facilities are very high, and may place a heavy burden on national budgets, despite using best efforts to control them. We can limit these costs by learning from one another's experience and sharing the development of new techniques and technologies. UKAEA has already initiated a programme of international collaboration, and hopes that other IAEA countries will be encouraged to follow suit. But whilst the costs of decommissioning may be high, the process normally meets with public acceptance. This is seldom the case for long term waste storage or disposal. Until waste management routes are available - either nationally or internationally

  10. 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)

  11. A Comparative Perspective on Reactor Decommissioning

    International Nuclear Information System (INIS)

    Devgun, J.S.; Zelmer, R.

    2006-01-01

    A comparative perspective on decommissioning, based on facts and figures as well as the national policies, is useful in identifying mutually beneficial 'lessons learned' from various decommissioning programs. In this paper we provide such a perspective on the US and European approaches based on a review of the programmatic experience and the decommissioning projects. The European countries selected for comparison, UK, France, and Germany, have nuclear power programs comparable in size and vintage to the US program but have distinctly different policies at the federal level. The national decommissioning scene has a lot to do with how national nuclear energy policies are shaped. Substantial experience exists in all decommissioning programs and the technology is in a mature state. Substantial cost savings can result from sharing of decommissioning information, technologies and approaches among various programs. However, the Achilles' heel for the decommissioning industry remains the lack of appropriate disposal facilities for the nuclear wastes. (authors)

  12. Information on Hydrologic Conceptual Models, Parameters, Uncertainty Analysis, and Data Sources for Dose Assessments at Decommissioning Sites

    International Nuclear Information System (INIS)

    Meyer, Philip D.; Gee, Glendon W.; Nicholson, Thomas J.

    1999-01-01

    This report addresses issues related to the analysis of uncertainty in dose assessments conducted as part of decommissioning analyses. The analysis is limited to the hydrologic aspects of the exposure pathway involving infiltration of water at the ground surface, leaching of contaminants, and transport of contaminants through the groundwater to a point of exposure. The basic conceptual models and mathematical implementations of three dose assessment codes are outlined along with the site-specific conditions under which the codes may provide inaccurate, potentially nonconservative results. In addition, the hydrologic parameters of the codes are identified and compared. A methodology for parameter uncertainty assessment is outlined that considers the potential data limitations and modeling needs of decommissioning analyses. This methodology uses generic parameter distributions based on national or regional databases, sensitivity analysis, probabilistic modeling, and Bayesian updating to incorporate site-specific information. Data sources for best-estimate parameter values and parameter uncertainty information are also reviewed. A follow-on report will illustrate the uncertainty assessment methodology using decommissioning test cases

  13. Information on Hydrologic Conceptual Models, Parameters, Uncertainty Analysis, and Data Sources for Dose Assessments at Decommissioning Sites

    International Nuclear Information System (INIS)

    Meyer D, Philip; Gee W, Glendon

    2000-01-01

    This report addresses issues related to the analysis of uncertainty in dose assessments conducted as part of decommissioning analyses. The analysis is limited to the hydrologic aspects of the exposure pathway involving infiltration of water at the ground surface, leaching of contaminants, and transport of contaminants through the groundwater to a point of exposure. The basic conceptual models and mathematical implementations of three dose assessment codes are outlined along with the site-specific conditions under which the codes may provide inaccurate, potentially nonconservative results. In addition, the hydrologic parameters of the codes are identified and compared. A methodology for parameter uncertainty assessment is outlined that considers the potential data limitations and modeling needs of decommissioning analyses. This methodology uses generic parameter distributions based on national or regional databases, sensitivity analysis, probabilistic modeling, and Bayesian updating to incorporate site-specific information. Data sources for best-estimate parameter values and parameter uncertainty information are also reviewed. A follow-on report will illustrate the uncertainty assessment methodology using decommissioning test cases

  14. Optimizing decommissioning strategies

    International Nuclear Information System (INIS)

    Passant, F.H.

    1993-01-01

    Many different approaches can be considered for achieving satisfactory decommissioning of nuclear installations. These can embrace several different engineering actions at several stages, with time variations between the stages. Multi-attribute analysis can be used to help in the decision making process and to establish the optimum strategy. It has been used in the Usa and the UK to help in selecting preferred sites for radioactive waste repositories, and also in UK to help with the choice of preferred sites for locating PWR stations, and in selecting optimum decommissioning strategies

  15. Present status of research reactor decommissioning programme in Indonesia

    International Nuclear Information System (INIS)

    Suripto, A.; Mulyanto, N.

    2002-01-01

    At present Indonesia has 3 research reactors, namely the 30 MW MTR-type multipurpose reactor at Serpong Site, two TRIGA-type research reactors, the first one being 1 MW located at Bandung Site and the second one a small reactor of 100 kW at Yogyakarta Site. The TRIGA Reactor at the Bandung Site reached its first criticality at 250 kW in 1964, and then was operated at 1000 kW since 1971. In October 2000 the reactor power was successfully upgraded to 2 MW. This reactor has already been operated for 38 years. There is not yet any decision for the decommissioning of this reactor. However it will surely be an object for the near future decommissioning programme and hence anticipation for the above situation becomes necessary. The regulation on decommissioning of research reactor is already issued by the independent regulatory body (BAPETEN) according to which the decommissioning permit has to be applied by the BATAN. For Indonesia, an early decommissioning strategy for research reactor dictates a restricted re-use of the site for other nuclear installation. This is based on high land price, limited availability of radwaste repository site, and other cost analysis. Spent graphite reflector from the Bandung TRIGA reactor is recommended for a direct disposal after conditioning, without any volume reduction treatment. Development of human resources, technological capability as well as information flow from and exchange with advanced countries are important factors for the future development of research reactor decommissioning programme in Indonesia. (author)

  16. Engineering Evaluation/Cost Analysis for Power Burst Facility (PER-620) Final End State and PBF Vessel Disposal

    Energy Technology Data Exchange (ETDEWEB)

    B. C. Culp

    2007-05-01

    Preparation of this engineering evaluation/cost analysis is consistent with the joint U.S. Department of Energy and U.S. Environmental Protection Agency Policy on Decommissioning of Department of Energy Facilities Under the Comprehensive Environmental Response, Compensation, and Liability Act, (DOE and EPA 1995) which establishes the Comprehensive Environmental, Response, Compensation, and Liability Act non-time critical removal action process as an approach for decommissioning. The scope of this engineering evaluation/cost analysis is to evaluate alternatives and recommend a preferred alternative for the final end state of the PBF and the final disposal location for the PBF vessel.

  17. Facilitation of decommissioning light water reactors

    International Nuclear Information System (INIS)

    Moore, E.B. Jr.

    1979-12-01

    Information on design features, special equipment, and construction methods useful in the facilitation of decommissioning light water reactors is presented. A wide range of facilitation methods - from improved documentation to special decommissioning tools and techniques - is discussed. In addition, estimates of capital costs, cost savings, and radiation dose reduction associated with these facilitation methods are given

  18. Challenges for decommissioning policies

    International Nuclear Information System (INIS)

    Riotte, H.

    2007-01-01

    In the coming years, OECD member countries will be increasingly faced with the need to make appropriate provisions, in terms of policy, finance and management, for all aspects of decommissioning. Decommissioning requires regulatory approval and oversight, the directions of which are guided by national policy. In several instances, governments have only recently begun to address their approaches to decommissioning policy and regulation in national legislation, and international overviews of such approaches, which may eventually lead to international harmonization, are only now beginning to emerge. In parallel, policy and regulation have been evolving and a broadened competence has developed in relevant regulatory authorities. The challenge lying ahead is to establish a framework that will allow for the growth of nuclear industrial activities in competitive, globalized markets, while maintaining and assuring the safety of decommissioning for the public and for workers. Within this context, institutional arrangements, stakeholder issues, costs and funding, waste management and policies for release from regulatory control, as well as the availability of technologies and skills, need to be reviewed. (author)

  19. Particle-accelerator decommissioning

    International Nuclear Information System (INIS)

    Opelka, J.H.; Mundis, R.L.; Marmer, G.J.; Peterson, J.M.; Siskind, B.; Kikta, M.J.

    1979-12-01

    Generic considerations involved in decommissioning particle accelerators are examined. There are presently several hundred accelerators operating in the United States that can produce material containing nonnegligible residual radioactivity. Residual radioactivity after final shutdown is generally short-lived induced activity and is localized in hot spots around the beam line. The decommissioning options addressed are mothballing, entombment, dismantlement with interim storage, and dismantlement with disposal. The recycle of components or entire accelerators following dismantlement is a definite possibility and has occurred in the past. Accelerator components can be recycled either immediately at accelerator shutdown or following a period of storage, depending on the nature of induced activation. Considerations of cost, radioactive waste, and radiological health are presented for four prototypic accelerators. Prototypes considered range from small accelerators having minimal amounts of radioactive mmaterial to a very large accelerator having massive components containing nonnegligible amounts of induced activation. Archival information on past decommissionings is presented, and recommendations concerning regulations and accelerator design that will aid in the decommissioning of an accelerator are given

  20. Conservation and balance principles approach in NPP decommissioning

    International Nuclear Information System (INIS)

    Anton, V.

    1997-01-01

    In this work some principles of mass, energy, activity level conservation are formulated. When some conditioning or treatment procedures for High Level Waste (HLW) are applied then the corresponding balance principles operate. It is important to note that in AECL computing code DECOM an analysis of different versions of decommissioning based on cost consideration is given.. Our approach pointed out many possibilities which are to be taken into account in the NPP decommissioning, besides the minimum cost principle. We also remarked other circumstances pointing to other conservation principles and to the corresponding balance principles. In our opinion this is the first approach of this kind in international literature. With the progress which is expected in decommissioning techniques some of the considerations presented in this work have to be developed and detailed. (author)

  1. 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

  2. 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)

  3. 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.

  4. Cost benefit analysis vs. referenda

    OpenAIRE

    Martin J. Osborne; Matthew A. Turner

    2007-01-01

    We consider a planner who chooses between two possible public policies and ask whether a referendum or a cost benefit analysis leads to higher welfare. We find that a referendum leads to higher welfare than a cost benefit analyses in "common value" environments. Cost benefit analysis is better in "private value" environments.

  5. Decommissioning commercial nuclear facilities: a review and analysis of current regulations

    International Nuclear Information System (INIS)

    Schilling, A.H.; Lippek, H.E.; Tegeler, P.D.; Easterling, J.D.

    1979-08-01

    This report describes and analyzes the regulatory requirements and guidelines applicable to the decommissioning of commercial light water reactors, other commercial nuclear fuel cycle facilities, and byproduct utilization facilities, as contained principally in the United States Code, the United States Code of Federal Regulations, and the United States Nuclear Regulatory Commission's Regulatory Guides. State requirements are discussed where appropriate. The report provides general background informaion to license applicants and to other interested parties. Included is an outline of procedural steps required of an applicant to comply with decommissioning regulatory requiremets

  6. The decommissioning and demolition of four suites of high active chemical analysis cells at DNPDE

    International Nuclear Information System (INIS)

    Black, R.M.; Spence, B.W.; Stewart, C.W.

    1987-11-01

    The decommissioning and demolition of four laboratory suites of high active cells at DNPDE is described. All four suites had suffered drain leaks of high active liquor into underfloor ducts; the options available at the time and current policy for dealing with the resultant activity deposits are given. The decommissioning procedures are detailed to provide information for future similar exercises. Features to ease demolition of such facilities and to eliminate the possibility of long term activity deposition from drain leaks are highlighted for incorporation in future designs. The waste arisings and radiation doses received during the work are tabulated. (author)

  7. 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

  8. Assessment of financial expenditure for Rivne NPP power units decommissioning

    International Nuclear Information System (INIS)

    Nosovskij, A.V.; Salij, L.M.

    2007-01-01

    The article covers some financial aspects of developing a decommissioning concept for Rivne NPP power units with reactor VVER-440 and VVER-1000. Possible methodological approaches to costs estimate have been analyzed. Preliminary results of cost estimation are presented for two decommissioning options: deferred and immediate dismantling. Principally possible options for accumulating assets have been analyzed to finance measures related to Rivne NPP decommissioning. A mathematical model has been proposed for creating decommissioning financial reserve

  9. Decommissioning high-level waste surface facilities

    International Nuclear Information System (INIS)

    1978-04-01

    The protective storage, entombment and dismantlement options of decommissioning a High-Level Waste Surface Facility (HLWSF) was investigated. A reference conceptual design for the facility was developed based on the designs of similar facilities. State-of-the-art decommissioning technologies were identified. Program plans and cost estimates for decommissioning the reference conceptual designs were developed. Good engineering design concepts were on the basis of this work identified

  10. An outsider's view of decommissioning

    International Nuclear Information System (INIS)

    Wilkie, T.

    1996-01-01

    The decommissioning of nuclear facilities is not just a technical or even a financial issue. Presenting decommissioning as a technically difficult task overcome by superhuman effort on the part of the industry will not gain much credit amongst sophisticated consumers who now require that any complex technology will work and work safely. Any engineering problems are surmountable given the money to find the solution. Some of the financial aspects of decommissioning are worrying, however, given their open-ended nature. The cost of waste disposal is one of these. Despite a lapse of fifty years since the start-up of its first reactor, the United Kingdom is unlikely to have available a repository for the disposal of intermediate level waste until about 2020. Waste disposal is a large consideration in decommissioning and the industry's forecasts of cost in this area lack credibility in the light of a poor track record in financial prediction. Financial engineering in the form of the segregated fund set up in March 1996 to cover the decommissioning of nuclear power stations in the United Kingdom is likely to provide only short term reassurance in the light of doubts about a credible future for nuclear power. This lack of confidence over the wider problems of nuclear power creates particular problems for decommissioning which go beyond technical difficulties and complicate financial considerations. (UK)

  11. 1982 international decommissioning symposium

    International Nuclear Information System (INIS)

    Mickelson, S.

    1982-01-01

    Sixty-four papers were presented at the following sessions: policy, regulations, and standards; management of decommissioning wastes; decommissioning experience; decommissioning tooling and techniques; radiological concerns; and planning and engineering

  12. Liabilities for the decommissioning and disposal in the nuclear area. Analysis and concept of reformation

    International Nuclear Information System (INIS)

    Meyer, Bettina

    2012-01-01

    The contribution under consideration examines the adequacy of the reserves for decommissioning / dismantling and disposal in order to finance long-term tasks. A reform concept is presented. The two key components of the reformation are the establishment of a public fund for the long-term obligations and a stronger insolvency protection of medium-term nuclear liabilities.

  13. Abbreviated sampling and analysis plan for planning decontamination and decommissioning at Test Reactor Area (TRA) facilities

    International Nuclear Information System (INIS)

    1994-10-01

    The objective is to sample and analyze for the presence of gamma emitting isotopes and hazardous constituents within certain areas of the Test Reactor Area (TRA), prior to D and D activities. The TRA is composed of three major reactor facilities and three smaller reactors built in support of programs studying the performance of reactor materials and components under high neutron flux conditions. The Materials Testing Reactor (MTR) and Engineering Test Reactor (ETR) facilities are currently pending D/D. Work consists of pre-D and D sampling of designated TRA (primarily ETR) process areas. This report addresses only a limited subset of the samples which will eventually be required to characterize MTR and ETR and plan their D and D. Sampling which is addressed in this document is intended to support planned D and D work which is funded at the present time. Biased samples, based on process knowledge and plant configuration, are to be performed. The multiple process areas which may be potentially sampled will be initially characterized by obtaining data for upstream source areas which, based on facility configuration, would affect downstream and as yet unsampled, process areas. Sampling and analysis will be conducted to determine the level of gamma emitting isotopes and hazardous constituents present in designated areas within buildings TRA-612, 642, 643, 644, 645, 647, 648, 663; and in the soils surrounding Facility TRA-611. These data will be used to plan the D and D and help determine disposition of material by D and D personnel. Both MTR and ETR facilities will eventually be decommissioned by total dismantlement so that the area can be restored to its original condition

  14. 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.)

  15. [Operating cost analysis of anaesthesia: activity based costing (ABC analysis)].

    Science.gov (United States)

    Majstorović, Branislava M; Kastratović, Dragana A; Vučović, Dragan S; Milaković, Branko D; Miličić, Biljana R

    2011-01-01

    Cost of anaesthesiology represent defined measures to determine a precise profile of expenditure estimation of surgical treatment, which is important regarding planning of healthcare activities, prices and budget. In order to determine the actual value of anaestesiological services, we started with the analysis of activity based costing (ABC) analysis. Retrospectively, in 2005 and 2006, we estimated the direct costs of anestesiological services (salaries, drugs, supplying materials and other: analyses and equipment.) of the Institute of Anaesthesia and Resuscitation of the Clinical Centre of Serbia. The group included all anesthetized patients of both sexes and all ages. We compared direct costs with direct expenditure, "each cost object (service or unit)" of the Republican Healthcare Insurance. The Summary data of the Departments of Anaesthesia documented in the database of the Clinical Centre of Serbia. Numerical data were utilized and the numerical data were estimated and analyzed by computer programs Microsoft Office Excel 2003 and SPSS for Windows. We compared using the linear model of direct costs and unit costs of anaesthesiological services from the Costs List of the Republican Healthcare Insurance. Direct costs showed 40% of costs were spent on salaries, (32% on drugs and supplies, and 28% on other costs, such as analyses and equipment. The correlation of the direct costs of anaestesiological services showed a linear correlation with the unit costs of the Republican Healthcare Insurance. During surgery, costs of anaesthesia would increase by 10% the surgical treatment cost of patients. Regarding the actual costs of drugs and supplies, we do not see any possibility of costs reduction. Fixed elements of direct costs provide the possibility of rationalization of resources in anaesthesia.

  16. The curious accountancy of decommissioning

    International Nuclear Information System (INIS)

    Anon.

    1990-01-01

    Financial provision for the decommissioning and waste management of the United Kingdom Magnox and AGR reactor is discussed. In the last set of accounts prior to privatisation a decommissioning provision of Pound 8.34 bn was indicated whereas previous figures had only shown Pound 2.88. It is suggested that the increase was only achieved on paper, without real financial provision. Estimates of decommissioning costs for the Magnox stations have increased greatly. Cost estimates for AGR decommissioning have still to be released but it is expected that the post-privatisation owners of the nuclear power industry, Nuclear Electric, will have to find Pound 6-7 bn to dismantle its own reactors. Much of this it hopes to put off for over 100 years. The South of Scotland Electicity Board has made much more realistic provision for its own Magnox and two AGR stations. Reprocessing costs for AGR reactor fuel is uncertain and high reprocessing and decommissioning costs will mean increases in the price of nuclear electricity. (UK)

  17. Cost Improvement Analysis

    Science.gov (United States)

    1986-06-01

    Cc) Ul y Cli U;ra ISO or.) . ............ t cc fl .9 it it ý I oli CC) I it cli L3 I HIM .......... 114 t4l t.r IM...Burroughz Cost AFIT/LSQ AV785-6280 Curve Programs Prof. Jeff Daneman Z-100 Cost Curve ASD/ACCR AV785- 8583 Programs Capt Arthur Mills * *- PROGRAMS CONCEPT

  18. 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

  19. 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)

  20. EDF decommissioning and dismantling policy a global commitment to safety, environment and cost efficiency of nuclear energy

    International Nuclear Information System (INIS)

    Rondeau, J.

    2001-01-01

    Until recently, EDF's policy regarding the dismantling of its decommissioned nuclear power plants was to reach 'level 2' (release of non-nuclear facilities) and to postpone final dismantling for another 30-40 years. Today, some studies suggest that a full deconstruction program of the first generation NPPs (9 units) could be optimized over the period 2000 - 2025. EDF has acquired during the last ten years an unique experience, both as an operator and as an engineering company, in the frame of the decommissioning programme of its own NPPs. Many types of reactors, including graphite moderated one, PWR, are at varying stages of the dismantling process.Plant operation quality is at the core of a satisfactory control of releases. Over the last decade, as a result of the efforts of all operating sites associated with good in-house operating practice feedback, the overall release volume has been divided by two, and the release activity by one hundred. Another issue given increased attention is radiological cleanliness. EDF-DPN launched a 'radiological cleanliness' action plan revolving around two main themes: increased monitoring of nuclear-related transportations, site entrance and access to controlled areas, along with on-site radiological cleanliness, particularly during maintenance work tasks. Progress is already apparent in several points at issue and the overall objective of the action plan should be attained. (author)

  1. Project No. 8 - Final decommissioning plan

    International Nuclear Information System (INIS)

    2000-01-01

    Ignalina NPP should prepare the final Ignalina NPP unit 1 decommissioning plan by march 31, 2002. This plan should include the following : description of Ignalina NPP and the Ignalina NPP boundary that could be influenced by decommissioning process; decommissioning strategy selected and a logical substantiation for this selection; description of the decommissioning actions suggested and a time schedule for the actions to be performed; conceptual safety and environmental impact assessment covering ionizing radiation and other man and environment impact; description of the environmental monitoring program proposed during decommissioning process; description of the waste management proposed; assessment of decommissioning expenses including waste management, accumulated funds and other sources. Estimated project cost - 0.75 M EURO

  2. Human resource development for management of decommissioning

    International Nuclear Information System (INIS)

    Tanaka, Kenichi

    2017-01-01

    This paper described the contents of 'Human resource development for the planning and implementation of safe and reasonable nuclear power plant decommissioning' as the nuclear human resource development project by the Ministry of Education, Culture, Sports, Science and Technology. The decommissioning of a nuclear power plant takes 30 to 40 years for its implementation, costing tens of billions of yen. As the period of decommissioning is almost the same as the operation period, it is necessary to provide a systematic and continuous supply of engineers who understand the essence of the decommissioning project. The engineers required here should have project management ability to take charge of preparation, implementation, and termination of decommissioning, and have the ability to perform not only technology, but also factor management, cost management, and the like. As the preconditions of these abilities, it is important to develop human resources who possess qualities that can oversee decommissioning in the future. The contents of human resource education are as follows; (1) desk training (teaching materials: facilities of nuclear power plants, management of nuclear fuels, related laws, decommissioning work, decontamination, dismantling, disposal of waste, etc.), (2) field training (simulators, inspection of power station under decommissioning, etc.), (3) practical training (radiation inventory evaluation, and safety assessment), and (4) inspection of overseas decommissioning, etc. (A.O.)

  3. Workshop on decommissioning

    International Nuclear Information System (INIS)

    Broden, K.

    2005-12-01

    A Nordic workshop on decommissioning of nuclear facilities was held at Risoe in Denmark September 13-15, 2005. The workshop was arranged by NKS in cooperation with the company Danish Decommissioning, DD, responsible for decommissioning of nuclear facilities at Risoe. Oral presentations were made within the following areas: International and national recommendations and requirements concerning decommissioning of nuclear facilities Authority experiences of decommissioning cases Decommissioning of nuclear facilities in Denmark Decommissioning of nuclear facilities in Sweden Plans for decommissioning of nuclear facilities in Norway Plans for decommissioning of nuclear facilities in Finland Decommissioning of nuclear facilities in German and the UK Decommissioning of nuclear facilities in the former Soviet Union Results from research and development A list with proposals for future work within NKS has been prepared based on results from group-work and discussions. The list contains strategic, economical and political issues, technical issues and issues regarding competence and communication. (au)

  4. Strategic aspects on waste management in decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Rannemalm, T.; Eliasson, S.; Larsson, A.; Lidar, P.; Bergh, N.; Hedin, G.

    2017-01-01

    A team composed of experts from the facility owner OKG, Westinghouse and Studsvik (today Cyclife Sweden and Studsvik Consulting) was asked to develop a basis for decision on an overall strategy for the management of the material and waste arising from the decommissioning of two BWR NPPs at the Oskarshamn site in Sweden. To be able to provide a good basis for decision the full waste management chain from generation to disposition, i.e. clearance or disposal had to be assessed, categorised, quantified and analysed with regards to costs, environmental impact and risks. A systematic approach was applied taking benefit of the decommissioning studies made previously for the two facilities, the decommissioning concepts developed by Ndcon (the partnership in decommissioning between Studsvik and Westinghouse) and the combined knowledge and experience in the project team. In total 4 different waste management concepts were compared individually and in combinations. The four concepts evaluated were based on: direct disposal in the national geological repository; treatment of the waste for volume reduction and where applicable clearance in an external waste treatment facility; decontamination and clearance in an on-site waste treatment facility; direct disposal in a near surface repository at the NPP site. It was important to be able to compare the different options in a quantifiable way. Therefore the project team set up a matrix with parameters for the different options gained from the utility, the national waste management company, external vendors and the experience of the team. In this way a quantitative analysis could be done with the four different waste management options. In addition to the quantitative analysis the team summarised decades of experience in radioactive waste management and decommissioning recommendations and risk analyses. Special attention was given to risk mitigation and redundancy in the waste management chain. The development of an overall waste

  5. Main Results of Updated Decommission Conception of NPPs Operating in Ukraine

    International Nuclear Information System (INIS)

    Purtov, Oleg; Masko, Alexander; Vasilchenko, Victor

    2014-01-01

    Results of long-term planning analysis based on consideration of 6 possible scenarios for the nuclear energy development with 15 years and 20 years life time extensions of operation of nuclear power units beyond 30 year provided by original design are presented in the updated decommission conception of NPP's operating in Ukraine. These characteristics of the two main options for NPP decommissioning deferred or immediate dismantling, which is close to the level of acceptability with relative superiority variant of deferred dismantling, are presented. The best option for NPP unit decommissioning as comparative analysis results is the option with deferred dismantling with 30 years endurance time. It can be taken as a basis for optimal strategies for NPP unit decommission design development. Cost estimations for the decommissioning of WWER-440 and WWER-1000 reactor type units are presented in the updated conception. The updated cost assessment for required annual payments with uniform accumulation costs to the Decommission Fund corresponding deferred dismantling variant with 20 years life time extension operation time is 98,2 mln US$ per year. This value is 3.61% of the electricity generated by NPP's in Ukraine and supplied to the wholesale electricity market of Ukraine in 2012 base year. (authors)

  6. Decontamination and decommissioning technology tree and the current status of the technologies

    Energy Technology Data Exchange (ETDEWEB)

    Oh, Won Zin; Won, H.J.; Kim, G.N.; Lee, K.W.; Chol, W.K.; Jung, C.H.; Kim, C.J.; Kim, S.H.; Kwon, S.O.; Chung, C.M

    2001-03-01

    A technology tree diagram was developed on the basis of the necessary technologies applicable to the decontamination and decommissioning of nuclear facilities. The technology tree diagram is consist of 6 main areas such as characterization, decontamination, decommissioning and remote technology, radwaste management, site restoration, and decommissioning plan and engineering. Characterization is divided into 4 regions such as sampling and data collection, general characterization, chemical analysis and radiological analysis. Decontamination is also divided into 4 regions such as chemical decontamination, mechanical decontamination, the other decontamination technologies and new decontamination technologies. Decommissioning and remote technology area is divided into 4 regions such as cutting techniques, decommissioning technologies, new developing technologies and remote technologies. Radwaste management area is divided into 5 regions such as solid waste treatment, sludge treatment, liquid waste treatment, gas waste treatment and thermal treatment. Site restoration area is divided into 3 regions such as the evaluation of site contamination, soil decontamination and ground water decontamination. Finally, permission, decommissioning process, cost evaluation, quality assurance and the estimation of radionuclide inventory were mentioned in the decommissioning plan and engineering area. The estimated items for each technology are applicable domestic D and D facilities, D and D problem area and contamination/requirement, classification of D and D technology, similar technology, principle and overview of technology, status, science technology needs, implementation needs, reference and contact point.

  7. Decontamination and decommissioning technology tree and the current status of the technologies

    International Nuclear Information System (INIS)

    Oh, Won Zin; Won, H. J.; Kim, G. N.; Lee, K. W.; Chol, W. K.; Jung, C. H.; Kim, C. J.; Kim, S. H.; Kwon, S. O.; Chung, C. M.

    2001-03-01

    A technology tree diagram was developed on the basis of the necessary technologies applicable to the decontamination and decommissioning of nuclear facilities. The technology tree diagram is consist of 6 main areas such as characterization, decontamination, decommissioning and remote technology, radwaste management, site restoration, and decommissioning plan and engineering. Characterization is divided into 4 regions such as sampling and data collection, general characterization, chemical analysis and radiological analysis. Decontamination is also divided into 4 regions such as chemical decontamination, mechanical decontamination, the other decontamination technologies and new decontamination technologies. Decommissioning and remote technology area is divided into 4 regions such as cutting techniques, decommissioning technologies, new developing technologies and remote technologies. Radwaste management area is divided into 5 regions such as solid waste treatment, sludge treatment, liquid waste treatment, gas waste treatment and thermal treatment. Site restoration area is divided into 3 regions such as the evaluation of site contamination, soil decontamination and ground water decontamination. Finally, permission, decommissioning process, cost evaluation, quality assurance and the estimation of radionuclide inventory were mentioned in the decommissioning plan and engineering area. The estimated items for each technology are applicable domestic D and D facilities, D and D problem area and contamination/requirement, classification of D and D technology, similar technology, principle and overview of technology, status, science technology needs, implementation needs, reference and contact point

  8. Eastern and Central Europe Decommissioning, ECED 2015 - Book of Abstracts

    International Nuclear Information System (INIS)

    2015-01-01

    Scientific conference deals with problems of reactor decommissioning and radioactive waste management in the Central Europe. The Conference included the following sessions: (1): Characterisation and Radioactive Waste Management; (2) Managerial Aspects of Decommissioning; (3) JAVYS Experience with Back-End of Nuclear Power Engineering - Progress in Last 2 Years; (4) Decommissioning Planning and Costing and Education; (5) Technical Aspects of Decommissioning; (6) Radioactive Waste Management; (4) Poster Session. The Book of Abstracts contains two invitation speeches and 30 abstracts.

  9. Decommissioning of Ukrainian NPPs

    International Nuclear Information System (INIS)

    Skripov, A.E.

    2002-01-01

    The decision about the development of 'Decommissioning Concept of Ukrainian NPPs' being on commercial operational stage was approved by NAEK 'Energoatom' Board of Administration by way of the decommissioning activity effective planning. The Concept will be the branch document, containing common approaches formulations on problem decisions according to the units decommissioning with generated resources, and RAW and SNF management strategy during decommissioning

  10. Volume Reduction of Decommissioning Radioactive Burnable and Metal Wastes

    Energy Technology Data Exchange (ETDEWEB)

    Min, B. Y.; Lee, Y. J.; Yun, G. S.; Lee, K. W.; Moon, J. K. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Choi, Y. K.; Cho, J. H. [SunKwang Atomic Energy Safety Co., Seoul (Korea, Republic of)

    2014-10-15

    A large quantity of radioactive waste was generated during the decommissioning projects. For the purpose of the volume reduction and clearance for decommissioning wastes from decommissioning projects, the incineration and high melting technology has been selected for the decommissioning wastes treatment. The volume reduction of the combustible wastes through the incineration technologies has merits from the view point of a decrease in the amount of waste to be disposed of resulting in a reduction of the disposal cost. Incineration is generally accepted as a method of reducing the volume of radioactive waste. The incineration technology is an effective treatment method that contains hazardous chemicals as well as radioactive contamination. Incinerator burns waste at high temperature. Incineration of a mixture of chemically hazardous and radioactive materials, known as 'mixed waste,' has two principal goals: to reduce the volume and total chemical toxicity of the waste. Incineration itself does not destroy the metals or reduce the radioactivity of the waste. A proven melting technology is currently used for low-level waste (LLW) at several facilities worldwide. These facilities use melting as a means of processing LLW for unrestricted release of the metal or for recycling within the nuclear sector. About 16.4 tons of decommissioning combustible waste has been treated using Oxygen Enriched incineration. The incineration facility operated quite smoothly through the analysis major critical parameters of off-gas.

  11. Volume Reduction of Decommissioning Radioactive Burnable and Metal Wastes

    International Nuclear Information System (INIS)

    Min, B. Y.; Lee, Y. J.; Yun, G. S.; Lee, K. W.; Moon, J. K.; Choi, Y. K.; Cho, J. H.

    2014-01-01

    A large quantity of radioactive waste was generated during the decommissioning projects. For the purpose of the volume reduction and clearance for decommissioning wastes from decommissioning projects, the incineration and high melting technology has been selected for the decommissioning wastes treatment. The volume reduction of the combustible wastes through the incineration technologies has merits from the view point of a decrease in the amount of waste to be disposed of resulting in a reduction of the disposal cost. Incineration is generally accepted as a method of reducing the volume of radioactive waste. The incineration technology is an effective treatment method that contains hazardous chemicals as well as radioactive contamination. Incinerator burns waste at high temperature. Incineration of a mixture of chemically hazardous and radioactive materials, known as 'mixed waste,' has two principal goals: to reduce the volume and total chemical toxicity of the waste. Incineration itself does not destroy the metals or reduce the radioactivity of the waste. A proven melting technology is currently used for low-level waste (LLW) at several facilities worldwide. These facilities use melting as a means of processing LLW for unrestricted release of the metal or for recycling within the nuclear sector. About 16.4 tons of decommissioning combustible waste has been treated using Oxygen Enriched incineration. The incineration facility operated quite smoothly through the analysis major critical parameters of off-gas

  12. Activation analysis of dual-purpose metal cask after the end of design lifetime for decommission

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Tae Man; Ku, Ji Young; Dho Ho Seog; Cho, Chun Hyung [Korea Radioactive Waste Agency, Daejeon (Korea, Republic of); Ko, Jae Hun [Korea Nuclear Engineering and Service Co., Daejeon (Korea, Republic of)

    2016-12-15

    The Korea Radioactive Waste Agency (KORAD) has developed a dual-purpose metal cask for the dry storage of spent nuclear fuel that has been generated by domestic light-water reactors. The metal cask was designed in compliance with international and domestic technology standards, and safety was the most important consideration in developing the design. It was designed to maintain its integrity for 50 years in terms of major safety factors. The metal cask ensures the minimization of waste generated by maintenance activities during the storage period as well as the safe management of the waste. An activation evaluation of the main body, which includes internal and external components of metal casks whose design lifetime has expired, provides quantitative data on their radioactive inventory. The radioactive inventory of the main body and the components of the metal cask were calculated by applying the MCNP5·ORIGEN-2 evaluation system and by considering each component's chemical composition, neutron flux distribution, and reaction rate, as well as the duration of neutron irradiation during the storage period. The evaluation results revealed that 10 years after the end of the cask's design life, {sup 60}Co had greater radioactivity than other nuclides among the metal materials. In the case of the neutron shield, nuclides that emit high-energy gamma rays such as {sup 28}Al and {sup 24}Na had greater radioactivity immediately after the design lifetime. However, their radioactivity level became negligible after six months due to their short half-life. The surface exposure dose rates of the canister and the main body of the metal cask from which the spent nuclear fuel had been removed with expiration of the design lifetime were determined to be at very low levels, and the radiation exposure doses to which radiation workers were subjected during the decommissioning process appeared to be at insignificant levels. The evaluations of this study strongly suggest that

  13. Decommissioning Trawsfynydd - How public consultation shaped the strategy

    Energy Technology Data Exchange (ETDEWEB)

    Kay, Martin J [Nuclear Electric plc. (United Kingdom)

    1995-07-01

    This case study discusses the ned of consulting the public when decommissioning a nuclear power plants. When Trawsfynydd power station in North Wales shutdown in July 1993, Nuclear Electric's strategy for decommissioning its stations was not clearly defined. The company had altered its corporate policy on decommissioning fro he strategy referred to as the 'Reference Case' which had been approved by the Government, to the preferred 'Deferred Safestore' strategy, which was waiting Government approval. Deferred Safestore is preferred as it simplifies the engineering work involved by capitalising an the basic strength and integrity of the reactor building. It minimises thd radiation exposure to workers and radioactivity released to the environment, reduces the amount of radioactive waste produced and significantly cuts the total decommissioning cost. The closure and the decommissioning of Trawsfynydd power station was a sensitive issue as: The station lies within a National Park of outstanding beauty. The economic circumstances in the area are such that employment opportunities are very limited. At a crucial time when the company was approaching a Government review which would decide its future, Nuclear Electric could not afford to lose any credibility. A public consultation programme was launched in the vicinity of the power station To gauge the reactions of the public and elected local government bodies to a series of decommissioning options. Nuclear Electric presented three main options with details on the employment opportunities, the costs, and the lorry loads of material involved with each. The people were identified on whom decommissioning Trawsfynydd power station is likely to have an environmental or socioeconomic impact. As a result of the polls the Nuclear Electric received feedback in two ways. Formal feedback from the local councils Independent analysis of the completed questionnaires. The company was wholly committed to a meaningful consultation. Before

  14. Decommissioning Trawsfynydd - How public consultation shaped the strategy

    International Nuclear Information System (INIS)

    Kay, Martin J.

    1995-01-01

    This case study discusses the ned of consulting the public when decommissioning a nuclear power plants. When Trawsfynydd power station in North Wales shutdown in July 1993, Nuclear Electric's strategy for decommissioning its stations was not clearly defined. The company had altered its corporate policy on decommissioning fro he strategy referred to as the 'Reference Case' which had been approved by the Government, to the preferred 'Deferred Safestore' strategy, which was waiting Government approval. Deferred Safestore is preferred as it simplifies the engineering work involved by capitalising an the basic strength and integrity of the reactor building. It minimises thd radiation exposure to workers and radioactivity released to the environment, reduces the amount of radioactive waste produced and significantly cuts the total decommissioning cost. The closure and the decommissioning of Trawsfynydd power station was a sensitive issue as: The station lies within a National Park of outstanding beauty. The economic circumstances in the area are such that employment opportunities are very limited. At a crucial time when the company was approaching a Government review which would decide its future, Nuclear Electric could not afford to lose any credibility. A public consultation programme was launched in the vicinity of the power station To gauge the reactions of the public and elected local government bodies to a series of decommissioning options. Nuclear Electric presented three main options with details on the employment opportunities, the costs, and the lorry loads of material involved with each. The people were identified on whom decommissioning Trawsfynydd power station is likely to have an environmental or socioeconomic impact. As a result of the polls the Nuclear Electric received feedback in two ways. Formal feedback from the local councils Independent analysis of the completed questionnaires. The company was wholly committed to a meaningful consultation. Before

  15. Life cycle cost estimation and systems analysis of Waste Management Facilities

    International Nuclear Information System (INIS)

    Shropshire, D.; Feizollahi, F.

    1995-01-01

    This paper presents general conclusions from application of a system cost analysis method developed by the United States Department of Energy (DOE), Waste Management Division (WM), Waste Management Facilities Costs Information (WMFCI) program. The WMFCI method has been used to assess the DOE complex-wide management of radioactive, hazardous, and mixed wastes. The Idaho Engineering Laboratory, along with its subcontractor Morrison Knudsen Corporation, has been responsible for developing and applying the WMFCI cost analysis method. The cost analyses are based on system planning level life-cycle costs. The costs for life-cycle waste management activities estimated by WMFCI range from bench-scale testing and developmental work needed to design and construct a facility, facility permitting and startup, operation and maintenance, to the final decontamination, decommissioning, and closure of the facility. For DOE complex-wide assessments, cost estimates have been developed at the treatment, storage, and disposal module level and rolled up for each DOE installation. Discussions include conclusions reached by studies covering complex-wide consolidation of treatment, storage, and disposal facilities, system cost modeling, system costs sensitivity, system cost optimization, and the integration of WM waste with the environmental restoration and decontamination and decommissioning secondary wastes

  16. Planning and management for reactor decommissioning

    International Nuclear Information System (INIS)

    Miyasaka, Yasuhiko

    2001-01-01

    This report describes decommissioning strategy, planning process, regulation, management and organization, radiological characterization and safety. Planning is used to identify, define and organize the requirements for decommissioning including decommissioning options, items to be accomplished (objective, scope), to solve problems of how it is to be accomplished (methods, means and procedures), questions of who will execute it (resources, organization and responsibilities, interfacing), and time when it will be executed (schedule for meeting the objectives). A plan is highly dependent on the quality of the management team assembled to carry it out. Radiological characterization involves a survey of existing data, calculation, in situ measurements and/or sampling and analyses. Using this databases decommissioning planner may assess options, considering: decontamination processes, dismantling procedures, tools required, radiological protection of workers and public/environment, waste classification, and resulting costs. Comparison and optimization of these factors will lead to selection of a decommissioning strategy, i.e. typically, immediate or deferred dismantling. The planning and implementation of decommissioning for nuclear reactors should be referred both recent dismantling techniques and many decommissioning experiences. The technical lessons learned from many projects will help in the planning for future decommissioning projects. And systematic planning and management are essential to successful completion of a decommissioning project. (author)

  17. 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

  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. 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

  1. Life cycle cost analysis rehabilitation costs.

    Science.gov (United States)

    2015-07-01

    This study evaluates data from CDOTs Cost Data books and Pavement Management Program. Cost : indices were used to normalize project data to year 2014. Data analyzed in the study was obtained from : the CDOTs Cost Data books and the Pavement Man...

  2. Principles of record keeping for decommissioning purposes

    International Nuclear Information System (INIS)

    Laraia, M.

    2003-01-01

    At the siting and conceptual design stage of a nuclear facility the first records pertaining to that facility are produced and stored. Subsequent phases in the facility's life cycle (detailed design, construction, commissioning, operation and shutdown) will include the production and retention of a large variety of records. Design, as-built drawings and operational records are essential for safe and efficient operation of any nuclear facility. This set of records is constantly updated and augmented during operation. Records from all phases of a nuclear facility are important for planning its decommissioning. Although not all of these records need to be included explicitly in the decommissioning plan itself, the process of initial, ongoing and final planning utilizes pertinent records for, and ultimately achieves, safe and cost effective decommissioning. When a nuclear facility is shutdown for decommissioning, current operating experience may be lost. Therefore, one important element of planning is to identify, secure and store appropriate operational records to support decommissioning. This process is preferably initiated during the design and construction phase and continues throughout operation including shutdown. Part of the records inventory from operation will become records for decommissioning and it is cost effective to identify these records before final facility shutdown. Experience shows that lack of attention to record keeping may result in an undue waste of time, other resources and additional costs. The newly established Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management recognizes the importance of keeping decommissioning-related records. In addition, the systematic management of records is an essential part of quality assurance and is often a licence condition. A good comprehensive decommissioning records management system (RMS) is one specific application of the broader concepts of 'Protection

  3. Survey of decontamination and decommissioning techniques

    International Nuclear Information System (INIS)

    Kusler, L.E.

    1977-01-01

    Reports and articles on decommissioning have been reviewed to determine the current technology status and also attempt to identify potential decommissioning problem areas. It is concluded that technological road blocks, which limited decommissioning facilities in the past have been removed. In general, techniques developed by maintenance in maintaining the facility have been used to decommission facilities. Some of the more promising development underway which will further simplify decommissioning activities are: electrolytic decontamination which simplifies some decontaminating operations; arc saw and vacuum furnace which reduce the volume of metallic contaminated material by a factor of 10; remotely operated plasma torch which reduces personnel exposure; and shaped charges, water cannon and rock splitters which simplify concrete removal. Areas in which published data are limited are detailed costs identifying various components included in the total cost and also the quantity of waste generated during the decommissioning activities. With the increased awareness of decommissioning requirements as specified by licensing requirements, design criteria for new facilities are taking into consideration final decommissioning of buildings. Specific building design features will evolve as designs are evaluated and implemented

  4. Radiological and economic impact of decommissioning charged particle accelerators

    International Nuclear Information System (INIS)

    Sonck, M.; Buls, N.; Hermanne, A.; Eggermont, G.

    2000-01-01

    To evaluate the real radiological and economic consequences of future dismantling of particle accelerators, only insufficient information was available in literature or even at the individual accelerator facilities themselves. DGXI of the European Commission hence launched a project with focus on gathering quantitative and scientifically sound data on the number of accelerators in the EU, on the status of activation of the different facilities, on the awareness of the possible problems at dismantling and on cost evacuations for full scale decommissioning. The project was granted to the VUB with subcontracts to NIRAS/ONDRAF, MAN and CEA-Saclay. With the replies received to an extensive questionnaire, a database was set up with the necessary data for evaluating the decommissioning problems to be expected at the different facilities. From this database three accelerators were chosen as reference cases (VUB medium energy cyclotron, IRMM 200 MeV electron linear accelerator and the 6 GeV proton synchrotron Saturne in Saclay). Extensive sampling of their concrete shieldings (more than 200 drill cores) and metal parts of accelerator and infrastructure, followed by accurate γ-spectrometric analysis and custom designed 3D interpolation, yield data on the 3D distribution of the activity in the different rooms of the installations. In addition to the γ-spectrometric analysis, an analysis of the tritium content of the concrete was performed by measuring the water liberated from heating ground concrete samples. These specific activity distributions allow evaluation of both immediate and deferred decommissioning costs using different scenarios (different clearance levels, different waste management prices, different labor costs and different decommissioning techniques) based on real situations in France, Germany and Great Britain. Several important conclusions and recommendations with respect to decommissioning both existing and future accelerator facilities will be presented

  5. 76 FR 35511 - Decommissioning Planning

    Science.gov (United States)

    2011-06-17

    ... licensees to conduct their operations to minimize the introduction of residual radioactivity into the site... account and line of credit as approved financial assurance mechanisms, and modify other financial... additional information on the costs of decommissioning and spent fuel management. DATES: The final rule is...

  6. Decommissioning of the CANDU-PHW reactor

    International Nuclear Information System (INIS)

    Unsworth, G.N.

    1977-04-01

    This report contains the results of a study of various aspects of decommissioning of reactors. The study places in perspective the size of the job, the hazards involved, the cost and the environmental impact. The three internationally agreed ''stages'' of decommissioning, namely, mothballing, entombment, and dismantling are defined and discussed. The single unit 600 MW(e) CANDU is chosen as the type of reactor on which the discussion is focussed but the conclusions reached will provide a basis for judgement of the costs and problems associated with decommissioning reactors of other sizes and types. (author)

  7. Asset Decommissioning Risk Metrics for Floating Structures in the Gulf of Mexico.

    Science.gov (United States)

    Kaiser, Mark J

    2015-08-01

    Public companies in the United States are required to report standardized values of their proved reserves and asset retirement obligations on an annual basis. When compared, these two measures provide an aggregate indicator of corporate decommissioning risk but, because of their consolidated nature, cannot readily be decomposed at a more granular level. The purpose of this article is to introduce a decommissioning risk metric defined in terms of the ratio of the expected value of an asset's reserves to its expected cost of decommissioning. Asset decommissioning risk (ADR) is more difficult to compute than a consolidated corporate risk measure, but can be used to quantify the decommissioning risk of structures and to perform regional comparisons, and also provides market signals of future decommissioning activity. We formalize two risk metrics for decommissioning and apply the ADR metric to the deepwater Gulf of Mexico (GOM) floater inventory. Deepwater oil and gas structures are expensive to construct, and at the end of their useful life, will be expensive to decommission. The value of proved reserves for the 42 floating structures in the GOM circa January 2013 is estimated to range between $37 and $80 billion for future oil prices between 60 and 120 $/bbl, which is about 10 to 20 times greater than the estimated $4.3 billion to decommission the inventory. Eni's Allegheny and MC Offshore's Jolliet tension leg platforms have ADR metrics less than one and are approaching the end of their useful life. Application of the proposed metrics in the regulatory review of supplemental bonding requirements in the U.S. Outer Continental Shelf is suggested to complement the current suite of financial metrics employed. © 2015 Society for Risk Analysis.

  8. Summary, analysis, and response to public comments on proposed amendments to 10 CFR Parts 30, 40, 50, 51, 70, and 72: Decommissioning criteria for nuclear facilities

    International Nuclear Information System (INIS)

    1988-06-01

    On February 11, 1985, the NRC issued for public comment proposed rules on decommissioning of nuclear facilities (50 FR 5600). Comment letters were received from 143 organizations and individuals. This report provides a summary and analysis and response to the public comments received

  9. Decommissioning Study of Oskarshamn NPP

    International Nuclear Information System (INIS)

    Larsson, Helena; Anunti, Aake; Edelborg, Mathias

    2013-06-01

    By Swedish law it is the obligation of the nuclear power utilities to satisfactorily demonstrate how a nuclear power plant can be safely decommissioned and dismantled when it is no longer in service as well as calculate the estimated cost of decommissioning of the nuclear power plant. Svensk Kaernbraenslehantering AB (SKB) has been commissioned by the Swedish nuclear power utilities to meet the requirements of current legislation by studying and reporting on suitable technologies and by estimating the costs of decommissioning and dismantling of the Swedish nuclear power plants. The present report is an overview, containing the necessary information to meet the above needs, for Oskarshamn NPP. Information is given for the plant about the inventory of materials and radioactivity at the time for final shutdown. A feasible technique for dismantling is presented and the waste management is described and the resulting waste quantities are estimated. Finally a schedule for the decommissioning phase is given and the costs associated are estimated as a basis for funding

  10. Decommissioning study of Forsmark NPP

    International Nuclear Information System (INIS)

    Anunti, Aake; Larsson, Helena; Edelborg, Mathias

    2013-06-01

    By Swedish law it is the obligation of the nuclear power utilities to satisfactorily demonstrate how a nuclear power plant can be safely decommissioned and dismantled when it is no longer in service as well as calculate the estimated cost of decommissioning of the nuclear power plant. Svensk Kaernbraenslehantering AB (SKB) has been commissioned by the Swedish nuclear power utilities to meet the requirements of current legislation by studying and reporting on suitable technologies and by estimating the costs of decommissioning and dismantling of the Swedish nuclear power plants. The present report is an overview, containing the necessary information to meet the above needs, for the Forsmark NPP. Information is given for the plant about the inventory of materials and radioactivity at the time for final shutdown. A feasible technique for dismantling is presented and the waste management is described and the resulting waste quantities are estimated. Finally a schedule for the decommissioning phase is given and the costs associated are estimated as a basis for funding

  11. Decommissioning Study of Oskarshamn NPP

    Energy Technology Data Exchange (ETDEWEB)

    Larsson, Helena; Anunti, Aake; Edelborg, Mathias [Westinghouse Electric Sweden AB, Vaesteraas (Sweden)

    2013-06-15

    By Swedish law it is the obligation of the nuclear power utilities to satisfactorily demonstrate how a nuclear power plant can be safely decommissioned and dismantled when it is no longer in service as well as calculate the estimated cost of decommissioning of the nuclear power plant. Svensk Kaernbraenslehantering AB (SKB) has been commissioned by the Swedish nuclear power utilities to meet the requirements of current legislation by studying and reporting on suitable technologies and by estimating the costs of decommissioning and dismantling of the Swedish nuclear power plants. The present report is an overview, containing the necessary information to meet the above needs, for Oskarshamn NPP. Information is given for the plant about the inventory of materials and radioactivity at the time for final shutdown. A feasible technique for dismantling is presented and the waste management is described and the resulting waste quantities are estimated. Finally a schedule for the decommissioning phase is given and the costs associated are estimated as a basis for funding.

  12. Decommissioning study of Forsmark NPP

    Energy Technology Data Exchange (ETDEWEB)

    Anunti, Aake; Larsson, Helena; Edelborg, Mathias [Westinghouse Electric Sweden AB, Vaesteraas (Sweden)

    2013-06-15

    By Swedish law it is the obligation of the nuclear power utilities to satisfactorily demonstrate how a nuclear power plant can be safely decommissioned and dismantled when it is no longer in service as well as calculate the estimated cost of decommissioning of the nuclear power plant. Svensk Kaernbraenslehantering AB (SKB) has been commissioned by the Swedish nuclear power utilities to meet the requirements of current legislation by studying and reporting on suitable technologies and by estimating the costs of decommissioning and dismantling of the Swedish nuclear power plants. The present report is an overview, containing the necessary information to meet the above needs, for the Forsmark NPP. Information is given for the plant about the inventory of materials and radioactivity at the time for final shutdown. A feasible technique for dismantling is presented and the waste management is described and the resulting waste quantities are estimated. Finally a schedule for the decommissioning phase is given and the costs associated are estimated as a basis for funding.

  13. 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

  14. Summit Station Skiway Cost Analysis

    Science.gov (United States)

    2016-07-01

    of fuel delivered to Summit via LC-130 at a price of $32/gal. (Lever et al. 2016), the cost for constructing and maintaining the skiway for the 2014...CRREL TR-16-9 18 The costs associated with the Twin Otter include a day rate plus an hourly mission rate, a per passenger rate, airport fees, fuel, a...ER D C/ CR RE L TR -1 6- 9 Engineering for Polar Operations, Logistics, and Research (EPOLAR) Summit Station Skiway Cost Analysis Co ld

  15. Decontamination and decommissioning of the SPERT-I Reactor Building at the Idaho National Engineering Laboratory. Final report

    International Nuclear Information System (INIS)

    Dolenc, M.R.

    1986-02-01

    This final report documents the decontamination and decommissioning of the SPERT-I Reactor Building. This 20- by 40-ft galvanized steel building was dismantled; and the resultant contaminated sludge, liquid, and carbon steel were disposed of at the Radioactive Waste Management Complex of the Idaho National Engineering Laboratory. This report presents the results of the characterization, decision analysis, planning, and decommissioning of the facility. The total cost of these activities was $139,500. Of this total, $103,500 was required for decommissioning operations. (This latter figure represents a 20% savings over the estimated costs generated during the planning effort.) The objectives of decommissioning this facility were to stabilize the seepage pit area and remove the reactor building. The D and D work was divided into two parts; the seepage pit was decommissioned in 1984, and the reactor building in 1985. The entire area was backfilled with radiologically clean soil, graded, and seeded. Two markers were installed to identify the locations of the pit and reactor building. The only isotopes found in either decommissioning operation were cesium-137 and uranium-235 in very low concentrations. Decommissioning operations of the reactor building were carried out during August 1985. The project generate 297 ft 3 of radioactive waste. No personnel radiation exposure above background was received by D and D workers

  16. 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)

  17. Safety analysis report. Decontamination and decommissioning of the EBR-I Complex

    International Nuclear Information System (INIS)

    Commander, J.C.; Macbeth, P.J.; Michels, D.E.

    1975-06-01

    The safety aspects of the planned EBR-I Complex decontamination and decommissioning operations are assessed. The major operations are: (1) removal of NaK from the EBR-I primary and secondary coolant systems, (2) processing of the NaK to produce solid caustic for disposal, (3) decontamination of contaminated areas of EBR-I and ZPR-III, (4) removal of items that cannot be decontaminated economically to acceptably safe levels, (5) isolation of contaminated areas, (6) demolition of the AFSR Shielding, and (7) removal of contaminated vessels from the NaK storage pit. It may be concluded that although potential hazards do exist from explosion, chemical burns and low-level radioactive exposure from the D and D operation, these hazards represent acceptable risks provided that the established procedures and precautions are followed. (U.S.)

  18. Web-Enabled Analysis of a Large-Scale Deactivation and Decommissioning Program

    International Nuclear Information System (INIS)

    Bollinger, James S.; Austin, William E.

    2008-01-01

    From the mid-1950's through the 1980's, the U.S. Department of Energy's Savannah River Site produced nuclear materials for the weapons stockpile, for medical and industrial applications, and for space exploration. Although SRS has a continuing defense-related mission, the overall site mission is now oriented toward environmental restoration and management of legacy chemical and nuclear waste. With the change in mission, SRS no longer has a need for much of the infrastructure developed to support the weapons program. This excess infrastructure, which includes over 1000 facilities, will be decommissioned and demolished over the forthcoming years. A comprehensive environmental management plan was developed in 2003 detailing the schedule and sequence for decommissioning and demolition (D and D) activities. Implementation of this plan was anticipated to have a significant impact at SRS; therefore, a sophisticated web-enabled mapping capability was developed to allow SRS management, employees, and other stakeholders, to view the contents of the plan in an interactive fashion. Web-enabled mapping allows users to view the overall impact of the plan from a unique geographic perspective that can be quickly updated to reflect changes on the ground. Development of the web-based D and D mapping and management system provides SRS personnel the ability to see the detailed contents of the facilities D and D plan in a geographic context and highly interactive environment. As the plan changes due to internal and external dynamic factors, updates can be quickly made so that the latest and most accurate information is available. Information content can be easily managed by the user in the application, allowing change in granularity with the click of a mouse button. As a result, the use of GIS and web-enabled mapping has had a revolutionary impact on the development and dissemination of D and D information at SRS

  19. 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

  20. A study on the applicability for primary system decontamination through analysis on NPP decommission technology and international experience

    Energy Technology Data Exchange (ETDEWEB)

    Song, Jong Soon; Jung, Min Young; Lee, Sang Heon [Chosun University, Gwangju (Korea, Republic of)

    2016-03-15

    Decontamination is one of the most important technologies for the decommissioning of NPP. The purpose of decontamination is to reduce the Risk of exposure of the decommissioning workers, and to recycle parts of the plant components. Currently, there is a lack of data on the efficiency of the decontamination technologies for decommissioning. In most cases, the local radiation level can be lowered below a regulatory limitation by decontamination. Therefore, more efficient decontamination technology must be continuously developed. This work describes the practical experiences in the United States and the European countries for NPP decommissioning using these decontamination technologies. When the decommissioning of domestic nuclear power plant is planned and implemented, this work will be helpful as a reference of previous cases.

  1. Extensive analysis of hydrogen costs

    Energy Technology Data Exchange (ETDEWEB)

    Guinea, D M; Martin, D; Garcia-Alegre, M C; Guinea, D [Consejo Superior de Investigaciones Cientificas, Arganda, Madrid (Spain). Inst. de Automatica Industrial; Agila, W E [Acciona Infraestructuras, Alcobendas, Madrid (Spain). Dept. I+D+i

    2010-07-01

    Cost is a key issue in the spreading of any technology. In this work, the cost of hydrogen is analyzed and determined, for hydrogen obtained by electrolysis. Different contributing partial costs are taken into account to calculate the hydrogen final cost, such as energy and electrolyzers taxes. Energy cost data is taken from official URLs, while electrolyzer costs are obtained from commercial companies. The analysis is accomplished under different hypothesis, and for different countries: Germany, France, Austria, Switzerland, Spain and the Canadian region of Ontario. Finally, the obtained costs are compared to those of the most used fossil fuels, both in the automotive industry (gasoline and diesel) and in the residential sector (butane, coal, town gas and wood), and the possibilities of hydrogen competing against fuels are discussed. According to this work, in the automotive industry, even neglecting subsidies, hydrogen can compete with fossil fuels. Hydrogen can also compete with gaseous domestic fuels. Electrolyzer prices were found to have the highest influence on hydrogen prices. (orig.)

  2. Decommissioning and decontamination

    International Nuclear Information System (INIS)

    Dadoumont, J.; Cantrel, E.; Valenduc, P.; Noynaert, L.

    2009-01-01

    The SCK-CEN has built a large know-how in decommissioning and decontamination, thanks to its BR3 decommissioning project. In 2007, the decommissioning activities at BR3 have been continued according to the strategy. This article discusses main realisations the following domains: decommissioning of the neutron shield tank and installation of new ventilation for the controlled area, dismantling of the former one and characterization of the stack

  3. Decommissioning of the nuclear facilities at Risoe National Laboratory. Descriptions and cost assessment. Danish summary[Denmark]; Dekommissionering af Risoes nukleare anlaeg - vurdering af opgaver og omkostninger. Dansk sammenfatning

    Energy Technology Data Exchange (ETDEWEB)

    Lauridsen, Kurt

    2001-02-01

    The report gives a brief description of relevant aspects of the decommissioning of all nuclear facilities at Risoe National Laboratory, including the necessary operations to be performed and the associated costs. Together with a more detailed report, written in English, this report is the result of a project initiated by Risoe in the summer of 2000. The English report has undergone an international review, the results of which are summarised in the present report. (au)

  4. Global solutions through simulation for better decommissioning

    International Nuclear Information System (INIS)

    Scoto Di Suoccio, Ines; Testard, Vincent

    2016-01-01

    be tried, analyzed and compared on all output parameters in a total accordance with the ALARA/ALARP approach. Then, contingencies can be prevented by testing an infinite number of situations whatever the uncertainties are, and this enables to determine the best scenario strategy for each set of data. Simulations also allow people to test not only access issues into some environment but also radiological access. By testing different dosimetric configurations or hot spot location, simulation allows you to test them and so reduce risks. For a specific environment, when many scenarios have been developed and tested, sensitivity studies are really important to choose the optimal decommissioning strategy. Sensitivity studies can be done with simulation tools by comparing results of scenarios directly into the software. This comparison helps to choose the optimal scenario according to which output data is considered as key determinant. Simulation offers a very good return on investment in the sense that many scenarios are quick to do, they can be copied and the user can change one input data to observe instantaneously the impacts of this change on results. Doing different simulations permit to quantify risks, reduce hazard and therefore reduce costs. Finally, simulation tools enable to collect output data of decommissioning projects during realization, comparing them in real time to the studies assessments. This improve the feedback acquisition, very important in the decommissioning field in which we do not have a lot of experience. Current experiences of studies using DEMplus on different kind of projects show several benefits either on the entry data consolidation, the scenario optimization and the risks studies. The ALARA/ALARP approach is fully developed by simulating a large set of strategies, using a cost-benefits analysis on many criteria. A unique software that deals with all types of entry data in order to compute results is clearly a powerful tool as a decision

  5. Decommissioning standards: the radioactive waste impact

    International Nuclear Information System (INIS)

    Russell, J.L.; Crofford, W.N.

    1979-01-01

    Several considerations are important in establishing standards for decommissioning nuclear facilities, sites and materials. The review includes discussions of some of these considerations and attempts to evaluate their relative importance. Items covered include the form of the standards, timing for decommissioning, occupational radiation protection, costs and financial provisions, and low-level radioactive waste. Decommissioning appears more closely related to radiation protection than to waste management, although it is often carried under waste management programs or activities. Basically, decommissioning is the removal of radioactive contamination from facilities, sites and materials so that they can be returned to unrestricted use or other actions designed to minimize radiation exposure of the public. It is the removed material that is the waste and, as such, it must be managed and disposed of in an environmentally safe manner. It is important to make this distinction even though, for programmatic purposes, decommissioning may be carried under waste management activities. It was concluded that the waste disposal problem from decommissioning activities is significant in that it may produce volumes comparable to volumes produced during the total operating life of a reactor. However, this volume does not appear to place an inordinate demand on shallow land burial capacity. It appears that the greater problems will be associated with occupational exposures and costs, both of which are sensitive to the timing of decommissioning actions

  6. Deactivation, Decontamination and Decommissioning Project Summaries

    Energy Technology Data Exchange (ETDEWEB)

    Peterson, David Shane; Webber, Frank Laverne

    2001-07-01

    This report is a compilation of summary descriptions of Deactivation, Decontamination and Decommissioning, and Surveillance and Maintenance projects planned for inactive facilities and sites at the INEEL from FY-2002 through FY-2010. Deactivations of contaminated facilities will produce safe and stable facilities requiring minimal surveillance and maintenance pending further decontamination and decommissioning. Decontamination and decommissioning actions remove contaminated facilities, thus eliminating long-term surveillance and maintenance. The projects are prioritized based on risk to DOE-ID, the public, and the environment, and the reduction of DOE-ID mortgage costs and liability at the INEEL.

  7. TA-2 Water Boiler Reactor Decommissioning Project

    International Nuclear Information System (INIS)

    Durbin, M.E.; Montoya, G.M.

    1991-06-01

    This final report addresses the Phase 2 decommissioning of the Water Boiler Reactor, biological shield, other components within the biological shield, and piping pits in the floor of the reactor building. External structures and underground piping associated with the gaseous effluent (stack) line from Technical Area 2 (TA-2) Water Boiler Reactor were removed in 1985--1986 as Phase 1 of reactor decommissioning. The cost of Phase 2 was approximately $623K. The decommissioning operation produced 173 m 3 of low-level solid radioactive waste and 35 m 3 of mixed waste. 15 refs., 25 figs., 3 tabs

  8. Criteria for decommissioning

    International Nuclear Information System (INIS)

    Ricci, P.F.

    1988-01-01

    In this paper the authors describe three risk acceptability criteria as parts of a strategy to clean up decommissioned facilities, related to both the status quo and to a variety of alternative technical clean-up options. The acceptability of risk is a consideration that must enter into any decision to establish when a site is properly decommissioned. To do so, both the corporate and public aspects of the acceptability issue must be considered. The reasons for discussion the acceptability of risk are to: Legitimize the process for making cleanup decisions; Determine who is at risk, who benefits, and who bears the costs of site cleanup, for each specific cleanup option, including the do nothing option; Establish those factors that, taken as a whole, determine measures of acceptability; Determine chemical-specific aggregate and individual risk levels; and Establish levels for cleanup. The choice of these reasons is pragmatic. The method consistent with these factors is risk-risk-effectiveness: the level of cleanup must be consistent with the foreseeable use of the site and budget constraints. Natural background contamination is the level below which further cleanup is generally inefficient. Case-by-case departures from natural background are to be considered depending on demonstrated risk. For example, a hot spot is obviously a prima facie exception, but should be rebuttable. Rebuttability means that, through consensus, the ''hot spot'' is shown not to be associated with exposure

  9. A database structure for radiological optimization analyses of decommissioning operations

    International Nuclear Information System (INIS)

    Zeevaert, T.; Van de Walle, B.

    1995-09-01

    The structure of a database for decommissioning experiences is described. Radiological optimization is a major radiation protection principle in practices and interventions, involving radiological protection factors, economic costs, social factors. An important lack of knowledge with respect to these factors exists in the domain of the decommissioning of nuclear power plants, due to the low number of decommissioning operations already performed. Moreover, decommissioning takes place only once for a installation. Tasks, techniques, and procedures are in most cases rather specific, limiting the use of past experiences in the radiological optimization analyses of new decommissioning operations. Therefore, it is important that relevant data or information be acquired from decommissioning experiences. These data have to be stored in a database in a way they can be used efficiently in ALARA analyses of future decommissioning activities

  10. Challenges in the management of decommission waste of nuclear facilities in Ghana

    International Nuclear Information System (INIS)

    Glover, E.T.; Fletcher, J.J.

    2002-01-01

    It is inevitable that every nuclear facility must one day be safely decommissioned. When considering decommissioning, large amounts of radioactive and non-radioactive waste have to be taken into account. Disposal of such materials can have large economic impact on the overall decommissioning cost. In developing countries like Ghana, the perception of environmental protection through waste management, is often not very high as compared to many other pressing needs. Therefore limited resources are allocated for environmental problems. Ghana operates a tank-in- pool type research reactor, 30kW output for research in neutron activation analysis, radioisotope preparation, education and training, a radiotherapy unit that utilizes a 185TBq Co-60 radioactive sources for the treatment of cancer and a gamma irradiation facility which utilizes 1.85PBq Co-60 radioactive source for the irradiation of various materials. All these facilities are operating without designed decommissioning in mind, an inadequate waste management infrastructure as well as a lack of a repository to handling the resulting waste. It is today's beneficials of the nuclear facility that has to deal with the legacies of the future decommissioning activities. The paper outlines some of the challenges and issues to be expected in the management of waste from future decommissioning of nuclear facilities in Ghana with the absence of a waste management infrastructure and inadequate financial resources. The paper puts forth a concept to perform meaningful and significant plans whilst the facilities are still operating. (author)

  11. Thermal analysis to support decommissioning of the molten salt reactor experiment

    International Nuclear Information System (INIS)

    Sulfredge, C.D.; Morris, D.G.; Park, J.E.; Williams, P.T.

    1996-06-01

    As part of the decommissioning process for the Molten Salt Reactor Experiment (MSRE) at Oak Ridge National Laboratory, several thermal-sciences issues were addressed. Apparently a mixture of UF 6 and F 2 had diffused into the upper portion of one charcoal column in the MSRE auxiliary charcoal bed (ACB), leading to radiative decay heating and possible chemical reaction sources. A proposed interim corrective action was planned to remove the water from the ACB cell to reduce criticality and reactivity concerns and then fill the ACB cell with an inert material. This report describes design of a thermocouple probe to obtain temperature measurements for mapping the uranium deposit, as well as development of steady-state and transient numerical models for the heat transfer inside the charcoal column. Additional numerical modeling was done to support filling of the ACB cell. Results from this work were used to develop procedures for meeting the goals of the MSRE Remediation Project without exceeding appropriate thermal limits

  12. Thermal analysis to support decommissioning of the molten salt reactor experiment

    Energy Technology Data Exchange (ETDEWEB)

    Sulfredge, C.D.; Morris, D.G.; Park, J.E.; Williams, P.T.

    1996-06-01

    As part of the decommissioning process for the Molten Salt Reactor Experiment (MSRE) at Oak Ridge National Laboratory, several thermal-sciences issues were addressed. Apparently a mixture of UF{sub 6} and F{sub 2} had diffused into the upper portion of one charcoal column in the MSRE auxiliary charcoal bed (ACB), leading to radiative decay heating and possible chemical reaction sources. A proposed interim corrective action was planned to remove the water from the ACB cell to reduce criticality and reactivity concerns and then fill the ACB cell with an inert material. This report describes design of a thermocouple probe to obtain temperature measurements for mapping the uranium deposit, as well as development of steady-state and transient numerical models for the heat transfer inside the charcoal column. Additional numerical modeling was done to support filling of the ACB cell. Results from this work were used to develop procedures for meeting the goals of the MSRE Remediation Project without exceeding appropriate thermal limits.

  13. New technologies in decommissioning and remediation

    International Nuclear Information System (INIS)

    Fournier, Vincent

    2016-01-01

    New and emerging technologies are making decommissioning and remediation more cost effective, faster and safer. From planning to execution and control, the use of new technologies is on the rise. Before starting decommissioning or environmental remediation, experts need to plan each step of the process, and to do that, they first need a clear idea of the characteristics of the structure and the level of radiation that they can expect to encounter

  14. Decommissioning co-operation in Europe

    International Nuclear Information System (INIS)

    Simon, R.A.

    1992-01-01

    Under the provisions of the Euratom treaty, member states of the European Community have since 1978 been conducting successive five-year R and D programmes in the field of decommissioning on the basis of cost-sharing contracts. The main objective of the programmes is to establish safe, socially acceptable and economic decommissioning strategies for obsolete nuclear plant. The programmes share the common aim of all Euratom activities in promoting cooperation, scientific exchange and industrial competition within the Community. (author)

  15. A Decommissioning Information Management System

    Energy Technology Data Exchange (ETDEWEB)

    Park, S. K.; Hong, S. B.; Chung, U. S.; Park, J. H. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2007-07-01

    In 1996, it was determined that research reactors, the KRR-1 and the KRR-2, would be shut down and dismantled. A project for the decommissioning of these reactors was launched in January 1997 with the goal of a completion by 2008. The total budget of the project was 19.4 million US dollars, including the cost for the waste disposal and for the technology development. The work scopes during the decommissioning project were the dismantling of all the facilities and the removal of all the radioactive materials from the reactor site. After the removal of the entire radioactivity, the site and buildings will be released for an unconditional use. A separate project for the decommissioning of the uranium conversion plant was initiated in 2001. The plant was constructed for the development of the fuel manufacturing technologies and the localization of nuclear fuels in Korea. It was shut downed in 1993 and finally it was concluded in 2000 that the plant would be decommissioned. The project will be completed by 2008 and the total budget was 9.2 million US dollars. During this project, all vessels and equipment will be dismantled and the building surface will be decontaminated to be utilized as general laboratories.

  16. 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

  17. Applicability of EPRI Decommissioning Pre-Planning Manual to International Decommissioning Projects

    International Nuclear Information System (INIS)

    Lessard, Leo; Kay, Jim; Lefrancois, Donald; Furr, Richard; Lucas, Matthieu; Schauer, Konrad

    2016-01-01

    Industry models for planning the efficient decommissioning of a nuclear power plant continue to evolve. Effective planning is a key to cost control, a critical aspect of decommissioning. In 2001, the Electric Power Research Institute (EPRI) published the 'Decommissioning Pre-Planning Manual', referred to as the 'Manual'. The goal of the Manual was to develop a framework for use in pre-planning the decommissioning of a nuclear power plant. The original research was based on information collected during the active decommissioning of power reactors in New England, and the ongoing decommissioning planning of another reactor still in operation. The research team identified thirty-two (32) major Decommissioning Tasks that support the strategic and tactical planning that can be conducted in advance of plant shutdown. The Decommissioning Tasks were organized in a logical sequence of execution, and sorted in common discipline groupings. Owners of U.S. nuclear plants that have shut down prematurely during the past 5 years have found the EPRI Decommissioning Pre-Planning Manual useful in developing their transition plans from an operating to shutdown facility. Concurrently, during the past 15 years, the IAEA has published numerous technical and safety reports on nuclear reactor decommissioning planning and execution. IAEA's goal is to provide its global members with useful and timely guidance for the planning and execution of nuclear decommissioning projects. This information has been used extensively by international nuclear plant operators. One of the key objectives will be to develop a road-map linking the 32 EPRI Decommissioning Tasks with the comparable (or equivalent) topics covered in the IAEA library of decommissioning knowledge. The logical and convenient structure of the Manual will be cross-referenced to the IAEA topics to aid in organizing the development of decommissioning plans. The road-map will serve to provide a basis for improved

  18. Funding Decommissioning - UK Experience

    International Nuclear Information System (INIS)

    MacKerron, Gordon

    2006-01-01

    % of all BE free cash flow to go to the Fund; - Government would pay for all Stage 1/2/3 decommissioning expenses that BE could not meet. BE is still a private company in a formal sense but the UK Office of National Statistics classifies it as a public sector company, because it regards control (not ownership) as in State hands. Government is now setting up the Nuclear Decommissioning Authority (NDA) to manage all public sector liabilities. Intention was to have a 'segregated account' to help give assurance that funding would be long-term and reliable. First draft Annual Plan does not mention segregation or any funding commitment beyond the first year (2005/6). The BNFL NLIP will presumably go to the Treasury. NLIP will presumably go to the Treasury. In conclusion, it is clean that the decommissioning funding system has been short term and has relied mainly on Government. Some consumer contributions have been made, but now that nuclear power competes in a private market place and is relatively expensive, there is no guarantee that consumers/polluters will pay for a significant proportion of decommissioning costs

  19. Planning for the decommissioning of a research reactor

    International Nuclear Information System (INIS)

    Dodson, W.J.; Isakari, H.H.; Munro, J.F.; Lim, T.H.; Denton, M.M.; Vernig, P.G.

    1988-01-01

    This paper describes the steps that must be taken and the uncertainties and potential pitfalls that can be encountered in decommissioning a research reactor, whether owned by private industry, a university, or a government agency. The paper is based on the experience in preparing for decommissioning the TRIGA Mark III Berkeley Research Reactor (BRR). Six topics of interest to an owner-operator are addressed: task and schedule planning, decommissioning organization, cost estimating, health and safety considerations, waste management, and regulatory concerns

  20. Administrative requirements of financial securities to cover decommissioning operations

    International Nuclear Information System (INIS)

    Sanchez, J.L.

    1983-01-01

    This paper points out that the lack of experience in decommissioning of nuclear power plants is reflected by the absence of specific legislation regarding the economic, fiscal and accounting aspects of the process. The author suggests that a fund be created for decommissioning costs through contributions deriving from plant operation. The paper analyses the procedures to be followed and draws attention to the need for clear legislation on decommissioning. (NEA) [fr

  1. Analysis of recently enacted national energy legislation and the Clean Air Act Amendments of 1990 as related to Decontamination and Decommissioning at Federal, State, and private facilities

    International Nuclear Information System (INIS)

    1994-01-01

    This report is a summary of an analysis of recently enacted national energy legislation and the Clean Air Act Amendments of 1990 as related to Decontamination and Decommissioning (D ampersand D) at Federal, State and private facilities. It is submitted pursuant to Appendix A of subcontract 9-X62-0785E-1, dated July 27, 1992, between the Regents of the University of California and Van Ness, Feldman ampersand Curtis

  2. Uranium enrichment decontamination and decommissioning fund

    International Nuclear Information System (INIS)

    1994-01-01

    One of the most challenging issues facing the Department of Energy's Office of Environmental Management is the cleanup of the three gaseous diffusion plants. In October 1992, Congress passed the Energy Policy Act of 1992 and established the Uranium Enrichment Decontamination and Decommissioning Fund to accomplish this task. This mission is being undertaken in an environmentally and financially responsible way by: devising cost-effective technical solutions; producing realistic life-cycle cost estimates, based on practical assumptions and thorough analysis; generating coherent long-term plans which are based on risk assessments, land use, and input from stakeholders; and, showing near-term progress in the cleanup of the gaseous diffusion facilities at Oak Ridge

  3. Economical aspect of the decommissioning for NPP

    International Nuclear Information System (INIS)

    Daryoko, M.

    1998-01-01

    The estimated, analysed and founding of the economical aspect at decommissioning of Nuclear Power Plant (NPP) have been studied. The data that have been obtained from literature, then the calculation and analysing have been done base to the future condition. The cost for NPP decommissioning depend on the internal factor such as type, capacity and safe storage time, and the external factor such as policy, manpower and the technology preparation. The successfulness of funding, depend on the rate of inflation, discount rate of interest and the currency fluctuation. For the internal factor, the influence of the type of the reactor (BWR or PWR) to the decommissioning cost is negligible, the big reactor capacity (±1100 MW), and the safe storage between 30 to 100 years are recommended, and for the external factor, specially Indonesia, to meet the future need the ratio of decommissioning cost and capital cost will be lower than in develop countries at the present (10%). The ratio between decommissioning fund and electricity generation cost relatively very low, are more less than 1.79 % for 30 years safe storage, and discount rate of interest 3%, or more less than 0.30 % for safe storage 30 years, and discount rate of interest 6%. (author)

  4. A study on the application of standards for clearance of metal waste generated during the decommissioning of NPP by using the RESRAD-RECYCLE

    Energy Technology Data Exchange (ETDEWEB)

    Song, Jong Soon; Kim, Dong Min; Lee, Sang Heon [Chosun University, Gwangju (Korea, Republic of)

    2016-12-15

    The metal waste generated during nuclear power plant decommissioning constitutes a large proportion of the total radioactive waste. This study investigates the current status of domestic and international regulatory requirements for clearance and the clearance experience of domestic institutions. The RESRAD-RECYCLE code was used for analyzing the clearance of the metal wastes generated during actual nuclear power plant decommissioning, and assessment of the exposure dose of twenty-six scenarios was carried out. The evaluation results will be useful in preliminary analysis of clearance and recycling during nuclear power plant decommissioning. As a next step, the effects of reducing disposal costs by clearance can be studied.

  5. Training for decommissioning

    International Nuclear Information System (INIS)

    Dietzold, A.

    2009-01-01

    Plants entering decommissioning face many challenges One of the most important is the challenge of training for decommissioning This is important because: The facility operators and management have spent many years successfully operating the facility; The facility management arrangements are geared to operation; Decommissioning will include non-nuclear specialists and other stakeholders; Other skills are needed to decommission successfully. UKAEA has decommissioned many facilities at its sites in Dounreay, Windscale, Harwell and Winfrith in the UK. We have faced all of the challenges previously described and have developed many training methods for ensuring the challenges are met safely and effectively. We have developed courses for specialised skills such as safety cases which can be deployed to support any decommissioning. (author)

  6. 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)

  7. 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

  8. 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

  9. Financial aspects of decommissioning. Report by an expert group

    International Nuclear Information System (INIS)

    2005-11-01

    Estimating decommissioning costs and collecting funds for eventual decommissioning of facilities that have used radioactive material is a prerequisite for safe, timely and cost effective decommissioning. A comprehensive overview of decommissioning costs and funding mechanisms was missing in the IAEA literature although the subject had been marginally dealt with in a few IAEA publications. Costing and funding issues were partially addressed by other international organizations, but there is a need to address the subject from the standpoint of the diverse social, economic and cultural environments that constitute IAEA membership. In its role of an international expert committee assisting the IAEA, the Technical Group on Decommissioning (TEGDE) debates and draws conclusions on topics omitted from general guidance. TEGDE members met in Vienna in 2003, 2004 and 2005 to develop the basis for this publication. The views expressed here reflect those of TEGDE and not necessarily those of the IAEA

  10. Decommissioning of NPP A-1

    International Nuclear Information System (INIS)

    Anon

    2009-01-01

    In this presentation the Operation history of A1 NPP, Project 'Decommissioning of A1 NPP' - I stage, Project 'Decommissioning of A1 NPP ' - II stage and Next stages of Project 'Decommissioning of A1 NPP ' are discussed.

  11. Fukushima Daiichi Unit 1 Accident Progression Uncertainty Analysis and Implications for Decommissioning of Fukushima Reactors - Volume I.

    Energy Technology Data Exchange (ETDEWEB)

    Gauntt, Randall O. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Mattie, Patrick D. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2016-01-01

    Sandia National Laboratories (SNL) has conducted an uncertainty analysis (UA) on the Fukushima Daiichi unit (1F1) accident progression with the MELCOR code. The model used was developed for a previous accident reconstruction investigation jointly sponsored by the US Department of Energy (DOE) and Nuclear Regulatory Commission (NRC). That study focused on reconstructing the accident progressions, as postulated by the limited plant data. This work was focused evaluation of uncertainty in core damage progression behavior and its effect on key figures-of-merit (e.g., hydrogen production, reactor damage state, fraction of intact fuel, vessel lower head failure). The primary intent of this study was to characterize the range of predicted damage states in the 1F1 reactor considering state of knowledge uncertainties associated with MELCOR modeling of core damage progression and to generate information that may be useful in informing the decommissioning activities that will be employed to defuel the damaged reactors at the Fukushima Daiichi Nuclear Power Plant. Additionally, core damage progression variability inherent in MELCOR modeling numerics is investigated.

  12. Instructional Cost Analysis: History and Present Inadequacies.

    Science.gov (United States)

    Humphrey, David A.

    The cost analysis of instruction is conducted according to principles of teaching and learning that have often become historically dated. Using today's costing systems prevents determination of whether cost effectiveness actually exists. The patterns of instruction in higher education and the systems employed for instructional cost analysis are…

  13. 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

  14. National Variation in Urethroplasty Cost and Predictors of Extreme Cost: A Cost Analysis with Policy Implications

    OpenAIRE

    Harris, Catherine R.; Osterberg, E. Charles; Sanford, Thomas; Alwaal, Amjad; Gaither, Thomas W.; McAninch, Jack W.; McCulloch, Charles E.; Breyer, Benjamin N.

    2016-01-01

    To determine which factors are associated with higher costs of urethroplasty procedure and whether these factors have been increasing over time. Identification of determinants of extreme costs may help reduce cost while maintaining quality.We conducted a retrospective analysis using the 2001-2010 Healthcare Cost and Utilization Project-Nationwide Inpatient Sample (HCUP-NIS). The HCUP-NIS captures hospital charges which we converted to cost using the HCUP cost-to-charge ratio. Log cost linear ...

  15. Action Memorandum for Decommissioning the Engineering Test Reactor Complex under the Idaho Cleanup Project

    International Nuclear Information System (INIS)

    A. B. Culp

    2007-01-01

    This Action Memorandum documents the selected alternative for decommissioning of the Engineering Test Reactor at the Idaho National Laboratory under the Idaho Cleanup Project. Since the missions of the Engineering Test Reactor Complex have been completed, an engineering evaluation/cost analysis that evaluated alternatives to accomplish the decommissioning of the Engineering Test Reactor Complex was prepared and released for public comment. The scope of this Action Memorandum is to encompass the final end state of the Complex and disposal of the Engineering Test Reactor vessel. The selected removal action includes removing and disposing of the vessel at the Idaho CERCLA Disposal Facility and demolishing the reactor building to ground surface

  16. Decommissioning of AECL Whiteshell laboratories - 16311

    International Nuclear Information System (INIS)

    Koroll, Grant W.; Bilinsky, Dennis M.; Swartz, Randall S.; Harding, Jeff W.; Rhodes, Michael J.; Ridgway, Randall W.

    2009-01-01

    Whiteshell Laboratories (WL) is a Nuclear Research and Test Establishment near Winnipeg, Canada, operated by AECL since the early 1960's and now under decommissioning. WL occupies approximately 4400 hectares of land and employed more than 1000 staff up to the late-1990's, when the closure decision was made. Nuclear facilities at WL included a research reactor, hot cell facilities and radiochemical laboratories. Programs carried out at the WL site included high level nuclear fuel waste management research, reactor safety research, nuclear materials research, accelerator technology, biophysics, and industrial radiation applications. In preparation for decommissioning, a comprehensive environmental assessment was successfully completed [1] and the Canadian Nuclear Safety Commission issued a six-year decommissioning licence for WL starting in 2003 - the first decommissioning licence issued for a Nuclear Research and Test Establishment in Canada. This paper describes the progress in this first six-year licence period. A significant development in 2006 was the establishment of the Nuclear Legacy Liabilities Program (NLLP), by the Government of Canada, to safely and cost effectively reduce, and eventually eliminate the nuclear legacy liabilities and associated risks, using sound waste management and environmental principles. The NLLP endorsed an accelerated approach to WL Decommissioning, which meant advancing the full decommissioning of buildings and facilities that had originally been planned to be decontaminated and prepared for storage-with-surveillance. As well the NLLP endorsed the construction of enabling facilities - facilities that employ modern waste handling and storage technology on a scale needed for full decommissioning of the large radiochemical laboratories and other nuclear facilities. The decommissioning work and the design and construction of enabling facilities are fully underway. Several redundant non-nuclear buildings have been removed and redundant

  17. Study on decommissioning

    International Nuclear Information System (INIS)

    2012-01-01

    This project consists of researches on (1) establishment of review plan on application of decommissioning, (2) establishment of specific method to confirm decommissioning completion, of decommissioning and (3) establishment of radioactive waste management guideline during dismantling and (4) development of the regulatory system on decommissioning in response to Fukushima Daiichi NPP accident. About researches on establishment of review plan on application of decommissioning. 'Planning of the Commercial Power Reactor Decommissioning:2001' which was published by Atomic Energy Society of Japan, was evaluated whether it suited the requirement for the decommissioning stipulated in the law, and the draft evaluation report was prepared. About researches on establishment of specific method to confirm decommissioning completion, technical information of practical procedures on the confirmation in U.S.A. were organized based on MARSSIM (Multi-Agency Radiation Survey and Site Investigation Manual, NUREG-1575) and applicability of MARSSIM on the confirmation in Japan was examined. Exposed doses for public during decommissioning period were estimated to study dose criterion of the confirmation. Radioactive concentrations in the soil of Tokai and Hamaoka NPP caused by the Fukushima Daiichi NPP accident were also investigated. About researches on establishment of radioactive waste management guideline during dismantling, one concrete core was sampled in biological shield of the Tokai NPP and radioactive concentrations were investigated. About researches on development of the regulatory system on decommissioning in response to Fukushima Daiichi NPP accident, present status of Three Mile Island Unit 2 and Chernobyl NPP Unit 4 were investigated. Present status of regulatory systems for decommissioning in foreign countries taken in consideration of the accident was also researched. (author)

  18. 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.

  19. Pre-decommissioning radiological characterization of concrete

    International Nuclear Information System (INIS)

    Boden, Sven; Cantrel, Eric

    2007-01-01

    The decommissioning of the BR3 (Belgian Reactor 3) approaches its final phase, in which the building structures are being decontaminated and either denuclearized for possible reuse or demolished. Apart from the presence of naturally occurring radionuclides in building materials, other radionuclides might be present due to contamination or activation. The overall process of the BR3 building structure D and D (Decontamination and Decommissioning) consists of the following steps: - make a complete inventory and preliminary categorize all elements based on historical data; characterize and determine the contamination or activation depth; - determine the decontamination method; - perform the decontamination and clean up; - a possible intermediate characterization followed by an additional decontamination step; and characterize for clearance. A good knowledge of the contamination and activation depth (second step) is fundamental in view of cost minimization. Currently, the method commonly used for the determination of the depth is based on core drilling and destructive analysis. Recently, we have introduced a complementary non destructive assay based on in-situ gamma spectroscopy. Field tests at BR3, both for contamination and activation, showed promising results. (authors)

  20. SGN's Dismantling and Decommissioning engineering, projects experience and capabilities

    International Nuclear Information System (INIS)

    Destrait, L.

    1998-01-01

    Its experience in waste treatment, conditioning, storage and disposal, its cooperation with CEA and COGEMA Group in license agreements give SGN expertise in the decommissioning field. SGN's experience and background in all areas of nuclear facility decommissioning, such as chemical and mechanical cells, nuclear advanced reactors, reprocessing facilities result in fruitful references to the customers. The poster is presenting different achievements and projects with SGN's participation such as: - The decommissioning of Windscale Advanced Gas cooled Reactors (WAGR), in particular providing methodology and equipment to dismantle the Pressure and Insulation Vessel of the reactor. - The decommissioning plan of Ignalina (Lithuania) and Paldiski (Estonia), defining strategies, scenarios, necessary equipments and tools and choosing the best solutions to decommission the site under different influencing parameters such as cost, dose rate exposure, etc... - Th One Site Assistance Team (OSAT) at Chernobyl regarding the preparation works for the waste management and decommissioning of the plant. - The decommissioning of French nuclear facilities such as reprocessing (UP1) and reactor (EL4) plants. The important experience acquired during the facility management and during the first dismantling and decommissioning operations is an important factor for the smooth running of these techniques for the future. The challenge to come is to control all the operations, the choice of strategies, the waste management, the efficiency of tools and equipments, and to provide nuclear operators with a full range of proven techniques to optimise costs and minimize decommissioning personnel exposure. (Author)

  1. Overview of decommissioning activities in the US

    International Nuclear Information System (INIS)

    LaGuardia, T.S.

    2006-01-01

    The U.S. has been involved the successful decontamination, decommissioning and reutilization of nuclear facilities for over 20 years. A number of commercial power plants in the United States have either completed their decommissioning, or will be in the next few years. In addition, the U.S. DOE has taken an aggressive approach to site remediation focusing on site closures so as to better utilize its financial resources. The U.S. initiative to deregulate the electrical generation industry to promote competition and presumably to reduce electricity prices to the consumer, is again in flux. Some utilities, facing the real or perceived threat of competition in its markets decided to shut down the 'costly' nuclear plants to alleviate the drain on their financial reserves. The older nuclear units experienced serious mechanical problems, entailing expensive repairs and replacements. Such difficulties have caused owner-operator utilities to decide to decommission these facilities rather than incur the expense of upgrading or repairing the plants to meet current regulatory and design criteria. Plants that were marginally cost-competitive, or not at all competitive, were shut down and decommissioned. Other utilities have bought some of the older nuclear plants in the Northeast (a high power demand region) to operate them and to extend their licenses for continued life. This paper will discuss the decommissioning lessons learned, management approaches, site characterization and challenges faced in disposition of radioactive waste and large components, contracting practice, and the status of several of these shut down reactor-decommissioning programs. The industry has proven that nuclear power plants can be cost effectively and safely decommissioned. (author)

  2. The Importance of Experience Based Decommissioning Planning

    International Nuclear Information System (INIS)

    Larsson, Arne; Lidar, Per; Hedin, Gunnar; Bergh, Niklas

    2016-01-01

    Decommissioning of a nuclear facility is an extensive and multidisciplinary task, which involves the management and technical actions associated with ceasing operation and thereafter the step-by-step transfer of the facility from an operating plant to an object under decommissioning. The decommissioning phase includes dismantling of systems and components, decontamination and clearance, demolition of buildings, remediation of any contaminated ground and finally a survey of the site. Several of these activities generate radioactive or potentially radioactive waste, which has to be managed properly prior to clearance or disposal. What makes decommissioning of nuclear installations unique is to large extent the radioactive waste management. No other industries have that complex regulatory framework for the waste management. If decommissioning project in the nuclear industry does not consider the waste aspects to the extent required, there is a large risk of failure causing a reduced trust by the regulators and other stakeholders as well as cost and schedule overruns. This paper will give an overview of important aspects and findings gathered during decades of planning and conducting decommissioning and nuclear facility modernization projects. (authors)

  3. 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

  4. Decommissioning and disposal of foreign uranium mine and mill facilities

    International Nuclear Information System (INIS)

    Pan Yingjie; Xue Jianxin; Yuan Baixiang; Xu Lechang

    2012-01-01

    Disposal techniques in decommissioning of foreign uranium mine and mill facilities are systematically discussed, including covering of uranium tailing impoundment, drainaging and consolidation of uranium tailing, and treatment of mining waste water and polluted groundwater, and the costs associated with disposal are analyzed. The necessity of strengthening the decommissioning disposal technology research and international exchanges and cooperation is emphasized. (authors)

  5. A nationwide modelling approach to decommissioning - 16182

    International Nuclear Information System (INIS)

    Kelly, Bernard; Lowe, Andy; Mort, Paul

    2009-01-01

    In this paper we describe a proposed UK national approach to modelling decommissioning. For the first time, we shall have an insight into optimizing the safety and efficiency of a national decommissioning strategy. To do this we use the General Case Integrated Waste Algorithm (GIA), a universal model of decommissioning nuclear plant, power plant, waste arisings and the associated knowledge capture. The model scales from individual items of plant through cells, groups of cells, buildings, whole sites and then on up to a national scale. We describe the national vision for GIA which can be broken down into three levels: 1) the capture of the chronological order of activities that an experienced decommissioner would use to decommission any nuclear facility anywhere in the world - this is Level 1 of GIA; 2) the construction of an Operational Research (OR) model based on Level 1 to allow rapid what if scenarios to be tested quickly (Level 2); 3) the construction of a state of the art knowledge capture capability that allows future generations to learn from our current decommissioning experience (Level 3). We show the progress to date in developing GIA in levels 1 and 2. As part of level 1, GIA has assisted in the development of an IMechE professional decommissioning qualification. Furthermore, we describe GIA as the basis of a UK-Owned database of decommissioning norms for such things as costs, productivity, durations etc. From level 2, we report on a pilot study that has successfully tested the basic principles for the OR numerical simulation of the algorithm. We then highlight the advantages of applying the OR modelling approach nationally. In essence, a series of 'what if...' scenarios can be tested that will improve the safety and efficiency of decommissioning. (authors)

  6. Safe decommissioning of the Romanian VVR-S research reactor

    International Nuclear Information System (INIS)

    Garlea, C.; Garlea, I.; Kelerman, C.; Rodna, A.

    2002-01-01

    The VVR-S Romania research reactor was operated between 1957-1997, at 2 MW nominal power, for research and radioisotopical production. The detailed decommissioning plan was developed between 1995-1998, in the frame of the International Atomic Energy Agency Technical assistance project ROM/9/017. The proposed strategy agreed by the counterpart as well as international experts was stage 1. In 1997, an independent analysis performed by European Commission experts, in the frame of PHARE project PH04.1/1994 was dedicated to the 'Study of Soviet Design Research Reactors', had consolidated the development of the project emphasizing technical options of safe management for radioactive wastes and VVR-S spent fuel. The paper presents the main technical aspects as well as those of social impact, which lead to the establishment of strategy for safe management of decommissioning. Technical analysis of the VVR-S reactor and associated radwaste facilities (Radioactive Waste Treatment Plant - Magurele and National Repository Baita-Bihor) proved the possibility of the classical method utilization for dismantling of the facility and treatment-conditioning-disposal of the arrised wastes in safe conditions. The decommissioning plan at stage 2 has been developed based on radiological safety assessment, evaluation of radwaste inventory (removed as well as preserved on site), cost analysis and environmental impact. Technical data were provided by the R and D programme including neutron calculations and experiments, radiological characterizing (for facility and its influence area), seismic analysis and environmental balance during the operation and after shut down of the reactor. A special chapter is dedicated to regulatory issues concerning the development of decommissioning under nuclear safety. Based on the Fundamental Norms of Radiological Safety, the Regulatory Body defined the clearance levels and safety criteria for the process. The development of National Norms for the

  7. 10 CFR 70.25 - Financial assurance and recordkeeping for decommissioning.

    Science.gov (United States)

    2010-01-01

    ... segregated from licensee assets and outside the licensee's administrative control of cash or liquid assets such that the amount of funds would be sufficient to pay decommissioning costs. Prepayment may be in... estimate for decommissioning and a description of the method of assuring funds for decommissioning from...

  8. New iteration of decommissioning program for NPP Krsko

    International Nuclear Information System (INIS)

    Lokner, V.; Levanat, I.; Rapic, A.; Zeleznik, N.; Mele, I.; Jenko, T.

    2004-01-01

    As required by the paragraph 10 of the Agreement between the governments of Slovenia and Croatia on status and other legal issues related to investment, exploitation, and decommissioning of Nuclear power plant Krsko, Decommissioning program for Krsko NPP including LILW and spent fuel management was drafted. The Intergovernmental body required that the Program should be extensive revision of existing program as one of several iterations to be prepared before the final version. The purpose of the Program is to estimate the expenses of the future decommissioning, radioactive waste and spent fuel management for Krsko NPP. Costing estimation would be the basis for establishment of a special fund in Croatia and for adjustment of the annual rates for the existing decommissioning fund in Slovenia. The Program development was entrusted to specialized organizations both in Croatia and Slovenia, which formed the Project team as the operative body. Consulting firms from Croatia and Slovenia were involved as well as experts from the International Atomic Energy Agency (through short visits to Zagreb and Ljubljana) for specialized fields (e.g. economic aspects of decommissioning, pre-feasibility study for spent fuel repository in crystalline rock, etc.). The analysis was performed in several steps. The first step was to develop rational and feasible integral scenarios (strategies) of decommissioning and LILW and spent fuel management on the basis of detailed technical analysis and within defined boundary conditions. Based on technological data, every scenario was attributed with time distribution of expenses for all main activities. In the second step, financial analysis of the scenarios was undertaken aiming at estimation of total discounted expense and the related annuity (19 installments to the single fund, empty in 2003) for each of the scenarios. The third step involves additional analysis of the chosen scenarios aiming at their (technical or financial) improvements even at

  9. Cost effectiveness analysis in radiopharmacy

    International Nuclear Information System (INIS)

    Carpentier, N.; Verbeke, S.; Ducloux, T.

    1999-01-01

    Objective: to evaluate the cost effectiveness of radiopharmaceuticals and their quality control. Materials and methods: this retrospective study was made in the Nuclear Medicine Department of the University Hospital of Limoges. Radiopharmaceutical costs were obtained with adding the price of the radiotracer, the materials, the equipments, the labour, the running expenses and the radioisotope. The costs of quality control were obtained with adding the price of labour, materials, equipments, running expenses and the cost of the quality control of 99m Tc eluate. Results: during 1998, 2106 radiopharmaceuticals were prepared in the Nuclear Medicine Department. The mean cost effectiveness of radiopharmaceutical was 1430 francs (846 to 4260). The mean cost effectiveness of quality control was 163 francs (84 to 343). The rise of the radiopharmaceutical cost induced by quality control was 11%. Conclusion: the technical methodology of quality control must be mastered to optimize the cost of this operation. (author)

  10. Cost analysis of reliability investigations

    International Nuclear Information System (INIS)

    Schmidt, F.

    1981-01-01

    Taking Epsteins testing theory as a basis, premisses are formulated for the selection of cost-optimized reliability inspection plans. Using an example, the expected testing costs and inspection time periods of various inspection plan types, standardized on the basis of the exponential distribution, are compared. It can be shown that sequential reliability tests usually involve lower costs than failure or time-fixed tests. The most 'costly' test is to be expected with the inspection plan type NOt. (orig.) [de

  11. 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.

  12. 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

  13. Development of improved technology for decommissioning operations

    International Nuclear Information System (INIS)

    Allen, R.P.

    1982-07-01

    This paper describes the technology development activities conducted at Pacific Northwest Laboratory under US Department of Energy sponsorship to help ensure the availability of safe, cost-effective and environmentally sound decommissioning technology for radioactively contaminated facilities. These improved decommissioning technologies include techniques for the removal of contaminated concrete surfaces and coatings, adaptation of electropolishing and vibratory finishing decontamination techniques for field decommissioning applications, development of sensitive field instrumentation and methods for the monitoring of large surface areas, techniques for the field sectioning of contaminated components, improved contamination-stabilizing coatings and application methods, and development of a small solidification system for the field solidification of liquid waste. The results of cost/benefit studies for some of these technologies are also reported

  14. Life-Cycle Cost-Benefit Analysis

    DEFF Research Database (Denmark)

    Thoft-Christensen, Palle

    2010-01-01

    The future use of Life-Cycle Cost-Benefit (LCCB) analysis is discussed in this paper. A more complete analysis including not only the traditional factors and user costs, but also factors which are difficult to include in the analysis is needed in the future.......The future use of Life-Cycle Cost-Benefit (LCCB) analysis is discussed in this paper. A more complete analysis including not only the traditional factors and user costs, but also factors which are difficult to include in the analysis is needed in the future....

  15. Incorporating psychological influences in probabilistic cost analysis

    Energy Technology Data Exchange (ETDEWEB)

    Kujawski, Edouard; Alvaro, Mariana; Edwards, William

    2004-01-08

    Today's typical probabilistic cost analysis assumes an ''ideal'' project that is devoid of the human and organizational considerations that heavily influence the success and cost of real-world projects. In the real world ''Money Allocated Is Money Spent'' (MAIMS principle); cost underruns are rarely available to protect against cost overruns while task overruns are passed on to the total project cost. Realistic cost estimates therefore require a modified probabilistic cost analysis that simultaneously models the cost management strategy including budget allocation. Psychological influences such as overconfidence in assessing uncertainties and dependencies among cost elements and risks are other important considerations that are generally not addressed. It should then be no surprise that actual project costs often exceed the initial estimates and are delivered late and/or with a reduced scope. This paper presents a practical probabilistic cost analysis model that incorporates recent findings in human behavior and judgment under uncertainty, dependencies among cost elements, the MAIMS principle, and project management practices. Uncertain cost elements are elicited from experts using the direct fractile assessment method and fitted with three-parameter Weibull distributions. The full correlation matrix is specified in terms of two parameters that characterize correlations among cost elements in the same and in different subsystems. The analysis is readily implemented using standard Monte Carlo simulation tools such as {at}Risk and Crystal Ball{reg_sign}. The analysis of a representative design and engineering project substantiates that today's typical probabilistic cost analysis is likely to severely underestimate project cost for probability of success values of importance to contractors and procuring activities. The proposed approach provides a framework for developing a viable cost management strategy for

  16. Department of the Army Cost Analysis Manual

    National Research Council Canada - National Science Library

    1997-01-01

    .... The specific goal of this manual is to help the cost analyst serve the customer. This is done by providing reference material on cost analysis processes, methods, techniques, structures, and definitions...

  17. RECTIFIED ETHANOL PRODUCTION COST ANALYSIS

    Directory of Open Access Journals (Sweden)

    Nikola J Budimir

    2011-01-01

    Full Text Available This paper deals with the impact of the most important factors of the total production costs in bioethanol production. The most influential factors are: total investment costs, price of raw materials (price of biomass, enzymes, yeast, and energy costs. Taking into account these factors, a procedure for estimation total production costs was establish. In order to gain insight into the relationship of production and selling price of bioethanol, price of bioethanol for some countries of the European Union and the United States are given.

  18. UK reactor decommissioning strategy

    International Nuclear Information System (INIS)

    Woollam, P.B.

    2004-01-01

    With the cessation of electricity generation, nuclear power stations move into the next stage of the overall life cycle of the facility: decommissioning. Decommissioning is defined as the process whereby a nuclear facility, at the end of its economic life, is taken permanently out of service and its site made available for other purposes. This involves the implementation of a structured and safe programme for dismantling and clearing the site and making it available for alternative use in the future. In practical terms, 'decommissioning' means the systematic and progressive reduction of hazards to the point where the site could eventually be de-licensed. (author)

  19. 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)

  20. Safety Assessment for Decommissioning

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-06-15

    In the past few decades, international guidance has been developed on methods for assessing the safety of predisposal and disposal facilities for radioactive waste. More recently, it has been recognized that there is also a need for specific guidance on safety assessment in the context of decommissioning nuclear facilities. The importance of safety during decommissioning was highlighted at the International Conference on Safe Decommissioning for Nuclear Activities held in Berlin in 2002 and at the First Review Meeting of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management in 2003. At its June 2004 meeting, the Board of Governors of the IAEA approved the International Action Plan on Decommissioning of Nuclear Facilities (GOV/2004/40), which called on the IAEA to: ''establish a forum for the sharing and exchange of national information and experience on the application of safety assessment in the context of decommissioning and provide a means to convey this information to other interested parties, also drawing on the work of other international organizations in this area''. In response, in November 2004, the IAEA launched the international project Evaluation and Demonstration of Safety for Decommissioning of Facilities Using Radioactive Material (DeSa) with the following objectives: -To develop a harmonized approach to safety assessment and to define the elements of safety assessment for decommissioning, including the application of a graded approach; -To investigate the practical applicability of the methodology and performance of safety assessments for the decommissioning of various types of facility through a selected number of test cases; -To investigate approaches for the review of safety assessments for decommissioning activities and the development of a regulatory approach for reviewing safety assessments for decommissioning activities and as a basis for regulatory decision making; -To provide a forum

  1. European Decommissioning Academy

    International Nuclear Information System (INIS)

    Slugen, V. S.; Hornacek, M.

    2016-01-01

    Full text: Experiences from the first run of the European Decommissioning Academy (EDA) are reported in details. EDA was created at the Slovak University of Technology in Bratislava Slovakia, based on discussion and expressed needs declared at many international meetings including ECED2013. The first run successfully passed 15 participants during 7–26 June 2015. Academy was focused on decommissioning issues via lessons, practical exercises in laboratories, on-site training prepared at NPP V-1 in Jaslovské Bohunice, Slovakia as well as four day technical tour to other European decommissioning facilities in Switzerland and Italy. Detailed information can be found at http://kome.snus.sk/inpe/. (author

  2. 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

  3. Optimal policies for aggregate recycling from decommissioned forest roads.

    Science.gov (United States)

    Thompson, Matthew; Sessions, John

    2008-08-01

    To mitigate the adverse environmental impact of forest roads, especially degradation of endangered salmonid habitat, many public and private land managers in the western United States are actively decommissioning roads where practical and affordable. Road decommissioning is associated with reduced long-term environmental impact. When decommissioning a road, it may be possible to recover some aggregate (crushed rock) from the road surface. Aggregate is used on many low volume forest roads to reduce wheel stresses transferred to the subgrade, reduce erosion, reduce maintenance costs, and improve driver comfort. Previous studies have demonstrated the potential for aggregate to be recovered and used elsewhere on the road network, at a reduced cost compared to purchasing aggregate from a quarry. This article investigates the potential for aggregate recycling to provide an economic incentive to decommission additional roads by reducing transport distance and aggregate procurement costs for other actively used roads. Decommissioning additional roads may, in turn, result in improved aquatic habitat. We present real-world examples of aggregate recycling and discuss the advantages of doing so. Further, we present mixed integer formulations to determine optimal levels of aggregate recycling under economic and environmental objectives. Tested on an example road network, incorporation of aggregate recycling demonstrates substantial cost-savings relative to a baseline scenario without recycling, increasing the likelihood of road decommissioning and reduced habitat degradation. We find that aggregate recycling can result in up to 24% in cost savings (economic objective) and up to 890% in additional length of roads decommissioned (environmental objective).

  4. Planning activities for ANPP decommissioning

    International Nuclear Information System (INIS)

    Ghazaryan, K.G.

    2002-01-01

    The Armenian NPP consists of two WWER-440, model 270 pressurized water reactors. After an earthquake in northern Armenia in December 1988 both units were shut down for safety reasons: Unit 1 in February 1988, Unit 2 in March 1989, respectively. Unit 2 was restarted in November 1995 after a number of safety upgrades. Unit 1 remains in a long-term shutdown mode. The design lifetime of Unit 2 expires in 2015. Opportunity to shutdown earlier has been discussed in the last years. In particular a statement has been issued by EC asking for an early shutdown of Unit 2 in exchange for the TACIS support in implementing the safety upgrades in a short term. Currently the safety improvement program is being successfully implemented in the framework of US DOE and TACIS assistance. At the moment the date of the permanent plant shutdown is not specified. As with many older reactors throughout the world, a decommissioning plan has not been developed for Armenian NPP at the design stage. After shutdown of ANPP in 1988-1989 the radiological characterization campaign at Unit 1 had been carried out. Recently two studies in the decommissioning area have been performed for ANPP. The first one has been carried out under the US DOE Assistance Program. The purpose of this study was to identify and evaluate feasible decommissioning options for ANPP. Some critical issues related to the waste management had been specified and the near-term activities within this project will be focused on issues of waste characterization and information data base creation as an important prerequisite to manage waste safely. The model used to calculate many of the decommissioning costs was NRC CECP reprogrammed for WWER NPPs. The second study had been carried out in the framework of TACIS project 'Assistance to Energy Strategic Center'. The purpose of the study was to select the best strategy to phase-out and decommission the ANPP and evaluate conditions, implications and consequence of this decision. A

  5. Environmental Cost Analysis System (ECAS) Status and Compliance Requirements for EM Consolidated Business Center Contracts - 13204

    International Nuclear Information System (INIS)

    Sanford, P.C.; Moe, M.A.; Hombach, W.G.; Urdangaray, R.

    2013-01-01

    The Department of Energy (DOE) Office of Environmental Management (EM) has developed a web-accessible database to collect actual cost data from completed EM projects to support cost estimating and analysis. This Environmental Cost Analysis System (ECAS) database was initially deployed in early 2009 containing the cost and parametric data from 77 decommissioning, restoration, and waste management projects completed under the Rocky Flats Closure Project. In subsequent years we have added many more projects to ECAS and now have a total of 280 projects from 8 major DOE sites. This data is now accessible to DOE users through a web-based reporting tool that allows users to tailor report outputs to meet their specific needs. We are using it as a principal resource supporting the EM Consolidated Business Center (EMCBC) and the EM Applied Cost Engineering (ACE) team cost estimating and analysis efforts across the country. The database has received Government Accountability Office review as supporting its recommended improvements in DOE's cost estimating process, as well as review from the DOE Office of Acquisition and Project Management (APM). Moving forward, the EMCBC has developed a Special Contract Requirement clause or 'H-Clause' to be included in all current and future EMCBC procurements identifying the process that contractors will follow to provide DOE their historical project data in a format compatible with ECAS. Changes to DOE O 413.3B implementation are also in progress to capture historical costs as part of the Critical Decision project closeout process. (authors)

  6. 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)

  7. 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

  8. 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

  9. Ethics and Cost-Benefit Analysis

    DEFF Research Database (Denmark)

    Arler, Finn

    The purpose of this research report is threefold. Firstly, the author traces the origins and justification of cost-benefit analysis in moral and political philosophy. Secondly, he explain some of the basic features of cost-benefit analysis as a planning tool in a step-bystep presentation. Thirdly......, he presents and discusses some of the main ethical difficulties related to the use of cost-benefit analysis as a planning tool....

  10. Decommissioning of the Northrop TRIGA reactor

    International Nuclear Information System (INIS)

    Cozens, George B.; Woo, Harry; Benveniste, Jack; Candall, Walter E.; Adams-Chalmers, Jeanne

    1986-01-01

    An overview of the administrative and operational aspects of decommissioning and dismantling the Northrop Mark F TRIGA Reactor, including: planning and preparation, personnel requirements, government interfacing, costs, contractor negotiations, fuel shipments, demolition, disposal of low level waste, final survey and disposition of the concrete biological shielding. (author)

  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. Chapter 17. Engineering cost analysis

    Energy Technology Data Exchange (ETDEWEB)

    Higbee, Charles V.

    1998-01-01

    In the early 1970s, life cycle costing (LCC) was adopted by the federal government. LCC is a method of evaluating all the costs associated with acquisition, construction and operation of a project. LCC was designed to minimize costs of major projects, not only in consideration of acquisition and construction, but especially to emphasize the reduction of operation and maintenance costs during the project life. Authors of engineering economics texts have been very reluctant and painfully slow to explain and deal with LCC. Many authors devote less than one page to the subject. The reason for this is that LCC has several major drawbacks. The first of these is that costs over the life of the project must be estimated based on some forecast, and forecasts have proven to be highly variable and frequently inaccurate. The second problem with LCC is that some life span must be selected over which to evaluate the project, and many projects, especially renewable energy projects, are expected to have an unlimited life (they are expected to live for ever). The longer the life cycle, the more inaccurate annual costs become because of the inability to forecast accurately.

  13. Cost-effectiveness Analysis for Technology Acquisition.

    Science.gov (United States)

    Chakravarty, A; Naware, S S

    2008-01-01

    In a developing country with limited resources, it is important to utilize the total cost visibility approach over the entire life-cycle of the technology and then analyse alternative options for acquiring technology. The present study analysed cost-effectiveness of an "In-house" magnetic resonance imaging (MRI) scan facility of a large service hospital against outsourcing possibilities. Cost per unit scan was calculated by operating costing method and break-even volume was calculated. Then life-cycle cost analysis was performed to enable total cost visibility of the MRI scan in both "In-house" and "outsourcing of facility" configuration. Finally, cost-effectiveness analysis was performed to identify the more acceptable decision option. Total cost for performing unit MRI scan was found to be Rs 3,875 for scans without contrast and Rs 4,129 with contrast. On life-cycle cost analysis, net present value (NPV) of the "In-house" configuration was found to be Rs-(4,09,06,265) while that of "outsourcing of facility" configuration was Rs-(5,70,23,315). Subsequently, cost-effectiveness analysis across eight Figures of Merit showed the "In-house" facility to be the more acceptable option for the system. Every decision for acquiring high-end technology must be subjected to life-cycle cost analysis.

  14. Model reduction by weighted Component Cost Analysis

    Science.gov (United States)

    Kim, Jae H.; Skelton, Robert E.

    1990-01-01

    Component Cost Analysis considers any given system driven by a white noise process as an interconnection of different components, and assigns a metric called 'component cost' to each component. These component costs measure the contribution of each component to a predefined quadratic cost function. A reduced-order model of the given system may be obtained by deleting those components that have the smallest component costs. The theory of Component Cost Analysis is extended to include finite-bandwidth colored noises. The results also apply when actuators have dynamics of their own. Closed-form analytical expressions of component costs are also derived for a mechanical system described by its modal data. This is very useful to compute the modal costs of very high order systems. A numerical example for MINIMAST system is presented.

  15. Funding for reactor decommissioning: the NRC perspective

    International Nuclear Information System (INIS)

    Wood, R.S.

    1981-01-01

    The cost of decommissioning a nuclear power plant is discussed. Four funding approaches that have received the most attention from the NRC are: prepayment into a trust fund of estimated decommissioning funds at the start of facility operation; annual contributions into a trust fund outside the control of the utility over the estimated life of a facility; internal reserve or sinking fund amortizations over the estimated life of a facility; and insurance or other surety mechanisms used separately or in conjunction with any of the first three mechanisms

  16. Decommissioning of a tritium-contaminated laboratory

    International Nuclear Information System (INIS)

    Harper, J.R.; Garde, R.

    1982-01-01

    A tritium laboratory facility at the Los Alamos National Laboratory, Los Alamos, New Mexico, was decommissioned in 1979. The project involved dismantling the laboratory equipment and disposing of the equipment and debris at an on-site waste disposal/storage area. The laboratory, constructed in 1953, was in service for tritium research and fabrication of lithium tritide components until 1974. The major features of the laboratory included 25 meters of gloveboxes and hoods, associated vacuum lines, utility lines, exhaust ducts, electrodryers, blowers, and laboratory benches. This report presents details on the decommissioning, health physics, waste management, environmental surveillance, and costs for the operation

  17. Hanford radiochemical site decommissioning demonstration program

    International Nuclear Information System (INIS)

    Nelson, D.C.

    1971-01-01

    A program is proposed for the innovation, development, and demonstration of technologies necessary to decommission the Hanford radiochemical plant area to the extent that the sites can have unrestricted public access. The five tasks selected for development and demonstration of restoration techniques were restoration of a burial ground, decommissioning of a separations plant, restoration of a separations plant waste interim storage tank farm, restoration of a liquid disposal area, and disposal of large contaminated equipment. Process development requirements are tabulated and discussed. A proposed schedule and estimated costs are given

  18. Cost analysis methodology of spent fuel storage

    International Nuclear Information System (INIS)

    1994-01-01

    The report deals with the cost analysis of interim spent fuel storage; however, it is not intended either to give a detailed cost analysis or to compare the costs of the different options. This report provides a methodology for calculating the costs of different options for interim storage of the spent fuel produced in the reactor cores. Different technical features and storage options (dry and wet, away from reactor and at reactor) are considered and the factors affecting all options defined. The major cost categories are analysed. Then the net present value of each option is calculated and the levelized cost determined. Finally, a sensitivity analysis is conducted taking into account the uncertainty in the different cost estimates. Examples of current storage practices in some countries are included in the Appendices, with description of the most relevant technical and economic aspects. 16 figs, 14 tabs

  19. A cost analysis: processing maple syrup products

    Science.gov (United States)

    Neil K. Huyler; Lawrence D. Garrett

    1979-01-01

    A cost analysis of processing maple sap to syrup for three fuel types, oil-, wood-, and LP gas-fired evaporators, indicates that: (1) fuel, capital, and labor are the major cost components of processing sap to syrup; (2) wood-fired evaporators show a slight cost advantage over oil- and LP gas-fired evaporators; however, as the cost of wood approaches $50 per cord, wood...

  20. 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)

  1. Securing decommissioning funds. Why organization matters?

    International Nuclear Information System (INIS)

    Tchapga, F.

    2005-01-01

    Full text: Securing decommissioning funds requires that the financial resources set aside for the purpose of decommissioning be managed prudently. Decommissioning of nuclear power plant is prescribed by National Atomic Laws or by other nuclear legislation. It is a mandatory operation. The operators of nuclear power plants set money aside for that purpose. This is known as 'Decommissioning reserve fund'. Decommissioning implies costs very distant in time. Thus, it is obvious, from an economic point of view, that the funds set aside should be managed. As decommissioning is mandatory, the funds accumulated should be secured. In others words, they should be available when needed. Availability of funds is influenced by endogenous and exogenous factors. Endogenous factors are a matter of design of the reserve funds. They include the management of the funds, its monitoring and control... Availability of funds is influenced by these factors, depending on the rules to which the behaviour of the manager of the funds is subjected. In contrast, exogenous factors deal with the energy context. These factors are mainly the electricity sector organisation and/or the overall economic situation. They are decisive factors of the economic performance of the reserve fund for a given design. Therefore, the requirement of availability of funds, when needed, is a matter of compatibility between the design of the decommissioning funds and the electricity context. Put differently, reserve fund's design need to be consistent with the electricity context's features in respect of the availability of funds. Current reserve funds were designed in a context of monopoly regime. In this context, availability of decommissioning funds was not questionable. At least, as far as the design of the reserve funds is concerned. This is because nuclear generator didn't confront any competition pressure. Electricity prices were set trough rate base mechanism, and all the business risks were borne by the

  2. Rancho Seco--Decommissioning Update

    International Nuclear Information System (INIS)

    Newey, J. M.; Ronningen, E. T.; Snyder, M. W.

    2003-01-01

    The Rancho Seco Nuclear Generating Station ceased operation in June of 1989 and entered an extended period of SAFSTOR to allow funds to accumulate for dismantlement. Incremental dismantlement was begun in 1997 of steam systems and based on the successful completion of work, the Sacramento Municipal Utility District (SMUD) board of directors approved full decommissioning in July 1999. A schedule has been developed for completion of decommissioning by 2008, allowing decommissioning funds to accumulate until they are needed. Systems removal began in the Auxiliary Building in October of 1999 and in the Reactor Building in January of 2000. Systems dismantlement continues in the Reactor Building and should be completed by the end of 2003. System removal is near completion in the Auxiliary Building with removal of the final liquid waste tanks in progress. The spent fuel has been moved to dry storage in an onsite ISFSI, with completion on August 21, 2002. The spent fuel racks are currently being removed from the pool, packaged and shipped, and then the pool will be cleaned. Also in the last year the reactor coolant pumps and primary piping were removed and shipped. Characterization and planning work for the reactor vessel and internals is also in progress with various cut-up and/or disposal options being evaluated. In the year ahead the remaining systems in the Reactor Building will be removed, packaged and sent for disposal, including the pressurizer. Work will be started on embedded and underground piping and the large outdoor tanks. Building survey and decontamination will begin. RFP's for removal of the vessel and internals and the steam generators are planned to fix the cost of those components. If the costs are consistent with current estimates the work will go forward. If they are not, hardened SAFSTOR/entombment may be considered

  3. Cost probability analysis of reprocessing spent nuclear fuel in the US

    International Nuclear Information System (INIS)

    Recktenwald, G.D.; Deinert, M.R.

    2012-01-01

    The methods by which nuclear power's radioactive signature could be reduced typically require the reprocessing of spent nuclear fuel. However, economic assessments of the costs that are associated with doing this are subject to a high degree of uncertainty. We present a probabilistic analysis of the costs to build, operate and decommission the facilities that would be required to reprocess all US spent nuclear fuel generated over a one hundred year time frame, starting from a 2010 power production rate. The analysis suggests a total life-cycle cost of 2.11 ± 0.26 mills/kWh, with a 90% and 99% confidence that the overall cost would remain below 2.45 and 2.75 mills/kWh respectively. The most significant effects on cost come from the efficiency of the reactor fleet and the growth rate of nuclear power. The analysis shows that discounting results in life-cycle costs decreasing as recycling is delayed. However the costs to store spent fuel closely counter the effect of discounting when an intergenerational discount rate is used.

  4. Platform decommissioning: Socio-economic impacts

    International Nuclear Information System (INIS)

    Scheelhaase, Janina D.

    1998-01-01

    The object of this presentation is to evaluate the socio-economic effects of the decommissioning of steel jacket platforms in the North Sea and in the North East Atlantic in the period up to 2020 in their entirety. It is focused on two different decommissioning options, namely total and partial removal of installations. Partial removal applies only to installations in water deeper than 75 meters. All other installations, i.e those in waters shallower than 75 meters, have to be totally removed and brought onshore for disposal. Areas being analyzed cover costs of different decommissioning options, effects of the different options on employment, fiscal aspects of the different options, and aspects of recycling onshore. 6 figs., 13 tabs

  5. Decommissioning of the Neuherberg Research Reactor (FRN)

    International Nuclear Information System (INIS)

    Demmeler, M.; Rau, G.; Strube, D.

    1982-01-01

    The Neuherberg Research Reactor is of type TRIGA MARK III with 1 MW steady state power and pulsable up to 2000 MW. During more than ten years of operation 12000 MWh and 6000 reactor pulses had been performed. In spite of its good technical condition and of permanent safe operation without any failures, the decommissioning of the Neuherberg research reactor was decided by the GSF board of directors to save costs for maintaining and personnel. As the mode of decommissioning the safe enclosure was chosen which means that the fuel elements will be transferred back to the USA. All other radioactive reactor components will be enclosed in the reactor block. Procedures for licensing of the decommissioning, dismantling procedures and time tables are presented

  6. Radioactive waste management and decommissioning in The United States

    International Nuclear Information System (INIS)

    Raymont, J.M.

    2005-01-01

    . Given that DOE disposal costs are about 1/10th to 1/100th that of commercial costs, the differences in disposal costs result in disposal avoidance as key utility LLW management approach and direct disposal as the key US DOE LLW management approach. In conclusion, it appears that, given the same regulatory environment, the cost of disposal generally dictates waste management and decommissioning practices due to the strong impact on life cycle analysis. (orig.)

  7. 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

  8. 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

  9. QUANTIFYING BENEFITS FOR COST-BENEFIT ANALYSIS

    OpenAIRE

    Attila GYORGY; Nicoleta VINTILA; Florian GAMAN

    2014-01-01

    Cost Benefit Analysis is one of the most widely used financial tools to select future investment projects in public and private sector. This method is based on comparing costs and benefits in terms of constant prices. While costs are easier to predict and monetize, the benefits should be identified not only in direct relation with the investment, but also widening the sphere of analysis to indirect benefits experienced by the community from the neighbourhood or the whole society. During finan...

  10. Cost analysis of in vitro fertilization.

    Science.gov (United States)

    Stern, Z; Laufer, N; Levy, R; Ben-Shushan, D; Mor-Yosef, S

    1995-08-01

    In vitro fertilization (IVF) has become a routine tool in the arsenal of infertility treatments. Assisted reproductive techniques are expensive, as reflected by the current "take home baby" rate of about 15% per cycle, implying the need for repeated attempts until success is achieved. Israel, today is facing a major change in its health care system, including the necessity to define a national package of health care benefits. The issue of infertility and whether its treatment should be part of the "health basket" is in dispute. Therefore an exact cost analysis of IVF is important. Since the cost of an IVF cycle varies dramatically between countries, we sought an exact breakdown of the different components of the costs involved in an IVF cycle and in achieving an IVF child in Israel. The key question is not how much we spend on IVF cycles but what is the cost of a successful outcome, i.e., a healthy child. This study intends to answer this question, and to give the policy makers, at various levels of the health care system, a crucial tool for their decision-making process. The cost analysis includes direct and indirect costs. The direct costs are divided into fixed costs (labor, equipment, maintenance, depreciation, and overhead) and variable costs (laboratory tests, chemicals, disposable supplies, medications, and loss of working days by the couples). The indirect costs are the costs of premature IVF babies, hospitalization of the IVF pregnant women in a high risk unit, and the cost of complications of the procedure. According to our economic analysis, an IVF cycle in Israel costs $2,560, of which fixed costs are about 50%. The cost of a "take home baby" is $19,267, including direct and indirect costs.

  11. 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)

  12. National Variation in Urethroplasty Cost and Predictors of Extreme Cost: A Cost Analysis With Policy Implications.

    Science.gov (United States)

    Harris, Catherine R; Osterberg, E Charles; Sanford, Thomas; Alwaal, Amjad; Gaither, Thomas W; McAninch, Jack W; McCulloch, Charles E; Breyer, Benjamin N

    2016-08-01

    To determine which factors are associated with higher costs of urethroplasty procedure and whether these factors have been increasing over time. Identification of determinants of extreme costs may help reduce cost while maintaining quality. We conducted a retrospective analysis using the 2001-2010 Healthcare Cost and Utilization Project-Nationwide Inpatient Sample (HCUP-NIS). The HCUP-NIS captures hospital charges which we converted to cost using the HCUP cost-to-charge ratio. Log cost linear regression with sensitivity analysis was used to determine variables associated with increased costs. Extreme cost was defined as the top 20th percentile of expenditure, analyzed with logistic regression, and expressed as odds ratios (OR). A total of 2298 urethroplasties were recorded in NIS over the study period. The median (interquartile range) calculated cost was $7321 ($5677-$10,000). Patients with multiple comorbid conditions were associated with extreme costs [OR 1.56, 95% confidence interval (CI) 1.19-2.04, P = .02] compared with patients with no comorbid disease. Inpatient complications raised the odds of extreme costs (OR 3.2, CI 2.14-4.75, P costs (OR 1.78, 95% CI 1.2-2.64, P = .005). Variations in patient age, race, hospital region, bed size, teaching status, payor type, and volume of urethroplasty cases were not associated with extremes of cost. Cost variation for perioperative inpatient urethroplasty procedures is dependent on preoperative patient comorbidities, postoperative complications, and surgical complexity related to graft usage. Procedural cost and cost variation are critical for understanding which aspects of care have the greatest impact on cost. Copyright © 2016 Elsevier Inc. All rights reserved.

  13. Decommissioning plan - decommissioning project for KRR 1 and 2 (revised)

    International Nuclear Information System (INIS)

    Jung, K. J.; Paik, S. T.; Chung, U. S.; Jung, K. H.; Park, S. K.; Lee, D. G.; Kim, H. R.; Kim, J. K.; Yang, S. H.; Lee, B. J.

    2000-10-01

    This report is the revised Decommissioning Plan for the license of TRIGA research reactor decommissioning project according to Atomic Energy Act No. 31 and No. 36. The decommissioning plan includes the TRIGA reactor facilities, project management, decommissioning method, decontamination and dismantling activity, treatment, packaging, transportation and disposal of radioactive wastes. the report also explained the radiation protection plan and radiation safety management during the decommissioning period, and expressed the quality assurance system during the period and the site restoration after decommissioning. The first decommissioning plan was made by Hyundai Engineering Co, who is the design service company, was submitted to the Ministry of Science and Technology, and then was reviewed by the Korea Institute of Nuclear Safety. The first decommissioning plan was revised including answers for the questions arising from review process

  14. Decommissioning plan - decommissioning project for KRR 1 and 2 (revised)

    Energy Technology Data Exchange (ETDEWEB)

    Jung, K. J.; Paik, S. T.; Chung, U. S.; Jung, K. H.; Park, S. K.; Lee, D. G.; Kim, H. R.; Kim, J. K.; Yang, S. H.; Lee, B. J

    2000-10-01

    This report is the revised Decommissioning Plan for the license of TRIGA research reactor decommissioning project according to Atomic Energy Act No. 31 and No. 36. The decommissioning plan includes the TRIGA reactor facilities, project management, decommissioning method, decontamination and dismantling activity, treatment, packaging, transportation and disposal of radioactive wastes. the report also explained the radiation protection plan and radiation safety management during the decommissioning period, and expressed the quality assurance system during the period and the site restoration after decommissioning. The first decommissioning plan was made by Hyundai Engineering Co, who is the design service company, was submitted to the Ministry of Science and Technology, and then was reviewed by the Korea Institute of Nuclear Safety. The first decommissioning plan was revised including answers for the questions arising from review process.

  15. 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)

  16. Decommissioning of a brachytherapy facility at the Oncology Hospital in Havana

    International Nuclear Information System (INIS)

    Benitez, J.C.; Salgado, M.; Madrazo, S.; Castillo, R.; Marcos, J.; Flores, J.

    2001-01-01

    , measurements of dose rate and surface contamination were carried out. The selection of the more convenient strategies for decommissioning included a justification, a proposed timetable and a demonstration of adequate financial provision. Different factors were considered, such as: the future use of the facility, the availability of a national waste treatment and storage facility, technical feasibility and cost benefit analysis. Dismantling, as one of the operations during decommissioning, was necessary for facilitating access to radium sources and for size reduction of contaminated materials to facilitate their handling. The dismantling strategy was very simple, using simple equipment. The generation of radioactive wastes from decommissioning process was kept to the minimum practical, by using appropriate decontamination and dismantling techniques. The decommissioning project was successfully completed. Adequate project management was applied to the program for safety assurance, radiation protection and waste management. One hundred and thirty six spent 226 Ra sources were recovered from the facility and properly managed. The requirements established by the Regulatory Body to release the facility from the regulatory control were achieved. Simple and effective decontamination and dismantling technology was applied for decommissioning of INOR brachytherapy facility allowing minimization of generated radioactive waste and the immediate site release from regulatory control. Upon successful completion of decommissioning, the Oncology Institute received the authorization from Regulatory Body for unrestricted use of the facility

  17. 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

  18. 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.

  19. A managerial accounting analysis of hospital costs.

    Science.gov (United States)

    Frank, W G

    1976-01-01

    Variance analysis, an accounting technique, is applied to an eight-component model of hospital costs to determine the contribution each component makes to cost increases. The method is illustrated by application to data on total costs from 1950 to 1973 for all U.S. nongovernmental not-for-profit short-term general hospitals. The costs of a single hospital are analyzed and compared to the group costs. The potential uses and limitations of the method as a planning and research tool are discussed.

  20. 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)

  1. Lessons learned from the decommissioning of NORM facility in Malaysia

    International Nuclear Information System (INIS)

    Kontol, Khairuddin M.; Omar, Muhamat; Ahmad, Syed H.S.S.

    2008-01-01

    Full text: Malaysia Decommissioning of Naturally Occurring Radioactive Materials (NORM) facility in Malaysia will run into unforeseeable complications and difficulties if there is no proper planning. The Atomic Energy Licensing Board (AELB) plays important role in guiding and assisting the operator/contractor in this NORM decommissioning project. A local Naturally Occurring Radioactive Materials (NORM) processing plant located in the northern region of peninsular Malaysia had ceased its operations and decided to decommission and remediate its site for the final release of the site. The remediated site is earmarked as an industrial site. During its operations, monazites are processed for rare earth elements such as cerium and lanthanum. It's plant capable of processing monazite to produce rare earth chloride and rare earth carbonate. The main by-product of monazite processing is the radioactive cake containing primarily thorium hydroxide. Operation of the monazite processing plant started in early eighties and terminated in early nineties. The decommissioning of the plant site started in late 2003 and completed its decommissioning and remediation works in early 2006. This paper described the lesson learned by Malaysian Nuclear Agency (Nuclear Malaysia) in conducting third party independent audit for the decommissioning of the NORM contaminated facility. By continuously reviewing the lessons learned, mistakes and/or inefficiencies in this plant decommissioning project, hopefully will result in a smoother, less costly and more productive future decommissioning works on NORM facilities in Malaysia. (author)

  2. Decommissioning the UHTREX Reactor Facility at Los Alamos, New Mexico

    International Nuclear Information System (INIS)

    Salazar, M.; Elder, J.

    1992-08-01

    The Ultra-High Temperature Reactor Experiment (UHTREX) facility was constructed in the late 1960s to advance high-temperature and gas-cooled reactor technology. The 3-MW reactor was graphite moderated and helium cooled and used 93% enriched uranium as its fuel. The reactor was run for approximately one year and was shut down in February 1970. The decommissioning of the facility involved removing the reactor and its associated components. This document details planning for the decommissioning operations which included characterizing the facility, estimating the costs of decommissioning, preparing environmental documentation, establishing a system to track costs and work progress, and preplanning to correct health and safety concerns in the facility. Work to decommission the facility began in 1988 and was completed in September 1990 at a cost of $2.9 million. The facility was released to Department of Energy for other uses in its Los Alamos program

  3. 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

  4. 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

  5. Decommissioning strategy selection

    International Nuclear Information System (INIS)

    Warnecke, E.

    2005-01-01

    At the end of their useful life nuclear facilities have to be decommissioned. The strategy selection on how to decommission a facility is a highly important decision at the very beginning of decommissioning planning. Basically, a facility may be subject to (a) immediate dismantling; (b) deferred dismantling after a period of ''safe enclosure'' or (c) entombment where a facility is turned into a near surface disposal facility. The first two strategies are normally applied. The third one may be accepted in countries without significant nuclear activities and hence without disposal facilities for radioactive waste. A large number of factors has to be taken into account when a decision on the decommissioning strategy is being made. Many of the factors cannot be quantified. They may be qualitative or subject to public opinion which may change with time. At present, a trend can be observed towards immediate dismantling of nuclear facilities, mainly because it is associated with less uncertainty, less local impact, a better public acceptance, and the availability of operational expertise and know how. A detailed evaluation of the various factors relevant to strategy selection and a few examples showing the situation regarding decommissioning strategy in a number of selected countries are presented in the following article. (orig.)

  6. Decommissioning in western Europe

    International Nuclear Information System (INIS)

    Lundqvist, K.

    1999-12-01

    This report gives an overview of the situation in Western Europe. The original aim was to focus on organisational and human issues with regard to nuclear reactor decommissioning, but very few articles were found. This is in sharp contrast to the substantial literature on technical issues. While most of the reports on decommissioning have a technical focus, several provide information on regulatory issues, strategies and 'state of the art'. The importance of the human and organizational perspective is however discovered, when reading between the lines of the technical publications, and especially when project managers summarize lessons learned. The results are to a large extent based on studies of articles and reports, mainly collected from the INIS database. Decommissioning of nuclear facilities started already in the sixties, but then mainly research and experimental facilities were concerned. Until now about 70 reactors have been shutdown world-wide. Over the years there have been plenty of conferences for exchanging experiences mostly about technical matters. Waste Management is a big issue. In the 2000s there will be a wave of decommissioning when an increasing amount of reactors will reach the end of their calculated lifetime (40 years, a figure now being challenged by both life-extension and pre-shutdown projects). Several reactors have been shut-down for economical reasons. Shutdown and decommissioning is however not identical. A long period of time can sometimes pass before an owner decides to decommission and dismantle a facility. The conditions will also differ depending on the strategy, 'immediate dismantling' or 'safe enclosure'. If immediate dismantling is chosen the site can reach 'green-field status' in less than ten years. 'Safe enclosure', however, seems to be the most common strategy. There are several pathways, but in general a safe store is constructed, enabling the active parts to remain in safe and waterproof conditions for a longer period of

  7. Methodology of personnel exposure calculation and optimisation within the decommissioning planning code OMEGA

    International Nuclear Information System (INIS)

    Vasko, Marek; Daniska, Vladimir; Rehak, Ivan; Necas, Vladimir

    2011-01-01

    Calculation of personnel exposure is a one of the main parameters being evaluated within the pre-decommissioning plans together with other decommissioning drivers such as costs, manpower, amounts of RAW and conventional waste and amount of discharged gaseous and liquid effluents. Alongside with manpower, the exposure is an indicator of the decommissioning process for need of staff, and quantifies impact of decommissioning on personnel from the radio hygienic point of view. At the same time it indicates suitability of individual work procedures use for decommissioning activities. For this reason it is important to estimate as precise as possible demands on personnel exposure even during preparatory decommissioning phase to quantify impact of decommissioning on personnel and eventually optimize the decommissioning process, if needed. The most appropriate way of staff exposure estimation during decommissioning preparatory phases is its calculation based on radiological and physical characteristics of equipment to be decommissioned and also quantitative and qualitative characterisation of typical decommissioning activities. On one hand, the methodology of exposure calculation should allow as much as possible realistic description and algorithmisation of exposure ways during decommissioning activities. On the other hand the calculation have to be systematic, well-arranged and clearly definable by appropriate mathematic relations. Calculation can be made by various approaches using more or less sophisticated software solutions from classic MS Excel sheets up to the complex calculation codes. In this paper, a methodology used for personnel exposure calculation and optimization implemented within the complex computer code OMEGA developed at DECOM, a.s. is described. (author)

  8. Decommissioning funding: ethics, implementation, uncertainties

    International Nuclear Information System (INIS)

    2006-01-01

    This status report on Decommissioning Funding: Ethics, Implementation, Uncertainties also draws on the experience of the NEA Working Party on Decommissioning and Dismantling (WPDD). The report offers, in a concise form, an overview of relevant considerations on decommissioning funding mechanisms with regard to ethics, implementation and uncertainties. Underlying ethical principles found in international agreements are identified, and factors influencing the accumulation and management of funds for decommissioning nuclear facilities are discussed together with the main sources of uncertainties of funding systems. (authors)

  9. FORECAST: Regulatory effects cost analysis software annual

    International Nuclear Information System (INIS)

    Lopez, B.; Sciacca, F.W.

    1991-11-01

    Over the past several years the NRC has developed a generic cost methodology for the quantification of cost/economic impacts associated with a wide range of new or revised regulatory requirements. This methodology has been developed to aid the NRC in preparing Regulatory Impact Analyses (RIAs). These generic costing methods can be useful in quantifying impacts both to industry and to the NRC. The FORECAST program was developed to facilitate the use of the generic costing methodology. This PC program integrates the major cost considerations that may be required because of a regulatory change. FORECAST automates much of the calculations typically needed in an RIA and thus reduces the time and labor required to perform these analysis. More importantly, its integrated and consistent treatment of the different cost elements should help assure comprehensiveness, uniformity, and accuracy in the preparation of needed cost estimates

  10. Shippingport Station Decommissioning Project

    International Nuclear Information System (INIS)

    McKernan, M.L.

    1989-01-01

    The Shippingport Atomic Power Station was located on the Ohio River in Shippingport Borough (Beaver County), Pennsylvania, USA. The US Atomic Energy Commission (AEC) constructed the plant in the mid-1950s on a seven and half acre parcel of land leased from Duquesne Light Company (DLC). The purposes were to demonstrate and to develop Pressurized Water Recovery technology and to generate electricity. DLC operated the Shippingport plant under supervision of (the successor to AEC) the Department of Energy (DOE)-Naval Reactors (NR) until operations were terminated on October 1, 1982. NR concluded end-of-life testing and defueling in 1984 and transferred the Station's responsibility to DOE Richland Operations Office (RL), Surplus Facility Management Program Office (SFMPO5) on September 5, 1984. SFMPO subsequently established the Shippingport Station Decommissioning Project and selected General Electric (GE) as the Decommissioning Operations Contractor. This report is intended to provide an overview of the Shippingport Station Decommissioning Project

  11. Site decommissioning management plan

    International Nuclear Information System (INIS)

    Fauver, D.N.; Austin, J.H.; Johnson, T.C.; Weber, M.F.; Cardile, F.P.; Martin, D.E.; Caniano, R.J.; Kinneman, J.D.

    1993-10-01

    The Nuclear Regulatory Commission (NRC) staff has identified 48 sites contaminated with radioactive material that require special attention to ensure timely decommissioning. While none of these sites represent an immediate threat to public health and safety they have contamination that exceeds existing NRC criteria for unrestricted use. All of these sites require some degree of remediation, and several involve regulatory issues that must be addressed by the Commission before they can be released for unrestricted use and the applicable licenses terminated. This report contains the NRC staff's strategy for addressing the technical, legal, and policy issues affecting the timely decommissioning of the 48 sites and describes the status of decommissioning activities at the sites

  12. Site decommissioning management plan

    Energy Technology Data Exchange (ETDEWEB)

    Fauver, D.N.; Austin, J.H.; Johnson, T.C.; Weber, M.F.; Cardile, F.P.; Martin, D.E.; Caniano, R.J.; Kinneman, J.D.

    1993-10-01

    The Nuclear Regulatory Commission (NRC) staff has identified 48 sites contaminated with radioactive material that require special attention to ensure timely decommissioning. While none of these sites represent an immediate threat to public health and safety they have contamination that exceeds existing NRC criteria for unrestricted use. All of these sites require some degree of remediation, and several involve regulatory issues that must be addressed by the Commission before they can be released for unrestricted use and the applicable licenses terminated. This report contains the NRC staff`s strategy for addressing the technical, legal, and policy issues affecting the timely decommissioning of the 48 sites and describes the status of decommissioning activities at the sites.

  13. International Good Practice on Practical Implementation of Characterisation in Decommissioning. Radiological Characterization in Decommissioning of Nuclear Facilities: International Good Practice on Practical Implementation

    International Nuclear Information System (INIS)

    Larsson, A.; Empdage, M.; Weber, I.; )

    2017-01-01

    Within the Nuclear Energy Agency (NEA), the Working Party on Decommissioning and Dismantling (WPDD) operates under the umbrella of the Radioactive Waste Management Committee (RWMC). The WPDD provides a focus for the analysis of decommissioning policy, strategy and regulation, including the related issues of waste management, release of buildings and sites from regulatory control and associated cost estimation and funding. WPDD also convenes task groups comprised of experts from the NEA member countries to review related topics such as characterisation techniques which support decommissioning and associated waste management. The Task Group on Radiological Characterisation and Decommissioning was established in 2011 to identify and present characterisation good practice at different stages of decommissioning and to identify areas that could, or should, be developed further through international cooperation and coordination. By the end of 2016 two phases of work will be complete. The first phase developed strategic guidance for decision makers on the selection and tailoring of strategies for radiological characterisation, which gives an overview of good practice for radiological characterisation at different phases of the life cycle of a nuclear installation. The second phase has focused on strategies for practical implementation of radiological characterisation from a waste and materials end-state perspective. This paper provides a summary of the phase 2 findings, covering: -) a major international survey (questionnaire) to elicit the views of characterisation experts regarding good practice; -) Learning drawn from recent international case studies; -) The collation and analysis of regulations, standards and guidance documents; -) Learning distilled from an international conference on characterisation co-organised by the task group; and -) Overall conclusions regarding characterisation good practice, recommendations and identified areas for further international

  14. Preparation for Ignalina NPP decommissioning

    International Nuclear Information System (INIS)

    Medeliene, D.

    2004-01-01

    Latest developments of atomic energy in Lithuania, works done to prepare Ignalina NPP for final shutdown and decommissioning are described. Information on decommissioning program for Ignalina NPP unit 1, decommissioning method, stages and funding is presented. Other topics: radiation protection, radioactive waste management and disposal. Key facts related to nuclear energy in Lithuania are listed

  15. 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

  16. Cost Analysis for Large Civil Transport Rotorcraft

    Science.gov (United States)

    Coy, John J.

    2006-01-01

    This paper presents cost analysis of purchase price and DOC+I (direct operating cost plus interest) that supports NASA s study of three advanced rotorcraft concepts that could enter commercial transport service within 10 to 15 years. The components of DOC+I are maintenance, flight crew, fuel, depreciation, insurance, and finance. The cost analysis aims at VTOL (vertical takeoff and landing) and CTOL (conventional takeoff and landing) aircraft suitable for regional transport service. The resulting spreadsheet-implemented cost models are semi-empirical and based on Department of Transportation and Army data from actual operations of such aircraft. This paper describes a rationale for selecting cost tech factors without which VTOL is more costly than CTOL by a factor of 10 for maintenance cost and a factor of two for purchase price. The three VTOL designs selected for cost comparisons meet the mission requirement to fly 1,200 nautical miles at 350 knots and 30,000 ft carrying 120 passengers. The lowest cost VTOL design is a large civil tilt rotor (LCTR) aircraft. With cost tech factors applied, the LCTR is reasonably competitive with the Boeing 737-700 when operated in economy regional service following the business model of the selected baseline operation, that of Southwest Airlines.

  17. 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 se