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Session 8-9 Abstracts 3) A SUCCESSFUL REMEDIATION PROJECT - 16400 L. Max Scott, Louisiana State University (USA) As part of a program to visit formerly licensed sites to determine if they meet current uncontrolled release conditions, a United States Nuclear Regulatory Commission (USNRC) inspection was conducted in the fall of 1993 at a site that had possessed a radioactive material license from about 1955 to 1970. While the license was in force, the plant processed magnesium scrap containing up to 4 percent thorium. <strong>The</strong> source of the scrap is believed to be the aircraft manufacturing industry. <strong>The</strong> scrap was placed in furnaces and heated to the melting point of magnesium, and the molten magnesium was drawn off, leaving the thorium with the residue (dross). Under the regulation in existence at that time, the thorium dross was buried on site in an approximate 14 acre field. In 1993 the inspector found readings up to 900uR/h. Early in 1994 an informal grid survey of most of the 14 acre site was conducted. Based on that survey, it was concluded that the thorium was widespread and extended beyond the property lines. <strong>The</strong> preliminary findings were reported to the USNRC, and in 1994 the site was designated as a Site Decommissioning Management Plan (SMPD) site. A remediation team was formed which included the following disciplines: remediation health physics, geology, hydrology, engineering, law, public relations, and project management. This remediation team planned, participated in selecting vendors, and provided project over site for all activities from site characterization through the final status survey. In 2006 the site was released for uncontrolled access. A chronology of activities with lessons learned will be presented. 4) EVALUATION AND POTENTIAL REMEDIATION OF THE INDUSTRIAL NORM LEGACY IN LIVERPOOL - 16096 Nigel Reeves, Gordon John, Bob Major, AMEC Nuclear Ltd.(UK) Sefton, on the north side of Liverpool, holds a radioactive legacy from its industrial past. This legacy is in the form of Tin slag buried in sub-surface seams. Located near the docks and adjacent to the rich Lancashire coal seams, Sefton became one of the main production centres of Tin plate in Britain. A consequence of this industrial process is the production of mildly radioactive waste slag. Tin rich ores are heated under reducing conditions to produce a molten metal stream This is then separated into the component metal streams. Solid wastes produced by this process are known as slag and were usually stored on site in spoil heaps. Because this slag is a very hard, glassy material it has been historically used as aggregate in underlying roads and rail way sleepers. Many of these sites pre-date the introduction of the regulation of radioactive substances in the UK and have never been under legislative control under the Radioactive Substances Act, RSA93. <strong>The</strong>re is a risk that the existence may not be known of some of these sites. U-238 and Th-232 and their associated decay chains, are the major contributors to the radionuclide inventory of the slags, levels of these radionuclides being in the range 1-10Bq/g. A series of alpha and beta decays for both chains leads eventually to the generation of a stable isotope of lead. Radiologically, the main area of concern is with the potential inhalation or ingestion of contaminated dusts. <strong>The</strong>re is also a potential for Ra-226 to leach out into groundwater. SESSION 9 - NATIONAL, MULTI-NATIONAL AND INTERNATIONAL 1) THE NUCLEAR ENGINEERING DOCTORATE AND NTEC CPD & MASTERS PROGRAMMES: EDUCATION, TRAINING AND RESEARCH FOR THE DECOMMISSIONING SKILLSBASE - 16395 John W. Roberts, University of Manchester (UK) Since its establishment in 2005 the Nuclear Decommissioning Authority has a remit to maintain the skillsbase for safe, secure and cost effective decommissioning of the existing UK civil nuclear power plants and associated facilities. With an aging workforce and a competitive tender process for each project a number of new companies are realising the potential of the UK decommissioning market. <strong>The</strong> Nuclear Engineering Doctorate and NTEC Masters Programmes have been designed to provide the nuclear workforce of the future. <strong>The</strong> doctorate is a partnership between industry, a university partner and the research engineer with the benefit to industry that the research engineer is based with the industrial partner. Technical and management modules are studied at the university whilst the research project is carried out in the industrial environment. <strong>The</strong> Masters programme draws on the expertise of 11 Higher Education Institutes and offers over 20 modules that are delivered in a short-fat format either as stand alone CPD courses or, by taking further modules, a certificate, diploma or on completion of a research project an M.Sc. Modules are available that cover the technical aspects of decommissioning as well as management of the decommissioning process. <strong>The</strong> availability of modules in a Distance Learning format now enables students based around the world to benefit from this programme. This paper will describe the two programmes in detail and provide examples of current projects that are delivering the research and workforce required for a successful decommissioning programme. 2) COLLABORATIVE RETEK EXCHANGE — AN INNOVATIVE SOLUTION TO THE SKILLS AND RESOURCE SHORTAGE IN THE NUCLEAR INDUSTRY - 16396 Corhyn Parr, Retek Consulting (UK) A Different Approach to the Skills and Resource Shortage. <strong>The</strong> Nuclear Industry has for many years been concerned about a skills and resource shortage. This has been due to a poor perception of the industry by those on the outside, highly competitive industries vying for the same resource pool, a steep retirement curve for highly qualified staff and a lack of graduates entering industry. Here in the UK the creation of the National Skill Academy for Nuclear (NSAN) has put in place a framework to record skills and look to accredit the training providers in the nuclear industry to ensure that the correct skills for the future are available. This has gone some way to solving the skills problem and developing a well recognised accredited system but what about resource where are the additional qualified resources going to be found? 64
Abstracts Session 9 3) SHARED, REGIONAL REPOSITORIES: DEVELOPING A PRACTICAL IMPLEMENTATION STRATEGY - 16310 Ewoud Verhoef, COVRA (Netherlands) Charles McCombie,Neil A. Chapman, Arius Association (Switzerland) <strong>The</strong> basic concept within both EC funded SAPIERR I and SAPIERR II projects (FP6) is that of one or more geological repositories developed in collaboration by two or more European countries to accept spent nuclear fuel, vitrified high-level waste and other long-lived radioactive waste from those partner countries. <strong>The</strong> SAPIERR II project (Strategic Action Plan for Implementation of Regional European Repositories) examines in detail issues that directly influence the practicability and acceptability of such facilities. This paper describes the work in the SAPIERR II project (2006-2008) on the development of a possible practical implementation strategy for shared, regional repositories in Europe and lays out the first steps in implementing that strategy. 4) UK SURPLUS SOURCE DISPOSAL PROGRAMME - 16097 Nigel Reeves, Gordon John, AMEC (UK) <strong>The</strong> UK Surplus Source Disposal Programme (SSDP), managed by the Environment Agency, was designed to remove redundant radioactive sources from the public domain. <strong>The</strong> UK Government Department for Environment, Food and Rural Affairs (Defra) was concerned that disused sources were being retained by hospitals, universities and businesses, posing a risk to public health and the environment. AMEC provided a range of technical and administrative services to support the SSDP. A questionnaire was issued to registered source holders and the submitted returns compiled to assess the scale of the project. A member of AMEC staff was seconded to the Environment Agency to provide technical support and liaise directly with source holders during funding applications, which would cover disposal costs. Funding for disposal of different sources was partially based on a sliding scale of risk as determined by the IAEA hazard categorisation system. This funding was also sector dependent. 5) GEOLOGICAL SITING REGIONS PROPOSED BY NAGRA FOR THE L/ILW AND THE HLW REPOSITORIES AS THE FIRST STEP IN THE APPLICATION OF THE RECENTLY ESTABLISHED SWISS SITE SELECTION PLAN - 16295 Jürg W. Schneider, Andreas Gautschi, Piet Zuidema, Nagra(Switzerland) In Switzerland, the Nuclear Energy Law requires the disposal of all radioactive waste in deep geological repositories. <strong>The</strong> Swiss programme foresees two types of repositories for this purpose: a low- and intermediate-level waste (L/ILW) and a high-level waste (HLW) repository. <strong>The</strong> necessary scientific and technical work preparing for deep geological disposal is well advanced and the feasibility of geological repositories that provide the required long-term safety has been successfully demonstrated for all waste types arising in Switzerland. <strong>The</strong>se feasibility demonstrations have been approved by the Swiss Government (the Federal Council). Sufficient knowledge is available to allow the next steps in the selection of repository sites to be defined. <strong>The</strong> legal framework is also in place and organisational measures have been provided that will allow the tasks to be performed in the coming years to be implemented efficiently. <strong>The</strong> concept part of the so-called Sectoral Plan Deep Geological Repositories (i.e. the rules for repository siting) that was issued by the Federal Council on 2nd April 2008 plays a major role, as it regulates the details of the site selection process to be conducted over the next years. <strong>The</strong> Sectoral Plan specifies that selection of geological siting regions and sites for repositories in Switzerland will be conducted in three stages. Stage 1 ends with the proposal of geological siting regions within which the repository projects will be elaborated in more detail in the later stages of the Sectoral Plan (stages 2 and 3); stage 3 will comprise field investigations (boreholes, 3D reflection seismic surveys). <strong>The</strong> final step will be the identification of a L/ILW and a HLW site for which general licences will be requested. 6) A SUMMARY OF RADIOLOGICAL WASTE DISPOSAL PRACTICES IN THE UNITED STATES AND THE UNITED KINGDOM - 16379 Victoria Maranville, AMEC Earth and Envorinmental (USA);Richard McGrath, AMEC Nuclear (UK) A systematic review of near-surface repositories for radioactive waste in the United States (US) was conducted. <strong>The</strong> main focus of the review consisted of a literature search of available documents and other published sources on low level radioactive waste (LLRW) disposal practices, remediation of LLRW sites in the US, and public participation for remediation efforts of near-surface radiological waste disposal sites in the US. This review was undertaken to provide background information in support of work by the UK’s Low Level Waste Repository (LLWR) and to aid in optimizing the future management of this site. <strong>The</strong> review contained a summary of the US and United Kingdom (UK) radiological waste classification requirements including a discussion of the waste types, disposal requirements, and the differences between US and UK disposal practices. A review of the regulatory process and evolution of regulatory requirements in the US is presented. <strong>The</strong> UK regulatory environment is also discussed and contrasted to the US process. <strong>The</strong> public participation, as part of the US regulatory process, is also provided and the mechanism for stakeholder identification and involvement is detailed. In an attempt to demonstrate how remediation of radiologically impacted sites is implemented in the US, existing US case studies, in which remediation activities were carried out, were reviewed. <strong>The</strong> following information was compiled: type of wastes disposed of to US shallow ground facilities [with comparison with UK classifications], facility designs (with special emphasis on those directly comparable to the subsurface conditions in the UK), and deficiencies identified in operation or in demonstrating safe post closure; and processes and difficulties in remedial actions encountered at the selected sites. Stakeholder involvement is also discussed within the case studies. Publicly available information related to radiological waste management and disposal practices were reviewed. Two sites are presented in this publication for discussion. <strong>The</strong>se US sites were selected based on the site similarities to conditions in the UK. 65
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FINAL PROGRAM ICEM’09/ DECOM’09
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Table of Contents ICEM’09/DECOM
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Transportation by Ferry to Liverpoo
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Convention Center — Cross Section
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