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Sample records for e3640 decommissioning aberdeen

  1. Geophysics: Building E5190 decommissioning, Aberdeen Proving Ground

    Miller, S.F.; Thompson, M.D.; McGinnis, M.G.; McGinnis, L.D.

    1992-07-01

    Building E5190 is one of ten potentially contaminated sites in the Canal Creek area of the Edgewood section of Aberdeen Proving Ground examined by a geophysical team from Argonne National Laboratory in April and May 1992. A noninvasive geophysical survey, including the complementary technologies of magnetics, electrical resistivity, and ground-penetrating radar, was conducted around the perimeter as a guide to developing a sampling and monitoring program prior to decommissioning and dismantling the building. The magnetics surveys indicated that multistation, positive magnetic sources are randomly distributed north and west of the building. Two linear trends were noted: one that may outline buried utility lines and another that is produced by a steel-covered trench. The resistivity profiling indicated three conductive zones: one due to increased moisture in a ditch, one associated with buried utility lines, and a third zone associated with the steel-covered trench. Ground-penetrating radar imaging detected two significant anomalies, which were correlated with small-amplitude magnetic anomalies. The objectives of the study -- to detect and locate objects and to characterize a located object were achieved.

  2. Interim progress report -- geophysics: Decommissioning of Buildings E5974 and E5978, Aberdeen Proving Ground

    Buildings E5974 and E5978, located near the mouth of Canal Creek, were among 10 potentially contaminated sites in the Westwood and Canal Creek areas of the Edgewood section of Aberdeen Proving Ground examined by a geophysical team from Argonne National Laboratory in April and May of 1992. Noninvasive geophysical surveys, including the complementary technologies of magnetics, electrical resistivity, and ground-penetrating radar, were conducted around the perimeters of the buildings to guide a sampling program prior to decommissioning and dismantling. The magnetic anomalies and the electrically conductive areas around these buildings have a spatial relationship similar to that observed in low-lying sites in the Canal Creek area; they are probably associated with construction fill. Electrically conductive terrain is dominant on the eastern side of the site, and resistive terrain predominates on the west. The smaller magnetic anomalies are not imaged with ground radar or by electrical profiling. The high resistivities in the northwest quadrant are believed to be caused by a natural sand lens. The causes of three magnetic anomalies in the high-resistivity area are unidentified, but they are probably anthropogenic

  3. Geophysics: Building E5190 decommissioning, Aberdeen Proving Ground. Interim progress report

    Miller, S.F.; Thompson, M.D.; McGinnis, M.G.; McGinnis, L.D.

    1992-07-01

    Building E5190 is one of ten potentially contaminated sites in the Canal Creek area of the Edgewood section of Aberdeen Proving Ground examined by a geophysical team from Argonne National Laboratory in April and May 1992. A noninvasive geophysical survey, including the complementary technologies of magnetics, electrical resistivity, and ground-penetrating radar, was conducted around the perimeter as a guide to developing a sampling and monitoring program prior to decommissioning and dismantling the building. The magnetics surveys indicated that multistation, positive magnetic sources are randomly distributed north and west of the building. Two linear trends were noted: one that may outline buried utility lines and another that is produced by a steel-covered trench. The resistivity profiling indicated three conductive zones: one due to increased moisture in a ditch, one associated with buried utility lines, and a third zone associated with the steel-covered trench. Ground-penetrating radar imaging detected two significant anomalies, which were correlated with small-amplitude magnetic anomalies. The objectives of the study -- to detect and locate objects and to characterize a located object were achieved.

  4. Environmental geophysics: Buildings E5485, E5487, and E5489 decommissioning - the open-quotes Ghost Townclose quotes complex, Aberdeen Proving Ground, Maryland

    Buildings E5485, E5487, and E5489, referred to informally as the open-quotes Ghost Townclose quotes complex, are potentially contaminated sites in the Edgewood section of Aberdeen Proving Ground. Noninvasive geophysical surveys, including magnetics, EM-31, EM-61, and ground-penetrating radar, were conducted to assist a sampling and monitoring program prior to decommissioning and dismantling of the buildings. The buildings are located on a marginal wetland bordering the west branch of Canal Creek. The dominant geophysical signature in the open-quotes Ghost Town close quotes complex is a pattern of northeast-southwest and northwest-southeast anomalies that appear to be associated with a trench/pipe/sewer system, documented by the presence of a manhole. Combinations of anomalies suggest that line sources include nonmetallic and ferromagnetic materials in trenches. On the basis of anomaly associations, the sewer lines probably rest in a trench, back-filled with conductive, amphibolitic, crushed rock. Where the sewer lines connect manholes or junctions with other lines, ferromagnetic materials are present. Isolated, unidentified magnetic anomalies litter the area around Building E5487, particularly to the north. Three small magnetic sources are located east of Building E5487

  5. Preliminary assessment of risk from toxic materials that might be mobilized in the decommissioning of Aberdeen Proving Ground Building E5032

    Rosenblatt, D.H.; Brubaker, K.L.

    1991-12-01

    Aberdeen Proving Ground Building E5032 is scheduled for decommissioning, that is, for demolition. Because the building was formerly used for small-scale operations with incendiary and toxic chemical agents, it presents unusual concerns for occupational and public health safety during the demolition. For this reason, an anticipatory risk assessment was conducted, taking into consideration the building`s history, properties of potential residual contaminants (particularly chemical and incendiary agents), and assumptions relating to meteorological conditions and envisioned modes of demolition. Safe maximum levels in concrete floors for the worst case were estimated to be: white phosphorus, 3200 mg/kg; mustard, 94 mg/kg; nerve agent GA (tabun), 6 mg/kg; cyanide, 500 mg/kg; and sulfide, 1400 mg/kg. These values will serve as planning guidance for the activities to follow. It is emphasized that the estimates must be reviewed, and perhaps revised, after sampling and analysis are completed, the demolition methodology is chosen, and dust emissions are measured under operating conditions.

  6. Preliminary assessment of risk from toxic materials that might be mobilized in the decommissioning of Aberdeen Proving Ground Building E5032

    Rosenblatt, D.H.; Brubaker, K.L.

    1991-12-01

    Aberdeen Proving Ground Building E5032 is scheduled for decommissioning, that is, for demolition. Because the building was formerly used for small-scale operations with incendiary and toxic chemical agents, it presents unusual concerns for occupational and public health safety during the demolition. For this reason, an anticipatory risk assessment was conducted, taking into consideration the building's history, properties of potential residual contaminants (particularly chemical and incendiary agents), and assumptions relating to meteorological conditions and envisioned modes of demolition. Safe maximum levels in concrete floors for the worst case were estimated to be: white phosphorus, 3200 mg/kg; mustard, 94 mg/kg; nerve agent GA (tabun), 6 mg/kg; cyanide, 500 mg/kg; and sulfide, 1400 mg/kg. These values will serve as planning guidance for the activities to follow. It is emphasized that the estimates must be reviewed, and perhaps revised, after sampling and analysis are completed, the demolition methodology is chosen, and dust emissions are measured under operating conditions.

  7. Clean-ups at Aberdeen Proving Ground

    The Department of Defense has utilized radiative material in numerous applications over several decades. Aberdeen Proving Ground has been an integral player in the Army's Research, Development, and Testing of items incorporating radionuclides, as well as developing new and innovative applications. As new information becomes available and society progresses, we find that the best management practices used decades, or even sometimes years earlier are inadequate to meet the current demands. Aberdeen Proving Ground is committed to remediating historic disposal sites, and utilizing the best available technology in current operations to prevent future adverse impact. Two projects which are currently ongoing at Aberdeen Proving Ground illustrates these points. The first, the remediation of contaminated metal storage areas, depicts how available technology has provided a means for recycling material whereby preventing the continued stock piling, and allowing for the decommissioning of the areas. The second, the 26Th Street Disposal Site Removal Action, shows how historic methods of disposition were inadequate to meet today's needs

  8. The Aberdeen Impedance Imaging System.

    Kulkarni, V; Hutchison, J M; Mallard, J R

    1989-01-01

    The Aberdeen Impedance Imaging System is designed to reconstruct 2 dimensional images of the average distribution of the amplitude and phase of the complex impedance within a 3 dimensional region. The system uses the four electrode technique in a 16 electrode split-array. The system hardware consists of task-orientated electronic modules for: driving a constant current, multiplexing the current drive, demultiplexing peripheral voltages, differential amplification, phase sensitive detection and low-pass filtration, digitisation with a 14 bit analog to digital converter (ADC), and -control logic for the ADC and multiplexors. A BBC microprocessor (Master series), initiates a controlled sequence for the collection of a number of data sets which are averaged and stored on disk. Image reconstruction is by a process of convolution-backprojection similar to the fan-beam reconstruction of computerised tomography and is also known as Equipotential Backprojection. In imaging impedance changes associated with fracture healing the changes may be large enough to allow retrieval of both the amplitude and phase of the complex impedance. Sequential imaging of these changes would necessitate monitoring electronic and electrode drift by imaging an equivalent region of the contralateral limb. Differential images could be retrieved when the image of the normal limb is the image template. Better characterisation of tissues would necessitate a cleaner retrieval of the quadrature signal. PMID:2742979

  9. Geophysics: Building E5476 decommissiong, Aberdeen Proving Ground

    Building E5476 was one of ten potentially contaminated sites in the Canal Creek and Westwood areas of the Edgewood section of Aberdeen Proving Ground examined by a geophysical team from Argonne National Laboratory in April and May of 1992. Noninvasive geophysical surveys, including magnetics, electrical resistivity, and ground-penetrating radar, were conducted around the perimeter of the building to guide a sampling program prior to decommissioning and dismantling. The large number of magnetic sources surrounding the building are believed to be contained in construction fill. The smaller anomalies, for the most part, were not imaged with ground radar or by electrical profiling. Large magnetic anomalies near the southwest comer of the building are due to aboveground standpipes and steel-reinforced concrete. Two high-resistivity areas, one projecting northeast from the building and another south of the original structure, may indicate the presence of organic pore fluids in the subsurface. A conductive lineament protruding from the south wall that is enclosed by the southem, high-resistivity feature is not associated with an equivalent magnetic anomaly. Magnetic and electrical anomalies south of the old landfill boundary are probably not associated with the building. The boundary is marked by a band of magnetic anomalies and a conductive zone trending northwest to southeast. The cause of high resistivities in a semicircular area in the southwest comer, within the landfill area, is unexplained

  10. Decommissioning Handbook

    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.

  11. Decommissioning handbook

    The purpose of this paper is to provide information on the Handbook and its application as a resource in decontamination and decommissioning (D and D) work. The nature of the unique hazards contained in nuclear facilities demand a comprehensive step-by-step program to cover their design, licensing, and commissioning or start-up. Similarly, because of residual radioactivity, a termination of operations (decommissioning) also presents hazards that must be addressed from a technological and programmatic standpoint. To meet the needs raised by these issues, the original Decommissioning Handbook was prepared in 1980 by Nuclear Energy Services under contract to the United States Department of Energy (DOE). Its mission was to provide technical guidance on the D and D of both commercial and government-owned nuclear facilities, including characterization, decontamination, dismantling, and disposition (disposal or salvage) of a facility's equipment and structure. In addition, depending on the regulatory requirements for material disposal and/or the wastes generated by decontamination, the management of waste can also be considered as a decommissioning activity. Chapters are Operational and predecommissioning activities; Decommissioning project; Decommissioning plan; Regulations; Final project configuration; Characterization; Waste treatment; Decontamination; Dismantling, segmenting, and demolition; Remote handling equipment; Environmental protection; Packaging and transportation; and Decommissioning cost estimates. Appendices contain a prediction method for estimation of radiactive inventory and a glossary

  12. Decommissioning handbook

    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

  13. Decommissioning handbook

    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.

  14. Decommissioning standards

    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. Nuclear decommissioning

    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)

  16. Unexploded ordnance issues at Aberdeen Proving Ground: Background information

    Rosenblatt, D.H.

    1996-11-01

    This document summarizes currently available information about the presence and significance of unexploded ordnance (UXO) in the two main areas of Aberdeen Proving Ground: Aberdeen Area and Edgewood Area. Known UXO in the land ranges of the Aberdeen Area consists entirely of conventional munitions. The Edgewood Area contains, in addition to conventional munitions, a significant quantity of chemical-munition UXO, which is reflected in the presence of chemical agent decomposition products in Edgewood Area ground-water samples. It may be concluded from current information that the UXO at Aberdeen Proving Ground has not adversely affected the environment through release of toxic substances to the public domain, especially not by water pathways, and is not likely to do so in the near future. Nevertheless, modest but periodic monitoring of groundwater and nearby surface waters would be a prudent policy.

  17. 1982 international decommissioning symposium

    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

  18. Workshop on decommissioning

    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)

  19. Decommissioning of Ukrainian NPPs

    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

  20. Decommissioning of nuclear facilities

    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

  1. Utility planning for decommissioning

    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

  2. Genetic characterization of Aberdeen Angus cattle using molecular markers

    Vasconcellos Luciana Pimentel de Mello Klocker

    2003-01-01

    Full Text Available Aberdeen Angus beef cattle from the Brazilian herd were studied genetically using restriction fragment length polymorphism (RFLP of the kappa-casein - HinfI (CSN3 - HinfI, beta-lactoglobulin - HaeIII (LGB - HaeIII and growth hormone AluI (GH- AluI genes, as well as four microsatellites (TEXAN15, CSFM50, BM1224 and BM7160. The RFLP genotypes were determined using the polymerase chain reaction (PCR followed by digestion with restriction endonucleases and electrophoresis in agarose gels. With the exception of the microsatellite BM7160, which was analyzed in an automatic sequencer, the PCR products were genotyped by silver staining. The allele and genotype frequencies, heterozygosities and gene diversity were estimated. The values for these parameters of variability were comparable to other cattle breeds. The genetic relationship of the Aberdeen Angus to other breeds (Caracu, Canchim, Charolais, Guzerath, Gyr, Nelore, Santa Gertrudis and Simmental was investigated using Nei's genetic distance. Cluster analysis placed the Aberdeen Angus in an isolated group in the Bos taurus breeds branch. This fact is in agreement with the geographic origin of this breed.

  3. Health assessment for Aberdeen Proving Grounds, Aberdeen, Maryland, Region 3. CERCLIS Nos. MD3210021355 and MD10020036. Preliminary report

    1989-01-19

    The Aberdeen Proving Grounds site is located in Aberdeen (Harford County) Maryland. Preliminary on-site groundwater and surface water sampling results have identified various metals, phosphorus, and volatile organic compounds. They include: 1,2-dichloroethylene, chloroform, 1,2-dichloroethane, trichloroethylene, benzene, 1,1,2,2-tetrachloroethane, tetrachloroethylene, 1,4-dithiane and 1,2-dichloroethylene. In addition, it has been reported that among the substances disposed of on-site are significant quantities of toxic metals, cyanide compounds, phosphorus, phosgene, napalm, and mustard gas. The site is considered to be of public health concern because of the risk to human health caused by the likelihood of human exposure to hazardous substances. Potential environmental pathways include those related to contaminated groundwater, surface water, on-site soils, and volatilization of contaminants in ambient air.

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

    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.

  5. Fort St. Vrain decommissioning experiences

    Public Service Company of Colorado (PSCo) is in the process of decommissioning the Fort St Vrain nuclear station, the first large-scale commercial nuclear plant to be decommissioned under the U.S. NRC's decommissioning rule. The experience has included providing for the disposition of spent fuel, choosing a decommissioning alternative, and actively decommissioning the plant from dismantlement and decontamination through final survey

  6. Training for decommissioning

    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)

  7. On decommissioning nuclear facilities

    As the number of nuclear power plants commissioned is increasing worldwide, both the responsible goverment agencies and the public are more and more concerned about decommissioning nuclear facilities after they have been shut down for good. IAEA organized a symposium on November 13-17, 1978 which dealt with problems of decommissioning, covering national objectives, technical processes, radiological questions, experience in plant decommissioning, decontamination techniques and remote handling procedures. It turned out that sufficient practical experience and highly developed decommissioning concepts and techniques are now available. Experts feel that also in the future no insoluble technical problems or problems must be expected which could only be solved at inordinately high technical expenditure. The article contains a survey of the present staus of problem solutions. Current work is being dedicated to the dose rates accumulated by decommissioning personnel and to the costs of decommissioning. (orig.)

  8. Decommissioning of Nuclear Facilities

    Atomic Energy Regulatory Board (AERB) is of the view that every organisation should focus attention on the decommissioning of nuclear facilities after completion of their useful life. AERB is aware that, internationally there is a growing interest in plant life extension due to economic considerations. Regulatory bodies stipulate upgradation of safety features based on international experience and current safety standards. However, decommissioning becomes a necessity at some time after the extended life of the plant. Nuclear industry has demonstrated that, with modern technological developments, decommissioning of nuclear facilities can be carried out without undue risk to the occupational workers, members of the public and protection of the environment. In view of limited experience in the field of decommissioning, this document is being issued as a safety manual instead of a safety guide. This manual elaborates the various technical and safety considerations in the decommissioning of nuclear facilities including ultimate disposal of radioactive materials/ wastes generated during decommissioning. Details that are required to be furnished to the regulatory body while applying for authorisation for decommissioning and till its completion are enumerated. This manual is issued to assist Department of Atomic Energy (DAE) units in formulating a decommissioning programme. Since the subject of decommissioning of nuclear facilities is a continuously evolving process, AERB is of the view, that provisions of this manual will apply for a period of five years from the date of issue and will be subsequently revised, if necessary

  9. Fort St. Vrain decommissioning

    The first commercial reactor to be decommissioned under the NRC's decommissioning rule is Public Service Company of Colorado's Fort St. Vrain Nuclear Station. The dismantlement and decontamination of this 330 MWe High Temperature Gas Cooled Reactor (HTGR) has involved many challenges for PSC, including establishing adequate funding, obtaining required regulatory approvals, selecting a decommissioning alternative, defueling to an Independent Spent Fuel Storage Installation, arranging for sufficient waste disposal, and managing a large fixed-price decommissioning contract. With physical dismantlement activities about one-third complete, the project is approximately on schedule and within the agreed upon costs

  10. NPP Krsko decommissioning concept

    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)

  11. NPP Krsko decommissioning concept

    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)

  12. Odin - lessons learnt. Decommissioning

    The article relates briefly to the abandoned natural gas field of Odin on the Norwegian continental shelf. The platform could be seen as the benchmark by which all other decommissioning activity in the North Sea takes place, since it is the first significantly large structure to have been decommissioned in deep water. 1 fig

  13. Decommissioning and jobs

    One aspect of the decommissioning web is its effect on socioeconomics, particularly jobs. What will reactor retirement mean to jobs, especially in rural communities where power plant operations may be the most reliable and dominant source of direct and indirect employment in the area? The problems which any plant closure produces for job security are generally understood, but the decommissioning of nuclear power plants is different because of the residual radioactivity and because of the greater isolation of the power plant sites. For example, what will be the specific employment effects of several possible decommissioning scenarios such as immediate dismantlement and delayed dismantlement? The varying effects of decommissioning on jobs is discussed. It is concluded that the decommissioning of nuclear power plants in some areas such as Wales could bring benefits to the surrounding communities. (author)

  14. Decommissioning activities in FUGEN

    FUGEN Decommissioning Engineering Center (hereinafter called as 'FUGEN'), JAEA obtained the approval of the decommissioning program for the prototype Advanced Thermal Reactor on February, 2008. FUGEN has been carrying out decommissioning works based on its decommissioning program since then. In the initial stage, the dismantling works were launched in turbine system whose contamination was relatively low level and their various data have been accumulating. And the draining heavy water, tritium decontamination and transferring of heavy water were carried out safely and reasonably. The preparation for introducing the clearance system, and the research and development works for the reactor core dismantling have been progressed steadily as well. Meanwhile, FUGEN has affiliations with local industries and universities for collaboration research, and has exchanged the decommissioning information with domestic and overseas organizations continuously. (author)

  15. International Decommissioning Strategies

    The IAEA has been developing guidance and technical information relating to the decommissioning and decommissioning strategies of nuclear facilities for over 20 years. During this time, the international concept of decommissioning strategies, and its importance, has changed. Three basic decommissioning strategies are envisaged as possibilities for nuclear installations: immediate dismantling, deferred dismantling and entombment. All have advantages and disadvantages, but the International Conference on Safe Decommissioning for Nuclear Activities demonstrated that immediate dismantling is the generally preferred option. However, there are a number of factors that might lead operators to choose one of the other strategies, and each situation has to be examined individually to identify the optimal strategy for that situation. The basic approach of these three strategies is discussed in the paper. (author)

  16. Nuclear decommissioning: Funding arrangements

    This statement describes the United Kingdom's approach to funding civil nuclear decommissioning activities and explain proposed changes to the current arrangements. The UK has nuclear operators both in the private and public sectors and the approach to decommissioning funding differs. British Energy (BE), which operates a fleet of AGR power stations and a PWR, is in the private sector. On privatization, a segregated fund was established to cover BE's future decommissioning costs. Money paid into the fund is invested and the accumulated assets used to meet future decommissioning and cleanup costs. The precise amount of money that will be required to cover decommissioning costs is not an exact science. That is why the performance of the segregated fund is reviewed at five yearly intervals, at which stage BE's annual contribution can be adjusted as appropriate. To ensure that the fund is managed effectively and investments are made wisely, the fund is managed by independent trustees jointly appointed by the Government and the company. So far, the fund is performing as expected and it is on target to cover BE's decommissioning costs. Operators in the public sector include British Nuclear Fuels Limited (BNFL) and the United Kingdom Atomic Energy Authority (UKAEA). BNFL operates the fleet of Magnox power stations, a number of which are in various stages of decommissioning. BNFL also operates Sellafield (reprocessing, MOX and other operations) and Springfields (fuel manufacture). UKAEA is responsible for decommissioning the UK's former research reactor sites at Dounreay, Windscale (Cumbria), Harwell and Winfrith (Dorset). Under current arrangements, taxpayers meet the cost of decommissioning and cleanup at UKAEA sites; taxpayers will also meet the costs associated with the decommissioning of Magnox power stations from 2008 onwards

  17. International decommissioning strategies

    Full text: The IAEA Safety Requirements for decommissioning states that the regulatory body shall establish requirements for the decommissioning of nuclear facilities, including conditions on the end points of decommissioning. One of the main important issues is that the operator shall be responsible for all aspects of safety of the facility during its lifetime and of the decommissioning activities until its completion. A mechanism for providing adequate financial resources shall be established to cover the costs of radioactive waste management and, in particular the cost of decommissioning. It shall be put in place before operation and shall be updated, as necessary. A safety assessment of the proposed decommissioning strategy shall be performed and its implementation shall not begin until approval has been received by the regulatory body. A decommissioning plan shall be prepared for each facility, to show that decommissioning can be accomplished safely. The decommissioning plan shall be reviewed regularly and shall be updated as required to reflect, in particular, changes in the facility or regulatory requirements, advances in technology and, finally, the needs of decommissioning operation. If it is intended to defer decommissioning, it shall be demonstrated in the final decommissioning plan that such an option is safe. Decontamination and dismantling techniques shall be chosen which minimizes waste and appropriate means shall be in place for safe managing any waste that might be generated during the decommissioning process. A quality assurance programme shall be established for the decommissioning process. Before a site may be released for unrestricted use, a survey shall be performed to demonstrate that the end point conditions, as established by regulatory body, have been met. If site cannot be released for unrestricted use, appropriate control shall be maintained to ensure protection of human health and environment. The IAEA Safety Guidance mainly addresses

  18. Research reactor decommissioning

    Full text: Of the ∼ 800 research reactors constructed worldwide to date, ∼50% have been shut down and are at various stages of decommissioning. Many reached the end of their design lives or were shut down due to strategic, economic or regulatory considerations. 27% of those in operation are over 40 years old and will need to be decommissioned soon. Decommissioning normally takes the facility permanently out of service and subjects it to progressive hazard reduction, dismantling and decontamination in a safe, secure economically viable way, using best practicable means to meet the best practicable environmental option, such that the risks and doses to workers and the general public are maintained as low as reasonably practicable. Whilst most decommissioning techniques are well established there are still some challenging and important issues that need resolution. Perhaps the most challenging issue is radioactive waste management and storage. It is vitally important that all local and national waste classification, transportation, storage and end point requirements are known, as the adopted strategy will be heavily influenced by these factors. Other equally important but softer issues include the requirement for early decommissioning plans, adequate funding/cost estimates and the involvement of all relevant stakeholders. A comprehensive decommissioning plan should be produced up front that encompasses an early radiological characterisation survey of the facility/site. An appropriate funding mechanism needs to be assured. Whilst regular revisions of the decommissioning cost study should help to determine required funds, it is important to validate these cost estimates by benchmarking other decommissioning projects and accumulated experience. The use of appropriate 'stakeholder dialogue' methods by the facility operator to inform and communicate with all interested parties, such as government and non-government organisations, regulators, trades unions, anti

  19. Decommissioning: an insurance perspective

    The nuclear insurance pools, through American Nuclear Insurers (ANI) and the Mutual Atomic Energy Liability Underwriters (MAELU), have been providing third-party nuclear liability insurance to the nuclear industry since 1957. Third-party liability and property damage coverage resulting from the nuclear hazard are provided by separate insurance policies issued by the nuclear insurance pools. A liability insurer's view of decommissioning is addressed by discussing the following: insurer's perspective of potential nuclear liability; insurance claim experience and trends; objectives and accomplishments of ANI/MAELU's involvement with facility decommissioning; and important nuclear liability considerations for facility decommissioning

  20. Decommissioning nuclear facilities

    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)

  1. Safety Assessment for Decommissioning

    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

  2. Decommissioning Russian Research Facilities

    Gosatomnadzor of Russia is conducting the safety regulation and inspection activity related to nuclear and radiation safety of nuclear research facilities (RR), including research reactors, critical assemblies and sub-critical assemblies. Most of the Russian RR were built and put in operation more than 30 years ago. The problems of ageing equipment and strengthening of safety requirements in time, the lack of further experimental programmes and financial resources, have created a condition when some of the RR were forced to take decisions on their decommissioning. The result of these problems was reflected in reducing the number of RR from 113 in 1998 to 81 in the current year. At present, seven RR are already under decommissioning or pending it. Last year, the Ministry of Atomic Energy took the decision to finally shut down two remaining actual research reactors in the Physics and Power Engineering Institute in Obninsk: AM-1, the first reactor in the world built for peaceful purposes, graphite-type reactor, and the fast liquid metal reactor BR-10, and to start their preparation for decommissioning. It is not enough just to declare the decommissioning of a RR: it is also vital to find financial resources for that purpose. For this reason, due to lack of financing, the MR reactor at the Kurchatov Institute has been pending decommissioning since 1992 and still is. The other example of long-lasting decommissioning is TVR, a heavy water reactor at the Institute of Theoretical Physics in Moscow (ITEF). The reason is also poor financing. Another example discussed in the paper concerns on-site disposal of a RR located above the Arctic Pole Circle, owned by the Norilsk Mining Company. Furthermore, the experience of the plutonium reactor decommissioning at the Joint Institute of Nuclear Research is also discussed. As shown, the Russian Federation has had good experiences in the decommissioning of nuclear research facilities. (author)

  3. Decommissioning and Decontamination

    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

  4. Decommissioning of commercial reactor

    Yui, Kohei [Japan Atomic Power Co., Tokyo (Japan)

    1997-02-01

    In the case of nuclear reactors, the diversion is often difficult as they are highly purposive, the disassembling is not easy as they are robust, and attention is required to handle the equipment containing radioactive substances. Decommissioning is defined as all the measures taken from the state that facilities become unused to the state of becoming green field. In Japan, already 40 years have elapsed since the effort for nuclear power was begun, and in this paper, the present state and future subjects of the decommissioning of nuclear power stations are summarized at the opportunity that the stop of commercial operation of Tokai Nuclear Power Station was decided recently. In the Tokai Nuclear Power Station, 166 MWe graphite-moderated, carbon dioxide-cooled reactor called improved Calder Hall type is installed, which started the operation in 1966. The circumstances of the decision to stop its operation are explained. The basic policy of the decommissioning of commercial nuclear power stations has been already published by the Advisory Committee for Energy. The state of the decommissioning in various foreign countries is reported. In Japan, the state of green field was realized in 1996 in the decommissioning of the JPDR in Japan Atomic Energy Research institute, and the decommissioning of the atomic powered ship ``Mutsu`` was completed. (K.I.)

  5. Geophysical study of the Building 103 Dump, Aberdeen Proving Ground

    McGinnis, L.D.; Miller, S.F.; Thompson, M.D.; McGinnis, M.G.

    1992-12-01

    The Building 103 Dump is one of ten potentially contaminated sites in the Canal Creek and Westwood areas of the Edgewood section of Aberdeen Proving Ground examined by a geophysical team from Argonne National Laboratory in April and May of 1992. Noninvasive geophysical surveys, including magnetics, resistivity, ground-penetrating radar, and seismic refraction, were conducted. These surveys indicate that much of the area is free of debris. However, prominent magnetic and resistivity anomalies occur along well-defined lineaments, suggestive of a dendritic stream pattern. Prior to the onset of dumping, the site was described as a ``sand pit,`` which suggests that headward erosion of Canal Creek tributaries cut into the surficial aquifer. Contaminants dumped into the landfill would have direct access to the surficial aquifer and thus to Canal Creek. Seismic refraction profiling indicates 6--12 ft of fill material now rests on the former land surface. Only the northern third of the former landfill was geophysically surveyed.

  6. The decommissioning of nuclear facilities

    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

  7. Decommissioning of research reactors

    Research reactors of WWR-S type were built in countries under Soviet influence in '60, last century and consequently reached their service life. Decommissioning implies removal of all radioactive components, processing, conditioning and final disposal in full safety of all sources on site of radiological pollution. The WWR-S reactor at Bucuresti-Magurele was put into function in 1957 and operated until 1997 when it was stopped and put into conservation in view of decommissioning. Presented are three decommissioning variants: 1. Reactor shut-down for a long period (30-50 years) what would entail a substantial decrease of contamination with lower costs in dismantling, mechanical, chemical and physical processing followed by final disposal of the radioactive wastes. The drawback of this solution is the life prolongation of a non-productive nuclear unit requiring funds for personnel, control, maintenance, etc; 2. Decommissioning in a single stage what implies large funds for a immediate investment; 3. Extending the operation on a series of stages rather phased in time to allow a more convenient flow of funds and also to gather technical solutions, better than the present ones. This latter option seems to be optimal for the case of the WWR-S Research at Bucharest-Magurele Reactor. Equipment and technologies should be developed in order to ensure the technical background of the first operations of decommissioning: equipment for scarification, dismantling, dismemberment in a highly radioactive environment; cutting-to-pieces and disassembling technologies; decontamination modern technologies. Concomitantly, nuclear safety and quality assurance regulations and programmes, specific to decommissioning projects should be implemented, as well as a modern, coherent and reliable system of data acquisition, recording and storing. Also the impact of decommissioning must be thoroughly evaluated. The national team of specialists will be assisted by IAEA experts to ensure the

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

    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

  9. Decommissioning in western Europe

    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

  10. Financial aspects of decommissioning

    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)

  11. Decommissioning funding: ethics, implementation, uncertainties

    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)

  12. Decommissioning Peach Bottom Unit 1

    Decommissioning activities are described for Peach Bottom Unit No. 1, a 40 mw(e) HTGR demonstration plant owned and operated by the Philadelphia Electric Company. Radiological aspects of decommission are discussed. The application of advance planning and effective health physics techniques used during the Peach Bottom decommission program demonstrated the feasibility of decommissioning a nuclear facility economically at low personnel exposure levels and with a negligible environmental impact

  13. Tunney's Pasture decommissioning project

    AECL's Tunney's Pasture facility located in Ottawa was used for research, production and worldwide shipping of radioisotopes. After 30 years of operation, it was shut down in 1984, and decommissioned in two phases. During the first phase, which began in 1985 and lasted until 1987, staff moving to the new Kanata facility, now the property of Nordion International, removed the bulk of the equipment. After a three year period of storage under surveillance, AECL in 1990 initiated the second phase of decommissioning, which was completed in August 1993. In January 1994, the AECB unconditionally released the facility for unrestricted use. The paper provides an overview of the second phase of decommissioning, and a summary of a few lessons learned. 4 figs

  14. Site decommissioning management plan

    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.

  15. Site decommissioning management plan

    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

  16. Decommissioning licensing procedure

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

  17. Preparation for Ignalina NPP decommissioning

    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

  18. Platform decommissioning costs

    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

  19. Planning of MZFR decommissioning

    The concept chosen for decommissioning the MZFR reactor of plant components followed by the safe enclosure of the reactor building for about 30 years. It is intended that after lifting of the controlled areas the auxiliary building will be reused within the framework of KfK research projects. A decommissioning will be carried out in steps, the scope of licensing will be broken down into partial licences. It is expected that the last partial licence for safe enclosure will be granted in 1988. (orig.)

  20. Decommissioning of IFEC

    The IFEC nuclear fuel fabrication plant operated in Italy for more then thirty years and has now been successfully decommissioned. The rules and regulations relating to Quality Assurance established during the fabrication of Cirene reactor fuel have been adhered to during the decommissioning phase. The use of personnel with large experience in the nuclear field has resulted in vast majority of cares of material and apparatus to be reutilized in conventional activities without the need of calling on the assistance of external firms. The whole decontamination process was successfully completed on time and in particular the quantity of contaminated wastes was kept to eminimun

  1. Vinca nuclear decommissioning program

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

  2. Particle-accelerator decommissioning

    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

  3. Decontamination and decommissioning

    The project scope of work included the complete decontamination and decommissioning (D and D) of the Westinghouse ARD Fuel Laboratories at the Cheswick Site in the shortest possible time. This has been accomplished in the following four phases: (1) preparation of documents and necessary paperwork; packaging and shipping of all special nuclear materials in an acceptable form to a reprocessing agency; (2) decontamination of all facilities, glove boxes and equipment; loading of generated waste into bins, barrels and strong wooden boxes; (3) shipping of all bins, barrels and boxes containing waste to the designated burial site; removal of all utility services from the laboratories; and (4) final survey of remaining facilities and certification for nonrestricted use; preparation of final report. These four phases of work were conducted in accordance with applicable regulations for D and D of research facilities and applicable regulations for packaging, transportation, and burial and storage of radioactive materials. The final result is that the Advanced Fuel Laboratories now meet requirements of ANSI 13.12 and can be released for unrestricted use. The four principal documents utilized in the D and D of the Cheswick Site were: (1) Plan for Fully Decontaminating and Decommissioning, Revision 3; (2) Environmental Assessment for Decontaminating and Decommissioning the Westinghouse Advanced Reactors Division Plutonium Fuel Laboratories, Cheswick, Pa.; (3) WARD-386, Quality Assurance Program Description for Decontaminating and Decommissioning Activities; and (4) Health Physics, Fire Control, and Site Emergency Manual. These documents are provided as Attachments 1, 2, 3 and 4

  4. An air quality survey and emissions inventory at Aberdeen Harbour

    Marr, I. L.; Rosser, D. P.; Meneses, C. A.

    A network of 10 stations, with passive sampling for VOCs (including benzene), NO 2, and SO 2, over 2-week periods, grab sampling for CO, and 48-h pumped sampling for PM 10, was set up to make an air quality survey for 12 months around Aberdeen Harbour. Benzene, CO, SO 2 and PM 10 were always well below the AQS target values. However, NO 2 frequently showed a pronounced gradient across the harbour reaching its highest concentrations at the city end, indicating that the road traffic was the principal source of the pollution. This was backed up by the predominance of aromatics in the VOCs in the city centre, derived from petrol engined vehicles, compared to the predominance of alkanes and alkenes around the docks, derived from diesel engined heavy trucks and possibly ships. Black carbon on the PM 10 filters also showed a gradient with highest levels in the city centre. It is proposed that for such surveys in future, NO 2 and black carbon would be the two most informative parameters. This emissions inventory has shown first, that trucks contribute very little to the total, and second, that the ro-ro ferries are the major contributors as they burn light fuel oil while the oil platform supply vessels burn low-sulphur marine gas oil with around 0.1% S. When the whole picture of the emissions from the city is considered, the emissions from the harbour constitute only a small part.

  5. Environmental geophysics at Beach Point, Aberdeen Proving Ground, Maryland

    McGinnis, L.D.; Daudt, C.R.; Thompson, M.D.; Miller, S.F. [Argonne National Lab., IL (United States). Reclamation Engineering and Geosciences Section; Mandell, W.A. [Jacobs Engineering Group, Inc., Washington, DC (United States); Wrobel, J. [Dept. of Defense, Aberdeen Proving Ground, MD (United States)

    1994-07-01

    Geophysical studies at Beach Point Peninsula, in the Edgewood area of Aberdeen Proving Ground, Maryland, provide diagnostic signatures of the hydrogeologic framework and possible contaminant pathways. These studies permit construction of the most reasonable scenario linking dense, nonaqueous-phase liquid contaminants introduced at the surface with their pathway through the surficial aquifer. Subsurface geology and contaminant presence were identified by drilling, outcrop mapping, and groundwater sampling and analyses. Suspected sources of near-surface contaminants were defined by magnetic and conductivity measurements. Negative conductivity anomalies may be associated with unlined trenches. Positive magnetic and conductivity anomalies outline suspected tanks and pipes. The anomalies of greatest concern are those spatially associated with a concrete slab that formerly supported a mobile clothing impregnating plant. Resistivity and conductivity profiling and depth soundings were used to identify an electrical anomaly extending through the surficial aquifer to the basal pleistocene unconformity, which was mapped by using seismic reflection methods. The anomaly may be representative of a contaminant plume connected to surficial sources. Major activities in the area included liquid rocket fuel tests, rocket fuel fire suppression tests, pyrotechnic material and smoke generator tests, and the use of solvents at a mobile clothing impregnating plant.

  6. Depleted uranium risk assessment at Aberdeen Proving Ground

    The Environmental Science Group at Los Alamos and the Test and Evaluation Command (TECOM) are assessing the risk of depleted uranium (DU) testing at Aberdeen Proving Ground (APG). Conceptual and mathematical models of DU transfer through the APG ecosystem have been developed in order to show the mechanisms by which DU migrates or remains unavailable to different flora and fauna and to humans. The models incorporate actual rates of DU transfer between different ecosystem components as much as possible. Availability of data on DU transport through different pathways is scarce and constrains some of the transfer rates that can be used. Estimates of transfer rates were derived from literature sources and used in the mass-transfer models when actual transfer rates were unavailable. Objectives for this risk assessment are (1) to assess if DU transports away from impact areas; (2) to estimate how much, if any, DU migrates into Chesapeake Bay; (3) to determine if there are appreciable risks to the ecosystems due to DU testing; (4) to estimate the risk to human health as a result of DU testing

  7. CNEA decommissioning program

    Full text: According to chapter I, Art. 2.e of the National Law Nr. 24804 ruling nuclear activities in Argentina, CNEA is responsible for determining the procedure for decommissioning Nuclear Power Plants and any other relevant radioactive facilities'. The implementation the Nuclear Law, states that CNEA is responsible for deactivation and decommissioning of all relevant radioactive facilities in the country, at end of life. Consequently CNEA have created the D and D Branch in order to perform this activity. It is important point out that none of the 28 nuclear installations in Argentina is undergoing decommissioning. Nevertheless planning stages prior decommissioning have been started with the criterion of prioritising those that will probably generate the greatest volume of radioactive waste. Decommissioning plan for research reactors and Atucha I Nuclear Power Plant, radiological characterization, decontamination and treatment of miscellaneous equipment and components of the Atucha I Nuclear Power Plant and old installations are being carry out. The main task is to get the technical capability of the steps which must be followed. In order to accomplish this objective the main activities are: a) Coordinates the training of personnel and organizes the experience and technical knowledge already existing in CNEA and members of the Argentinean nuclear sector; b) Coordinates a R and D program on D and D technologies; c) Establishes close links with the operators of nuclear facilities, whose participation both in planning and in actual D and D work is considered extremely important; d)Preliminary planning and radiological characterization of significant nuclear installations. This paper summarizes general aspects of the activities which are currently in progress. (author)

  8. Decommissioning of offshore installations

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

    2010-07-01

    New legislation on the handling and storage of radioactive substances came into force 1 January 2011. This version of the report is updated to reflect this new regulation and will therefore in some chapters differ from the Norwegian version (see NEI-NO--1660). The Ministry of the Environment commissioned the Climate and Pollution Agency to examine the environmental impacts associated with the decommissioning of offshore installations (demolition and recycling). This has involved an assessment of the volumes and types of waste material and of decommissioning capacity in Norway now and in the future. This report also presents proposals for measures and instruments to address environmental and other concerns that arise in connection with the decommissioning of offshore installations. At present, Norway has four decommissioning facilities for offshore installations, three of which are currently involved in decommissioning projects. Waste treatment plants of this kind are required to hold permits under the Pollution Control Act. The permit system allows the pollution control authority to tailor the requirements in a specific permit by evaluating conditions and limits for releases of pollutants on a case-to-case basis, and the Act also provides for requirements to be tightened up in line with the development of best available techniques (BAT). The environmental risks posed by decommissioning facilities are much the same as those from process industries and other waste treatment plants that are regulated by means of individual permits. Strict requirements are intended to ensure that environmental and health concerns are taken into account. The review of the four Norwegian decommissioning facilities in connection with this report shows that the degree to which requirements need to be tightened up varies from one facility to another. The permit for the Vats yard is newest and contains the strictest conditions. The Climate and Pollution Agency recommends a number of measures

  9. Environmental geophysics at J-Field, Aberdeen Proving Ground, Maryland

    Daudt, C.R.; McGinnis, L.D.; Miller, S.F.; Thompson, M.D.

    1994-11-01

    Geophysical data collected at J-Field, Aberdeen Proving Ground, Maryland, were used in the characterization of the natural hydrogeologic framework of the J-Field area and in the identification of buried disturbances (trenches and other evidences of contamination). Seismic refraction and reflection data and electrical resistivity data have aided in the characterization of the leaky confining unit at the base of the surficial aquifer (designated Unit B of the Tertiary Talbot Formation). Excellent reflectors have been observed for both upper and lower surfaces of Unit B that correspond to stratigraphic units observed in boreholes and on gamma logs. Elevation maps of both surfaces and an isopach map of Unit B, created from reflection data at the toxic burning pits site, show a thickening of Unit B to the east. Abnormally low seismic compressional-wave velocities suggest that Unit B consists of gassy sediments whose gases are not being flushed by upward or downward moving groundwater. The presence of gases suggests that Unit B serves as an efficient aquitard that should not be penetrated by drilling or other activities. Electromagnetic, total-intensity magnetic, and ground-penetrating radar surveys have aided in delineating the limits of two buried trenches, the VX burning pit and the liquid smoke disposal pit, both located at the toxic burning pits site. The techniques have also aided in determining the extent of several other disturbed areas where soils and materials were pushed out of disposal pits during trenching activities. Surveys conducted from the Prototype Building west to the Gunpowder River did not reveal any buried trenches.

  10. High resolution seismic reflection profiling at Aberdeen Proving Grounds, Maryland

    The effectiveness of shallow high resolution seismic reflection (i.e., resolution potential) to image geologic interfaces between about 70 and 750 ft at the Aberdeen Proving Grounds, Maryland (APG), appears to vary locally with the geometric complexity of the unconsolidated sediments that overlay crystalline bedrock. The bedrock surface (which represents the primary geologic target of this study) was imaged at each of three test areas on walkaway noise tests and CDP (common depth point) stacked data. Proven high resolution techniques were used to design and acquire data on this survey. Feasibility of the technique and minimum acquisition requirements were determined through evaluation and correlation of walkaway noise tests, CDP survey lines, and a downhole velocity check shot survey. Data processing and analysis revealed several critical attributes of shallow seismic data from APG that need careful consideration and compensation on reflection data sets. This survey determined: (1) the feasibility of the technique, (2) the resolution potential (both horizontal and vertical) of the technique, (3) the optimum source for this site, (4) the optimum acquisition geometries, (5) general processing flow, and (6) a basic idea of the acoustic variability across this site. Source testing involved an accelerated weight drop, land air gun, downhole black powder charge, sledge hammer/plate, and high frequency vibrator. Shallow seismic reflection profiles provided for a more detailed picture of the geometric complexity and variability of the distinct clay sequences (aquatards), previously inferred from drilling to be present, based on sparse drill holes and basewide conceptual models. The seismic data also reveal a clear explanation for the difficulties previously noted in correlating individual, borehole-identified sand or clay units over even short distances

  11. Decommissioning and decontamination studies

    The decommissioning of retired Hanford facilities requires careful consideration of environmentally-related factors. Applicable ecology programs have been designed to: develop the technology associated with burial ground stabilization, thereby minimizing biotic access and transport of radioactive wastes and, characterize present 300 Area burial grounds to ascertain the potential biotic transport of waste materials away from managed facilities. Results are reported from studies on the role of plants, small mammals, and ants as potential transport vectors of radionuclides from radioactive waste burial grounds

  12. Fort St. Vrain decommissioning project

    Public Service Company of Colorado (PSCo), owner of the Fort St. Vrain nuclear generating station, achieved its final decommissioning goal on August 5, 1997 when the Nuclear Regulatory Commission terminated the Part 50 reactor license. PSCo pioneered and completed the world's first successful decommissioning of a commercial nuclear power plant after many years of operation. In August 1989, PSCo decided to permanently shutdown the reactor and proceed with its decommissioning. The decision to proceed with early dismantlement as the appropriate decommissioning method proved wise for all stake holders - present and future - by mitigating potential environmental impacts and reducing financial risks to company shareholders, customers, employees, neighboring communities and regulators. We believe that PSCo's decommissioning process set an exemplary standard for the world's nuclear industry and provided leadership, innovation, advancement and distinguished contributions to other decommissioning efforts throughout the world. (author)

  13. Decommissioning of nuclear submarines

    The intention of this Report is to set out in simple terms the options open to the Ministry of Defence in disposing of nuclear submarines, and the extent of the problem. To this end oral evidence was taken from United Kingdom Nirex Limited (Nirex) and from the Ministry of Defence, and written evidence was taken from MoD, Nirex, the United Kingdom Atomic Energy Authority and Rolls-Royce and Associates Limited. The immediate problem is what to do with the nuclear submarine, DREADNOUGHT. Since decommissioning in 1982, the submarine has been lying at Rosyth Naval Base on the Firth of Forth. Upon decommissioning, the highly radioactive reactor core with the uranium fuel was removed and transported to the Sellafield reprocessing plant. The remaining radioactive part is the reactor compartment and it is the size of this, not its level of radioactivity which makes it hard to deal with. By the year 2000 a further seven nuclear submarines will have been decommissioned. There are three main options for disposing of the reactor compartments; dumping at sea, land burial in a shallow trench and land burial in a deep repository. Dumping at sea is the option favoured by the Ministry of Defence and Government, but shallow land burial remains an option. Deep burial is not an option which is available immediately as there will not be a repository ready until 2005. (author)

  14. Tokai-1 decommissioning project

    Tokai-1 (GCR, Gas Cooled Reactor) nuclear power plant of JAPC (the Japan Atomic Power Company) started commercial operation in 1966 as the first commercial nuclear power plant in Japan. The unit had helped introduction and establishment of the construction and operation technologies regarding nuclear power plant at early stage in Japan by its construction and operating experiences. However, The Japan Atomic Power Company (JAPC), the operator and owner of Tokai-1, decided to cease its operation permanently because of a fulfillment of its mission and economical reason. The unit was finally shut down in March 1998 after about 32 year operation. It took about three years for removal of all spent fuels from the site, and then decommissioning started in 2001. JAPC, always on the forefront of the nation's nuclear power generation, is now grappling Japan's first decommissioning of a commercial nuclear power plant, striving to establish effective, advanced decommissioning. The decommissioning for Tokai-1 was scheduled as 20 years project. At the beginning, the reactor was started to be in a static condition ('safe storage period'). While the reactor had been safely stored, the phased decommissioning works started from non-radioactive or low radioactive equipment toward high radioactive equipment. First five years of the project, JAPC concentrated to drain and clean spent fuel cartridge cooling pond and to remove conventional equipments such as turbine, feed water pump and fuel charge machine as planed and budgeted. From 2006, the project came into a new phase. JAPC has been trying to remove four Steam Raising Units (SRUs). The SRUs are huge component (750ton, φ6.3m, H24.7m) of the Gas Cooling Reactor (GCR) and inside of the SRUs are radioactively contaminated. Major concerns are workers safety and minimizing contamination areas during SRU removal. Therefore, JAPC is developing and introducing Jack-down method and remote control multi-functional dismantling system. This

  15. Shivers Junior/Senior High School: Aberdeen School District in Mississippi. Case Study in Sustainable Design.

    Zimmerman, David

    Design information, floor plan, photos, and energy use data are presented of a combined 45,000 square foot junior/senior high school in Mississippi's Aberdeen School District, built in 1956, and retrofitted over time to improve its usability. Exterior and interior photos are presented showing classrooms, the cafeteria, and gymnasium. Data are…

  16. Decommissioning of Radiotherapy Facilities

    Radiotherapy units containing high activity sealed radioactive sources of 60Co or 137Cs are mainly use for medical, research or calibration applications. After several half-lives of decay, the radionuclide source has to be changed or the unit is decommissioned if no longer required. Before starting a decommissioning project it is very important to look for documents relating to any sources held or installed in equipment. In general this should be no problem because the recommended working life of such sealed radioactive sources is limited to 10 or a maximum of 15 years. These time periods are short in comparison with other facilities like research laboratories or small reactors. These documents (source certificates) will be very helpful to plan the decommissioning because they say everything about the original activity of the source at a reference date, the type of the source and the manufacturer. The next step may be to contact the machine supplier or the source manufacturer, but be aware that neither may still be in existence or may have changed their type of business. In such cases, it is recommended to contact national or international sealed source manufacturers or suppliers for help. Sometimes it is also helpful to contact colleagues in other hospitals or research centres to ask for information about specialists in this topic. In general it is not useful, and even very dangerous, to try to decommission such a unit without expert help It is essential to have specialist tools and shielded containers to recover the source out of the unit. It is strongly recommended to invite the source removal specialist for a site visit to review the situation before starting any decommissioning process. A further problem can occur, if the source must be transported to a national storage centre or even an international storage facility, as the source must be packaged to meet international transport requirements. The end state of such a project should be an empty room where the

  17. ORNL decontamination and decommissioning program

    A program has been initiated at ORNL to decontaminate and decommission surplus or abandoned nuclear facilities. Program planning and technical studies have been performed by UCC-ND Engineering. A feasibility study for decommissioning the Metal Recovery Facility, a fuel reprocessing pilot plant, has been completed

  18. BNFL decommissioning strategy and techniques

    This paper provides an overview of the range of reactor decommissioning projects being managed by BNFL, both on its own sites and for other client organizations in the UK and abroad. It also describes the decommissioning strategies and techniques that have been developed by BNFL and adopted in order to carry out this work

  19. Workshop on decommissioning; Seminarium om avveckling

    Broden, K. (ed.)

    2005-12-15

    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)

  20. Decommissioning policy in Sweden

    In Sweden the nuclear power program is, according to a parliamentary decision, limited to twelve power producing reactors. The last reactor shall be taken out of service no later than the year 2010. As a result of the Chernobyl accident the program for taking the reactors out of service will be accelerated. This report is the first approach by the Swedish authorities to formulate a decommissioning policy. It is not the final policy document but it discusses the principal questions from the special Swedish viewpoint. (orig.)

  1. Managing the Unexpected in Decommissioning

    This publication explores the implications of decommissioning in the light of unexpected events and the trade-off between activities to reduce them and factors militating against any such extra work. It classifies and sets out some instances where unexpected findings in a decommissioning programme led to a need to either stop, or reconsider the work, re-think the options, or move forward on a different path. It provides practical guidance in planning and management of decommissioning taking into account unexpected events. This guidance includes an evaluation of the experience and lessons learned in tackling decommissioning that is often neglected. Thus it will enable future decommissioning teams to adopt the relevant lessons to reduce additional costs, time delays and radiation exposures

  2. Decommissioning Funding: Ethics, Implementation, Uncertainties

    This status report on decommissioning funding: ethics, implementation, uncertainties is based on a review of recent literature and materials presented at NEA meetings in 2003 and 2004, and particularly at a topical session organised in November 2004 on funding issues associated with the decommissioning of nuclear power facilities. The report also draws on the experience of the NEA Working Party on Decommissioning and Dismantling (WPDD). This 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

  3. Financing nuclear power plant decommissioning

    Much is at stake in developing a financial strategy for decommissioning nuclear power plants. Since decommissioning experience is limited to relatively small reactors, will the costs associated with larger reactors be significantly higher. Certainly the decommissioning issue intersects with other critical issues that will help to determine the future of commercial nuclear power in the US. The author examines briefly the basic concepts and terms related to decommissioning expenses, namely: (1) segregated fund; (2) non-segregated fund; (3) external method; and (4) internal method. He concludes that state regulatory commissions have turned increasingly to the external funding method because of increasing costs and related problems associated with nuclear power, changing conditions and uncertainties concerned with utility restructuring, and recent changes in federal tax laws related to decommissioning. Further, this trend is likely to continue if financial assurance remains a primary concern of regulators to protect this public interest

  4. Decommissioning of VHTRC

    JAERI modified the Semi-Homogeneous Experimental Critical Assembly (SHE) which had been used for reactor physical experiments of graphite moderated reactor since January 1961 to the Very High Temperature Reactor Critical Assembly (VHTRC) in 1985 in order to carry out nuclear safety evaluation etc. for the High Temperature Engineering Test Reactor (HTTR). Since HTTR, which was constructed in the Oarai Research Establishment, achieved criticality in November 1998, JAERI decided to decommissioning VHTRC in 1999. The decommissioning project is planned to perform in two stages. At the first stage sampling and analysis were carried out for comparison of calculated results. Following these activities, reactor instruments, reactor control system and reactor itself were dismantled. The first stage was completed in FY2000. At the second stage, radiation shielding blocks and reactor building will be dismantled completely to green field conditions. These activities will be carried out after the clearance level is legislated in Japan. The first stage activities, which are the site characterization, radioactive inventory evaluation, surface contamination measurements for releasing the control room and the machine room from radiation controlled area to unrestricted area, neutron activation estimation on the basis of theoretical calculations, sampling and analyses of reactor components, and dismantling of reactor etc., are described in this report. (author)

  5. Criteria for decommissioning

    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

  6. Funding Decommissioning - UK Experience

    'Funding' started with CEGB and SSEB (state-owned electric utilities) in 1976 using the internal un-segregated fund route (i.e unfunded). This continued until privatisation of electricity industry (excluding nuclear) in 1990. Assets bought with the internal un-segregated fund were mostly transferred into non-nuclear private utilities. New state-owned Nuclear Electric (England and Wales) was given a 'Fossil Fuel Levy', a consumer charge of 10% on retail bills, amounting to c. BP 1 bn. annually. This allowed Nuclear Electric to trade legally (A reserve of BP 2.5 bn. was available from Government if company ran out of money). By 1996 the newer nuclear stations (AGRS plus PWR) were privatised as British Energy. British Energy started an external segregated fund, the Nuclear Decommissioning Fund, with a starting endowment of c. BP 225 m. - and BE made annual contributions of British Pound 16 m. into the Fund. Assumptions were that BE had 70 to accumulate cash and could get a 3.5% average annual real return. Older stations (Magnox) were left in private sector and went to BNFL in 1997. Magnox inherited the surplus cash in BE - mostly unspent Fossil Fuel Levy receipts - of c. BP 2.6 bn. Government gave an 'Undertaking' to pay BP 3.8 bn. (escalating at 4.5% real annually) for Magnox liabilities, should Magnox Electric run out of cash. BNFL inherited the BP 2.6 bn. and by 2000 had a 'Nuclear Liabilities Investment Portfolio' of c. BP 4 bn. This was a quasi-segregated internal fund for liabilities in general. [Note: overall UK nuclear liabilities in civilian sector were running at c. BP 48 bn. by now]. BE started profitable and paid BP 100 m. annually in dividends to private investors for several years. BE ran into severe financial problems after 2001 and Government organised restructuring aid, now approved by European Commission. Terms include: - BE now to contribute BP 20 m. a year into an expanded Nuclear Liabilities Fund; - A bond issue of BP 275 m. to go to Fund; - 65

  7. Evaluation of Nuclear Facility Decommissioning Projects program

    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

  8. Planning for decommissioning of Hifar

    The Australian Nuclear Science and Technology Organisation (ANSTO) has operated the 10MW HIFAR research reactor since 1958. In addition to its role in research, the reactor provides radioisotopes for medical and industrial use and is a major supplier of NTD silicon for the semi-conductor industry. It is anticipated that HIFAR will finally shut down operations in December 2006. Although ANSTO has successfully decommissioned MOATA and undertaken other smaller decommissioning projects the proposed HIFAR decommissioning project will be the largest ever undertaken by ANSTO. ANSTO faces a number of challenges in HIFAR's final year of operation. These include: the establishment of a modern decommissioning strategy in the absence of a long-term nuclear waste repository management facility or waste acceptance criteria for the material generated by the decommissioning; the impact of the impeding closure of the facility on staff morale and retention of key staff; and to meet the our customer's needs up to the final closure. These challenges are compounded by competition for skilled resources required to commission the new research reactor (OPAL) and the need to continue to supply radioisotopes. Important 'lessons in progress' that will be discussed in this paper include staffing the decommissioning team, maintenance of a strong safety culture during final stages of operation, working towards regulatory approval for decommissioning and strategies for knowledge retention. (author)

  9. Technologies for nuclear plant decommissioning

    After the commercial operation of a nuclear power plant has been shutdown, the plant enters a decommissioning phase where it is dismantled and removed. The Tokai Power Station was shutdown at the end of March 1998, followed by 'Fugen' and a light water reactor. The number of decommissioned plants in Japan is likely to increase in the future. Based on experience gained from the construction and maintenance of nuclear plants, Fuji Electric has developed techniques essential for decommissioning work. This paper describes recent technologies developed in this field, such as remote dismantling techniques for the reactor core and treatment and disposal techniques for the dismantled waste. (author)

  10. Progress of JPDR decommissioning project

    The Japan Power Demonstration Reactor (JPDR) decommissioning project is progressively achieving its final goal; the project will be finished by March 1996 to release the JPDR's site into unrestricted use in a green field condition. The new techniques which developed or improved in R and D, the first phase of this program, have been successfully applied to the actual dismantling activities. Some decommissioning wastes have been managed as the first case of onsite shallow land burial based on the new regulatory frame of radioactive waste management. The experiences and the data obtained from the JPDR dismantling activities are expected to contribute to future decommissioning of commercial nuclear power plants. (author)

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

    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.

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

    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

  13. Power Plant decommissioning

    Mažeika Jonas

    2014-11-01

    Full Text Available On a first attempt, the determination of 14C and 36Cl activity concentrations in basic operational waste (spent ion-exchange resins and perlite mixture, in decommissioning waste (construction concrete, sand, stainless steel and serpentinite and irradiated graphite from the Ignalina NPP has been performed. The samples for measurement of the specific activity of 14C and 36Cl were obtained from the selected places, where the highest values of the dose rate and the activity concentrations of gamma emitters were found. The performed study of the total 14C and 36Cl activity concentrations was based on estimated chemical forms of 14C (inorganic and organic compounds and 36Cl as Cl- ion. The tested methods used in this study were found to be suitable for estimation of activity concentrations of measured radionuclides.

  14. Decommissioning Cost Assessment

    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

  15. Decontamination & decommissioning focus area

    NONE

    1996-08-01

    In January 1994, the US Department of Energy Office of Environmental Management (DOE EM) formally introduced its new approach to managing DOE`s environmental research and technology development activities. The goal of the new approach is to conduct research and development in critical areas of interest to DOE, utilizing the best talent in the Department and in the national science community. To facilitate this solutions-oriented approach, the Office of Science and Technology (EM-50, formerly the Office of Technology Development) formed five Focus AReas to stimulate the required basic research, development, and demonstration efforts to seek new, innovative cleanup methods. In February 1995, EM-50 selected the DOE Morgantown Energy Technology Center (METC) to lead implementation of one of these Focus Areas: the Decontamination and Decommissioning (D & D) Focus Area.

  16. Remedial investigation report for J-Field, Aberdeen Proving Ground, Maryland. Volume 3: Ecological risk assessment

    Hlohowskyj, I.; Hayse, J.; Kuperman, R.; Van Lonkhuyzen, R.

    2000-02-25

    The Environmental Management Division of the U.S. Army Aberdeen Proving Ground (APG), Maryland, is conducting a remedial investigation (RI) and feasibility study (FS) of the J-Field area at APG, pursuant to the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), as amended. As part of that activity, Argonne National Laboratory (ANL) conducted an ecological risk assessment (ERA) of the J-Field site. This report presents the results of that assessment.

  17. Remedial investigation report for J-Field, Aberdeen Proving Ground, Maryland. Volume 3: Ecological risk assessment

    The Environmental Management Division of the U.S. Army Aberdeen Proving Ground (APG), Maryland, is conducting a remedial investigation (RI) and feasibility study (FS) of the J-Field area at APG, pursuant to the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), as amended. As part of that activity, Argonne National Laboratory (ANL) conducted an ecological risk assessment (ERA) of the J-Field site. This report presents the results of that assessment

  18. Analysis of cosmic-ray-muon induced spallation neutrons in Aberdeen Tunnel experiment in Hong Kong

    Cui, Kexi; 崔科晰

    2014-01-01

    The muon-induced radioactive isotopes, especially neutrons, are dangerous background component for rare-event detection in underground experiments, like neutrino-less double-beta decay and dark matter search. Understanding these cosmogenic backgrounds is crucial for these experiments. An underground experiment aiming at measuring the cosmic-ray muons' flux and their neutron production yield in liquid scintillator through spallation process is being carried out in the Aberdeen Tunnel laborator...

  19. Improvising innovation in UK urban district heating: The convergence of social and environmental agendas in Aberdeen

    Research on district heating has focused on technical-economic appraisal of its contribution to energy and carbon saving in urban centres. There is however lack of analysis of political and social processes which govern its actual take up. This paper examines these processes through a case study of Aberdeen, Scotland. Interviews and documentary analysis are used to examine the 2002 development of Aberdeen Heat and Power (AHP), an independent energy services company (ESCo). Technical-economic feasibility was a necessary component of appraisal, but not sufficient to govern decision-making. In the UK centralised energy market, DH investment is unattractive to commercial investors, and local authorities lack capacity and expertise in energy provision. In Aberdeen, the politics of fuel poverty converged with climate politics, creating an a-typical willingness to innovate through improvisation. The welfare priority resulted in creation of a non-profit locally-owned ESCo, using cost- rather than market-based heat tariffs. AHP has developed three combined heat and power energy centres and heat networks, supplying 34 MWh/pa of heat. Carbon savings are estimated to be 45% in comparison with electric heating, and heating costs are reduced by a similar amount. The conclusion outlines potential policy improvements. - Highlights: • UK policy proposes district heating for urban low carbon heat. • Technical and economic feasibility are insufficient to drive take-up. • In Aberdeen convergence of social and environmental goals gave impetus to improvisation. • The resulting non-profit ESCo has three CHP and district heat networks, supplying 34 MWh of heat pa. • Carbon and cost savings are 45% in comparison with electric heating

  20. DECOM experience with decommissioning costing

    The OMEGA code has been used in numerous Slovak and international decommissioning planning and costing projects and in IAEA R and D projects and is continuously updated and upgraded. The next goal for the DECOM costing activities is to develop an universal and user-friendly ISDC costing tool accessible via internet - eOMEGA taking over the advantages of the long-term experience of DECOM and being in line with up-to date trends in decommissioning costing. DECOM members participate in international expert groups for further improvement of costing methodologies, such as the uncertainties, cost practices and cost peer reviews in decommissioning costing. DECOM members participate also in IAEA projects, expert missions and training courses related to decommissioning costing and planning. (authors)

  1. Decommissioning of the Loviisa NPP

    Imatran Voima Oy has revised the decommissioning plan for the Loviisa Nuclear Power Plant (Loviisa 1 and Loviisa 2) by the end of the year 1998. The thermal power of the power plant has been increased to 2x1500 MWth, and the life time has been designed to be extended to 45 years in the decommissioning plan. The decommissioning of the power plant is designed to begin in 2022 and it will be finished in 2048. The plan is based on immediate dismantlement (i.e. DECON) after the shut down of the power plant. Experienced plant personnel will still be available to lead the decommissioning work. Only the radioactive plant systems, components and structures will be dismantled and disposed of. Decommissioning wastes will be disposed into the underground disposal tunnels situating at the site in the depth of about 110 m. These tunnels are already partly ready for power plant wastes. The big and heavy reactor components, e.g. pressure vessels and steam generators, will be disposed of as such, without cutting them into smaller parts. This saves time and radiation doses. The total volume of decommissioning wastes is 14 800 m3, when packed in boxes. The manpower needed for decommissioning is about 2 800 manyears. The collective radiation dose for personnel is estimated to be about 9.2 manSv. The cost estimate of the decommissioning is about 1 117 million FIM. The spent fuel will be stored at the plant for 20 years after the shut down of the power plant. After that it will be transported from the site to the encapsulation plant for final disposal. (orig.)

  2. An outsider's view of decommissioning

    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)

  3. Decommissioning challenges - an industrial reality

    Sellafield Limited has undergone many transformations in previous years. The Nuclear Decommissioning Authority (NDA) has managed the site from April 2005, and a new Parent Body Organisation (PBO) is soon to be announced. In addition, it is an exciting time for the nuclear industry following the announcement of the UK government support new reactor builds. Should the site be selected for new build, the impact on Sellafield, its decommissioning program and economic impact on the local area can only be speculated at the current time. Every past, present and future decommissioning project at the Sellafield Limited site offers complex challenges, as each facility is unique. Specialist skills and experience must be engaged at pre-planned phases to result in a safe, efficient and successful decommissioning project. This paper provides an overview of a small selection of decommissioning projects, including examples of stakeholder engagement, plant and equipment dismantling using remote handling equipment and the application of innovative techniques and technologies. In addition, the final section provides a summary upon how future technologies required by the decommissioning projects are being assessed and developed. (authors)

  4. Money Related Decommissioning and Funding Decision Making

    '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

  5. Current international issues in decommissioning

    In 1999, the Italian Environmental Protection authorities (ANPA at that time) hosted in Rome a Nuclear Energy Agency (NEA) meeting on the Regulatory Aspects of Decommissioning. This 'stock-taking' conference heard views from regulatory authorities, the decommissioning industry, waste management organisations and other relevant industrial sectors (e.g. the scrap metal industry) regarding the issues and aspects of decommissioning that should be further addressed, particularly at an international level. From this conference, six issues of relevance were identified which, since that time, have been addressed within the framework of the NEA. These issues are: - Decommissioning policies and strategies; - Waste management and materials reuse considerations; - Authorised release of sites and facilities; - Securing long-term funding and responsibility; - Framework for safety regulation of decommissioning; - Research and development in decommissioning. The NEA has focused on the international aspects of these issues, and on the roles of national governments in addressing the national and international aspects of these issues. This paper will present an overview of the NEA's findings in these areas. Realizing that these issues are important to the work of other international organisations, the NEA has tried to assess and use as appropriate the work of others in discussing these issues. As such, a brief review of relevant work at other international organisations will be presented. Based on its work, and in order to further advance these issues, the NEA is planning a second workshop on the Regulatory Aspects of Decommissioning, which will again be hosted by the Italian authorities in Rome, and will be held during the second half of 2004. (author)

  6. The Tokai NPP decommissioning technique

    Tokai power station was closed down in March 1998 and started decommissioning from December 2001 as a pioneer of NPP decommissioning. This article presented current state of Tokai NPP decommissioning technique. As the second stage of decommissioning works, removal works of steam raising unit (four units of heat exchangers) were started from 2006 by jacking down method with decommissioning data accumulated. Each heat exchanger was divided into top head, seven 'tears' of shell and bottom head. Each 'tear' was out and separated into a cylinder, and then divided into two by remote-operated cutting equipment with manipulators for gas cutting and motor disk cutting under monitoring works by fixed and mobile cameras. Divided 'tear' was further cut into center baffle plate, heat transfer tubes and fine pieces of shell. Cutting works would produce radioactive fine particles, which were filtered by temporary ventilation equipment with exhaust fan and filters. Appropriate works using existing technique combined and their rationalization were important at this stage. (T. Tanaka)

  7. Costs of Decommissioning Nuclear Power Plants

    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)

  8. Phenix Decommissioning Project - Overview

    The first heading of your manuscript must be 'Introduction'. Phenix is the only remaining French fast breeder reactor after the shutdown of Superphenix (1999) and Rapsodie (1983). Phenix is located inside the Marcoule nuclear site along the Rhone river near Bagnols-sur-Ceze in southeastern France. Phenix is one of the facilities belonging the French Atomic Energy Commission (CEA) on the Marcoule site. It is a fast breeder reactor (FBR) developed at the end of the 1960's. that has been in operation since 1973 and was connected to the power grid in 1974. It is a second generation prototype developed while the first generation FBR, Rapsodie, was still in operation. Phenix is a 250 electrical MW power plant. During the first 20 years of operation, its main aim was to demonstrate the viability of sodium-cooled FBRs. Since the 1991 radioactive waste management act, Phenix has become an irradiation tool for the actinide transmutation program. To extend its operating life for 6 additional cycles, it was necessary to refurbish the plant; this involved major work performed from 1999 to 2003 at a total cost of about 250 M??. Today, with a realistic expectation, the final shutdown is planned for the beginning of 2009. The main objective of the Phenix dismantling project is to eliminate all the process equipment and clean all the building to remove all the radioactive zones. To reach this objective, three main hazards must be eliminated: Fuel (criticality hazard), Sodium, Radioactive equipment. The complexity of decommissioning a facility such as Phenix is increased by: - the lack of storage facility for high radioactive material, - the decision to treat all the radioactive sodium and sodium waste inside the plant, - the very high irradiation of the core structures due to the presence of cobalt alloys. On the other hand, Phenix plant is still under operating with a qualified staff and the radioactivity coming from structural activation is well known. After the final shutdown

  9. The Italian decommissioning industry

    Full text: Italy's step out from nuclear activities in 1987 deeply affected an industry that, in the previous years, had managed to grow up in quality and technology levels to meet the nuclear standards. Only a few companies were able to partially retain their skills through activities abroad. The decommissioning program represents a new challenge for the Italian industry at large and will require a consistent effort to properly qualify the potential suppliers. On the other side, a program with such implications in terms of investments and so depending from social aspects cannot be effectively implemented without a significant involvement of the local industry. Essential conditions for the success are a reliable program, as well as a careful supply management scheme, which must facilitate aggregation of skills spread among different subjects. 'Human Resources: Maintaining a Nuclear Culture in Italy' Bruno Panella Politecnico di Torino, Giuseppe Forasassi, Universita di Pisa, Inter-University Consortium for the Nuclear Technological Research (CIRTEN). After a brief history of the nuclear engineering education in Italy within the international and national nuclear energy scenario, the present situation, with reference to the Italian universities, is shown. In order to maintain a nuclear culture in Italy the solution, exploited with different peculiarities in each University, is to carry out high quality research activities in reciprocal collaboration (mostly within the CIRTEN inter university Consortium) as well as with the Industry and research Organisations and to collaborate actively in establishing a stable network and a synergy of teaching activities in Europe in the field of Nuclear Engineering Education. The aim is to maintain at a high level and as updated as possible the Italian educational offer in nuclear engineering and also to attract the best students for the enrolment. (author)

  10. Decommissioning: a problem or a challenge?

    Mele Irena

    2004-01-01

    With the ageing of nuclear facilities or the reduced interest in their further operation, a new set of problems, related to the decommissioning of these facilities, has come into forefront. In many cases it turns out that the preparations for decommissioning have come too late, and that financial resources for covering decommissioning activities have not been provided. To avoid such problems, future liailities should be thoroughly estimated in drawing up the decommissioning and waste manageme...

  11. 77 FR 41107 - Decommissioning Planning During Operations

    2012-07-12

    ... Decommissioning Planning Rule (DPR) (June 17, 2011, 76 FR 33512). The DPR applies to the operational phase of a..., ``Decommissioning Planning During Operations'' (December 13, 2011, 76 FR 77431). The NRC received more than 100..., Decommissioning and Uranium Recovery Licensing Directorate, Division of Waste Management and...

  12. Platform decommissioning. Environmental challenges and practical solutions

    The publication gives a short introduction of platform decommissioning, followed by an overview of what to be decommissioned and removed. This will be followed by some of the vital technologies and methods within decommissioning, abandonment of wells, removal and handling of remains that is reuse and scrapping. A final presentation with a view of current research and developments is given. 3 figs

  13. Development of decommissioning system engineering technology

    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

  14. Fort St. Vrain decommissioning experience

    Nuclear plant decommissioning represents a significant expenditure of time and resources for nuclear utilities. Public Service Company of Colorado (PSC) is in the process of completing the decommissioning of the Fort St. Vrain (FSV) Nuclear Station, the first large-scale commercial nuclear plant to be decommissioned under the U.S. Nuclear Regulatory Commission's (NRC's) 1988 decommissioning rule. PSC's experience has included dispositioning spent fuel, choosing a decommissioning alternative, and actively decommissioning the plant from dismantlement and decontamination through final survey. When the plant was prematurely shut down in August 1989, PSC's initial task was to find a storage location for FSV's spent fuel. PSC had a contract with the U.S. Department of Energy (DOE) to ship FSV spent fuel to the Idaho National Engineering Laboratory (INEL), and all previously removed spent fuel had been shipped there. However, Idaho legally blocked further FSV spent-fuel shipments to INEL, and PSC decided to license and build an on-site, passively cooled independent spent-fuel storage installation (ISFSI). By June 1992, all FSV spent fuel was transferred from the reactor building to the ISFSI. PSC has been able to use low-level radioactive waste (LLWR) disposal facilities in the Northwest Compact, and disposal costs are within estimates. Industrial and radiological safety have been emphasized throughout the project, and performance in these areas has been outstanding. PSC has obtained NRC Aprilproval of a final survey plan that allows for many of the plant's components and systems to remain in place, and final survey activities are nearing completion. PSC is in the process of repowering the facility with natural gas-fired combustion turbines and heat recovery boilers. The first combustion turbine was placed in service Ap 30, 1996

  15. Decommissioning Experience: Chalk River, Canada

    Full text: Atomic Energy of Canada Limited has reported that work has continued on the decommissioning of old structures on the Chalk River laboratory site. An environmental assessment was approved in 2006 for the decommissioning of the NRX reactor fuel bays (A and B). The regulator approved two work packages for the removal of water and the wooden structure over the bays. The A bays were cleaned as far as possible and were emptied in 2007. Decontamination work will continue. Sections of the B bays were filled with sand and other parts filled with water. NRX is currently in storage (i.e. a dormant state) with surveillance. (author)

  16. Decommissioning of uranium conversion plant

    Since about 20 years have passed after the construction of the uranium conversion plant, most equipments installed have worn out. Liquid wastes stored in lagoons which were generated during the operation of this plant are needed to be treated safely. Therefore, the decommissioning project on the uranium conversion plant was started from 2001. This study is a preliminary step for the decommissioning of the uranium conversion plant. It was reviewed on the plant status overall, especially facility descriptions and operational histories for the installations located inside and outside of the plant and methods of decontamination and of dismantling to the contamination conditions. And some proper options on each main object was proposed

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

    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.

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

    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

  19. Initial building investigations at Aberdeen Proving Ground, Maryland: Objectives and methodology

    Brubaker, K.L.; Dougherty, J.M.; McGinnis, L.D.

    1994-12-01

    As part of an environmental-contamination source-definition program at Aberdeen Proving Ground, detailed internal and external inspections of 23 potentially contaminated buildings are being conducted to describe and characterize the state of each building as it currently exists and to identify areas potentially contaminated with toxic or other hazardous substances. In addition, a detailed geophysical investigation is being conducted in the vicinity of each target building to locate and identify subsurface structures, associated with former building operations, that are potential sources of contamination. This report describes the objectives of the initial building inspections, including the geophysical investigations, and discusses the methodology that has been developed to achieve these objectives.

  20. Methods of power reactor decommissioning cost recovery

    This paper analyzes rate-regulatory tax, accounting and cost recovery factors, and these analyses lead to the following overall conclusions in connection with decommissioning cost recovery. 1) The internal use of accumulated decommissioning funds is strongly recommended because it results in the lowest net ratepayer cost of decommissioning, and 2) The most equitable decommissioning cost recovery method is based on current costs and on the prompt and continuous maintenance of the purchasing power of accumulated funds. Finally, it is noted that the cost recovery approach recommended for decommissioning would have similar advantage if applied to spent fuel cost recovery as well

  1. Decommissioning study of Forsmark NPP

    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.

  2. Decommissioning Study of Oskarshamn NPP

    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.

  3. 76 FR 35511 - Decommissioning Planning

    2011-06-17

    ... the January 27, 1988 (53 FR 24018), rule on planning for decommissioning require licensees to provide... regulations in 1997 as Subpart E of 10 CFR part 20 (62 FR 39058; July 21, 1997). This set of requirements is... contamination and the amount of funds set aside and expended on cleanup. (62 FR 39082; July 21, 1997)....

  4. Reactor decommissioning experience and perspectives

    This paper first describes the existing market context and available techniques, then reviews the contribution of past and present operations and research before discussing the future orientations necessary to develop the means (cutting tools, decontamination processes, telemanipulation and waste conditioning) required to improve the cost effectiveness of decommissioning nuclear power plants. (author)

  5. Decommissioning study of Forsmark NPP

    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

  6. Decommissioning Study of Oskarshamn NPP

    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

  7. Options for Steam Generator Decommissioning

    Selecting the best option for decommissioning steam generators is a key consideration in preparing for decommissioning PWR nuclear power plants. Steam Generators represent a discrete waste stream of large, complex items that can lend themselves to a variety of options for handling, treatment, recycling and disposal. Studsvik has significant experience in processing full size Steam Generators at its metal recycling facility in Sweden, and this paper will introduce the Studsvik steam generator treatment concept and the results achieved to date across a number of projects. The paper will outline the important parameters needed at an early stage to assess options and to help consider the balance between off-site and on-site treatment solutions, and the role of prior decontamination techniques. The paper also outlines the use of feasibility studies and demonstration projects that have been used to help customers prepare for decommissioning. The paper discusses physical, radiological and operational history data, Pro and Contra factors for on- and off-site treatment, the role of chemical decontamination prior to treatment, planning for off-site shipments as well as Studsvik experience This paper has an original focus upon the coming challenges of steam generator decommissioning and potential external treatment capacity constraints in the medium term. It also focuses on the potential during operations or initial shut-down to develop robust plans for steam generator management. (authors)

  8. Decommissioning of nuclear reactor systems

    The decision-making process involving the decommissioning of the British graphite-moderated, gas-cooled Magnox power stations is complex. There are timing, engineering, waste disposal, cost and lost generation capacity factors and the ultimate uptake of radiation dose to consider and, bearing on all of these, the overall decision of when and how to proceed with decommissioning may be heavily weighed by political and public tolerance dimensions. These factors and dimensions are briefly reviewed with reference to the ageing Magnox nuclear power stations, of which Berkeley and Hunterston A are now closed down and undergoing the first stages of decommissioning and Trawsfynydd, although still considered as available capacity, has had both reactors closed down since February 1991 and is awaiting substantiation and acceptance of a revised reactor pressure vessel safety case. Although the other first-generation Magnox power station at Hinkley Point, Bradwell, Dungeness and Sizewell are operational, it is most doubtful that these stations will be able to eke out a generating function for much longer. It is concluded that the British nuclear industry has adopted a policy of deferred decommissioning, that is delaying the process of complete dismantlement of the radioactive components and assemblies for at least one hundred years following close-down of the plant. (Author)

  9. A Decommissioning Information Management System

    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.

  10. Decommissioning: a problem or a challenge?

    Mele Irena

    2004-01-01

    Full Text Available With the ageing of nuclear facilities or the reduced interest in their further operation, a new set of problems, related to the decommissioning of these facilities, has come into forefront. In many cases it turns out that the preparations for decommissioning have come too late, and that financial resources for covering decommissioning activities have not been provided. To avoid such problems, future liailities should be thoroughly estimated in drawing up the decommissioning and waste management programme for each nuclear facility in time, and financial provisions for implementing such programme should be provided. In this paper a presentation of current decommissioning experience in Slovenia is given. The main problems and difficulties in decommissioning of the Žirovski Vrh Uranium Mine are exposed and the lesson learned from this case is presented. The preparation of the decommissioning programme for the Nuclear Power Plant Krško is also described, and the situation at the TRIGA research reactor is briefly discussed.

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

    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

  12. Nuclear decommissioning in Italy

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

  13. Ecological survey of M-Field, Edgewood Area Aberdeen Proving Ground, Maryland

    Downs, J.L.; Eberhardt, L.E.; Fitzner, R.E.; Rogers, L.E.

    1991-12-01

    An ecological survey was conducted on M-Field, at the Edgewood Area, Aberdeen Proving Ground, Maryland. M-Field is used routinely to test army smokes and obscurants, including brass flakes, carbon fibers, and fog oils. The field has been used for testing purposes for the past 40 years, but little documented history is available. Under current environmental regulations, the test field must be assessed periodically to document the presence or potential use of the area by threatened and endangered species. The M-Field area is approximately 370 acres and is part of the US Army`s Edgewood Area at Aberdeen Proving Ground in Harford County, Maryland. The grass-covered field is primarily lowlands with elevations from about 1.0 to 8 m above sea level, and several buildings and structures are present on the field. The ecological assessment of M-Field was conducted in three stages, beginning with a preliminary site visit in May to assess sampling requirements. Two field site visits were made June 3--7, and August 12--15, 1991, to identify the biota existing on the site. Data were gathered on vegetation, small mammals, invertebrates, birds, large mammals, amphibians, and reptiles.

  14. Ecological survey of M-Field, Edgewood Area Aberdeen Proving Ground, Maryland

    Downs, J.L.; Eberhardt, L.E.; Fitzner, R.E.; Rogers, L.E.

    1991-12-01

    An ecological survey was conducted on M-Field, at the Edgewood Area, Aberdeen Proving Ground, Maryland. M-Field is used routinely to test army smokes and obscurants, including brass flakes, carbon fibers, and fog oils. The field has been used for testing purposes for the past 40 years, but little documented history is available. Under current environmental regulations, the test field must be assessed periodically to document the presence or potential use of the area by threatened and endangered species. The M-Field area is approximately 370 acres and is part of the US Army's Edgewood Area at Aberdeen Proving Ground in Harford County, Maryland. The grass-covered field is primarily lowlands with elevations from about 1.0 to 8 m above sea level, and several buildings and structures are present on the field. The ecological assessment of M-Field was conducted in three stages, beginning with a preliminary site visit in May to assess sampling requirements. Two field site visits were made June 3--7, and August 12--15, 1991, to identify the biota existing on the site. Data were gathered on vegetation, small mammals, invertebrates, birds, large mammals, amphibians, and reptiles.

  15. Molecular Signature of the Ebola Virus Associated with the Fishermen Community Outbreak in Aberdeen, Sierra Leone, in February 2015

    Gruber, Cesare E. M.; Carletti, Fabrizio; Meschi, Silvia; Castilletti, Concetta; Vairo, Francesco; Biava, Mirella; Minosse, Claudia; Strada, Gino; Portella, Gina; Miccio, Rossella; Minardi, Valeria; Rolla, Luca; Kamara, Abdul; Chillemi, Giovanni; Desideri, Alessandro; Di Caro, Antonino; Ippolito, Giuseppe

    2015-01-01

    We report the complete genome sequence of Ebola virus from a health worker linked to a cluster of cases occurring in the fishing community of Aberdeen, Sierra Leone (February 2015), which were characterized by unusually severe presentation. The sequence, clustering in the SL subclade 3.2.4, harbors mutations potentially relevant for pathogenesis. PMID:26404609

  16. Considerations about the European Decommissioning Academy (EDA)

    According to analyses presented at EC meeting focused on decommissioning organized at 11.9.2012 in Brussels, it was stated that at least 500 new international experts for decommissioning will be needed in Europe up to 2025, which means about 35 per year.Having in mind the actual EHRO-N report from 2013 focused on operation of nuclear facilities and an assumption that the ratio between nuclear experts, nuclearized and nuclear aware people is comparable also for decommissioning (16:74:10), as well as the fact that the special study branch for decommissioning in the European countries almost does not exist, this European Decommissioning Academy (EDA) could be helpful in the overbridging this gap.For the first run of the EDA scheduled on 2014 we would like to focus on VVER decommissioning issues because this reactor type is the most distributed design in the world and many of these units are actually in decommissioning process or will be decommissioned in the near future in Europe.A graduate of the European Decommissioning Academy (EDA) should have at least bachelor level from technical or natural science Universities or Colleges and at least one year working experiences in the area of NPP decommissioning or nuclear power engineering. This study creates prerequisites for acquiring and completion of professional and specialized knowledge in the subjects which are described. (authors)

  17. Status of the NRC Decommissioning Program

    Orlando, D. A.; Camper, L.; Buckley, J.; Pogue, E.; Banovac, K.

    2003-02-24

    On July 21, 1997, the U.S. Nuclear Regulatory Commission (NRC) published the final rule on Radiological Criteria for License Termination (the License Termination Rule or LTR) as Subpart E to 10 CFR Part 20. NRC regulations require that materials licensees submit Decommissioning Plans to support the decommissioning of its facility if it is required by license condition, or if the procedures and activities necessary to carry out the decommissioning have not been approved by NRC and these procedures could increase the potential health and safety impacts to the workers or the public. NRC regulations also require that reactor licensees submit Post-shutdown Decommissioning Activities Reports and License Termination Plans to support the decommissioning of nuclear power facilities. This paper provides an update on the status of the NRC's decommissioning program that was presented during WM'02. It discusses the staff's current efforts to streamline the decommissioning process, current issues being faced in the decommissioning program, such as partial site release and restricted release of sites, as well as the status of the decommissioning of complex sites and those listed in the Site Decommissioning Management Plan. The paper discusses the status of permanently shut-down commercial power reactors and the transfer of complex decommissioning sites and sites listed on the SDMP to Agreement States. Finally the paper provides an update of the status of various tools and guidance the NRC is developing to assist licensees during decommissioning, including an effort to consolidate and risk-inform decommissioning guidance.

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

    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.

  19. Decommissioning of Salaspils Research Reactor

    The Salaspils Research Reactor (SRR) is out of operation since July 1998 and the decommissioning of SRR was started in 1999 according to the decision of the Government of Latvia. The main decommissioning activities up to 2006 were connected with collecting and conditioning of historical radioactive wastes from different storages outside and inside of reactor hall. The total amount of dismantled materials was about 700 tons, more than 77 tons were conditioned in concrete containers for disposal in repository. The radioactive wastes management technology is discussed in the paper. It was found, that additional efforts must be spent for immobilization of radionuclides in cemented matrix to be comply with the wastes acceptance criteria. The investigations of mechanical stability of water-cement matrix are described and discussed in the paper

  20. Integrated decommissioning management tools (IDMT)

    Full text: Nuclear Power Plant decommissioning requires a number of demolition activities related to civil works and systems as well as the construction of temporary facilities used for treatment and conditioning of the dismantled parts. The presence of a radiological, potentially hazardous, environment due to the specific configuration and history of the plant require a professional, expert and qualified approach approved by the national safety authority. Dismantling activities must be designed, planned and analysed in detail during an evaluation phase taking into account different scenarios generated by possible dismantling sequences and specific waste treatments to be implemented. The optimisation process of the activities becomes very challenging taking into account the requirement of the minimisation of the radiological impact on exposed workers and people during normal and accident conditions. While remote operated equipment, waste treatment and conditioning facilities may be designed taking into account this primary goal also a centralised management system and corresponding software tools have to be designed and operated in order to guarantee the fulfilment of the imposed limits as well as the traceability of wastes. Ansaldo Nuclear Division has been strongly involved in the development of a qualified and certified software environment to manage the most critical activities of a decommissioning project. The IDMT system (Integrated Decommissioning Management Tools) provide a set of stand alone user friendly applications able to work in an integrated configuration to guarantee waste identification, traceability during treatment and conditioning process as well as location and identification at the Final Repository site. Additionally, the system can be used to identify, analyse and compare different specific operating scenarios to be optimised in term of both economical and radiological considerations. The paper provides an overview of the different phases of

  1. IDMT, Integrated Decommissioning Management Tools

    Nuclear Power Plant decommissioning requires a number of demolition activities related to civil works and systems as well as the construction of temporary facilities used for treatment and conditioning of the dismantled parts. The presence of a radiological, potentially hazardous, environment due to the specific configuration and history of the plant require a professional, expert and qualified approach approved by the national safety authority. Dismantling activities must be designed, planned and analysed in detail during an evaluation phase taking into account different scenarios generated by possible dismantling sequences and specific waste treatments to be implemented. The optimisation process of the activities becomes very challenging taking into account the requirement of the minimisation of the radiological impact on exposed workers and people during normal and accident conditions. While remote operated equipment, waste treatment and conditioning facilities may be designed taking into account this primary goal also a centralised management system and corresponding software tools have to be designed and operated in order to guarantee the fulfilment of the imposed limits as well as the traceability of wastes. Ansaldo Nuclear Division has been strongly involved in the development of a qualified and certified software environment to manage the most critical activities of a decommissioning project. The IDMT system (Integrated Decommissioning Management Tools) provide a set of stand alone user friendly applications able to work in an integrated configuration to guarantee waste identification, traceability during treatment and conditioning process as well as location and identification at the Final Repository site. Additionally, the system can be used to identify, analyse and compare different specific operating scenarios to be optimised in term of both economical and radiological considerations. The paper provides an overview of the different phases of

  2. The decommissioning of Berkeley II

    This paper describes the decommissioning progress at the Magnox site at Berkeley in Gloucestershire.Throughout the work at Berkeley the emphasis has been on conducting decommissioning safely. This has been reflected in the progress of decommissioning starting with removal of the fuel from site and thus much greater than 99% of the radioactive inventory. The major radioactive hazard is the Intermediate Level Waste in the form of fuel element debris (graphite struts and extraneous magnox components removed to increase the packing density of fuel elements in flasks going to Sellafield), miscellaneous activated components, sludges and resins. Approximately 1500 m3 of such material exists and is stored in underground waste vaults on site. Work is underway to recover and encapsulate the waste in cement so rendering it 'passively safe'. All work on site is covered by a nuclear safety case which has a key objective of minimising the radiological exposures that could accrue to workers. Reflecting this an early decision has been taken to leave work on the Reactor Pressure Vessels themselves for several decades. Also important in protection of the workforce has been control of asbestos.Much material has been removed with redundant plant and equipment, but a programme of remediation in line with government legislation has been required to ensure personnel safety throughout the decommissioning period and into Care and Maintenance.In addition to health and safety matters the site approach to environmental issues has been consistent. Formally such standards as ISO 14001 have been adhered to and the appropriate certification maintained. At a working level the principles of reduce, reuse and recycle have been inculcated

  3. Residual activity criteria for decommissioning

    The U.S. Nuclear Regulatory Commission development of criteria for release of facilities and sites for unrestricted use following decommissioning is described. Residual activity limits for both materials and soil are covered. The objectives are: small risk of exposure, consistency with relevant existing standards, and feasibility of demonstration of compliance by measurement. Specific aspects discussed related to establishment of limits are: appropriate risk and dose limits, identification of radionuclides to be considered, dose assessment methodology, and confirmatory measurements

  4. Decommissioning - The keys to success

    The United Kingdom Atomic Energy Authority (UKAEA) owns and operates five sites across the United Kingdom. The Winfrith site in Dorset was established in the late 1950's as a centre for development of prototype reactors. During its history, nine research reactors have operated on the site together with: a fuel fabrication facility; a post irradiation examination facility; radiochemistry laboratories, etc. The largest reactor, a 100MWe Steam Generating Heavy Water Reactor, was closed down in 1990 and the last research reactor was closed in 1995. Since the early 1990's the site has been undergoing a programme of progressive decommissioning with a view to releasing the site for alternative use unrestricted by the site's nuclear history. Key drivers for the design of the programme were safety, minimising adverse environmental effects, minimising costs and ensuring stakeholder support. One requirement of the stakeholders was to ensure that the site continued to provide high quality employment. This was successfully achieved by developing a Science and Technology Park on the nuclear site. Over 40 companies are now located on the Park providing over 1000 jobs. This paper will focus on the lessons learnt from over a decade of experience of decommissioning at Winfrith and will attempt to identify the 'keys to successful decommissioning'. These 'keys' will include: defining the site end-point; planning the programme; defining the commercial strategy; cost estimation; evaluation and management of risks; safety and environmental management; and stakeholder engagement. In particular, the paper will explore the very close relationship between: funding profiles; cost estimation; risk management and commercial strategy. It will show that these aspects of the programme cannot be considered separately. The paper will attempt to show that, with careful planning; decommissioning can be achieved safety and give good value for money to the funding authority. (author)

  5. Decommissioning plans and activities in Slovenia

    With the ageing of nuclear facilities, or the reduced interest in their further operation, a new set of problems, related to the decommissioning of these facilities, has come into forefront. In many cases it turns out that the preparations for decommissioning have come too late, and that financial resources for covering decommissioning activities have not been provided. In this paper a presentation is given of current decommissioning experience in Slovenia. The main problems and difficulties in decommissioning of the Zirovski vrh Uranium Mine are exposed, and the lesson learned from this case is presented. The preparation of the decommissioning programme for the nuclear power plant Krsko is also described, and the situation at the TRIGA research reactor is briefly discussed. (author)

  6. Fort St. Vrain defueling ampersand decommissioning considerations

    Fort St. Vrain Nuclear Generating Station (FSV) is one of the first commercial reactors to be decommissioned under NRC's decommissioning rule. The defueling and decommissioning of this 330 MWe High Temperature Gas Cooled Reactor (HTGR) has involved many challenges for Public Service Company of Colorado (PSC) including defueling to an Independent Spent Fuel Storage Installation (ISFSI), establishing decommissioning funding, obtaining regulatory approvals, arranging for waste disposal, and managing a large fixed price decommissioning contract. In 1990, a team comprised of the Westinghouse Corporation and Morrison Knudsen Corporation, with the Scientific Ecology Group as a major subcontractor, was contracted by PSC to perform the decommissioning under a fixed price contract. Physical work activities began in August 1992. Currently, physical dismantlement activities are about 45% complete, the project is on schedule, and is within budget

  7. Nuclear decommissioning planning, execution and international experience

    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 ...

  8. Safety yields decommissioning successes. Panel Discussion

    Full text of publication follows: Panelists will speak to the most recent decommissioning projects successfully conducted. The projects represent facilities over the full range of commercial decommissioning, fuel storage, and weapons facilities. Lessons learned will be stressed to guide interested parties through future decommissioning activities. Human Factors Assessment of D and D Technologies and How This Relates to Improvement of Safety in Decommissioning Projects (Bruce Lippy (OENHP)); PPPL's Safety Practices, Safety Records, and Corrective Actions to Address Safety Issues (Keith Rule (PPPL)); INEEL's Safety Practices in Decommissioning Projects and Safety-Enhancing D and D Technologies (Richard Meservey (BWXT)); Big Rock Point Restoration Project Decommissioning Successes from a Safety Culture Perspective (William Trubilowicz (Consumers PWR, Big Rock Point))

  9. Decommissioning: a United Kingdom perspective

    The paper considers the United Kingdom legislative framework relevant to decommissioning of facilities on nuclear licensed sites. It describes the various legislative bodies involved in regulating this activity and the inspectorate concerned. The licensing regime is described in some detail highlighting the UK arrangements whereby a license is granted for the site upon which nuclear facilities are planned or exist. The license remains in place throughout the life of the plant on the site: from initial planning through to the end of decommissioning. A site (of part of) is not de-licensed until it can be stated that there has ceased to be any danger from ionising radiations from anything on the site (or appropriate part of the site). The final part of the paper considers the changes arising from the commercialization of the nuclear power industry in UK and the restatement of the Nuclear Installation Inspectorate's policy on decommissioning which has arisen as a result of a review made in response to these changes. (author)

  10. Decommissioning of naval nuclear ships

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

  11. Decommissioning: a United Kingdom perspective

    Haworth, A.; Reed, D.L.; Bleeze, A. [Health and Safety Executive, London (United Kingdom)

    1995-12-31

    The paper considers the United Kingdom legislative framework relevant to decommissioning of facilities on nuclear licensed sites. It describes the various legislative bodies involved in regulating this activity and the inspectorate concerned. The licensing regime is described in some detail highlighting the UK arrangements whereby a license is granted for the site upon which nuclear facilities are planned or exist. The license remains in place throughout the life of the plant on the site: from initial planning through to the end of decommissioning. A site (of part of) is not de-licensed until it can be stated that there has ceased to be any danger from ionising radiations from anything on the site (or appropriate part of the site). The final part of the paper considers the changes arising from the commercialization of the nuclear power industry in UK and the restatement of the Nuclear Installation Inspectorate`s policy on decommissioning which has arisen as a result of a review made in response to these changes. (author).

  12. Shippingport Station Decommissioning Project: overview and justification

    The purpose of this booklet is to brief the reader on the Shippingport Station Decommissioning Project and to summarize the benefits of funding the project in FY 1984. Background information on the station and the decommissioning project is provided in this section of the booklet; the need for a reactor decommissining demonstration is discussed in the next section; and a summary of how the Shippingport Station Decommissioning Project (SSDP) provides the needed demonstration is provided in the final section

  13. IAEA Perspectives on Preparation for Decommissioning

    There are about 160 power reactors in decommissioning phase worldwide. In addition, more than 400 other nuclear facilities, such as research reactors or nuclear fuel cycle facilities, have been shutdown for decommissioning, have been undergoing active decommissioning or have already been fully dismantled. Planned and systematic preparation for decommissioning is very important for further effective implementation of dismantling activities. While some preparatory activities for decommissioning start early in the facility life-cycle, the main preparatory activities are implemented towards the end of the operational period and during the transition period from operation to decommissioning. These may include a wide range of technical actions, such as physical and radiological characterization, pre-decommissioning decontamination, management of spent fuel and operational waste, establishment of new waste management facilities and modification of safety systems needed to support decommissioning. In parallel, some non-technical tasks are to be completed, e.g. preparation of the final decommissioning plan and its supporting documents, licensing activities, organizational changes, training of personnel for decommissioning, etc. Preparatory activities may be organized in various ways depending on considered decommissioning strategies and physical and radiological status of the nuclear facility after its routine operation is over. The IAEA published numerous safety and technical reports providing guidance, recommendations, experiences, good practices and lessons learned, fully or to some extent covering the preparatory phase for decommissioning. Many training courses, workshops, seminars etc. were organized to support sharing of good practices among specialists and organizations involved. This paper provides an overview of relevant activities and perspectives of the IAEA in this area. The paper also draws some general conclusions and identifies lessons learned on the basis of

  14. U.S. decommissioning requirements and recommendations on international principles and rules on decommissioning

    U.S. requirements for decommissioning nuclear power plants have been under development for the past seven years. During the year 1985, policies and requirements for the following areas will be developed: methods of decommissioning, timing, planning, and financial security. Due to the common nature of the problems with decommissioning, international exchange of information is highly desirable. (CW)

  15. Decommissioning Technology Development for Nuclear Research Facilities

    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

  16. Status of the Fort St. Vrain decommissioning

    Fort St. Vrain is a high temperature gas cooled reactor. It has been shut down as a result of financial and technical difficulties. Fort St. Vrain has been planning for defueling and decommissioning for at least three years. The preliminary decommissioning plan, in accordance with the NRC's final rule, has been submitted and is being reviewed by the NRC. The basis of the preliminary decommissioning plan has been SAFSTOR. Public Service Company, who is the owner and operator of FSV, is scheduled to submit a proposed decommissioning plan to the NRC in the fourth quarter of 1990. PSC has gone out for bid on the decontamination and dismantlement of FSV. This paper includes the defueling schedule, the independent spent fuel storage installation status, the probability of shipping fuel to DOE, the status of the preliminary decommissioning plan submittal, the issuance of a possession only license and what are the results of obtaining this license amendment, preliminary decommissioning activities allowed prior to the approval of a proposed decommissioning plan, the preparation of a proposed decommissioning plan and the status of our decision to proceed with SAFSTOR or DECON as identified in the NRC's final decommissioning rule

  17. European Decommissioning Academy (EDA). Ready to start

    Slugen, Vladimir [Slovak University of Technology, Bratislava (Slovakia). Inst. of Nuclear and Physical Engineering

    2015-02-15

    According to analyses presented at EC meeting focused on decommissioning organized at 11 September 2012 in Brussels, it was stated that at least 2,000 new international experts for decommissioning will be needed in Europe up to 2025, which means about 150 each year. The article describes the European Decommissioning Academy (EDA) which is prepared for the first term in June 2015 in Slovakia. The main goal is a creation of new nuclear experts generation for decommissioning via the Academy, which will include lessons, practical exercises in laboratories as well as 2 days on-site training at NPP V-1 in Jaslovske Bohunice (Slovakia). Four days technical tour via most interesting European decommissioning facilities in Switzerland and Italy are planned as well. After the final exam, there is the option to continue in knowledge collection via participation at the 2nd Eastern and Central European Decommissioning (ECED) conference in Trnava (Slovakia). We would like to focus on VVER decommissioning issues because this reactor type is the most distributed design in the world and many of these units are actually in decommissioning process or will be decommissioned in the near future.

  18. European Decommissioning Academy (EDA). Ready to start

    According to analyses presented at EC meeting focused on decommissioning organized at 11 September 2012 in Brussels, it was stated that at least 2,000 new international experts for decommissioning will be needed in Europe up to 2025, which means about 150 each year. The article describes the European Decommissioning Academy (EDA) which is prepared for the first term in June 2015 in Slovakia. The main goal is a creation of new nuclear experts generation for decommissioning via the Academy, which will include lessons, practical exercises in laboratories as well as 2 days on-site training at NPP V-1 in Jaslovske Bohunice (Slovakia). Four days technical tour via most interesting European decommissioning facilities in Switzerland and Italy are planned as well. After the final exam, there is the option to continue in knowledge collection via participation at the 2nd Eastern and Central European Decommissioning (ECED) conference in Trnava (Slovakia). We would like to focus on VVER decommissioning issues because this reactor type is the most distributed design in the world and many of these units are actually in decommissioning process or will be decommissioned in the near future.

  19. Experiences in teaching decommissioning - 16179

    The paper describes the experience gained by the author in teaching decommissioning in the Highlands of Scotland. Initially when asked to teach the subject of decommissioning to students sitting for a BSc degree in 'Electrical or Mechanical Engineering with Decommissioning Studies', the author was taken aback, not having previously taught degree students and there was no precedent since there was no previous material or examples to build on. It was just as difficult for the students since whilst some had progressed from completing HND studies, the majority were employed at the Dounreay site and were mature students with families who were availing themselves of the opportunity for career advancement (CPD). Some of the students were from the UKAEA and its contractors whilst others were from Rolls-Royce working at Vulcan, the Royal Navy's establishment for testing nuclear reactors for submarines. A number of the students had not been in a formal learning environment for many years. The College which had originally been funded by the UKAEA and the nuclear industry in the 1950's was anxious to break into the new field of Decommissioning and were keen to promote these courses in order to support the work progressing on site. Many families in Thurso, and in Caithness, have a long tradition of working in the nuclear industry and it was thought at the time that expertise in nuclear decommissioning could be developed and indeed exported elsewhere. In addition the courses being promoted by the College would attract students from other parts so that a centre of excellence could be established. In parallel with formal teaching, online courses were also developed to extend the reach of the College. The material was developed as a mixture of power point presentations and formal notes and was obtained from existing literature, web searches and interactive discussions with people in the industry as well as case studies obtained from actual situations. Assignments were set and

  20. Evaluation of the I. Stage of decommissioning and implementation of the II. Stage of decommissioning of NPP V1

    In this paper author deals with following aspects: 1. Introduction of company Nuclear and Decommissioning Company, plc; 2. Evaluation of the I. stage of decommissioning and implementation of the II. Stage of decommissioning of NPP V1; (author)

  1. An apparatus for studying spallation neutrons in the Aberdeen Tunnel laboratory

    Blyth, S C; Chen, X C; Chu, M C; Hahn, R L; Ho, T H; Hsiung, Y B; Hu, B Z; Kwan, K K; Kwok, M W; Kwok, T; Lau, Y P; Lee, K P; Leung, J K C; Leung, K Y; Lin, G L; Lin, Y C; Luk, K B; Luk, W H; Ngai, H Y; Ngan, S Y; Pun, C S J; Shih, K; Tam, Y H; Tsang, R H M; Wang, C H; Wong, C M; Wong, H L; Wong, H H C; Wong, K K; Yeh, M

    2013-01-01

    In this paper, we describe the design, construction and performance of an apparatus installed in the Aberdeen Tunnel laboratory in Hong Kong for studying spallation neutrons induced by cosmic-ray muons under a vertical rock overburden of 611 meter water equivalent (m.w.e.). The apparatus comprises of six horizontal layers of plastic-scintillator hodoscopes for determining the direction and position of the incident cosmic-ray muons. Sandwiched between the hodoscope planes is a neutron detector filled with 650 kg of liquid scintillator doped with about 0.06% of Gadolinium by weight for improving the e?ciency of detecting the spallation neutrons. Performance of the apparatus is also presented.

  2. Research in decommissioning techniques for nuclear fuel cycle facilities in JNC. 7. JWTF decommissioning techniques

    Ogawa, Ryuichiro; Ishijima, Noboru [Japan Nuclear Cycle Development Inst., Oarai, Ibaraki (Japan). Oarai Engineering Center

    1999-02-01

    Decommissioning techniques such as radiation measuring and monitoring, decontamination, dismantling and remote handling in the world were surveyed to upgrading technical know-how database for decommissioning of Joyo Waste Treatment Facility (JWTF). As the result, five literatures for measuring and monitoring techniques, 14 for decontamination and 22 for dismantling feasible for JWTF decommissioning were obtained and were summarized in tables. On the basis of the research, practical applicability of those techniques to decommissioning of JWTF was evaluated. This report contains brief surveyed summaries related to JWTF decommissioning. (H. Itami)

  3. Decommissioning of Russian research facilities

    When the most of our research facilities were built and put in operation more than 30 years ago there had been neither requirements no regulations concerning their future decommissioning (D and D). And due to that fact nobody thought of that in the initial designs of these facilities. The situation changed when in 1994 a top-level safety standard 'Safety Provision for Safety of Research Reactors' was issued by Gosatomnadzor of Russia with a special chapter 7, devoted to D and D issues. Unfortunately, it was just one page of requirements pertaining RR D and D in general terms and was not specific. Only in 2001 Gosatomnadzor of Russia developed and issued a more specific standard 'Rules for Safety Decommissioning of Nuclear Research Facilities'. From the total number of 85 Nuclear Research Facilities, including 34 research reactors, 36 critical assemblies and 15 subcritical assemblies, we have now 7 facilities under decommissioning. The situation is inevitably changing over the time. In the end of 2003 the decision was made to permanently shutdown two RR: AM, graphite type with channels, 15 MBt; BR-10, LMFR type, 10 MBt, and to start preparatory work for their future decommissioning, starting from 2005. It needs to be mentioned that from this list we have 6 reactors with which we face many difficulties in developing decommissioning technologies, namely: for TVR reactor: handling of heavy water and high radiation field in the core; for MR reactor: very complex reactor with many former radioactive spills, which is required a careful and expensive D and D work; AM: graphite utilization problem; BR-10: a problem of coolant poisoned with other heavy metals (like lead, bismuth); IBR-30: the fuel cannot be removed from the core prior the D and D project starts; RG-1M: location is above Arctic Circle, problem of transfer of irradiated parts of the reactor. The decision was made to bury then on the site thus creating a shallow-land radwaste storage facility. The established D

  4. AREVA decommissioning strategy and programme

    As with any industrial installation, a nuclear facility has an operating life that requires accounting for its shutdown. In compliance with its sustainable development commitments, AREVA accounts this via its own decommissioning resources to value and make sites fit for further use. These capabilities guarantee the reversibility of the nuclear industry. Thus, the nuclear site value development constitutes an important activity for AREVA, which contributes to the acceptance of nuclear in line with the AREVA continuous policy of sustainable development which is to be fully responsible from the creation, during the operation, to the dismantling of its facilities in all respects with safety, local acceptance and environment. AREVA has already performed a large variety of operation during the life-time of its installations such as heavy maintenance, equipment replacement, upgrading operation. Nowadays, a completely different dimension is emerging with industrial decommissioning operations of nuclear fuel cycle installations: enrichment gaseous diffusion plant, fuel assembly plants, recycling and reprocessing facilities. These activities constitute a major know-how for AREVA. For this reason, the group decided, beginning of 2008, to gather 4 projects in one business unit called Nuclear Site Value Development - a reprocessing plant UP2 400 on AREVA La Hague site, a reprocessing plant UP1 on AREVA Marcoule site, a MOX fuel plant on Cadarache and 2 sites (SICN Veurey and Annecy) that handled GCR fuel fabrication). The main objectives are to enhance the feed back, to contribute to performance improvements, to value professionals and to put innovation forward. The following article will describe in a first part the main decommissioning programmes managed by AREVA NC Nuclear Site Value Development Business Unit. The second part will deal with strategic approaches. A more efficient organization with integration of the supply chain and innovation will be part of the main drivers

  5. STANDARD OPERATING PROTOCOLS FOR DECOMMISSIONING

    Decommissioning projects at Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) sites are conducted under project-specific decision documents, which involve extensive preparation time, public comment periods, and regulatory approvals. Often, the decision documents must be initiated at least one year before commencing the decommissioning project, and they are expensive and time consuming to prepare. The Rocky Flats Environmental Technology Site (RFETS) is a former nuclear weapons production plant at which hazardous substances and wastes were released or disposed during operations. As a result of the releases, RFETS was placed on the National Priorities List in 1989, and is conducting cleanup activities under a federal facilities compliance agreement. Working closely with interested stakeholders and state and federal regulatory agencies, RFETS has developed and implemented an improved process for obtaining the approvals. The key to streamlining the approval process has been the development of sitewide decision documents called Rocky Flats Cleanup Agreement Standard Operating Protocols or ''RSOPs.'' RSOPs have broad applicability, and could be used instead of project-specific documents. Although no two decommissioning projects are exactly the same and they may vary widely in contamination and other hazards, the basic steps taken for cleanup are usually similar. Because of this, using RSOPs is more efficient than preparing a separate project-specific decision documents for each cleanup action. Over the Rocky Flats cleanup life cycle, using RSOPs has the potential to: (1) Save over 5 million dollars and 6 months on the site closure schedule; (2) Eliminate preparing one hundred and twenty project-specific decision documents; and (3) Eliminate writing seventy-five closure description documents for hazardous waste unit closure and corrective actions

  6. Project gnome decontamination and decommissioning plan

    The document presents the operational plan for conducting the final decontamination and decommissioning work at the site of the first U.S. nuclear detonation designed specifically for peaceful purposes and the first underground event on the Plowshare Program to take place outside the Nevada Test Site. The plan includes decontamination and decommissioning procedures, radiological guidelines, and the NV concept of operations

  7. Interim Storage Facility decommissioning. Final report

    Decontamination and decommissioning of the Interim Storage Facility were completed. Activities included performing a detailed radiation survey of the facility, removing surface and imbedded contamination, excavating and removing the fuel storage cells, restoring the site to natural conditions, and shipping waste to Hanford, Washington, for burial. The project was accomplished on schedule and 30% under budget with no measurable exposure to decommissioning personnel

  8. 76 FR 3837 - Nuclear Decommissioning Funds; Correction

    2011-01-21

    ... 23, 2010 (75 FR 80697) relating to deductions for contributions to trusts maintained for decommissioning nuclear power plants. DATES: This correction is effective on January 21, 2011, and is applicable... Internal Revenue Service 26 CFR Part 1 RIN 1545-BF08 Nuclear Decommissioning Funds; Correction...

  9. Survey of decontamination and decommissioning techniques

    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

  10. Meeting the challenge of BNFL's decommissioning programme

    The paper reviews the co-ordinated and integrated programme, adopted by BNFL, in the decommissioning of its radioactive plants. It examines BNFL's approach to the challenges posed by the eventual decommissioning of its 120 plants, its overall strategies, the constraints and the progress achieved to date, drawing on real experience from the 22 completed projects and the 24 projects currently underway. (author)

  11. Training of experts on NPP decommissioning

    The paper presents difficulties and problems in training of NPP decommissioning experts in Ukraine. The scientific and technical cluster is offered to be constructed as a territorial association of enterprises and organizations related to NPP decommissioning issues and spent nuclear fuel and radioactive waste management. The center is to be based on scientific and educational center in Slavutych, satellite city of Chornobyl NPP.

  12. 76 FR 77431 - Decommissioning Planning During Operations

    2011-12-13

    ... that the NRC staff considers acceptable for use in complying with the NRC's Decommissioning Planning... that the NRC staff considers acceptable for use in complying with the NRC's Decommissioning Planning Rule (DPR), which will become effective on December 17, 2012 (76 FR 35511; June 17, 2011). That...

  13. Facilitation of decommissioning light water reactors

    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

  14. Decommission of nuclear ship `MUTSU`

    Tateyama, Takeshi [Ishikawajima-Harima Heavy Industries Co. Ltd., Tokyo (Japan)

    1996-11-01

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

  15. Decommissioning of a University Cyclotron

    In the decommissioning of a university cyclotron, the cost estimate provided by a decommissioning company to carry out the entire project was in excess of Pounds 1million. This level of funding was not available, and a more modest budget of Pounds 125 thousand was provided (about US$ 250 000 or Euro 180 000). This made it essential that as much of the work as possible was carried out by existing staff. Whereas existing staff could be trained to draft all the required documentation, complete the characterization survey and deliver some aspects of the decontamination programme, their greatest contribution to the project was in sorting, segregation, measurement, packaging and consignment for disposal of all of the decommissioning wastes. This necessitated provision of additional training to existing operators. At an early stage it was identified that an experienced decommissioning consultant was needed to oversee the project. The Decommissioning Consultant appointed external contractors to carry out all the heavy dismantling and demolition work associated with the project. This work involved: -Assembly of a caged storage area adjacent to the cyclotron to hold the wastes from dismantling and demolition, pending characterization for segregation and disposal by existing staff at the facility; -Removal of the D's and cutting them up in situ ready for characterization for shipment to the low level waste repository; -Removal of all rotating machinery in the adjacent generator house, then dismantling the concrete block and brick wall between the inner vault and the generator house; -Removal of extra shielding supported by girder matrix to assist removal of the concrete block wall. Collect core samples of bricks and blocks for activity estimation by operators working at the facility; -Moving of the resonator into the generator house for dismantling, monitoring and characterization; -Dismantling of ancillary equipment such as beam lines, remote target handling system, vacuum

  16. The IAEA Safety Regime for Decommissioning

    Full text of publication follows: The International Atomic Energy Agency is developing an international framework for decommissioning of nuclear facilities that consists of the Joint Convention on the Safety of Spent Fuel Management and the Safety of Radioactive Waste Management, and a hierarchy of Safety Standards applicable to decommissioning. The Joint Convention entered into force on 18 June 2001 and as of December 2001 had been ratified by 27 IAEA Member States. The Joint Convention contains a number of articles dealing with planning for, financing, staffing and record keeping for decommissioning. The Joint Convention requires Contracting Parties to apply the same operational radiation protection criteria, discharge limits and criteria for controlling unplanned releases during decommissioning that are applied during operations. The IAEA has issued Safety Requirements document and three Safety Guides applicable to decommissioning of facilities. The Safety Requirements document, WS-R-2, Pre-disposal Management of Radioactive Waste, including Decommissioning, contains requirements applicable to regulatory control, planning and funding, management of radioactive waste, quality assurance, and environmental and safety assessment of the decommissioning process. The three Safety Guides are WS-G-2.1, Decommissioning of Nuclear Power Plants and Research Reactors, WS-G-2.2, Decommissioning of Medical, Industrial and Research Facilities, an WS-G-2.4, Decommissioning of Nuclear Fuel Cycle Facilities. They contain guidance on how to meet the requirements of WS-R-2 applicable to decommissioning of specific types of facilities. These Standards contain only general requirements and guidance relative to safety assessment and do not contain details regarding the content of the safety case. More detailed guidance will be published in future Safety Reports currently in preparation within the Waste Safety Section of the IAEA. Because much material arising during the decommissioning

  17. Decontamination and decommissioning of nuclear facilities

    The objectives of this coordinated research programme (CRP) were to promote the exchange of information on the practical experience by Member States in decontamination and decommissioning. The scope of the programme included several areas of decontamination and decommissioning rather than focusing on a single aspect of it, in line with recommendation of the experts who participated in Phase 1 of the CRP. Experts felt that this format would generate better awareness of decontamination and decommissioning and would be more effective vehicle for the exchange of information by stimulating broader discussion on all aspects of decontamination and decommissioning. Special emphasis was given to the development of principles and methodologies to facilitate decommissioning and to the new methods and techniques for optimization of decontamination and disassembly of equipment. Refs, figs, tabs

  18. Decommissioning of nuclear research facilities at KAERI

    At the Korea Atomic Energy Research Institute (KAERI), two research reactors (KRR-1 and KRR-2) and one uranium conversion plant (UCP) are being decommissioned. The main reason of the decommissioning was the diminishing utilities; the start of a new research reactor, HANARO, and the higher conversion cost than that of international market for the UCP. Another reason of the decommissioning was prevention from spreading radioactive materials due to the deterioration of the facilities. Two separate projects have already been started and are carried out as planned. The KAERI selected several strategies, considering the small scale of the projects, the internal standards in KAERI, and the future prospects of the decommissioning projects in Korea. In this paper, the current status of the decommissioning including the waste management and the technology development will be explained

  19. Decommissioning plan for TRIGA Mark-2

    Park, Seung Kook; Lee, B.J.

    1999-04-01

    Korea Research Reactor 1(KRR 1; TRIGA Mark-2) is the first reactor in Korea, but its decommissioning is underway due to its life. In this paper, presenting the reason and object of decommissioning KRR 1, then describing reactor structure and survey result of the facility, activation and contamination status around reactor and nearby equipment and vicinity. Estimating dose rate was evaluated for every work stage. Those of survey, evaluation and radiological status were considered to determine the safe and reasonable decommissioning methods. The order of decommissioning works are divided by section to minimize possible hazard. Proposed decommissioning plan is based on hazard and operability study to protect workers and residents from radiation expose. (author). 12 refs., 5 tabs., 6 figs.

  20. Conceptual data modeling on the decommissioning database

    ISP (Information Strategy Planning), which is the first step of the whole database development, has been studied to manage effectively information and data related to the decommissioning activities of the Korea Research Reactor 1 and 2 (KRR 1 and 2). A record management system (RMS) of large nuclear facilities of national experience such as in the U. S. A., Japan, Belgium, and Russian were reviewed. In order to establish the scope of the decommissioning DB, user requirement and the importance of the information were analyzed and set up the conceptual design of the decommissioning DB. The results have been reviewed an national experience were recognized to acquire the technology of the decommissioning DB for the whole decommissioning process. It has been extracted the principle information such as working information, facilities information, radioactive waste treatment, and radiological surveying and analysis during the interviewing with an experts. These information and data will be used as the basic data to design the prototyping

  1. Decommissioning progress at Fort St Vrain

    The Fort St. Vrain Nuclear Generating Station in Colorado in the United States is well along in Decommissioning for release of the site from its Nuclear Regulatory Commission license. This decommissioning is being performed under a fixed price contract between the owner, Public Service Company of Colorado and a team of Westinghouse and Morrison-Knudsen. This paper will discuss the innovative decommissioning technique of filling the gas cooled reactor with water for shielding and contamination control and the other practical and readily available technologies used. This Decommissioning is demonstrating that a full size commercial nuclear reactor can be successfully decommissioned with a reasonable schedule, cost, and radiation dose to the work force. (Author)

  2. Asbestos removal in Shippingport Decommissioning Project

    The Shippingport Station Decommissioning Project (SSDP) is being performed under contract to the DOE by the General Electric Company and its integrated subcontractor, MK-Ferguson Company, as the Decommissioning Operations Contractor (DOC). During the planning of this project, it was found that asbestos was the primary insulating material which was used on the nuclear steam supply system and the plant heating system. The original decommissioning plan required that each subcontractor remove the asbestos from the particular component(s) they had to remove. However, since removal of the radioactivity-contaminated asbestos would require special procedures and worker training, the original decommissioning plan was modified so that a single subcontractor removed all of the asbestos prior to other decommissioning tasks. IT Corporation was selected as the asbestos removal subcontractor. Their approach to the project is described

  3. Decommissioning plan for TRIGA Mark-2

    Korea Research Reactor 1(KRR 1; TRIGA Mark-2) is the first reactor in Korea, but its decommissioning is underway due to its life. In this paper, presenting the reason and object of decommissioning KRR 1, then describing reactor structure and survey result of the facility, activation and contamination status around reactor and nearby equipment and vicinity. Estimating dose rate was evaluated for every work stage. Those of survey, evaluation and radiological status were considered to determine the safe and reasonable decommissioning methods. The order of decommissioning works are divided by section to minimize possible hazard. Proposed decommissioning plan is based on hazard and operability study to protect workers and residents from radiation expose. (author). 12 refs., 5 tabs., 6 figs

  4. Measuring and reporting on decommissioning progress

    One of the challenges facing AECL, as well as other organizations charged with the responsibility of decommissioning nuclear facilities, is the means by which to measure and report on decommissioning progress to various audiences which, in some cases, may only have a peripheral knowledge or understanding of the complexities associated with the decommissioning process. The reporting and measurement of decommissioning progress is important for a number of reasons, i.e., It provides a vehicle by which to effectively communicate the nature of the decommissioning process; It ensures that stakeholders and shareholders are provided with a transparent and understandable means for assessing value for money; It provides a means by which to integrate the planning, measurement, and operational aspects of decommissioning One underlying reason behind the challenge of reporting decommissioning progress lies in the fact that decommissioning programs are generally executed over periods of time that far exceed those generally associated with typical design and build projects. For example, a decommissioning program could take decades to complete in which case progress on the order of a few percent in any one year might be typical. However, such progress may appear low compared to that seen with more typical projects that can be completed in a matter of years. As a consequence, AECL undertook to develop a system by which to measure decommissioning progress in a straightforward, meaningful, and understandable fashion. The system is not rigorously objective, and there are subjective aspects that are necessitated by the need to keep the system readily understandable. It is also important to note that while the system is simple in concept, there is, nonetheless, significant effort involved in generating and updating the parameters used as input, and in the actual calculations. (author)

  5. The decommissioning NPP A-1

    Project of decommissioning NPP A-1 is split into 4 main groups of tasks. Tasks in group 1 are focused on the solution of selected problems that have immediate impact on the environment. It is mainly the solution of problems in the building of cleaning station of wastage water and in the building with underground storage tanks for wastage water and solid radwaste, including the prevention of wash-out and penetration of contaminated soil from these buildings into surface and underground waters. A part of addressing these tasks is a controlled of generated radwaste-predominatly sludge with various physical and chemical properties. Tasks in group 2- following the removal of spent fuel-are focused on the management of all radwaste in the long-term storage facility, in the short-term storage facility, equipment of transport and technology part, equipment in hot cells. Tasks in group 3 are focused on development of technology procedures for treatment and conditioning of sludge, contaminated soils and concrete crush, saturated ionexes and ash from incineration facility of the Bohunice radwaste treatment and conditioning complex. Tasks in group 4 are focused on the methodology. And technical support for particular activities applicable during decommissioning NPP

  6. Decommissioning of Salaspils nuclear reactor

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

  7. Uranium hexafluoride production plant decommissioning

    The Institute of Energetic and Nuclear Research - IPEN is a research and development institution, located in a densely populated area, in the city of Sao Paulo. The nuclear fuel cycle was developed from the Yellow Cake to the enrichment and reconversion at IPEN. After this phase, all the technology was transferred to private enterprises and to the Brazilian Navy (CTM/SP). Some plants of the fuel cycle were at semi-industrial level, with a production over 20 kg/h. As a research institute, IPEN accomplished its function of the fuel cycle, developing and transferring technology. With the necessity of space for the implementation of new projects, the uranium hexafluoride (UF6) production plant was chosen, since it had been idle for many years and presented potential leaking risks, which could cause environmental aggression and serious accidents. This plant decommission required accurate planning, as this work had not been carried out in Brazil before, for this type of facility, and there were major risks involving gaseous hydrogen fluoride aqueous solution of hydrofluoric acid (HF) both highly corrosive. Evaluations were performed and special equipment was developed, aiming to prevent leaking and avoid accidents. During the decommissioning work, the CNEN safety standards were obeyed for the whole operation. The environmental impact was calculated, showing to be not relevant.The radiation doses, after the work, were within the limits for the public and the area was released for new projects. (author)

  8. Planning of the BN-350 reactor decommissioning

    The experimental and commercial BN-350 NPP equipped with a fast neutron sodium cooled reactor is located in Kazakhstan near the Aktau city on the Caspian Sea coast. It was commissioned in 1973 and intended for weapon-grade plutonium production and as stream supply to a water desalination facility and the turbines of the Mangyshlak Atomic Energy Complex. Taking into account technical, financial and political issues, the Government of Kazakhstan enacted the Decree no. 456 'On Decommissioning of the Reactor BN-350 in the Aktau City of the Mangystau Region'. Because the decision on reactor decommissioning was adopted before the end of scheduled operation (2003), the plan to decommission the BN-350 reactor has not yet been developed. To determine the activities required for ensuring reactor safety and in preparation for decommission in the period prior, the development and ensuring approval by the Republic of Kazakhstan Government of the decommissioning plan, a 'Plan of Priority Actions for BN-350 Reactor Decommissioning' was developed and approved. Actions provided for in the plan include the following: Development of BN-350 Reactor Decommissioning Plan; Accident prevention during the period of transition; Unloading nuclear fuel from reactor and draining the coolant from the heat exchange circuits. Decommission is defined as a complex of administrative and technical actions taken to allow the removal of some or all of regulatory controls over a nuclear facility. These actions involve decontamination, dismantling and removal of radioactive materials, waste, components and structures. They are carried out to achieve a progressive and systematic reduction in radiological hazards and are undertaken on the basis of planning and assessment in order to ensure safety decommissioning operations. In accordance with the decision of Kazakhstan Government, three basic stages for BN-350 reactor decommissioning are envisaged: First stage - Placement of BN-350 into long-term storage

  9. Government Assigns New Supervisory Task. Safe Decommissioning

    When the Government decided to shutdown one of the two Barsebaeck reactors in February of 1998, it presented SKI with a task that came much earlier than expected; the supervision of the decommissioning of a reactor. As a result of proposals presented in Parliament, SKI began the formulation of a long-term strategy in 1997 for the inspection of a nuclear plant during the decommissioning process. As a preliminary task, SKI started a research programme dealing with the potential risks associated with the transition from normal operations through shutdown to final deconstruction of the power plant. Emphasis was laid on safety culture issues and on questions of organization, as opposed to an earlier stress on the purely technical aspects of decommissioning. After a long period of uncertainty, following much discussion, in July 1998 a Government decision was finally reached to shutdown the first reactor at Barsebaeck. This was carried out in November 1999. It is still uncertain as to when the other reactor will be decommissioned; a decision is expected at the earliest in 2004. This uncertainty, resulting from the prolonged decision making process, could be detrimental to the safety culture on the site; motivation could diminish, and key personnel could be lost. Decommissioning is a new phase in the life cycle of a plant, giving rise to new inspection issues of supervision. During the period of uncertainty, while awaiting SKI has identified ten key areas, dealing with the safety culture of the organization, in connection with the decommissioning of Barsebaeck 1. 1. Obtaining and retaining staff competence during decommissioning; 2. Sustaining organizational memory; 3. Identifying key organizational functions and management skills that are critical during the transition from operations to decommissioning. 4. Sustaining organizational viability and accountability for decommissioning; 5. Sustaining motivation and trust in management of dismantlement; 6. Overseeing

  10. The decommissioning plan of the Nuclear Ship MUTSU

    Adachi, M.; Matsuo, R.; Fujikawa, S.; Nomura, T. [Japan Atomic Energy Research Inst., Mutsu, Aomori (Japan). Mutsu Establishment

    1995-07-01

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

  11. The decommissioning plan of the Nuclear Ship MUTSU

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

  12. International radiation safety recommendations on decommissioning

    Full text: The IAEA Safety Requirements for decommissioning states that the regulatory body shall establish requirements for the decommissioning of nuclear facilities, including conditions on the end points of decommissioning. One of the main important issues is that the operator shall be responsible for all aspects of safety of the facility during its lifetime and of the decommissioning activities until its completion. A mechanism for providing adequate financial resources shall be established to cover the costs of radioactive waste management and, in particular the cost of decommissioning. It shall be put in place before operation and shall be updated, as necessary. A safety assessment of the proposed decommissioning strategy shall be performed and its implementation shall not begin until approval has been received by the regulatory body. A decommissioning plan shall be prepared for each facility, to show that decommissioning can be accomplished safely. The decommissioning plan shall be reviewed regularly and shall be updated as required to reflect, in particular, changes in the facility or regulatory requirements, advances in technology and, finally, the needs of decommissioning operation. If it is intended to defer decommissioning, it shall be demonstrated in the final decommissioning plan that such an option is safe. Decontamination and dismantling techniques shall be chosen which minimizes waste and appropriate means shall be in place for safe managing any waste that might be generated during the decommissioning process. A quality assurance programme shall be established for the decommissioning process. Before a site may be released for unrestricted use, a survey shall be performed to demonstrate that the end point conditions, as established by regulatory body, have been met. If site cannot be released for unrestricted use, appropriate control shall be maintained to ensure protection of human health and environment. The IAEA Safety Guidance mainly addresses

  13. Waste management in decommissioning projects at KAERI

    Two decommissioning projects are being carried out at the KAERI (Korean Atomic Energy Research Institute), one for the Korea research reactors, KRR-1 and KRR-2, and another for the uranium conversion plant (UCP). The concept of the management of the wastes from the decommissioning sites was reviewed with relation to the decommissioning strategies, technologies for the treatment and the decontamination, and the characteristics of the waste. All the liquid waste generated from the KRR-1 and KRR-2 decommissioning site is evaporated by a solar evaporation facility and all the liquid waste from the UCP is treated together with the lagoon sludge waste. The solid wastes from the decommissioning sites are categorized into three groups; not contaminated, restricted releasable and radioactive waste. The not-contaminated waste will be reused and/or disposed of an industrial disposal site, and the releasable waste will be stored for a future disposal at the KAERI. The radioactive waste is packed into containers, and it will be stored at the decommissioning sites till it is sent to a national repository site. The reduction of the radioactive solid waste is one of the strategies for the decommissioning projects and could be achieved by a repeated decontamination. By the achievement of a minimization strategy, the amount of radioactive waste was reduced and the disposal cost will be reduced, but the cost for the manpower, and for a direct handling of the materials as well as for the administration was increased

  14. Methodology and technology of decommissioning nuclear facilities

    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

  15. Decommissioning standards: the radioactive waste impact

    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

  16. Disposition of fuel elements from the Aberdeen and Sandia pulse reactor (SPR-II) assemblies

    Mckerley, Bill [Los Alamos National Laboratory; Bustamante, Jacqueline M [Los Alamos National Laboratory; Costa, David A [Los Alamos National Laboratory; Drypolcher, Anthony F [Los Alamos National Laboratory; Hickey, Joseph [Los Alamos National Laboratory

    2010-01-01

    We describe the disposition of fuel from the Aberdeen (APR) and the Sandia Pulse Reactors (SPR-II) which were used to provide intense neutron bursts for radiation effects testing. The enriched Uranium - 10% Molybdenum fuel from these reactors was shipped to the Los Alamos National Laboratory (LANL) for size reduction prior to shipment to the Savannah River Site (SRS) for final disposition in the H Canyon facility. The Shipper/Receiver Agreements (SRA), intra-DOE interfaces, criticality safety evaluations, safety and quality requirements and key materials management issues required for the successful completion of this project will be presented. This work is in support of the DOE Consolidation and Disposition program. Sandia National Laboratories (SNL) has operated pulse nuclear reactor research facilities for the Department of Energy since 1961. The Sandia Pulse Reactor (SPR-II) was a bare metal Godiva-type reactor. The reactor facilities have been used for research and development of nuclear and non-nuclear weapon systems, advanced nuclear reactors, reactor safety, simulation sources and energy related programs. The SPR-II was a fast burst reactor, designed and constructed by SNL that became operational in 1967. The SPR-ll core was a solid-metal fuel enriched to 93% {sup 235}U. The uranium was alloyed with 10 weight percent molybdenum to ensure the phase stabilization of the fuel. The core consisted of six fuel plates divided into two assemblies of three plates each. Figure 1 shows a cutaway diagram of the SPR-II Reactor with its decoupling shroud. NNSA charged Sandia with removing its category 1 and 2 special nuclear material by the end of 2008. The main impetus for this activity was based on NNSA Administrator Tom D'Agostino's six focus areas to reenergize NNSA's nuclear material consolidation and disposition efforts. For example, the removal of SPR-II from SNL to DAF was part of this undertaking. This project was in support of NNSA's efforts

  17. Decommissioning activities for Salaspils research reactor - 59055

    In May 1995, the Latvian government decided to shut down the Salaspils Research Reactor (SRR). The reactor is out of operation since July 1998. A conceptual study for the decommissioning of SRR has been carried out by Noell-KRC-Energie- und Umwelttechnik GmbH at 1998-1999. The Latvian government decided to start the direct dismantling to 'green field' in October 26, 1999. The upgrade of decommissioning and dismantling plan was performed in 2003-2004 years, which change the main goal of decommissioning to the 'brown field'. The paper deals with the SRR decommissioning experience during 1999-2010. The main decommissioning stages are discussed including spent fuel and radioactive wastes management. The legal aspects and procedures for decommissioning of SRR are described in the paper. It was found, that the involvement of stakeholders at the early stages significantly promotes the decommissioning of nuclear facility. Radioactive waste management's main efforts were devoted to collecting and conditioning of 'historical' radioactive wastes from different storages outside and inside of reactor hall. All radioactive materials (more than 96 tons) were conditioned in concrete containers for disposal in the radioactive wastes repository 'Radons' at Baldone site. The dismantling of contaminated and activated components of SRR systems is discussed in paper. The cementation of dismantled radioactive wastes in concrete containers is discussed. Infrastructure of SRR, including personal protective and radiation measurement equipment, for decommissioning purposes was upgraded significantly. Additional attention was devoted to the free release measurement's technique. The certified laboratory was installed for supporting of all decommissioning activities. All non-radioactive equipments and materials outside of reactor buildings were released for clearance and dismantled for reusing or conventional disposing. Weakly contaminated materials from reactor hall were collected

  18. Decommissioning of underground structures, systems and components

    A large number of operational and shut down nuclear installations have underground systems, structures and components such as pipes, tanks or vaults. This practice of incorporating such features into the design of nuclear facilities has been in use for an extended period of time during which decommissioning was not perceived as a serious issue and was rarely considered in plant design and construction. Underground features can present formidable decontamination and/or dismantling issues, and these are addressed in this report. Decommissioning issues include, among others, difficulty of access, the possible need for remotely operated technologies, leakage of the contents and the resulting contamination of foundations and soil, as well as issues such as problematic radiological characterization. Although to date there have been more than 40 IAEA publications on decommissioning, none of them has ever addressed this subject. Although cases of decommissioning of such facilities have been described in the technical literature, no systematic treatment of relevant decommissioning strategies and technologies is currently available. It was perhaps assumed that generic decontamination and dismantling approaches would also be adequate for these 'difficult' facilities. This may be only partly true due to a number of unique physical, layout and radiological characteristics. With growing experience in the decommissioning field, it is timely to address this subject in a systematic and comprehensive fashion. Practical guidance is given in this report on relevant decommissioning strategies and technologies for underground features of facilities. Also described are alternative design and construction approaches that could facilitate a smoother path forward through the decommissioning process. The objective of this report is to highlight important points in the decommissioning of underground systems, structures or components for policy makers, operators, waste managers and other

  19. Modelling of nuclear power plant decommissioning financing

    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. (authors)

  20. UK policy for nuclear decommissioning: viewpoint

    The importance of the United Kingdom Government formulating a policy for the decommissioning of nuclear installations is stressed in this article because of the UK's aging nuclear reactors, especially the Magnox type reactors, the decommissioning of which is likely to cause particular difficulties. Funds have not, so far, been properly set aside, as estimated costs continue to rise, nor have actual management strategies been developed. The author raises ethical, environmental, technical and economic objections to current plans to postpone decommissioning until 100 years after reactors are closed. (UK)

  1. Decommissioning and reclamation of ANHUA uranium mine

    Since the late 1980s a number of uranium production facilities in China were closed and are in various stages of decommissioning. To date 5 mines have been decommissioned. ANHUA mine is situated in west part of Hunan province in South China. The production of uranium ore began in 1974 and stopped in 1986. Decommissioning and reclamation programme started in July 1992 and completed in May 1997. This paper describes the experience in sealing of drift entrances, covering of waste rock piles and rehabilitation of cadmium contaminated farmland with replantation. (author)

  2. Pipeline Decommissioning Trial AWE Berkshire UK - 13619

    Agnew, Kieran [AWE, Aldermaston, Reading, RG7 4PR (United Kingdom)

    2013-07-01

    This Paper details the implementation of a 'Decommissioning Trial' to assess the feasibility of decommissioning the redundant pipeline operated by AWE located in Berkshire UK. The paper also presents the tool box of decommissioning techniques that were developed during the decommissioning trial. Constructed in the 1950's and operated until 2005, AWE used a pipeline for the authorised discharge of treated effluent. Now redundant, the pipeline is under a care and surveillance regime awaiting decommissioning. The pipeline is some 18.5 km in length and extends from AWE site to the River Thames. Along its route the pipeline passes along and under several major roads, railway lines and rivers as well as travelling through woodland, agricultural land and residential areas. Currently under care and surveillance AWE is considering a number of options for decommissioning the pipeline. One option is to remove the pipeline. In order to assist option evaluation and assess the feasibility of removing the pipeline a decommissioning trial was undertaken and sections of the pipeline were removed within the AWE site. The objectives of the decommissioning trial were to: - Demonstrate to stakeholders that the pipeline can be removed safely, securely and cleanly - Develop a 'tool box' of methods that could be deployed to remove the pipeline - Replicate the conditions and environments encountered along the route of the pipeline The onsite trial was also designed to replicate the physical prevailing conditions and constraints encountered along the remainder of its route i.e. working along a narrow corridor, working in close proximity to roads, working in proximity to above ground and underground services (e.g. Gas, Water, Electricity). By undertaking the decommissioning trial AWE have successfully demonstrated the pipeline can be decommissioned in a safe, secure and clean manor and have developed a tool box of decommissioning techniques. The tool box of includes

  3. Pipeline Decommissioning Trial AWE Berkshire UK - 13619

    This Paper details the implementation of a 'Decommissioning Trial' to assess the feasibility of decommissioning the redundant pipeline operated by AWE located in Berkshire UK. The paper also presents the tool box of decommissioning techniques that were developed during the decommissioning trial. Constructed in the 1950's and operated until 2005, AWE used a pipeline for the authorised discharge of treated effluent. Now redundant, the pipeline is under a care and surveillance regime awaiting decommissioning. The pipeline is some 18.5 km in length and extends from AWE site to the River Thames. Along its route the pipeline passes along and under several major roads, railway lines and rivers as well as travelling through woodland, agricultural land and residential areas. Currently under care and surveillance AWE is considering a number of options for decommissioning the pipeline. One option is to remove the pipeline. In order to assist option evaluation and assess the feasibility of removing the pipeline a decommissioning trial was undertaken and sections of the pipeline were removed within the AWE site. The objectives of the decommissioning trial were to: - Demonstrate to stakeholders that the pipeline can be removed safely, securely and cleanly - Develop a 'tool box' of methods that could be deployed to remove the pipeline - Replicate the conditions and environments encountered along the route of the pipeline The onsite trial was also designed to replicate the physical prevailing conditions and constraints encountered along the remainder of its route i.e. working along a narrow corridor, working in close proximity to roads, working in proximity to above ground and underground services (e.g. Gas, Water, Electricity). By undertaking the decommissioning trial AWE have successfully demonstrated the pipeline can be decommissioned in a safe, secure and clean manor and have developed a tool box of decommissioning techniques. The tool box of includes; - Hot tapping - a method

  4. Development of a Decommissioning Certificate Program

    A Decommissioning Certificate Program has been developed at Washington State University Tri-Cities (WSU TC) in conjunction with Bechtel Hanford, Inc. (BHI), and the U.S. Department of Energy (DOE)to address the increasing need for qualified professionals to direct and manage decommissioning projects. The cooperative effort between academia, industry, and government in the development and delivery of this Program of education and training is described, as well as the Program's design to prepare students to contribute sooner, and at a higher level, to decommissioning projects

  5. Social effects of decommissioning Trawsfynydd Power Station

    The decision to close Trawsfynydd in 1993 had significant implications for the staff and local community. The site is situated within a National Park and local employment opportunities are limited. The staff and local communities were consulted regarding the issues arising from closure and decommissioning. This consultation influenced the decommissioning strategy for the site, with emphasis placed on the mitigation of the effects of closure. Subsequent studies have shown that the adopted strategies have served to limit the social and economic effects. The experience at Trawsfynydd has proved to be generally applicable at other decommissioning sites. (author)

  6. Deactivation, Decontamination and Decommissioning Project Summaries

    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. Considerations about the European Decommissioning Academy (EDA)

    The concept of the European Decommissioning Academy, to be launched in Slovakia in June 2015, is described. The main goal is to educate a new generation of experts in the decommissioning of nuclear facilities, with focus on VVER type reactors. This year the Academy activities will include lessons, practical exercises in laboratories, and 2 days on-site training at the Jaslovske Bohunice V-1 nuclear power plant. A 4-days' visit to major European decommissioning facilities in Switzerland and Italy is also planned. (orig.)

  8. Bankruptcy potential threatens decommissioning funds, says NRC

    Electric utilities and the Nuclear Regulatory Commission (NRC) disagreed at an America Nuclear Society seminar on how reactor decommissioning should be financed. Industry and state regulators claim it should be handled by standard depreciation methods without involving the NRC, which argues that it must guard against safety risks from industry bankruptices and premature decommissioning. Both sides agreed that funds must be collected, but disagreed on the best method. Their options include the deposit method, external sinking fund, internal reserve, and insurance or surety bond. The NRC feels that too many utilities face possible bankruptcy unrelated to decommissioning or accidents, and that this possibility should outweigh other considerations. 1 table

  9. Studies on the decommissioning cost of nuclear power plants

    This study analyzes the existing literature on decommissioning costs abroad systematically, giving special attention to the OECD member states. Then, the feasible range of decommissioning costs obtained by the analysis is compared to the decommissioning fund being raised by the country's only electric utility, KEPCO. This study concludes that the decommissioning fund is being raised enough to cover future expenses for the decommissioning of nuclear power plants. 1 fig., 13 tabs., 8 refs. (Author)

  10. Decommissioning cost estimates based on the international structure for decommissioning costing

    Decommissioning cost estimates is essential part of decommissioning planning in all stages of nuclear installation lifetime. It has been recognized that there is a variety of formats, content and practice in decommissioning costing, due to the specific national requirement or to different assumptions. These differences make the process of decommissioning costing less transparent and more complicated to review. To solve these issues the document: 'A Proposed Standardised List of Items for Costing Purposes in the Decommissioning of Nuclear Installation' (known as 'Yellow Book') was jointly published by IAEA, OECD/NEA and EC in 1999. After a decade, the document was revised and issued by same organizations under the title: 'International Structure for Decommissioning Costing (ISDC) of Nuclear Installation. ISDC as the list of typical decommissioning activities (could be used also a check-list) provides s general cost structure suitable for use for all types of nuclear installations i.e. power plants, research reactors, fuel cycle facilities or laboratories. The purpose of the ISDC, is to facilitate the communication and to promote uniformity and to provide a common platform in presenting the decommissioning costs. Clear definition of ISDC items supports the common understanding of cost items, i.e. what is behind the cost. ISDC decommissioning activities are organised in a hierarchical structure, with the 1st and 2nd levels being aggregations of basic activities identified at the 3rd level. At (author)

  11. Decommissioning information management in decommissioning planning and operations at AECL (Ref 5054)

    As the AECL Decommissioning program has grown over the past few years, particularly with regard to long-term planning, so has its need to manage the records and information required to support the program. The program encompasses a diverse variety of facilities, including prototype and research reactors, fuel processing facilities, research laboratories, waste processing facilities, buildings, structures, lands and waste storage areas, many of which have changed over time. The decommissioning program involves planning, assessing, monitoring and executing projects to decommission the facilities. The efficient and effective decommissioning planning, assessment, monitoring and execution for the facilities and projects are dependent on a sound information base, upon which decisions can be made. A vital part of this Information Base is the ongoing management of historical facility records, including decommissioning records, throughout the full life cycle of the facilities. This paper describes AECL's and particularly DP and O's approach to: 1) Establishing a decommissioning records and information framework, which identifies what records and information are relevant to decommissioning, prioritizing the decommissioning facilities, identifying sources of relevant information and providing a user-friendly, electronic, search and retrieval tool for facility information accessible to staff. 2) Systematically, gathering, assessing, archiving and identifying important information and making that information available to staff to support their ongoing decommissioning work. 3) Continually managing and enhancing the records and information base and its support infrastructure to ensure its long-term availability. 4) Executing special information enhancement projects, which transform historic records into information for analysis. (author)

  12. ECED 2013: Eastern and Central Europe Decommissioning. International Conference on Decommissioning of Nuclear Facilities. Conference Guide and Book of Abstracts

    The Conference included the following sessions: (I) Opening session (2 contributions); (II) Managerial and Funding Aspects of Decommissioning (5 contributions); (III) Technical Aspects of Decommissioning I (6 contributions); (IV) Experience with Present Decommissioning Projects (4 contributions); (V) Poster Session (14 contributions); (VI) Eastern and Central Europe Decommissioning - Panel Discussion; (VII) Release of Materials, Waste Management and Spent Fuel Management (6 contributions); (VIII) Technical Aspects of Decommissioning II (5 contributions).

  13. Decommissioning of DR 1, Final report

    Lauridsen, Kurt

    2006-01-15

    The report describes the decommissioning activities carried out at the 2kW homogeneous reactor DR 1 at Risoe National Laboratory. The decommissioning work took place from summer 2004 until late autumn 2005. The components with the highest activity, the core vessel the recombiner and the piping and valves connected to these, were dismantled first by Danish Decommissioning's own technicians. Demolition of the control rod house and the biological shield as well as the removal of the floor in the reactor hall was carried out by an external demolition contractor. The building was emptied and left for other use. Clearance measurements of the building showed that radionuclide concentrations were everywhere below the clearance limit set by the Danish nuclear regulatory authorities. Furthermore, measurements on the surrounding area showed that there was no contamination that could be attributed to the operation and decommissioning of DR 1. (au)

  14. Nuclear submarine decommissioning and related environmental problems

    The issue of nuclear powered submarines occupies a particular place among the problems related to nuclear wastes. Nuclear submarines that were withdrawn from military service as well as those intended fro utilization represent a potential source of both nuclear and radiation hazard. By the beginning of 1966 more than one hundred and fifty nuclear powered vessels were decommissioned in Russia both for the reason of expiration of their service life and due to treaties on reduction of strategic offensive weapons. By 200 this number is expected to increase to one hundred and seventy-eighty units. According to published data the number of nuclear submarines decommissioned in USA to date exceeds twenty units. Major problems associated with utilization of nuclear submarines are related to safety and special security measures are to undertaken for decommissioned nuclear submarines. One of the most significant problems is related with management and/or storage of spent fuel from decommissioned nuclear submarines

  15. Safety issues in decommissioning, strategies and regulation

    Many plants throughout the world are undergoing decommissioning. There are some differences in the safety issues associated with decommissioning as compared with operations. These pose challenges to operators, regulators and those responsible for developing policies and strategies.The paper aims to set the scene for future discussion by identifying these issues. This includes regulatory systems, regulating the changing situation and factors that need to be taken into account in developing decommissioning strategies. In particular, the situation in the absence of a disposal route for waste and issues associated with care and maintenance periods are discussed.A key point that is identified is that well considered and justified strategies need to be developed to act as the basis for detailed decommissioning plans. (author)

  16. Health physics considerations in decontamination and decommissioning

    These proceedings contain papers on legal considerations, environmental aspects, decommissioning equipment and methods, instrumentation, applied health physics, waste classification and disposal, and project experience. Separate abstracts have been prepared for individual papers

  17. Decommissioning of DR 1, Final report

    The report describes the decommissioning activities carried out at the 2kW homogeneous reactor DR 1 at Risoe National Laboratory. The decommissioning work took place from summer 2004 until late autumn 2005. The components with the highest activity, the core vessel the recombiner and the piping and valves connected to these, were dismantled first by Danish Decommissioning's own technicians. Demolition of the control rod house and the biological shield as well as the removal of the floor in the reactor hall was carried out by an external demolition contractor. The building was emptied and left for other use. Clearance measurements of the building showed that radionuclide concentrations were everywhere below the clearance limit set by the Danish nuclear regulatory authorities. Furthermore, measurements on the surrounding area showed that there was no contamination that could be attributed to the operation and decommissioning of DR 1. (au)

  18. The cost of decommissioning uranium mill tailings

    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

  19. Decommissioning and disposal costs in Switzerland

    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

  20. Sellafield Decommissioning Programme - Update and Lessons Learned

    Lutwyche, P. R.; Challinor, S. F.

    2003-02-24

    The Sellafield site in North West England has over 240 active facilities covering the full nuclear cycle from fuel manufacture through generation, reprocessing and waste treatment. The Sellafield decommissioning programme was formally initiated in the mid 1980s though several plants had been decommissioned prior to this primarily to create space for other plants. Since the initiation of the programme 7 plants have been completely decommissioned, significant progress has been made in a further 16 and a total of 56 major project phases have been completed. This programme update will explain the decommissioning arrangements and strategies and illustrate the progress made on a number of the plants including the Windscale Pile Chimneys, the first reprocessing plan and plutonium plants. These present a range of different challenges and requiring approaches from fully hands on to fully remote. Some of the key lessons learned will be highlighted.

  1. Decommissioning: from COMECON to CIS and RUSSIA

    NPP decommissioning experience in the USSR and the Commonwealth Independent States (CIS) members was actively accumulated over ten years since 1982, by Russian experts in particular. Nevertheless, it is not well renowned throughout the scientists and engineers from both Russia and other near' (the CIS) and 'distant' foreign countries. A general review on NPP decommissioning in the CIS has been published just now. An unshown before NPP decommissioning issues are presented in the report. The first program on NPP decommissioning was developed under the aegis of COMECOM with the leadership of Russian experts. The most considerable results are the feasibility studies of Armenia NPP, the Novovoronezh NPP first construction stage (two units) and Bohunice V - 1 unit. (J.P.N.)

  2. Remedial investigation report for J-Field, Aberdeen Proving Ground, Maryland. Volume 1: Remedial investigation results

    Yuen, C. R.; Martino, L. E.; Biang, R. P.; Chang, Y. S.; Dolak, D.; Van Lonkhuyzen, R. A.; Patton, T. L.; Prasad, S.; Quinn, J.; Rosenblatt, D. H.; Vercellone, J.; Wang, Y. Y.

    2000-03-14

    This report presents the results of the remedial investigation (RI) conducted at J-Field in the Edgewood Area of Aberdeen Proving Ground (APG), a U.S. Army installation located in Harford County, Maryland. Since 1917, activities in the Edgewood Area have included the development, manufacture, and testing of chemical agents and munitions and the subsequent destruction of these materials at J-Field by open burning and open detonation. These activities have raised concerns about environmental contamination at J-Field. This RI was conducted by the Environmental Conservation and Restoration Division, Directorate of Safety, Health and Environmental Division of APG, pursuant to requirements outlined under the Comprehensive Environmental Response, Compensation, and Liability Act, as amended (CERCLA). The RI was accomplished according to the procedures developed by the U.S. Environmental Protection Agency (EPA 1988). The RI provides a comprehensive evaluation of the site conditions, nature of contaminants present, extent of contamination, potential release mechanisms and migration pathways, affected populations, and risks to human health and the environment. This information will be used as the basis for the design and implementation of remedial actions to be performed during the remedial action phase, which will follow the feasibility study (FS) for J-Field.

  3. Contamination source review for Building E3180, Edgewood Area, Aberdeen Proving Ground, Maryland

    Zellmer, S.D.; Smits, M.P.; Rueda, J.; Zimmerman, R.E.

    1995-09-01

    This report was prepared by Argonne National Laboratory (ANL) to document the results of a contamination source review of Building E3180 at the Aberdeen Proving Ground (APG) in Maryland. The report may be used to assist the US Army in planning for the future use or disposition of this building. The review included a historical records search, physical inspection, photographic documentation, geophysical investigation, collection of air samples, and review of available records regarding underground storage tanks associated with Building E3180. The field investigations were performed by ANL during 1994. Building,E3180 (current APG designation) is located near the eastern end of Kings Creek Road, north of Kings Creek, and about 0.5 miles east of the airstrip within APG`s Edgewood Area. The building was constructed in 1944 as a facsimile of a Japanese pillbox and used for the development of flame weapons systems until 1957 (EAI Corporation 1989). The building was not used from 1957 until 1965, when it was converted and used as a flame and incendiary laboratory. During the 1970s, the building was converted to a machine (metal) shop and used for that purpose until 1988.

  4. Ecological risk assessment of depleted uranium in the environment at Aberdeen Proving Ground

    A preliminary ecological risk assessment was conducted to evaluate the effects of depleted uranium (DU) in the Aberdeen Proving Ground (APG) ecosystem and its potential for human health effects. An ecological risk assessment of DU should include the processes of hazard identification, dose-response assessment, exposure assessment, and risk characterization. Ecological risk assessments also should explicitly examine risks incurred by nonhuman as well as human populations, because risk assessments based only on human health do not always protect other species. To begin to assess the potential ecological risk of DU release to the environment we modeled DU transport through the principal components of the aquatic ecosystem at APG. We focused on the APG aquatic system because of the close proximity of the Chesapeake Bay and concerns about potential impacts on this ecosystem. Our objective in using a model to estimate environmental fate of DU is to ultimately reduce the uncertainty about predicted ecological risks due to DU from APG. The model functions to summarize information on the structure and functional properties of the APG aquatic system, to provide an exposure assessment by estimating the fate of DU in the environment, and to evaluate the sources of uncertainty about DU transport

  5. Remedial investigation report for J-Field, Aberdeen Proving Ground, Maryland. Volume 1: Remedial investigation results

    This report presents the results of the remedial investigation (RI) conducted at J-Field in the Edgewood Area of Aberdeen Proving Ground (APG), a U.S. Army installation located in Harford County, Maryland. Since 1917, activities in the Edgewood Area have included the development, manufacture, and testing of chemical agents and munitions and the subsequent destruction of these materials at J-Field by open burning and open detonation. These activities have raised concerns about environmental contamination at J-Field. This RI was conducted by the Environmental Conservation and Restoration Division, Directorate of Safety, Health and Environmental Division of APG, pursuant to requirements outlined under the Comprehensive Environmental Response, Compensation, and Liability Act, as amended (CERCLA). The RI was accomplished according to the procedures developed by the U.S. Environmental Protection Agency (EPA 1988). The RI provides a comprehensive evaluation of the site conditions, nature of contaminants present, extent of contamination, potential release mechanisms and migration pathways, affected populations, and risks to human health and the environment. This information will be used as the basis for the design and implementation of remedial actions to be performed during the remedial action phase, which will follow the feasibility study (FS) for J-Field

  6. Contamination source review for Building E3162, Edgewood Area, Aberdeen Proving Ground, Maryland

    Miller, G.A.; Draugelis, A.K.; Rueda, J.; Zimmerman, R.E.

    1995-09-01

    This report was prepared by Argonne National Laboratory (ANL) to document the results of a contamination source review for Building E3162 at the Aberdeen Proving Ground (APG) in Maryland. The report may be used to assist the US Army in planning for the future use or disposition of this building. The review included a historical records search, physical inspection, photographic documentation, geophysical investigation, and collection of air samples. The field investigations were performed by ANL during 1994 and 1995. Building E3162 (APG designation) is part of the Medical Research Laboratories Building E3160 Complex. This research laboratory complex is located west of Kings Creek, east of the airfield and Ricketts Point Road, and south of Kings Creek Road in the Edgewood Area of APG. The original structures in the E3160 Complex were constructed during World War 2. The complex was originally used as a medical research laboratory. Much of the research involved wound assessment involving chemical warfare agents. Building E3162 was used as a holding and study area for animals involved in non-agent burns. The building was constructed in 1952, placed on inactive status in 1983, and remains unoccupied. Analytical results from these air samples revealed no distinguishable difference in hydrocarbon and chlorinated solvent levels between the two background samples and the sample taken inside Building E3162.

  7. Environmental geophysics at the Southern Bush River Peninsula, Aberdeen Proving Ground, Maryland

    Davies, B.E.; Miller, S.F.; McGinnis, L.D. [and others

    1995-05-01

    Geophysical studies have been conducted at five sites in the southern Bush River Peninsula in the Edgewood Area of Aberdeen Proving Ground, Maryland. The goals of the studies were to identify areas containing buried metallic objects and to provide diagnostic signatures of the hydrogeologic framework of the site. These studies indicate that, during the Pleistocene Epoch, alternating stands of high and low sea level resulted in a complex pattern of channel-fill deposits. Paleochannels of various sizes and orientations have been mapped throughout the study area by means of ground-penetrating radar and EM-31 techniques. The EM-31 paleochannel signatures are represented onshore either by conductivity highs or lows, depending on the depths and facies of the fill sequences. A companion study shows the features as conductivity highs where they extend offshore. This erosional and depositional system is environmentally significant because of the role it plays in the shallow groundwater flow regime beneath the site. Magnetic and electromagnetic anomalies outline surficial and buried debris throughout the areas surveyed. On the basis of geophysical measurements, large-scale (i.e., tens of feet) landfilling has not been found in the southern Bush River Peninsula, though smaller-scale dumping of metallic debris and/or munitions cannot be ruled out.

  8. Natural attenuation of chlorinated volatile organic compounds in a freshwater tidal wetland, Aberdeen Proving Ground, Maryland

    Lorah, Michelle M.; Olsen, Lisa D.; Smith, Barrett L.; Johnson, Mark A.; Fleck, William B.

    1997-01-01

    Ground-water contaminant plumes that are flowing toward or currently discharging to wetland areas present unique remediation problems because of the hydrologic connections between ground water and surface water and the sensitive habitats in wetlands. Because wetlands typically have a large diversity of microorganisms and redox conditions that could enhance biodegradation, they are ideal environments for natural attenuation of organic contaminants, which is a treatment method that would leave the ecosystem largely undisturbed and be cost effective. During 1992-97, the U.S. Geological Survey investigated the natural attenuation of chlorinated volatile organic compounds (VOC's) in a contaminant plume that discharges from a sand aquifer to a freshwater tidal wetland along the West Branch Canal Creek at Aberdeen Proving Ground, Maryland. Characterization of the hydrogeology and geochemistry along flowpaths in the wetland area and determination of the occurrence and rates of biodegradation and sorption show that natural attenuation could be a feasible remediation method for the contaminant plume that extends along the West Branch Canal Creek.

  9. Decommissioning of a 5 MW research reactor

    The complete decommissioning of a research reactor is described. Planning and execution of all activities, including schedules, budgets, waste management, health physics and subcontracted operations are presented. Flexibility in operations was obtained by using the operating staff as the decommissioning progressed. Totals for waste shipments and costs are given. Final site conditions are presented along with a description of the subsequent use of the facility. (author)

  10. Russian nuclear-powered submarine decommissioning

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

  11. Decommissioning Project Manager's Implementing Instructions (PMII)

    Decommissioning Project personnel are responsible for complying with these PMII. If at any time in the performance of their duties a conflict between these instructions and other written or verbal direction is recognized or perceived, the supervisor or worker shall place his/her work place in a safe condition, stop work, and seek resolution of the conflict from the Decommissioning Project Manager or his designee

  12. Risk Management of Large Component in Decommissioning

    Nah, Kyung Ku; Kim, Tae Ryong [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

    2014-10-15

    The need for energy, especially electric energy, has been dramatically increasing in Korea. Therefore, a rapid growth in nuclear power development has been achieved to have about 30% of electric power production. However, such a large nuclear power generation has been producing a significant amount of radioactive waste and other matters such as safety issue. In addition, owing to the severe accidents at the Fukushima in Japan, public concerns regarding NPP and radiation hazard have greatly increased. In Korea, the operation of KORI 1 has been scheduled to be faced with end of lifetime in several years and Wolsong 1 has been being under review for extending its life. This is the reason why the preparation of nuclear power plant decommissioning is significant in this time. Decommissioning is the final phase in the life-cycle of a nuclear facility and during decommissioning operation, one of the most important management in decommissioning is how to deal with the disused large component. Therefore, in this study, the risk in large component in decommissioning is to be identified and the key risk factor is to be analyzed from where can be prepared to handle decommissioning process safely and efficiently. Developing dedicated acceptance criteria for large components at disposal site was analyzed as a key factor. Acceptance criteria applied to deal with large components like what size of those should be and how to be taken care of during disposal process strongly affect other major works. For example, if the size of large component was not set up at disposal site, any dismantle work in decommissioning is not able to be conducted. Therefore, considering insufficient time left for decommissioning of some NPP, it is absolutely imperative that those criteria should be laid down.

  13. Decommissioning of the BR3 PWR

    The objectives, programme and main achievements of SCK-CEN's decommissioning programme in 1997 are summarised. Particular emphasis is on the BR3 decommissioning project. In 1997, auxiliary equipment and loops were dismantled; concrete antimissile slabs were decontaminated; the radiology of the primary loop was modelled; the quality assurance procedure for dismantling loops and equipment were implemented; a method for the dismantling of the reactor pressure vessel was selected; and contaminated thermal insulation of the primary loop containing asbestos was removed

  14. Risk Management of Large Component in Decommissioning

    The need for energy, especially electric energy, has been dramatically increasing in Korea. Therefore, a rapid growth in nuclear power development has been achieved to have about 30% of electric power production. However, such a large nuclear power generation has been producing a significant amount of radioactive waste and other matters such as safety issue. In addition, owing to the severe accidents at the Fukushima in Japan, public concerns regarding NPP and radiation hazard have greatly increased. In Korea, the operation of KORI 1 has been scheduled to be faced with end of lifetime in several years and Wolsong 1 has been being under review for extending its life. This is the reason why the preparation of nuclear power plant decommissioning is significant in this time. Decommissioning is the final phase in the life-cycle of a nuclear facility and during decommissioning operation, one of the most important management in decommissioning is how to deal with the disused large component. Therefore, in this study, the risk in large component in decommissioning is to be identified and the key risk factor is to be analyzed from where can be prepared to handle decommissioning process safely and efficiently. Developing dedicated acceptance criteria for large components at disposal site was analyzed as a key factor. Acceptance criteria applied to deal with large components like what size of those should be and how to be taken care of during disposal process strongly affect other major works. For example, if the size of large component was not set up at disposal site, any dismantle work in decommissioning is not able to be conducted. Therefore, considering insufficient time left for decommissioning of some NPP, it is absolutely imperative that those criteria should be laid down

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

    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

  16. Safety in decommissioning of research reactors

    This Guide covers the technical and administrative considerations relevant to the nuclear aspects of safety in the decommissioning of reactors, as they apply to the reactor and the reactor site. While the treatment, transport and disposal of radioactive wastes arising from decommissioning are important considerations, these aspects are not specifically covered in this Guide. Likewise, other possible issues in decommissioning (e.g. land use and other environmental issues, industrial safety, financial assurance) which are not directly related to radiological safety are also not considered. Generally, decommissioning will be undertaken after planned final shutdown of the reactor. In some cases a reactor may have to be decommissioned following an unplanned or unexpected event of a series or damaging nature occurring during operation. In these cases special procedures for decommissioning may need to be developed, peculiar to the particular circumstances. This Guide could be used as a basis for the development of these procedures although specific consideration of the circumstances which create the need for them is beyond its scope

  17. The Importance of Experience Based Decommissioning Planning

    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)

  18. Investigation on decommissioning of smelting conversion facilities

    To carry out decommissioning of smelting and conversion plant (containing apparatuses) in future, it is required to develop planned businesses. As JNC constructed a general WBS on the decommissioning on last fiscal years, further detailed investigations on WBS is necessary for promotion of its operations. Therefore, aiming at construction of detailed WBS with less than the fourth level, intention of updating on subdivision and radioactive decommission, and addition of data on determining methods on polluting condition of uranium series wastes, here were reported results on four items, such as reviewing of WBS on the decommissioning, construction of detailed WBS with less than the fourth level, updating of databases on subdivision and decommission, and data addition on determining methods on polluting conditions of uranium series wastes to the subdivision and the decommission databases. On this fiscal year, it was carried out investigation on contents of WBS on the 'Construction of investigating items on subdivision and removal engineerings (sixteen sheets of construction figure)' to consult WBS with less than the fourth level for eight sheets of figure in details on the second item, to carry out literature retrieval on reuse since 1998, to input sixty extracted data to database on the third item, and to carry out literature retrieval on the determining method since 1990, to input eight extracted data to database by preparing a new term in 'testing'. (G.K.)

  19. Decommissioning cost estimating and contingency application

    The funding of nuclear power plant decommissioning has matured into an integral part of utility planning. State public utility commission regulators and the US Nuclear Regulatory Commission have recognized the need to assure the availability of funds to safely decommission these facilities at the end of their useful lives. The cost estimates for decommissioning need to reflect the changes in labor and material costs due to inflation, changes in waste disposal costs for packaging, transporting and burying radioactive materials, and the site-specific factors for each unit that account for differences in plant design and construction. Decommissioning activities involve remote tooling to segment the reactor vessel and internals, decontamination of contaminated systems to reduce occupational exposure, controlled blasting to demolish concrete structures, and removal and disposal of radioactive wastes by controlled burial. The unforeseeable problems encountered in performing these activities result in additional costs that are accounted for through contingency. The recent progress in nuclear power plant decommissioning cost estimation and contingency application are discussed. The important factor to be included in planning for the establishment of a decommissioning fund are identified, and typical results of recent estimates are provided. The nuclear industry is probably one of the first industries to plan for the eventual retirement of its facilities, and the public needs to be aware of these efforts

  20. Decommissioning Licensing Process of Nuclear Installations in Spain

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

  1. Decommissioning of nuclear power plants in the Slovak Republic

    The article deals with the current situation in nuclear power plant decommissioning in the Slovak Republic. Slovak NPPs which are being operated or decommissioned are listed, and the major aspects influencing the selection of the most convenient decommissioning option are outlined. Some of these aspects, such as the responsibility for the decommissioning, financing, the object of decommissioning, radioactive waste management, and decommissioning legislation are discussed in more detail. The current state of decommissioning of NPPs in the Slovak Republic is highlighted. It is concluded that the Slovenske Elektrarne company, which is the utility responsible for NPP decommissioning in the Slovak Republic, guarantees feasibility of decommissioning within the required time-scale while observing the relevant safety principles and minimizing all adverse impacts on the personnel, on the public living in the surroundings, and on the environment. (author)

  2. Problems in decommissioning uranium exploration facility and monitoring parameters after decommission

    This paper discussed the problems in the decommission of uranium exploration facilities. Tailings with the uranium over cut-off grade was suggested to fill back to the pit, while those under cut-off grade can be buried in shallow depth. The parameters to monitor the facility after decommission was also discussed in the paper. (author)

  3. International Atomic Energy Agency activities in decommissioning

    Full text: The International Atomic Energy Agency (IAEA) has been addressing the safety and technical issues of decommissioning for over 20 years, but their focus has been primarily on planning. Up to know, the activities have been on an ad hoc basis and sometimes, important issues have been missed. A new Action Plan on the Decommissioning of Nuclear Facilities has recently been approved by the Agency's board of Governors which will focus the Agency's efforts and ensure that our Member States' concerns are addressed. The new initiatives associated with this Action Plan will help ensure that decommissioning activities in the future are performed in a safe and coherent manner. The International Atomic Energy Agency (IAEA) has been preparing safety and technical documents concerning decommissioning since the mid-1980's. There have been over 30 documents prepared that provide safety requirements, guidance and supporting technical information. Many of these documents are over 10 years old and need updating. The main focus in the past has been on planning for decommissioning. During the past five years, a set of Safety Standards have been prepared and issued to provide safety requirements and guidance to Member States. However, decommissioning was never a real priority with the Agency, but was something that had to be addressed. To illustrate this point, the first requirements documents on decommissioning were issued as part of a Safety Requirements [1] on pre-disposal management of radioactive waste. It was felt that decommissioning did not deserve its own document because it was just part of the normal waste management process. The focus was mostly on waste management. The Agency has assisted Member States with the planning process for decommissioning. Most of these activities have been focused on nuclear power plants and research reactors. Now, support for the decommissioning of other types of facilities is being requested. The Agency is currently providing technical

  4. Decommissioning of nuclear facilities: Germany’s experience

    Germany has gained considerable experience in the decommissioning of nuclear facilities since the 1970s. Currently 16 nuclear power plants, both power and prototype reactors, are at different stages of decommissioning. Three decommissioning projects have been completed. Future tasks in Germany are the completion of the current decommissioning projects and the decommissioning of the nuclear facilities that are still operating once they have reached the end of their operating life. The number of parallel decommissioning projects of large scale facilities required by the phase-out of nuclear power could pose challenges in terms of the availability and maintenance of competences at all levels (operators, regulatory body, technical support organizations, and suppliers)

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

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

  6. Securing decommissioning funds. Why organization matters?

    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

  7. Decontamination and decommissioning costing efforts

    The US Department of Energy (DOE), Office of Environmental Management (EM) is responsible for decontamination and decommissioning (D and D) of a wide variety of facilities ranging from reactors to fuel cycle processing buildings throughout the country. The D and D effort represents a large financial investment and a considerable challenge for the DOE and contractor program and project managers. Specifically, the collection and sharing of useful cost data and development of cost estimates are difficult in an environment in which the availability of these data is limited and the technologies and project methods are evolving. Sound cost data are essential for developing project cost estimates; baselines; and project management, benchmarking, and continuous improvement purposes. This paper will focus on some initiatives that in coordination with other federal agencies and international organizations, the DOE Environmental Management Applied Cost Engineering (ACE) Team is taking to standardize cost definitions; to collect, analyze, and report D and D cost data; and to develop fast, accurate, and easy-to-use cost-estimating models for D and D work

  8. Decommissioning of fast reactors after sodium draining

    Acknowledging the importance of passing on knowledge and experience, as well mentoring the next generation of scientists and engineers, and in response to expressed needs by Member States, the IAEA has undertaken concrete steps towards the implementation of a fast reactor data retrieval and knowledge preservation initiative. Decommissioning of fast reactors and other sodium bearing facilities is a domain in which considerable experience has been accumulated. Within the framework and drawing on the wide expertise of the Technical Working Group on Fast Reactors (TWG-FR), the IAEA has initiated activities aiming at preserving the feedback (lessons learned) from this experience and condensing those to technical recommendations on fast reactor design features that would ease their decommissioning. Following a recommendation by the TWG-FR, the IAEA had convened a topical Technical Meeting (TM) on 'Operational and Decommissioning Experience with Fast Reactors', hosted by CEA, Centre d'Etudes de Cadarache, France, from 11 to 15 March 2002 (IAEA-TECDOC- 1405). The participants in that TM exchanged detailed technical information on fast reactor operation and decommissioning experience with various sodium cooled fast reactors, and, in particular, reviewed the status of the various decommissioning programmes. The TM concluded that the decommissioning of fast reactors to reach safe enclosure presented no major difficulties, and that this had been accomplished mainly through judicious adaptation of processes and procedures implemented during the reactor operation phase, and the development of safe sodium waste treatment processes. However, the TM also concluded that, on the path to achieving total dismantling, challenges remain with regard to the decommissioning of components after sodium draining, and suggested that a follow-on TM be convened, that would provide a forum for in-depth scientific and technical exchange on this topic. This publication constitutes the Proceedings of

  9. Decommissioning Challenges, strategy and programme development

    This document gathers 4 short articles. The first one presents the IAEA decommissioning activities. These activities include: -) the development and implementation of the international action on decommissioning, -) the provision of experts and equipment to assist member states, -) networking activities such as training or exchange of knowledge and experience. The second article presents the work program of the Nea (nuclear energy agency) in the field of decommissioning and reports on the lessons that have been learnt. Among these lessons we can quote: -) selecting a strategy for decommissioning and funding it adequately, -) regulating the decommissioning of nuclear activities, -) thinking of the future in terms of reusing materials, buildings and sites, -) involving local and regional actors in the decommissioning process from decision-making to dismantling work itself, and -) increasing transparency in decision-making in order to build trust. The third article presents the management of radioactive wastes in France. This management is based on the categorization of wastes in 6 categories according to both the activity level and the radioactive half-life T: 1) very low activity, 2) low activity and T 31 years, 4) intermediate activity and T 31 years, and 6) high activity. For categories 1, 2, 3 and 5, the waste treatment process and the disposal places have been operating for a long time while for categories 4 and 6, the disposal places are still being studied: low-depth repository and deep geological repository respectively. The last article presents the action of the US Department of energy in decommissioning activities and environmental remediation, the example of the work done at the ancient nuclear site of Rocky Flats gives an idea of the magnitude and complexity of the operations made. (A.C.)

  10. Work plan for conducting an ecological risk assessment at J-Field, Aberdeen Proving Ground, Maryland

    Hlohowskyj, I.; Hayse, J.; Kuperman, R. [Argonne National Lab., IL (United States). Environmental Assessment Div.] [and others

    1995-03-01

    The Environmental Management Division of Aberdeen Proving Ground (APG), Maryland, is conducting a remedial investigation and feasibility study (RI/FS) of the J-Field area at APG pursuant to the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), as amended. J-Field is within the Edgewood Area of APG in Harford County, Maryland, and activities at the Edgewood Area since World War II have included the development, manufacture, testing, and destruction of chemical agents and munitions. The J-Field site was used to destroy chemical agents and munitions by open burning and open detonation. This work plan presents the approach proposed to conduct an ecological risk assessment (ERA) as part of the RI/FS program at J-Field. This work plan identifies the locations and types of field studies proposed for each area of concern (AOC), the laboratory studies proposed to evaluate toxicity of media, and the methodology to be used in estimating doses to ecological receptors and discusses the approach that will be used to estimate and evaluate ecological risks at J-Field. Eight AOCs have been identified at J-Field, and the proposed ERA is designed to evaluate the potential for adverse impacts to ecological receptors from contaminated media at each AOC, as well as over the entire J-Field site. The proposed ERA approach consists of three major phases, incorporating field and laboratory studies as well as modeling. Phase 1 includes biotic surveys of the aquatic and terrestrial habitats, biological tissue sampling and analysis, and media toxicity testing at each AOC and appropriate reference locations. Phase 2 includes definitive toxicity testing of media from areas of known or suspected contamination or of media for which the Phase 1 results indicate toxicity or adverse ecological effects. In Phase 3, the uptake models initially developed in Phase 2 will be finalized, and contaminant dose to each receptor from all complete pathways will be estimated.

  11. Potential health impacts from range fires at Aberdeen Proving Ground, Maryland.

    Willians, G.P.; Hermes, A.M.; Policastro, A.J.; Hartmann, H.M.; Tomasko, D.

    1998-03-01

    This study uses atmospheric dispersion computer models to evaluate the potential for human health impacts from exposure to contaminants that could be dispersed by fires on the testing ranges at Aberdeen Proving Ground, Maryland. It was designed as a screening study and does not estimate actual human health risks. Considered are five contaminants possibly present in the soil and vegetation from past human activities at APG--lead, arsenic, trichloroethylene (TCE), depleted uranium (DU), and dichlorodiphenyltrichloroethane (DDT); and two chemical warfare agents that could be released from unexploded ordnance rounds heated in a range fire--mustard and phosgene. For comparison, dispersion of two naturally occurring compounds that could be released by burning of uncontaminated vegetation--vinyl acetate and 2-furaldehyde--is also examined. Data from previous studies on soil contamination at APG are used in conjunction with conservative estimates about plant uptake of contaminants, atmospheric conditions, and size and frequency of range fires at APG to estimate dispersion and possible human exposure. The results are compared with US Environmental Protection Agency action levels. The comparisons indicate that for all of the anthropogenic contaminants except arsenic and mustard, exposure levels would be at least an order of magnitude lower than the corresponding action levels. Because of the compoundingly conservative nature of the assumptions made, they conclude that the potential for significant human health risks from range fires is low. The authors recommend that future efforts be directed at fire management and control, rather than at conducting additional studies to more accurately estimate actual human health risk from range fires.

  12. Potential health impacts from range fires at Aberdeen Proving Ground, Maryland

    This study uses atmospheric dispersion computer models to evaluate the potential for human health impacts from exposure to contaminants that could be dispersed by fires on the testing ranges at Aberdeen Proving Ground, Maryland. It was designed as a screening study and does not estimate actual human health risks. Considered are five contaminants possibly present in the soil and vegetation from past human activities at APG--lead, arsenic, trichloroethylene (TCE), depleted uranium (DU), and dichlorodiphenyltrichloroethane (DDT); and two chemical warfare agents that could be released from unexploded ordnance rounds heated in a range fire--mustard and phosgene. For comparison, dispersion of two naturally occurring compounds that could be released by burning of uncontaminated vegetation--vinyl acetate and 2-furaldehyde--is also examined. Data from previous studies on soil contamination at APG are used in conjunction with conservative estimates about plant uptake of contaminants, atmospheric conditions, and size and frequency of range fires at APG to estimate dispersion and possible human exposure. The results are compared with US Environmental Protection Agency action levels. The comparisons indicate that for all of the anthropogenic contaminants except arsenic and mustard, exposure levels would be at least an order of magnitude lower than the corresponding action levels. Because of the compoundingly conservative nature of the assumptions made, they conclude that the potential for significant human health risks from range fires is low. The authors recommend that future efforts be directed at fire management and control, rather than at conducting additional studies to more accurately estimate actual human health risk from range fires

  13. Economical aspect of the decommissioning for NPP

    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)

  14. Panel Discussion - Eastern and Central Europe decommissioning

    In conjunction with technical session 'Experience with Present Decommissioning Projects' the Panel Discussion is organized in the frame of ECED 2013 Conference. The main purposes of the panel was to analyse more in details the information given in the previous session and mainly to answer the questions from the audience. The panel was focused on the on-going decommissioning projects and on the projects in the final phase of preparation in the region of Eastern and Central Europe as follows: - Ignalina Nuclear Power Plant in Lithuania - RBMK-1500 reactors; - Chernobyl Nuclear Power Plant in Ukraine - RBMK-1000 reactors; - Kozloduy Nuclear Power Plant in Bulgaria - VVER-440 reactors; - Metsamor Armenian Nuclear Power Plant - VVER-440 reactors; - Greifswald Nuclear Power Plant in Germany (former East Germany) - VVER-440 reactors; - V1 Nuclear Power Plant in Slovakia - VVER-440 reactors; - A1 Nuclear Power Plant in Slovakia - Heavy Water Gas Cooled Reactor; shutdown after accident. The panel speakers listed the skilled and experienced representatives from all above mentioned countries and from Russian Federation where many decommissioning projects are ongoing or under preparation. The region of Eastern and Central Europe has actually become very important in the field of decommissioning and the lessons learned from the performed projects could make a significant base for decommissioning projects worldwide.

  15. Legislative conditions for decommissioning nuclear facilities

    Decommissioning nuclear facilities, like building and operating them, is associated with legal conditions spelt out in the German Atomic Energy Act and other applicable legal regulations. Under the Atomic Energy Act, the basis is the required permit for decommissioning with the main requirement that all necessary precautions against damage have been taken in the light of the state of the art. Applicability needs to be examined in each individual case, and every decommissioning step must reduce the risk potential by further removing radioactive plant components. Considerable expense is entailed by the Environmental Impact Assessment (EIA) required under the directives of the European Union. The directive in existence so far required an EIA only for the construction and operation of nuclear power plants, and was executed in Germany with the EIA Act of 1990. This EU directive is being extended so as to include also decommissioning activities; the integration of this extension into national law in Germany is still in the stage of a ministerial draft bill. In the licensing procedure under the Atomic Energy Act, the basic question arises with respect to the demolition of plants whether the 'entire range planned' of decommissioning measures requires a step-by-step procedure with a so-called positive overall decision. This question arises out of the comparison between the construction phase and the demolition phase. Basically, in very few special cases, an analogy can be drawn to the requirement of a preliminary positive overall decision. (orig.)

  16. Management of Sellafield site decommissioning - recent experiences

    History of the British Nuclear Site Sellafield - located in Western Cambria goes back to 1940, when it served for military and energy independence tasks in the Great Britain. Since then Sellafield served as the major British nuclear site providing wide range of services to the British nuclear industry, including fuel and waste storage/management, nuclear fuel reprocessing, electricity production and decommissioning. Currently the Sellafield site is one of the largest site under decommissioning facing serious challenges associated with the process and cost management. In November 2008 the Nuclear Management Partners, the consortium consisting URS Washington Group, AMEC and AREVA NC, were awarded the contract as the new Parent Body Organization of Sellafield Ltd. that provides management expertise and governance to the client (Nuclear Decommissioning Authority). Since 2008 AMEC has gained extensive experiences from management of complex decommissioning projects that are applicable across different geographies and projects of similar nature. Presentation describes the development of the process system of the project management from the side of PBO as well as complex scheme of the Sellafield site decommissioning project. (author)

  17. Decommissioning database of V1 NPP

    Since 2001, the preparation of V1 NPP practical decommissioning has been supported and partly financed by the Bohunice International Decommissioning Support Fund (BIDSF), under the administration of the European Bank for Reconstruction and Development. AMEC Nuclear Slovakia, together with partners STM Power and EWN GmbH, have been carrying out BIDSF B6.4 project - Decommissioning database development (June 2008 until July 2010). The main purpose of the B6.4 project is to develop a comprehensive physical and radiological inventory database to support RAW management development of the decommissioning studies and decommissioning project of Bohunice V1 NPP. AMEC Nuclear Slovakia was responsible mainly for DDB design, planning documents and physical and radiological characterization including sampling and analyses of the plant controlled area. After finalization of all activities DDB includes over 75.000 records related to individual equipment and civil structures described by almost 3.000.000 parameters. On the basis of successful completion of the original contract the amendment was signed between JAVYS and Consultant's Consortium related to experimental characterization of NPP activated components. The works within this amendment have been still running. (authors)

  18. Verification for radiological decommissioning - Lessons learned

    During the past 10 years, the Environmental Survey and Site Assessment Program (ESSAP) at Oak ridge Associated Universities has performed radiological surveys to confirm the adequacy of cleanup and/or decommissioning actions at sites and facilities where radioactive materials have been handled. These surveys are part of the independent oversight programs of the US Department of Energy (DOE) and the US Nuclear Regulatory Commission (NRC). Results of verification activities have been discouraging. Numerous independent surveys have identified residual contamination requiring further remediation; in some cases, initial decontamination and postremedial action monitoring were totally inadequate. While participating in decommission projects, ESSAP learned valuable lessons and has given this information to regulating agencies and decommissioning sites. The goal of this presentation is to highlight the difficulties encountered by ESSAP in its involvement with NRC and DOE decommissioning projects. Decommissioning projects require teamwork, and success depends to a large degree on the communication, cooperation, and coordination of efforts among the individual organizations involved. This information could be used by organizations involved in future decontamination projects to avoid some of the pitfalls associated with this process

  19. Closing responsibilities: decommissioning and the law

    Laws change over time, with the times. Interpretations of old laws shift and the need for new laws emerges. There are endless reasons for these necessary changes, but the basic impetus is the changing nature of societal circumstance. Fifty years ago there were no laws directly governing nuclear power in any way. Today we know that nuclear power touches people from their wallets to their descendants. Currently, many laws related to nuclear power are in place, laws which protect all sectors of society from electricity generating bodies to a newborn child, and the Chernobyl accident has broadened the legal ramifications of nuclear power even more. This expanding body of nuclear law reflects our expanding understanding of nuclear power from its technical beginnings to its societal consequences and implications. The law is now beginning to reflect the growing significance of decommissioning. What are the relationships between decommissioning and the existing laws, government agencies, and policies? Ironically, although the UK will lead the world in addressing decommissioning responsibilities, there are no explicit laws in place to govern the process. In the absence of specific legislation governing decommissioning, the primary responsibilities fall to the operators of the power plants, a circumstance not lost on those involved in privatization. In this chapter, the wide and varied legal ramifications of decommissioning are examined. (author)

  20. Current trends in decommissioning and environmental remediation of nuclear facilities

    The decommissioning and environmental remediation of civil nuclear facilities represents a considerable challenge for the countries involved in this activity around the world. It includes aspects and problems associated with management, technology, safety and the environment. Over the past few decades, operators worldwide have acquired important experience in the decommissioning and environmental remediation of nuclear sites. A large number of nuclear facilities have ceased operations, and it is envisaged that this number will increase considerably over the coming years. Seventeen power reactors have already been decommissioned, out of more than 150 power reactors shut down or undergoing decommissioning, while more than 180 research reactors have been shut down or are being decommissioned with more than 300 already fully decommissioned. A total of 170 other nuclear cycle facilities have been shut down or are being decommissioned and a further 125 have been completely decommissioned. Spain is one of the countries with experience and activity under way in this field

  1. Treatment of mine-water from decommissioning uranium mines

    Treatment methods for mine-water from decommissioning uranium mines are introduced and classified. The suggestions on optimal treatment methods are presented as a matter of experience with decommissioned Chenzhou Uranium Mine

  2. Detritiation studies for JET decommissioning

    JET is the world largest tokamak and has the capacity of operating with a tritium plasma. Three experimental campaigns, the Preliminary Tritium Experiment (0.1g T2) in 1991, the Trace Tritium Experiment (5g T2) in 2005, and the large experiment, the Deuterium-Tritium Experiment (DTE1) (100g T2) in 1997, were carried out at JET with tritium plasmas. In DTE1 about 35 grams of tritium were fed directly into the vacuum vessel, with about 30% of this tritium being retained inside the vessel. In several years time JET will cease experimental operations and enter a decommissioning phase. In preparation for this the United Kingdom Atomic Energy Authority, the JET Operator, has been carrying out studies of various detritiation techniques. The materials which have been the subject of these studies include solid materials, such as various metals (Inconel 600 and 625, stainless steel 316L, beryllium, ''oxygen-free'' copper, aluminium bronze), carbon fibre composite tiles, ''carbon'' flakes and dust present in the vacuum vessel and also soft housekeeping materials. Liquid materials include organic liquids, such as vacuum oils and scintillation cocktails, and water. Detritiation of gas streams was also investigated. The purpose of the studies was to select and experimentally prove primary and auxiliary technologies for in-situ detritiation of in-vessel components and ex-situ detritiation of components removed from the vessel. The targets of ex-vessel detritiation were a reduction of the tritium inventory in and the rate of tritium out-gassing from the materials, and conversion, if possible, of intermediate level waste to low level waste and a reduction in volume of waste for disposal. The results of experimental trials and their potential application are presented. (orig.)

  3. Decommissioning of research nuclear reactor WWR-S Bucharest. Analysis, justification and selection of decommissioning strategy

    The decommissioning of Research Nuclear Reactor WWR-S Bucharest involves the removal of the radioactive and hazardous materials to enable the facility to be released and not represent a further risk to human health and the environment. The National Institute of Physics and Nuclear Engineering has overall responsibilities in decommissioning including actions of contractors, submit a decommissioning plan to the regulatory body for approval and no decommissioning activities shall begin without the appropriate approval of the regulatory body. A very important aspect of decommissioning is analysis, justification and selection of decommissioning strategy. There are three strategies: Immediate Dismantling, Safe Enclosure, and Entombment. These strategies have been analyzed taking into account: - Future use of site and facilities; - Infrastructure of the specific site and facilities; - Waste storage and disposal options; - Financial aspects; - Geographical Location; - National, Local and International Legislation; - Facility characterization; Identification of decommissioning objectives; - Description of alternatives: scope, features, specific end points, release criteria, risks and safety issues, effectiveness, feasibility, nature and amount of waste of generated and disposal plans, material recycling/reusing opportunities, cost, schedule, comparative analysis; - Rationale for selecting the preferred alternative. (authors)

  4. Development Of Decommissioning Information Management System for 101 HWRR

    Yi Song

    2016-01-01

    Decommissioning of 101 Heavy Water Research Reactor (HWRR) is radioactive and high-risk project which has to consider the effects of radiation and nuclear waste disposal, so the information system covering 101 HWRR decommissioning project must be established to ensure safety of the project. In this study, by col ecting the decommissioning activity data to establish the decommissioning database, and based on the database to develop information management system.

  5. Decommissioning in the United Kingdom Atomic Energy Authority

    The United Kingdom Atomic Energy Authority's policy on decommissioning is described. Several fission reactors have already been taken out of service and the state of decommissioning is given. Estimates of the volume of decommissioning wastes are made. The wastes will be either intermediate-level or low-level wastes. Research and development programmes have been undertaken to allow decommissioning to be safe and cost-effective. Some of the contaminated facilities have been decontaminated and re-used. (U.K.)

  6.  Heavy Lift Methods in Decommissioning of Installations

    Breidablikk, Line Småge

    2010-01-01

     In this report decommissioning of offshore petroleum platforms have been investigated. It treats decommissioning in general, the process of a typical project. A variety of suitable lifting vessels have been presented, and some concepts of removal have been evaluated.Decommissioning is important to go through with because of the environment and the use of the area after the petroleum activities ceases. Other ocean users benefit from the decommissioning because the area can be utilized when it...

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

    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.

  8. Decommissioning in western Europe; Kaernkraftsavveckling i Vaesteuropa

    Lundqvist, K. [Castor arbetslivskonsulter AB, Stockholm (Sweden)

    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

  9. Mound's decommissioning experience, tooling, and techniques

    Monsanto Research Corporation (MRC), which operates Mound for the Department of Energy (DOE), has been decommissioning radioactively contaminated facilities since 1949. We are currently decommissioning three plutonium-238 contaminated facilities (approximately 50,000 ft2) that contained 1100 linear ft of gloveboxes; 900 linear ft of conveyor housing; 2650 linear ft of dual underground liquid waste lines; and associated contaminated piping, services, equipment, structures, and soil. As of June 1982, over 29,000 Ci of plutonium-238 have been removed in waste and scrap residues. As a result of the current and previous decommissioning projects, valuable experience has been gained in tooling and techniques. Special techniques have been developed in planning, exposure control, contamination control, equipment removal, structural decontamination, and waste packaging

  10. The Ministry of Dilemmas [decommissioning nuclear submarines

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

  11. The economics and financing of decommissioning

    Economics and financing have the most immediate interest to the public. Largely this interest stems from the effect of decommissioning on current utility rates, but there are other related issues as well. These include the question of whether adequate funds will be available when needed, how they will be collected and invested, and what constitute reasonable contingency factors and discount rates. Preliminary examination of the economics of decommissioning raises more questions than it answers. Each country or area of a country (as in the USA) will be faced with establishing its own policies. Whichever methods and logic are finally applied to the economics of decommissioning in the United Kingdom, the public will eventually pay. For this reason, a clear working knowledge of the principal elements of this consideration is important. (author)

  12. Decommissioning trust funds ordered by PSC

    The Wisconsin public service commission ordered four electric utilities to set up external trust funds for decommissioning expenses instead of collecting the money from its ratepayers to offset current borrowing needs. The change is to assure that funds will be available when they are needed for the Point Beach 1 and 2 and the Kewaunee plants, which are due for relicensing and possible decommissioning in 2007 and 2008. The external fund will be available at a time when ratepayers will likely be paying for replacement power plants. Critics claim the order will cost utility customers $800 million over the next 23 years, and note that Wisconsin Electric Power Co. has a reputation for financial health. One area of concern is the treatment of funds already collected for decommissioning

  13. Reactor decommissioning in a deregulated market

    This paper seeks to summarise BNFL's experience with regard to recent developments in reactor decommissioning and demonstrate how commercial projects in crucial areas of strategy development, project implementation and site restoration are beginning to reduce the risks and uncertainties associated with this important aspect of the nuclear power generation industry. Although the reactor decommissioning market cannot yet be regarded as mature, the key elements of strategy development, waste treatment, dismantling and delicensing have been separately demonstrated as achievable. Together with the implementation of the right organisation, and the developing technology, the risks are being reduced. As more decommissioning projects are delivered, the risks will be reduced further and the confidence of the regulator in the process will improve. This paper sets out to demonstrate this viewpoint. (author)

  14. Site Decommissioning Management Plan. Supplement 1

    The Nuclear Regulatory Commission (NRC) staff has identified 51 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 stairs strategy for addressing the technical, legal, and policy issues affecting the timely decommissioning of the 51 sites and describes the status of decommissioning activities at the sites. This is supplement number one to NUREG-1444, which was published in October 1993

  15. Decommissioning and environmental remediation: An overview

    The objective in both decommissioning and environmental remediation is to lower levels of residual radioactivity enough that the sites may be used for any purpose, without restriction. In some cases, however, this may not be practical and restrictions may be placed on future land use. Following decommissioning, for example, some sites may be reused for non-nuclear industrial activities, but not for habitation. Some former uranium mining sites may be released for reuse as nature reserves or for other leisure activities. Both decommissioning and environmental remediation are major industrial projects in which the safety of the workforce, the local public and the environment must be ensured from both radiological and conventional hazards. Hence, an appropriate legal and regulatory framework, as well as proper training for personnel both in implementation and in regulatory oversight are among the necessary preconditions to ensure safety

  16. Decommissioning of the Neuherberg Research Reactor (FRN)

    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

  17. Decommissioning of reactor facilities (2). Required technology

    Decommissioning of reactor facilities was planned to perform progressive dismantling, decontamination and radioactive waste disposal with combination of required technology in a safe and economic way. This article outlined required technology for decommissioning as follows: (1) evaluation of kinds and amounts of residual radioactivity of reactor facilities with calculation and measurement, (2) decontamination technology of metal components and concrete structures so as to reduce worker's exposure and production of radioactive wastes during dismantling, (3) dismantling technology of metal components and concrete structures such as plasma arc cutting, band saw cutting and controlled demolition with mostly remote control operation, (3) radioactive waste disposal for volume reduction and reuse, and (4) project management of decommissioning for safe and rational work to secure reduction of worker's exposure and prevent the spreading of contamination. (T. Tanaka)

  18. Decommissioning of DR 2. Final report

    This report describes the work of dismantling and demolishing reactor DR 2, the waste volumes generated, the health physical conditions and the clearance procedures used for removed elements and waste. Since the ultimate goal for the decommissioning project was not clearance of the building, but downgrading the radiological classification of the building with a view to converting it to further nuclear use, this report documents how the lower classification was achieved and the known occurrence of remaining activity. The report emphasises some of the deliberations made and describes the lessons learned through this decommissioning project. The report also intends to contribute towards the technical basis and experience basis for further decommissioning of the nuclear facilities in Denmark. (au)

  19. Initiative for decommissioning of Chernobyl Nuclear Plant

    Construction of the New Safety Confinement (NSC) for the Chernobyl unit 4 started 2010, after about 25 years of Chernobyl accident and will complete summer of 2015. This project is being conducted by assistance of EU, USA and other countries including Japan. NSC can cover the whole facility of unit 4, and is installed various components or tools including big bridge crane for decommissioning unit 4 and has durability over 100 years. In addition to construction of NSC, various activities for preparing the decommissioning including developing the technology of monitoring the inside of destructive building and remote access technologies. The spent fuel storage facility and waste proposal facilities are also constructed.. These activities include many valuable information about how to smoothly conduct the decommissioning and it would be important to learn the above activities in conducting the post-processing activities on the Fukushima-Daiichi accident successfully. (author)

  20. Decommissioning of the Loviisa power plant

    In accordance with the provisions laid in the decision of the Ministry for Trade and Industry Imatran Voima Oy has revised the decommissioning plan for the Loviisa power plant, and submitted it to the authorities for review in December 1993. The plan outlines the technical measures needed to dismantle the radioactive parts of the Loviisa power plant, explains how the resulting waste will be packed and disposed of, and estimates how many people will be needed for the decommissioning waste will be. A general timetable and a cost estimate have also been drawn up on the basis of a detailed working plan. In this report the plan has been revised for cost estimate, activity inventory of the decommissioning waste and radiation dose caused by dismantling work. (orig.). (11 refs., 10 figs., 8 tabs.)

  1. Narbalek uranium mine: from EIS to decommissioning

    The Nabarlek uranium mine operated in Northern Australia from 1979 until 1989 and was the first of the 'new generation' of uranium mines to go through the cycle of EIS, operation and decommissioning. The paper describes the environmental and operational approval processes, the regulatory regime and the decommissioning procedures at the mine. The mine was located on land owned by indigenous Aboriginal people and so there were serious cultural considerations to be taken into account throughout the mine's life. Site work for decommissioning and rehabilitation was completed in 1995 but revegetation assessment has continued until the present time (1999). The paper concludes with the latest assessment and monitoring data and discusses the lessons learned by all parties from the completion of the cycle of mine life 'from cradle to grave'. (author)

  2. Platform decommissioning: Socio-economic impacts

    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

  3. Nuclear data requirements for fission reactor decommissioning

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

  4. Decommissioning of DR 2. Final report

    Strufe, N.

    2009-02-15

    This report describes the work of dismantling and demolishing reactor DR 2, the waste volumes generated, the health physical conditions and the clearance procedures used for removed elements and waste. Since the ultimate goal for the decommissioning project was not clearance of the building, but downgrading the radiological classification of the building with a view to converting it to further nuclear use, this report documents how the lower classification was achieved and the known occurrence of remaining activity. The report emphasises some of the deliberations made and describes the lessons learned through this decommissioning project. The report also intends to contribute towards the technical basis and experience basis for further decommissioning of the nuclear facilities in Denmark. (au)

  5. General principles underlying the decommissioning of nuclear facilities

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

  6. Feedback Experience from Decommissioning of Uranium Conversion Plant

    KAERI has been conducting decommissioning activities of Uranium Conversion Plant (UCP) for the last decade. As a result of all this work KAERI has accumulated significant experience in the field of decommissioning of nuclear facilities. On the basis of the experience gained from decommissioning activities, this paper describes several lessons learned

  7. 78 FR 64028 - Decommissioning of Nuclear Power Reactors

    2013-10-25

    ... COMMISSION Decommissioning of Nuclear Power Reactors AGENCY: Nuclear Regulatory Commission. ACTION... regulatory guide (RG) 1.184 ``Decommissioning of Nuclear Power Reactors.'' This guide describes a method NRC... decommissioning process for nuclear power reactors. The revision takes advantage of the 13 years...

  8. An analysis on the annual decommissioning deposit in NPP

    This study re-evaluated the methods for estimating and distributing decommissioning cost of nuclear power plant over lifetime. It was resulted out that the annual decommissioning deposit and consequently, the annual decommissioning cost could vary significantly depending on estimating and distributing methods, for instances, the accounting method being used presently by KEPCO and the lifetime levelized method being commonly applied in economic analysis

  9. Waste from decommissioning of nuclear power plants

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

  10. Maintaining Quality in a Decommissioning Environment

    The decommissioning of AECL's Whiteshell Laboratories is Canada's largest nuclear decommissioning project to date. This research laboratory has operated for forty years since it was set up in 1963 in eastern Manitoba as the Whiteshell Nuclear Research Establishment, complete with 60 MW(Th) test reactor, hot cells, particle accelerators, and multiple large-scale research programs. Returning the site to almost complete green state will require several decades of steady work in combination with periods of storage-with-surveillance. In this paper our approach to maintaining quality during the long decommissioning period is explained. In this context, 'quality' includes both regulatory aspects (compliance with required standards) and business aspects (meeting the customers' needs and exceeding their expectations). Both aspects are discussed, including examples and lessons learned. The five years of development and implementation of a quality assurance program for decommissioning the WL site have led to a number of lessons learned. Many of these are also relevant to other decommissioning projects, in Canada and elsewhere: - Early discussions with the regulator can save time and effort later in the process; - An iterative process in developing documentation allows for steady improvements and input throughout the process; - Consistent 2-way communication with staff regarding the benefits of a quality program assists greatly in adoption of the philosophy and procedures; - Top-level management must lead in promoting quality; - Field trials of procedures ('beta testing') ensures they are easy to use as well as useful. Success in decommissioning the Whiteshell Laboratories depends on the successful implementation of a rigorous quality program. This will help to ensure both safety and efficiency of all activities on site, from planning through execution and reporting. The many aspects of maintaining this program will continue to occupy quality practitioners in AECL, reaping

  11. Decision framework for platform decommissioning in California.

    Bernstein, Brock B

    2015-10-01

    This article describes the overall decision framework for eventual decisions about decommissioning the 27 operating oil and gas platforms offshore southern California. These platforms will eventually reach the end of their useful lifetimes (estimated between 2015 and 2030, although specific dates have not been determined). Current law and regulations allow for alternative uses in lieu of the complete removal required in existing leases. To prepare for eventual decommissioning, the California Natural Resources Agency initiated an in-depth process to identify and investigate issues surrounding possible decommissioning alternatives. The detailed evaluation of alternatives focused on 2-complete removal and artificial reefing that included partial removal to 85 feet below the waterline. These were selected after a comparison of the technical and economic feasibility of several potential alternatives, availability of a legal framework for implementation, degree of interest from proponents, and relative acceptance by state and federal decision makers. Despite California's history of offshore oil and gas production, only 7 decommissioning projects have been completed and these were all relatively small and close to shore. In contrast, nearly 30% of the California platforms are in water depths (as much as 1200 feet) that exceed any decommissioning project anywhere in the world. Most earlier projects considered an artificial reefing alternative but none were implemented and all platforms were completely removed. Future decisions about decommissioning must grapple with a more complex decision context involving greater technological and logistical challenges and cost, a wider range of viable options, tradeoffs among environmental impacts and benefits, and an intricate maze of laws, regulations, and authorities. The specific engineering differences between complete and partial removal provide an explicit basis for a thorough evaluation of their respective impacts. PMID:26259879

  12. Planning for decommissioning power plants in Japan

    Komatsu, Junji (Research Association for Nuclear Facility Decommissioning, Tokaimura, Ibaraki (Japan))

    1993-02-01

    The first decommissioning of a commercial nuclear power plant in Japan is not expected before the early 2000s, but the technology and regulations needed are being developed now. Valuable technical experience is being gained from three current projects. These are the decommissioning of the Japan Reprocessing Test Facility, the Japan Power Demonstration Reactor and the nuclear ship Mutsu. Improving and commercialising the technology are seen as essential for the future to reduce occupational radiation exposure, the amount of waste and costs. International cooperation and information exchange are of increasing importance for developing technology and regulations. (U.K.).

  13. Knowledge management during decommissioning of Chornobyl NPP

    The article deals with issues on knowledge management during decommissioning by the example of the Chornobyl NPP. This includes how the duration of decommissioning stage, change in organization goal and final state of the site influence on human resources and knowledge management system. The main attention is focused on human assets and intellectual strength of Chornobyl NPP. Mathematical dependencies are proposed to substantiate numerical values. An analysis is given for the current situation, and forecast estimates for values dynamics is performed. The conclusion gives solutions on providing experienced staff in the future.

  14. Cost Estimation for Research Reactor Decommissioning

    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

  15. No small fry: Decommissioning research reactors

    To get a permit to build a research reactor, would-be operators need to submit an initial decommissioning plan for the eventual shutdown of their new facility. This, however, was not a requirement back in the 1950s, 60s and 70s when most research reactors that are now nearing the end of their working lives were built. The result: many unused reactors sit idle in the middle of university campuses, research parks and hospital compounds, because their operators lack the proper plans to decommission them

  16. Optimization in the decommissioning of uranium tailings

    This report examines in detail the problem of choosing the optimal decommissioning approach for uranium and mill tailings sites. Various decision methods are discussed and evaluated, and their application in similar decision problems are summarized. This report includes, by means of a demonstration, a step by step guide of how a number of selected techniques can be applied to a decommissioning problem. The strengths and weaknesses of various methods are highlighted. A decision system approach is recommended for its flexibility and incorporation of many of the strengths found in other decision methods

  17. Shippingport station decommissioning project technology transfer program

    The US Department of Energy (DOE) Shippingport Station Decommissioning Project (SSDP) decontaminated and dismantled the world's first nuclear-fueled, commercial-size electric power plant. The SSDP programmatic goal direction for technology transfer is documentation of project management and operations experience. The objective is to provide future nuclear facility decommissioning projects with pertinent SSDP performance data for project assessment, planning, and operational implementation. This paper sets out access and availability directions for SSDP technology acquisition. Discusses are technology transfer definition; technology transfer products including topical and other project reports, professional-technical society presentations, other project liaison and media relations, visual documentation, and technology transfer data base; and retrieving SSDP information

  18. MCNP calculations in decommissioning of VVER-440

    The paper briefly describes the issue of neutron fluence and radionuclide inventory determination in components of decommissioned nuclear power plants with emphasis on VVER-440 reactor type. According to induced activity calculation, it will be possible to optimize the time frame and choose the appropriate dismantling procedure during the disposal of reactor internal and external components in the decommissioning of a nuclear power plant. Prerequisite for this calculation is the collection of reactor operation data. In this paper, abilities of MCNP5 and MCNPX codes in this field are presented. (authors)

  19. Ignalina NPP pre-decommissioning projects

    Description of the main projects for the preparation to the decommissioning of unit 1 of Ignalina NPP is presented. These projects are to be financed by international donors as one of the conditions to shutdown unit before the year 2005. These projects were presented during Donors conference held in 21-22 June 2000 in Vilnius. The conference was organized jointly by Lithuanian Government and European Commission. Projects are devoted to the construction of radioactive waste management facilities and improvement of existing waste management practices at Ignalina NPP as well for the general management of decommissioning process preparation of necessary documentation

  20. Decommissioning of a tritium-contaminated laboratory

    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 was constructed in 1953 and was in service for tritium research and fabrication of lithium tritide components until 1974. The major features of the laboratory included some 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

  1. Nuclear power plants. Safe and efficient decommissioning

    The process of dismantling a nuclear power plant consists of several phases that involve significant challenges along the way for authorities, operators, and suppliers. It is necessary to ensure safety at all times and to achieve certainty in respect of key project parameters, especially time and cost. Therefore, careful planning as well as detailed knowledge of local standards and regulations, best available techniques and practical implementation strategies are crucial. Independent expertise and knowledge service can be utilised for demanding projects worldwide. This guarantees safety for people and the environment in every phase of decommissioning. The article gives an overview on different decommissioning options and their challenges.

  2. Nuclear power plants. Safe and efficient decommissioning

    Huger, Helmut [TUEV SUED Energietechnik GmbH, Filderstadt (Germany). Div. of Radiation Protection, Waste Management and Decommissioning; Woodcock, Richard [TUEV SUED Nuclear Technologies, Warrington, Cheshire (United Kingdom). Environment and Radioactive Waste Management

    2016-02-15

    The process of dismantling a nuclear power plant consists of several phases that involve significant challenges along the way for authorities, operators, and suppliers. It is necessary to ensure safety at all times and to achieve certainty in respect of key project parameters, especially time and cost. Therefore, careful planning as well as detailed knowledge of local standards and regulations, best available techniques and practical implementation strategies are crucial. Independent expertise and knowledge service can be utilised for demanding projects worldwide. This guarantees safety for people and the environment in every phase of decommissioning. The article gives an overview on different decommissioning options and their challenges.

  3. Intelligence, Social Class of Origin, Childhood Behavior Disturbance and Education as Predictors of Status Attainment in Midlife in Men: The Aberdeen Children of the 1950s Study

    von Stumm, Sophie; Macintyre, Sally; Batty, David G.; Clark, Heather; Deary, Ian J.

    2010-01-01

    In a birth cohort of 6281 men from Aberdeen, Scotland, social class of origin, childhood intelligence, childhood behavior disturbance and education were examined as predictors of status attainment in midlife (46 to 51 years). Social class of origin, intelligence and behavior disturbance were conceptualized as correlated predictors, whose effects…

  4. Decommissioning technology development for research reactors; establishment on the classification scheme of the decommissioning information and data

    Ser, J. S.; Jang, Se Kyu; Kim, Young Do [Chungchong Institute of Regional Information System, Taejeon (Korea)

    2002-04-01

    The establishment of the decommissioning DB is the first thing in KOREA. It has never been decided the standardization in relation to the decommissioning DB all over the world and many countries has been constructed their decommissioning DB which serve their purpose. Owing to get the classification of the decommissioning information and data, it is used a prototyping design that is needed the DB construction as a basic data and applied to a nuclear facilities in the future. 10 refs. (Author)

  5. Good practices in decommissioning planning and pre-decommissioning activities for the Magurele VVR-S nuclear research reactor

    The VVR-S Nuclear Research Reactor at the 'Horia Hulubei' National Institute of Physics and Nuclear Engineering in Magurele, Bucharest, will be decommissioned applying the immediate dismantling strategy. The implementation of the decommissioning project started in 2010 and is planned for completion within 11 years. Good practices in decommissioning planning, organization, funding, and logistics are described in this paper. (author)

  6. The decommissioning and redevelopment of NECSA site

    Full text: The South African nuclear programme started in 1948 and was focussed on research and development in the nuclear field. In the early 70s a uranium conversion plant and a uranium enrichment plant were constructed on the NECSA site. The enriched uranium was used for military purposes, as fuel for the research reactor SAFARI-1 at Necsa. A semi-commercial uranium enrichment plant and a fuel manufacturing plant were commissioned in the 80's to supply fuel for the nuclear power plant at Koeberg near Cape Town. Currently the research reactor is utilized for the generation of radioactive isotopes for industrial and medical applications. Various other research projects were initiated and buildings constructed on the Necsa site to accommodate the different projects. The uranium conversion and enrichment projects were terminated in the early 90's, and many buildings on the Necsa site became redundant. An initial decommissioning strategy was to return the Necsa site to green fields. This endpoint of decommissioning has changed dramatically with the nuclear renaissance to include redevelopment and reuse options. In the case of a multi-facility nuclear site, such as the Necsa site, it is vital to develop a total site redevelopment plan rather than to decommission and allocate individual facilities for isolated reuse demands. A holistic approach should be assured by considering current and projected future redevelopment demands in the development of a redevelopment and reuse plan. It is important not to allow the redevelopment and reuse of a single facility on a multi-facility site based on short- term financial gain. With the recent increase in demand for nuclear facilities the redevelopment and reuse of nuclear facilities for non-nuclear applications should generally not be considered due to the inherent advantages associated with an existing licensed site. The initial decommissioning plan did not consider the Necsa site as a whole. Decommissioning costs, and the

  7. The institutional framework of decommissioning in Italy

    Full text: Decommissioning of the NPP is generally viewed in a negative framework. On the contrary, it is an activity which aims is said to obtain the final removal of the risk factors from the environment. It is the last step of the production cycle, whose importance is underlined by the Regulation recently issued for the correct management of resources in the territory. Decommissioning NPP involves the final arrangements of the radioactive wastes, produced either during the past operation period or resulting from the dismantling operation. All the radioactive wastes must be conditioned and maintained in safe conditions. Radioactive waste management is no longer a problem for those countries that decided to face it, that is the majority of the industrialised countries. Correct technological solutions exist, due exist, respectful of the environment, of the people, of the ethical principles. The centrality of the problem is also decreed by the fact that sometimes now, the European Commission has been working on the issue of the directive on waste management, an effort which Italy has strongly supported, also during the Presidency period. Decommissioning on NPP is moreover an activity that implies advanced technological solutions, multilateral overlapping programs, working of style situations. Not many countries have completed yet (the) decommissioning of their plants: such activity should therefore be seen as an opportunity for the growth and the assertion of the Italian industry, also in view of the potential new market and the alliance with European industries. Of the 530 nuclear reactors present in world today, approximately 100 are undergoing decommissioning. In the next 2 years another 100 will reach the end of their operative life. Probably after the necessary system improvement many of them will continue to work, but it is clear that the international market of the decommissioning will continue to grow in the next years. Italy can play an important role in

  8. Needs for European decommissioning academy (EDA)

    According to analyses presented at EC meeting focused on decommissioning organized at 11.9.2012 in Brussels, it was stated that at least 500 new international experts for decommissioning will be needed in Europe up to 2025, which means about 35 per year. Having in mind the actual EHRO-N report from 2013 focused on operation of nuclear facilities and an assumption that the ratio between nuclear experts, nuclearized and nuclear aware people is comparable also for decommissioning, as well as the fact that the special study branch for decommissioning in the European countries almost does not exist, this European Decommissioning Academy (EDA) could be helpful in the over-bridging this gap. The main goal is - from about 74% of nuclearized experts (graduated at different technical Universities and increased their nuclear knowledge and skills mostly via on-job training and often in the area of NPP operation) to create nuclear experts for decommissioning via our post-gradual coursed organized in two semester study at our Academy, which will include the lessons, practical exercises in our laboratories, on-site training at NPP V-1 in Jaslovske Bohunice, Slovakia as well as 3 days technical tour to JAVYS (Slovakia), UJV Rez (Czech Rep.) and PURAM (Hungary), respectively. Beside the exams in selected topics (courses), the final thesis written under supervision of recognized experts will be the precondition for graduation and certification of the participants. For the first run of the EDA scheduled on 2014 we would like to focus on VVER decommissioning issues because this reactor type is the most distributed design in the world and many of these units are actually in decommissioning process or will be decommissioned in the near future in Europe. The growing decommissioning market creates a potential for new activities, with highly skilled jobs in an innovative field, involving high-level technologies. A clear global positioning of the EU will stimulate the export of know-how to

  9. Validation of Decommissioning Engineering System Application against KRR-2

    KAERI is the only expert group which has decommissioning experiences and KAERI is trying to develop computer code to converge all the data which has been accumulated during KRR (Korea Research Reactor)-1 and 2 and UCP (Uranium Conversion Plant) decommission. This paper contains validation results of the KAERI DES by using KRR-2 decommissioning data. As a responsible leading group of Korean decommissioning research field, KAERI has been developing DES application program. One of decommissioning experience data, KRR-2 was used for KAERI DES validation and it successfully is reflected in KAERI DES

  10. Status of industry standards for decommissioning of nuclear facilities

    This paper discusses how several professional societies are preparing industry standards on nuclear facility decommissioning: ASTM (American Society for Testing and Materials), Nuclear Technology Committee, Decommissioning Subcommittee, E10.03; ASME (American Society of Mechanical Engineers), Nuclear Quality Assurance (NQA) Committee's Working Group on Decommissioning and the Reactor Services Committee's Subcommittee on Decommissioning; and Health Physics Society Standards Committee (HPSSC) working under the auspices of the American National Standards Institute (ANSI). According to the author, the standards of these diverse groups mesh to form a cohesive body of guidance for planning a nuclear facility decommissioning

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

    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)

  12. Validation of Decommissioning Engineering System Application against KRR-2

    Jin, Hyung Gon; Park, Seungkook; Park, Heeseong; Song, Chanho; Ha, Jaehyun [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-05-15

    KAERI is the only expert group which has decommissioning experiences and KAERI is trying to develop computer code to converge all the data which has been accumulated during KRR (Korea Research Reactor)-1 and 2 and UCP (Uranium Conversion Plant) decommission. This paper contains validation results of the KAERI DES by using KRR-2 decommissioning data. As a responsible leading group of Korean decommissioning research field, KAERI has been developing DES application program. One of decommissioning experience data, KRR-2 was used for KAERI DES validation and it successfully is reflected in KAERI DES.

  13. A study of the decommissioning cost estimation for nuclear facilities

    Lee, Dong Gyu; Jeong, Kwan Seong; Lee, Keun Woo; Oh, Won Zin [KAERI, Taejon (Korea, Republic of)

    2004-07-01

    This paper is to study on the decommissioning cost estimation for nuclear facilities of advanced nuclear organizations and countries for deriving the cost factors to be taken considerations into accomplishing decommissioning projects. Of cost categories producing the factors of decommissioning costs, dismantling and waste processing and disposals activities are examined to increase the its costs. Of labor, materials and other costs categories, labor costs are summarized to have overall majorities in the decommissioning cost factors. The main parameters of all factors affecting the decommissioning costs are analyzed as work difficulty, regional labor costs, peripheral cost, disposal cost and final burial costs.

  14. A study of the decommissioning cost estimation for nuclear facilities

    This paper is to study on the decommissioning cost estimation for nuclear facilities of advanced nuclear organizations and countries for deriving the cost factors to be taken considerations into accomplishing decommissioning projects. Of cost categories producing the factors of decommissioning costs, dismantling and waste processing and disposals activities are examined to increase the its costs. Of labor, materials and other costs categories, labor costs are summarized to have overall majorities in the decommissioning cost factors. The main parameters of all factors affecting the decommissioning costs are analyzed as work difficulty, regional labor costs, peripheral cost, disposal cost and final burial costs

  15. Decontamination and decommissioning of Shippingport commercial reactor

    Schreiber, J. [Dept. of Energy, Pittsburgh, PA (United States)

    1989-11-01

    To a certain degree, the decontamination and decommissioning (D and D) of the Shippingport reactor was a joint venture with Duquesne Light Company. The structures that were to be decommissioned were to be removed to at least three feet below grade. Since the land had been leased from Duquesne Light, there was an agreement with them to return the land to them in a radiologically safe condition. The total enclosure volume for the steam and nuclear containment systems was about 1.3 million cubic feet, more than 80% of which was below ground. Engineering plans for the project were started in July of 1980 and the final environmental impact statement (EIS) was published in May of 1982. The plant itself was shut down in October of 1982 for end-of-life testing and defueling. The engineering services portion of the decommissioning plans was completed in September of 1983. DOE moved onto the site and took over from the Navy in September of 1984. Actual physical decommissioning began after about a year of preparation and was completed about 44 months later in July of 1989. This paper describes the main parts of D and D.

  16. Consideration of ISDC for Decommissioning Cost Estimation

    In 2009, they decided to update the Yellow Book, and began to update it by analyzing user experiences. They found that several countries have adopted the proposed standardized cost structure for the production of cost estimates directly or for mapping national estimates onto a common structure. They also made conclusions that more detailed advice should be given on the use of the standardized structure and on the definition of cost items to avoid ambiguity. The revised cost structure, to be known as the International Structure for Decommissioning Costing (ISDC), was published in 2012. The standardized cost structure developed in the report may be used for estimating the costs of decommissioning of any type of nuclear facility. We analyzed this standardized cost structure (ISDC) and applied it to DECOMMIS which was developed by KAERI. The appropriate estimation system for domestic application was examined by comparing the estimation results. KAERI made WBS code in DECOMMIS and data obtained during decommissioning work of KRR2 and UCP. Recently the IAEA updated the decommissioning cost items and its structure by ISDC. The cost estimation items of the DECOMMIS were applied to ISDC structure. For applying, the ISDC code compared with WBS code of DECOMMIS as on text of the activity name from daily report basis. The mapping result of the ISDC items to WBS code of the DECOMMIS is much different. AS results of this study that it need the corresponding cost category which classified in accordance with the national standard price estimates

  17. CECP, Decommissioning Costs for PWR and BWR

    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)

  18. Decontamination and decommissioning focus area. Technology summary

    This report presents details of the facility deactivation, decommissioning, and material disposition research for development of new technologies sponsored by the Department of Energy. Topics discussed include; occupational safety, radiation protection, decontamination, remote operated equipment, mixed waste processing, recycling contaminated metals, and business opportunities

  19. Spent fuel disposal impact on plant decommissioning

    Regardless of the decommissioning option selected (DECON, SAFSTOR, or ENTOMB), a 10 CFR 50 license cannot be terminated until the spent fuel is either removed from the site or stored in a separately 10 CFR 72 licensed Independent Spent Fuel Storage Installation (ISFSI). Humboldt Bay is an example of a plant which has selected the SAFSTOR option. Its spent fuel is currently in wet storage in the plant's spent fuel pool. When it completes its dormant period and proceeds with dismantlement, it will have to dispose of its fuel or license an ISFSI. Shoreham is an example of a plant which has selected the DECON option. Fuel disposal is currently critical path for license termination. In the event an ISFSI is proposed to resolve the spent fuel removal issue, whether wet or dry, utilities need to properly determine the installation, maintenance, and decommissioning costs for such a facility. In considering alternatives for spent fuel removal, it is important for a utility to properly account for ISFSI decommissioning costs. A brief discussion is presented on one method for estimating ISFSI decommissioning costs

  20. Virtual reality technology and nuclear decommissioning

    During past years, an important activity at the Halden VR Centre (HVRC), Institute for Energy Technology (IFE) in Halden has been the development of virtual reality (VR) software for use in the decommissioning of nuclear facilities. It is hoped that use of VR technology in the planning process may prove beneficial both with regard to minimizing workers' radiation exposure, as well as in helping to achieve the efficient use of human resources. VR can also be a valuable tool in the dismantling phase. In addition to this, VR provides the decommissioning project team with an effective medium in presentations to the public, as well as for communicating with relevant engineers and licensing authorities. The most extensive IFE VR decommissioning project is at present the VRdose project, conducted in co-operation with the Japan Nuclear Cycle Development Institute (JNC). VRdose will be used in the decommissioning of one of JNC's reactors, the Fugen Nuclear Power Station.The paper describes the present and planned versions of the VRdose system, but also briefly describes other related activities at HVRC. (author)

  1. The decommissioning of the water boiler reactor

    Following completion of service, the Water Boiler Reactor (WBR) has been decommissioned by the Institute of Nuclear Energy Research (INER) under the Atomic Energy Council's (AEC) regulation. The WBR is a light water moderated and graphite reflected research reactor with peak thermal power of 100 kW. The unique feature of the WBR is that it is fueled with uranyl sulfate (UO2SO4) which is in liquid form. Since there is another research reactor owned by I7NER of megawatt scale in the planning stages for decommissioning, the WBR project was conducted with great care to accumulate experience. Extensive planning by INER and step-by-step regulative activities by AEC were followed regardless of the structural simplicity of the WBR. Valuable information was gathered in the task and will be useful for preparing future decommissioning needs. The major work in the WBR decommissioning project was finished within six months and the accumulated dose received during the work was 1 9.63mSv. (author)

  2. Decommissioning progress at Fort St. Vrain

    Decommissioning of commercial nuclear power plants in the US has initiated with the current dismantling of the Fort St. Vrain Nuclear Generation Station in Colorado. Owned and operated by Public Service Company of Colorado (PSC), the unit was permanently shutdown in 1989. After a thorough evaluation by the utility of the DECON versus SAFSTOR options, the decision was made to proceed with decommissioning the power station for unrestricted release. In 1990 a team comprised of Westinghouse Electric Corporation and Morrison Knudsen Corporation was selected by PSC to perform the decommissioning on a fixed price, turnkey basis. The Westinghouse Team (WT) concept was based on an innovative approach for dismantling the Prestressed Concrete Reactor Vessel (PCRV) by flooding it and performing most operations using underwater tooling. This approach provided the maximum shielding and contamination control along with an optimum balance of schedule, cost and ALARA with minimum risks. An overview of the decommissioning progress to date plus overall perspectives of the factors facing utilities in this area will be reviewed

  3. Decommissioning technology development for research reactors

    Although it is expected that the decommissioning of a nuclear power plant will happen since 2020, the need of partial decommissioning and decontamination for periodic inspection and life extension has been on an increasing trend and domestic market has gradually been extended. Therefore, in this project the decommissioning DB system on the KRR-1 and 2 was developed as establishing the information classification system of the research reactor dismantling and the structural design and optimization of the decommissioning DB system. Also in order to secure the reliability and safety about the dismantling process, the main dismantling simulation technology that can verify the dismantling process before their real dismantling work was developed. And also the underwater cutting equipment was developed to remove these stainless steel parts highly activated from the RSR. First, the its key technologies were developed and then the design, making, and capability analysis were performed. Finally the actual proof was achieved for applying the dismantling site. an automatic surface contamination measuring equipment was developed in order to get the sample automatically and measure the radiation/radioactivity

  4. Financing strategies for nuclear power decommissioning

    None,

    1980-07-01

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

  5. Estimation of decommissioning costs: History and status

    In the mid-1970s. the subject of the cost of decommissioning nuclear power stations became a topic of considerable interest to the industry. A number of early demonstration plants in the US had been retired and most had been entombed. Only one plant, the Elk River Reactor (a small boiling water facility) had been totally dismantled and removed from the site (Welsh 1974). Thus, there was a very limited data base from which to develop estimates for decommissioning the much larger stations then under construction and coming into service. The nuclear industry sponsored another study for estimating decommissioning costs using an approach known as the Unit Cost Factor (UCF) method. This methodology is documented in AIF/NESP-0036 (LaGuardia 1986). and forms the basis for many of the estimates prepared by (or for) utilities for usein making submissions to their utility rate commissions to recover future decommissioning costs through current rates. This and other estimating approaches mentioned above are discussed in more detail in this paper

  6. BNFL nuclear decommissioning liabilities management program

    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

  7. Decontamination and decommissioning focus area. Technology summary

    NONE

    1995-06-01

    This report presents details of the facility deactivation, decommissioning, and material disposition research for development of new technologies sponsored by the Department of Energy. Topics discussed include; occupational safety, radiation protection, decontamination, remote operated equipment, mixed waste processing, recycling contaminated metals, and business opportunities.

  8. Y-12 Plant Decontamination and Decommissioning Program

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

  9. Sodium Reactor Experiment decommissioning. Final report

    Carroll, J.W.; Conners, C.C.; Harris, J.M.; Marzec, J.M.; Ureda, B.F.

    1983-08-15

    The Sodium Reactor Experiment (SRE) located at the Rockwell International Field Laboratories northwest of Los Angeles was developed to demonstrate a sodium-cooled, graphite-moderated reactor for civilian use. The reactor reached full power in May 1958 and provided 37 GWh to the Southern California Edison Company grid before it was shut down in 1967. Decommissioning of the SRE began in 1974 with the objective of removing all significant radioactivity from the site and releasing the facility for unrestricted use. Planning documentation was prepared to describe in detail the equipment and techniques development and the decommissioning work scope. A plasma-arc manipulator was developed for remotely dissecting the highly radioactive reactor vessels. Other important developments included techniques for using explosives to cut reactor vessel internal piping, clamps, and brackets; decontaminating porous concrete surfaces; and disposing of massive equipment and structures. The documentation defined the decommissioning in an SRE dismantling plan, in activity requirements for elements of the decommissioning work scope, and in detailed procedures for each major task.

  10. Offshore decommissioning issues: Deductibility and transferability

    Dealing with the decommissioning of petroleum installations is a relatively new challenge to most producer countries. It is natural to expect that industry's experience in building platforms is much greater than the one of dismantling them. Even if manifold and varied efforts are underway towards establishing international 'best practices' standards in this sector, countries still enjoy rather extensive discretionary power as they practice a particular national style in the regulation of decommissioning activities in their state's jurisdiction. The present paper offers a broad panorama of this discussion, concentrating mainly on two controversial aspects. The first one analyses the ex-ante deductibility of decommissioning costs as they constitute an ex-post expense. The second discussion refers to the assignment of decommissioning responsibility in the case of transfer of exploration and production rights to new lessees during the project's life. Finally the paper applies concepts commonly used in project financing as well as structures generally used in organising pension funds to develop insights into these discussions

  11. MODELLING OF NUCLEAR POWER PLANT DECOMMISSIONING FINANCING

    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: 0.913, year: 2014

  12. Modelling of nuclear power plant decommissioning financing

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

    Vol. 2015. Oxford: Oxford Journals, 2015, s. 1-4. ISSN 1742-3406. [8th International Conference on High Levels of Natural Radiation and Radon Areas (ICHLNRRA 2014). Prague (CZ), 01.09.2014-05.09.2014] Institutional support: RVO:61389005 Keywords : nuclear power plant * methodology * future decommissioning costs Subject RIV: BG - Nuclear, Atomic and Molecular Physics, Colliders

  13. Radiological characterization of nuclear plants under decommissioning

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

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

    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)

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

    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

  16. STATUS OF THE NRC'S DECOMMISSIONING PROGRAM

    Orlando, D. A.; Camper, L. W.; Buckley, J.

    2002-02-25

    On July 21, 1997, the U.S. Nuclear Regulatory Commission published the final rule on Radiological Criteria for License Termination (the License Termination Rule) as Subpart E to 10 CFR Part 20. NRC regulations require that materials licensees submit Decommissioning Plans to support the decommissioning of its facility if it is required by license condition, or if the procedures and activities necessary to carry out the decommissioning have not been approved by NRC and these procedures could increase the potential health and safety impacts to the workers or the public. NRC regulations also require that reactor licensees submit Post-shutdown Decommissioning Activities Reports and License Termination Plans to support the decommissioning of nuclear power facilities. This paper provides an update on the status of the NRC's decommissioning program. It discusses the status of permanently shut-down commercial power reactors, complex decommissioning sites, and sites listed in the Site Decommissioning Management Plan. The paper provides the status of various tools and guidance the NRC is developing to assist licensees during decommissioning, including a Standard Review Plan for evaluating plans and information submitted by licensees to support the decommissioning of nuclear facilities and the D and D Screen software for determining the potential doses from residual radioactivity. Finally, it discusses the status of the staff's current efforts to streamline the decommissioning process.

  17. Decommissioning of Facilities. General Safety Requirements. Pt. 6

    Decommissioning is the last step in the lifetime management of a facility. It must also be considered during the design, construction, commissioning and operation of facilities. This publication establishes requirements for the safe decommissioning of a broad range of facilities: nuclear power plants, research reactors, nuclear fuel cycle facilities, facilities for processing naturally occurring radioactive material, former military sites, and relevant medical, industrial and research facilities. It addresses all the aspects of decommissioning that are required to ensure safety, aspects such as roles and responsibilities, strategy and planning for decommissioning, conduct of decommissioning actions and termination of the authorization for decommissioning. It is intended for use by those involved in policy development, regulatory control and implementation of decommissioning

  18. Decommissioning of Facilities. General Safety Requirements. Pt. 6 (Arabic Edition)

    Decommissioning is the last step in the lifetime management of a facility. It must also be considered during the design, construction, commissioning and operation of facilities. This publication establishes requirements for the safe decommissioning of a broad range of facilities: nuclear power plants, research reactors, nuclear fuel cycle facilities, facilities for processing naturally occurring radioactive material, former military sites, and relevant medical, industrial and research facilities. It addresses all the aspects of decommissioning that are required to ensure safety, aspects such as roles and responsibilities, strategy and planning for decommissioning, conduct of decommissioning actions and termination of the authorization for decommissioning. It is intended for use by those involved in policy development, regulatory control and implementation of decommissioning

  19. Decommissioning of Facilities. General Safety Requirements. Pt. 6 (Chinese Edition)

    Decommissioning is the last step in the lifetime management of a facility. It must also be considered during the design, construction, commissioning and operation of facilities. This publication establishes requirements for the safe decommissioning of a broad range of facilities: nuclear power plants, research reactors, nuclear fuel cycle facilities, facilities for processing naturally occurring radioactive material, former military sites, and relevant medical, industrial and research facilities. It addresses all the aspects of decommissioning that are required to ensure safety, aspects such as roles and responsibilities, strategy and planning for decommissioning, conduct of decommissioning actions and termination of the authorization for decommissioning. It is intended for use by those involved in policy development, regulatory control and implementation of decommissioning

  20. Roadmap for implementation of light water reactor decommissioning

    While decommissioning of Tokai-mura reactor and JATR reactor has already started in Japan, Tsuruga reactor is announced shutdown in 2010 as the first decommissioning of commercial light water reactor (LWR). In 2030s or may be more earlier due to economic reasons, decommissioning of LWRs will take place in succession. Since rational decommissioning needs operating data of individual plants, ample time should be allowed for planning the reactor decommissioning. Committee of Nuclear Power Engineering Cooperation (NUPEC) had identified relevant issues to implement LWR decommissioning and established roadmaps showing fundamental approaches to solve seventeen items categorized in seven areas as action items. Harmonization of policy, regulations and technology development as a whole and reflection of accumulated lessons learned from overseas decommissioning experiences needed further study. (T. Tanaka)

  1. Development of the Decommissioning Project Management System, DECOMMIS

    Chung, U. S.; Park, J. H.; Lee, K. W.; Hwang, D. S.; Park, S. K.; Hwang, S. T.; Paik, S. T.; Choi, Y. D.; Chung, K. H.; Lee, K. I.; Hong, S. B

    2007-03-15

    At the Korea Atomic Energy Research Institute(KAERI), two projects for decommissioning of the research reactors and uranium conversion plant are carried out. The management of the projects can be defined as 'the decision of the changes of the decommissioning methodologies for the more efficient achievement of the project at an adequate time and to an improved method'. The correct decision comes from the experiences on the decommissioning project and the systematic experiences can be obtained from the good management of the decommissioning information. For this, a project management tool, DECOMMIS, was developed in the D and D Technology Division, which has the charge of the decommissioning projects at the KAERI, and its purpose was extended to following fields; generation of reports on the dismantling waste for WACID, record keeping for the next decommissioning projects of nuclear facilities, provision of fundamental data for the R and D of the decommissioning technologies.

  2. Study on decommissioning (Annual safety research report, JFY 2010)

    This project consists of researches for 1. review plan for decommissioning plan, 2. specific method to confirm completion of decommissioning and 3. dismantling waste management method. Dismantling experiences and knowledge of domestic and international trends of decommissioning were examined and the confirmation items for authorization of decommissioning plan were extracted. The estimation of site contamination during dismantling period was performed by use of radioactive material release data of the Tokai NPP. Domestic and some foreign countries knowledge of experience of decommissioning completion confirmation was examined. This knowledge was reflected in NISA's Committee Report 'Basic concept to confirm completion of decommissioning (Interim report) - Main issues and direction of future investigation-'. Three concrete cores were sampled in biological shield of the Tokai NPP to establish method of waste package verification based on radiation level evaluation in decommissioning and dismantling waste management method. (author)

  3. Decommissioning of TRIGA Mark II type reactor

    The first research reactor in Korea, KRR 1, is a TRIGA Mark II type with open pool and fixed core. Its power was 100 kWth at its construction and it was upgraded to 250 kWth. Its construction was started in 1957. The first criticality was reached in 1962 and it had been operated for 36,000 hours. The second reactor, KRR 2, is a TRIGA Mark III type with open pool and movable core. These reactors were shut down in 1995, and the decision was made to decommission both reactors. The aim of the decommissioning activities is to decommission the KRR 2 reactor and decontaminate the residual building structures and site, and to release them as unrestricted areas. The KRR 1 reactor was decided to be preserve as a historical monument. A project was launched for the decommissioning of these reactors in 1997, and approved by the regulatory body in 2000. A total budget for the project was 20.0 million US dollars. It was anticipated that this project would be completed and the site turned over to KEPCO by 2010. However, it was discovered that the pool water of the KRR 1 reactor was leaked into the environment in 2009. As a result, preservation of the KRR 1 reactor as a monument had to be reviewed, and it was decided to fully decommission the KRR 1 reactor. Dismantling of the KRR 1 reactor takes place from 2011 to 2014 with a budget of 3.25 million US dollars. The scope of the work includes licensing of the decommissioning plan change, removal of pool internals including the reactor core, removal of the thermal and thermalizing columns, removal of beam port tubes and the aluminum liner in the reactor tank, removal of the radioactive concrete (the entire concrete structure will not be demolished), sorting the radioactive waste (concrete and soil) and conditioning the radioactive waste for final disposal, and final statuses of the survey and free release of the site and building, and turning over the site to KEPCO. In this paper, the current status of the TRIGA Mark-II type reactor

  4. Decommissioning of TRIGA Mark II type reactor

    Hwang, Dooseong; Jeong, Gyeonghwan; Moon, Jeikwon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2012-10-15

    The first research reactor in Korea, KRR 1, is a TRIGA Mark II type with open pool and fixed core. Its power was 100 kWth at its construction and it was upgraded to 250 kWth. Its construction was started in 1957. The first criticality was reached in 1962 and it had been operated for 36,000 hours. The second reactor, KRR 2, is a TRIGA Mark III type with open pool and movable core. These reactors were shut down in 1995, and the decision was made to decommission both reactors. The aim of the decommissioning activities is to decommission the KRR 2 reactor and decontaminate the residual building structures and site, and to release them as unrestricted areas. The KRR 1 reactor was decided to be preserve as a historical monument. A project was launched for the decommissioning of these reactors in 1997, and approved by the regulatory body in 2000. A total budget for the project was 20.0 million US dollars. It was anticipated that this project would be completed and the site turned over to KEPCO by 2010. However, it was discovered that the pool water of the KRR 1 reactor was leaked into the environment in 2009. As a result, preservation of the KRR 1 reactor as a monument had to be reviewed, and it was decided to fully decommission the KRR 1 reactor. Dismantling of the KRR 1 reactor takes place from 2011 to 2014 with a budget of 3.25 million US dollars. The scope of the work includes licensing of the decommissioning plan change, removal of pool internals including the reactor core, removal of the thermal and thermalizing columns, removal of beam port tubes and the aluminum liner in the reactor tank, removal of the radioactive concrete (the entire concrete structure will not be demolished), sorting the radioactive waste (concrete and soil) and conditioning the radioactive waste for final disposal, and final statuses of the survey and free release of the site and building, and turning over the site to KEPCO. In this paper, the current status of the TRIGA Mark-II type reactor

  5. European Nuclear Decommissioning Training Facility II

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

  6. The BR-3 decommissioning project, Belgium

    BR-3 was a small 10 MW(e) PWR which was shut down in 1987 after 25 years of operation. It was selected as an EU pilot project for the research and development programme on decommissioning of nuclear installations. The decommissioning project started in 1989. The optimization of the management of waste material generated by decommissioning activities has always been an intensive task and the minimization of the radioactive waste a priority. Over the past 16 years, the factors influencing the management of waste have been constantly evolving in Belgium, steered mainly by the following changes in technologies, regulations and economic conditions: - The publication of the Royal Decree of 20 July 2001, establishing a legal frame on decommissioning and including a set of clearance levels; - The improvement of the instrumentation used for characterization; - The increase in the performance of decontamination techniques; - The cost increase of the waste disposal paths; - The implementation of international recommendations in areas such as environmental impact, waste categorization, human aspects, ethics, etc.; -The strengthening of the legislation related to industrial safety and environmental release; - The diminution of the background radiation level at the decommissioning site itself. The first part of this annex gives a description of relevant influencing factors in order to define the context in which the dismantling activities took place. The second part puts in perspective the strategy chosen for the management of the waste, recognizing the influencing factors. As mentioned in the scope of this report, the focus is LLW. High and intermediate level wastes for which disposal in dedicated repositories is assumed are outside the scope of this report. They are therefore not examined in detail here

  7. Características da carcaça de bovinos Canchim e Aberdeen Angus e de seus cruzamentos recíprocos terminados em confinamento Carcass traits of Canchim, Aberdeen Angus and reciprocal crosses finished in confinement

    Daniel Perotto; José Luiz Moletta; Antonio Carlos Cubas

    1999-01-01

    Foram analisadas quatorze características quantitativas das carcaças de 137 machos bovinos inteiros pertencentes aos grupos Canchim (Ca), Aberdeen Angus (Ab), 3/4Ca+1/4Ab, 3/4Ab+1/4Ca, 5/8Ca+3/8Ab e 5/8Ab+3/8Ca, nascidos na Estação Experimental Fazenda Modelo, em Ponta Grossa-PR, no período de 1988 a 1993. As médias para a idade e para o peso ao início do confinamento, duração do confinamento, idade e peso ao abate foram, respectivamente, 737 dias, 356kg, 97 dias, 834 dias e 468kg. Durante o ...

  8. Tradução e adaptação cultural do Questionário Aberdeen para Veias Varicosas Translation and cultural adaptation of Aberdeen Varicose Veins Questionnaire

    Flávia de Jesus Leal

    2012-03-01

    Full Text Available CONTEXTO: Atualmente há um crescente interesse por instrumentos de avaliação em saúde produzidos e validados em todo o mundo. Apesar disso, ainda não temos no Brasil instrumentos que avaliem o impacto da doença venosa crônica na vida de seu portador. Para utilização dessas medidas torna-se necessária a realização da tradução e da adaptação cultural ao idioma em questão. OBJETIVO: Traduzir e adaptar culturalmente para a população brasileira o Aberdeen Varicose Veins Questionnaire (AVVQ- Brasil. MÉTODOS: O processo consistiu de duas traduções e duas retrotraduções realizadas por tradutores independentes, da avaliação das versões seguida da elaboração de versão consensual e de pré-teste comentado. RESULTADOS: Os pacientes do pré-teste eram do sexo feminino, com média de idade de 49,9 anos, média de tempo de resposta 7,73 minutos, que variou entre 4,55 minutos (tempo mínimo a 10,13 minutos (tempo máximo. Escolaridade: 20% analfabetismo funcional, 1º grau completo e 2º grau completo; 30% 1º grau incompleto; e 10% 3º grau completo. Gravidade clínica 40% C3 e C6S, 10% C2 e C5, havendo cinco termos incompreendidos na aplicação. CONCLUSÕES: A versão na língua portuguesa do Aberdeen Varicose Veins Questionnaire está traduzida e adaptada para uso na população brasileira, podendo ser utilizada após posterior análise de suas propriedades clinimétricas.BACKGROUND: Currently there is a growing interest in health assessment tools produced and validated throughout the world. Nevertheless, it is still inadequate the number of instruments that assess the impact of chronic venous disease in the life of its bearer. To use these measures it is necessary to accomplish the translation and cultural adaptation to the language in question. OBJECTIVE: Translate to Portuguese and culturally adapted for the Brazilian population the Aberdeen Varicose Veins Questionnaire (AVVQ-Brazil. METHODS: The process consisted of two

  9. SOGIN Decommissioning strategy and funding (Italy)

    Statement: In Italy, as it is well known, there are no more operational NPPs. The four existing nuclear plants are definitely shutdown and ready for decommissioning. Considerations on decommissioning funding system have to take into account this particular situation. Strategy for decommissioning: New inputs given to SOGIN by the Italian Government are: conditioning all radioactive waste existing on the NPPs within the year 2010, release all nuclear sites - free of radiological constraints - by 2020. The last task is conditioned by availability of the national waste repository by the year 2009. Strategy for decommissioning: Key issue is prompt dismantling considering No more nuclear activities in Italy and Progressive loss of competencies. Previously Existing funds: Before plant shutdown, ENEL has cumulated provisions for decommissioning, even in absence of a clear regulatory framework. These provisions were not sufficient for decommissioning, considering the early closure of the plants. An additional fund was granted to ENEL by the government, in the form of a 'credit' to be paid by the 'electric system' (CCSE). This fund (provisions + credit) was considered sufficient by ENEL for a decommissioning with Safe Store strategy (fund = discounted foreseen costs). The total fund (provisions + credit) was assigned to Sogin at the incorporation date. The amount, money 1999, was about 800 M euros. Considering the new context: new strategy (Prompt Dismantling with site release by 2020), Sogin constitution (societal costs), new economic conditions. The fund was not considered sufficient for all Sogin tasks. This conclusion was agreed upon also by the independent 'Authority for electric energy and gas'. A new regulatory framework was therefore defined. Regulatory aspects: The Legislative Decree 79/99 has stated that costs for the decommissioning of NPP, fuel cycle back end and related activities should be considered as stranded costs for the general electric system. The same

  10. Stratégie bas carbone écossaise : l’exemple de la ville d’Aberdeen

    Guyet, Rachel

    2016-01-01

    A l’instar de l’Ecosse, le modèle énergétique de la ville d’Aberdeen se caractérise par un paradoxe : comment transformer une économie reposant essentiellement sur le gaz et le pétrole en un modèle de développement bas carbone ? Sans renier la manne financière que représente encore à court terme les énergies fossiles, l’Ecosse poursuit également une stratégie de déploiement d’énergie bas carbone dans le secteur de l’électricité et de la chaleur. Elle a même défini des objectifs...

  11. NMSS handbook for decommissioning fuel cycle and materials licensees

    The US Nuclear Regulatory Commission amended its regulations to set forth the technical and financial criteria for decommissioning licensed nuclear facilities. These regulations were further amended to establish additional recordkeeping requirements for decommissioning; to establish timeframes and schedules for the decommissioning; and to clarify that financial assurance requirements must be in place during operations and updated when licensed operations cease. Reviews of the Site Decommissioning Management Plan (SDMP) program found that, while the NRC staff was overseeing the decommissioning program at nuclear facilities in a manner that was protective of public health and safety, progress in decommissioning many sites was slow. As a result NRC determined that formal written procedures should be developed to facilitate the timely decommissioning of licensed nuclear facilities. This handbook was developed to aid NRC staff in achieving this goal. It is intended to be used as a reference document to, and in conjunction with, NRC Inspection Manual Chapter (IMC) 2605, ''Decommissioning Inspection Program for Fuel Cycle and Materials Licensees.'' The policies and procedures discussed in this handbook should be used by NRC staff overseeing the decommissioning program at licensed fuel cycle and materials sites; formerly licensed sites for which the licenses were terminated; sites involving source, special nuclear, or byproduct material subject to NRC regulation for which a license was never issued; and sites in the NRC's SDMP program. NRC staff overseeing the decommissioning program at nuclear reactor facilities subject to regulation under 10 CFR Part 50 are not required to use the procedures discussed in this handbook

  12. NMSS handbook for decommissioning fuel cycle and materials licensees

    Orlando, D.A.; Hogg, R.C.; Ramsey, K.M. [and others

    1997-03-01

    The US Nuclear Regulatory Commission amended its regulations to set forth the technical and financial criteria for decommissioning licensed nuclear facilities. These regulations were further amended to establish additional recordkeeping requirements for decommissioning; to establish timeframes and schedules for the decommissioning; and to clarify that financial assurance requirements must be in place during operations and updated when licensed operations cease. Reviews of the Site Decommissioning Management Plan (SDMP) program found that, while the NRC staff was overseeing the decommissioning program at nuclear facilities in a manner that was protective of public health and safety, progress in decommissioning many sites was slow. As a result NRC determined that formal written procedures should be developed to facilitate the timely decommissioning of licensed nuclear facilities. This handbook was developed to aid NRC staff in achieving this goal. It is intended to be used as a reference document to, and in conjunction with, NRC Inspection Manual Chapter (IMC) 2605, ``Decommissioning Inspection Program for Fuel Cycle and Materials Licensees.`` The policies and procedures discussed in this handbook should be used by NRC staff overseeing the decommissioning program at licensed fuel cycle and materials sites; formerly licensed sites for which the licenses were terminated; sites involving source, special nuclear, or byproduct material subject to NRC regulation for which a license was never issued; and sites in the NRC`s SDMP program. NRC staff overseeing the decommissioning program at nuclear reactor facilities subject to regulation under 10 CFR Part 50 are not required to use the procedures discussed in this handbook.

  13. Nuclear submarine decommissioning. Radiation risk assessments

    Decommissioning of the ships and vessels with nuclear power installations is a problem of primary and worldwide importance. It is essential for both the naval fleet and the military industrial complex as a whole. Nuclear submarines decommissioning is accompanied by a number of questions concerning the development and performance of the safe technologies for managing radioactive equipment and nuclear waste from the vessels with the nuclear power facilities. Decommissioning of nuclear submarines including unloading of the spent fuel should take place at the operating ship yards and repairing plants that are usually situated close to the densely populated areas and living blocks. Decommissioning includes a series of the potentially dangerous operations with radioactive materials, e.g. fuel unloading, disposal of coolant, dismantling of the contaminated equipment, cutting out the reactor compartment, etc. As a result a great amount of highly radioactive liquid and solid wastes are formed including the cut-out reactor compartment and spent fuel that produce additional radioactive load on the local environment and population. Estimation of the radiation risk for the environment and population due to decommissioning becomes an actual and necessary question. Apart from this the process of decommissioning may cause accidents followed by complicated radiation situation with high dose rates and contamination of the environment. Analysis of the most probable scenarios of the accident development and estimation of the expected radiation consequences should help to assess the risk rate for radiation impact on the environment and population as well as to develop an adequate environmental monitoring and to undertake measures for the accident localisation and liquidation of its consequences. A separate problem is management of the reactor compartment containing radioactive equipment of the steam producing installation and biological protection. Since there are no specialised

  14. On Decommissioning Costs of the Ranstad Site

    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

  15. 30 CFR 250.1753 - After I decommission a pipeline, what information must I submit?

    2010-07-01

    ... Decommissioning Activities Pipeline Decommissioning § 250.1753 After I decommission a pipeline, what information must I submit? Within 30 days after you decommission a pipeline, you must submit a written report to... 30 Mineral Resources 2 2010-07-01 2010-07-01 false After I decommission a pipeline,...

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

    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 m3) 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

  17. Decommissioning policy and programme progress BNFL

    British Nuclear Fuels Ltd (BNFL) reviewed decommissioning liabilities in 1988 and established a revised policy covering the technical and financial provisioning requirements for the next 100 years. At the Sellafield site the work programme has been steadily expanded over the past ten years and now includes all shutdown facilities. Of 26 projects identified, four have been completed and substantial progress made on the remainder. Approximately 35M pounds has been spent to date and a further 54M pounds financially sanctioned against the 390M pounds estimated for the programme. Project needs are leading a supporting development programme targeted at cost reduction and towards improving the quality of long-term estimates. The policy, programme and some of the projects are briefly described and an outline is given of some of the enhanced capabilities which have matured the capability for safe and cost effective decommissioning of fuel cycle facilities. (author) 8 refs.; 2 tabs

  18. Decommissioning of an uranium hexafluoride pilot plant

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

  19. Perspective of decommissioning in East European countries

    A regional co-operation was organized in 1986 between East European countries on problems connected with the last stage of the NPP unit life cycle. Closure of a nuclear power plant (NPP) unit is considered as a problem with influence upon the safety of the nuclear energetics. Bulgaria, the USSR and Czechoslovakia have united their efforts establishing the Joint Venture for Decommissioning NPP 'Decom' thus giving a possibility for a safe and effective NPP unit decommissioning. At present a preparatory work is being conducted at the Joint Venture on all aspects of the problem - ecological, social, technical and economic. A certain practical experience has been accumulated. Research performed previously has delivered certain scientific and technical results. (author) 1 tab

  20. Decommissioning Experience: Apsara Research Reactor, India

    Full text: In India, at the Bhabha Atomic Research Centre, a 1 MW(th) pool type research reactor called Apsara was built in 1956 and shut down in 2009. The reactor fuel and internals were removed, leaving the pool available for draining and decontamination. The pool was drained progressively while monitoring for hot spots. Additional material and debris at the bottom were removed. The lining was cleaned by water jetting using detergents. In summary, the defuelling and partial decommissioning were successfully completed in around six months, with a total dose consumption of 23.5 man mSv (approximately 10% of budget). The generation of waste amounted to a solid waste volume of around 20 m3 (low level) and a liquid waste volume of 280 m3 (low level). A detailed description of achievements and plans for the Apsara decommissioning is given. (author)

  1. Decommissioning plan for the TRIGA mark-3

    TRIGA Mark-III (KRR-2) is the second research reactor in Korea. Construction of KRR-2 was started in 1969 and first criticality was achieved in 1972. After 24 years operation, KRR-2 has stopped its operation at the end of 1995 due to normal operation of HANARO. KRR-2 was then decided to decommission in 1996 by government. Decontamination and decommissioning (D and D) will be conducted in accordance with domestic laws and international regulations. Selected method of D and D will be devoted to protect workers and environment and to minimize radioactive wastes produced. The major D and D work will be conducted safely by using conventional industrial equipment because of relatively low radioactivity and contamination in the facility. When removing activated concrete from reactor pool, it will be installed a temporary containment and ventilation system. In this paper, structure of KRR-2 and method of D and D in each step are presented and discussed

  2. Decommissioning of the Tokamak Fusion Test Reactor

    E. Perry; J. Chrzanowski; C. Gentile; R. Parsells; K. Rule; R. Strykowsky; M. Viola

    2003-10-28

    The Tokamak Fusion Test Reactor (TFTR) at the Princeton Plasma Physics Laboratory was operated from 1982 until 1997. The last several years included operations with mixtures of deuterium and tritium. In September 2002, the three year Decontamination and Decommissioning (D&D) Project for TFTR was successfully completed. The need to deal with tritium contamination as well as activated materials led to the adaptation of many techniques from the maintenance work during TFTR operations to the D&D effort. In addition, techniques from the decommissioning of fission reactors were adapted to the D&D of TFTR and several new technologies, most notably the development of a diamond wire cutting process for complex metal structures, were developed. These techniques, along with a project management system that closely linked the field crews to the engineering staff who developed the techniques and procedures via a Work Control Center, resulted in a project that was completed safely, on time, and well below budget.

  3. Decommissioning of the Tokamak Fusion Test Reactor

    The Tokamak Fusion Test Reactor (TFTR) at the Princeton Plasma Physics Laboratory was operated from 1982 until 1997. The last several years included operations with mixtures of deuterium and tritium. In September 2002, the three year Decontamination and Decommissioning (D and D) Project for TFTR was successfully completed. The need to deal with tritium contamination as well as activated materials led to the adaptation of many techniques from the maintenance work during TFTR operations to the D and D effort. In addition, techniques from the decommissioning of fission reactors were adapted to the D and D of TFTR and several new technologies, most notably the development of a diamond wire cutting process for complex metal structures, were developed. These techniques, along with a project management system that closely linked the field crews to the engineering staff who developed the techniques and procedures via a Work Control Center, resulted in a project that was completed safely, on time, and well below budget

  4. Decommissioning plan for Andujar uranium mill facilities

    The milling of radioactive ores results in contaminated buildings and facilities which must be decommissioned, and large quantities of tailings which must be managed safely so that residual environmental and health risks do not exceed acceptable levels. In the south of Spain on the outskirts of the town of Andujar an inactive uranium mill facility is under decommissioning. Mill equipment, buildings and process facilities have been dismantled and demolished and the resulting metal wastes and debris have been placed in the pile. The tailing mass is being reshaped by flattening the sideslopes and a cover system will be placed over the pile. This paper describes the safety aspects and technical approaches which are being used for the remediation and closure of the Andujar mill site. (author). 7 figs

  5. 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

    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

  6. Experimental feedback on sodium loop decommissioning

    The aim of this paper is to present experimental feedback on sodium loop dismantling techniques at the CEA (The French Atomic Energy Commission) and to offer recommendations for the decommissioning of Fast Reactor secondary sodium loops. This study is based on acquired CEA decommissioning experience which primarily concerns the following: the decommissioning of RAPSODIE (France's first Fast Reactor), the Phenix reactor secondary loop replacement, the sodium loop decommissioning carried out by the Laboratory of Sodium Technologies and Treatment, and several technical documents. This paper deals with the main results of this survey. First, a comparison of 8 pipe-cutting techniques is made, taking into account speed in cutting, reliability, dissemination, fire risk due to the presence of sodium, cutting depth, and different types of waste (empty pipes, sodium-filled pipes, tanks). This comparison has led us to recommend the use of an alternative saw or a chain saw rather than the use of the plasma torch or grinder. Different techniques are recommended depending on if they are on-site, initial cuttings or if they are to be carried out in a specially-designed facility referred to hereafter as 'the cutting building'. After the cutting stage, the sodium waste must be processed with water to become an ultimate stable waste. Four treatment processes are compared with different standards: speed, cost, low activity adaptability and 'large sodium quantity' adaptability. Recommendations are also made for reliable storage, and for the general dismantling system organization. Last, calculations are presented concerning a complete dismantling facility prototype capable of treating large amounts and volume of sodium wastes. (author)

  7. CEA experimental feedback on sodium loop decommissioning

    The aim of this paper is to present experimental feedback on sodium loop dismantling techniques at the CEA (The French Atomic Energy Commission) and to offer recommendations for the decommissioning of Fast Reactor secondary sodium loops. This study is based on acquired CEA decommissioning experience which primarily concerns the following: the decommissioning of RAPSODIE (France's first Fast Reactor), the PHENIX reactor secondary loop replacement, the sodium loop decommissioning carried out by the Laboratory of Sodium Technologies and Treatment, and several technical documents. This paper deals with the main results of this survey. First, a comparison of 8 pipe-cutting techniques is made, taking into account speed in cutting, reliability, dissemination, fire risk due to the presence of sodium, cutting depth, and different types of waste (empty pipes, sodium-filled pipes, tanks...). This comparison has led us to recommend the use of an alternative saw or a chain saw rather than the use of the plasma torch or grinder. Different techniques are recommended depending on if they are on-site, initial cuttings or if they are to be carried out in a specially-designed facility referred to hereafter as 'the cutting building'. After the cutting stage, the sodium waste must be processed with water to become an ultimate stable waste. Four treatment processes are compared with different standards : speed, cost, low activity adaptability and 'large sodium quantity' adaptability. Recommendations are also made for reliable storage, and for the general dismantling system organization. Last, calculations are presented concerning a complete dismantling facility prototype capable of treating large amounts and volume of sodium wastes. (author)

  8. Decommissioning a tritium glove-box facility

    Folkers, C.L.; Homann, S.G.; Nicolosi, A.S.; Hanel, S.L.; King, W.C.

    1979-08-08

    A large glove-box facility for handling reactive metal tritides was decommissioned. Major sections of the glove box were decontaminated and disassembled for reuse at another tritium facility. To achieve the desired results, decontamnation required repeated washing, first with organic liquids, then with water and detergents. Worker protection was provided by simple ventilation combined with careful monitoring of the work areas and employees. Several innovative techniques are described.

  9. Decontamination and decommissioning of nuclear facilities

    Since 1973, when the IAEA first introduced the subject of decontamination and decommissioning into its programme, twelve Agency reports reflecting the needs of the Member States on these topics have been published. These reports summarize the work done by various Technical Committees, Advisory Groups, and International Symposia. While the basic technology to accomplish decontamination and decommissioning (D and D) is fairly well developed, the Agency feels that a more rapid exchange of information and co-ordination of work are required to foster technology, reduce duplication of effort, and provide useful results for Member States planning D and D activities. Although the Agency's limited financial resources do not make possible direct support of every research work in this field, the IAEA Co-ordinated Research Programme (CRP) creates a forum for outstanding workers from different Member States brought into closer contact with one another to provide for more effective interaction and, perhaps subsequently, closer collaboration. The first IAEA Co-ordinated Research Programme (CRP) on decontamination and decommissioning was initiated in 1984. Nineteen experts from 11 Member States and two international organizations (CEC, OECD/NEA) took part in the three Research Co-ordination Meetings (RCM) during 1984-87. The final RCM took place in Pittsburgh, USA, in conjunction with the 1987 International Decommissioning Symposium (sponsored by the US DOE and organized in co-operation with the IAEA and OECD/NEA). The present document summarizes the salient features and achievements of the co-ordinated research work performed during the 1984-87 programme period. The document consists of two parts: Part 1, Summary of the three research co-ordination meetings and Part 2, Final submissions by participants on the research work performed during 1984-1987. A separate abstract was prepared for each of the 7 reports presented. Refs, figs and tabs

  10. Decommissioning a tritium glove-box facility

    A large glove-box facility for handling reactive metal tritides was decommissioned. Major sections of the glove box were decontaminated and disassembled for reuse at another tritium facility. To achieve the desired results, decontamnation required repeated washing, first with organic liquids, then with water and detergents. Worker protection was provided by simple ventilation combined with careful monitoring of the work areas and employees. Several innovative techniques are described

  11. Decommissioning of the BR3 PWR

    The dismantling and the decommissioning of nuclear installations at the end of their life-cycle is a new challenge to the nuclear industry. Different techniques and procedures for the dismantling of a nuclear power plant on an existing installation, the BR-3 pressurized-water reactor, are described. The scientific program, objectives, achievements in this research area at the Belgian Nuclear Research Centre SCK-CEN for 1997 are summarized

  12. Decommissioning of the Risoe Hot Cell facility

    Concise description of progress in hot cell facility decommissioning at Risoe National Laboratory is presented. Removal of the large contaminated equipment has been completed, all the concrete cells have been finally cleaned. The total contamination left on the concrete walls is of the order of 1850 GBq. Preliminary smear tests proved the stack to be probably clean. The delay in project completion seems to be around 7 months, the remaining work being of rather conventional character. (EG)

  13. Evaluation of decommissioning programs: Material, waste and cost analysis

    The estimation of decommissioning materials, waste and costs constitutes one of the major activities in decommissioning programs. These estimates are required for new installations or installations still in operation in order to plan future waste management programs and to define the financial provisions necessary to ensure satisfactory execution of future programs. The estimates are also required for installations currently being decommissioned in order to plan detailed programs and to verify and update previous evaluations. The Belgian legislator entrusted the National Agency with several assignments regarding decommissioning of nuclear installations. To perform these assignments, the Agency set up an integrated data processing system able to record the inventory of a plant and to evaluate the nature and the quantities of decommissioning materials and waste as well as the decommissioning costs

  14. Research reactor back-end options - decommissioning: a necessary consideration

    Decommissioning is a challenge, which all radioactive site licensees eventually need to face and research reactors are no exception. BNFL has completed numerous major decommissioning projects at its own operational sites and has undertaken similar works at customers' sites including the decommissioning of the Universities Research Reactor (URR), Risley and the ICI TRIGA 1-Mk I Reactor at Billingham. Based on the execution of such projects BNFL has gained an understanding of the variety of customer requirements and the effectiveness of specific decommissioning techniques for research reactors. This paper addresses factors to be considered when reviewing the way forward following shut down and how these affect the final decisions for fuel management and the extent of decommissioning. Case studies are described from BNFL's recent experience decommissioning both the URR and ICI TRIGA reactors. (author)

  15. The U.S. Nuclear Regulatory Commission's decommissioning process

    The term 'Decommission' is defined in the U.S.. Nuclear Regulatory Commission's (USNRC's) regulations at 10 CFR 20.1003 as to remove a facility or site safely from service and reduce residual radioactivity to a level that permits 1) release of the property for unrestricted use and termination of the license; or, 2) release of the property under restricted conditions and the termination of the license. USNRC's decommissioning program encompasses the decommissioning of all NRC licensed facilities, ranging from routine license terminations for sealed source users, to the oversight of complex sites and those on the Site Decommissioning Management Plan (SDMP), as well as power and non-power reactors. This paper describes the USNRC's decommissioning process for materials and reactor facilities and presents an overview of USNRC's decommissioning program activities. (author)

  16. The regulatory challenges of decommissioning nuclear reactors

    Each nuclear power plant, fuel cycle facility and nuclear research and test facility that is operating today will eventually reach the end of its useful life and cease operation. During the period of its decommissioning, it is important to properly manage the health and environmental hazards and physical protection measures of the shutdown facility in order to protect the health and safety of the public and workers and to safeguard any nuclear materials. In this regard, the nuclear safety regulatory body is responsible for independently assuring that decommissioning activities are conducted safely, that radioactive materials and spent nuclear fuel are disposed of properly and that the site is in an acceptable end state. The purpose of this report is to describe the broad range of safety, environmental, organisational, human factors and public policy issues that may arise during the decommissioning of nuclear reactors and that the regulatory body should be prepared to deal with in the framework of its national regulatory system. The intended audience is primarily nuclear regulators, although the information and ideas may also be of interest to government authorities, environmental regulators, nuclear operating organisations, technical expert organisations and the general public. (author)

  17. Decommissioning strategies for facilities using radioactive material

    The planning for the decommissioning of facilities that have used radioactive material is similar in many respects to other typical engineering projects. However, decommissioning differs because it involves equipment and materials that are radioactive and therefore have to be handled and controlled appropriately. The project management principles are the same. As with all engineering projects, the desired end state of the project must be known before the work begins and there are a number of strategies that can be used to reach this end state. The selection of the appropriate strategy to be used to decommission a facility can vary depending on a number of factors. No two facilities are exactly the same and their locations and conditions can result in different strategies being considered acceptable. The factors that are considered cover a wide range of topics from purely technical issues to social and economic issues. Each factor alone may not have a substantial impact on which strategy to select, but their combination could lead to the selection of the preferred or best strategy for a particular facility. This Safety Report identifies the factors that are normally considered when deciding on the most appropriate strategy to select for a particular facility. It describes the impact that each factor can have on the strategy selection and also how the factors in combination can be used to select an optimum strategy

  18. The use of managing agencies in decommissioning

    On 1 April 1994 UKAEA Government Division was formed and one of its main responsibilities is the safe and cost effective management of the facilities which have already closed and the fuel reprocessing and radioactive waste management plant required to assist in the current programme of decommissioning. UKAEA Government Division, working on behalf of DTI, is intended to be a lean and efficient programme management and procurement organisation. Rather than build up its own project management capability it intends to use external resources for this function, obtained in future by competitive tendering. For each major facility undergoing decommissioning a Managing Agency has been, or will be, appointed to act on behalf of UKAEA Government Division. The responsibilities of each Managing Agency will be to assist in the definition of tasks, the commissioning of option studies and safety studies, the specification of individual contracts, management of the tendering processes and the subsequent management of the Implementation Contractors carrying out the decommissioning work, including the associated safety and training responsibilities. Teams involved in Managing Agency work require skills in project management, relevant technical issues, contract and safety management. (author)

  19. Lessons learned on stakeholder issues in decommissioning

    Issues of public concern during decommissioning and dismantling (D and D) are partly the same and partly different from those of the preceding phases (planning, construction and operation). While in the course of construction and operation the main challenges include meeting expectations of a higher quality of life, accommodating a growing population, mitigating construction nuisances, and assuring the safe operation of the facility, the main concerns in the D and D phase are decreasing employment rate, the eventual reduction of revenues for the municipality, the future use of the affected land and negative social impacts (e.g., out-migration). The decommissioning phase is characterised by heterogeneity of stakeholder interests and values, difficulties of reaching consensus or compromise, and difficulties in connection with the harmonization of energy production, environmental protection and sustainable socio-economic development considerations. Typically, there might also be tensions between local and regional decisions. As in other phases, the building of trust between stakeholder is crucial from the point of view of conflict management, and social lessons learnt from the siting and developments of nuclear facilities are widely applicable in the field of D and D as well. A review is presented of major lessons to be learnt from NEA activities in the field of decommissioning and stakeholder involvement. (author)

  20. Lessons learned on stakeholder issues in decommissioning

    O' Sullivan, P.; Pescatore, C. [OECD Nuclear Energy Agency, 92 - Issy les Moulineaux (France)

    2008-07-01

    Issues of public concern during decommissioning and dismantling (D and D) are partly the same and partly different from those of the preceding phases (planning, construction and operation). While in the course of construction and operation the main challenges include meeting expectations of a higher quality of life, accommodating a growing population, mitigating construction nuisances, and assuring the safe operation of the facility, the main concerns in the D and D phase are decreasing employment rate, the eventual reduction of revenues for the municipality, the future use of the affected land and negative social impacts (e.g., out-migration). The decommissioning phase is characterised by heterogeneity of stakeholder interests and values, difficulties of reaching consensus or compromise, and difficulties in connection with the harmonization of energy production, environmental protection and sustainable socio-economic development considerations. Typically, there might also be tensions between local and regional decisions. As in other phases, the building of trust between stakeholder is crucial from the point of view of conflict management, and social lessons learnt from the siting and developments of nuclear facilities are widely applicable in the field of D and D as well. A review is presented of major lessons to be learnt from NEA activities in the field of decommissioning and stakeholder involvement. (author)

  1. Investment management for nuclear decommissioning trusts

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

  2. Large transport packages for decommissioning waste

    The main tasks performed during the period related to the influence of manufacture, transport and disposal on the design of such packages. It is deduced that decommissioning wastes will be transported under the IAEA Transport Regulations under either the Type B or Low Specific Activity (LSA) categories. If the LSA packages are self-shielded, reinforced concrete is the preferred material of construction. But the high cost of disposal implies that there is a strong reason to investigate the use of returnable shields for LSA packages and in such cases they are likely to be made of ferrous metal. Economic considerations favour the use of spheroidal graphite cast iron for this purpose. Transport operating hazards have been investigated using a mixture of desk studies, routes surveys and operations data from the railway organisations. Reference routes were chosen in the Federal Republic of Germany, France and the United Kingdom. This work has led to a description of ten accident scenarios and an evaluation of the associated accident probabilities. The effect of disposal on design of packages has been assessed in terms of the radiological impact of decommissioning wastes, an in addition corrosion and gas evolution have been examined. The inventory of radionuclides in a decommissioning waste package has low environmental impact. If metal clad reinforced concrete packages are to be used, the amount of gas evolution is such that a vent would need to be included in the design. Similar unclad packages would be sufficiently permeable to gases to prevent a pressure build-up. (author)

  3. Decommissioning of the Salaspils Research Reactor

    Abramenkovs Andris

    2011-01-01

    Full Text Available In May 1995, the Latvian government decided to shut down the Salaspils Research Reactor and to dispense with nuclear energy in the future. The reactor has been out of operation since July 1998. A conceptual study on the decommissioning of the Salaspils Research Reactor was drawn up by Noell-KRC-Energie- und Umwelttechnik GmbH in 1998-1999. On October 26th, 1999, the Latvian government decided to start the direct dismantling to “green-field” in 2001. The upgrading of the decommissioning and dismantling plan was carried out from 2003-2004, resulting in a change of the primary goal of decommissioning. Collecting and conditioning of “historical” radioactive wastes from different storages outside and inside the reactor hall became the primary goal. All radioactive materials (more than 96 tons were conditioned for disposal in concrete containers at the radioactive wastes depository “Radons” at the Baldone site. Protective and radiation measurement equipment of the personnel was upgraded significantly. All non-radioactive equipment and materials outside the reactor buildings were released for clearance and dismantled for reuse or conventional disposal. Contaminated materials from the reactor hall were collected and removed for clearance measurements on a weekly basis.

  4. Decommissioning U.K. power stations

    The strategy for decommissioning U.K. commercial nuclear power stations at the end of their operating lives has hitherto been based on early partial dismantling and clearance to green-field site after about 100 years. This strategy involves a considerable financial liability particularly in the early years following shutdown of the stations. In 1990 Nuclear Electric identified the potential for significantly reducing this liability by reviewing a range of alternative strategies for decommissioning. This review has now been completed by Nuclear Electric and this paper describes the background to it, the review itself and the conclusions. As a result Nuclear Electric are now proposing to adopt a new strategy, referred to as the ''Deferred Safestore strategy'' for all its gas-cooled power stations. This does not involve any significant active dismantling until about 135 years after shutdown, allowing radioactivity levels in the plant to decay to very low levels in-situ. Following defuelling, an initial care and maintenance phase of about 30 years occurs followed by construction of containments (Safestores) around all buildings containing active plant. The purpose of these is to protect the buildings and their contents from deterioration due to weathering for a further 100 years. Complete dismantling is carried out after that time. An alternative option at that time, with further considerable cost savings, could be In-situ decommissioning. (Author)

  5. Governments' role in decommissioning nuclear power facilities

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

  6. New technologies in decommissioning and remediation

    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. While characterization for planning purposes can be done using manual approaches, such as drawing up blueprints and taking measurements and photos, laser scanning technologies are now allowing decommissioning teams to more quickly and accurately map out the physical characteristics of a facility’s structures, systems and components. This is complemented by highly sensitive measurements taken with high-tech devices, such as remotely operated gamma cameras that can precisely and efficiently measure the radiological characteristics of the facility, including the amount and type of radiation. Similar measurements are needed once the contamination has been removed, to verify that any residual radiation levels are indeed insignificant

  7. Training practices to support decommissioning of nuclear facilities

    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

  8. Administrative requirements of financial securities to cover decommissioning operations

    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)

  9. Unrestricted re-use of decommissioned nuclear laboratories

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

    1996-09-18

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

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

    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

  11. Use of data processing tools in decommissioning nuclear facilities

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

  12. Computer System Analysis for Decommissioning Management of Nuclear Reactor

    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)

  13. The decommissioning program of JAERI's Reprocessing Test Facility

    Decommissioning program of JAERI's Reprocessing Test Facility (JRTF) has been carried out to establish decommissioning techniques for nuclear fuel facilities. The project consists of 2 phases ; phase 1 is preparatory stage of decommissioning project, and phase 2 is execution stage of the JRTF decommissioning. The project started in 1990 under a contract with the Science and Technology Agency, and will be finished in 2001. Up to now, treatment of some radioactive liquid waste and physical inventory estimation were carried out. In addition to the technical development for dismantling, the design for treatment of the unpurified uranium solution and high level liquid waste are in progress steadily. (author)

  14. Planning for safe decommissioning of research reactors in Egypt

    Egypt operates two Research Reactors: ETRR-1: Tank type, 2 MW power, 10% enrichment EK-10 fuel, and commissioned in 1960 and ETRR-2: Open pool type, 22 MW power, 20% enrichment plate type fuel and commissioned in 1997. A proposed decommissioning plan for each reactor will be presented. The established decommissioning plan includes facility characterization, procedures and radiological protection aspects. The safety assessment during the decommissioning identifies the actions that are necessary to ensure continuous safety during all phases of decommissioning. Protective measures should provide the necessary defense in depth. (author)

  15. Conclusions and theses relating to the decommissioning of nuclear installations

    Most of the problems encountered in decommissioning are due to deficiencies on the side of the laws. Items of controversy revealed at the meeting are: -content covered by the term decommissioning; - definition of decommissioning stages and their hierarchy in schedule; - subject matter of decommissioning; -interfaces between operation and decommissioning processes; - substantive requirements to be met; - formal requirements to be met. The meaning of the term 'nuclear installation' used in paragraph 7 sub-sec. (3), 1st sentence Atomic Energy Act corresponds to the meaning of the term used in paragraph 7 sub-sec. 1 Atomic Energy Act. However, the licensee is free to proceed with the decommissioning of individual components of an installation that can be disconnected from the safety programme of decommissioning activities. Those measures in the post-shutdown phase under regulatory control under the operating licence or the surveillance programme do not require to be licensed anew. All other measures require a licence for decommissioning ('as far as'). Decommissioning cannot be 'directed' by orders under the surveillance programme. The (unlawful) nuclear power phaseout cannot be imposed on the basis of paragraph 7 sub-sec. 3 Atomic Energy Act. (orig./HSCH)

  16. Decommissioning of fuel cycle facilities in South Africa

    Experience gained in South Africa on the decommissioning of uranium conversion, enrichment and fuel fabrication facilities is briefly summarized with emphasis on the lessons learned. The South African Nuclear Energy Corporation (Necsa) has consolidated its nuclear decommissioning and waste management activities at Pelindaba and introduced a comprehensive, all-embracing nuclear liability management approach. The paper describes the experience gained on various aspects of decommissioning and waste management including the social impacts of the decommissioning and waste related activities during the decade from 1995 to 2005. Certain technological difficulties arose during this period and the approaches adopted to resolve these difficulties are also addressed. (author)

  17. Chemical decontamination for decommissioning (DFD) and DFDX

    DFD is an acronym for the 'Decontamination for Decommissioning' process developed in 1996 by the Electric Power Research Institute (EPRI). The process was designed to remove radioactivity from the surfaces of metallic components to allow these components to be recycled or free-released for disposal as non-radioactive. DFD is a cyclic process consisting of fluoroboric acid, potassium permanganate and oxalic acid. The process continues to uniformly remove base metal once oxide dissolution is complete. The DFD process has been applied on numerous components, sub-systems and systems including the reactor systems at Big Rock Point and Maine Yankee in the United States, and the Jose Cabrera (Zorita) Nuclear Power Plant (NPP) in Spain. The Big Rock Point site has been returned to Greenfield and at Maine Yankee the land under the license was reduced for an Independent Spent Fuel Storage Installation (ISFSI). In the upcoming months in Zorita NPP in Spain will initiate dismantlement and decommissioning activities to return the site to a non-nuclear facility. The development of the EPRI DFD process has been an on-going evolution and much has been learned from its use in the past. It is effective in attaining very high decontamination factors; however, DFD also produces secondary waste in the form of ion exchange resins. This secondary waste generation adds to the decommissioning quota but this can be improved upon at a time when radioactive waste storage at nuclear facilities and waste disposal sites is limited. To reduce the amount of secondary waste, EPRI has developed the DFDX process. This new process is an enhancement to the DFD process and produces a smaller amount of metallic waste rather than resin waste; this reduction in volume being a factor of ten or greater. Electrochemical ion exchange cells are the heart of the DFDX system and contain electrodes and cation ion exchange resin. It has been used very successfully in small system applications and the next evolution

  18. Radiological characterisation and decommissioning in Denmark

    Danish Decommissioning (DD) is currently decommissioning the last Danish research reactor (DR3) and the Hot Cell facility. The DR3 project will soon finish dismantling of the external parts of the reactor (January 2012). The approval for dismantling of neutron activated and tritium contaminated heavy water pumps and tubing was granted in December 2011. DD will begin the work on the inner parts as the tendering process for equipment will start in 2012. Hereafter the dismantling of the top of the reactor will begin using the obtained remote controlled equipment. The Hot Cell facility consists of 6 contaminated cells. The first cell have been opened and cleaned. Currently the work progresses by removing parts and hot spots from the other cells with the use of robotic equipment. Challenges, lack of conventional and radiological documentation, dose rates and contamination higher than expected and the confined space in the cells have delayed the project. No final repository exists in Denmark. Therefore no official Waste Acceptance Criteria (WAC) have been formulated. However the Danish authority (SIS) does require a description of the waste in the interim storage facility (Inventory). Furthermore radiological characterisation of key nuclides is needed during decommissioning and dismantling. The information gained from the characterisation helps in the planning phase prior to the dismantling and for inventory calculations for later use. DD performs the radiological characterisation via both non-destructive and destructive analysis on samples. The samples are measured with gamma spectroscopy using mathematical and geometrical analysis. Scaling factors are used for neutron activated waste (DR3) to determine the difficult-to-measure isotopes and pure beta emitters. The primary scaling isotope is Co-60. Waste from the Hot Cell facility is alpha contaminated and scaling procedures for determination of alpha contamination are currently used in the planning process. Scaling of

  19. Heavy Water Components Test Reactor Decommissioning

    The Heavy Water Components Test Reactor (HWCTR) Decommissioning Project was initiated in 2009 as a Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) Removal Action with funding from the American Recovery and Reinvestment Act (ARRA). This paper summarizes the history prior to 2009, the major D and D activities, and final end state of the facility at completion of decommissioning in June 2011. The HWCTR facility was built in 1961, operated from 1962 to 1964, and is located in the northwest quadrant of the Savannah River Site (SRS) approximately three miles from the site boundary. The HWCTR was a pressurized heavy water test reactor used to develop candidate fuel designs for heavy water power reactors. In December of 1964, operations were terminated and the facility was placed in a standby condition as a result of the decision by the U.S. Atomic Energy Commission to redirect research and development work on heavy water power reactors to reactors cooled with organic materials. For about one year, site personnel maintained the facility in a standby status, and then retired the reactor in place. In the early 1990s, DOE began planning to decommission HWCTR. Yet, in the face of new budget constraints, DOE deferred dismantlement and placed HWCTR in an extended surveillance and maintenance mode. The doors of the reactor facility were welded shut to protect workers and discourage intruders. In 2009 the $1.6 billion allocation from the ARRA to SRS for site footprint reduction at SRS reopened the doors to HWCTR - this time for final decommissioning. Alternative studies concluded that the most environmentally safe, cost effective option for final decommissioning was to remove the reactor vessel, both steam generators, and all equipment above grade including the dome. The transfer coffin, originally above grade, was to be placed in the cavity vacated by the reactor vessel and the remaining below grade spaces would be grouted. Once all above equipment

  20. Childhood IQ and life course socioeconomic position in relation to alcohol induced hangovers in adulthood: the Aberdeen children of the 1950s study

    Batty, G D; Deary, I J; MacIntyre, S

    2006-01-01

    Objective: To examine the association between scores on IQ tests in childhood and alcohol induced hangovers in middle aged men and women. Design, Setting, and Participants: A cohort of 12 150 people born in Aberdeen (Scotland) who took part in a school based survey in 1962 when IQ test scores were extracted from educational records. Between 2000 and 2003, 7184 (64%) responded to questionnaire inquiries regarding drinking behaviour. Main outcome measures: Self reported hangovers attr...

  1. Lumbar Disc Screening Using Back Pain Questionnaires: Oswestry Low Back Pain Score, Aberdeen Low Back Pain Scale, and Acute Low Back Pain Screening Questionnaire

    Kim, Do Yeon; Oh, Chang Hyun; Yoon, Seung Hwan; Park, Hyung Chun; Park, Chong Oon

    2012-01-01

    Objective To evaluate the usefulness of back pain questionnaires for lumbar disc screening among Korean young males. Methods We carried out a survey for lumbar disc screening through back pain questionnaires among the volunteers with or without back pain. Three types of back pain questionnaire (Oswestry Low Back Pain Score, Aberdeen Low Back Pain Scale, and Acute Low Back Pain Screeing Questionnaire) were randomly assigned to the examinees. The authors reviewed lumbar imaging studies (simple ...

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

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

  3. Decommissioning of nuclear facilities in Korea

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

  4. Heterose sobre os pesos de bovinos Canchim e Aberdeen Angus e de seus cruzamentos recíprocos Heterosis upon weights in Canchim and Aberdeen Angus calves and in their reciprocal crosses

    DANIEL PEROTTO

    2000-12-01

    Full Text Available O trabalho foi conduzido para estimar a heterose sobre os pesos ao nascimento (PNT, à desmama (P210 e ao ano (P365 e sobre os ganhos de pesos médios diários do nascimento à desmama (G210 e da desmama ao ano (G365 nas quatro primeiras gerações do sistema de cruzamentos alternados entre as raças Canchim (C e Aberdeen Angus (A. Os dados de 1.147 bezerros nascidos de 1981 a 1998 foram analisados pelo método dos mínimos quadrados, ajustando-se um modelo linear que incluiu os efeitos linear e quadrático da idade da mãe do bezerro e os efeitos fixos de sexo, grupo genético, mês e ano de nascimento do bezerro. Estimativas de heterose e de outras diferenças genéticas foram estimadas por contrastes entre médias e testadas pelo teste t. O contraste "CA" foi positivo e significativo (PThe study was conducted to estimate heterosis upon birth weight (PNT, weaning weight (P210, yearling weight (P365 and daily weight gain from birth to weaning (G210 and from weaning to one year of age (G365 in the first, second, third and fourth generations of a rotational crossbreeding system between Canchim (C and Aberdeen Angus (A. Data from 1,147 calves born from 1981 to 1998 were analyzed by least squares procedures fitting a linear model that included the linear and the quadratic effects of age of the dam of the calf plus the fixed effects of sex, genetic group, month and year of birth of calf. Estimates of heterosis and of other genetic differences were obtained by linear contrasts of appropriate means and tested by the t test. The contrast CA was positive and significant (P<0.001 for all five traits. The contrast F1CAF1AC was negative and highly significant (P<0.001 for P210 and for G210 and significant (P<0.05 for P365. The F1 generation exhibited heterosis of 4.8% for P210 and of 4.9% for G210. Maternal heterosis was 3.7%, 5.8%, 6.3% and 20.4%, respectively, for P210, G210, P365 and G365. The heterosis estimated for the mean of the third and fourth

  5. IAEA Assistance on Decommissioning of Small Facilities with Limited Resources

    The number of facilities reaching their lifetime is increasing and drawing the attention of operators, regulators, public and other interested parties (potential users of the site after decommissioning) on the importance of adequate planning, funding and implementation of decommissioning activities in compliance with regulatory requirements and criteria. Specific attention is required for small facilities that have been used for research purposes and in most cases state owned by and dependent on state funding. With the current tendency for expansion of the nuclear industry such small facilities could become less of importance for the operators which can increase the probability that these facilities become abandoned, hazardous and imposing undue burden to future generations. This concern is more related to countries with limited human and financial resources at the operating organizations and the regulatory body. The International Atomic Energy Agency (IAEA) has been working on the; (i) establishment of internationally recognized safety standards on decommissioning and (ii) providing Member States with assistance on the application of these standards. The recent international conference on Lessons Learned from the Decommissioning of Nuclear Facilities and the Safe Termination of Practices (Athens, Greece, 2006) has demonstrated that the set of IAEA standards is almost complete and that the International Action Plan on Decommissioning (2004), that is addressing decommissioning of small facilities, is being successfully implemented. However the need for further assistance on decommissioning of small facilities in countries with limited resources was also recognized and the Agency is planning its future work in this field. The IAEA also addresses the needs of small nuclear countries that have only a limited number of nuclear facilities, e.g. a research reactor, in its Research Reactor Decommissioning Demonstration Project (R2D2P. The Philippine Research Reactor (PRR-1

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

    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

  7. 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

    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

  8. Study on decommissioning (Annual safety research report, JFY 2011)

    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)

  9. Problems and experience of research reactor decommissioning

    According to the IAEA research reactor database there are about 300 research reactors worldwide. At present above 30% of them have lifetime more than 35 years, 60% - more then 25 years. After the Chernobyl accident significant efforts have been made by many countries to modernize old research reactors aiming, first of all, at ensuring of its safe operation. However, a large number of aging research reactor will be facing shutdown in the near future. Before developing the design and planning of the works it is necessary to define the concept of the reactor decommissioning. It is defined by the time of the beginning of dismantling works after the reactor shutdown and the finite state of the reactor site.The concept of the reactor decommissioning provides 3 variants in a general case: reactor conservation, or partial dismantling, or complete dismantling to 'green field' state. Specialists of three International institutions (European Commission, IAEA and the Nuclear Energy Agency/Organization for Economic Cooperation and Development) have developed a detailed plan of all actions and operations on nuclear power plants decommissioning in the framework of a joint project for cost assessment. For the reactor decontamination the following main constructions, equipment and devices are necessary: temporary storage facility for the spent fuel; general site-dismantling equipment including manipulators and 'hot' cells; facilities for 'active' equipment, personnel, tooling and washing decontamination; equipment for concentration of liquid and compactness of solid radioactive waste; temporary storage facility for radioactive waste; instrumentation and radiometric devices including , α,β,γ-spectrometers; transportable containers and other means for transportation of fuel and radioactive materials

  10. Feedback from the decommissioning of two accelerators

    Saclay Linear Accelerator (ALS) and Saturne synchrotron, both well known as international research instruments, have definitively stopped operating in 1990 and 1997 respectively. The French Atomic Energy Commission (CEA) has decided proceeding with the appropriate actions in order to dismantle these two nuclear installations (NIs) known as INB 43 (ALS) and INB 48 (Saturne). The SDA (Accelerator Decommissioning Division) was created to be in charge of the dismantling procedure of the above NIs under the following conditions: - to maintain within the team a few employees from the previous exploitation of two NIs, in order not to loose the details and history of accelerator operation; - to import the necessary skills for a good management of dismantling operation such as waste management, ANDRA rules, project AMEC34omelt.com. Learn more about GeoMelt ats-gssr410nuclear safety, radiation protection, ALARA concepts, etc. Presently the dismantling operations are well under way at INB 43 and nearly finished at INB 48. The project organisation established by SDA has allowed meeting both the schedule and cost requirements of the decommissioning. At the beginning, major decommissioning safety characteristics of large research instruments will be presented and dismantling aspects in particular. Afterwards, the organization of both projects will be detailed, emphasizing their statutory aspects (e.g., safety documents, zoning, traceability, etc.) and technical difficulties. Waste characterisation as well as the choice of evacuation paths for each category of the waste will then be described in detail for both accelerators. A number of difficulties met during these procedures will be analysed and proposals will be made in order to improve the statutory framework in particular, both on technical and nuclear safety aspects. The application of the above experience to the dismantling of two fuel cycle installations, namely the research nuclear reactors, is presently under study

  11. FAMS DECOMMISSIONING END-STATE ALTERNATIVE EVALUATION

    Nuclear Material Management (NMM) completed a comprehensive study at the request of the Department of Energy Savannah River Operations Office (DOE-SR) in 2004 (Reference 11.1). The study evaluated the feasibility of removal and/or mitigation of the Pu-238 source term in the F-Area Material Storage (FAMS) facility during on-going material storage operations. The study recommended different options to remove and/or mitigate the Pu-238 source term depending on its location within the facility. During April 2005, the Department of Energy (DOE) sent a letter of direction (LOD) to Washington Savannah River Company (WSRC) directing WSRC to implement a new program direction that would enable an accelerated shutdown and decommissioning of FAMS (Reference 11.2). Further direction in the LOD stated that effective December 1, 2006 the facility will be transitioned to begin deactivation and decommissioning (D and D) activities. To implement the LOD, Site D and D (SDD) and DOE agreed the planning end-state would be demolition of the FAMS structure to the building slab. SDD developed the D and D strategy, preliminary cost and schedule, and issued the deactivation project plan in December 2005 (Reference 11.3). Due to concerns and questions regarding the FAMS planning end-state and in support of the project's Critical Decision 1, an alternative study was performed to evaluate the various decommissioning end-states and the methods by which those end-states are achieved. This report documents the results of the alternative evaluation which was performed in a structured decision-making process as outlined in the E7 Manual, Procedure 2.15, ''Alternative Studies'' (Reference 11.4)

  12. Modern practice of cost estimates for the NPP units decommissioning

    The results of analysis of current practices of cost estimates for decommissioning of nuclear power units with different reactor types present is reviewed. Cost estimates intervals are shown for decommissioning of units with PWR,BWR and AP1000 reactors and the main factors influencing the cost amount are analyzed

  13. Decommissioning cost evaluation for Korean Nuclear Power Plants

    A systematic study was performed to develop decommissioning cost evaluation technology and to establish optimum decommissioning plan for Korean nuclear power plants. Eight decommissioning options for Kori unit I including DECON, SAFSTOR and ENTOMB were considered for detailed cost analysis. Immediate and delayed dismantling scenarios were compared each other in regards to economic, technical and social aspects. Fourteen decommissioning unit activities were considered in estimating unit cost factors including labor cost, consumables cost and equipment cost. The decommissioning cost for Kori unit 1 was lowest for DECON option and highest for ENTOMB-3 option in which the site recovery was made after entombment of 300 years. The main cost of the SAFSTOR option resulted from the dismantling and extended safe storage. For a long decommissioning period, the discount rate is crucial in estimating the decommissioning cost. The difference among decommissioning options was negligible in cost if a discount rate of 2% was assumed. The long-term safe storage option also became advantageous relative to the immediate dismantling option as the discount rate increased. (author)

  14. Decommissioning and material recycling. Radiation risk management issues

    Once nuclear fuel cycle facilities have permanently stopped operations they have to be decommissioned. The decommissioning of a nuclear facility involves the surveillance and dismantling of the facility systems and buildings, the management of the materials resulting from the dismantling activities and the release of the site for further use. The management of radiation risks associated with these activities plays an important role in the decommissioning process. Existing legislation covers many aspects of the decommissioning process. However, in most countries with nuclear power programmes legislation with respect to decommissioning is incomplete. In particular this is true in the Netherlands, where government policy with respect to decommissioning is still in development. Therefore a study was performed to obtain an overview of the radiation risk management issues associated with decommissioning and the status of the relevant legislation. This report describes the results of that study. It is concluded that future work at the Netherlands Energy Research Foundation on decommissioning and radiation risk management issues should concentrate on surveillance and dismantling activities and on criteria for site release. (orig.)

  15. IPR-R1 TRIGA research reactor decommissioning plan

    The International Atomic Energy Agency (IAEA) is concerning to establish or adopt standards of safety for the protection of health, life and property in the development and application of nuclear energy for peaceful purposes. In this way the IAEA recommends that decommissioning planning should be part of all radioactive installation licensing process. There are over 200 research reactors that have either not operated for a considerable period of time and may never return to operation or, are close to permanent shutdown. Many countries do not have a decommissioning policy, and like Brazil not all installations have their decommissioning plan as part of the licensing documentation. Brazil is signatory of Joint Convention on the safety of spent fuel management and on the safety of radioactive waste management, but until now there is no decommissioning policy, and specifically for research reactor there is no decommissioning guidelines in the standards. The Nuclear Technology Development Centre (CDTN/CNEN) has a TRIGA Mark I Research Reactor IPR-R1 in operation for 47 years with 3.6% average fuel burn-up. The original power was 100 k W and it is being licensed for 250 k W, and it needs the decommissioning plan as part of the licensing requirements. In the paper it is presented the basis of decommissioning plan, an overview and the end state / final goal of decommissioning activities for the IPR-R1, and the Brazilian ongoing activities about this subject. (author)

  16. Decommissioning and material recycling. Radiation risk management issues

    Dodd, D.H.

    1996-09-01

    Once nuclear fuel cycle facilities have permanently stopped operations they have to be decommissioned. The decommissioning of a nuclear facility involves the surveillance and dismantling of the facility systems and buildings, the management of the materials resulting from the dismantling activities and the release of the site for further use. The management of radiation risks associated with these activities plays an important role in the decommissioning process. Existing legislation covers many aspects of the decommissioning process. However, in most countries with nuclear power programmes legislation with respect to decommissioning is incomplete. In particular this is true in the Netherlands, where government policy with respect to decommissioning is still in development. Therefore a study was performed to obtain an overview of the radiation risk management issues associated with decommissioning and the status of the relevant legislation. This report describes the results of that study. It is concluded that future work at the Netherlands Energy Research Foundation on decommissioning and radiation risk management issues should concentrate on surveillance and dismantling activities and on criteria for site release. (orig.).

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

    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)

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

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

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

    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)

  20. Studies on future decommissioning of the Swiss nuclear power plants

    The financing of future decommissioning of the Swiss nuclear power plants and the permanent, safe disposal of the wastes arising therefrom is secured by payments into a legally established decommissioning fund. In order to update the required level of payments into the fund, which have been ongoing since 1984, 20 years after the first study the costs of decommissioning have been re-calculated from scratch using complete decommissioning studies for each plant. Following the specification of boundary conditions which take into account the specific situation in Switzerland, decommissioning concepts are drawn up for the individual plants. The measures outlined in these concepts are integrated into a cost structuring plan and the decommissioning costs are then calculated using standard models (e.g. STILLKO). The radiological inventory, which is re-calculated for each plant, has a significant influence on costs. Furthermore, the disposal costs which can be allocated to decommissioning waste have to be determined; these are based on a concept in which only two types of containers are considered for disposal. The studies have resulted in decommissioning costs which, with a range between 200 and 390 million Euro, are comparable with costs in other countries. (orig.)

  1. Estimated doses from decommissioning activities at commercial nuclear power stations

    This paper reviews generic population dose estimates for decommissioning reference boiling water reactors (BWRs) and pressurized water reactors (PWRs) and provides extrapolated estimates of the total collective dose resulting from decommissioning commercial nuclear reactors operated in the United States. Decontamination and decommissioning of retired nuclear power reactors is a necessary part of the nuclear fuel cycle. During decommissioning of large facilities, radioactivity will be encountered in activated reactor components and in contaminated piping, equipment, and building surfaces. The US Nuclear Regulatory Commission (NRC) sponsored a series of studies to evaluate the technology, safety, and costs of decommissioning a variety of nuclear fuel cycle facilities. The NRC adopted the following standardized definitions concerning decommissioning: (1) decommissioning: the measures taken at the end of a facility's operating lifetime to ensure the protection of the public from any residual radioactivity or other hazards present in the facility; (2) DECON: immediate decontamination leading to the release of the facility for unrestricted use; (3) SAFSTOR: safe storage plus deferred decontamination leading to release of the facility for unrestricted use; and (4) ENTOMB: entombment plus decay leading to release of the facility for unrestricted use. In the NRC studies, the most likely decommissioning alternative for most facilities was assumed to be DECON or SAFSTOR

  2. Decontamination and decommissioning project for the nuclear facilities

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

  3. Decontamination and decommissioning project for the nuclear facilities

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

    2007-02-15

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

  4. IPR-R1 TRIGA research reactor decommissioning plan

    The International Atomic Energy Agency (IAEA) is concerning to establish or adopt standards of safety for the protection of health, life and property in the development and application of nuclear energy for peaceful purposes. In this way the IAEA recommends that decommissioning planning should be part of all radioactive installation licensing process. There are over 200 research reactors that have either not operated for a considerable period of time and may never return to operation or, are close to permanent shutdown. Many countries do not have a decommissioning policy, and like Brazil not all installations have their decommissioning plan as part of the licensing documentation. Brazil is signatory of Joint Convention on the safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, but until now there is no decommissioning policy, and specifically for research reactor there is no decommissioning guidelines in the standards. The Nuclear Technology Development Centre (CDTN/CNEN) has a TRIGA Mark I Research Reactor IPR-R1 in operation for 47 years with 3.6% average fuel burn-up. The original power was 100 kW and it is being licensed for 250 kW, and it needs the decommissioning plan as part of the licensing requirements. In the paper it is presented the basis of decommissioning plan, an overview and the end state / final goal of decommissioning activities for the IPR-R1, and the Brazilian ongoing activities about this subject. (author)

  5. Optimization of Decommission Strategy for Offshore Wind Farms

    Hou, Peng; Hu, Weihao; Soltani, Mohsen;

    2016-01-01

    The life time of offshore wind farm is around 20 years. After that, the whole farm should be decommissioned which is also one of the main factors that contribute to the high investment. In order to make a costeffective wind farm, a novel optimization method for decommission is addressed in this...

  6. The regulatory process for the decommissioning of nuclear facilities

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

  7. Optimising waste management performance - The key to successful decommissioning

    Available in abstract form only. Full text of publication follows: On the 1. of April 2005 the United Kingdom's Nuclear Decommissioning Authority became responsible for the enormous task of decommissioning the UK's civilian nuclear liabilities. The success of the NDA in delivering its key objectives of safer, cheaper and faster decommissioning depends on a wide range factors. It is self-evident, however, that the development of robust waste management practices by those charged with decommissioning liability will be at the heart of the NDA's business. In addition, the implementation of rigorous waste minimisation techniques throughout decommissioning will deliver tangible environmental benefits as well as better value for money and release funds to accelerate the decommissioning program. There are mixed views as to whether waste minimisation can be achieved during decommissioning. There are those that argue that the radioactive inventory already exists, that the amount of radioactivity cannot be minimised and that the focus of activities should be focused on waste management rather than waste minimisation. Others argue that the management and decommissioning of the UK's civilian nuclear liability will generate significant volumes of additional radioactive waste and it is in this area where the opportunities for waste minimisation can be realised. (author)

  8. Utilization of reactor bays of decommissioned submarines

    Radiation concerns regarding dismantling and storage of decommissioned reactors and reactor bays from nuclear submarines are briefly summarized. Calculation results are presented for gamma dose rates, contamination density, and the expected location of maximum exposure dose rate on the submarine hull. However, it is noted that radiation measurements must be obtained for each ship due to differences in operating conditions. Long-term storage options for containerized reactors and reactor bays are very briefly outlined; these include placing them in concrete-lined trenches shielded from the atmosphere or in underground tunnels shielded from water. 5 refs., 1 fig., 1 tab

  9. Barseback NPP in Sweden - transition to decommissioning

    On 5 February 1998, the government decided, [on the basis of the law on the phasing-out of nuclear power], that Barsebaeck 1 should close in June 1998. An appeal to the Supreme Administrative Court meant that the closure was temporarily postponed. After the Supreme Administrative Court declared that the government's decision should stand, Barsebaeck 1 was closed permanently on 30 November 1999. BKAB organization during service operation, labour turnover, scenario for decommissioning of Barsebaeck-1 and personnel development and staff reduction are presented. (author)

  10. Decommissioning of surplus facilities at ORNL

    The Surplus Facilities Management Program (SFMP) at Oak Ridge National Laboratory (ORNL) is part of the Department of Energy's (DOE) National SFMP, administered by the Richland Operations Office. This program was established to provide for the management of certain DOE surplus radioactively contaminated facilities from the end of their operating life until final facility disposition is completed. As part of this program, the ORNL SFMP oversees some 75 facilities, ranging in complexity from abandoned waste storage tanks to large experimental reactors. This paper describes the scope of the ORNL program and outlines the decommissioning activities currently underway, including a brief description of the decontamination techniques being utilized. 4 refs., 3 figs., 2 tabs

  11. Decommissioning of nuclear installations at CIEMAT

    This report presents the work carried out by CIEMAT in the frame of decommissioning the research reactor JEN-1. Studies for evaluating different metal cutting techniques, including plasma-arc cutting, contact-arc cutting and mechanical saw cutting led to assessing the performance, advantages and associated problems for each technique. The main metallic material studied was aluminium, but some experiments with stainless steel were also conducted. Melting was also studied as a decontamination technique and as a way to reduce volume and facilitate the management of radioactive waste. (author)

  12. Nuclear power plant A-1 decommissioning

    In the presentation, some information concerning the historical background of NPP A-1 in Jaslovske Bohunice, Slovakia is given. The main technical parameters used during production activities concerning the decommissioning of the NPP A-1 to a first stage (i.e. to obtain radiologically safe stage) are solved together with the main contractor, Nuclear Power Plant Research Institute, Trnava, according to an approved project by the Slovak Government and Nuclear Authorities. The technological schemes for the radioactive waste treatment at SE-VYZ o.z. and their main technical parameters are shown as well. (author)

  13. Allocation of Decommissioning and Waste Liabilities

    The work demonstrates that there are a number of methods available for cost allocation, the pros and cons of which are examined. The study investigates potential proportional and incremental methods in some depth. A recommendation in principle to use the latter methodology is given. It is concluded that a 'fair assumption' is that the potential allocation of costs for 'the RMA Leaching Hall' probably is small, in relation to the total costs, and estimated to be not more than about 175 kSEK, plus any costs associated with decommissioning/ disposal of a number of small pieces of equipment added by the current operator

  14. Decommissioning of nuclear power plants - safety aspects

    The stages of decommissioning a nuclear power plant are presented in popular form. There exist two alternatives: Safe containment of activated and highly contaminated components within the nuclear power plant unit or dismantling of all components and buildings. Stage 1 provides for safe containment in a) previously sealed buildings without any dismantling; b) containment resp. reactor building; c) underground structures. Stage 2 provides for partial dismantling with safe containment of the remaining parts a) within the biological shield, b) underground, after dismantling the parts above ground level. Stage 3 provides for total dismantling. (orig.)

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

    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

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

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

  17. Treatment of Decommissioning Combustible Wastes with Incineration Technology

    Min, B. Y. Min; Yang, D. S.; Yun, G. S.; Lee, K. W.; Moon, J. K. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-05-15

    The aim of the paper is current status of management for the decommissioning radioactive combustible and metal waste in KAERI. In Korea, two decommissioning projects were carried out for nuclear research facilities (KRR-1 and KRR-2) and a uranium conversion plant (UCP). Through the two decommissioning projects, lots of decommissioning wastes were generated. Decommissioning waste can be divided into radioactive waste and releasable waste. The negative pressure of the incineration chamber remained constant within the specified range. Off-gas flow and temperature were maintained constant or within the desired range. The measures gases and particulate materials in the stack were considerably below the regulatory limits. The achieved average volume reduction ratio during facility operation is about 1/65.

  18. Treatment of Decommissioning Combustible Wastes with Incineration Technology

    The aim of the paper is current status of management for the decommissioning radioactive combustible and metal waste in KAERI. In Korea, two decommissioning projects were carried out for nuclear research facilities (KRR-1 and KRR-2) and a uranium conversion plant (UCP). Through the two decommissioning projects, lots of decommissioning wastes were generated. Decommissioning waste can be divided into radioactive waste and releasable waste. The negative pressure of the incineration chamber remained constant within the specified range. Off-gas flow and temperature were maintained constant or within the desired range. The measures gases and particulate materials in the stack were considerably below the regulatory limits. The achieved average volume reduction ratio during facility operation is about 1/65

  19. Windscale advanced gas-cooled reactor (WAGR) decommissioning project overview

    The current BNFL reactor decommissioning projects are presented. The projects concern power reactor sites at Berkely, Trawsfynydd, Hunterstone, Bradwell, Hinkley Point; UKAEA Windscale Pile 1; Research reactors within UK Scottish Universities at East Kilbride and ICI (both complete); WAGR. The BNFL environmental role include contract management; effective dismantling strategy development; implementation and operation; sentencing, encapsulation and transportation of waste. In addition for the own sites it includes strategy development; baseline decommissioning planning; site management and regulator interface. The project objectives for the Windscale Advanced Gas-Cooled Reactor (WAGR) are 1) Safe and efficient decommissioning; 2) Building of good relationships with customer; 3) Completion of reactor decommissioning in 2005. The completed WAGR decommissioning campaigns are: Operational Waste; Hot Box; Loop Tubes; Neutron Shield; Graphite Core and Restrain System; Thermal Shield. The current campaign is Lower Structures and the remaining are: Pressure vessel and Insulation; Thermal Columns and Outer Vault Membrane. An overview of each campaign is presented

  20. Standard Guide for Radiation Protection Program for Decommissioning Operations

    American Society for Testing and Materials. Philadelphia

    1987-01-01

    1.1 This guide provides instruction to the individual charged with the responsibility for developing and implementing the radiation protection program for decommissioning operations. 1.2 This guide provides a basis for the user to develop radiation protection program documentation that will support both the radiological engineering and radiation safety aspects of the decommissioning project. 1.3 This guide presents a description of those elements that should be addressed in a specific radiation protection plan for each decommissioning project. The plan would, in turn, form the basis for development of the implementation procedures that execute the intent of the plan. 1.4 This guide applies to the development of radiation protection programs established to control exposures to radiation and radioactive materials associated with the decommissioning of nuclear facilities. The intent of this guide is to supplement existing radiation protection programs as they may pertain to decommissioning workers, members of...

  1. Decommissioning of a mixed oxide fuel fabrication facility

    Decommissioning of the coprecipitation plant, which made plutonium/uranium oxide fuel, is a lead project in the BNFL Sellafield decommissioning programme. The overall programme has the objectives of gaining data and experience in a wide range of decommissioning operations and hence in this specific project to pilot the decommissioning of plant heavily contaminated with plutonium and other actinides. Consequently the operations have been used to test improvements in temporary containment, contamination control and decontamination methods and also to develop in situ plutonium assay, plutonium recovery and size-reduction methods. Finally the project is also yielding data on manpower requirements, personnel radiation uptake and waste arisings to help in the planning of future decommissioning projects

  2. Introduction to decommissioning activities implemented by EWN in Germany

    Germany stands among the front runners in the field old decommissioning of commercial nuclear power plants, from the standpoints of length of experience and scale of work. In Germany, EWN is now working on the decommissioning of six nuclear reactors. This is the largest decommissioning activity being performed in the world. JGC concluded a collaboration agreement with EWN in February 1999 with the aim of utilizing all the decommissioning-related information and technologies accumulated by EWN since 1991. This report introduces 1) the status of the decommissioning which EWN has implemented at the Greifswald NPP; 2) project management practices which are required for efficient work; and 3) remote techniques for the reactor dismantling, these being important from a schedule point of view. (author)

  3. U.S. experience with organizational issues during decommissioning

    The report provides information from a variety of sources, including interviews with US NRC management and staff, interviews and discussions with former employees of a decommissioned plant, discussions with subject matter experts, and relevant published documents. The NRC has modified its rule regarding decommissioning requirements. Two key reasons for these modifications are that plants have been decommissioning early and for economic reasons instead of at the end of their license period and, a desire for a more efficient rule that would more effectively use NRC staff. NRC management and staff expressed the opinion that resource requirements for the regulatory have been higher than anticipated. Key observations about decommissioning included that: The regulator faces new challenges to regulatory authority and performance during decommissioning. The public concern over decommissioning activities can be very high. There are changes in the types of safety concerns during decommissioning. It is important to balance planning and the review of plans with verification of activities. There are important changes in the organizational context at the plant during decommissioning. Retention of key staff is important. In particular, the organizational memory about the plant that is in the staff should not be lost. Six key areas of risk during decommissioning are fuel storage, potential accidents that could cause an offsite release, inappropriate release of contaminated material, radiation protection of workers, industrial accidents, and shipment of hazardous materials. Deconstruction of one unit while a co-located unit is still operating could create risks with regard to shared systems, specific risks of dismantling activities and coordination and management. Experience with co-located units at one site in the US was that there was a lack of attention to the decommissioning plant

  4. Feedback experience from the decommissioning of Spanish nuclear facilities

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

  5. Review of decommissioning, spent fuel and radwaste management in Slovakia

    Two nuclear power plants with two WWER reactors are currently under operation in Jaslovske Bohunice and NPP A-1 is under decommissioning on the same site. At the second nuclear site in the Slovak Republic in Mochovce third nuclear power plant with two units is in operation. In accordance with the basic Slovak legislation (Act on Peaceful Utilisation of Nuclear Energy) defining the responsibilities, roles and authorities for all organisations involved in the decommissioning of nuclear installations Nuclear Regulatory Authority requires submission of conceptual decommissioning plans by the licensee. The term 'decommissioning' is used to describe the set of actions to be taken at the end of the useful life of a facility, in order to retire the facility from service while, simultaneously, ensuring proper protection of the workers, the general public and the environment. This set of activities is in principle comprised of planning and organisation of decommissioning inclusive strategy development, post-operational activities, implementation of decommissioning (physical and radiological characterisation, decontamination, dismantling and demolition, waste and spent fuel management), radiological, aspects, completion of decommissioning as well as ensuring of funding for these activities. Responsibility for nuclear installations decommissioning, radwaste and spent fuel, management in Slovakia is with a subsidiary of Slovak Electric called Nuclear Installations Decommissioning Radwaste and Spent Fuel Management (acronym SE VYZ), established on January 1, 1996. This paper provides description of an approach to planning of the NPP A-1 and NPPs with WWER reactors decommissioning, realisation of treatment, conditioning and disposal of radwaste, as well as spent fuel management in Slovakia. It takes into account that detail papers on all these issues will follow later during this meeting. (author)

  6. Nuclear facility decommissioning and site remedial actions

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

  7. Decommissioning plan depleted uranium manufacturing facility

    Aerojet Ordnance Tennessee, Inc. (Aerojet) is decommissioning its California depleted uranium (DU) manufacturing facility. Aerojet has conducted manufacturing and research and development activities at the facility since 1977 under a State of California Source Materials License. The decontamination is being performed by a contractor selector for technical competence through competitive bid. Since the facility will be released for uncontrolled use it will be decontaminated to levels as low as reasonably achievable (ALARA). In order to fully apply the principles of ALARA, and ensure the decontamination is in full compliance with appropriate guides, Aerojet has retained Rogers and Associaties Engineering Corporation (RAE) to assist in the decommissioning. RAE has assisted in characterizing the facility and preparing contract bid documents and technical specifications to obtain a qualified decontamination contractor. RAE will monitor the decontamination work effort to assure the contractor's performance complies with the contract specifications and the decontamination plan. The specifications require a thorough cleaning and decontamination of the facility, not just sufficient cleaning to meet the numeric cleanup criteria

  8. Lessons learnt from Ignalina NPP decommissioning project

    The Ignalina Nuclear Power Plant (INPP) is located in Lithuania, 130 km north of Vilnius, and consists of two 1500 MWe RBMK type units, commissioned respectively in December 1983 and August 1987. On the 1. of May 2004, the Republic of Lithuania became a member of the European Union. With the protocol on the Ignalina Nuclear Power in Lithuania which is annexed to the Accession Treaty, the Contracting Parties have agreed: - On Lithuanian side, to commit closure of unit 1 of INPP before 2005 and of Unit 2 by 31 December 2009; - On European Union side, to provide adequate additional Community assistance to the efforts of Lithuania to decommission INPP. The paper is divided in two parts. The first part describes how, starting from this agreement, the project was launched and organized, what is its present status and which activities are planned to reach the final ambitious objective of a green field. To give a global picture, the content of the different projects that were defined and the licensing process will also be presented. In the second part, the paper will focus on the lessons learnt. It will explain the difficulties encountered to define the decommissioning strategy, considering both immediate or differed dismantling options and why the first option was finally selected. The paper will mention other challenges and problems that the different actors of the project faced and how they were managed and solved. The paper will be written by representatives of the Ignalina NPP and of the Project Management Unit. (author)

  9. Decommissioning plan for TRIGA Mark-3

    Park, Seung Kook; Jung, Ki Jung

    1999-04-01

    TRIGA Mark-3(KRR-2) is the second research reactor in Korea. Construction of KRR-2 was started in 1969 and first criticality was achieved in 1972. After 24 years operation, KRR-2 has stopped its operation at the end of 1995 due to normal operation of HANARO. KRR-2 was then decided to decommission in 1996 by government. Decontamination and decommissioning(D and D) will be conducted in accordance with domestic laws and international regulations. Selected method of D and D will be devoted to protect workers and environment and to minimize radioactive wastes produced. The major D and D work will be conducted safely by using conventional industrial equipment because of relatively low radioactivity and contamination in the facility. When removing activated concrete from reactor pool, it will be installed a temporary containment and ventilation system. In this paper, structure of KRR-2 and method of D and D in each step are presented and discussed. (author). 12 refs., 8 tabs., 12 figs.

  10. The Decommissioning Facility Characterization DB System (DEFACS)

    The computer system for the characterization on the nuclear facilities is established as the name of the DEFACS (DEcommissioning FAcility Characterization DB System). his system is consist of the four main part with the grouping of the items and it's code creation and management system, data input system, data processing and data out put system. All the data was processed by a simplified and formatted manner to provide useful information to the decommissioning planner. The four nuclear facilities are objected for the system; the KRR-1 and 2 (Research reactor), Uranium conversion plant (Nuclear chemical plant), UF4 pilot plant and the North Korea nuclear facility (5MWe Research Reactor). All the data from a nuclear facility was categorized and inputted into the several data fields in the input system, which were chosen by considering the facility characteristics. All the hardware is workstation for Web and DB server and PC grade computers for the users and the software 'ORACLE, RDBMS 11g' operated on the WINDOW 2008 O/S, was selected

  11. Nuclear facility decommissioning and site remedial actions

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

    1990-09-01

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

  12. Nuclear facility decommissioning and site remedial actions

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

    1989-09-01

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

  13. Decommissioning of the Risoe Hot Cell facility

    The Hot Cell facility at Risoe has been in active use since 1964. During the years several types of nuclear fuels have been handled and examined: test reactor fuel pins from the Danish reactor DR3, the Norwegian Halden reactor, etc; power reactor fuel pins from several foreign reactors, including plutonium enriched pins; HTGR fuel from the Dragon reactor. All kinds of physical and chemical non-destructive and destructive post irradiation examinations have been performed. Besides, different radiotherapy sources have been produced, mainly cobalt sources. The general object of the decommissioning programme for the Hot Cell facility was to obtain a safe condition for the total building that does not require the special safety provisions. The hot cell building will be usable for other purposes after decommissioning. The facilicy comprised six concrete cells, lead cells, glove boxes, a shielded unit for temporary storage of waste, frogman area, decontamination areas, workshops, various installations of importance for safe operation of the plant, offices, etc. The tasks comprised e.g. removal of all irradiated fuel items, removal of other radioactive items, removal of contaminated equipment, and decontamination of all the cells and rooms. The goal was to decontaminate all the concrete cells to a degree where no loose contamination exists in the cells, and where the radiation level is so low, that total removal of the cell structures can be done at any time in the future without significant dose commitments. (AB)

  14. Santo Amaro mineral sand mill decommissioning

    This site of 16 503 m2 held a monazite processing plant and in the metropolitan area of Sao Paulo, which is the largest city in Brazil. The plant operated for more than 60 years. As it has not been classified as a nuclear installation, the facility was not controlled by the national regulatory authority. As a consequence of the operations carried out at the site, it became contaminated with residues from mineral sands processing. Decommissioning activities started in 1994 and finished at the end of 1998. Decommissioning was carried out in five stages: (1) initially suitable packaging of contaminated material and waste removal took place; (2) decontamination and dismantling of equipment; (3) decontamination of floors and walls and demolition of the buildings (built area was about 13 000 m2); (4) land radiological characterization; 5) site clean-up. As long as Brazil does not have a national repository for low and intermediate level wastes, some of the generated wastes (about 60 m3) had to be stored in an adapted building at the Interlagos Mill site. Presently the most serious issue to be solved regards the final destination of the generated wastes

  15. Nuclear facility decommissioning and site remedial actions

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

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

    There are 48 commercial nuclear power stations in operation in Japan as of January 1, 1995, which supplies about 28% (2.2 x 108 MWh) of total annual electricity generation in FY 1992. Accordingly, as the nuclear power contributes so much in electricity generation, there is a growing concern in the public toward the safety on decommissioning nuclear power station. It is gravely important to secure the safety throughout the decommissioning. This paper discusses: the decommissioning situation in Japan; the Japanese national policy for decommissioning of commercial nuclear power stations; R and D for decommissioning of commercial nuclear power stations in Japan; and the present conditions of low-level radioactive wastes disposal in Japan

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

    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

    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. An audit to review the characteristics and management of placenta praevia at Aberdeen Maternity Hospital, 2009-2011.

    Pande, B; Shetty, A

    2014-07-01

    Placenta praevia (PP) is an important cause of maternal and fetal morbidity. We reviewed the characteristics and management of PP at the Aberdeen Maternity Hospital (AMH) to evaluate performance. In the years 2009-2011, a total of 60 cases with confirmed PP underwent caesarean section (CS) at the AMH. Two-fifths of cases had previous CS and two-thirds were posterior praevias. Four-fifths were major praevias. Diagnosis was mostly by trans-abdominal scanning (TAS). A little less than two-thirds underwent hospital admission (half of them for antepartum haemorrhage). Most received steroid and ferrous sulphate as appropriate. The majority were delivered at greater than 36 weeks' gestation. There was good support in theatre by senior obstetricians and anaesthetists. Cell salvage was used in theatre. Overall, the outcomes were good. Improvements could be made on documentation of counselling preoperatively and practice of trans-vaginal scans (TVS) to confirm low lying placentae even at the 20-week scan for better diagnosis, as per the RCOG guidelines. PMID:24702527

  20. Evaluation of depleted uranium in the environment at Aberdeen Proving Grounds, Maryland and Yuma Proving Grounds, Arizona. Final report

    This report represents an evaluation of depleted uranium (DU) introduced into the environment at the Aberdeen Proving Grounds (APG), Maryland and Yuma Proving Grounds (YPG) Arizona. This was a cooperative project between the Environmental Sciences and Statistical Analyses Groups at LANL and with the Department of Fishery and Wildlife Biology at Colorado State University. The project represents a unique approach to assessing the environmental impact of DU in two dissimilar ecosystems. Ecological exposure models were created for each ecosystem and sensitivity/uncertainty analyses were conducted to identify exposure pathways which were most influential in the fate and transport of DU in the environment. Research included field sampling, field exposure experiment, and laboratory experiments. The first section addresses DU at the APG site. Chapter topics include bioenergetics-based food web model; field exposure experiments; bioconcentration by phytoplankton and the toxicity of U to zooplankton; physical processes governing the desorption of uranium from sediment to water; transfer of uranium from sediment to benthic invertebrates; spead of adsorpion by benthic invertebrates; uptake of uranium by fish. The final section of the report addresses DU at the YPG site. Chapters include the following information: Du transport processes and pathway model; field studies of performance of exposure model; uptake and elimination rates for kangaroo rates; chemical toxicity in kangaroo rat kidneys

  1. Evaluation of depleted uranium in the environment at Aberdeen Proving Grounds, Maryland and Yuma Proving Grounds, Arizona. Final report

    Kennedy, P.L.; Clements, W.H.; Myers, O.B.; Bestgen, H.T.; Jenkins, D.G. [Colorado State Univ., Fort Collins, CO (United States). Dept. of Fishery and Wildlife Biology

    1995-01-01

    This report represents an evaluation of depleted uranium (DU) introduced into the environment at the Aberdeen Proving Grounds (APG), Maryland and Yuma Proving Grounds (YPG) Arizona. This was a cooperative project between the Environmental Sciences and Statistical Analyses Groups at LANL and with the Department of Fishery and Wildlife Biology at Colorado State University. The project represents a unique approach to assessing the environmental impact of DU in two dissimilar ecosystems. Ecological exposure models were created for each ecosystem and sensitivity/uncertainty analyses were conducted to identify exposure pathways which were most influential in the fate and transport of DU in the environment. Research included field sampling, field exposure experiment, and laboratory experiments. The first section addresses DU at the APG site. Chapter topics include bioenergetics-based food web model; field exposure experiments; bioconcentration by phytoplankton and the toxicity of U to zooplankton; physical processes governing the desorption of uranium from sediment to water; transfer of uranium from sediment to benthic invertebrates; spead of adsorpion by benthic invertebrates; uptake of uranium by fish. The final section of the report addresses DU at the YPG site. Chapters include the following information: Du transport processes and pathway model; field studies of performance of exposure model; uptake and elimination rates for kangaroo rates; chemical toxicity in kangaroo rat kidneys.

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

    Cost information is developed for the conceptual decommissioning of non-fuel-cycle nuclear facilities that represent a significant decommissioning task in terms of decontamination and disposal activities. This study is a re-evaluation of the original study (NUREG/CR-1754 and NUREG/CR-1754, Addendum 1). The reference facilities examined in this study are the same as in the original study and include: a laboratory for the manufacture of 3H-labeled compounds; a laboratory for the manufacture of 14C-labeled compounds; a laboratory for the manufacture of 123I-labeled compounds; a laboratory for the manufacture of 137Cs sealed sources; a laboratory for the manufacture of 241Am sealed sources; and an institutional user laboratory. In addition to the laboratories, three reference sites that require some decommissioning effort were also examined. These sites are: (1) a site with a contaminated drain line and hold-up tank; (2) a site with a contaminated ground surface; and (3) a tailings pile containing uranium and thorium residues. Decommissioning of these reference facilities and sites can be accomplished using techniques and equipment that are in common industrial use. Essentially the same technology assumed in the original study is used in this study. For the reference laboratory-type facilities, the study approach is to first evaluate the decommissioning of individual components (e.g., fume hoods, glove boxes, and building surfaces) that are common to many laboratory facilities. The information obtained from analyzing the individual components of each facility are then used to determine the cost, manpower requirements and dose information for the decommissioning of the entire facility. DECON, the objective of the 1988 Rulemaking for materials facilities, is the decommissioning alternative evaluated for the reference laboratories because it results in the release of the facility for restricted or unrestricted use as soon as possible. For a facility, DECON requires that

  3. Stakeholder involvement in the decommissioning of Dounreay

    The United Kingdom Atomic Energy Authority (UKAEA) was established in the 1950's to pioneer the development of nuclear energy within the UK. Today its primary mission is to decommission UK's former nuclear research sites and restore its environment in a way that is safe and secure, environmentally friendly, value for money and publicly Acceptable. UKAEA Dounreay celebrated its 50 birthday in 2005, having pioneered the development of fast reactor technology since 1955. Today the site is now leading the way in decommissioning. The Dounreay nuclear site licence covers an area of approximately 140 acres and includes 3 reactors: the Dounreay Material Test Reactor (DMTR), the Dounreay Fast Reactor (DFR), and the Prototype Fast Reactor (PFR). In addition there are 180 facilities on site which have supported the fast reactor programme, including a fuel reprocessing capability, laboratories and administration buildings. The reactors are now all in advanced stages of decommissioning. In October 2000 the Dounreay Site Restoration Plan (DSRP) was published to provide a framework for the site's restoration. The plan's objective was to reduce the site's hazards progressively by decontaminating and dismantling the plant, equipment and facilities, remediating contaminated ground and treating and packaging waste so it is suitable for long term storage or disposal. Whilst hailed as the most detailed plan integrating some 1500 activities and spanning 60 years it was criticised for having no stakeholder involvement. In response to this criticism, UKAEA developed a process for public participation over the following 2 years and launched its stakeholder engagement programme in October 2002. In order to provide a larger platform for the engagement process an advertisement was placed in the Scottish media inviting people to register as stakeholders in the Dounreay Site Restoration Plan. The stakeholder list now total over 1000. In October 2002 UKAEA launched their commitment to public

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

    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). PMID:18481140

  5. DECOMMISSIONING OF A CAESIUM-137 SEALED SOURCE PRODUCTION FACILITY

    Murray, A.; Abbott, H.

    2003-02-27

    Amersham owns a former Caesium-137 sealed source production facility. They commissioned RWE NUKEM to carry out an Option Study to determine a strategy for the management of this facility and then the subsequent decommissioning of it. The decommissioning was carried out in two sequential phases. Firstly robotic decommissioning followed by a phase of manual decommissioning. This paper describes the remote equipment designed built and operated, the robotic and manual decommissioning operations performed, the Safety Management arrangements and summarizes the lessons learned. Using the equipment described the facility was dismantled and decontaminated robotically. Some 2300kg of Intermediate Level Waste containing in the order of 4000Ci were removed robotically from the facility. Ambient dose rates were reduced from 100's of R per hour {gamma} to 100's of mR per hour {gamma}. The Telerobotic System was then removed to allow man access to complete the decommissioning. Manual decommissioning reduced ambient dose rates further to less than 1mR per hour {gamma} and loose contamination levels to less than 0.25Bq/cm2. This allowed access to the facility without respiratory protection.

  6. Decommissioning planning for the Joint European Torus Fusion Reactor

    The Joint European Torus (JET) machine is an experimental nuclear fusion device built in the United Kingdom by a European consortium. Tritium was first introduced into the Torus as a fuel in 1991 and it is estimated that at the end of operations and following a period of tritium recovery there will be 2 grams of tritium in the vacuum circuit. All in-vessel items are also contaminated with beryllium and the structure of the machine is neutron activated. Decommissioning of the facility will commence immediately JET operations cease and the UKAEA's plan is to remove all the facilities and to landscape the site within 10 years. The decommissioning plan has been through a number of revisions since 1995 that have refined the detail, timescales and costs. The latest 2005 revision of the decommissioning plan highlighted the need to clarify the size reduction and packaging requirements for the ILW and LLW. Following a competitive tender exercise, a contract was placed by UKAEA with NUKEM Limited to undertake a review of the waste estimates and to produce a concept design for the planned size reduction and packaging facilities. The study demonstrated the benefit of refining decommissioning planning by increasing the detail as the decommissioning date approaches. It also showed how a review of decommissioning plans by independent personnel can explore alternative strategies and result in improved methodologies and estimates of cost and time. This paper aims to describe this part of the decommissioning planning process and draw technical and procedural conclusions. (authors)

  7. Education and Training in Decommissioning Needs, Opportunities and Challenges

    The decommissioning of nuclear facilities is an industrial activity that is growing worldwide, creating job opportunities at all educational levels. Over the last decades, European companies have been involved in decommissioning projects that are targeted at delivering an environmentally friendly end-product, in line with the 'circular economy', as promoted by EU and national policies. European industry has acquired know-how and today Europe can position itself at the top level in the world decommissioning market. However, in view of the preparation of future decommissioning programmes, efforts are necessary to ensure and share the underpinning knowledge, skills and competences. In this perspective, the University of Birmingham in association with the European Commission's Joint Research Centre have organised a joint seminar to address the following questions in relation to education and training in nuclear decommissioning: - What are the competence needs for the future? - What are the education and training opportunities? - How can we stimulate interest and future talent? In answering these questions a report has been published which provides suggestions for helping the development, coordination and promotion of adequate education and training programmes at EU level in nuclear decommissioning. It highlights, in particular, the necessity to improve the long term planning of the resources and competences, addressing the specifics of decommissioning activities, to give more visibility to the career possibilities in the sector, and to enhance the cooperation between the existing education and training programmes, providing also more clarity in the learning outcomes. (authors)

  8. Decommissioning Experience: Magnox Reactors in the United Kingdom

    There are ten Magnox sites in the United Kingdom, nine of which are shut down and are defuelling and decommissioning. The Wylfa facility, in Wales, was due to shut down in 2014 but has been delayed. Magnox ponds are reinforced poured concrete structures with an epoxy paint coating. The decommissioning of Magnox ponds takes place once defuelling has been completed and is subject to an overarching fleet plan called the Magnox optimized decommissioning programme (MODP). The MODP has been determined to enable the most cost effective hazard reduction across the Magnox sites and to enable learning to be gained and transferred through delivering decommissioning as consistent programmes across all sites. For pond decommissioning, this involves the movement of experienced staff between sites to integrate with site teams and deliver the decommissioning of the ponds to a consistent methodology. Magnox has a decommissioning and radioactive waste management strategy that indicates full decontamination and removal and backfill of ponds and reflects lessons being learned from work completed to establish the most practicable means of risk reduction for each site. A summary of current Magnox experience is given below. An up to date overview of pond programme experiences across the Magnox sites is available on the Magnox web site

  9. Integrated approach to planning the remediation of sites undergoing decommissioning

    Available in abstract form only. Full text of publication follows: Decommissioning and remediation activities are subject to some common driving forces that influence the ability of decommissioning and remediation programs to achieve end-states that correspond to planned or anticipated (future) end-uses (i.e., facility or site re-use). In addition, decommissioning and remediation programs have common resources needs that, when identified and fully utilized in an integrated framework, can result in optimizing the use of available resources to achieve risk-based results faster and at lower costs. To achieve this, it is necessary that the goals of individual decommissioning and remediation activities are aligned and not conflict with each other while costs are minimized and net health, safety, security and environmental benefits are maximized. Managing the decommissioning and remediation activities in an integrated program can result in enhanced environmental conditions, and/or reduced requirements for additional remediation work, both of which impact the effort to achieve the ultimate site remediation objectives. The most important step in this process is the establishment of the site remediation objectives, which principally involves selecting the best re-use option for the site. Different technological approaches and different sequences of decommissioning and remediation tasks can be taken to transform the site to achieve its intended end-state. This paper presents a framework in which decommissioning and remediation activities developed altogether (i.e., in an integrated manner) will enhance the outcomes of both tasks. (authors)

  10. Procedures and Practices - Challenges for Decommissioning Management and Teamwork

    The mental and practical approach to a decommissioning project is often not the same at all levels of an organization. Studies indicate that the early establishment of a decommissioning mindset throughout an organization is an important and frequently overlooked process. It is not enough to establish procedures, if practices and mental approaches are overlooked; and for decommissioning projects that are more often than not dominated by one of a kind problem solving, procedure design is challenging, and new requirements are put on communication. Our research considers stakeholder involvement in these processes in the wider sense of the term; however the main stakeholders in focus are regulators and the work force that will perform or lead the tasks related to decommissioning. Issues here treated include: Decommissioning mindset and the manifestation of mindset issues in decommissioning projects, including challenges and prospective solutions; trust building and trust breaking factors in communication and collaboration relevant to transition and decommissioning; new technologies for collaboration and communication and how these may impair or empower participants - experiences from several domains. This paper is based on work done in collaboration with the OECD NEA Halden Reactor Project. (author)

  11. Decommissioning of small nuclear facilities: Problems encountered and lessons learned

    The decommissioning of small facilities may present a lower radiological risk and easier planning and implementation than the decommissioning of large facilities but some practical difficulties, lack of strategies, regulatory considerations and financial resources can create serious problems in the decommissioning of small facilities that should be solved properly. In past years, the Radioactive Waste Management Service of the Centre for Radiation Protection and Hygiene has been involved in different decommissioning projects involving small facilities, including laboratories and medical facilities, in which radioisotopes were used for research, diagnosis and treatment. For different reasons, some of these facilities became contaminated. The facilities were closed for a long time and no actions were taken. The decommissioning was not considered during the useful life of these facilities and therefore no plans were in place and no decommissioning related records were kept. Despite these problems, the decommissioning projects were carried out and successfully completed. Several difficulties were overcome and the safety issues received the adequate priority. The paper gives special emphasis on the problems encountered, the solutions, and the lessons learned from each situation. (author)

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

    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)

  13. Estimation of the Decommissioning Waste Arising for a PWR

    In Korea, Kori Unit 1(Pressurized Water Reactor, 587MW) began the first life extension operation since 2008 and Wolsong Unit 1(Canadian Deuterium Uranium Reactor, 679MW) has waited for the admission of life extension after license expiration since November 2012. However, after Fukushima Daichi nuclear power plant accident happened March 2011, the public support for the nuclear power plant life extension has been faded. This is reason why the preparation of nuclear power plant decommissioning is significant in this time. When it comes to the decommissioning cost estimation, the waste treatment and disposal possess about 17% ∼ 43% in the total decommissioning expense. Hence, the accurate analysis of the decommissioning cost has the immense influence on the determination of decommissioning strategy in later. Namely, as the fundamental investigation of the decommissioning outlay, the approach to the expected waste weight estimation is worth of study. In this study, the arising of waste weight during the decommissioning of Kori Unit 1 was estimated with some documents listed in the reference. Finally, the total expected waste amount during the Kori Unit 1 decommissioning is about 49,139 tons. Among them, assumed radioactive waste material is 1,915,214 kg(869 tons). Based on IAEA standard, these wastes are divided in HLW, ILW, LLW, VLLW and EW respectively. Future plan is to assess the radioactivity of primary side components and dose rate distribution of Kori Unit 1 using MCNP and ORIGEN-2 codes. This action will be helpful to design the reasonable decommissioning scenario in the future 4 session

  14. Safety Oversight of Decommissioning Activities at DOE Nuclear Sites

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

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

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

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

    Schulz, J.; Crawford, A.C. (Nuclear Behavioral Sciences Group of Applied Behavioral Sciences, Englewood, CO (United States))

    1993-07-01

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

  17. Operating Procedures to Identify Wastes of Decommissioning

    There are a number of sites in Iraq which have been used for nuclear activities and which contain potentially significant amounts of radioactive material. Many of these sites suffered substantial physical damage during the Gulf Wars as well as the challenging of the difficult security situation in the country.The destruction of the former nuclear facilities during the 1991 Gulf war aggravated the problem. As a result of these events, many of these nuclear facilities have lost their containment of the radioactive material and it now has an increased potential to be dispersed into the environment.Iraqi Decommissioning Directorate (IDD) is one of the Ministry of Science and Technology (MoST) formations. It deals with decommissioning of former Iraqi nuclear sites. It considers a producer of radioactive waste.Therefore, waste management represents the vital requirement to work accomplishment.The work carries out on-site waste pretreatment which considers as a minimization of waste management.W M is necessary to: Segregate 'at source' as much materials as possible to minimize quantities of radioactive waste, clear or exempt as much materials as possible and decontaminate and recycle as much radioactive waste as possible. And in more general terms: to control and account for radioactive waste to protect human health and the environment, to make sure we do not leave unnecessary burdens for future generations, to concentrate, contain and isolate the waste from the environment therefore, this make any releases to the environment to be restricted and subject to regulatory control.This procedure applies on-site waste pretreatment which comprises segregating, characterizing, minimizing, classifying, packaging and relocating of generated wastes during decommissioning of destroyed nuclear facilities. The stationary waste treatment activities are the responsibility of RWTD/MoST.The (RPC/MoE) is the national regulatory body during the whole radioactive waste management

  18. Development of decommissioning management system. 8. Study of JWTF decommissioning procedures

    The decommissioning evaluation system that evaluated and optimizes the decommissioning scenario (total amount of men and days, period of works, exposure dose, abundance of waste, cost) has been developed. In this report, for test study of old JWTF decontamination using the decommissioning evaluation system, survey work of location and surface dose rate of machines and pipes in old JWTF, calculation using the decommissioning evaluation system, comparing a scenario carrying out a decontamination work and one which did not use the decontamination work were carried out. Results are as follows. (1) The DECMAN calculated that total amount of men and days was 4.5 x 103 man day, period of works was 490 days, cost was 3.9 x 105 yen, abundance of waste was 1.4 x 102 ton (radioactive waste was 6.9 ton). (2) Total amount of men and days of a scenario using decontamination (scenario A) was nearly 1.3 times as large as one of a scenario which did not use decontamination (scenario B). Cost of 'A' was 2.0 times as large as that of B'. Exposure dose of 'A' was 1/4 times as low as that of 'B'. (3) The DECMAN overestimated exposed dose. The reason was thought as follows. The exposed dose from each equipments was estimated in 2 dimension. Distance between each equipments in the DECMAN was estimated short compared with actual distance. Workers were moving around the equipment in actual work, and averted stopping at high dose rate points. The system could not add the process in calculation. (author)

  19. Decontamination and Decommissioned Small Nuclear AIP Hybrid Systems Submarines

    Guangya Liu

    2013-11-01

    Full Text Available Being equipped with small reactor AIP is the trend of conventional submarine power in 21st century as well as a real power revolution in conventional submarine. Thus, the quantity of small reactor AIP Submarines is on the increase, and its decommissioning and decontamination will also become a significant international issue. However, decommissioning the small reactor AIP submarines is not only a problem that appears beyond the lifetime of the small reactor nuclear devices, but the problem involving the entire process of design, construction, running and closure. In the paper, the problem is explored based on the conception and the feasible decommissioning and decontamination means are supplied to choose from.

  20. Decommissioning health physics a handbook for MARSSIM users

    Abelquist, Eric W

    2001-01-01

    Decommissioning Health Physics presents many of the technical issues and challenges that arise during the planning and implementation of decommissioning and decontamination (D&D) projects. The focus is on the final status survey performed during the later stages of decommissioning projects. It expands upon and provides greater technical detail than Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM) in areas of survey design strategies.Featuring a number of completely worked examples of final status survey strategies, the book prepares the reader for the real-world ap

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

    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

  2. Decommissioning Planning for Nuclear Units at the Oskarshamn Site

    This paper will describe the process that OKG is now in and how the regulatory framework in Sweden is set out with EIA preparation, SAR updates, decommissioning plans etc. and how OKG plans to meet some of the challenges that need to be considered in front of the decommissioning. There will be a discussion on which strategic decisions will have priority and why. The paper will also discuss some of the difficulties with having a site with two units in decommissioning and one unit in power operation. (authors)

  3. MARSSIM recommended in states' guidance document for decommissioning.

    McBaugh, Debra; Stoffey, Phillip; Shuman, Howard; Young, Robert; Zannoni, Dennis

    2003-06-01

    States appreciate guidance for activities done infrequently or at only a few locations in the state. For many states, this is the case for decommissioning. Some states have reactors being decommissioned, some DOE sites undergoing cleanup, and some uranium mill or radium sites. Many, however, only occasionally do a small facility cleanup or, once in a great while, a large one. For this reason, most states participated in the readily available MARSSIM training and now recommend its use. For this same reason, the CRCPD Committee on Decontamination and Decommissioning (E24) developed a brief guidance document for state and licensee use. PMID:12792402

  4. R and D for decommissioning in the European Communities

    Since 1979, the European Community (EC) has been conducting three successive R and D programmes in the field of decommissioning of nuclear installations with the main objective of reinforcing the scientific and technical basis of decommissioning with a view to strengthening the safety and protection aspects. The current programme covers: six R and D projects concerning building integrity, decontamination, dismantling, treatment of waste materials, remote-controlled manipulator systems, estimation of radioactive wastes; identification of guidelines related to application of ALARA principle on decommissioning, and the technical elements of a Community policy; testing of new techniques in practice, particularly in the four pilot dismantling projects. (R.P.) 2 figs.; 3 tabs

  5. Radiological planning and implementation for nuclear-facility decommissioning

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

  6. Some aspects of the decommissioning of nuclear power plants

    Khvostova, M. S., E-mail: marinakhvostova@list.ru [St. Petersburg State Maritime Technical University (Sevmashvtuz), Severodvinsk Branch (Russian Federation)

    2012-03-15

    The major factors influencing the choice of a national concept for the decommissioning of nuclear power plants are examined. The operating lifetimes of power generating units with nuclear reactors of various types (VVER-1000, VVER-440, RBMK-1000, EGP-6, and BN-600) are analyzed. The basic approaches to decommissioning Russian nuclear power plants and the treatment of radioactive waste and spent nuclear fuel are discussed. Major aspects of the ecological and radiation safety of personnel, surrounding populations, and the environment during decommissioning of nuclear installations are identified.

  7. A study on the decommissioning of research reactor

    As the result of study on decommissioning, discussion has made and data have been collected about experiences, plannings, and techniques for decommissioning through visit to GA and JAERI. GA supplied our Research Reactor No. 1 and No. 2, and JAERI made a memorial museum after dicommissioning of JRR-1 and is dismentling JPDR now. Also many kinds of documents are collected and arranged such as documents related to TRIGA reactor dicommissioning, 30 kinds of documents including decommissioning plan, technical criteria and related regulatory, and 1,200 kinds of facility description data. (Author)

  8. European Decommissioning Academy (EDA) - successful 1. run in june 2015

    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 14 participants during 7.-20.6. 2015. Academy was focused on decommissioning issues via lessons, practical exercises in laboratories, on-site training prepared at NPP V-1 in Jaslovske Bohunice, Slovakia as well as 4 days technical tour to other European decommissioning facilities (Swiss, Italy), respectively. Detailed information can be found at http://kome.snus.sk/inpe/. (authors)

  9. KIT competence center for decommissioning. Innovation and promotion of trainees

    The safe decommissioning of nuclear installations is technically feasible, but is also still a challenge for science, technology and industry. The expertise and know how for decommissioning must be ensured because it will be needed for further decades. Already in 2008 the Karlsruhe Institute of Technology (KIT) had identified this challenge that later emerged through the closure of nuclear power plants in Germany. The KIT opened the professorship Technology and Management of the Decommissioning of Nuclear Installations. In 2014, this section was extended through the dismantling of conventional installations.

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

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

  11. Características da carcaça de bovinos Canchim e Aberdeen Angus e de seus cruzamentos recíprocos terminados em confinamento Carcass traits of Canchim, Aberdeen Angus and reciprocal crosses finished in confinement

    Daniel Perotto

    1999-06-01

    Full Text Available Foram analisadas quatorze características quantitativas das carcaças de 137 machos bovinos inteiros pertencentes aos grupos Canchim (Ca, Aberdeen Angus (Ab, 3/4Ca+1/4Ab, 3/4Ab+1/4Ca, 5/8Ca+3/8Ab e 5/8Ab+3/8Ca, nascidos na Estação Experimental Fazenda Modelo, em Ponta Grossa-PR, no período de 1988 a 1993. As médias para a idade e para o peso ao início do confinamento, duração do confinamento, idade e peso ao abate foram, respectivamente, 737 dias, 356kg, 97 dias, 834 dias e 468kg. Durante o confinamento, os garrotes receberam silagem de milho à vontade mais uma ração concentrada (79% de NDT, 17,8% de PB fornecida à base de 1% do peso vivo do animal por dia. Os grupos Ca e Ab diferiram entre si para todas as características, exceto para percentagem de costilhar (PEC. O Ca foi superior ao Ab para peso de carcaça quente (PCQ, rendimento de carcaça quente (RCQ, área de olho de lombo (AOL, conformação, percentagem de músculos (PEM, peso da porção comestível da carcaça (PPC e peso de carcaça quente por dia de vida ao abate (PCQ/DDV. O Ab superou o Ca quanto à espessura de gordura de cobertura (ECG e à percentagem de gordura (PEG. Houve heterose para PCQ, RCQ, AOL, PPC e PCQ/DDV. As duas gerações avançadas de cruzamentos alternados Ca x Ab apresentaram desempenho superior à média das raças paternas para PCQ, RCQ, AOL, PPC e PCQ/DDV. O desempenho de um esquema alternado de cruzamentos entre Ca e Ab seria melhor que o de qualquer dessas duas criada isoladamente.Fourteen quantitative carcass traits of 137 Canchim; 5/8 Charolais + 3/8 Zebu, (Ca, Aberdeen Angus (Ab, 3/4Ca+1/4Ab, 3/4Ab+1/4Ca, 5/8Ca+3/8Ab and 5/8Ab+3/8Ca, born at Est. Exp. Fazenda Modelo, in Ponta Grossa-PR, Brazil, from 1988 to 1993, were analyzed. Averages for age at beginning of confinement, initial weight, length of confinement period, final age and final weight were, respectively, 737 days, 356kg, 97 days, 834 days and 468kg. During the confinement period

  12. Estimated decommissioning cost for the 23 operating nuclear power reactors in Korea

    The decommissioning of nuclear power reactors requires considerable funds and is carried out over a long period. In order to forecast the total decommissioning funds needed by the licensee as well as provide a basis for industrial strategy and decommissioning activity planning, hence, this paper estimates the annual costs for decommissioning the 23 nuclear power plants in Korea between 2014 and 2083. For this estimation, 4 scenarios for decommissioning the 23 nuclear power reactors were developed and evaluated. (orig.)

  13. Design features facilitating the decommissioning of advanced gas-cooled reactors

    The design of the advanced gas-cooled reactors is discussed as is the proposed decommissioning plan for delayed decommissioning. The special features which assist in decommissioning are presented. As a result of the study a catalogue of design features which will facilitate decommissioning is given. In addition to the catalogue of design features, the radioactive inventory 10 years after shutdown and 100 years after shutdown has been calculated. From this a provisional operator dose from activities associated with decommissioning has been assessed

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

    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.

  15. Organization and management for decommissioning of large nuclear facilities

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

  16. Uranium enrichment decontamination and decommissioning fund

    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

  17. Remote control: Decommissioning RTGs [radioisotope theromelectric generators

    Several hundred radioisotope thermoelectric generators (RTGs) are deployed along the Russian Federation's Arctic coast to power remote lighthouses and navigation beacons. Similar RTGs were also used as power sources in other remote locations in the Russian Federation and elsewhere in the former Soviet Union. All Russian RTG's have out-lived their lifespan and are in need of decommissioning. The RTGs typically contain one or more radionuclide heat sources (RHS) each with an activity of thousands of TBq of strontium-90. This means that they are Category 1 sources as defined in the IAEA international 'Code of Conduct on the Safety and Security of Radioactive Sources'. According to the Federal Atomic Energy Agency of the Russian Federation (Rosatom), there are 651 RTGs at various locations in the Russian Federation which are subject to decommissioning or replacement with alternative sources of energy. The Norwegian Government has played a significant role in international efforts, fully cooperating with Russian authorities to safely decommission RTGs and provide alternative power sources. Norway has actively supported improvement of nuclear safety and security in northwest Russia for more then ten years. Over this period, the Norwegian Government has spent approximately $150 million on a variety of industrial projects, including specific improvements in radioactive waste treatment and storage, physical security, and infrastructure support. The national authority, the Norwegian Radiation Protection Authority (NRPA), takes an active part advising the Government regarding prioritization and quality assurance of all these activities. In addition, the Plan of Action places great emphasis on adequate regulatory supervision. Accordingly, the NRPA programme includes a variety of regulatory support projects. These are designed to assist the Russian authorities in ensuring that work is properly carried out within the framework of Russian law, taking into account international

  18. Decontamination, decommissioning, and vendor advertorial issue, 2008

    Agnihotri, Newal (ed.)

    2008-07-15

    The focus of the July-August issue is on Decontamination, decommissioning, and vendor advertorials. Articles and reports in this issue include: D and D technical paper summaries; The role of nuclear power in turbulent times, by Tom Chrisopher, AREVA, NP, Inc.; Enthusiastic about new technologies, by Jack Fuller, GE Hitachi Nuclear Energy; It's important to be good citizens, by Steve Rus, Black and Veatch Corporation; Creating Jobs in the U.S., by Guy E. Chardon, ALSTOM Power; and, and, An enviroment and a community champion, by Tyler Lamberts, Entergy Nuclear Operations, Inc. The Industry Innovations article is titled Best of the best TIP achievement 2008, by Edward Conaway, STP Nuclear Operating Company.

  19. Decontamination, decommissioning, and vendor advertorial issue, 2008

    The focus of the July-August issue is on Decontamination, decommissioning, and vendor advertorials. Articles and reports in this issue include: D and D technical paper summaries; The role of nuclear power in turbulent times, by Tom Chrisopher, AREVA, NP, Inc.; Enthusiastic about new technologies, by Jack Fuller, GE Hitachi Nuclear Energy; It's important to be good citizens, by Steve Rus, Black and Veatch Corporation; Creating Jobs in the U.S., by Guy E. Chardon, ALSTOM Power; and, and, An enviroment and a community champion, by Tyler Lamberts, Entergy Nuclear Operations, Inc. The Industry Innovations article is titled Best of the best TIP achievement 2008, by Edward Conaway, STP Nuclear Operating Company

  20. The DR-2 decommissioning project, Denmark

    The DR-2 reactor of the Risoe National Laboratory was closed down in 1975, the fuel removed, the circuits drained and the reactor sealed. In 1997 the DR-2 Study Project was initiated to determine the remaining radioactivity in the reactor and to plan the final decommissioning. So far all movable components have been removed from the reactor tank, measured and stored. The same is true, with two exceptions, for the hold-up tank room and work is under way on the components of the igloo at the thermal column. Later the thermal column, beam tubes and the interior of the primary circuit will be examined and holes will be drilled through the concrete shield. The lessons learned during the project are discussed. (author)