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Sample records for facilitate semi-autonomous decommissioning

  1. Advanced Sensing and Control Techniques to Facilitate Semi-Autonomous Decommissioning

    SciTech Connect

    Schalkoff, Robert J.

    1999-06-01

    This research is intended to advance the technology of semi-autonomous teleoperated robotics as applied to Decontamination and Decommissioning (D&D) tasks. Specifically, research leading to a prototype dual-manipulator mobile work cell is underway. This cell is supported and enhanced by computer vision, virtual reality and advanced robotics technology.

  2. Advanced sensing and control techniques to facilitate semi-autonomous decommissioning. 1998 annual progress report

    SciTech Connect

    Schalkoff, R.J.; Geist, R.M.; Dawson, D.M.

    1998-06-01

    'This research is intended to advance the technology of semi-autonomous teleoperated robotics as applied to Decontamination and Decommissioning (D and D) tasks. Specifically, research leading to a prototype dual-manipulator mobile work cell is underway. This cell is supported and enhanced by computer vision, virtual reality and advanced robotics technology. This report summarizes work after approximately 1.5 years of a 3-year project. The autonomous, non-contact creation of a virtual environment from an existing, real environment (virtualization) is an integral part of the workcell functionality. This requires that the virtual world be geometrically correct. To this end, the authors have encountered severe sensitivity in quadric estimation. As a result, alternative procedures for geometric rendering, iterative correction approaches, new calibration methods and associated hardware, and calibration quality examination software have been developed. Following geometric rendering, the authors have focused on improving the color and texture recognition components of the system. In particular, the authors have moved beyond first-order illumination modeling to include higher order diffuse effects. This allows us to combine the surface geometric information, obtained from the laser projection and surface recognition components of the system, with a stereo camera image. Low-level controllers for Puma 560 robotic arms were designed and implemented using QNX. The resulting QNX/PC based low-level robot control system is called QRobot. A high-level trajectory generator and application programming interface (API) as well as a new, flexible robot control API was required. Force/torque sensors and interface hardware have been identified and ordered. A simple 3-D OpenGL-based graphical Puma 560 robot simulator was developed and interfaced with ARCL and RCCL to assist in the development of robot motion programs.'

  3. Advanced Sensing and Control Techniques to Facilitate Semi-Autonomous Decommissioning of Hazardous Sites - Final Report

    SciTech Connect

    Schalkoff, R.J.

    2000-12-01

    This report summarizes work after 4 years of a 3-year project (no-cost extension of the above-referenced project for a period of 12 months granted). The fourth generation of a vision sensing head for geometric and photometric scene sensing has been built and tested. Estimation algorithms for automatic sensor calibration updating under robot motion have been developed and tested. We have modified the geometry extraction component of the rendering pipeline. Laser scanning now produces highly accurate points on segmented curves. These point-curves are input to a NURBS (non-uniform rational B-spline) skinning procedure to produce interpolating surface segments. The NURBS formulation includes quadrics as a sub-class, thus this formulation allows much greater flexibility without the attendant instability of generating an entire quadric surface. We have also implemented correction for diffuse lighting and specular effects. The QRobot joint level control was extended to a complete semi-autonomous robot control system for D and D operations. The imaging and VR subsystems have been integrated and tested.

  4. Semi autonomous mine detection system

    NASA Astrophysics Data System (ADS)

    Few, Doug; Versteeg, Roelof; Herman, Herman

    2010-04-01

    CMMAD is a risk reduction effort for the AMDS program. As part of CMMAD, multiple instances of semi autonomous robotic mine detection systems were created. Each instance consists of a robotic vehicle equipped with sensors required for navigation and marking, countermine sensors and a number of integrated software packages which provide for real time processing of the countermine sensor data as well as integrated control of the robotic vehicle, the sensor actuator and the sensor. These systems were used to investigate critical interest functions (CIF) related to countermine robotic systems. To address the autonomy CIF, the INL developed RIK was extended to allow for interaction with a mine sensor processing code (MSPC). In limited field testing this system performed well in detecting, marking and avoiding both AT and AP mines. Based on the results of the CMMAD investigation we conclude that autonomous robotic mine detection is feasible. In addition, CMMAD contributed critical technical advances with regard to sensing, data processing and sensor manipulation, which will advance the performance of future fieldable systems. As a result, no substantial technical barriers exist which preclude - from an autonomous robotic perspective - the rapid development and deployment of fieldable systems.

  5. Semi autonomous mine detection system

    SciTech Connect

    Douglas Few; Roelof Versteeg; Herman Herman

    2010-04-01

    CMMAD is a risk reduction effort for the AMDS program. As part of CMMAD, multiple instances of semi autonomous robotic mine detection systems were created. Each instance consists of a robotic vehicle equipped with sensors required for navigation and marking, a countermine sensors and a number of integrated software packages which provide for real time processing of the countermine sensor data as well as integrated control of the robotic vehicle, the sensor actuator and the sensor. These systems were used to investigate critical interest functions (CIF) related to countermine robotic systems. To address the autonomy CIF, the INL developed RIK was extended to allow for interaction with a mine sensor processing code (MSPC). In limited field testing this system performed well in detecting, marking and avoiding both AT and AP mines. Based on the results of the CMMAD investigation we conclude that autonomous robotic mine detection is feasible. In addition, CMMAD contributed critical technical advances with regard to sensing, data processing and sensor manipulation, which will advance the performance of future fieldable systems. As a result, no substantial technical barriers exist which preclude – from an autonomous robotic perspective – the rapid development and deployment of fieldable systems.

  6. Semi-Autonomous Vehicle Project

    NASA Technical Reports Server (NTRS)

    Stewart, Christopher

    2016-01-01

    The primary objective this summer is "evaluating standards for wireless architecture for the internet of things". The Internet of Things is the network of physical objects or "things" embedded with electronics, software, sensors and network connectivity which enables these objects to collect and exchange data and make decisions based on said data. This was accomplished by creating a semi-autonomous vehicle that takes advantage of multiple sensors, cameras, and onboard computers and combined them with a mesh network which enabled communication across large distances with little to no interruption. The mesh network took advantage of what is known as DTN - Disruption Tolerant Networking which according to NASA is the new communications protocol that is "the first step towards interplanetary internet." The use of DTN comes from the fact that it will store information if an interruption in communications is detected and even forward that information via other relays within range so that the data is not lost. This translates well into the project because as the car moves further away from whatever is sending it commands (in this case a joystick), the information can still be forwarded to the car with little to no loss of information thanks to the mesh nodes around the driving area.

  7. Identification and evaluation of facilitation techniques for decommissioning light water power reactors

    SciTech Connect

    LaGuardia, T.S.; Risley, J.F.

    1986-06-01

    This report describes a study sponsored by the US Nuclear Regulatory Commission to identify practical techniques to facilitate the decommissioning of nuclear power generating facilities. The objective of these ''facilitation techniques'' is to reduce the radioactive exposures and/or volumes of waste generated during the decommissioning process. The report presents the possible facilitation techniques identified during the study and discusses the corresponding facilitation of the decommissioning process. Techniques are categorized by their applicability of being implemented during the three stages of power reactor life: design/construction, operation, or decommissioning. Detailed cost-benefit analyses were performed for each technique to determine the anticipated exposure and/or radioactive waste reduction; the estimated costs for implementing each technique were then calculated. Finally, these techniques were ranked by their effectiveness in facilitating the decommissioning process. This study is a part of the Nuclear Regulatory Commission's evaluation of decommissioning policy and its modification of regulations pertaining to the decommissioning process. The findings can be used by the utilities in the planning and establishment of activities to ensure that all objectives of decommissioning will be achieved.

  8. Advanced sensing and control techniques to facilitate semi-autonomous decommissioning of hazardous sites. 1997 annual progress report, September 15, 1996--September 14, 1997

    SciTech Connect

    Schalkoff, R.J.

    1997-10-01

    'The first year of this effort emphasized independent development and refinement of each of the three major subsystems (imaging/AI, robotics and virtual reality). Two of the three efforts emphasized the critical task of site. virtualization, prior to telepresence-guided D and D. Substantial algorithm refinement and software and hardware development occurred in each area. Relevant publications resulting from this work are cited below.'

  9. Performance evaluation of 3D vision-based semi-autonomous control method for assistive robotic manipulator.

    PubMed

    Ka, Hyun W; Chung, Cheng-Shiu; Ding, Dan; James, Khara; Cooper, Rory

    2017-03-22

    We developed a 3D vision-based semi-autonomous control interface for assistive robotic manipulators. It was implemented based on one of the most popular commercially available assistive robotic manipulator combined with a low-cost depth-sensing camera mounted on the robot base. To perform a manipulation task with the 3D vision-based semi-autonomous control interface, a user starts operating with a manual control method available to him/her. When detecting objects within a set range, the control interface automatically stops the robot, and provides the user with possible manipulation options through audible text output, based on the detected object characteristics. Then, the system waits until the user states a voice command. Once the user command is given, the control interface drives the robot autonomously until the given command is completed. In the empirical evaluations conducted with human subjects from two different groups, it was shown that the semi-autonomous control can be used as an alternative control method to enable individuals with impaired motor control to more efficiently operate the robot arms by facilitating their fine motion control. The advantage of semi-autonomous control was not so obvious for the simple tasks. But, for the relatively complex real-life tasks, the 3D vision-based semi-autonomous control showed significantly faster performance. Implications for Rehabilitation A 3D vision-based semi-autonomous control interface will improve clinical practice by providing an alternative control method that is less demanding physically as well cognitively. A 3D vision-based semi-autonomous control provides the user with task specific intelligent semiautonomous manipulation assistances. A 3D vision-based semi-autonomous control gives the user the feeling that he or she is still in control at any moment. A 3D vision-based semi-autonomous control is compatible with different types of new and existing manual control methods for ARMs.

  10. Tele-assistance for semi-autonomous robots

    NASA Technical Reports Server (NTRS)

    Rogers, Erika; Murphy, Robin R.

    1994-01-01

    This paper describes a new approach in semi-autonomous mobile robots. In this approach the robot has sufficient computerized intelligence to function autonomously under a certain set of conditions, while the local system is a cooperative decision making unit that combines human and machine intelligence. Communication is then allowed to take place in a common mode and in a common language. A number of exception-handling scenarios that were constructed as a result of experiments with actual sensor data collected from two mobile robots were presented.

  11. Skills based evaluation of alternative input methods to command a semi-autonomous electric wheelchair.

    PubMed

    Rojas, Mario; Ponce, Pedro; Molina, Arturo

    2016-08-01

    This paper presents the evaluation, under standardized metrics, of alternative input methods to steer and maneuver a semi-autonomous electric wheelchair. The Human-Machine Interface (HMI), which includes a virtual joystick, head movements and speech recognition controls, was designed to facilitate mobility skills for severely disabled people. Thirteen tasks, which are common to all the wheelchair users, were attempted five times by controlling it with the virtual joystick and the hands-free interfaces in different areas for disabled and non-disabled people. Even though the prototype has an intelligent navigation control, based on fuzzy logic and ultrasonic sensors, the evaluation was done without assistance. The scored values showed that both controls, the head movements and the virtual joystick have similar capabilities, 92.3% and 100%, respectively. However, the 54.6% capacity score obtained for the speech control interface indicates the needs of the navigation assistance to accomplish some of the goals. Furthermore, the evaluation time indicates those skills which require more user's training with the interface and specifications to improve the total performance of the wheelchair.

  12. 77 FR 41107 - Decommissioning Planning During Operations

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-07-12

    ...; ] NUCLEAR REGULATORY COMMISSION 10 CFR Parts 20, 30, 40, 50, 70, and 72 Decommissioning Planning During... on revised draft regulatory guide (DG) 4014, ``Decommissioning Planning During Operations.'' This... Decommissioning Planning Rule. The NRC will hold a public meeting and concurrent Webinar to facilitate the...

  13. Decommissioning Handbook

    SciTech Connect

    Not Available

    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.

  14. Aladdin: a semi-autonomous door opening system for EOD-class robots

    NASA Astrophysics Data System (ADS)

    Craft, Jack; Wilson, Jack; Huang, Wesley H.; Claffee, Mark R.; Phillips, Emilie A.

    2011-05-01

    This paper describes our results to date on the Aladdin project, an ongoing effort to enable small UGVs to open doors semi-autonomously. Our system consists of a modular general-purpose gripper and software that provides semiautonomous capabilities. The gripper features compliant elements which simplify operations such as turning a doorknob and opening a door; this gripper can be retrofitted onto existing general-purpose robotic manipulators without extensive hardware modifications. The software provides semi-autonomous door opening capability through an OCU; these capabilities are focused on targeting and reaching for a doorknob, a subtask that our initial testing showed would provide the greatest improvement in door opening operations. This paper describes our system and the results of our evaluations on the door opening task. We continue to develop both the hardware and software with the ultimate goal of fully autonomous door-opening.

  15. Semi-autonomous Simulated Brain Tumor Ablation with RavenII Surgical Robot using Behavior Tree.

    PubMed

    Hu, Danying; Gong, Yuanzheng; Hannaford, Blake; Seibel, Eric J

    2015-05-01

    Medical robots have been widely used to assist surgeons to carry out dexterous surgical tasks via various ways. Most of the tasks require surgeon's operation directly or indirectly. Certain level of autonomy in robotic surgery could not only free the surgeon from some tedious repetitive tasks, but also utilize the advantages of robot: high dexterity and accuracy. This paper presents a semi-autonomous neurosurgical procedure of brain tumor ablation using RAVEN Surgical Robot and stereo visual feedback. By integrating with the behavior tree framework, the whole surgical task is modeled flexibly and intelligently as nodes and leaves of a behavior tree. This paper provides three contributions mainly: (1) describing the brain tumor ablation as an ideal candidate for autonomous robotic surgery, (2) modeling and implementing the semi-autonomous surgical task using behavior tree framework, and (3) designing an experimental simulated ablation task for feasibility study and robot performance analysis.

  16. Virtual Reality-based Telesurgery via Teleprogramming Scheme Combined with Semi-autonomous Control.

    PubMed

    Zhijiang, Du; Zhiheng, Jia; Minxiu, Kong

    2005-01-01

    Telesurgery systems have long been suffering variable and unpredictable Internet commutation time delay, operation fatigue, and other drawbacks. Based on virtual reality technology, a teleprogramming scheme combined with semi-autonomous control is introduced to guarantee the robustness and efficiency of teleoperation of HIT-RAOS, a robot-assisted orthopedic surgery system. In this system, without considering time delay, the operator can just interact with virtual environment which provides real-time 3D vision, stereophonic sound, and tactile and force feedback imitated by a parallel master manipulator. And several tasks can be managed simultaneously via semi-autonomous control. Finally, the method is experimentally demonstrated on an experiment of locking of intramedullary nails, and is shown to effectively provide stability and performances.

  17. Semi-autonomous Simulated Brain Tumor Ablation with RavenII Surgical Robot using Behavior Tree

    PubMed Central

    Hu, Danying; Gong, Yuanzheng; Hannaford, Blake; Seibel, Eric J.

    2015-01-01

    Medical robots have been widely used to assist surgeons to carry out dexterous surgical tasks via various ways. Most of the tasks require surgeon’s operation directly or indirectly. Certain level of autonomy in robotic surgery could not only free the surgeon from some tedious repetitive tasks, but also utilize the advantages of robot: high dexterity and accuracy. This paper presents a semi-autonomous neurosurgical procedure of brain tumor ablation using RAVEN Surgical Robot and stereo visual feedback. By integrating with the behavior tree framework, the whole surgical task is modeled flexibly and intelligently as nodes and leaves of a behavior tree. This paper provides three contributions mainly: (1) describing the brain tumor ablation as an ideal candidate for autonomous robotic surgery, (2) modeling and implementing the semi-autonomous surgical task using behavior tree framework, and (3) designing an experimental simulated ablation task for feasibility study and robot performance analysis. PMID:26405563

  18. Effectiveness and driver acceptance of a semi-autonomous forward obstacle collision avoidance system.

    PubMed

    Itoh, Makoto; Horikome, Tatsuya; Inagaki, Toshiyuki

    2013-09-01

    This paper proposes a semi-autonomous collision avoidance system for the prevention of collisions between vehicles and pedestrians and objects on a road. The system is designed to be compatible with the human-centered automation principle, i.e., the decision to perform a maneuver to avoid a collision is made by the driver. However, the system is partly autonomous in that it turns the steering wheel independently when the driver only applies the brake, indicating his or her intent to avoid the obstacle. With a medium-fidelity driving simulator, we conducted an experiment to investigate the effectiveness of this system for improving safety in emergency situations, as well as its acceptance by drivers. The results indicate that the system effectively improves safety in emergency situations, and the semi-autonomous characteristic of the system was found to be acceptable to drivers.

  19. Low-cost semi-autonomous manipulation technique for explosive ordnance disposal robots

    NASA Astrophysics Data System (ADS)

    Czop, Andrew; Del Signore, Michael J.; Hacker, Kurt

    2008-04-01

    Robotic manipulators used on current EOD robotic platforms exhibit very few autonomous capabilities. This lack of autonomy forces the operator to completely control manipulator movements. With the increasing complexity of robotic manipulators, this can prove to be a very complex and tedious task. The development of autonomous capabilities for platform navigation are currently being extensively researched and applied to EOD robots. While autonomous manipulation has also been researched, this technology has yet to appear in fielded EOD robotic systems. As a result, there is a need for the exploration and development of manipulator automation within the scope of EOD robotics. In addition, due to the expendable nature of EOD robotic assets, the addition of this technology needs to add little to the overall cost of the robotic system. To directly address the need for a low-cost semi-autonomous manipulation capability for EOD robots, the Naval Explosive Ordnance Disposal Technology Division (NAVEODTECHDIV) proposes the Autonomous Robotic Manipulator (ARM). The ARM incorporates several semi-autonomous manipulation behaviors including point-and-click movement, user-defined distance movement, user-defined angle positioning, memory locations to save and recall manipulator positions, and macros to memorize and repeat multi-position repetitive manipulator movements. These semi-autonomous behaviors will decrease an EOD operator's time on target by reducing the manipulation workload in a user-friendly fashion. This conference paper will detail the background of the project, design of the prototype, algorithm development, implementation, results, and future work.

  20. First experiences with semi-autonomous robotic harvesting of protein crystals.

    PubMed

    Viola, Robert; Walsh, Jace; Melka, Alex; Womack, Wesley; Murphy, Sean; Riboldi-Tunnicliffe, Alan; Rupp, Bernhard

    2011-07-01

    The demonstration unit of the Universal Micromanipulation Robot (UMR) capable of semi-autonomous protein crystal harvesting has been tested and evaluated by independent users. We report the status and capabilities of the present unit scheduled for deployment in a high-throughput protein crystallization center. We discuss operational aspects as well as novel features such as micro-crystal handling and drip-cryoprotection, and we extrapolate towards the design of a fully autonomous, integrated system capable of reliable crystal harvesting. The positive to enthusiastic feedback from the participants in an evaluation workshop indicates that genuine demand exists and the effort and resources to develop autonomous protein crystal harvesting robotics are justified.

  1. PointCom: semi-autonomous UGV control with intuitive interface

    NASA Astrophysics Data System (ADS)

    Rohde, Mitchell M.; Perlin, Victor E.; Iagnemma, Karl D.; Lupa, Robert M.; Rohde, Steven M.; Overholt, James; Fiorani, Graham

    2008-04-01

    Unmanned ground vehicles (UGVs) will play an important role in the nation's next-generation ground force. Advances in sensing, control, and computing have enabled a new generation of technologies that bridge the gap between manual UGV teleoperation and full autonomy. In this paper, we present current research on a unique command and control system for UGVs named PointCom (Point-and-Go Command). PointCom is a semi-autonomous command system for one or multiple UGVs. The system, when complete, will be easy to operate and will enable significant reduction in operator workload by utilizing an intuitive image-based control framework for UGV navigation and allowing a single operator to command multiple UGVs. The project leverages new image processing algorithms for monocular visual servoing and odometry to yield a unique, high-performance fused navigation system. Human Computer Interface (HCI) techniques from the entertainment software industry are being used to develop video-game style interfaces that require little training and build upon the navigation capabilities. By combining an advanced navigation system with an intuitive interface, a semi-autonomous control and navigation system is being created that is robust, user friendly, and less burdensome than many current generation systems. mand).

  2. Decommissioning handbook

    SciTech Connect

    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.

  3. Demonstration of a Spoken Dialogue Interface for Planning Activities of a Semi-autonomous Robot

    NASA Technical Reports Server (NTRS)

    Dowding, John; Frank, Jeremy; Hockey, Beth Ann; Jonsson, Ari; Aist, Gregory

    2002-01-01

    Planning and scheduling in the face of uncertainty and change pushes the capabilities of both planning and dialogue technologies by requiring complex negotiation to arrive at a workable plan. Planning for use of semi-autonomous robots involves negotiation among multiple participants with competing scientific and engineering goals to co-construct a complex plan. In NASA applications this plan construction is done under severe time pressure so having a dialogue interface to the plan construction tools can aid rapid completion of the process. But, this will put significant demands on spoken dialogue technology, particularly in the areas of dialogue management and generation. The dialogue interface will need to be able to handle the complex dialogue strategies that occur in negotiation dialogues, including hypotheticals and revisions, and the generation component will require an ability to summarize complex plans. This demonstration will describe a work in progress towards building a spoken dialogue interface to the EUROPA planner for the purposes of planning and scheduling the activities of a semi-autonomous robot. A prototype interface has been built for planning the schedule of the Personal Satellite Assistant (PSA), a mobile robot designed for micro-gravity environments that is intended for use on the Space Shuttle and International Space Station. The spoken dialogue interface gives the user the capability to ask for a description of the plan, ask specific questions about the plan, and update or modify the plan. We anticipate that a spoken dialogue interface to the planner will provide a natural augmentation or alternative to the visualization interface, in situations in which the user needs very targeted information about the plan, in situations where natural language can express complex ideas more concisely than GUI actions, or in situations in which a graphical user interface is not appropriate.

  4. INTERNATIONAL DECOMMISSIONING SYMPOSIUM 2000

    SciTech Connect

    M.A. Ebadian, Ph.D.

    2001-01-01

    The purpose of IDS 2000 was to deliver a world-class conference on applicable global environmental issues. The objective of this conference was to publicize environmental progress of individual countries, to provide a forum for technology developer and problem-holder interaction, to facilitate environmental and technology discussions between the commercial and financial communities, and to accommodate information and education exchange between governments, industries, universities, and scientists. The scope of this project included the planning and execution of an international conference on the decommissioning of nuclear facilities, and the providing of a business forum for vendors and participants sufficient to attract service providers, technology developers, and the business and financial communities. These groups, when working together with attendees from regulatory organizations and government decision-maker groups, provide an opportunity to more effectively and efficiently expedite the decommissioning projects.

  5. Development and Characteristics of a Mobile, Semi-Autonomous Floating Platform for in situ Lake Measurements

    NASA Astrophysics Data System (ADS)

    Barry, D.; Lemmin, U.; Le Dantec, N.; Zulliger, L.; Rusterholz, M.; Bolay, M.; Rossier, J.; Kangur, K.

    2013-12-01

    In the development of sustainable management strategies of lakes more insight into their physical, chemical and ecological dynamics is needed. Field data obtained from various types of sensors with adequate spatial and temporal sampling rate are essential to understand better the processes that govern fluxes and pathways of water masses and transported compounds, whether for model validation or for monitoring purposes. One advantage of unmanned platforms is that they limit the disturbances typically affecting the quality of data collected on small vessels, including perturbations caused by movements of onboard crew. We have developed a mobile, semi-autonomous floating platform with 8 h power autonomy using a 5 m long by 2.5 m wide catamaran. Our approach focused on modularity and high payload capacity in order to accommodate a large number of sensors both in terms of electronic (power and data) and mechanical constraints of integration. Software architecture and onboard electronics use National Instruments technology to simplify and standardize integration of sensors, actuators and communication. Piecewise-movable deck sections allow optimizing platform stability depending on the payload. The entire system is controlled by a remote computer located on an accompanying vessel and connected via a wireless link with a range of over 1 km. Real-time transmission of GPS-stamped measurements allows immediate modifications in the survey plan if needed. The displacement of the platform is semi-autonomous, with the options of either autopilot mode following a pre-planned course specified by waypoints or remote manual control from the accompanying vessel. Maintenance of permanent control over the platform displacement is required for safety reasons with respect to other users of the lake. Currently, the sensor payload comprises an array of fast temperature probes, a bottom-tracking ADCP and atmospheric sensors including a radiometer. A towed CTD with additional water quality

  6. Summary of comments received at workshop on use of a Site Specific Advisory Board (SSAB) to facilitate public participation in decommissioning cases

    SciTech Connect

    Caplin, J.; Padge, G.; Smith, D.; Wiblin, C.

    1995-06-01

    The Nuclear Regulatory Commission (NRC) is conducting an enhanced participatory rulemaking to establish radiological criteria for the decommissioning of NRC-licensed facilities. As part of this rulemaking, On August 20, 1994 the NRC published a proposed rule for public comment. Paragraph 20.1406(b) of the proposed rule would require that the licensee convene a Site Specific Advisory Board (SSAB) if the licensee proposed release of the site for restricted use after decommissioning. To encourage comment the NRC held a workshop on the subject of $SABs on December 6, 7, and 8, 1994. This report summarizes the 567 comments categorized from the transcript of the workshop. The commenters at the workshop generally supported public participation in decommissioning cases. Many participants favored promulgating requirements in the NRC`s rules. Some industry participants favored relying on voluntary exchanges between the public and the licensees. Many participants indicated that a SSAB or something functionally equivalent is needed in controversial decommissioning cases, but that some lesser undertaking can achieve meaningful public participation in other cases. No analysis or response to the comments is included in this report.

  7. Adaptive Kalman snake for semi-autonomous 3D vessel tracking.

    PubMed

    Lee, Sang-Hoon; Lee, Sanghoon

    2015-10-01

    In this paper, we propose a robust semi-autonomous algorithm for 3D vessel segmentation and tracking based on an active contour model and a Kalman filter. For each computed tomography angiography (CTA) slice, we use the active contour model to segment the vessel boundary and the Kalman filter to track position and shape variations of the vessel boundary between slices. For successful segmentation via active contour, we select an adequate number of initial points from the contour of the first slice. The points are set manually by user input for the first slice. For the remaining slices, the initial contour position is estimated autonomously based on segmentation results of the previous slice. To obtain refined segmentation results, an adaptive control spacing algorithm is introduced into the active contour model. Moreover, a block search-based initial contour estimation procedure is proposed to ensure that the initial contour of each slice can be near the vessel boundary. Experiments were performed on synthetic and real chest CTA images. Compared with the well-known Chan-Vese (CV) model, the proposed algorithm exhibited better performance in segmentation and tracking. In particular, receiver operating characteristic analysis on the synthetic and real CTA images demonstrated the time efficiency and tracking robustness of the proposed model. In terms of computational time redundancy, processing time can be effectively reduced by approximately 20%.

  8. Use of Semi-Autonomous Tools for ISS Commanding and Monitoring

    NASA Technical Reports Server (NTRS)

    Brzezinski, Amy S.

    2014-01-01

    As the International Space Station (ISS) has moved into a utilization phase, operations have shifted to become more ground-based with fewer mission control personnel monitoring and commanding multiple ISS systems. This shift to fewer people monitoring more systems has prompted use of semi-autonomous console tools in the ISS Mission Control Center (MCC) to help flight controllers command and monitor the ISS. These console tools perform routine operational procedures while keeping the human operator "in the loop" to monitor and intervene when off-nominal events arise. Two such tools, the Pre-positioned Load (PPL) Loader and Automatic Operators Recorder Manager (AutoORM), are used by the ISS Communications RF Onboard Networks Utilization Specialist (CRONUS) flight control position. CRONUS is responsible for simultaneously commanding and monitoring the ISS Command & Data Handling (C&DH) and Communications and Tracking (C&T) systems. PPL Loader is used to uplink small pieces of frequently changed software data tables, called PPLs, to ISS computers to support different ISS operations. In order to uplink a PPL, a data load command must be built that contains multiple user-input fields. Next, a multiple step commanding and verification procedure must be performed to enable an onboard computer for software uplink, uplink the PPL, verify the PPL has incorporated correctly, and disable the computer for software uplink. PPL Loader provides different levels of automation in both building and uplinking these commands. In its manual mode, PPL Loader automatically builds the PPL data load commands but allows the flight controller to verify and save the commands for future uplink. In its auto mode, PPL Loader automatically builds the PPL data load commands for flight controller verification, but automatically performs the PPL uplink procedure by sending commands and performing verification checks while notifying CRONUS of procedure step completion. If an off-nominal condition

  9. Development of a semi-autonomous service robot with telerobotic capabilities

    NASA Technical Reports Server (NTRS)

    Jones, J. E.; White, D. R.

    1987-01-01

    The importance to the United States of semi-autonomous systems for application to a large number of manufacturing and service processes is very clear. Two principal reasons emerge as the primary driving forces for development of such systems: enhanced national productivity and operation in environments whch are hazardous to humans. Completely autonomous systems may not currently be economically feasible. However, autonomous systems that operate in a limited operation domain or that are supervised by humans are within the technology capability of this decade and will likely provide reasonable return on investment. The two research and development efforts of autonomy and telerobotics are distinctly different, yet interconnected. The first addresses the communication of an intelligent electronic system with a robot while the second requires human communication and ergonomic consideration. Discussed here are work in robotic control, human/robot team implementation, expert system robot operation, and sensor development by the American Welding Institute, MTS Systems Corporation, and the Colorado School of Mines--Center for Welding Research.

  10. Semi-autonomous surgical tasks using a miniature in vivo surgical robot.

    PubMed

    Dumpert, Jason; Lehman, Amy C; Wood, Nathan A; Oleynikov, Dmitry; Farritor, Shane M

    2009-01-01

    Natural Orifice Translumenal Endoscopic Surgery (NOTES) is potentially the next step in minimally invasive surgery. This type of procedure could reduce patient trauma through eliminating external incisions, but poses many surgical challenges that are not sufficiently overcome with current flexible endoscopy tools. A robotic platform that attempts to emulate a laparoscopic interface for performing NOTES procedures is being developed to address these challenges. These robots are capable of entering the peritoneal cavity through the upper gastrointestinal tract, and once inserted are not constrained by incisions, allowing for visualization and manipulations throughout the cavity. In addition to using these miniature in vivo robots for NOTES procedures, these devices can also be used to perform semi-autonomous surgical tasks. Such tasks could be useful in situations where the patient is in a location far from a trained surgeon. A surgeon at a remote location could control the robot even if the communication link between surgeon and patient has low bandwidth or very high latency. This paper details work towards using the miniature robot to perform simple surgical tasks autonomously.

  11. A learning-based semi-autonomous controller for robotic exploration of unknown disaster scenes while searching for victims.

    PubMed

    Doroodgar, Barzin; Liu, Yugang; Nejat, Goldie

    2014-12-01

    Semi-autonomous control schemes can address the limitations of both teleoperation and fully autonomous robotic control of rescue robots in disaster environments by allowing a human operator to cooperate and share such tasks with a rescue robot as navigation, exploration, and victim identification. In this paper, we present a unique hierarchical reinforcement learning-based semi-autonomous control architecture for rescue robots operating in cluttered and unknown urban search and rescue (USAR) environments. The aim of the controller is to enable a rescue robot to continuously learn from its own experiences in an environment in order to improve its overall performance in exploration of unknown disaster scenes. A direction-based exploration technique is integrated in the controller to expand the search area of the robot via the classification of regions and the rubble piles within these regions. Both simulations and physical experiments in USAR-like environments verify the robustness of the proposed HRL-based semi-autonomous controller to unknown cluttered scenes with different sizes and varying types of configurations.

  12. Decontamination & decommissioning focus area

    SciTech Connect

    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.

  13. NMSS handbook for decommissioning fuel cycle and materials licensees

    SciTech Connect

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

    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.

  14. 76 FR 35511 - Decommissioning Planning

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-06-17

    ... Regulatory Commission (NRC or the Commission) is amending its regulations to improve decommissioning planning... financial assurance requirements. The amended regulations require decommissioning power reactor licensees to... with respect to permanently shutdown reactor decommissioning fund status and spent fuel management...

  15. Decommissioning at AWE

    SciTech Connect

    Biles, K.; Hedges, M.; Campbell, C

    2008-07-01

    AWE (A) has been at the heart of the UK Nuclear deterrent since it was established in the early 1950's. It is a nuclear licensed site and is governed by the United Kingdoms Nuclear Installation Inspectorate (NII). AWE plc on behalf of the Ministry of Defence (MOD) manages the AWE (A) site and all undertakings including decommissioning. Therefore under NII license condition 35 'Decommissioning', AWE plc is accountable to make and implement adequate arrangements for the decommissioning of any plant or process, which may affect safety. The majority of decommissioning projects currently being undertaken are to do with Hazard category 3, 4 or 5 facilities, systems or plant that have reached the end of their operational span and have undergone Post-Operational Clean-Out (POCO). They were either built for the production of fissile components, for supporting the early reactor fuels programmes or for processing facility waste arisings. They either contain redundant contaminated gloveboxes associated process areas, process plant or systems or a combination of all. In parallel with decommissioning project AWE (A) are undertaking investigation into new technologies to aid decommissioning projects; to remove the operative from hands on operations; to develop and implement modifications to existing process and techniques used. AWE (A) is currently going thorough a sustained phase of upgrading its facilities to enhance its scientific capability, with older facilities, systems and plant being replaced, making decommissioning a growth area. It is therefore important to the company to reduce these hazards progressively and safety over the coming years, making decommissioning an important feature of the overall legacy management aspects of AWE PLC's business. This paper outlines the current undertakings and progress of Nuclear decommissioning on the AWE (A) site. (authors)

  16. Adaptive Control of Semi-Autonomous Teleoperation System With Asymmetric Time-Varying Delays and Input Uncertainties.

    PubMed

    Zhai, Di-Hua; Xia, Yuanqing

    2016-06-07

    This paper addresses the adaptive task-space bilateral teleoperation for heterogeneous master and slave robots to guarantee stability and tracking performance, where a novel semi-autonomous teleoperation framework is developed to ensure the safety and enhance the efficiency of the robot in remote site. The basic idea is to stabilize the tracking error in task space while enhancing the efficiency of complex teleoperation by using redundant slave robot with subtask control. To unify the study of the asymmetric time-varying delays, passive/nonpassive exogenous forces, dynamic parameter uncertainties and dead-zone input in the same framework, a novel switching technique-based adaptive control scheme is investigated, where a special switched error filter is developed. By replacing the derivatives of position errors with their filtered outputs in the coordinate torque design, and employing the multiple Lyapunov-Krasovskii functionals method, the complete closed-loop master (slave) system is proven to be state-independent input-to-output stable. It is shown that both the position tracking errors in task space and the adaptive parameter estimation errors remain bounded for any bounded exogenous forces. Moreover, by using the redundancy of the slave robot, the proposed teleoperation framework can autonomously achieve additional subtasks in the remote environment. Finally, the obtained results are demonstrated by the simulation.

  17. A review of decommissioning considerations for new reactors

    SciTech Connect

    Devgun, J.S.Ph.D.

    2008-07-01

    At a time of 'nuclear renaissance' when the focus is on advanced reactor designs and construction, it is easy to overlook the decommissioning considerations because such a stage in the life of the new reactors will be some sixty years down the road. Yet, one of the lessons learned from major decommissioning projects has been that decommissioning was not given much thought when these reactors were designed three or four decades ago. Hence, the time to examine what decommissioning considerations should be taken into account is right from the design stage with regular updates of the decommissioning strategy and plans throughout the life cycle of the reactor. Designing D and D into the new reactor designs is necessary to ensure that the tail end costs of the nuclear power are manageable. Such considerations during the design stage will facilitate a more cost-effective, safe and timely decommissioning of the facility when a reactor is eventually retired. This paper examines the current regulatory and industry design guidance for the new reactors with respect to the decommissioning issues and provides a review of the design considerations that can help optimize the reactor designs for the eventual decommissioning. (authors)

  18. Estimating decommissioning costs: The 1994 YNPS decommissioning cost study

    SciTech Connect

    Szymczak, W.J.

    1994-12-31

    Early this year, Yankee Atomic Electric Company began developing a revised decommissioning cost estimate for the Yankee Nuclear Power Station (YNPS) to provide a basis for detailed decommissioning planning and to reflect slow progress in siting low-level waste (LLW) and spent-nuclear-fuel disposal facilities. The revision also reflects the need to change from a cost estimate that focuses on overall costs to a cost estimate that is sufficiently detailed to implement decommissioning and identify the final cost of decommissioning.

  19. Factors Impacting Decommissioning Costs - 13576

    SciTech Connect

    Kim, Karen; McGrath, Richard

    2013-07-01

    The Electric Power Research Institute (EPRI) studied United States experience with decommissioning cost estimates and the factors that impact the actual cost of decommissioning projects. This study gathered available estimated and actual decommissioning costs from eight nuclear power plants in the United States to understand the major components of decommissioning costs. Major costs categories for decommissioning a nuclear power plant are removal costs, radioactive waste costs, staffing costs, and other costs. The technical factors that impact the costs were analyzed based on the plants' decommissioning experiences. Detailed cost breakdowns by major projects and other cost categories from actual power plant decommissioning experiences will be presented. Such information will be useful in planning future decommissioning and designing new plants. (authors)

  20. Site decommissioning management plan

    SciTech Connect

    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.

  1. 10 CFR 72.30 - Financial assurance and recordkeeping for decommissioning.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... the decontamination and decommissioning of the ISFSI or MRS at the end of its useful life will provide... design features of the ISFSI or MRS that facilitate its decontamination and decommissioning at the end of... plan containing information on how reasonable assurance will be provided that funds will be...

  2. ORNL decontamination and decommissioning program

    SciTech Connect

    Bell, J. P.

    1980-01-01

    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.

  3. Effects of automation and task load on task switching during human supervision of multiple semi-autonomous robots in a dynamic environment.

    PubMed

    Squire, P N; Parasuraman, R

    2010-08-01

    The present study assessed the impact of task load and level of automation (LOA) on task switching in participants supervising a team of four or eight semi-autonomous robots in a simulated 'capture the flag' game. Participants were faster to perform the same task than when they chose to switch between different task actions. They also took longer to switch between different tasks when supervising the robots at a high compared to a low LOA. Task load, as manipulated by the number of robots to be supervised, did not influence switch costs. The results suggest that the design of future unmanned vehicle (UV) systems should take into account not simply how many UVs an operator can supervise, but also the impact of LOA and task operations on task switching during supervision of multiple UVs. The findings of this study are relevant for the ergonomics practice of UV systems. This research extends the cognitive theory of task switching to inform the design of UV systems and results show that switching between UVs is an important factor to consider.

  4. Demonstration of a semi-autonomous hybrid brain-machine interface using human intracranial EEG, eye tracking, and computer vision to control a robotic upper limb prosthetic.

    PubMed

    McMullen, David P; Hotson, Guy; Katyal, Kapil D; Wester, Brock A; Fifer, Matthew S; McGee, Timothy G; Harris, Andrew; Johannes, Matthew S; Vogelstein, R Jacob; Ravitz, Alan D; Anderson, William S; Thakor, Nitish V; Crone, Nathan E

    2014-07-01

    To increase the ability of brain-machine interfaces (BMIs) to control advanced prostheses such as the modular prosthetic limb (MPL), we are developing a novel system: the Hybrid Augmented Reality Multimodal Operation Neural Integration Environment (HARMONIE). This system utilizes hybrid input, supervisory control, and intelligent robotics to allow users to identify an object (via eye tracking and computer vision) and initiate (via brain-control) a semi-autonomous reach-grasp-and-drop of the object by the MPL. Sequential iterations of HARMONIE were tested in two pilot subjects implanted with electrocorticographic (ECoG) and depth electrodes within motor areas. The subjects performed the complex task in 71.4% (20/28) and 67.7% (21/31) of trials after minimal training. Balanced accuracy for detecting movements was 91.1% and 92.9%, significantly greater than chance accuracies (p < 0.05). After BMI-based initiation, the MPL completed the entire task 100% (one object) and 70% (three objects) of the time. The MPL took approximately 12.2 s for task completion after system improvements implemented for the second subject. Our hybrid-BMI design prevented all but one baseline false positive from initiating the system. The novel approach demonstrated in this proof-of-principle study, using hybrid input, supervisory control, and intelligent robotics, addresses limitations of current BMIs.

  5. Real-time performance of a hands-free semi-autonomous wheelchair system using a combination of stereoscopic and spherical vision.

    PubMed

    Nguyen, Jordan S; Nguyen, Tuan Nghia; Tran, Yvonne; Su, Steven W; Craig, Ashley; Nguyen, Hung T

    2012-01-01

    This paper is concerned with the operational performance of a semi-autonomous wheelchair system named TIM (Thought-controlled Intelligent Machine), which uses cameras in a system configuration modeled on the vision system of a horse. This new camera configuration utilizes stereoscopic vision for 3-Dimensional (3D) depth perception and mapping ahead of the wheelchair, combined with a spherical camera system for 360-degrees of monocular vision. The unique combination allows for static components of an unknown environment to be mapped and any surrounding dynamic obstacles to be detected, during real-time autonomous navigation, minimizing blind-spots and preventing accidental collisions with people or obstacles. Combining this vision system with a shared control strategy provides intelligent assistive guidance during wheelchair navigation, and can accompany any hands-free wheelchair control technology for people with severe physical disability. Testing of this system in crowded dynamic environments has displayed the feasibility and real-time performance of this system when assisting hands-free control technologies, in this case being a proof-of-concept brain-computer interface (BCI).

  6. Demonstration of a Semi-Autonomous Hybrid Brain-Machine Interface using Human Intracranial EEG, Eye Tracking, and Computer Vision to Control a Robotic Upper Limb Prosthetic

    PubMed Central

    McMullen, David P.; Hotson, Guy; Katyal, Kapil D.; Wester, Brock A.; Fifer, Matthew S.; McGee, Timothy G.; Harris, Andrew; Johannes, Matthew S.; Vogelstein, R. Jacob; Ravitz, Alan D.; Anderson, William S.; Thakor, Nitish V.; Crone, Nathan E.

    2014-01-01

    To increase the ability of brain-machine interfaces (BMIs) to control advanced prostheses such as the modular prosthetic limb (MPL), we are developing a novel system: the Hybrid Augmented Reality Multimodal Operation Neural Integration Environment (HARMONIE). This system utilizes hybrid input, supervisory control, and intelligent robotics to allow users to identify an object (via eye tracking and computer vision) and initiate (via brain-control) a semi-autonomous reach-grasp-and-drop of the object by the MPL. Sequential iterations of HARMONIE were tested in two pilot subjects implanted with electrocorticographic (ECoG) and depth electrodes within motor areas. The subjects performed the complex task in 71.4% (20/28) and 67.7% (21/31) of trials after minimal training. Balanced accuracy for detecting movements was 91.1% and 92.9%, significantly greater than chance accuracies (p < 0.05). After BMI-based initiation, the MPL completed the entire task 100% (one object) and 70% (three objects) of the time. The MPL took approximately 12.2 seconds for task completion after system improvements implemented for the second subject. Our hybrid-BMI design prevented all but one baseline false positive from initiating the system. The novel approach demonstrated in this proof-of-principle study, using hybrid input, supervisory control, and intelligent robotics, addresses limitations of current BMIs. PMID:24760914

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

    SciTech Connect

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

    1987-09-01

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

  8. DASAO: software tool for the management of safeguards, waste and decommissioning

    SciTech Connect

    Noynaert, Luc; Verwaest, Isi; Libon, Henri; Cuchet, Jean-Marie

    2013-07-01

    Decommissioning of nuclear facilities is a complex process involving operations such as detailed surveys, decontamination and dismantling of equipment's, demolition of buildings and management of resulting waste and nuclear materials if any. This process takes place in a well-developed legal framework and is controlled and followed-up by stakeholders like the Safety Authority, the Radwaste management Agency and the Safeguards Organism. In the framework of its nuclear waste and decommissioning program and more specifically the decommissioning of the BR3 reactor, SCK-CEN has developed different software tools to secure the waste and material traceability, to support the sound management of the decommissioning project and to facilitate the control and the follow-up by the stakeholders. In the case of Belgium, it concerns the Federal Agency for Nuclear Control, the National Agency for radioactive waste management and fissile material and EURATOM and IAEA. In 2005, Belgonucleaire decided to shutdown her Dessel MOX fuel fabrication plant and the production stopped in 2006. According to the final decommissioning plan ('PDF') approved by NIRAS, the decommissioning works should start in 2008 at the earliest. In 2006, the management of Belgonucleaire identified the need for an integrated database and decided to entrust SCK-CEN with its development, because SCK-CEN relies on previous experience in comparable applications namely already approved by authorities such as NIRAS, FANC and EURATOM. The main objectives of this integrated software tool are: - simplified and updated safeguards; - waste and material traceability; - computerized documentation; - support to project management; - periodic and final reporting to waste and safety authorities. The software called DASAO (Database for Safeguards, Waste and Decommissioning) was successfully commissioned in 2008 and extensively used from 2009 to the satisfaction of Belgonucleaire and the stakeholders. SCK-CEN is now implementing

  9. Waste minimization value engineering workshop for the Los Alamos National Laboratory Omega West Reactor Decommissioning Project

    SciTech Connect

    Hartnett, S.; Seguin, N.; Burns, M.

    1995-12-31

    The Los Alamos National Laboratory Pollution Prevention Program Office sponsored a Value Engineering (VE) Workshop to evaluate recycling options and other pollution prevention and waste minimization (PP/WMin) practices to incorporate into the decommissioning of the Omega West Reactor (OWR) at the laboratory. The VE process is an organized, systematic approach for evaluating a process or design to identify cost saving opportunities, or in this application, waste reduction opportunities. This VE Workshop was a facilitated process that included a team of specialists in the areas of decontamination, decommissioning, PP/WMin, cost estimating, construction, waste management, recycling, Department of Energy representatives, and others. The uniqueness of this VE Workshop was that it used an interdisciplinary approach to focus on PP/WMin practices that could be included in the OWR Decommissioning Project Plans and specifications to provide waste reduction. This report discusses the VE workshop objectives, summarizes the OWR decommissioning project, and describes the VE workshop activities, results, and lessons learned.

  10. 76 FR 3837 - Nuclear Decommissioning Funds; Correction

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-01-21

    ... Internal Revenue Service 26 CFR Part 1 RIN 1545-BF08 Nuclear Decommissioning Funds; Correction AGENCY... decommissioning nuclear power plants. DATES: This correction is effective on January 21, 2011, and is applicable... interest in a nuclear power plant. * * * * * (e) * * * (3) * * * Example 2. * * * Pursuant to paragraph...

  11. STANDARD OPERATING PROTOCOLS FOR DECOMMISSIONING

    SciTech Connect

    Foss, D. L.; Stevens, J. L.; Gerdeman, F. W.

    2002-02-25

    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.

  12. Rancho Seco--Decommissioning Update

    SciTech Connect

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

    2003-02-26

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

  13. Lessons Learned from the Decommissioning of Nuclear Facilities and the Safe Termination of Nuclear Activities. Outcomes of the International Conference, 11-15 December 2006, Athens, Greece

    SciTech Connect

    Batandjieva, B.; Laraia, M.

    2008-01-15

    Full text of publication follows: decommissioning activities are increasing worldwide covering wide range of facilities - from nuclear power plant, through fuel cycle facilities to small laboratories. The importance of these activities is growing with the recognition of the need for ensuring safe termination of practices and reuse of sites for various purposes, including the development of new nuclear facilities. Decommissioning has been undertaken for more than forty years and significant knowledge has been accumulated and lessons have been learned. However the number of countries encountering decommissioning for the first time is increasing with the end of the lifetime of the facilities around the world, in particular in countries with small nuclear programmes (e.g. one research reactor) and limited human and financial resources. In order to facilitate the exchange of lessons learned and good practices between all Member States and to facilitate and improve safety of the planned, ongoing and future decommissioning projects, the IAEA in cooperation with the Nuclear Energy Agency to OECD, European Commission and World Nuclear Association organised the international conference on Lessons Learned from the Decommissioning of Nuclear Facilities and the Safe Termination of Nuclear Activities, held in Athens, Greece. The conference also highlighted areas where future cooperation at national and international level is required in order to improve decommissioning planning and safety during decommissioning and to facilitate decommissioning by selecting appropriate strategies and technologies for decontamination, dismantling and management of waste. These and other aspects discussed at the conference are presented in this paper, together with the planned IAEA measures for amendment and implementation of the International Action Plan on Decommissioning of Nuclear Facilities and its future programme on decommissioning.

  14. Pipeline Decommissioning Trial AWE Berkshire UK - 13619

    SciTech Connect

    Agnew, Kieran

    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; - Hot tapping - a method

  15. Modelling of nuclear power plant decommissioning financing.

    PubMed

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

    2015-06-01

    Costs related to the decommissioning of nuclear power plants create a significant financial burden for nuclear power plant operators. This article discusses the various methodologies employed by selected European countries for financing of the liabilities related to the nuclear power plant decommissioning. The article also presents methodology of allocation of future decommissioning costs to the running costs of nuclear power plant in the form of fee imposed on each megawatt hour generated. The application of the methodology is presented in the form of a case study on a new nuclear power plant with installed capacity 1000 MW.

  16. Sellafield Decommissioning Programme - Update and Lessons Learned

    SciTech Connect

    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.

  17. Russian nuclear-powered submarine decommissioning

    SciTech Connect

    Bukharin, O.; Handler, J.

    1995-11-01

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

  18. 77 FR 14047 - Guidance for Decommissioning Planning During Operations

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-03-08

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Guidance for Decommissioning Planning During Operations AGENCY: Nuclear Regulatory Commission... public comment period for Draft Regulatory Guide (DG)-4014, ``Decommissioning Planning During...

  19. Decommissioning and dismantling strategies in the Federal Republic of Germany

    SciTech Connect

    Brennecke, P.; Berg, H.P.; Weil, L.

    1993-12-31

    This report discusses the following aspects of decommissioning and dismantling strategies in the federal republic of germany: legal requirements, nuclear installations to be decommissioned, reactor dismantling techniques, and radioactive waste management.

  20. 26 CFR 1.88-1 - Nuclear decommissioning costs.

    Code of Federal Regulations, 2010 CFR

    2010-04-01

    ... 26 Internal Revenue 2 2010-04-01 2010-04-01 false Nuclear decommissioning costs. 1.88-1 Section 1... (CONTINUED) INCOME TAXES (CONTINUED) Items Specifically Included in Gross Income § 1.88-1 Nuclear decommissioning costs. (a) In general. Section 88 provides that the amount of nuclear decommissioning...

  1. 78 FR 64028 - Decommissioning of Nuclear Power Reactors

    Federal Register 2010, 2011, 2012, 2013, 2014

    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...

  2. 26 CFR 1.88-1 - Nuclear decommissioning costs.

    Code of Federal Regulations, 2014 CFR

    2014-04-01

    ... 26 Internal Revenue 2 2014-04-01 2014-04-01 false Nuclear decommissioning costs. 1.88-1 Section 1... (CONTINUED) INCOME TAXES (CONTINUED) Items Specifically Included in Gross Income § 1.88-1 Nuclear decommissioning costs. (a) In general. Section 88 provides that the amount of nuclear decommissioning...

  3. 26 CFR 1.88-1 - Nuclear decommissioning costs.

    Code of Federal Regulations, 2011 CFR

    2011-04-01

    ... 26 Internal Revenue 2 2011-04-01 2011-04-01 false Nuclear decommissioning costs. 1.88-1 Section 1... (CONTINUED) INCOME TAXES (CONTINUED) Items Specifically Included in Gross Income § 1.88-1 Nuclear decommissioning costs. (a) In general. Section 88 provides that the amount of nuclear decommissioning...

  4. 26 CFR 1.88-1 - Nuclear decommissioning costs.

    Code of Federal Regulations, 2012 CFR

    2012-04-01

    ... 26 Internal Revenue 2 2012-04-01 2012-04-01 false Nuclear decommissioning costs. 1.88-1 Section 1... (CONTINUED) INCOME TAXES (CONTINUED) Items Specifically Included in Gross Income § 1.88-1 Nuclear decommissioning costs. (a) In general. Section 88 provides that the amount of nuclear decommissioning...

  5. 26 CFR 1.88-1 - Nuclear decommissioning costs.

    Code of Federal Regulations, 2013 CFR

    2013-04-01

    ... 26 Internal Revenue 2 2013-04-01 2013-04-01 false Nuclear decommissioning costs. 1.88-1 Section 1... (CONTINUED) INCOME TAXES (CONTINUED) Items Specifically Included in Gross Income § 1.88-1 Nuclear decommissioning costs. (a) In general. Section 88 provides that the amount of nuclear decommissioning...

  6. Decision framework for platform decommissioning in California.

    PubMed

    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.

  7. Decontamination, decommissioning, and vendor advertorial issue, 2006

    SciTech Connect

    Agnihotri, Newal

    2006-07-15

    The focus of the July-August issue is on Decontamination, decommissioning, and vendor advertorials. Major articles/reports in this issue include: NPP Krsko revised decommissioning program, by Vladimir Lokner and Ivica Levanat, APO d.o.o., Croatia, and Nadja Zeleznik and Irena Mele, ARAO, Slovenia; Supporting the renaissance, by Marilyn C. Kray, Exelon Nuclear; Outage world an engineer's delight, by Tom Chrisopher, Areva, NP Inc.; Optimizing refueling outages with R and D, by Ross Marcoot, GE Energy; and, A successful project, by Jim Lash, FirstEnergy.

  8. The environmental issues of platform decommissioning

    SciTech Connect

    Susani, L.

    1996-12-31

    This paper provides a review of the environmental impacts of offshore platform disposal, based on past activities and technical and research studies. Environmental impacts are considered in relation to four main decommissioning options. The most significant effects stem from explosive cutting, sediment resuspension and release of contamination during initial production shut-down, well purging and removal of the jacket structure from the seabed. Any decommissioning option that minimizes movement of structures and avoids explosive cutting must therefore be viewed as preferable from an ecological viewpoint. Complete removal is preferred on the grounds of energy conservation, fisheries and navigational safety, and controlled disposal of potential contaminants.

  9. The Windscale Advanced Gas Cooled Reactor (WAGR) Decommissioning Project A Close Out Report for WAGR Decommissioning Campaigns 1 to 10 - 12474

    SciTech Connect

    Halliwell, Chris

    2012-07-01

    The reactor core of the Windscale Advanced Gas-Cooled Reactor (WAGR) has been dismantled as part of an ongoing decommissioning project. The WAGR operated until 1981 as a development reactor for the British Commercial Advanced Gas cooled Reactor (CAGR) power programme. Decommissioning began in 1982 with the removal of fuel from the reactor core which was completed in 1983. Subsequently, a significant amount of engineering work was carried out, including removal of equipment external to the reactor and initial manual dismantling operations at the top of the reactor, in preparation for the removal of the reactor core itself. Modification of the facility structure and construction of the waste packaging plant served to provide a waste route for the reactor components. The reactor core was dismantled on a 'top-down' basis in a series of 'campaigns' related to discrete reactor components. This report describes the facility, the modifications undertaken to facilitate its decommissioning and the strategies employed to recognise the successful decommissioning of the reactor. Early decommissioning tasks at the top of the reactor were undertaken manually but the main of the decommissioning tasks were carried remotely, with deployment systems comprising of little more than crane like devices, intelligently interfaced into the existing structure. The tooling deployed from the 3 tonne capacity (3te) hoist consisted either purely mechanical devices or those being electrically controlled from a 'push-button' panel positioned at the operator control stations, there was no degree of autonomy in the 3te hoist or any of the tools deployed from it. Whilst the ATC was able to provide some tele-robotic capabilities these were very limited and required a good degree of driver input which due to the operating philosophy at WAGR was not utilised. The WAGR box proved a successful waste package, adaptable through the use of waste box furniture specific to the waste-forms generated throughout

  10. 75 FR 80697 - Nuclear Decommissioning Funds

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-12-23

    ...This document contains final regulations under section 468A of the Internal Revenue Code relating to deductions for contributions to trusts maintained for decommissioning nuclear power plants. These final regulations affect taxpayers that own an interest in a nuclear power plant and reflect recent statutory changes. The corresponding temporary regulations are...

  11. Decontamination and decommissioning of Shippingport commercial reactor

    SciTech Connect

    Schreiber, J.

    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.

  12. Sodium Reactor Experiment decommissioning. Final report

    SciTech Connect

    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.

  13. 76 FR 77431 - Decommissioning Planning During Operations

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-12-13

    ...; ] NUCLEAR REGULATORY COMMISSION 10 CFR Parts 20, 30, 40, 50, 70, and 72 RIN 3150-AI55 Decommissioning Planning During Operations AGENCY: Nuclear Regulatory Commission. ACTION: Draft regulatory guide; request for comment. SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment...

  14. 78 FR 663 - Decommissioning Planning During Operations

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-01-04

    ..., Regulatory Guide Development Branch, Division of Engineering, Office of Nuclear Regulatory Research. BILLING... / Friday, January 4, 2013 / Rules and Regulations#0;#0; ] NUCLEAR REGULATORY COMMISSION 10 CFR Parts 20, 30, 40, 50, 70, and 72 RIN 3150-AI55 Decommissioning Planning During Operations AGENCY:...

  15. Decontamination and decommissioning focus area. Technology summary

    SciTech Connect

    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.

  16. University of Virginia Reactor Facility Decommissioning Results

    SciTech Connect

    Ervin, P. F.; Lundberg, L. A.; Benneche, P. E.; Mulder, R. U.; Steva, D. P.

    2003-02-24

    The University of Virginia Reactor Facility started accelerated decommissioning in 2002. The facility consists of two licensed reactors, the CAVALIER and the UVAR. This paper will describe the progress in 2002, remaining efforts and the unique organizational structure of the project team.

  17. 30 CFR 250.1753 - After I decommission a pipeline, what information must I submit?

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... 30 Mineral Resources 2 2012-07-01 2012-07-01 false After I decommission a pipeline, what... SHELF 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...

  18. 30 CFR 250.1754 - When must I remove a pipeline decommissioned in place?

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... 30 Mineral Resources 2 2013-07-01 2013-07-01 false When must I remove a pipeline decommissioned in... Decommissioning Activities Pipeline Decommissioning § 250.1754 When must I remove a pipeline decommissioned in place? You must remove a pipeline decommissioned in place if the Regional Supervisor determines that...

  19. 30 CFR 250.1750 - When may I decommission a pipeline in place?

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... 30 Mineral Resources 2 2012-07-01 2012-07-01 false When may I decommission a pipeline in place... Decommissioning Activities Pipeline Decommissioning § 250.1750 When may I decommission a pipeline in place? You may decommission a pipeline in place when the Regional Supervisor determines that the pipeline...

  20. 30 CFR 250.1754 - When must I remove a pipeline decommissioned in place?

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... 30 Mineral Resources 2 2012-07-01 2012-07-01 false When must I remove a pipeline decommissioned in... Decommissioning Activities Pipeline Decommissioning § 250.1754 When must I remove a pipeline decommissioned in place? You must remove a pipeline decommissioned in place if the Regional Supervisor determines that...

  1. 30 CFR 250.1754 - When must I remove a pipeline decommissioned in place?

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... 30 Mineral Resources 2 2011-07-01 2011-07-01 false When must I remove a pipeline decommissioned in... SHELF Decommissioning Activities Pipeline Decommissioning § 250.1754 When must I remove a pipeline decommissioned in place? You must remove a pipeline decommissioned in place if the Regional Supervisor...

  2. 30 CFR 250.1753 - After I decommission a pipeline, what information must I submit?

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 30 Mineral Resources 2 2010-07-01 2010-07-01 false After I decommission a pipeline, what... 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...

  3. 30 CFR 250.1754 - When must I remove a pipeline decommissioned in place?

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... 30 Mineral Resources 2 2014-07-01 2014-07-01 false When must I remove a pipeline decommissioned in... Decommissioning Activities Pipeline Decommissioning § 250.1754 When must I remove a pipeline decommissioned in place? You must remove a pipeline decommissioned in place if the Regional Supervisor determines that...

  4. 30 CFR 250.1753 - After I decommission a pipeline, what information must I submit?

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... 30 Mineral Resources 2 2014-07-01 2014-07-01 false After I decommission a pipeline, what... SHELF 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...

  5. 30 CFR 250.1750 - When may I decommission a pipeline in place?

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... 30 Mineral Resources 2 2011-07-01 2011-07-01 false When may I decommission a pipeline in place... SHELF Decommissioning Activities Pipeline Decommissioning § 250.1750 When may I decommission a pipeline in place? You may decommission a pipeline in place when the Regional Supervisor determines that...

  6. 30 CFR 250.1750 - When may I decommission a pipeline in place?

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... 30 Mineral Resources 2 2014-07-01 2014-07-01 false When may I decommission a pipeline in place... Decommissioning Activities Pipeline Decommissioning § 250.1750 When may I decommission a pipeline in place? You may decommission a pipeline in place when the Regional Supervisor determines that the pipeline...

  7. 30 CFR 250.1751 - How do I decommission a pipeline in place?

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... 30 Mineral Resources 2 2013-07-01 2013-07-01 false How do I decommission a pipeline in place? 250... Decommissioning Activities Pipeline Decommissioning § 250.1751 How do I decommission a pipeline in place? You must do the following to decommission a pipeline in place: (a) Submit a pipeline...

  8. 30 CFR 250.1750 - When may I decommission a pipeline in place?

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... 30 Mineral Resources 2 2013-07-01 2013-07-01 false When may I decommission a pipeline in place... Decommissioning Activities Pipeline Decommissioning § 250.1750 When may I decommission a pipeline in place? You may decommission a pipeline in place when the Regional Supervisor determines that the pipeline...

  9. 30 CFR 250.1753 - After I decommission a pipeline, what information must I submit?

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... 30 Mineral Resources 2 2013-07-01 2013-07-01 false After I decommission a pipeline, what... SHELF 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...

  10. 30 CFR 250.1753 - After I decommission a pipeline, what information must I submit?

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... 30 Mineral Resources 2 2011-07-01 2011-07-01 false After I decommission a pipeline, what... OUTER CONTINENTAL SHELF Decommissioning Activities Pipeline Decommissioning § 250.1753 After I decommission a pipeline, what information must I submit? Within 30 days after you decommission a pipeline,...

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

    SciTech Connect

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

    2013-07-01

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

  12. Decommissioning of the Tokamak Fusion Test Reactor

    SciTech Connect

    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.

  13. Yankee Nuclear Power Station - analysis of decommissioning costs

    SciTech Connect

    Lessard, L.P.

    1996-12-31

    The preparation of decommissioning cost estimates for nuclear power generating stations has received a great deal of interest in the last few years. Owners are required by regulation to ensure that adequate funds are collected for the timely decommissioning of their facilities. The unexpected premature shutdown of several facilities and uncertainties associated with radioactive waste disposal and long-term spent-fuel storage, when viewed in the light of a deregulated electric utility industry, has caused many companies to reevaluate their decommissioning cost estimates. The decommissioning of the Yankee Nuclear Power Station represents the first large-scale project involving the complete decontamination and dismantlement of a commercial light water nuclear power generation facility in the United States. Since this pressurized water reactor operated for 32 yr at a respectable 74% lifetime capacity factor, the actual costs and resources required to decommission the plant, when compared with decommissioning estimates, will yield valuable benchmarking data.

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

    SciTech Connect

    Manning, R.; Gilmour, J.

    2002-02-26

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

  15. Reactor Design and Decommissioning - An Overview of International Activities in Post Fukushima Era1 - 12396

    SciTech Connect

    Devgun, Jas S.; Laraia, Michele; Dinner, Paul

    2012-07-01

    perspective in the post Fukushima -accident era. Accidents at the Fukushima Daiichi reactors in the aftermath of the devastating earthquake and tsunami of March 11, 2011 have slowed down the nuclear renaissance world-wide and may have accelerated decommissioning either because some countries have decided to halt or reduce nuclear, or because the new safety requirements may reduce life-time extensions. Even in countries such as the UK and France that favor nuclear energy production existing nuclear sites are more likely to be chosen as sites for future NPPs. Even as the site recovery efforts continue at Fukushima and any decommissioning decisions are farther into the future, the accidents have focused attention on the reactor designs in general and specifically on the Fukushima type BWRs. The regulatory authorities in many countries have initiated a re-examination of the design of the systems, structures and components and considerations of the capability of the station to cope with beyond-design basis events. Enhancements to SSCs and site features for the existing reactors and the reactors that will be built will also impact the decommissioning phase activities. The newer reactor designs of today not only have enhanced safety features but also take into consideration the features that will facilitate future decommissioning. Lessons learned from past management and operation of reactors as well as the lessons from decommissioning are incorporated into the new designs. However, in the post-Fukushima era, the emphasis on beyond-design-basis capability may lead to significant changes in SSCs, which eventually will also have impact on the decommissioning phase. Additionally, where some countries decide to phase out the nuclear power, many reactors may enter the decommissioning phase in the coming decade. While the formal updating and expanding of existing guidance documents for accident cleanup and decommissioning would benefit by waiting until the Fukushima project has progressed

  16. HEAVY WATER COMPONENTS TEST REACTOR DECOMMISSIONING

    SciTech Connect

    Austin, W.; Brinkley, D.

    2011-10-13

    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&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

  17. FROM CONCEPT TO REALITY, IN-SITU DECOMMISSIONING OF THE P AND R REACTORS AT THE SAVANNAH RIVER SITE

    SciTech Connect

    Musall, J.; Blankenship, J.; Griffin, W.

    2012-01-09

    SRS recently completed an approximately three year effort to decommission two SRS reactors: P-Reactor (Building 105-P) and R-Reactor (Building 105-R). Completed in December 2011, the concurrent decommissionings marked the completion of two relatively complex and difficult facility disposition projects at the SRS. Buildings 105-P and 105-R began operating as production reactors in the early 1950s with the mission of producing weapons material (e.g., tritium and plutonium-239). The 'P' Reactor and was shutdown in 1991 while the 'R' Reactor and was shutdown in 1964. In the intervening period between shutdown and deactivation & decommissioning (D&D), Buildings 105-P and 105-R saw limited use (e.g., storage of excess heavy water and depleted uranium oxide). For Building 105-P, deactivation was initiated in April 2007 and was essentially complete by June 2010. For Building 105-R, deactivation was initiated in August 2008 and was essentially complete by September 2010. For both buildings, the primary objective of deactivation was to remove/mitigate hazards associated with the remaining hazardous materials, and thus prepare the buildings for in-situ decommissioning. Deactivation removed the following hazardous materials to the extent practical: combustibles/flammables, residual heavy water, acids, friable asbestos (as needed to protect workers performing deactivation and decommissioning), miscellaneous chemicals, lead/brass components, Freon(reg sign), oils, mercury/PCB containing components, mold and some radiologically-contaminated equipment. In addition to the removal of hazardous materials, deactivation included the removal of hazardous energy, exterior metallic components (representing an immediate fall hazard), and historical artifacts along with the evaporation of water from the two Disassembly Basins. Finally, so as to facilitate occupancy during the subsequent in-situ decommissioning, deactivation implemented repairs to the buildings and provided temporary power.

  18. Semi-Autonomous Manipulation of Natural Objects

    DTIC Science & Technology

    2012-11-01

    contiguous re- gions that share a particular property. These methods process an image to identify boundaries between regions that share a particular property...All of the methods in this category are based on the assumption that the boundaries of objects correspond to discontinuities in color, texture, or...brightness—and that these discontinuities do not occur anywhere else. Most methods rely on thresholding, edge detection, clustering, 2 or region growing

  19. Decommissioning: Nuclear Power's Missing Link. Worldwatch Paper 69.

    ERIC Educational Resources Information Center

    Pollock, Cynthia

    The processes and associated dilemmas of nuclear power plant decommissioning are reviewed in this publication. Decommissioning involves the clearing up and disposal of a retired nuclear plant and its equipment of such a way as to safeguard the public from the dangers of radioactivity. Related problem areas are identified and include: (1) closure…

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

    SciTech Connect

    Keep, Matthew

    2007-07-01

    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)

  1. Decommissioning considerations at a time of nuclear renaissance

    SciTech Connect

    Devgun, Jas S.

    2007-07-01

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

  2. Decontamination, decommissioning, and vendor advertorial issue, 2007

    SciTech Connect

    Agnihotri, Newal

    2007-07-15

    The focus of the July-August issue is on Decontamination, decommissioning, and vendor advertorials. Major articles/reports in this issue include: An interesting year ahead of us, by Tom Christopher, AREVA NP Inc.; U.S.-India Civil Nuclear Cooperation; Decontamination and recycling of retired components, by Sean P. Brushart, Electric Power Research Institute; and, ANO is 33 and going strong, by Tyler Lamberts, Entergy Nuclear Operations, Inc. The industry innovation article is: Continuous improvement process, by ReNae Kowalewski, Arkansas Nuclear One.

  3. Environmental Impact Assessment (EIA) Process of V1 NPP Decommissioning

    SciTech Connect

    Matejovic, Igor; Polak, Vincent

    2007-07-01

    Through the adoption of Governmental Resolution No. 801/99 the Slovak Republic undertook a commitment to shutdown units 1 and 2 of Jaslovske Bohunice V 1 NPP (WWER 230 reactor type) in 2006 and 2008 respectively. Therefore the more intensive preparation of a decommissioning documentation has been commenced. Namely, the VI NPP Conceptual Decommissioning Plan and subsequently the Environmental Impact Assessment Report of VI NPP Decommissioning were developed. Thus, the standard environmental impact assessment process was performed and the most suitable alternative of V1 NPP decommissioning was selected as a basis for development of further decommissioning documents. The status and main results of the environmental impact assessment process and EIA report are discussed in more detail in this paper. (authors)

  4. Pre-decommissioning radiological characterization of concrete

    SciTech Connect

    Boden, Sven; Cantrel, Eric

    2007-07-01

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

  5. Nuclear facility decommissioning and site remedial actions

    SciTech Connect

    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.

  6. Nuclear facility decommissioning and site remedial actions

    SciTech Connect

    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.

  7. Lessons learnt from Ignalina NPP decommissioning project

    SciTech Connect

    NAISSE, Jean-Claude

    2007-07-01

    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)

  8. 26 CFR 1.468A-4T - Treatment of nuclear decommissioning fund (temporary).

    Code of Federal Regulations, 2010 CFR

    2010-04-01

    ... 26 Internal Revenue 6 2010-04-01 2010-04-01 false Treatment of nuclear decommissioning fund...-4T Treatment of nuclear decommissioning fund (temporary). (a) In general. A nuclear decommissioning... income earned by the assets of the nuclear decommissioning fund. (b) Modified gross income. For...

  9. 26 CFR 1.468A-4 - Treatment of nuclear decommissioning fund.

    Code of Federal Regulations, 2011 CFR

    2011-04-01

    ... 26 Internal Revenue 6 2011-04-01 2011-04-01 false Treatment of nuclear decommissioning fund. 1...-4 Treatment of nuclear decommissioning fund. (a) In general. A nuclear decommissioning fund is... by the assets of the nuclear decommissioning fund. (b) Modified gross income. For purposes of...

  10. 26 CFR 1.468A-4 - Treatment of nuclear decommissioning fund.

    Code of Federal Regulations, 2012 CFR

    2012-04-01

    ... 26 Internal Revenue 6 2012-04-01 2012-04-01 false Treatment of nuclear decommissioning fund. 1...-4 Treatment of nuclear decommissioning fund. (a) In general. A nuclear decommissioning fund is... by the assets of the nuclear decommissioning fund. (b) Modified gross income. For purposes of...

  11. 26 CFR 1.468A-4 - Treatment of nuclear decommissioning fund.

    Code of Federal Regulations, 2014 CFR

    2014-04-01

    ... 26 Internal Revenue 6 2014-04-01 2014-04-01 false Treatment of nuclear decommissioning fund. 1...-4 Treatment of nuclear decommissioning fund. (a) In general. A nuclear decommissioning fund is... by the assets of the nuclear decommissioning fund. (b) Modified gross income. For purposes of...

  12. 26 CFR 1.468A-4 - Treatment of nuclear decommissioning fund.

    Code of Federal Regulations, 2013 CFR

    2013-04-01

    ... 26 Internal Revenue 6 2013-04-01 2013-04-01 false Treatment of nuclear decommissioning fund. 1...-4 Treatment of nuclear decommissioning fund. (a) In general. A nuclear decommissioning fund is... by the assets of the nuclear decommissioning fund. (b) Modified gross income. For purposes of...

  13. 30 CFR 250.1750 - When may I decommission a pipeline in place?

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 30 Mineral Resources 2 2010-07-01 2010-07-01 false When may I decommission a pipeline in place... Pipeline Decommissioning § 250.1750 When may I decommission a pipeline in place? You may decommission a pipeline in place when the Regional Supervisor determines that the pipeline does not constitute a...

  14. 30 CFR 250.1754 - When must I remove a pipeline decommissioned in place?

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 30 Mineral Resources 2 2010-07-01 2010-07-01 false When must I remove a pipeline decommissioned in... Activities Pipeline Decommissioning § 250.1754 When must I remove a pipeline decommissioned in place? You must remove a pipeline decommissioned in place if the Regional Supervisor determines that the...

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

    SciTech Connect

    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.

  16. Decommissioning planning for the Joint European Torus Fusion Reactor

    SciTech Connect

    Wilson, K.A.; Stevens, K.

    2007-07-01

    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)

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

    SciTech Connect

    Schulz, J.; Crawford, A.C. )

    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.

  18. Safety Oversight of Decommissioning Activities at DOE Nuclear Sites

    SciTech Connect

    Zull, Lawrence M.; Yeniscavich, William

    2008-01-15

    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.

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

    SciTech Connect

    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.

  20. Application of Robotics in Decommissioning and Decontamination - 12536

    SciTech Connect

    Banford, Anthony; Kuo, Jeffrey A.; Bowen, R.A.; Szilagyi, Andrew; Kirk, Paula

    2012-07-01

    Decommissioning and dismantling of nuclear facilities is a significant challenge worldwide and one which is growing in size as more plants reach the end of their operational lives. The strategy chosen for individual projects varies from the hands-on approach with significant manual intervention using traditional demolition equipment at one extreme to bespoke highly engineered robotic solutions at the other. The degree of manual intervention is limited by the hazards and risks involved, and in some plants are unacceptable. Robotic remote engineering is often viewed as more expensive and less reliable than manual approaches, with significant lead times and capital expenditure. However, advances in robotics and automation in other industries offer potential benefits for future decommissioning activities, with the high probability of reducing worker exposure and other safety risks as well as reducing the schedule and costs required to complete these activities. Some nuclear decommissioning tasks and facility environments are so hazardous that they can only be accomplished by exclusive use of robotic and remote intervention. Less hazardous tasks can be accomplished by manual intervention and the use of PPE. However, PPE greatly decreases worker productivity and still exposes the worker to both risk and dose making remote operation preferable to achieve ALARP. Before remote operations can be widely accepted and deployed, there are some economic and technological challenges that must be addressed. These challenges will require long term investment commitments in order for technology to be: - Specifically developed for nuclear applications; - At a sufficient TRL for practical deployment; - Readily available as a COTS. Tremendous opportunities exist to reduce cost and schedule and improve safety in D and D activities through the use of robotic and/or tele-operated systems. - Increasing the level of remote intervention reduces the risk and dose to an operator. Better

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

    SciTech Connect

    Agnihotri, Newal

    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.

  2. Uranium enrichment decontamination and decommissioning fund

    SciTech Connect

    1994-12-31

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

  3. Lessons Learned from the NASA Plum Brook Reactor Facility Decommissioning

    NASA Technical Reports Server (NTRS)

    2010-01-01

    NASA has been conducting decommissioning activities at its PBRF for the last decade. As a result of all this work there have been several lessons learned both good and bad. This paper presents some of the more exportable lessons.

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

    SciTech Connect

    Salazar, M.; Elder, J.

    1992-08-01

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

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

    SciTech Connect

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

    2013-07-01

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

  6. Progress in Decommissioning of Ignalina NPP Unit 1

    SciTech Connect

    Ancius, Darius; Krenevicius, Rimantas; Kutas, Saulius; Chouha, Michel

    2002-07-01

    The aim of the paper is to present the Lithuanian legal framework regarding the nuclear safety in Decommissioning and Waste Management, and the progress in the Decommissioning Programme of the unit 1 of Ignalina Nuclear Power Plant (INPP). INPP is the only nuclear plant in Lithuania. It comprises two RBMK-1500 reactors. After Lithuania has restored its independence, responsibility for Ignalina NPP was transferred to the Republic of Lithuania. To ensure the control of the Nuclear Safety in Lithuania, The State Nuclear Power Safety Inspectorate (VATESI) was created on 18 October 1991, by a resolution of the Lithuanian Government. Significant work has been performed over the last decade, aiming at upgrading the safety level of the Ignalina NPP with reference to the International standards. On 5 October 1999 the Seimas (Parliament) adopted the National Energy Strategy: It has been decided that unit 1 of Ignalina NPP will be closed down before 2005, The conditions and precise final date of the decommissioning of Unit 2 will be stated in the updated National Energy strategy in 2004. On 20-21 June 2000, the International Donors' Conference for the Decommissioning of Ignalina NPP took place in Vilnius. More than 200 Millions Euro were pledged of which 165 M funded directly from the European Union's budget, as financial support to the Decommissioning projects. The Decommissioning Program encompasses legal, organizational, financial and technical means including the social and economical impacts in the region of Ignalina. The Program is financed from International Support Fund, State budget, National Decommissioning Fund of Ignalina NPP and other funds. Decommissioning of Ignalina NPP is subject to VATESI license according to the Law on Nuclear Energy. The Government established the licensing procedure in the so-called 'Procedure for licensing of Nuclear Activities'; and the document 'General Requirements for Decommissioning of the Ignalina NPP' has been issued by VATESI. A

  7. The Decommissioning of the Trino Nuclear Power Plant

    SciTech Connect

    Brusa, L.; DeSantis, R.; Nurden, P. L.; Walkden, P.; Watson, B.

    2002-02-27

    Following a referendum in Italy in 1987, the four Nuclear Power Plants (NPPs) owned and operated by the state utility ENEL were closed. After closing the NPPs, ENEL selected a ''safestore'' decommissioning strategy; anticipating a safestore period of some 40-50 years. This approach was consistent with the funds collected during plant operation, and was reinforced by the lack of both a waste repository and a set of national free release limits for contaminated materials in Italy. During 1999, twin decisions were made to privatize ENEL and to transform the nuclear division into a separate subsidiary of the ENEL group. This group was renamed Sogin and during the following year, ownership of the company was transferred to the Italian Treasury. On formation, Sogin was asked by the Italian government to review the national decommissioning strategy. The objective of the review was to move from a safestore strategy to a prompt decommissioning strategy, with the target of releasing all of the nuclear sites by 2020. It was recognized that this target was conditional upon the availability of a national LLW repository together with interim stores for both spent fuel and HLW by 2009. The government also agreed that additional costs caused by the acceleration of the decommissioning program would be considered as stranded costs. These costs will be recovered by a levy on the kWh price of electricity, a process established and controlled by the Regulator of the Italian energy sector. Building on the successful collaboration to develop a prompt decommissioning strategy for the Latina Magnox reactor (1), BNFL and Sogin agreed to collaborate on an in depth study for the prompt decommissioning of the Sogin PWR at Trino. BNFL is currently decommissioning six NPPs and is at an advanced stage of planning for two further units, having completed a full and rigorous exercise to develop Baseline Decommissioning Plans (BDP's) for these stations. The BDP exercise utilizes the full range of

  8. Radioactive waste management and decommissioning of accelerator facilities.

    PubMed

    Ulrici, Luisa; Magistris, Matteo

    2009-11-01

    During the operation of high-energy accelerators, the interaction of radiation with matter can lead to the activation of the machine components and of the surrounding infrastructures. As a result of maintenance operation and during decommissioning of the installation, considerable amounts of radioactive waste are evacuated and shall be managed according to the radiation-protection legislation. This paper gives an overview of the current practices in radioactive waste management and decommissioning of accelerators.

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

    SciTech Connect

    Prosser, J.L.

    2006-07-01

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

  10. The unit cost factors and calculation methods for decommissioning - Cost estimation of nuclear research facilities

    SciTech Connect

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

    2007-07-01

    Available in abstract form only. Full text of publication follows: The uncertainties of decommissioning costs increase high due to several conditions. Decommissioning cost estimation depends on the complexity of nuclear installations, its site-specific physical and radiological inventories. Therefore, the decommissioning costs of nuclear research facilities must be estimated in accordance with the detailed sub-tasks and resources by the tasks of decommissioning activities. By selecting the classified activities and resources, costs are calculated by the items and then the total costs of all decommissioning activities are reshuffled to match with its usage and objectives. And the decommissioning cost of nuclear research facilities is calculated by applying a unit cost factor method on which classification of decommissioning works fitted with the features and specifications of decommissioning objects and establishment of composition factors are based. Decommissioning costs of nuclear research facilities are composed of labor cost, equipment and materials cost. Of these three categorical costs, the calculation of labor costs are very important because decommissioning activities mainly depend on labor force. Labor costs in decommissioning activities are calculated on the basis of working time consumed in decommissioning objects and works. The working times are figured out of unit cost factors and work difficulty factors. Finally, labor costs are figured out by using these factors as parameters of calculation. The accuracy of decommissioning cost estimation results is much higher compared to the real decommissioning works. (authors)

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

    SciTech Connect

    MC Bierschbach; DR Haffner; KJ Schneider; SM Short

    2002-12-01

    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 {sup 3}H-labeled compounds; a laboratory for the manufacture of {sup 14}C-labeled compounds; a laboratory for the manufacture of {sup 123}I-labeled compounds; a laboratory for the manufacture of {sup 137}Cs sealed sources; a laboratory for the manufacture of {sup 241}Am 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

  12. Evaluation of nuclear facility decommissioning projects. Project summary report, Elk River Reactor

    SciTech Connect

    Miller, R.L.; Adams, J.A.

    1982-12-01

    This report summarizes information concerning the decommissioning of the Elk River Reactor. Decommissioning data from available documents were input into a computerized data-handling system in a manner that permits specific information to be readily retrieved. The information is in a form that assists the Nuclear Regulatory Commission in its assessment of decommissioning alternatives and ALARA methods for future decommissionings projects. Samples of computer reports are included in the report. Decommissioning of other reactors, including NRC reference decommissioning studies, will be described in similar reports.

  13. An overview of U.S. decommissioning experience -- A basic introduction

    SciTech Connect

    Boing, L.E.

    1998-03-09

    This paper presents an overview of the US experiences in the decommissioning technical area. Sections included are: (1) an overview of the magnitude of the problem, (2) a review of the US decommissioning process, (3) regulation of decommissioning, (4) regulatory and funding requirements for decommissioning, and (5) a general overview of all on-going and completed decommissioning projects to date in the US. The final section presents a review of some issues in the decommissioning area currently being debated in the technical specialists community.

  14. DEACTIVATION AND DECOMMISSIONING (D AND D) TECHNOLOGY INTEGRATION

    SciTech Connect

    M.A. Ebadian, Ph.D.

    1999-01-01

    As part of the ongoing task of making Deactivation and Decommissioning (D&D) operations more efficient, this subtask has addressed the need to integrate existing characterization technologies with decontamination technologies in order to provide real-time data on the progress of contamination removal. Specifically, technologies associated with concrete decontamination and/or removal have been examined with the goal of integrating existing technologies and commercializing the resulting hybrid. The Department of Energy (DOE) has estimated that 23 million cubic meters of concrete will require disposition as 1200 buildings undergo the D&D process. All concrete removal to be performed will also necessitate extensive use of characterization techniques. The in-process characterization presents the most potential for improvement and cost-savings as compared to other types. Current methods for in-process characterization usually require cessation of work to allow for radiation surveys to assess the rate of decontamination. Combining together decontamination and characterization technologies would allow for in-process evaluation of decontamination efforts. Since the present methods do not use in-process evaluations for the progress of decontamination, they may allow for ''overremoval'' of materials (removal of contaminated along with non-contaminated materials). Overremoval increases the volume of waste and therefore the costs associated with disposal. Integrating technologies would facilitate the removal of only contaminated concrete and reduce the total volume of radioactive waste, which would be disposed of. This would eventually ensure better productivity and time savings. This project presents a general procedure to integrate the above-mentioned technologies in the form of the Technology Integration Module (TIM) along with combination lists of commercially available decontamination and characterization technologies. The scope of the project has also been expanded by FIU

  15. Mobile workstation for decontamination and decommissioning operations

    SciTech Connect

    Whittaker, W.L.; Osborn, J.F.; Thompson, B.R.

    1993-10-01

    This project is an interdisciplinary effort to develop effective mobile worksystems for decontamination and decommissioning (D&D) of facilities within the DOE Nuclear Weapons Complex. These mobile worksystems will be configured to operate within the environmental and logistical constraints of such facilities and to perform a number of work tasks. Our program is designed to produce a mobile worksystem with capabilities and features that are matched to the particular needs of D&D work by evolving the design through a series of technological developments, performance tests and evaluations. The project has three phases. In this the first phase, an existing teleoperated worksystem, the Remote Work Vehicle (developed for use in the Three Mile Island Unit 2 Reactor Building basement), was enhanced for telerobotic performance of several D&D operations. Its ability to perform these operations was then assessed through a series of tests in a mockup facility that contained generic structures and equipment similar to those that D&D work machines will encounter in DOE facilities. Building upon the knowledge gained through those tests and evaluations, a next generation mobile worksystem, the RWV II, and a more advanced controller will be designed, integrated and tested in the second phase, which is scheduled for completion in January 1995. The third phase of the project will involve testing of the RWV II in the real DOE facility.

  16. Successful decommissioning and demolition at Weldon Spring

    SciTech Connect

    Davis, M.L.

    1994-12-31

    B&W Nuclear Environmental Services, Inc. (B&W NESI) and OHM Corporation (OHM) formed a joint venture company, B&W/OHM Weldon Spring, Inc. (B&W/OHM WSI) to perform work at the U.S. Department of Energy`s (DOE`s) Weldon Spring Site Remedial Action Project (WSSRAP). This joint venture company combines the hazardous and toxic waste remediation experience of OHM with the radiological decontamination and decommissioning experience of B&W NESI. Together, the two companies have over 60 yr of relevant experience and a strong record of performance in resolving problems associated with nuclear and hazardous materials contamination. The B&W/OHM WSI is under contract to MK-Ferguson, DOE`s project management contractor (PMC), at WSSRAP to provide supervision, tools, labor, and equipment to decontaminate and dismantle 11 buildings at the chemical plant site. The Weldon Spring site, located in St. Charles, Missouri, was used by the U.S. Atomic Energy Commission from 1957 through 1966 as a feed material production site to process uranium and thorium ore concentrates. Since the cessation of production activity at this site, the buildings and structures contained in the chemical plant have badly deteriorated, posing an immediate potential threat to workers, the general public, and the environment, prompting the DOE to initiate an Expedited Response Action to decontaminate, empty, and dismantle all the buildings and structures.

  17. Windscale pile reactors - Decommissioning progress on a fifty year legacy

    SciTech Connect

    Sexton, Richard J.

    2007-07-01

    The decommissioning of the Windscale Pile 1 reactor, fifty years after the 1957 fire, is one of the most technically challenging decommissioning projects in the UK, if not the world. This paper presents a summary of the 1957 Windscale Pile 1 accident, its unique challenges and a new technical approach developed to safely and efficiently decommission the two Windscale Pile Reactors. The reactors will be decommissioned using a top down approach that employs an array of light weight, carbon fiber, high payload robotic arms to remove the damaged fuel, the graphite core, activated metals and concrete. This relatively conventional decommissioning approach has been made possible by a recently completed technical assessment of reactor core fire and criticality risk which concluded that these types of events are not credible if relatively simple controls are applied. This paper presents an overview of the design, manufacture and testing of equipment to remove the estimated 15 tons of fire damaged fuel and isotopes from the Pile 1 reactor. The paper also discusses recently conducted characterization activities which have allowed for a refined waste estimate and conditioning strategy. These data and an innovative approach have resulted in a significant reduction in the estimated project cost and schedule. (authors)

  18. The Chernobyl NPP decommissioning: Current status and alternatives

    SciTech Connect

    Mikolaitchouk, H.; Steinberg, N.

    1996-08-01

    After the Chernobyl accident of April 26, 1986, many contradictory decisions were taken concerning the Chernobyl nuclear power plant (NPP) future. The principal source of contradictions was a deadline for a final shutdown of the Chernobyl NPP units. Alterations in a political and socioeconomic environment resulted in the latest decision of the Ukrainian Authorities about 2000 as a deadline for a beginning of the Chernobyl NPP decommissioning. The date seems a sound compromise among the parties concerned. However, in order to meet the data a lot of work should be done. First of all, a decommissioning strategy has to be established. The problem is complicated due to both site-specific aspects and an absence of proven solutions for the RBMK-type reactor decommissioning. In the paper the problem of decommissioning option selection is considered taking into account an influence of the following factors: relevant legislative and regulatory requirements; resources required to carry out decommissioning (man-power, equipment, technologies, waste management infrastructure, etc.); radiological and physical status of the plant, including structural integrity and predictable age and weather effects; impact of planned activities at the destroyed unit 4 and within the 30-km exclusion zone of the Chernobyl NPP; planed use of the site; socio-economic considerations.

  19. Regulatory process for decommissioning nuclear power reactors. Final report

    SciTech Connect

    1998-03-01

    This report provides regulatory guidance for utilities consistent with the changes in the decommissioning rule, 10 CFR50.82 as revised in July 1996. The purpose of this report is to explain the new rule in the context of related industry experience and to provide practical guidance to licensees contemplating or implementing a shutdown. Because the regulatory process is still rapidly evolving, this report reflects only a current status of the acceptable methods and practices derived from a review of the current regulations, guidance documents and industry experience for decommissioning a nuclear power reactor. EPRI anticipates periodic updates of this document to incorporate various utility experiences with decommissioning, and also to reflect any regulatory changes. The report provides a summary of ongoing federal agency and industry activities and the regulatory requirements that are currently applicable, or no longer applicable, to nuclear power plants at the time of permanent shutdown through the early decommissioning stage. The report describes the major components of a typical decommissioning action plan, providing industry experience and guidance for licensees considering or implementing permanent shutdown.

  20. The shielding design process--new plants to decommissioning.

    PubMed

    Jeffries, Graham; Cooper, Andrew; Hobson, John

    2005-01-01

    BNFL have over 25 years experience of designing nuclear plant for the whole-fuel cycle. In the UK, a Nuclear Decommissioning Authority (NDA) is to be set up to ensure that Britain's nuclear legacy is cleaned up safely, securely and cost effectively. The resulting challenges and opportunities for shielding design will be substantial as the shielding design process was originally devised for the design of new plants. Although its underlying principles are equally applicable to decommissioning and remediation of old plants, there are many aspects of detailed application that need to adapt to this radically different operating environment. The paper describes both the common issues and the different challenges of shielding design at different operational phases. Sample applications will be presented of both new plant and decommissioning projects that illustrate not only the robust nature of the processes being used, but also how they lead to cost-effective solutions making a substantive and appropriate contribution to radiological protection goals.

  1. Management of the decommissioning of the Thetis reactor

    SciTech Connect

    Ooms, Luc; Maris, Patrick; Noynaert, Luc

    2013-07-01

    The Thetis research reactor on the site of the Nuclear Sciences Institute of the Ghent University has been in operation from 1967 until December 2003. This light-water moderated graphite-reflected low-enriched uranium pool-type reactor has been used for various purposes e.g. the production of radioisotopes and activation analyses. During the first years its core power was 15 kW. In the early '70, a core enlargement allowed for operation at typically 150 kW, while the maximum was allowed to be 250 kW In September 2007, Ghent University entrusted to SCK-CEN the management of the back-end of the spent fuel and the decommissioning of the reactor. In 2010, the spent fuel was removed from the reactor and transported to Belgoprocess for cementation in 400 l drums and interim storage awaiting final disposal. This activity allows tackling the decommissioning of the reactor. The objective is to complete its decommissioning by the end of 2014. In the framework of the decommissioning of the Thetis reactor, SCK-CEN set-up the final decommissioning plan and the decommissioning licensing file. These documents include among others a radiological inventory of the reactor. The graphite moderator blocks, the control and the safety pates, the liner of the pool were modeled to assess the activation products (isotopic vector and intensity). At the end of the unloading of the reactor in 2010 a brief mapping of the equipment's and internals of the reactor pool was performed. In 2012, we realized a more detailed mapping. These results confirmed those performed earlier and allowed to confirm the assumptions made in the final decommissioning plan. We set-up the terms of reference for the first decommissioning phase of the reactor namely the dismantling of the reactor i.e. reactor pool, circuits and rabbit system, equipment's and ventilation ducts. The removal of asbestos is also included into this phase. We conducted the selection process and the awarding of this decommissioning job. We

  2. DEACTIVATION AND DECOMMISSIONING PLANNING AND ANALYSIS WITH GEOGRAPHIC INFORMATION SYSTEMS

    SciTech Connect

    Bollinger, J; William Austin, W; Larry Koffman, L

    2007-09-17

    From the mid-1950's through the 1980's, the U.S. Department of Energy's Savannah River Site produced nuclear materials for the weapons stockpile, for medical and industrial applications, and for space exploration. Although SRS has a continuing defense-related mission, the overall site mission is now oriented toward environmental restoration and management of legacy chemical and nuclear waste. With the change in mission, SRS no longer has a need for much of the infrastructure developed to support the weapons program. This excess infrastructure, which includes over 1000 facilities, will be decommissioned and demolished over the forthcoming years. Dispositioning facilities for decommissioning and deactivation requires significant resources to determine hazards, structure type, and a rough-order-of-magnitude estimate for the decommissioning and demolition cost. Geographic information systems (GIS) technology was used to help manage the process of dispositioning infrastructure and for reporting the future status of impacted facilities.

  3. Beneficial Re-use of Decommissioned Former Nuclear Facilities

    SciTech Connect

    Boing, L.E.

    1997-06-01

    With the decision to decommission a nuclear facility, it is necessary to evaluate whether to fully demolish a facility or to re-use the facility in some capacity. This evaluation is often primarily driven by both the past mission of the site and the facility and the site's perceived future mission. In the case where the facility to be decommissioned is located within a large research or industrial complex and represents a significant resource to the site's future mission, it may be a perfect candidate to be re-used in some fashion. However, if the site is a rather remote older facility with little chance of being modified to today's standards for its re-use, the chances for its re-use will be substantially reduced. In this presentation, some specific cases of former nuclear facilities being decommissioned and re-used will be reviewed and some factors required to be considered in making this decision will be reviewed.

  4. Completion of decommissioning: Monitoring for site release and license termination

    SciTech Connect

    Boing, L.E.

    1997-08-01

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

  5. 26 CFR 1.468A-1T - Nuclear decommissioning costs; general rules (temporary).

    Code of Federal Regulations, 2010 CFR

    2010-04-01

    ... 26 Internal Revenue 6 2010-04-01 2010-04-01 false Nuclear decommissioning costs; general rules...-1T Nuclear decommissioning costs; general rules (temporary). (a) Introduction. Section 468A provides an elective method for taking into account nuclear decommissioning costs for Federal income...

  6. 30 CFR 585.1019 - What are the decommissioning requirements for an Alternate Use RUE?

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... an Alternate Use RUE? 585.1019 Section 585.1019 Mineral Resources BUREAU OF OCEAN ENERGY MANAGEMENT... Facilities Decommissioning An Alternate Use Rue § 585.1019 What are the decommissioning requirements for an Alternate Use RUE? (a) Decommissioning requirements will be determined by BOEM on a case-by-case basis,...

  7. 30 CFR 285.1019 - What are the decommissioning requirements for an Alternate Use RUE?

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... an Alternate Use RUE? 285.1019 Section 285.1019 Mineral Resources MINERALS MANAGEMENT SERVICE... Facilities Decommissioning An Alternate Use Rue § 285.1019 What are the decommissioning requirements for an Alternate Use RUE? (a) Decommissioning requirements will be determined by MMS on a case-by-case basis,...

  8. 30 CFR 585.1019 - What are the decommissioning requirements for an Alternate Use RUE?

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... an Alternate Use RUE? 585.1019 Section 585.1019 Mineral Resources BUREAU OF OCEAN ENERGY MANAGEMENT... Facilities Decommissioning An Alternate Use Rue § 585.1019 What are the decommissioning requirements for an Alternate Use RUE? (a) Decommissioning requirements will be determined by BOEM on a case-by-case basis,...

  9. 30 CFR 285.1019 - What are the decommissioning requirements for an Alternate Use RUE?

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... an Alternate Use RUE? 285.1019 Section 285.1019 Mineral Resources BUREAU OF OCEAN ENERGY MANAGEMENT... Activities Using Existing OCS Facilities Decommissioning An Alternate Use Rue § 285.1019 What are the decommissioning requirements for an Alternate Use RUE? (a) Decommissioning requirements will be determined by...

  10. 30 CFR 585.1019 - What are the decommissioning requirements for an Alternate Use RUE?

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... an Alternate Use RUE? 585.1019 Section 585.1019 Mineral Resources BUREAU OF OCEAN ENERGY MANAGEMENT... Facilities Decommissioning An Alternate Use Rue § 585.1019 What are the decommissioning requirements for an Alternate Use RUE? (a) Decommissioning requirements will be determined by BOEM on a case-by-case basis,...

  11. 26 CFR 1.468A-1 - Nuclear decommissioning costs; general rules.

    Code of Federal Regulations, 2014 CFR

    2014-04-01

    ... 26 Internal Revenue 6 2014-04-01 2014-04-01 false Nuclear decommissioning costs; general rules. 1...-1 Nuclear decommissioning costs; general rules. (a) Introduction. Section 468A provides an elective method for taking into account nuclear decommissioning costs for Federal income tax purposes. In...

  12. 26 CFR 1.468A-1 - Nuclear decommissioning costs; general rules.

    Code of Federal Regulations, 2012 CFR

    2012-04-01

    ... 26 Internal Revenue 6 2012-04-01 2012-04-01 false Nuclear decommissioning costs; general rules. 1...-1 Nuclear decommissioning costs; general rules. (a) Introduction. Section 468A provides an elective method for taking into account nuclear decommissioning costs for Federal income tax purposes. In...

  13. 26 CFR 1.468A-1 - Nuclear decommissioning costs; general rules.

    Code of Federal Regulations, 2011 CFR

    2011-04-01

    ... 26 Internal Revenue 6 2011-04-01 2011-04-01 false Nuclear decommissioning costs; general rules. 1...-1 Nuclear decommissioning costs; general rules. (a) Introduction. Section 468A provides an elective method for taking into account nuclear decommissioning costs for Federal income tax purposes. In...

  14. 26 CFR 1.468A-1 - Nuclear decommissioning costs; general rules.

    Code of Federal Regulations, 2013 CFR

    2013-04-01

    ... 26 Internal Revenue 6 2013-04-01 2013-04-01 false Nuclear decommissioning costs; general rules. 1...-1 Nuclear decommissioning costs; general rules. (a) Introduction. Section 468A provides an elective method for taking into account nuclear decommissioning costs for Federal income tax purposes. In...

  15. 77 FR 8902 - Draft Regulatory Guide: Issuance, Availability Decommissioning of Nuclear Power Reactors

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-02-15

    ... COMMISSION Draft Regulatory Guide: Issuance, Availability Decommissioning of Nuclear Power Reactors AGENCY... ``Decommissioning of Nuclear Power Reactors.'' This guide describes a method NRC considers acceptable for use in decommissioning power reactors. DATES: Submit comments by April 16, 2012. Comments received after this date...

  16. 77 FR 75198 - Standard Format and Content for Post-Shutdown Decommissioning Activities Report

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-12-19

    ... COMMISSION Standard Format and Content for Post-Shutdown Decommissioning Activities Report AGENCY: Nuclear... Format and Content for Post-shutdown Decommissioning Activities Report.'' This guide describes a method...) 1.185, ``Standard Format and Content for Post-shutdown Decommissioning Activities Report,''...

  17. A costing model for offshore decommissioning in California.

    PubMed

    Bressler, Andrew; Bernstein, Brock B

    2015-10-01

    California's 27 offshore oil and gas platforms will reach the end of their useful lifetimes sometime in the near future and will require decommissioning. Although existing leases require complete removal of all platforms and associated infrastructure, the underlying laws and regulations have changed in recent years to allow a number of alternative uses after decommissioning. In particular, AB 2503, signed into law in September 2010, provides for a rigs-to-reefs program that allows the state to accept ownership of decommissioned platforms in federal waters. Decisions about whether to remove platforms completely or leave them in place as artificial reefs will depend in part on the relative cost of the 2 options. In this study, we describe the design and use of a mathematical decision model that provides detailed cost estimates of complete and partial removal (to 85 feet below the water line) for California's offshore platforms. The model, PLATFORM, is loaded with Bureau of Safety and Environmental Enforcement (BSEE) and Bureau of Ocean Energy Management (BOEM) costs for complete removal, along with costs for partial removal calculated for this study and estimates of the uncertainty associated with decommissioning cost estimates. PLATFORM allows users to define a wide range of decommissioning and costing scenarios (e.g., number of platforms, choice of heavy lift vessel, shell mound removal, reef enhancement). As a benchmark cost, complete removal of all 27 offshore platforms, grouped into the 7 decommissioning projects defined by the most recent federal cost estimates produced in 2010, would cost an estimated $1.09 billion, whereas partial removal of these platforms, grouped into the same set of projects, would cost $478 million, with avoided costs of $616 million (with minor rounding).

  18. The involvement of SCK-CEN in decommissioning projects

    SciTech Connect

    Noynaert, Luc; Cornelissen, Rene; Dadoumont, Jerome; Van den Dungen, Kurt

    2013-07-01

    SCK-CEN is the Belgian Nuclear Research Centre. Founded in the mid-fifties, it has accumulated experience and know-how in all fields of the nuclear power production: in the neutronics calculation, radiation protection, waste management, fuel performance and analysis, nuclear measurements, radiochemistry, reactor technology, etc. Since 1989, SCK-CEN has launched Decommissioning activities to deal with the Technical Liabilities created by 40 years of operation. The main projects started were: - the dismantling of the BR3 PWR reactor; - the dismantling of active laboratories and the decontamination of buildings for unrestricted reuse; - the management of the waste arising from the refurbishment activities of the BR2, especially the management of the high active beryllium matrix. In 1989, the BR3 reactor, a Pressurized Water Reactor, was selected by the European Commission as one of the four pilot dismantling projects in the framework of the EC five year RTD program on dismantling nuclear installations. Through this project, SCK-CEN has built up a broad know-how in dismantling and decommissioning operations. This know how concerns the decontamination for dose rate reduction and/or free release of materials, tele-operated techniques for cutting highly activated components of a reactor, concrete decontamination techniques, characterization techniques of radioactive waste or for free release of components and development of decommissioning management and record-keeping of material streams and of nuclear material accountancy. SCK-CEN is now actively involved in other decommissioning projects in Belgium and in expertise abroad. After giving an overview of the main achievements and the perspectives of the decommissioning of the BR3 reactor, the paper intends to present the involvement of SCK-CEN in the other decommissioning projects and to give an overview of our activities and capacities. (authors)

  19. Technology demonstrations in the Decontamination and Decommissioning Focus Area

    SciTech Connect

    Bossart, S.J.

    1996-02-01

    This paper describes three large-scale demonstration projects sponsored jointly by the Decontamination and Decommissioning Focus Area (DDFA), and the three US Department of Energy (DOE) Operations Offices that successfully offered to deactivate or decommission (D&D) one of its facilities using a combination of innovative and commercial D&D technologies. The paper also includes discussions on recent technology demonstrations for an Advanced Worker Protection System, an Electrohydraulic Scabbling System, and a Pipe Explorer{trademark}. The references at the conclusion of this paper should be consulted for more detailed information about the large-scale demonstration projects and recent technology demonstrations sponsored by the DDFA.

  20. Regulatory Reform and License Termination Planning in Decommissioning

    SciTech Connect

    Michael J. Meisner

    2000-06-04

    Decommissioning of commercial nuclear power plants (NPPs) must be safe and cost-effective and consider the needs of a wide range of stakeholders. The creative tension among these objectives has provided opportunities to reform the way these plants are regulated and managed in decommissioning. Enlightened and visionary leaders from the U.S. Nuclear Regulatory Commission (NRC) and industry are seizing these opportunities to create new paradigms for risk-informed regulation; creative stakeholder involvement; and effective, end-state focused, license termination planning.

  1. Jose Cabrera dismantling and decommissioning project

    SciTech Connect

    Ondaro, Manuel

    2013-07-01

    The Jose Cabrera Nuclear Power Plant (NPP) was the first commercial power reactor (Westinghouse 1 loop PWR 510 MWth, 160 MWe) commissioned in Spain and provided the base for future development and training. The reactor construction started in 1963 and it was officially on-line by 1969. The NPP operated from 1969 until 2006 when it became the first reactor to be shut down after completing its operational period. The containment is reinforced concrete with a stainless steel head. In 2010 responsibility for D and D was transferred to Enresa to achieve IAEA level 3 (a green field site available for unrestricted re-uses) by 2017. Of the total of more than 104,000 tons of materials that will be generated during dismantling, it is estimated that only ∼4,000 tons will be radioactive waste, some of which, 40 t are considered as intermediate level long-lived wastes and the rest (3,960 t) will be categorized as VLLW and ILLW. The Project is divided into five phases: Phase 0 - Removal of fuel and preliminary work.. Phase 1 - Preparatory Activities for D and D. complete. Phase 2 - Dismantling of Major Components. Phase 3 - Removal of Auxiliary Installations, Decontamination and Demolition. Phase 4 - Environmental Restoration. Phase 2, is currently ongoing (50% completed). To manage the diverse aspects of decommissioning operations, Enresa uses an internally developed computerized project management tool. The tool, based on knowledge gathered from other Enresa projects, can process operations management, maintenance operations, materials, waste, storage areas, procedures, work permits, operator dose management and records. Enresa considers that communication is important for both internal and external stakeholder relations and can be used to inform, to neutralize negative opinions and attitudes, to remove false expectations and for training. Enresa has created a new multi-purpose area (exhibition/visitor centre) and encourages visits from the public, local schools, local and

  2. Decommissioning Project of Bohunice A1 NPP

    SciTech Connect

    Stubna, M.; Pekar, A.; Moravek, J.; Spirko, M.

    2002-02-26

    1977 to terminate plant operation. The decision on the A1 plant decommissioning was issued in 1979.

  3. 26 CFR 1.468A-5 - Nuclear decommissioning fund qualification requirements; prohibitions against self-dealing...

    Code of Federal Regulations, 2012 CFR

    2012-04-01

    ... taxpayer for decommissioning costs of the nuclear power plant to which the nuclear decommissioning fund... premiums on a policy to pay for the nuclear decommissioning costs of a nuclear power plant. Such term also... decommissioning costs of the nuclear power plant to which the nuclear......

  4. 26 CFR 1.468A-5 - Nuclear decommissioning fund qualification requirements; prohibitions against self-dealing...

    Code of Federal Regulations, 2014 CFR

    2014-04-01

    ... taxpayer for decommissioning costs of the nuclear power plant to which the nuclear decommissioning fund... premiums on a policy to pay for the nuclear decommissioning costs of a nuclear power plant. Such term also... decommissioning costs of the nuclear power plant to which the nuclear......

  5. 26 CFR 1.468A-5 - Nuclear decommissioning fund qualification requirements; prohibitions against self-dealing...

    Code of Federal Regulations, 2011 CFR

    2011-04-01

    ... taxpayer for decommissioning costs of the nuclear power plant to which the nuclear decommissioning fund... premiums on a policy to pay for the nuclear decommissioning costs of a nuclear power plant. Such term also... decommissioning costs of the nuclear power plant to which the nuclear......

  6. 26 CFR 1.468A-5 - Nuclear decommissioning fund qualification requirements; prohibitions against self-dealing...

    Code of Federal Regulations, 2013 CFR

    2013-04-01

    ... taxpayer for decommissioning costs of the nuclear power plant to which the nuclear decommissioning fund... premiums on a policy to pay for the nuclear decommissioning costs of a nuclear power plant. Such term also... decommissioning costs of the nuclear power plant to which the nuclear......

  7. Integration of improved decontamination and characterization technologies in the decommissioning of the CP-5 research reactor

    SciTech Connect

    Bhattacharyya, S. K.; Boing, L. E.

    2000-02-17

    The aging of research reactors worldwide has resulted in a heightened awareness in the international technical decommissioning community of the timeliness to review and address the needs of these research institutes in planning for and eventually performing the decommissioning of these facilities. By using the reactors already undergoing decommissioning as test beds for evaluating enhanced or new/innovative technologies for decommissioning, it is possible that new techniques could be made available for those future research reactor decommissioning projects. Potentially, the new technologies will result in: reduced radiation doses to the work force, larger safety margins in performing decommissioning and cost and schedule savings to the research institutes in performing the decommissioning of these facilities. Testing of these enhanced technologies for decontamination, dismantling, characterization, remote operations and worker protection are critical to furthering advancements in the technical specialty of decommissioning. Furthermore, regulatory acceptance and routine utilization for future research reactor decommissioning will be assured by testing and developing these technologies in realistically contaminated environments prior to use in the research reactors. The decommissioning of the CP-5 Research Reactor is currently in the final phase of dismantlement. In this paper the authors present results of work performed at Argonne National Laboratory (ANL) in the development, testing and deployment of innovative and/or enhanced technologies for the decommissioning of research reactors.

  8. Korea Research Reactor -1 & 2 Decommissioning Project in Korea

    SciTech Connect

    Park, S. K.; Chung, U. S.; Jung, K. J.; Park, J. H.

    2003-02-24

    Korea Research Reactor 1 (KRR-1), the first research reactor in Korea, has been operated since 1962, and the second one, Korea Research Reactor 2 (KRR-2) since 1972. The operation of both of them was phased out in 1995 due to their lifetime and operation of the new and more powerful research reactor, HANARO (High-flux Advanced Neutron Application Reactor; 30MW). Both are TRIGA Pool type reactors in which the cores are small self-contained units sitting in tanks filled with cooling water. The KRR-1 is a TRIGA Mark II, which could operate at a level of up to 250 kW. The second one, the KRR-2 is a TRIGA Mark III, which could operate at a level of up 2,000 kW. The decontamination and decommissioning (D & D) project of these two research reactors, the first D & D project in Korea, was started in January 1997 and will be completed to stage 3 by 2008. The aim of this decommissioning program is to decommission the KRR-1 & 2 reactors and to decontaminate the residual building structure s and the site to release them as unrestricted areas. KAERI (Korea Atomic Energy Research Institute) submitted the decommissioning plan and the environmental impact assessment reports to the Ministry of Science and Technology (MOST) for the license in December 1998, and was approved in November 2000.

  9. 10 CFR 72.130 - Criteria for decommissioning.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Criteria for decommissioning. 72.130 Section 72.130 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER THAN CLASS C WASTE General...

  10. 77 FR 8751 - Guidance for Decommissioning Planning During Operations

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-02-15

    ... Planning During Operations AGENCY: Nuclear Regulatory Commission. ACTION: Draft regulatory guide; re... Commission (NRC) re-issued Draft Regulatory Guide, DG-4014, ``Decommissioning Planning During Operations'' in... Planning Rule. DATES: Submit comments by March 30, 2012. Comments received after this date will...

  11. 18 CFR 2.24 - Project decommissioning at relicensing.

    Code of Federal Regulations, 2012 CFR

    2012-04-01

    ... 18 Conservation of Power and Water Resources 1 2012-04-01 2012-04-01 false Project decommissioning at relicensing. 2.24 Section 2.24 Conservation of Power and Water Resources FEDERAL ENERGY REGULATORY COMMISSION, DEPARTMENT OF ENERGY GENERAL RULES GENERAL POLICY AND INTERPRETATIONS Statements of...

  12. 18 CFR 2.24 - Project decommissioning at relicensing.

    Code of Federal Regulations, 2013 CFR

    2013-04-01

    ... 18 Conservation of Power and Water Resources 1 2013-04-01 2013-04-01 false Project decommissioning at relicensing. 2.24 Section 2.24 Conservation of Power and Water Resources FEDERAL ENERGY REGULATORY COMMISSION, DEPARTMENT OF ENERGY GENERAL RULES GENERAL POLICY AND INTERPRETATIONS Statements of...

  13. 18 CFR 2.24 - Project decommissioning at relicensing.

    Code of Federal Regulations, 2010 CFR

    2010-04-01

    ... 18 Conservation of Power and Water Resources 1 2010-04-01 2010-04-01 false Project decommissioning at relicensing. 2.24 Section 2.24 Conservation of Power and Water Resources FEDERAL ENERGY REGULATORY COMMISSION, DEPARTMENT OF ENERGY GENERAL RULES GENERAL POLICY AND INTERPRETATIONS Statements of...

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

    SciTech Connect

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

    1996-01-01

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

  15. Decommissioning of the BR3 reactor: status and perspectives

    SciTech Connect

    Noynaert, L.; Verstraeten, I.

    2007-07-01

    The BR3 plant at Mol in Belgium built at the end of the fifties was the first PWR plant built outside the USA. The reactor had a small net power output (10 MWe) but comprised all the loops and features of a commercial PWR plant. The BR3 plant was operated with the main objective of testing advanced PWR fuels under irradiation conditions similar to those encountered in large commercial PWR plants. The reactor was started in 1962 and shut down in 1987 after 25 years of continuous operation. Since 1989, SCK.CEN is decommissioning the BR3 PWR research reactor. The dismantling of the metallic components including reactor pressure vessel and internals is completed and extensively reported in the literature. The dismantling of auxiliary components and the decontamination of parts of the infrastructure are now going on. The decommissioning progress is continuously monitored and costs and strategy are regularly reassessed. The first part of the paper describes the main results and lessons learned from the reassessment exercises performed in 1994, 1999, 2004 and 2007. Impacts of changes in legal framework on the decommissioning costs will be addressed. These changes concern e.g. licensing aspects, clearance levels, waste management... The middle part of the paper discusses the management of activated and/or contaminated concrete. The costing exercise performed in 1995 highlighted that the management of activated and contaminated concrete is the second main cost item after the dismantling of the reactor pressure vessel and internals. Different possible solutions were studied. These are evacuation as radioactive waste with or without supercompaction, recycling this 'radioactive' grout or concrete for conditioning of radioactive waste e.g. conditioning of metallic waste. The paper will give the results of the cost-benefit analysis made to select the solution retained. The last part of the paper will discuss the end goal of the decommissioning of the BR3. In the final

  16. Decommissioning of U.S. uranium production facilities

    SciTech Connect

    Not Available

    1995-02-01

    From 1980 to 1993, the domestic production of uranium declined from almost 44 million pounds U{sub 3}O{sub 8} to about 3 million pounds. This retrenchment of the U.S. uranium industry resulted in the permanent closing of many uranium-producing facilities. Current low uranium prices, excess world supply, and low expectations for future uranium demand indicate that it is unlikely existing plants will be reopened. Because of this situation, these facilities eventually will have to be decommissioned. The Uranium Mill Tailings and Radiation Control Act of 1978 (UMTRCA) vests the U.S. Environmental Protection Agency (EPA) with overall responsibility for establishing environmental standards for decommissioning of uranium production facilities. UMTRCA also gave the U.S. Nuclear Regulatory Commission (NRC) the responsibility for licensing and regulating uranium production and related activities, including decommissioning. Because there are many issues associated with decommissioning-environmental, political, and financial-this report will concentrate on the answers to three questions: (1) What is required? (2) How is the process implemented? (3) What are the costs? Regulatory control is exercised principally through the NRC licensing process. Before receiving a license to construct and operate an uranium producing facility, the applicant is required to present a decommissioning plan to the NRC. Once the plan is approved, the licensee must post a surety to guarantee that funds will be available to execute the plan and reclaim the site. This report by the Energy Information Administration (EIA) represents the most comprehensive study on this topic by analyzing data on 33 (out of 43) uranium production facilities located in Colorado, Nebraska, New Mexico, South Dakota, Texas, Utah, and Washington.

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

    SciTech Connect

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

    1997-08-01

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

  18. How utilities can achieve more accurate decommissioning cost estimates

    SciTech Connect

    Knight, R.

    1999-07-01

    The number of commercial nuclear power plants that are undergoing decommissioning coupled with the economic pressure of deregulation has increased the focus on adequate funding for decommissioning. The introduction of spent-fuel storage and disposal of low-level radioactive waste into the cost analysis places even greater concern as to the accuracy of the fund calculation basis. The size and adequacy of the decommissioning fund have also played a major part in the negotiations for transfer of plant ownership. For all of these reasons, it is important that the operating plant owner reduce the margin of error in the preparation of decommissioning cost estimates. To data, all of these estimates have been prepared via the building block method. That is, numerous individual calculations defining the planning, engineering, removal, and disposal of plant systems and structures are performed. These activity costs are supplemented by the period-dependent costs reflecting the administration, control, licensing, and permitting of the program. This method will continue to be used in the foreseeable future until adequate performance data are available. The accuracy of the activity cost calculation is directly related to the accuracy of the inventory of plant system component, piping and equipment, and plant structural composition. Typically, it is left up to the cost-estimating contractor to develop this plant inventory. The data are generated by searching and analyzing property asset records, plant databases, piping and instrumentation drawings, piping system isometric drawings, and component assembly drawings. However, experience has shown that these sources may not be up to date, discrepancies may exist, there may be missing data, and the level of detail may not be sufficient. Again, typically, the time constraints associated with the development of the cost estimate preclude perfect resolution of the inventory questions. Another problem area in achieving accurate cost

  19. Carbon-14 bioassay for decommissioning of Hanford reactors.

    PubMed

    Carbaugh, Eugene H; Watson, David J

    2012-05-01

    The production reactors at the U.S. Department of Energy Hanford Site used large graphite piles as the moderator. As part of long-term decommissioning plans, the potential need for ¹⁴C radiobioassay of workers was identified. Technical issues associated with ¹⁴C bioassay and worker monitoring were investigated, including anticipated graphite characterization, potential intake scenarios, and the bioassay capabilities that may be required to support the decommissioning of the graphite piles. A combination of urine and feces sampling would likely be required for the absorption type S ¹⁴C anticipated to be encountered. However, the concentrations in the graphite piles appear to be sufficiently low that dosimetrically significant intakes of ¹⁴C are not credible, thus rendering moot the need for such bioassay.

  20. Decontamination and Decommissioning activities photobriefing book FY 1997

    SciTech Connect

    1998-04-01

    The Decontamination and Decommissioning (D and D) Program at Argonne National Laboratory-East (ANL-E) is dedicated to the safe and cost effective D{ampersand}D of surplus nuclear facilities. There is currently a backlog of more than 7,000 contaminated US Department of Energy facilities nationwide. Added to this are 110 licensed commercial nuclear power reactors operated by utilities learning to cope with deregulation and an aging infrastructure that supports the commercial nuclear power industry, as well as medical and other uses of radioactive materials. With this volume it becomes easy to understand the importance of addressing the unique issues and objectives associated with the D{ampersand}D of surplus nuclear facilities. This photobriefing book summarizes the decontamination and decommissioning projects and activities either completed or continuing at the ANL-E site during the year.

  1. Carbon-14 Bioassay for Decommissioning of Hanford Reactors

    SciTech Connect

    Carbaugh, Eugene H.; Watson, David J.

    2012-05-01

    The old production reactors at the US Department of Energy Hanford Site used large graphite piles as the moderator. As part of long-term decommissioning plans, the potential need for 14C radiobioassay of workers was identified. Technical issues associated with 14C bioassay and worker monitoring were investigated, including anticipated graphite characterization, potential intake scenarios, and the bioassay capabilities that may be required to support the decommissioning of the graphite piles. A combination of urine and feces sampling would likely be required for the absorption type S 14C anticipated to be encountered. However the concentrations in the graphite piles appear to be sufficiently low that dosimetrically significant intakes of 14C are not credible, thus rendering moot the need for such bioassay.

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

    SciTech Connect

    Cantor, R.

    1986-08-01

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

  3. Reducing environmental risk associated with laboratory decommissioning and property transfer.

    PubMed

    Dufault, R; Abelquist, E; Crooks, S; Demers, D; DiBerardinis, L; Franklin, T; Horowitz, M; Petullo, C; Sturchio, G

    2000-12-01

    The need for more or less space is a common laboratory problem. Solutions may include renovating existing space, leaving or demolishing old space, or acquiring new space or property for building. All of these options carry potential environmental risk. Such risk can be the result of activities related to the laboratory facility or property (e.g., asbestos, underground storage tanks, lead paint), or the research associated with it (e.g., radioactive, microbiological, and chemical contamination). Regardless of the option chosen to solve the space problem, the potential environmental risk must be mitigated and the laboratory space and/or property must be decommissioned or rendered safe prior to any renovation, demolition, or property transfer activities. Not mitigating the environmental risk through a decommissioning process can incur significant financial liability for any costs associated with future decommissioning cleanup activities. Out of necessity, a functioning system, environmental due diligence auditing, has evolved over time to assess environmental risk and reduce associated financial liability. This system involves a 4-phase approach to identify, document, manage, and clean up areas of environmental concern or liability, including contamination. Environmental due diligence auditing includes a) historical site assessment, b) characterization assessment, c) remedial effort and d) final status survey. General practice standards from the American Society for Testing and Materials are available for conducting the first two phases. However, standards have not yet been developed for conducting the third and final phases of the environmental due diligence auditing process. Individuals involved in laboratory decommissioning work in the biomedical research industry consider this a key weakness.

  4. TECHNOLOGY REQUIREMENTS FOR IN SITU DECOMMISSIONING WORKSHOP REPORT

    SciTech Connect

    Jannik, T.; Lee, P.; Gladden, J.; Langton, C.; Serrato, M.; Urland, C.; Reynolds, E.

    2009-06-30

    In recognition of the increasing attention being focused on In Situ Decommissioning (ISD or entombment) as an acceptable and beneficial decommissioning end state, the Department of Energy's (DOE) Office of Environmental Management (EM) is developing guidance for the implementation of ISD of excess facilities within the DOE complex. Consistent with the overarching DOE goals for increased personnel and environmental safety, reduced technical uncertainties and risks, and overall gains in efficiencies and effectiveness, EM's Office of Deactivation and Decommissioning and Facility Engineering (EM-23) initiated efforts to identify the technical barriers and technology development needs for the optimal implementation of ISD. Savannah River National Laboratory (SRNL), as the EM Corporate Laboratory, conducted an ISD Technology Needs Workshop to identify the technology needs at DOE sites. The overall goal of the workshop was to gain a full understanding of the specific ISD technical challenges, the technologies available, and those needing development. The ISD Workshop was held December 9-10, 2008 in Aiken, SC. Experienced decommissioning operations personnel from Richland Operations Office (RL), Idaho National Laboratory (INL) and Savannah River Site (SRS) along with scientists and engineers specific expertise were assembled to identify incremental and 'game changing' solutions to ISD technology challenges. The workshop and follow-up activities yielded 14 technology needs statements and the recommendation that EM-23 prioritize and pursue the following specific technology development and deployment actions. For each action, the recommended technology acquisition mechanisms (competitive solicitation (CS) or direct funding (TCR)) are provided. Activities that are time critical for ISD projects, or require unique capabilities that reside in the DOE Laboratory system will be funded directly to those institutions. Activities that have longer lead times and where the private

  5. Reducing environmental risk associated with laboratory decommissioning and property transfer.

    PubMed Central

    Dufault, R; Abelquist, E; Crooks, S; Demers, D; DiBerardinis, L; Franklin, T; Horowitz, M; Petullo, C; Sturchio, G

    2000-01-01

    The need for more or less space is a common laboratory problem. Solutions may include renovating existing space, leaving or demolishing old space, or acquiring new space or property for building. All of these options carry potential environmental risk. Such risk can be the result of activities related to the laboratory facility or property (e.g., asbestos, underground storage tanks, lead paint), or the research associated with it (e.g., radioactive, microbiological, and chemical contamination). Regardless of the option chosen to solve the space problem, the potential environmental risk must be mitigated and the laboratory space and/or property must be decommissioned or rendered safe prior to any renovation, demolition, or property transfer activities. Not mitigating the environmental risk through a decommissioning process can incur significant financial liability for any costs associated with future decommissioning cleanup activities. Out of necessity, a functioning system, environmental due diligence auditing, has evolved over time to assess environmental risk and reduce associated financial liability. This system involves a 4-phase approach to identify, document, manage, and clean up areas of environmental concern or liability, including contamination. Environmental due diligence auditing includes a) historical site assessment, b) characterization assessment, c) remedial effort and d) final status survey. General practice standards from the American Society for Testing and Materials are available for conducting the first two phases. However, standards have not yet been developed for conducting the third and final phases of the environmental due diligence auditing process. Individuals involved in laboratory decommissioning work in the biomedical research industry consider this a key weakness. PMID:11121365

  6. Decontamination and decommissioning of the Mayaguez (Puerto Rico) facility

    SciTech Connect

    Jackson, P.K.; Freemerman, R.L.

    1989-11-01

    On February 6, 1987 the US Department of Energy (DOE) awarded the final phase of the decontamination and decommissioning of the nuclear and reactor facilities at the Center for Energy and Environmental Research (CEER), in Mayaguez, Puerto Rico. Bechtel National, Inc., was made the decontamination and decommissioning (D and D) contractor. The goal of the project was to enable DOE to proceed with release of the CEER facility for use by the University of Puerto Rico, who was the operator. This presentation describes that project and lesson learned during its progress. The CEER facility was established in 1957 as the Puerto Rico Nuclear Center, a part of the Atoms for Peace Program. It was a nuclear training and research institution with emphasis on the needs of Latin America. It originally consisted of a 1-megawatt Materials Testing Reactor (MTR), support facilities and research laboratories. After eleven years of operation the MTR was shutdown and defueled. A 2-megawatt TRIGA reactor was installed in 1972 and operated until 1976, when it woo was shutdown. Other radioactive facilities at the center included a 10-watt homogeneous L-77 training reactor, a natural uranium graphite-moderated subcritical assembly, a 200KV particle accelerator, and a 15,000 Ci Co-60 irradiation facility. Support facilities included radiochemistry laboratories, counting rooms and two hot cells. As the emphasis shifted to non-nuclear energy technology a name change resulted in the CEER designation, and plans were started for the decontamination and decommissioning effort.

  7. A NOVEL APPROACH TO SPENT FUEL POOL DECOMMISSIONING

    SciTech Connect

    R. L. Demmer

    2011-04-01

    The Idaho National Laboratory (INL) has been at the forefront of developing methods to reduce the cost and schedule of deactivating spent fuel pools (SFP). Several pools have been deactivated at the INL using an underwater approach with divers. These projects provided a basis for the INL cooperation with the Dresden Nuclear Power Station Unit 1 SFP (Exelon Generation Company) deactivation. It represents the first time that a commercial nuclear power plant (NPP) SFP was decommissioned using this underwater coating process. This approach has advantages in many aspects, particularly in reducing airborne contamination and allowing safer, more cost effective deactivation. The INL pioneered underwater coating process was used to decommission three SFPs with a total combined pool volume of over 900,000 gallons. INL provided engineering support and shared project plans to successfully initiate the Dresden project. This report outlines the steps taken by INL and Exelon to decommission SFPs using the underwater coating process. The rationale used to select the underwater coating process and the advantages and disadvantages are described. Special circumstances are also discussed, such as the use of a remotely-operated underwater vehicle to visually and radiologically map the pool areas that were not readily accessible. A larger project, the INTEC-603 SFP in-situ (grouting) deactivation, is reviewed. Several specific areas where special equipment was employed are discussed and a Lessons Learned evaluation is included.

  8. Evaluating alternatives for decommissioning California's offshore oil and gas platforms.

    PubMed

    Bernstein, Brock B

    2015-10-01

    This paper introduces a series of 6 additional papers in this issue that describe an in-depth analysis of options for decommissioning oil and gas platforms offshore southern California. Although current leases require lessees in both state and federal waters to completely remove all production facilities and restore the seafloor to its pre-platform condition, other options have emerged since these leases were signed. Laws and regulations in other jurisdictions (particularly in federal waters) have evolved to allow a number of other uses such as aquaculture, alternative energy production, and artificial reefing. In response, the California Natural Resources Agency initiated an effort to investigate the issues associated with these and other decommissioning alternatives. The papers in this series are the result of the second phase in this process, a broad investigation of the engineering, economic, and environmental costs and benefits of the most feasible and likely options. In addition to the project's final report, the authors produced an interactive mathematical decision model, PLATFORM, that enables users to explore the implications of different decommissioning projects and options, as well as the effects of different approaches to valuing the associated costs and benefits.

  9. Aroma potential of oak battens prepared from decommissioned oak barrels.

    PubMed

    Li, Sijing; Crump, Anna M; Grbin, Paul R; Cozzolino, Daniel; Warren, Peter; Hayasaka, Yoji; Wilkinson, Kerry L

    2015-04-08

    During barrel maturation, volatile compounds are extracted from oak wood and impart aroma and flavor to wine, enhancing its character and complexity. However, barrels contain a finite pool of extractable material, which diminishes with time. As a consequence, most barrels are decommissioned after 5 or 6 years. This study investigated whether or not decommissioned barrels can be "reclaimed" and utilized as a previously untapped source of quality oak for wine maturation. Oak battens were prepared from staves of decommissioned French and American oak barrels, and their composition analyzed before and after toasting. The oak lactone glycoconjugate content of untoasted reclaimed oak was determined by liquid chromatography-tandem mass spectrometry, while the concentrations of cis- and trans-oak lactone, guaiacol, 4-methlyguaiacol, vanillin, eugenol, furfural, and 5-methylfurfural present in toasted reclaimed oak were determined by gas chromatography-mass spectrometry. Aroma potential was then evaluated by comparing the composition of reclaimed oak with that of new oak. Comparable levels of oak lactone glycoconjugates and oak volatiles were observed, demonstrating the aroma potential of reclaimed oak and therefore its suitability as a raw material for alternative oak products, i.e., chips or battens, for the maturation of wine. The temperature profiles achieved during toasting were also measured to evaluate the viability of any yeast or bacteria present in reclaimed oak.

  10. Decontamination and decommissioning surveillance and maintenance report for FY 1991

    SciTech Connect

    Gunter, David B.; Burwinkle, T. W.; Cannon, T. R.; Ford, M. K.; Holder, Jr., L.; Clotfelter, O. K.; Faulkner, R. L.; Smith, D. L.; Wooten, H. O.

    1991-12-01

    The Decontamination and Decommissioning (D D) Program has three distinct phases: (1) surveillance and maintenance (S M); (2) decontamination and removal of hazardous materials and equipment (which DOE Headquarters in Washington, D.C., calls Phase I of remediation); and (3) decommissioning and ultimate disposal, regulatory compliance monitoring, and property transfer (which DOE Headquarters calls Phase II of remediation). A large part of D D is devoted to S M at each of the sites. Our S M activities, which are performed on facilities awaiting decommissioning, are designed to minimize potential hazards to human health and the environment by: ensuring adequate containment of residual radioactive and hazardous materials; and, providing physical safety and security controls to minimize potential hazards to on-site personnel and the general public. Typically, we classify maintenance activities as either routine or special (major repairs). Routine maintenance includes such activities as painting, cleaning, vegetation control, minor structural repairs, filter changes, and building system(s) checks. Special maintenance includes Occupational Safety and Health Act facility upgrades, roof repairs, and equipment overhaul. Surveillance activities include inspections, radiological measurements, reporting, records maintenance, and security (as required) for controlling and monitoring access to facilities. This report summarizes out FY 1991 S M activities for the Tennessee plant sites, which include the K-25 Site, the Gas Centrifuge facilities, ORNL, and the Y-12 Plant.

  11. Radioactive waste from decommissioning of fast reactors (through the example of BN-800)

    NASA Astrophysics Data System (ADS)

    Rybin, A. A.; Momot, O. A.

    2017-01-01

    Estimation of volume of radioactive waste from operating and decommissioning of fast reactors is introduced. Preliminary estimation has shown that the volume of RW from decommissioning of BN-800 is amounted to 63,000 cu. m. Comparison of the amount of liquid radioactive waste derived from operation of different reactor types is performed. Approximate costs of all wastes disposal for complete decommissioning of BN-800 reactor are estimated amounting up to approx. 145 million.

  12. The Regulatory Challenges of Decommissioning Nuclear Power Plants in Korea - 13101

    SciTech Connect

    Lee, Jungjoon; Ahn, Sangmyeon; Choi, Kyungwoo; Kim, Juyoul; Kim, Juyub

    2013-07-01

    As of 2012, 23 units of nuclear power plants are in operation, but there is no experience of permanent shutdown and decommissioning of nuclear power plant in Korea. It is realized that, since late 1990's, improvement of the regulatory framework for decommissioning has been emphasized constantly from the point of view of International Atomic Energy Agency (IAEA)'s safety standards. And it is known that now IAEA prepare the safety requirement on decommissioning of facilities, its title is the Safe Decommissioning of Facilities, General Safety Requirement Part 6. According to the result of IAEA's Integrated Regulatory Review Service (IRRS) mission to Korea in 2011, it was recommended that the regulatory framework for decommissioning should require decommissioning plans for nuclear installations to be constructed and operated and these plans should be updated periodically. In addition, after the Fukushima nuclear disaster in Japan in March of 2011, preparedness for early decommissioning caused by an unexpected severe accident became also important issues and concerns. In this respect, it is acknowledged that the regulatory framework for decommissioning of nuclear facilities in Korea need to be improved. First of all, we identify the current status and relevant issues of regulatory framework for decommissioning of nuclear power plants compared to the IAEA's safety standards in order to achieve our goal. And then the plan is to be established for improvement of regulatory framework for decommissioning of nuclear power plants in Korea. After dealing with it, it is expected that the revised regulatory framework for decommissioning could enhance the safety regime on the decommissioning of nuclear power plants in Korea in light of international standards. (authors)

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

    SciTech Connect

    Sangmyeon Ahn; Jungjoon Lee; Chanwoo Jeong; Kyungwoo Choi

    2013-07-01

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

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

    SciTech Connect

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

    1980-06-01

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

  15. A Plutonium Finishing Plant Model for the Cercla Removal Action and Decommissioning Construction Final Report

    SciTech Connect

    Hopkins, A.

    2008-07-01

    The joint policy between the U.S. Environmental Protection Agency (EPA) and the U.S. Department of Energy (DOE) for decommissioning buildings at DOE facilities documents an agreement between the agencies to perform decommissioning activities including demolition under the Comprehensive Environmental Response Compensation and Liability Act (CERCLA). The use of removal actions for decommissioning integrates EPA oversight authority, DOE lead agency responsibility, and state authority for decommissioning activities. Once removal actions have been performed under CERCLA, a construction completion report is required to document the completion of the required action. Additionally, a decommissioning report is required under DOE guidance. No direct guidance was found for documenting completion of decommissioning activities and preparing a final report that satisfies the CERCLA requirements and the DOE requirements for decommissioning. Additional guidance was needed for the documentation of construction completion under CERCLA for D and D projects undertaken under the joint policy that addresses the requirements of both agencies. A model for the construction completion report was developed to document construction completion for CERCLA D and D activities performed under the joint EPA/DOE policy at the Plutonium Finishing Plant (PFP). The model documentation report developed at PFP integrates the DOE requirements for establishing decommissioning end-points, documenting end-point completion and preparing a final decommissioning report with the CERCLA requirements to document completion of the action identified in the Action Memorandum (AM). The model includes the required information on health and safety, data management, cost and schedule and end-points completion. (authors)

  16. Evaluation of nuclear facility decommissioning projects: summary report. Plum Brook Reactor Facility

    SciTech Connect

    Doerge, D.H.; Miller, R.L.

    1984-02-01

    This document summarizes information concerning the decommissioning of the Plum Brook Reactor Facility, which was placed in a Nuclear Regulatory Commission (NRC) approved safe storage configuration. The data were placed in a computerized information retrieval/manipulation system which permits future utilization of this information in decommissioning of similar facilities. The information is presented both in computer output form and a manually assembled summarization. Complete cost data were not readily available and decommissioning activities did not in all cases conform with current criteria for the SAFSTOR decommissioning mode, therefore no cost comparisons were made.

  17. DECOMMISSIONING THE PHYSICS LABORATORY, BUILDING 777-10A, AT THE SAVANNAH RIVER SITE (SRS)

    SciTech Connect

    Musall, J; Cathy Sizemore, C

    2007-01-17

    SRS recently completed a four-year mission to decommission {approx}250 excess facilities. As part of that effort, SRS decommissioned a 48,000 ft{sup 2} laboratory that housed four low-power test reactors, formerly used by SRS to determine reactor physics. This paper describes and reviews the decommissioning, with a focus on component segmentation and handling (i.e. hazardous material removal, demolition, and waste handling). The paper is intended to be a resource for engineers, planners, and project managers who face similar decommissioning challenges.

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

    SciTech Connect

    Murphy, E.S.

    1984-09-01

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

  19. Technology, safety and costs of decommissioning a reference boiling water reactor power station. Classification of decommissioning wastes. Addendum 2

    SciTech Connect

    Murphy, E.S.

    1984-09-01

    The radioactive wastes expected to result from decommissioning of the reference boiling water reactor power station are reviewed and classified in accordance with 10 CFR 61. The 18,949 cubic meters of waste from DECON are classified as follows: Class A, 97.5%; Class B, 2.0%; Class C, 0.3%. About 0.2% (47 cubic meters) of the waste would be generally unacceptable for disposal using near-surface disposal methods.

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

    SciTech Connect

    Konzek, G.J.

    1983-07-01

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

  1. Heavy Water Components Test Reactor Decommissioning - Major Component Removal

    SciTech Connect

    Austin, W.; Brinkley, D.

    2010-05-05

    The Heavy Water Components Test Reactor (HWCTR) facility (Figure 1) 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 facility is on high, well-drained ground, about 30 meters above the water table. The HWCTR was a pressurized heavy water test reactor used to develop candidate fuel designs for heavy water power reactors. It was not a defense-related facility like the materials production reactors at SRS. The reactor was moderated with heavy water and was rated at 50 megawatts thermal power. 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 1965, fuel assemblies were removed, systems that contained heavy water were drained, fluid piping systems were drained, deenergized and disconnected and the spent fuel basin was drained and dried. The doors of the reactor facility were shut and it wasn't until 10 years later that decommissioning plans were considered and ultimately postponed due to budget constraints. In the early 1990s, DOE began planning to decommission HWCTR again. 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. The $1.6 billion allocation from the American Recovery and Reinvestment Act to SRS for site clean up at SRS has opened the doors to the HWCTR again - this time for final decommissioning. During the lifetime of HWCTR, 36 different fuel assemblies were tested in the facility. Ten of these

  2. 76 FR 3540 - Proposed Generic Communications Reporting for Decommissioning Funding Status Reports

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-01-20

    ... Funding Status Reports AGENCY: Nuclear Regulatory Commission. ACTION: Proposed generic communication... information that they should use and present to the NRC in the Decommissioning Funding Status reports to... . The Draft Regulatory Issue Summary 2010-XXX, ``10 CFR 50-75, Reporting for Decommissioning...

  3. 76 FR 65541 - Assuring the Availability of Funds for Decommissioning Nuclear Reactors

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-10-21

    ... COMMISSION Assuring the Availability of Funds for Decommissioning Nuclear Reactors AGENCY: Nuclear Regulatory... Decommissioning Nuclear Reactors.'' This guide provides guidance to applicants and licensees of nuclear power, research, and test reactors concerning methods acceptable to the staff of the U.S. Nuclear...

  4. 26 CFR 1.468A-0 - Nuclear decommissioning costs; table of contents.

    Code of Federal Regulations, 2013 CFR

    2013-04-01

    ... 26 Internal Revenue 6 2013-04-01 2013-04-01 false Nuclear decommissioning costs; table of contents...-0 Nuclear decommissioning costs; table of contents. This section lists the paragraphs contained in.... (b) Definitions. (c) Special rules applicable to certain experimental nuclear facilities. §...

  5. 26 CFR 1.468A-0 - Nuclear decommissioning costs; table of contents.

    Code of Federal Regulations, 2014 CFR

    2014-04-01

    ... 26 Internal Revenue 6 2014-04-01 2014-04-01 false Nuclear decommissioning costs; table of contents...-0 Nuclear decommissioning costs; table of contents. This section lists the paragraphs contained in.... (b) Definitions. (c) Special rules applicable to certain experimental nuclear facilities. §...

  6. 26 CFR 1.468A-0 - Nuclear decommissioning costs; table of contents.

    Code of Federal Regulations, 2011 CFR

    2011-04-01

    ... 26 Internal Revenue 6 2011-04-01 2011-04-01 false Nuclear decommissioning costs; table of contents...-0 Nuclear decommissioning costs; table of contents. This section lists the paragraphs contained in.... (b) Definitions. (c) Special rules applicable to certain experimental nuclear facilities. §...

  7. 26 CFR 1.468A-0 - Nuclear decommissioning costs; table of contents.

    Code of Federal Regulations, 2012 CFR

    2012-04-01

    ... 26 Internal Revenue 6 2012-04-01 2012-04-01 false Nuclear decommissioning costs; table of contents...-0 Nuclear decommissioning costs; table of contents. This section lists the paragraphs contained in.... (b) Definitions. (c) Special rules applicable to certain experimental nuclear facilities. §...

  8. 30 CFR 585.907 - How will BOEM process my decommissioning application?

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... decommissioning application with the decommissioning general concept in your approved SAP, COP, or GAP to determine what technical and environmental reviews are needed. (b) You will likely have to revise your SAP... change in the impacts previously identified and evaluated in your SAP, COP, or GAP; (2) Require...

  9. 30 CFR 285.907 - How will MMS process my decommissioning application?

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... compare your decommissioning application with the decommissioning general concept in your approved SAP... to revise your SAP, COP, or GAP, and MMS will begin the appropriate NEPA analysis and other... a significant change in the impacts previously identified and evaluated in your SAP, COP, or GAP;...

  10. 30 CFR 585.907 - How will BOEM process my decommissioning application?

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... decommissioning application with the decommissioning general concept in your approved SAP, COP, or GAP to determine what technical and environmental reviews are needed. (b) You will likely have to revise your SAP... change in the impacts previously identified and evaluated in your SAP, COP, or GAP; (2) Require...

  11. 30 CFR 585.907 - How will BOEM process my decommissioning application?

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... Environmental and Safety Management, Inspections, and Facility Assessments for Activities Conducted Under SAPs... your decommissioning application with the decommissioning general concept in your approved SAP, COP, or... revise your SAP, COP, or GAP, and BOEM will begin the appropriate NEPA analysis and other...

  12. 10 CFR 50.75 - Reporting and recordkeeping for decommissioning planning.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... funds accumulated to the end of the calendar year preceding the date of the report; a schedule of the... of decommissioning funds accumulated to the end of the calendar year preceding the date of the report... provide reasonable assurance that funds will be available for the decommissioning process. For...

  13. 30 CFR 550.255 - What decommissioning information must accompany the DPP or DOCD?

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... 30 Mineral Resources 2 2014-07-01 2014-07-01 false What decommissioning information must accompany the DPP or DOCD? 550.255 Section 550.255 Mineral Resources BUREAU OF OCEAN ENERGY MANAGEMENT... brief description of how you intend to decommission your wells, platforms, pipelines, and...

  14. 30 CFR 550.255 - What decommissioning information must accompany the DPP or DOCD?

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... 30 Mineral Resources 2 2012-07-01 2012-07-01 false What decommissioning information must accompany the DPP or DOCD? 550.255 Section 550.255 Mineral Resources BUREAU OF OCEAN ENERGY MANAGEMENT... brief description of how you intend to decommission your wells, platforms, pipelines, and...

  15. 30 CFR 550.255 - What decommissioning information must accompany the DPP or DOCD?

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... 30 Mineral Resources 2 2013-07-01 2013-07-01 false What decommissioning information must accompany the DPP or DOCD? 550.255 Section 550.255 Mineral Resources BUREAU OF OCEAN ENERGY MANAGEMENT... brief description of how you intend to decommission your wells, platforms, pipelines, and...

  16. SAVANNAH RIVER SITE R REACTOR DISASSEMBLY BASIN IN SITU DECOMMISSIONING

    SciTech Connect

    Langton, C.; Blankenship, J.; Griffin, W.; Serrato, M.

    2009-12-03

    The US DOE concept for facility in-situ decommissioning (ISD) is to physically stabilize and isolate in tact, structurally sound facilities that are no longer needed for their original purpose of, i.e., generating (reactor facilities), processing(isotope separation facilities) or storing radioactive materials. The 105-R Disassembly Basin is the first SRS reactor facility to undergo the in-situ decommissioning (ISD) process. This ISD process complies with the105-R Disassembly Basin project strategy as outlined in the Engineering Evaluation/Cost Analysis for the Grouting of the R-Reactor Disassembly Basin at the Savannah River Site and includes: (1) Managing residual water by solidification in-place or evaporation at another facility; (2) Filling the below grade portion of the basin with cementitious materials to physically stabilize the basin and prevent collapse of the final cap - Sludge and debris in the bottom few feet of the basin will be encapsulated between the basin floor and overlying fill material to isolate if from the environment; (3) Demolishing the above grade portion of the structure and relocating the resulting debris to another location or disposing of the debris in-place; and (4) Capping the basin area with a concrete slab which is part of an engineered cap to prevent inadvertent intrusion. The estimated total grout volume to fill the 105-R Reactor Disassembly Basin is 24,424 cubic meters or 31,945 cubic yards. Portland cement-based structural fill materials were design and tested for the reactor ISD project and a placement strategy for stabilizing the basin was developed. Based on structural engineering analyses and work flow considerations, the recommended maximum lift height is 5 feet with 24 hours between lifts. Pertinent data and information related to the SRS 105-R-Reactor Disassembly Basin in-situ decommissioning include: regulatory documentation, residual water management, area preparation activities, technology needs, fill material designs

  17. HLRW management during MR reactor decommissioning in NRC 'Kurchatov Institute'

    SciTech Connect

    Chesnokov, Alexander; Ivanov, Oleg; Kolyadin, Vyacheslav; Lemus, Alexey; Pavlenko, Vitaly; Semenov, Sergey; Stepanov, Vyacheslav; Smirnov, Sergey; Potapov, Victor; Fadin, Sergey; Volkov, Victor; Shisha, Anatoly

    2013-07-01

    A program of decommissioning of MR research reactor in the Kurchatov institute started in 2008. The decommissioning work presumed a preliminary stage, which included: removal of spent fuel from near reactor storage; removal of spent fuel assemble of metal liquid loop channel from a core; identification, sorting and disposal of radioactive objects from gateway of the reactor; identification, sorting and disposal of radioactive objects from cells of HLRW storage of the Kurchatov institute for radwaste creating form the decommissioning of MR. All these works were performed by a remote controlled means with use of a remote identification methods of high radioactive objects. A distribution of activity along high radiated objects was measured by a collimated radiometer installed on the robot Brokk-90, a gamma image of the object was registered by gamma-visor. Spectrum of gamma radiation was measured by a gamma locator and semiconductor detector system. For identification of a presence of uranium isotopes in the HLRW a technique, based on the registration of characteristic radiation of U, was developed. For fragmentation of high radiated objects was used a cold cutting technique and dust suppression system was applied for reduction of volume activity of aerosols in air. The management of HLRW was performed by remote controlled robots Brokk-180 and Brokk-330. They executed sorting, cutting and parking of high radiated part of contaminated equipment. The use of these techniques allowed to reduce individual and collective doses of personal performed the decommissioning. The average individual dose of the personnel was 1,9 mSv/year in 2011, and the collective dose is estimated by 0,0605 man x Sv/year. Use of the remote control machines enables reducing the number of working personal (20 men) and doses. X-ray spectrometric methods enable determination of a presence of the U in high radiated objects and special cans and separation of them for further spent fuel inspection. The

  18. Waste management for Shippingport Station Decommissioning Project: Extended summary

    SciTech Connect

    Mullee, G.R.; Schulmeister, A.R.

    1987-01-01

    The Shippingport Station (SSDP) is demonstrating that the techniques and methodologies of waste management, which are currently employed by the nuclear industry, provide adequate management and control of waste activities for the decommissioning of a large scale nuclear plant. The SSDP has some unique aspects in that as part of the objective to promote technology transfer, multiple subcontractors are being utilized in the project. The interfaces resulting from multiple subcontractors require additional controls. Effective control has been accomplished by the use of a process control and inventory system, coupled with personnel training in waste management activities. This report summarizes the waste management plan and provides a status of waste management activities for SSDP.

  19. Remote machine engineering applications for nuclear facilities decommissioning

    SciTech Connect

    Toto, G.; Wyle, H.R.

    1983-01-01

    Decontamination and decommissioning of a nuclear facility require the application of techniques that protect the worker and the enviroment from radiological contamination and radiation. Remotely operated portable robotic arms, machines, and devices can be applied. The use of advanced systems should enhance the productivity, safety, and cost facets of the efforts; remote automatic tooling and systems may be used on any job where job hazard and other factors justify application. Many problems based on costs, enviromental impact, health, waste generation, and political issues may be mitigated by use of remotely operated machines. The work that man can not do or should not do will have to be done by machines.

  20. ANSYS analyses on the Shippingport Station Decommissioning Project

    SciTech Connect

    DeSantis, P.V.; McNamee, H.G.

    1987-01-01

    The nuclear reactor vessel from the Shippingport Station, located in Shippingport, Pennsylvania, will be removed as part of the overall Decommissioning Project. The reactor vessel along with a specially designed lifting beam and skirt were modelled to examine the stresses and behavior of the combined structure. Both the PC/Linear Version of ANSYS and the Cray Version were used in the two phases of the analysis. This paper describes the modelling and analytical techniques used to evaluate the design of this one-of-a-kind structure. The combination of the two versions of ANSYS provided the design team with excellent results in a timely and cost effective manner.

  1. Shutdown plus 3 - a look at Yankee decommissioning experience

    SciTech Connect

    Szymczak, W.J.

    1995-12-31

    In three years, the Yankee Nuclear Power Station has not only made the transition from a facility with a full power operating license to a shut down facility but to a facility with a mature and experienced organization poised to effectively and efficiently decommission the remainder of the plant. Opportunities were acted upon to reduce the cost of running and dismantling a shut-down facility. This paper describes some of those opportunities and Yankee`s future strategy for dismantling in an environment with limited waste disposal availability.

  2. 30 CFR 585.902 - What are the general requirements for decommissioning for facilities authorized under my SAP, COP...

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... decommissioning for facilities authorized under my SAP, COP, or GAP? 585.902 Section 585.902 Mineral Resources... authorized under my SAP, COP, or GAP? (a) Except as otherwise authorized by BOEM under § 585.909, within 2... decommissioning the facilities under your SAP, COP, or GAP, you must submit a decommissioning application...

  3. 30 CFR 585.902 - What are the general requirements for decommissioning for facilities authorized under my SAP, COP...

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... decommissioning for facilities authorized under my SAP, COP, or GAP? 585.902 Section 585.902 Mineral Resources... authorized under my SAP, COP, or GAP? (a) Except as otherwise authorized by BOEM under § 585.909, within 2... decommissioning the facilities under your SAP, COP, or GAP, you must submit a decommissioning application...

  4. Resource book: Decommissioning of contaminated facilities at Hanford

    SciTech Connect

    Not Available

    1991-09-01

    In 1942 Hanford was commissioned as a site for the production of weapons-grade plutonium. The years since have seen the construction and operation of several generations of plutonium-producing reactors, plants for the chemical processing of irradiated fuel elements, plutonium and uranium processing and fabrication plants, and other facilities. There has also been a diversification of the Hanford site with the building of new laboratories, a fission product encapsulation plant, improved high-level waste management facilities, the Fast Flux test facility, commercial power reactors and commercial solid waste disposal facilities. Obsolescence and changing requirements will result in the deactivation or retirement of buildings, waste storage tanks, waste burial grounds and liquid waste disposal sites which have become contaminated with varying levels of radionuclides. This manual was established as a written repository of information pertinent to decommissioning planning and operations at Hanford. The Resource Book contains, in several volumes, descriptive information of the Hanford Site and general discussions of several classes of contaminated facilities found at Hanford. Supplementing these discussions are appendices containing data sheets on individual contaminated facilities and sites at Hanford. Twelve appendices are provided, corresponding to the twelve classes into which the contaminated facilities at Hanford have been organized. Within each appendix are individual data sheets containing administrative, geographical, physical, radiological, functional and decommissioning information on each facility within the class. 68 refs., 54 figs., 18 tabs.

  5. Characterisation of radioactive waste products associated with plant decommissioning.

    PubMed

    Sejvar, J; Fero, A H; Gil, C; Hagler, R J; Santiago, J L; Holgado, A; Swenson, R

    2005-01-01

    The inventory of radioactivity that must be considered in the decommissioning of a typical 1000 MWe Spanish pressurised water reactor (PWR) was investigated as part of a generic plant decommissioning study. Analyses based on DORT models (in both R-Z and R-theta geometries) were used with representative plant operating history and core power distribution data in defining the expected neutron environment in regions near the reactor core. The activation analyses were performed by multiplying the DORT scalar fluxes by energy-dependent reaction cross sections (based on ENDF/B-VI data) to generate reaction rates on a per atom basis. The results from the ORIGEN2 computer code were also used for determining the activities associated with certain nuclides where multi-group cross section data were not available. In addition to the bulk material activation of equipment and structures near the reactor, the activated corrosion-product (or 'crud') deposits on system and equipment surfaces were considered. The projected activities associated with these sources were primarily based on plant data and experience from operating PWR plants.

  6. Resource book: Decommissioning of contaminated facilities at Hanford

    SciTech Connect

    Not Available

    1991-09-01

    In 1942 Hanford was commissioned as a site for the production of weapons-grade plutonium. The years since have seen the construction and operation of several generations of plutonium-producing reactors, plants for the chemical processing of irradiated fuel elements, plutonium and uranium processing and fabrication plants, and other facilities. There has also been a diversification of the Hanford site with the building of new laboratories, a fission product encapsulation plant, improved high-level waste management facilities, the Fast Flux test facility, commercial power reactors and commercial solid waste disposal facilities. Obsolescence and changing requirements will result in the deactivation or retirement of buildings, waste storage tanks, waste burial grounds and liquid waste disposal sites which have become contaminated with varying levels of radionuclides. This manual was established as a written repository of information pertinent to decommissioning planning and operations at Hanford. The Resource Book contains, in several volumes, descriptive information of the Hanford Site and general discussions of several classes of contaminated facilities found at Hanford. Supplementing these discussions are appendices containing data sheets on individual contaminated facilities and sites at Hanford. Twelve appendices are provided, corresponding to the twelve classes into which the contaminated facilities at Hanford have been organized. Within each appendix are individual data sheets containing administrative, geographical, physical, radiological, functional and decommissioning information on each facility within the class. 49 refs., 44 figs., 14 tabs.

  7. Radiological characterization of a vitrification facility for decommissioning

    SciTech Connect

    Asou, M.

    2007-07-01

    Cleanup operations in the Marcoule Vitrification Facility (AVM) will start in 2007. This plant includes 20 highly irradiating storage tanks for high-level liquid waste before vitrification. The objective of the cleanup phase is to significantly decrease the amount of highly radioactive waste resulting from dismantling. A comprehensive radiological survey of the plant was initiated in 2000. Most of the tanks were characterized using advanced technologies: gamma imaging, CdZnTe gamma spectroscopy, dose rate measurements and 3D calculations codes. At the same time, inspections were conducted to develop 3D geometrical models of the tanks. The techniques used and the main results obtained are described as well as lessons learned from these operations. The rinsing program was defined in 2006. Decontamination operations are expected to begin in 2007, and radiological surveys will be followed up to monitor the efficiency of the decontamination process. Specific rinsing of all tanks and equipment will be carried out from 2007 to 2009. Concentrated liquid solutions will be vitrified between 2008 and 2010; the decommissioning of AVM will be delayed until the end of 2010. This strategy aims at producing less than 5% 'B' type (long-lived intermediate-level) waste from the decommissioning operations, as well as reducing the dose rate and risks by simplified remote dismantling. The paper reviews the main options selected for decontamination, as well as the radiological characterization strategy. Some cost-related aspects will also be analyzed. (authors)

  8. The AVR (HTGR) decommissioning project with new strategy

    SciTech Connect

    Sterner, Hakan; Rittscher, Dieter

    2007-07-01

    The 15-MWel prototype pilot reactor AVR is a pebble bed HTGR. It was designed in the late 50's and was connected to the grid end of 1967. After 21 y of successful operation the reactor was shut down end of 1988. In 1994 the first decommissioning license was granted and work with defueling, dismantling and preparation of a Safe Enclosure started. The primary system is contaminated with the fission products Sr{sup 90} and Cs{sup 137} and the activation products are Co{sup 60}, C{sup 14} and H{sup 3}. Due to the large amounts of Sr and Cs bound to graphite dust, the dismantling of systems connected to the pressure vessel is very tedious. In 2003 the AVR company was restructured and the strategy of the decommissioning was changed from safe enclosure to green field, i.e. the complete direct dismantling of all facilities and clean up of the site. The highlight during the dismantling is the removal of the reactor vessel (diameter ca. 7.6 m and length ca. 26 m) in one piece. Before handling the reactor vessel it will be filled with low density cellular concrete. Subsequently the reactor building will be cut open and the reactor vessel (total weight ca. 2100 Mg) lifted out and transported to an interim store. (authors)

  9. Nuclear facility decommissioning and site remedial actions: a selected bibliography

    SciTech Connect

    Owen, P.T.; Knox, N.P.; Fielden, J.M.; Johnson, C.A.

    1982-09-01

    This bibliography contains 693 references with abstracts on the subject of nuclear facility decommissioning, uranium mill tailings management, and site remedial actions. Foreign, as well as domestic, literature of all types - technical reports, progress reports, journal articles, conference papers, symposium proceedings, theses, books, patents, legislation, and research project descriptions - has been included in this publication. The bibliography contains scientific (basic research as well as applied technology), economic, regulatory, and legal literature pertinent to the US Department of Energy's Remedial Action Program. Major chapters are Surplus Facilities Management Program, Nuclear Facilities Decommissioning, Formerly Utilized Sites Remedial Action Program, Uranium Mill Tailings Remedial Action Program, Grand Junction Remedial Action Program, and Uranium Mill Tailings Management. Chapter sections for chapters 1 and 2 include: Design, Planning, and Regulations; Site Surveys; Decontamination Studies; Dismantlement and Demolition; Land Decontamination and Reclamation; Waste Disposal; and General Studies. The references within each chapter are arranged alphabetically by leading author. References having no individual author are arranged by corporate author or by title. Indexes are provided for (1) author; (2) corporate affiliation; (3) title; (4) publication description; (5) geographic location; and (6) keywords. An appendix of 202 bibliographic references without abstracts or indexes has been included in this bibliography. This appendix represents literature identified but not abstracted due to time constraints.

  10. DECOMMISSIONING THE BROOKHAVEN NATIONAL LABORATORY BUILDING 830 GAMMA IRRADIATION FACILITY.

    SciTech Connect

    BOWERMAN, B.S.; SULLIVAN, P.T.

    2001-08-13

    The Building 830 Gamma Irradiation Facility (GIF) at Brookhaven National Laboratory (BNL) was decommissioned because its design was not in compliance with current hazardous tank standards and its cobalt-60 sources were approaching the end of their useful life. The facility contained 354 stainless steel encapsulated cobalt-60 sources in a pool, which provided shielding. Total cobalt-60 inventory amounted to 24,000 Curies when the sources were shipped for disposal. The decommissioning project included packaging, transport, and disposal of the sources and dismantling and disposing of all other equipment associated with the facility. Worker exposure was a major concern in planning for the packaging and disposal of the sources. These activities were planned carefully according to ALARA (As Low As Reasonably Achievable) principles. As a result, the actual occupational exposures experienced during the work were within the planned levels. Disposal of the pool water required addressing environmental concerns, since the planned method was to discharge the slightly contaminated water to the BNL sewage treatment plant. After the BNL evaluation procedure for discharge to the sewage treatment plant was revised and reviewed by regulators and BNL's Community Advisory Council, the pool water was discharged to the Building 830 sanitary system. Because the sources were sealed and the pool water contamination levels were low, most of the remaining equipment was not contaminated; therefore disposal was straightforward, as scrap metal and construction debris.

  11. Decommissioning of the high flux beam reactor at Brookhaven Lab

    SciTech Connect

    Hu, J.P.; Reciniello, R.N.; Holden, N.E.

    2011-07-01

    The high-flux beam reactor (HFBR) at the Brookhaven National Laboratory was a heavy water cooled and moderated reactor that achieved criticality on Oct. 31, 1965. It operated at a power level of 40 megawatts. An equipment upgrade in 1982 allowed operations at 60 megawatts. After a 1989 reactor shutdown to reanalyze safety impact of a hypothetical loss of coolant accident, the reactor was restarted in 1991 at 30 megawatts. The HFBR was shut down in December 1996 for routine maintenance and refueling. At that time, a leak of tritiated water was identified by routine sampling of groundwater from wells located adjacent to the reactor's spent fuel pool. The reactor remained shut down for almost three years for safety and environmental reviews. In November 1999 the United States Dept. of Energy decided to permanently shut down the HFBR. The decontamination and decommissioning of the HFBR complex, consisting of multiple structures and systems to operate and maintain the reactor, were complete in 2009 after removing and shipping off all the control rod blades. The emptied and cleaned HFBR dome, which still contains the irradiated reactor vessel, is presently under 24/7 surveillance for safety. Detailed dosimetry performed for the HFBR decommissioning during 1996-2009 is described in the paper. (authors)

  12. Technology, Safety and Costs of Decommissioning Nuclear Reactors At Multiple-Reactor Stations

    SciTech Connect

    Wittenbrock, N. G.

    1982-01-01

    Safety and cost information is developed for the conceptual decommissioning of large (1175-MWe) pressurized water reactors (PWRs) and large (1155-MWe) boiling water reactors {BWRs) at multiple-reactor stations. Three decommissioning alternatives are studied: DECON (immediate decontamination), SAFSTOR (safe storage followed by deferred decontamination), and ENTOMB (entombment). Safety and costs of decommissioning are estimated by determining the impact of probable features of multiple-reactor-station operation that are considered to be unavailable at a single-reactor station, and applying these estimated impacts to the decommissioning costs and radiation doses estimated in previous PWR and BWR decommissioning studies. The multiple-reactor-station features analyzed are: the use of interim onsite nuclear waste storage with later removal to an offsite nuclear waste disposal facility, the use of permanent onsite nuclear waste disposal, the dedication of the site to nuclear power generation, and the provision of centralized services. Five scenarios for decommissioning reactors at a multiple-reactor station are investigated. The number of reactors on a site is assumed to be either four or ten; nuclear waste disposal is varied between immediate offsite disposal, interim onsite storage, and immediate onsite disposal. It is assumed that the decommissioned reactors are not replaced in one scenario but are replaced in the other scenarios. Centralized service facilities are provided in two scenarios but are not provided in the other three. Decommissioning of a PWR or a BWR at a multiple-reactor station probably will be less costly and result in lower radiation doses than decommissioning an identical reactor at a single-reactor station. Regardless of whether the light water reactor being decommissioned is at a single- or multiple-reactor station: • the estimated occupational radiation dose for decommissioning an LWR is lowest for SAFSTOR and highest for DECON • the estimated

  13. Ecological and political issues surrounding decommissioning of offshore oil facilities in the Southern California Bight

    USGS Publications Warehouse

    Schroeder, Donna M.; Love, Milton S.

    2004-01-01

    To aid legislators, resource managers, and the general public, this paper summarizes and clarifies some of the issues and options that the federal government and the state of California face in decommissioning offshore oil and gas production platforms, particularly as these relate to platform ecology. Both local marine ecology and political climate play a role in decommissioning offshore oil production platforms. Compared to the relatively supportive political climate in the Gulf of Mexico for “rigs-to-reefs” programs, conflicting social values among stakeholders in Southern California increases the need for understanding ecological impacts of various decommissioning alternatives (which range from total removal to allowing some or all of platform structure to remain in the ocean). Additional scientific needs in the decommissioning process include further assessment of platform habitat quality, estimation of regional impacts of decommissioning alternatives to marine populations, and determination of biological effects of any residual contaminants. The principal management need is a ranking of environmental priorities (e.g. species-of-interest and marine habitats). Because considerable numbers of economically important species reside near oil platforms, National Oceanic and Atmospheric Administration Fisheries should consider the consequences of decommissioning alternatives in their overall management plans. Management strategies could include designating reefed platforms as marine protected areas. The overarching conclusion from both ecological and political perspectives is that decommissioning decisions should be made on a case-by-case basis.

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

    PubMed

    Kaiser, Mark J

    2015-08-01

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

  15. Semi-autonomous UAV/UGV for dismounted urban operations

    NASA Astrophysics Data System (ADS)

    Trentini, Michael; Beckman, Blake

    2010-04-01

    Dismounted soldiers are clearly at the centre of modern asymmetric conflicts and unmanned systems of the future will play important roles in their support. Moreover, the nature of modern asymmetric conflicts requires dismounted soldiers to operate in urban environments with challenges of communication and limited situational awareness. To improve the situational awareness of dismounted soldiers in complex urban environments, Defence R&D Canada - Suffield (DRDC Suffield) envision Unmanned Air Vehicles (UAV) rotorcraft and Unmanned Ground Vehicles (UGV) cooperating in the battlespace. The capabilities provided to the UAV rotorcraft will include high speed maneuvers through urban terrain, overthe- horizon and loss of communications operations, and/or low altitude over-watch of dismounted units. This information is shared with both the dismounted soldiers and UGV. The man-sized, man-mobile UGV operates in close support to dismounted soldiers to provide a payload carrying capacity. Some of the possible payloads include chemical, biological, radiological and nuclear (CBRN) detection, intelligence, surveillance and reconnaissance (ISR), weapons, supplies, etc.. These unmanned systems are intended to increase situational awareness in urban environments and can be used to call upon nearby forces to react swiftly by providing acquired information to concentrate impact where required.

  16. Passive stereo range imaging for semi-autonomous land navigation

    NASA Technical Reports Server (NTRS)

    Matthies, Larry

    1992-01-01

    The paper examines the use of stereo vision (SV) for obstacle detection in semiautonomous land navigation. Feature-based and field-based paradigms for SV are reviewed. The paper presents stochastic models and simple, efficient stereo matching algorithms for the field-based approach and describes a near-real-time vision system using these algorithms. Experimental results illustrate aspects of the stochastic models and lead to the first semiautonomous traversals of natural terrain to use SV for obstacle detection.

  17. Semi-autonomous competency assessment of powered mobility device users.

    PubMed

    Miro, Jaime Valls; Black, Ross; De Bruijn, Freek; Dissanayake, Dissanayake

    2011-01-01

    This paper describes a stand-alone sensor package and algorithms for aiding the assessment by an occupational therapist whether a person has the capacity to safely and effectively operate a powered mobility device such as a walking aid or a wheelchair. The sensor package employed consists of a laser range finder, an RGB camera and an inertial measurement unit that can be attached to any mobility device with minimal modifications. Algorithms for capturing the data received by the sensor package and for generating the map of the environment as well as the trajectory of the mobility device have been developed. Such information presents occupational therapists with the capability to provide a quantitative assessment of whether patients are ready to be safely deployed with mobile aids for their daily activities. Preliminary evaluation of the sensor package and associated algorithms based on experiments, conducted at the premises of the Prince of Wales Hospital in Sydney, are presented.

  18. Inexpensive semi-autonomous ground vehicles for defusing IEDs

    NASA Astrophysics Data System (ADS)

    Davenport, Chris; Lodmell, James; Womble, Phillip C.; Barzilov, Alexander; Paschal, Jon; Hernandez, Robert; Moss, Kyle T.; Hopper, Lindsay

    2008-04-01

    Improvised explosive devices (IEDs) are an important concern to coalition forces during the conflicts in the Middle East. These devices are responsible for many casualties to American armed forces in the Middle East. These explosives are particularly dangerous because they are improvised with materials readily available to the designer, and there is no systematic way of explosive ordinance disposal. IEDs can be made from things such as standard military ammunition and can be detonated with common electronic devices such as cell phones and garage door openers. There is a great need for a low cost solution to neutralize these IEDs. At the Applied Physics Institute we are building a single function disrupter robot whose sole purpose is to neutralize these IEDs. We are modifying a toy remote control car to control it either wirelessly using WI-FI (IEEE 802.11) or wired by tethering the vehicle with an Ethernet cable (IEEE 802.3). The robot will be equipped with a high velocity fuze disrupter to neutralize the IED as well as a video camera for inspection and aiming purposes. This robot utilizes commercial-off-the-shelf (COTS) components which keeps the cost relatively low. Currently, similar robot systems have been deployed in Iraq and elsewhere but their method of operation is such that it is impractical to use in non-combat situations. We will discuss our design and possible deployment scenarios.

  19. TWRS privatization: Phase I monitoring well engineering study and decommissioning plan

    SciTech Connect

    Williams, B.A.

    1996-09-11

    This engineering study evaluates all well owners and users, the status or intended use of each well, regulatory programs, and any future well needs or special purpose use for wells within the TWRS Privatization Phase I demonstration area. Based on the evaluation, the study recommends retaining 11 of the 21 total wells within the demonstration area and decommissioning four wells prior to construction activities per the Well Decommissioning Plan (WHC-SD-EN-AP-161, Rev. 0, Appendix I). Six wells were previously decommissioned.

  20. How Does Decommissioning Forest Roads Effect Hydrologic and Geomorphic Risk?

    NASA Astrophysics Data System (ADS)

    Black, T.; Luce, C.; Cissel, R. M.; Nelson, N.; Staab, B.

    2010-12-01

    The US Forest Service is investigating road decommissioning projects to understand how treatments change hydrologic and geomorphic risks. Road treatment effect was measured using a before after control impact design (BACI), using the Geomorphic Road Analysis and Inventory Package (http://www.fs.fed.us/GRAIP). This suite of inventory and analysis tools evaluates: road-stream hydrologic connectivity, fine sediment production and delivery, shallow landslide risk, gully initiation risk, and risks associated with stream crossing failures. The Skokomish River study site is steep and wet and received a high intensity treatment including the removal of stream crossing pipes and fills, all ditch relief pipes and a full hillslope recontouring. Road to stream hydrologic connectivity was reduced by 70%. The treatments reduced fine sediment delivery by 21.8 tons or 81%. The removal of the stream crossing culverts and large associated road fills eliminated the risk of pipe plugging related failures and the eventual erosion of over 4,000 m3 of fill. The slope stability risk was assessed using a modified version of SINMAP (Pack et al, 2005). Risk below drain point locations on the original road was reduced as water was redistributed across the hillslope to waterbars and diffuse drainage. It is unclear; however, if landslide risk was reduced across the entire treated road length because treatments slightly increased risk in some areas where new concentrated drainage features were added above steep slopes. Similarly, values of a gully index ESI (Istanbulluoglu et al, 2003), were reduced at many of the original drainage points, however some new drainage was added. ESI values still exceed a predicted conservative initiation thresholds at some sites, therefore it is uncertain if gully risk will be changed. Mann Creek occupies a moderately steep mid-elevation site in Southern Idaho. The high intensity treatments removed all constructed road drainage features including stream crossing

  1. TA-2 water boiler reactor decommissioning (Phase 1)

    SciTech Connect

    Elder, J.C.; Knoell, C.L.

    1986-12-01

    Removal of external structures and underground piping associated with the gaseous effluent (stack) line from the TA-2 Water Boiler Reactor was performed as Phase I of reactor decommissioning. Six concrete structures were dismantled and 435 ft of contaminated underground piping was removed. Extensive soil contamination by /sup 137/Cs was encountered around structure TA-2-48 and in a suspected leach field near the stream flowing through Los Alamos Canyon. Efforts to remove all contaminated soil were hampered by infiltrating ground water and heavy rains. Methods, cleanup guidelines, and ALARA decisions used to successfully restore the area are described. The cost of the project was approximately $320K; 970 m/sup 3/ of low-level solid radioactive waste resulted from the cleanup operations.

  2. Decontamination and decommissioning experience at the Savannah River Site

    SciTech Connect

    Monson, R.W.

    1994-07-01

    A continuing concern within the DOE complex is how to address the retirement contains special of a facility which nuclear material (SNM). When the life expectancy of a facility has been reached, decisions must be made pertaining to (1) rial from the facility, removing the mate (2) accounting for the material and (3) final disposition of the material. This paper will discuss such a decontamination and decommissioning (D&D) process which we are presently dealing with at the Savannah River Site. The process must follow DOE Order 5633.3A as well as internal Company procedures regarding MC&A. In some D&D cases the material can be exempt from the DOE Order when all of the following criteria are met: (1) the material has been declared waste, (2) the material has been written off the MC&A books, and (3) the material is under the control of a waste management organization.

  3. Overcoming decommissioning challenges through client/laboratory co-operation

    SciTech Connect

    Wharton, Mike; Gray, Lesley

    2007-07-01

    Available in abstract form only. Full text of publication follows: Accelerated decommissioning projects of the type underway at the former gaseous diffusion plant at BNG Capenhurst, UK, involve characterisation and radiochemical fingerprinting of a variety of unusual materials derived from legacy wastes. The project management and technical challenges that can occur during such a program can be successfully surmounted if a close working relationship between the client and the analytical laboratory is achieved. The Capenhurst Integrated Decommissioning Program (IDP) is an example of how such co-operation can reduce costs and time scales by providing the analytical laboratory with key sample and technical information prior to the shipping of the samples to the lab. This ensures that challenges associated with unusual sample matrices can be anticipated and dealt with at an early stage in the project. Gamma spectrometry is the most common analytical technique when analysing samples for radioactive content as it is non-destructive, relatively inexpensive and fast. However, accurate measurement generally requires samples of a known density to be counted in calibrated geometries. This becomes a challenge as many legacy wastes comprise materials of uneven geometry and/or varying density, as has been the case during the Capenhurst IDP. Liaising with the client to ensure a representative sub-sample of the material is taken on-site, and a series of additional checks when analysing the sample ensure that accurate results are obtained even for non-routine materials. Often it is only one or two radionuclides that dominate the radioactive inventory for legacy wastes. (authors)

  4. Sensor Network Demonstration for In Situ Decommissioning - 13332

    SciTech Connect

    Lagos, L.; Varona, J.; Awwad, A.; Rivera, J.; McGill, J.

    2013-07-01

    Florida International University's (FIU's) Applied Research Center is currently supporting the Department of Energy's (DOE) Environmental Management Office of D and D and Facility Engineering program. FIU is supporting DOE's initiative to improve safety, reduce technical risks, and limit uncertainty within D and D operations by identifying technologies suitable to meet specific facility D and D requirements, assessing the readiness of those technologies for field deployment, and conducting feasibility studies and large scale demonstrations of promising technologies. During FY11, FIU collaborated with Savannah River National Laboratory in the development of an experimental test site for the demonstration of multiple sensor systems for potential use in the in situ decommissioning process. In situ decommissioning is a process in which the above ground portion of a facility is dismantled and removed, and the underground portion is filled with a cementious material such as grout. In such a scenario, the question remains on how to effectively monitor the structural health of the grout (cracking, flexing, and sinking), as well as track possible migration of contaminants within and out of the grouted monolith. The right types of sensors can aid personnel in better understanding the conditions within the entombed structure. Without sensors embedded in and around the monolith, it will be very difficult to estimate structural integrity and contaminant transport. Yet, to fully utilize the appropriate sensors and the provided data, their performance and reliability must be evaluated outside a laboratory setting. To this end, a large scale experimental setup and demonstration was conducted at FIU. In order to evaluate a large suite of sensor systems, FIU personnel designed and purchased a pre-cast concrete open-top cube, which served as a mock-up of an in situ DOE decommissioned facility. The inside of the cube measures 10 ft x 10 ft x 8 ft. In order to ensure that the

  5. 75 FR 13568 - MMS Information Collection Activity: 1010-0142, Decommissioning Activities, Extension of a...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-03-22

    ... Minerals Management Service MMS Information Collection Activity: 1010-0142, Decommissioning Activities, Extension of a Collection; Comment Request AGENCY: Minerals Management Service (MMS), Interior. ACTION... comments to the Department of the Interior; Minerals Management Service; Attention: Cheryl Blundon;...

  6. 76 FR 8785 - ABB Inc.; License Amendment Request for Decommissioning of the ABB Inc., Combustion Engineering...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-02-15

    ...--Resident Farmer Thorium and Radium. August 2010. ML102310548. 5. ABB, Inc. Decommissioning Plan Revision 2.... ABB, Inc. Derivation of the Site Specific Soil DCGLs, Addendum, Soil DCGLs for thorium and...

  7. 78 FR 49553 - Three Mile Island, Unit 2; Post Shutdown Decommissioning Activities Report

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-08-14

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Three Mile Island, Unit 2; Post Shutdown Decommissioning Activities Report AGENCY: Nuclear...) for Three Mile Island, Unit 2 (TMI-2). The PSDAR provides an overview of GPUN's...

  8. Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 13: Part 2, Indexes

    SciTech Connect

    Goins, L.F.; Webb, J.R.; Cravens, C.D.; Mallory, P.K.

    1992-09-01

    This is part 2 of a bibliography on nuclear facility decommissioning and site remedial action. This report contains indexes on the following: authors, corporate affiliation, title words, publication description, geographic location, subject category, and key word.

  9. 75 FR 54363 - BOEMRE Information Collection Activity: 1010-0142, Decommissioning Activities, Extension of a...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-09-07

    ... information. SUPPLEMENTARY INFORMATION: Title: 30 CFR 250, subpart Q, Decommissioning Activities. OMB Control... prevent or minimize the likelihood of blowouts, loss of well control, fires, spillages, physical... equipment and subsea protective covering; or other departures. Subtotal 50 responses 150...

  10. 30 CFR 250.1751 - How do I decommission a pipeline in place?

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... to be decommissioned; and (4) Length (feet) of segment remaining. (b) Pig the pipeline, unless the Regional Supervisor determines that pigging is not practical; (c) Flush the pipeline; (d) Fill the...

  11. An Analysis of Decommissioning Costs for the AFRRI TRIGA Reactor Facility

    DTIC Science & Technology

    1989-12-01

    Laboratory, as provided in U.S. Nuclear Regulatory Commission publication NUREG /CR-1756. The data in this study were adapted to reflect the decommissioning requirements of the AFRRI TRIGA reactor facility.

  12. Applying and adapting the Swedish regulatory system for decommissioning to nuclear power reactors - The regulator's perspective.

    PubMed

    Amft, Martin; Leisvik, Mathias; Carroll, Simon

    2017-03-16

    Half of the original 13 Swedish nuclear power reactors will be shut down by 2020. The decommissioning of these reactors is a challenge for all parties involved, including the licensees, the waste management system, the financing system, and the Swedish Radiation Safety Authority (SSM). This paper presents an overview of the Swedish regulations for decommissioning of nuclear facilities. It describes some of the experiences that SSM has gained from the application of these regulations. The focus of the present paper is on administrative aspects of decommissioning, such as SSM's guidelines, the definition of fundamental concepts in the regulatory framework, and a proposed revision of the licensing process according to the Environmental Act. These improvements will help to streamline the administration of the commercial nuclear power plant decommissioning projects that are anticipated to commence in Sweden in the near future.

  13. Radiochemistry Lab Decommissioning and Dismantlement. AECL, Chalk River Labs, Ontario, Canada

    SciTech Connect

    Kenny, Stephen

    2008-01-15

    Atomic Energy of Canada (AECL) was originally founded in the mid 1940's to perform research in radiation and nuclear areas under the Canadian Defense Department. In the mid 50's The Canadian government embarked on several research and development programs for the development of the Candu Reactor. AECL was initially built as a temporary site and is now faced with many redundant buildings. Prior to 2004 small amounts of Decommissioning work was in progress. Many reasons for deferring decommissioning activities were used with the predominant ones being: 1. Reduction in radiation doses to workers during the final dismantlement, 2. Development of a long-term solution for the management of radioactive wastes in Canada, 3. Financial constraints presented by the number of facilities shutdown that would require decommissioning funds and the absence of an approved funding strategy. This has led to the development of a comprehensive decommissioning plan that is all inclusive of AECL's current and legacy liabilities. Canada does not have a long-term disposal site; therefore waste minimization becomes the driving factor behind decontamination for decommissioning before and during dismantlement. This decommissioning job was a great learning experience for decommissioning and the associated contractors who worked on this project. Throughout the life of the project there was a constant focus on waste minimization. This focus was constantly in conflict with regulatory compliance primarily with respect to fire regulations and protecting the facility along with adjacent facilities during the decommissioning activities. Discrepancies in historical documents forced the project to treat every space as a contaminated space until proven differently. Decommissioning and dismantlement within an operating site adds to the complexity of the tasks especially when it is being conducted in the heart of the plant. This project was very successful with no lost time accidents in over one hundred

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

    SciTech Connect

    A. B. Culp

    2006-10-01

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

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

    SciTech Connect

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

    1982-03-01

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

  16. Facilitating Facilitators: Enhancing PBL through a Structured Facilitator Development Program

    ERIC Educational Resources Information Center

    Salinitri, Francine D.; Wilhelm, Sheila M.; Crabtree, Brian L.

    2015-01-01

    With increasing adoption of the problem-based learning (PBL) model, creative approaches to enhancing facilitator training and optimizing resources to maintain effective learning in small groups is essential. We describe a theoretical framework for the development of a PBL facilitator training program that uses the constructivist approach as the…

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

    SciTech Connect

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

    2008-01-15

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

  18. Rosie - mobile robot worksystem for decommissioning and dismantling operations. Final report, April 1, 1996--January 31, 1997

    SciTech Connect

    1998-12-31

    RedZone Robotics, Inc. has undertaken development of an advanced remote worksystem - Rosie - specifically designed to meet the challenges of performing a wide range of decontamination and dismantlement (D&D) operations in nuclear environments. The Rosie worksystem includes a locomotor, heavy manipulator, operator console, and control system for remote operations. The locomotor is a highly mobile platform with tether management and hydraulic power onboard. The heavy manipulator is a high-payload, long-reach boom used to deploy a wide variety of tools and/or sensors into the work area. Rosie`s advanced control system, broad work capabilities, and hardening/reliability for hazardous duty make it a new and unique capability that facilitates completion of significant cleanup projects throughout the Department of Energy (DOE) and private sector. Endurance testing of the first Rosie system from September 1995 to March 1996 has proven its capabilities and appropriateness for D&D applications. Design enhancements were incorporated into the second Rosie system to improve and add features necessary for deployment at a DOE facility decommissioning. This second Rosie unit was deployed to the Argonne National Laboratory`s CP-5 reactor facility in early December 1996, and it is currently being used in the decommissioning of the reactor there. This report will overview this second Rosie system and the design enhancements made to it based on the lessons learned during the design, fabrication, and testing of the first Rosie system. The Rosie system has been designed to be a versatile and adaptable tool that can be used in many different applications in D&D work at nuclear facilities. It can carry a wide variety of tooling, sensors, and other robotic equipment at the tip of its heavy manipulator, and it can deploy those items to many different hazardous work areas. Rosie`s capabilities and system design address the need for durability and reliability in these environments.

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

    SciTech Connect

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

    1980-06-01

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

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

    SciTech Connect

    Per Lidar; Arne Larsson; Niklas Bergh; Gunnar Hedin

    2013-07-01

    Decommissioning of nuclear power plants generates large volumes of radioactive or potentially radioactive waste. The proper management of the dismantling waste plays an important role for the time needed for the dismantling phase and thus is critical to the decommissioning cost. An efficient and thorough process for inventorying, characterization and categorization of the waste provides a sound basis for the planning process. As part of comprehensive decommissioning studies for Nordic NPPs, Westinghouse has developed the decommissioning inventories that have been used for estimations of the duration of specific work packages and the corresponding costs. As part of creating the design basis for a national repository for decommissioning waste, the total production of different categories of waste packages has also been predicted. Studsvik has developed a risk based concept for categorization and handling of the generated waste using six different categories with a span from extremely small risk for radiological contamination to high level waste. The two companies have recently joined their skills in the area of decommissioning on selected market in a consortium named ndcon to further strengthen the proposed process. Depending on the risk for radiological contamination or the radiological properties and other properties of importance for waste management, treatment routes are proposed with well-defined and proven methods for on-site or off-site treatment, activity determination and conditioning. The system is based on a graded approach philosophy aiming for high confidence and sustainability, aiming for re-use and recycling where found applicable. The objective is to establish a process where all dismantled material has a pre-determined treatment route. These routes should through measurements, categorization, treatment, conditioning, intermediate storage and final disposal be designed to provide a steady, un-disturbed flow of material to avoid interruptions. Bottle

  1. Waste Management Strategy for Dismantling Waste to Reduce Costs for Power Plant Decommissioning - 13543

    SciTech Connect

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

    2013-07-01

    Decommissioning of nuclear power plants generates large volumes of radioactive or potentially radioactive waste. The proper management of the dismantling waste plays an important role for the time needed for the dismantling phase and thus is critical to the decommissioning cost. An efficient and thorough process for inventorying, characterization and categorization of the waste provides a sound basis for the planning process. As part of comprehensive decommissioning studies for Nordic NPPs, Westinghouse has developed the decommissioning inventories that have been used for estimations of the duration of specific work packages and the corresponding costs. As part of creating the design basis for a national repository for decommissioning waste, the total production of different categories of waste packages has also been predicted. Studsvik has developed a risk based concept for categorization and handling of the generated waste using six different categories with a span from extremely small risk for radiological contamination to high level waste. The two companies have recently joined their skills in the area of decommissioning on selected market in a consortium named 'ndcon' to further strengthen the proposed process. Depending on the risk for radiological contamination or the radiological properties and other properties of importance for waste management, treatment routes are proposed with well-defined and proven methods for on-site or off-site treatment, activity determination and conditioning. The system is based on a graded approach philosophy aiming for high confidence and sustainability, aiming for re-use and recycling where found applicable. The objective is to establish a process where all dismantled material has a pre-determined treatment route. These routes should through measurements, categorization, treatment, conditioning, intermediate storage and final disposal be designed to provide a steady, un-disturbed flow of material to avoid interruptions. Bottle

  2. Progress on the decommissioning of Zion nuclear generating station

    SciTech Connect

    Moloney, B. P.; Hess, J.

    2013-07-01

    The decommissioning of the twin 1040 MWe PWRs at Zion, near Chicago USA is a ground breaking programme. The original owner, Exelon Nuclear Corporation, transferred the full responsibility for reactor dismantling and site license termination to a subsidiary of EnergySolutions. The target end state of the Zion site for return to Exelon will be a green field with the exception of the dry fuel storage pad. In return, ZionSolutions has access to the full value of the decommissioning trust fund. There are two potential attractions of this model: lower overall cost and significant schedule acceleration. The Zion programme which commenced in September 2010 is designed to return the cleared site with an Independent Spent Fuel Storage Installation (ISFSI) pad in 2020, 12 years earlier than planned by Exelon. The overall cost, at $500 M per full size power reactor is significantly below the long run trend of $750 M+ per PWR. Implementation of the accelerated programme has been underway for nearly three years and is making good progress. The programme is characterised by numerous projects proceeding in parallel. The critical path is defined by the inspection and removal of fuel from the pond and transfer into dry fuel storage casks on the ISFSI pad and completion of RPV segmentation. Fuel loading is expected to commence in mid- 2013 with completion in late 2014. In parallel, ZionSolutions is proceeding with the segmentation of the Reactor Vessel (RV) and internals in both Units. Removal of large components from Unit 1 is underway. Numerous other projects are underway or have been completed to date. They include access openings into both containments, installation of heavy lift crane capacity, rail upgrades to support waste removal from the site, radiological characterization of facilities and equipment and numerous related tasks. As at February 2013, the programme is just ahead of schedule and within the latest budget. The paper will provide a fuller update. The first two

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

    SciTech Connect

    Neal A. Yancey

    2003-02-27

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

  4. Oak Ridge National Laboratory Technology Logic Diagram. Volume 2, Technology Logic Diagram: Part A, Decontamination and Decommissioning

    SciTech Connect

    Not Available

    1993-09-01

    This report documents activities of decontamination and decommissioning at ORNL. Topics discussed include general problems, waste types, containment, robotics automation and decontamination processes.

  5. Geophysics: Building E5375 decommissioning, Aberdeen Proving Ground

    SciTech Connect

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

    1992-08-01

    Building E5375 was 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. Noninvasive geophysical surveys, including magnetics, electrical resistivity, and ground-penetrating radar (GPR), were conducted around the perimeter of the building to guide a sampling program prior to decommissioning and dismantling. Several anomalies wear, noted: (1) An underground storage tank located 25 ft east of Building E5375 was identified with magnetic, resistivity, and GPR profiling. (2) A three-point resistivity anomaly, 12 ft east of the northeast comer of Building E5374 (which borders Building E5375) and 5 ft south of the area surveyed with the magnetometer, may be caused by another underground storage tank. (3) A 2,500-gamma magnetic anomaly near the northeast corner of the site has no equivalent resistivity anomaly, although disruption in GPR reflectors was observed. (4) A one-point magnetic anomaly was located at the northeast comer, but its source cannot be resolved. A chaotic reflective zone to the east represents the radar signature of Building E5375 construction fill.

  6. Geophysics: Building E5282 decommissioning, Aberdeen Proving Ground

    SciTech Connect

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

    1992-08-01

    This report discusses Building E5282 which was one of 10 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 of 1992. Noninvasive geophysical surveys, including magnetics, electrical resistivity, and ground-penetrating radar (GPR), were conducted around the perimeter of the building to guide a sampling program prior to decommissioning and dismantling. Magnetic surveys identified small, complicated, multiple anomalies west, north, and northeast of the building that may be caused by construction fill. Two underground storage tanks, at the northeast and southeast corners, were identified. A large magnetic anomaly complex east of the building was caused by aboveground pipes and unexploded ordnance fragments scattered at the surface. Electrical resistivity profiling showed a broad, conductive terrain superimposed over magnetic anomalies on the north and west. A broad, high-resistivity, nonmagnetic area centered 25 ft east of the building has an unknown origin, but it may be due to nonconductive organic liquids, construction fill, or a buried concrete slab; GPR imaging showed this area as a highly reflective zone at a depth of about 5 ft. The GPR data also showed a small-diameter pipe oriented north-south located east of the building.

  7. Assessment of strippable coatings for decontamination and decommissioning

    SciTech Connect

    Ebadian, M.A.

    1998-01-01

    Strippable or temporary coatings were developed to assist in the decontamination of the Three Mile Island (TMI-2) reactor. These coatings have become a viable option during the decontamination and decommissioning (D and D) of both US Department of Energy (DOE) and commercial nuclear facilities to remove or fix loose contamination on both vertical and horizontal surfaces. A variety of strippable coatings are available to D and D professionals. However, these products exhibit a wide range of performance criteria and uses. The Hemispheric Center for Environmental Technology (HCET) at Florida International University (FIU) was commissioned to perform a 2-year investigation into strippable coatings. This investigation was divided into four parts: (1) identification of commercially available strippable coating products; (2) survey of D and D professionals to determine current uses of these coatings and performance criteria; (3) design and implementation of a non-radiological testing program to evaluate the physical properties of these coatings; and (4) design and implementation of a radiological testing program to determine decontamination factors and effects of exposure to ionizing radiation. Activities during fiscal year 1997 are described.

  8. Ecological risk assessment of a decommissioned military base

    SciTech Connect

    Starodub, M.E.; Feniak, N.A.; Willes, R.F.; Moore, C.E.; Mucklow, L.; Marshall, L.

    1995-12-31

    The ecological health risks to selected terrestrial animals at a decommissioned military base in Atlantic Canada have been assessed. Areas of the base varied in terms of terrain, ground cover, as well as types and extent of contamination, dependent on former uses of the sites. Analysis of surficial soils, sediments, water and fish tissue at the base indicated contamination by metals, PCBs, and various petroleum products and their constituents. Identification of chemicals of concern was based on these analyses, in conjunction with detailed chemical selection procedures. Exposures to chemicals of concern for ecological receptors were assessed in one of two ways. The exposures of moose, snowshoe hare and meadow vole were estimated in areas with surficial contamination, based on expected exposures to environmental media via oral inhalation, and dermal routes of exposure. For two top predators (mink and bald-headed eagle), exposures to bioaccumulative chemicals (cadmium, lead, mercury and PCBs) via transport through the aquatic and/or terrestrial foodchain were estimated. A toxicological assessment was conducted for the chemicals of concern, to yield exposure limits derived from governmental regulations or developed based on no-observed-effect-levels (NOELs) reported in scientifically sound toxicological assays in relevant species. The risk evaluation of each chemical of concern was conducted as a comparison of the estimated total exposures to the exposure limits derived for the selected ecological receptors.

  9. Geophysics: Building E5190 decommissioning, Aberdeen Proving Ground

    SciTech Connect

    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.

  10. Decommissioning of the High Flux Beam Reactor at Brookhaven Lab

    SciTech Connect

    Hu, J. P.; Reciniello, R. N.; Holden, N. E.

    2011-05-27

    The High Flux Beam Reactor at the Brookhaven National Laboratory was a heavy water cooled and moderated reactor that achieved criticality on October 31, 1965. It operated at a power level of 40 mega-watts. An equipment upgrade in 1982 allowed operations at 60 mega-watts. After a 1989 reactor shutdown to reanalyze safety impact of a hypothetical loss of coolant accident, the reactor was restarted in 1991 at 30 mega-watts. The HFBR was shutdown in December 1996 for routine maintenance and refueling. At that time, a leak of tritiated water was identified by routine sampling of ground water from wells located adjacent to the reactor’s spent fuel pool. The reactor remained shutdown for almost three years for safety and environmental reviews. In November 1999 the United States Department of Energy decided to permanently shutdown the HFBR. The decontamination and decommissioning of the HFBR complex, consisting of multiple structures and systems to operate and maintain the reactor, were complete in 2009 after removing and shipping off all the control rod blades. The emptied and cleaned HFBR dome which still contains the irradiated reactor vessel is presently under 24/7 surveillance for safety. Details of the HFBR cleanup conducted during 1999-2009 will be described in the paper.

  11. UK contractors' experience of management of tritium during decommissioning projects

    SciTech Connect

    Green, Tommy; Stevens, Keith; Heaney, John; Murray, Alan; Warwick, Phil; Croudace, Ian

    2007-07-01

    Available in abstract form only. Full text of publication follows: This paper provides an account of the tritium management experience of a UK decommissioning and remediation contracting organisation (NUKEM Limited), supported by a specialist radio-analysis organisation (GAU-Radioanalytical). This experience was gained during the execution of projects which involved the characterisation and remediation of facilities which had previously been used for tritium work and were contaminated with tritium. The emphasis of the paper is on the characterisation (sampling and analysis) of tritium. An account is given of the development of a methodology to improve the accuracy of tritium characterisation. The improved methodology evolved from recognition of the need to minimise tritium losses during sampling, storage, transport and preparation for analysis. These improvements were achieved in a variety of ways, including use of cold and dry sampling techniques in preference to hot or wet ones and freezing relevant samples during storage and transport. The major benefit was an improvement in the accuracy and reliability of the analyses results, essential for proper categorisation, sentencing and future management of tritiated waste. (authors)

  12. Geophysics: Building E5440 decommissioning, Aberdeen Proving Ground

    SciTech Connect

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

    1992-11-01

    Building E5440 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 1992. Noninvasive geophysical surveys, including magnetics, electrical resistivity, and ground-penetrating radar (GPR), were conducted around the perimeter of the building to guide a sampling program prior to decommissioning and dismantling. The results show several complex geophysical signatures. Isolated, one-point, magnetic anomalies surrounding the building may be associated with construction fill. A 10-ft-wide band of strongly magnetic positive anomalies bordering the north side of the building obliterates small magnetic sources that might otherwise be seen. A prominent magnetic nose'' extending northward from this band toward a standpipe at 100N,63E may be connected to an underground tank. The southeast corner of the site is underlain by a rectangular, magnetized source associated with strong radar images. A magnetic lineament extending south from the anomaly may be caused by a buried pipe; the anomaly itself may be caused by subsurface equipment associated with a manhole or utility access pit. A 2,500-gamma, positive magnetic anomaly centered at 0N,20E, which is also the location of a 12 [Omega]-m resistivity minimum, may be caused by a buried vault. It appears on radar imaging as a strong reflector.

  13. Geophysics: Building E5481 decommissioning, Aberdeen Proving Ground

    SciTech Connect

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

    1992-11-01

    Building E5481 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, 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 building is located on the northern margin of a landfill that was sited in a wetland. The large number of magnetic sources surrounding the building are believed to be contained in construction fill that had been used to raise the grade. The smaller anomalies, for the most part, are not imaged with ground radar or by electrical profiling. A conductive zone trending northwest to southeast across the site is spatially related to an old roadbed. Higher resistivity areas in the northeast and east are probably representive of background values. Three high-amplitude, positive, rectangular magnetic anomalies have unknown sources. The features do not have equivalent electrical signatures, nor are they seen with radar imaging.

  14. Lessons Learned in the Decommissioning of the Stardust Spacecraft

    NASA Technical Reports Server (NTRS)

    Larson, Timothy W.

    2012-01-01

    The Stardust spacecraft completed its prime mission in 2006, returning samples from the coma of comet Wild 2 to earth in the sample return capsule. Still healthy, and in a heliocentric orbit, the Stardust spacecraft was repurposed for a new mission - Stardust NExT. This new mission would take the veteran spacecraft to a 2011 encounter with comet Tempel 1, providing a new look at the comet visited in 2005 by the Deep Impact mission. This extended mission for Stardust would push it to the limits of its fuel reserves, prompting several studies aimed at determining the actual remaining fuel on board. The results were used to plan mission events within the constraints of this dwindling resource. The team tracked fuel consumption and adjusted the mission plans to stay within the fuel budget. This effort intensified toward the end of the mission, when a final assessment showed even less remaining fuel than previously predicted, triggering a delay in the start of comet imaging during the approach phase. The flyby of comet Tempel 1 produced spectacular up close views of this comet, imaging previously seen areas as well as new territory, and providing clear views of the location of the 2005 impact. The spacecraft was decommissioned about a month after the flyby, revealing that the fuel tank was now empty after having flown successfully for 12 years, returned comet dust samples to earth, and flown by an asteroid and two comets.

  15. Action Memorandum for Decommissioning of TAN-607 Hot Shop Area

    SciTech Connect

    M. A. Pinzel

    2007-05-01

    The Department of Energy is documenting the selection of an alternative for the TAN-607 Hot Shop Area using a Comprehensive Environmental Response, Compensation, and Liability Act non-time-critical removal action (NTCRA). The scope of the removal action is limited to TAN-607 Hot Shop Area. An engineering evaluation/cost analysis (EE/CA) has assisted the Department of Energy Idaho Operations Office in identifuomg the most effective method for performing the decommissioning of this structure whose mission has ended. TAN-607 Hot Shop Area is located at Test Area North Technical Support Facility within the Idaho National Laboratory Site. The selected alternative consists of demolishing the TAN-607 aboveground structures and components, removing belowground noninert components (e.g. wood products), and removing the radiologically contaminated debris that does not meet remedial action objectives (RAOs), as defined in the Record of Decision Amendment for the V-Tanks and Explanation of Significant Differences for the PM-2A Tanks at Test Area North, Operable Unit 1-10.

  16. Lessons learned from decommissioning projects at Los Alamos National Laboratory

    SciTech Connect

    Salazar, M.

    1995-09-01

    This paper describes lessons learned over the last 20 years from 12 decommissioning projects at Los Alamos National Laboratory. These lessons relate both to overall program management and to management of specific projects during the planning and operations phases. The issues include waste management; the National Environmental Policy Act (NEPA); the Resource Conservation and Recovery Act (RCRA); the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA); contracting; public involvement; client/customer interface; and funding. Key elements of our approach are to be proactive; follow the observation method; perform field activities concurrently; develop strategies to keep reportable incidents from delaying work; seek and use programs, methods, etc., in existence to shorten learning curves; network to help develop solutions; and avoid overstudying and overcharacterizing. This approach results in preliminary plans that require very little revision before implementation, reasonable costs and schedules, early acquisition of permits and NEPA documents, preliminary characterization reports, and contracting documents. Our track record is good -- the last four projects (uranium and plutonium-processing facility and three research reactors) have been on budget and on schedule.

  17. DECOMMISSIONING OF NUCLEAR FACILITIES IN GERMANY - STATUS AT BMBF SITES

    SciTech Connect

    Papp, R.; Komorowski, K.

    2002-02-25

    In a period of approximately 40 years prior to 1994, the German Federal Government had spent about {approx} 15 billion to promote nuclear technology. These funds were earmarked for R&D projects as well as demonstration facilities which took up operation between 1960 and 1980. These BMBF (Federal Ministry for Research) facilities were mainly located at the sites of the federal research centers at Juelich and Karlsruhe (the research reactors AVR, FR2, FRJ-1, KNK, and MZFR, the pilot reprocessing plant WAK) but included also the pilot plants SNR-300 and THTR-300 for fast breeder and high-temperature gas-cooled reactor development, respectively, and finally the salt mine Asse which had been used for waste emplacement prior to conversion into an underground research laboratory. In the meantime, almost all of these facilities were shut down and are now in a state of decommissioning and dismantling. This is mainly due to the facts that R&D needs are satisfied or do not exist any more and that, secondly, the lack of political consensus led to the cancellation of advanced nuclear technology.

  18. Decommissioning of the Molten Salt Reactor Experiment: A technical evaluation

    SciTech Connect

    Notz, K.J.

    1988-01-01

    This report completes a technical evaluation of decommissioning planning for the former Molten Salt Reactor Experiment, which was shut down in December, 1969. The key issues revolve around the treatment and disposal of some five tons of solid fuel salt which contains over 30 kg of fissionable uranium-233 plus fission products and higher actinides. The chemistry of this material is complicated by the formation of elemental fluorine via a radiolysis reaction under certain conditions. Supporting studies carried out as part of this evaluation include (a) a broad scope analysis of possible options for storage/disposal of the salts, (b) calculation of nuclide decay in future years, (c) technical evaluation of the containment facility and hot cell penetrations, (d) review and update of surveillance and maintenance procedures, (e) measurements of facility groundwater radioactivity and sump pump operation, (f) laboratory studies of the radiolysis reaction, and (g) laboratory studies which resulted in finding a suitable getter for elemental fluorine. In addition, geologic and hydrologic factors of the surrounding area were considered, and also the implications of entombment of the fuel in-place with concrete. The results of this evaluation show that the fuel salt cannot be left in its present form and location permanently. On the other hand, extended storage in its present form is quite acceptable for 20 to 30 years, or even longer. For continued storage in-place, some facility modifications are recommended. 30 refs., 5 figs., 9 tabs.

  19. Radioactive Waste Management and Nuclear Facility Decommissioning Progress in Iraq - 13216

    SciTech Connect

    Al-Musawi, Fouad; Shamsaldin, Emad S.; Jasim, Hadi; Cochran, John R.

    2013-07-01

    Management of Iraq's radioactive wastes and decommissioning of Iraq's former nuclear facilities are the responsibility of Iraq's Ministry of Science and Technology (MoST). The majority of Iraq's former nuclear facilities are in the Al-Tuwaitha Nuclear Research Center located a few kilometers from the edge of Baghdad. These facilities include bombed and partially destroyed research reactors, a fuel fabrication facility and radioisotope production facilities. Within these facilities are large numbers of silos, approximately 30 process or waste storage tanks and thousands of drums of uncharacterised radioactive waste. There are also former nuclear facilities/sites that are outside of Al-Tuwaitha and these include the former uranium processing and waste storage facility at Jesira, the dump site near Adaya, the former centrifuge facility at Rashdiya and the former enrichment plant at Tarmiya. In 2005, Iraq lacked the infrastructure needed to decommission its nuclear facilities and manage its radioactive wastes. The lack of infrastructure included: (1) the lack of an organization responsible for decommissioning and radioactive waste management, (2) the lack of a storage facility for radioactive wastes, (3) the lack of professionals with experience in decommissioning and modern waste management practices, (4) the lack of laws and regulations governing decommissioning or radioactive waste management, (5) ongoing security concerns, and (6) limited availability of electricity and internet. Since its creation eight years ago, the MoST has worked with the international community and developed an organizational structure, trained staff, and made great progress in managing radioactive wastes and decommissioning Iraq's former nuclear facilities. This progress has been made, despite the very difficult implementing conditions in Iraq. Within MoST, the Radioactive Waste Treatment and Management Directorate (RWTMD) is responsible for waste management and the Iraqi Decommissioning

  20. Activities ONDRAF/NIRAS related to the decommissioning of nuclear facilities

    SciTech Connect

    Cantarella, J.; Simenon, R.; Braeckeveldt, M.

    2013-07-01

    Since 1980, the Agency is responsible by law for the safe management of all radioactive waste produced in Belgium, including decommissioning wastes. By the law of 11 January 1991 and the implementing Royal Decree of 16/10/1991, ONDRAF/NIRAS has been entrusted with a mission concerning the decommissioning of nuclear facilities. This mission involves the collection and assessment of data concerning decommissioning forecasts for nuclear facilities, the approval of facilities' decommissioning programmes, the establishment - in consultation with operators - of financing conditions for decommissioning, as well as the implementation of these programmes on request by the operator, or in the case of its failure to do so. This is the case for the company Best Medical Belgium SA located at Fleurus (MDS Nordion SA, till April 2011), which produced radioisotopes for medical applications and went bankrupt in 2012. These installations have been entrusted to ONDRAF/NIRAS. A plan of action was developed for taking over the operations in the framework of remediation and decommissioning. Steps have been taken to integrate his new role as a nuclear operator. The installations of Best Medical Belgium SA are now referred to as the 'O/N - Site Fleurus.' Nuclear facility operators, or any person requesting to operate a nuclear facility, are obliged to provide ONDRAF/NIRAS, under their responsibility and in due time, with all the necessary information concerning these facilities' decommissioning forecasts, the nature, quantities and dates of transfer of the resulting waste, and the financing conditions for these facilities' decommissioning. In order to make the necessary funds available for decommissioning a nuclear facility when it will be shut down, operators are obliged to establish provisions during the facility's active life. These provisions are calculated in such a way that the total amount established at the time of the final shutdown covers all costs resulting from the facility

  1. Historical site assessments--they're not just for decommissioning anymore.

    PubMed

    Aker, Rock E

    2002-02-01

    At the conclusion of its mission, every nuclear facility eventually undergoes decommissioning. An early and essential part of decommissioning is the conduct of an extensive site characterization process. A Historical Site Assessment (HSA), a critical aspect of the site characterization process, sufficiently informs the facility owner and stakeholders of the radiological contaminants on the facility site. This allows for a safe and optimal decommissioning process. Although many nuclear facilities in the United States are permanently closed, many are entering a long-term storage condition typically known as safe storage (SAFSTOR). In these cases, only minimal characterization may be conducted initially. Full characterization may not occur for several decades. Additional delays in decommissioning will occur in operating facilities that successfully extend their operating licenses. In both of these cases, the conduct of a robust HSA can provide a valuable and cost-beneficial decommissioning step. This paper suggests that a substantial portion of the early site characterization process should be conducted prior to the conclusion of a facility's mission.

  2. DECOMMISSIONING OF THE NUCLEAR FACILITIES OF VKTA AT THE ROSSENDORF RESEARCH SITE

    SciTech Connect

    U. Helwig, W. Boessert

    2003-02-27

    VKTA decommissioned the old nuclear facilities of former GDR's (German Democratic Republic) Central Institute of Nuclear Research which was closed end of 1991. VKTA is responsible for fissile material and waste management, environmental and radiation protection and runs an accredited laboratory for environmental and radionuclide analytics. The Rossendorf research site is located east of the city of Dresden. The period from 1982 to about 1997 was mainly characterized by obtaining the necessary licenses for decommissioning and developing a new infrastructure (i.e. waste treatment facility, interim storages for fissile material and waste, clearance monitoring facility). The decommissioning work has been in progress since that time. The decommissioning projects are concentrated on three complexes: (1) the reactors and a fuel development and testing facility, (2) the radioisotope production facilities, and (3) the former liquid and solid waste storage facilities. The status of decommissioning progress and treatment of the residues will be demonstrated. Finally an outlook will be given on the future tasks of VKTA based on the ''Conception VKTA 2000 plus'', which was confirmed by the Saxonian government last year.

  3. Guide for radiological characterization and measurements for decommissioning of US Department of Energy surplus facilities

    SciTech Connect

    Denahm, D. H.; Barnes, M. G.; Jaquish, R. E.; Corley, J. P.; Gilbert, R. O.; Hoenes, G. R.; Jamison, J. D.; McMurray, B. J.; Watson, E. C.

    1983-08-01

    This Guide describes the elements of radiological characterization at DOE excess facilities in preparation for, during, and subsequent to decommissioning operations. It is the intent of this Guide and accompanying appendices to provide the reader (user) with sufficient information to carry out that task with a minimum of confusion and to provide a uniform basis for evaluating site conditions and verifying that decommissioning operations are conducted according to a specific plan. Some areas of particular interest in this Guide are: the need to involve appropriate staff from the affected states in the early planning stages of decommissioning; the need for and suggested methods of radiological site characterization to complete a decommissioning project, including: historical surveys, environmental pathway analyses, statistical sampling design, and choosing appropriate instrumentation and measurements; the need for and emphasis on quality assurance, documentation and records retention; the establishment of a Design Objective approach to applying site-specific contamination limits based on the ALARA philosophy; the establishment of a ''de minimis'' or minimum dose level of concern for decommissioning operations based on existing standards, experience and ALARA considerations.

  4. The conceptual solutions concerning decommissioning and dismantling of Russian civil nuclear powered ships

    SciTech Connect

    Kulikov, Konstantin N.; Nizamutdinov, Rinat A.; Abramov, Andrey N.

    2013-07-01

    From 1959 up to 1991 nine civil nuclear powered ships were built in Russia: eight ice-breakers and one lash lighter carrier (cargo ship). At the present time three of them were taking out of service: ice-breaker 'Lenin' is decommissioned as a museum and is set for storage in the port of Murmansk, nuclear ice-breakers 'Arktika' and 'Sibir' are berthing. The ice-breakers carrying rad-wastes appear to be a possible source of radiation contamination of Murmansk region and Kola Bay because the ship long-term storage afloat has the negative effect on hull's structures. As the result of this under the auspices of the Federal Targeted Program 'Nuclear and Radiation Safety of Russia for 2008 and the period until 2015' the conception and projects of decommissioning of nuclear-powered ships are developed by the State corporation Rosatom with the involvement of companies of United Shipbuilding Corporation. In developing the principal provisions of conception of decommissioning and dismantling of icebreakers the technical and economic assessment of dismantling options in ship-repairing enterprises of North-West of Russia was performed. The paper contains description of options, research procedure, analysis of options of decommissioning and dismantling of nuclear ice-breakers, taking into account the principle of optimization of potential radioactive effect to personnel, human population and environment. The report's conclusions contain the recommendations for selection of option for development of nuclear icebreaker decommissioning and dismantling projects. (authors)

  5. Mobile worksystems for decontamination and decommissioning operations. Final report

    SciTech Connect

    1997-02-01

    This project is an interdisciplinary effort to develop effective mobile worksystems for decontamination and decommissioning (D&D) of facilities within the DOE Nuclear Weapons Complex. These mobile worksystems will be configured to operate within the environmental and logistical constraints of such facilities and to perform a number of work tasks. Our program is designed to produce a mobile worksystem with capabilities and features that are matched to the particular needs of D&D work by evolving the design through a series of technological developments, performance tests and evaluations. The Phase I effort was based on a robot called the Remote Work Vehicle (RWV) that was previously developed by CMU for use in D&D operations at the Three Mile Island Unit 2 Reactor Building basement. During Phase I of this program, the RWV was rehabilitated and upgraded with contemporary control and user interface technologies and used as a testbed for remote D&D operations. We established a close working relationship with the DOE Robotics Technology Development Program (RTDP). In the second phase, we designed and developed a next generation mobile worksystem, called Rosie, and a semi-automatic task space scene analysis system, called Artisan, using guidance from RTDP. Both systems are designed to work with and complement other RTDP D&D technologies to execute selective equipment removal scenarios in which some part of an apparatus is extricated while minimally disturbing the surrounding objects. RTDP has identified selective equipment removal as a timely D&D mission, one that is particularly relevant during the de-activation and de-inventory stages of facility transitioning as a means to reduce the costs and risks associated with subsequent surveillance and monitoring. In the third phase, we tested and demonstrated core capabilities of Rosie and Artisan; we also implemented modifications and enhancements that improve their relevance to DOE`s facility transitioning mission.

  6. Decommissioning and PIE of the MEGAPIE spallation target

    SciTech Connect

    Latge, C.; Henry, J.; Wohlmuther, M.; Dai, Y.; Gavillet, D.; Hammer, B.; Heinitz, S.; Neuhausen, J.; Schumann, D.; Thomsen, K.; Tuerler, A.; Wagner, W.; Gessi, A.; Guertin, A.; Konstantinovic, M.; Lindau, R.; Maloy, S.; Saito, S.

    2013-07-01

    A key experiment in the Accelerated Driven Systems roadmap, the MEGAwatt PIlot Experiment (MEGAPIE) (1 MW) was initiated in 1999 in order to design and build a liquid lead-bismuth spallation target, then to operate it into the Swiss spallation neutron facility SINQ at Paul Scherrer Institute. The target has been designed, manufactured, and tested during integral tests, before irradiation carried out end of 2006. During irradiation, neutron and thermo hydraulic measurements were performed allowing deep interpretation of the experiment and validation of the models used during design phase. The decommissioning, Post Irradiation Examinations and waste management phases were defined properly. The phases dedicated to cutting, sampling, cleaning, waste management, samples preparation and shipping to various laboratories were performed by PSI teams: all these phases constitute a huge work, which allows now to perform post-irradiation examination (PIE) of structural material, irradiated in relevant conditions. Preliminary results are presented in the paper, they concern chemical characterization. The following radio-nuclides have been identified by γ-spectrometry: {sup 60}Co, {sup 101}Rh, {sup 102}Rh, {sup 108m}Ag, {sup 110m}Ag, {sup 133}Ba, {sup 172}Hf/Lu, {sup 173}Lu, {sup 194}Hg/Au, {sup 195}Au, {sup 207}Bi. For some of these nuclides the activities can be easily evaluated from γ-spectrometry results ({sup 207}Bi, {sup 194}Hg/Au), while other nuclides can only be determined after chemical separations ({sup 108m}Ag, {sup 110m}Ag, {sup 195}Au, {sup 129}I, {sup 36}Cl and α-emitting {sup 208-210}Po). The concentration of {sup 129}I is lower than expected. The chemical analysis already performed on spallation and corrosion products in the lead-bismuth eutectic (LBE) are very relevant for further applications of LBE as a spallation media and more generally as a coolant.

  7. Decontamination and decommissioning activities photobriefing book FY 1999

    SciTech Connect

    2000-03-08

    The Chicago Pile 5 (CP-5) Reactor, the first reactor built on the Argonne National Laboratory-East site, followed a rich history that had begun in 1942 with Enrico Fermi's original pile built under the west stands at the Stagg Field Stadium of The University of Chicago. CP-5 was a 5-megawatt, heavy water-moderated, enriched uranium-fueled reactor used to produce neutrons for scientific research from 1954--79. The reactor was shut down and defueled in 1979, and placed into a lay-up condition pending funding for decontamination and decommissioning (D and D). In 1990, work was initiated on the D and D of the facility in order to alleviate safety and environmental concerns associated with the site due to the deterioration of the building and its associated support systems. A decision was made in early Fiscal Year (FY) 1999 to direct focus and resources to the completion of the CP-5 Reactor D and D Project. An award of contract was made in December 1998 to Duke Engineering and Services (Marlborough, MA), and a D and D crew was on site in March 1999 to begin work, The project is scheduled to be completed in July 2000. The Laboratory has determined that the building housing the CP-5 facility is surplus to the Laboratory's needs and will be a candidate for demolition. In addition to a photographic chronology of FY 1999 activities at the CP-5 Reactor D and D Project, brief descriptions of other FY 1999 activities and of projects planned for the future are provided in this photobriefing book.

  8. DEVELOPMENT OF PERSONAL PROTECTIVE EQUIPMENT FOR DECONTAMINATION AND DECOMMISSIONING

    SciTech Connect

    M.A. Ebadian, Ph.D.

    1999-01-01

    The purpose of this one-year investigation is to perform a technology integration/search, thereby ensuring that the safest and most cost-effective options are developed and subsequently used during the deactivation and decommissioning (D&D) of U.S. Department of Energy Environmental Management (DOE-EM) sites. Issues of worker health and safety are the main concern, followed by cost. Two lines of action were explored: innovative Personal Cooling Systems (PCS) and Personal Monitoring Equipment (PME). PME refers to sensors affixed to the worker that warn of an approaching heat stress condition, thereby preventing it. Three types of cooling systems were investigated: Pre-Chilled or Forced-Air System (PCFA), Umbilical Fluid-Chilled System (UFCS), and Passive Vest System (PVS). Of these, the UFCS leads the way. The PVS or Gel pack vest lagged due to a limited cooling duration. And the PCFA or chilled liquid air supply was cumbersome and required an expensive and complex recharge system. The UFCS in the form of the Personal Ice Cooling System (PICS) performed exceptionally. The technology uses a chilled liquid circulating undergarment and a Personal Protective Equipment (PPE) external pump and ice reservoir. The system is moderately expensive, but the recharge is low-tech and inexpensive enough to offset the cost. There are commercially available PME that can be augmented to meet the DOE's heat stress alleviation need. The technology is costly, in excess of $4,000 per unit. Workers easily ignore the alarm. The benefit to health & safety is indirect so can be overlooked. A PCS is a more justifiable expenditure.

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

    SciTech Connect

    Elder, H. K.

    1981-10-01

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

  10. 30 CFR 250.1731 - Who is responsible for decommissioning an OCS facility subject to an Alternate Use RUE?

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... facility subject to an Alternate Use RUE? 250.1731 Section 250.1731 Mineral Resources BUREAU OF SAFETY AND... responsible for decommissioning an OCS facility subject to an Alternate Use RUE? (a) The holder of an Alternate Use RUE issued under 30 CFR part 585 is responsible for all decommissioning obligations...

  11. 30 CFR 285.1018 - Who is responsible for decommissioning an OCS facility subject to an Alternate Use RUE?

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... facility subject to an Alternate Use RUE? 285.1018 Section 285.1018 Mineral Resources BUREAU OF OCEAN...- and Marine-Related Activities Using Existing OCS Facilities Decommissioning An Alternate Use Rue § 285.1018 Who is responsible for decommissioning an OCS facility subject to an Alternate Use RUE? (a)...

  12. 30 CFR 285.1018 - Who is responsible for decommissioning an OCS facility subject to an Alternate Use RUE?

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... facility subject to an Alternate Use RUE? 285.1018 Section 285.1018 Mineral Resources MINERALS MANAGEMENT... Existing OCS Facilities Decommissioning An Alternate Use Rue § 285.1018 Who is responsible for decommissioning an OCS facility subject to an Alternate Use RUE? (a) The holder of an Alternate Use RUE...

  13. 30 CFR 250.1731 - Who is responsible for decommissioning an OCS facility subject to an Alternate Use RUE?

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... facility subject to an Alternate Use RUE? 250.1731 Section 250.1731 Mineral Resources MINERALS MANAGEMENT... for decommissioning an OCS facility subject to an Alternate Use RUE? (a) The holder of an Alternate Use RUE issued under part 285 of this subchapter is responsible for all decommissioning...

  14. 30 CFR 250.1731 - Who is responsible for decommissioning an OCS facility subject to an Alternate Use RUE?

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... facility subject to an Alternate Use RUE? 250.1731 Section 250.1731 Mineral Resources BUREAU OF SAFETY AND... responsible for decommissioning an OCS facility subject to an Alternate Use RUE? (a) The holder of an Alternate Use RUE issued under 30 CFR part 585 is responsible for all decommissioning obligations...

  15. 30 CFR 250.1731 - Who is responsible for decommissioning an OCS facility subject to an Alternate Use RUE?

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... facility subject to an Alternate Use RUE? 250.1731 Section 250.1731 Mineral Resources BUREAU OF SAFETY AND... responsible for decommissioning an OCS facility subject to an Alternate Use RUE? (a) The holder of an Alternate Use RUE issued under 30 CFR part 585 is responsible for all decommissioning obligations...

  16. 30 CFR 285.517 - How will MMS determine the amounts of the supplemental and decommissioning financial assurance...

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... supplemental and decommissioning financial assurance requirements associated with commercial leases? 285.517... Assurance Requirements Financial Assurance Requirements for Commercial Leases § 285.517 How will MMS... decommissioning financial assurance requirements on estimates of the cost to meet all accrued lease...

  17. 75 FR 15423 - U.S. Nuclear Regulatory Commission Technical Evaluation Report for the Phase 1 Decommissioning...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-03-29

    .... Nuclear Regulatory Commission Technical Evaluation Report for the Phase 1 Decommissioning Plan for the... Regulatory Commission (NRC) Technical Evaluation Report (TER) for the Phase 1 Decommissioning Plan for the... Center (DOE/ EIS-0226). ADDRESSES: Copies of the U.S. Nuclear Regulatory Commission Technical...

  18. 30 CFR 285.902 - What are the general requirements for decommissioning for facilities authorized under my SAP, COP...

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... decommissioning for facilities authorized under my SAP, COP, or GAP? 285.902 Section 285.902 Mineral Resources... facilities authorized under my SAP, COP, or GAP? (a) Except as otherwise authorized by MMS under § 285.909...) Before decommissioning the facilities under your SAP, COP, or GAP, you must submit a...

  19. 30 CFR 585.902 - What are the general requirements for decommissioning for facilities authorized under my SAP, COP...

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... decommissioning for facilities authorized under my SAP, COP, or GAP? 585.902 Section 585.902 Mineral Resources..., Inspections, and Facility Assessments for Activities Conducted Under SAPs, COPs and GAPs Decommissioning... authorized under my SAP, COP, or GAP? (a) Except as otherwise authorized by BOEM under § 585.909, within...

  20. 30 CFR 285.902 - What are the general requirements for decommissioning for facilities authorized under my SAP, COP...

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... decommissioning for facilities authorized under my SAP, COP, or GAP? 285.902 Section 285.902 Mineral Resources... SAP, COP, or GAP? (a) Except as otherwise authorized by MMS under § 285.909, within 2 years following... under your SAP, COP, or GAP, you must submit a decommissioning application and receive approval from...

  1. 77 FR 58591 - Report on Waste Burial Charges: Changes in Decommissioning Waste Disposal Costs at Low-Level...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-09-21

    ... COMMISSION Report on Waste Burial Charges: Changes in Decommissioning Waste Disposal Costs at Low-Level Waste... document entitled: NUREG-1307 Revision 15, ``Report on Waste Burial Charges: Changes in Decommissioning Waste Disposal Costs at Low-Level Waste Burial Facilities.'' DATES: Please submit comments by October...

  2. 77 FR 64361 - Report on Waste Burial Charges: Changes in Decommissioning Waste Disposal Costs at Low-Level...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-10-19

    ... COMMISSION Report on Waste Burial Charges: Changes in Decommissioning Waste Disposal Costs at Low-Level Waste... Commission (NRC or the Commission) issued Draft NUREG-1307, Revision 15, ``Report on Waste Burial Charges: Changes in Decommissioning Waste Disposal Costs at Low-Level Waste Burial Facilities,'' in the...

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

    SciTech Connect

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

    1982-03-01

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

  4. Environmental, health and safety assessment of decommissioning radioisotope thermoelectric generators (RTGs) in northwest Russia.

    PubMed

    Standring, W J F; Dowdall, M; Sneve, M; Selnaes, Ø G; Amundsen, I

    2007-09-01

    This paper presents findings from public health and environmental assessment work that has been conducted as part of a joint Norwegian-Russian project to decommission radioisotope thermoelectric generators (RTG) in northwest Russia. RTGs utilise heat energy from radioactive isotopes, in this case 90Sr and its daughter nuclide 90Y, to generate electricity as a power source. Different accident scenarios based on the decommissioning process for RTGs are assessed in terms of possible radiation effects to humans and the environment. Doses to humans and biota under the worst-case scenario were lower than threshold limits given in ICRP and IAEA literature.

  5. Environmental assessment of decommissioning radioisotope thermoelectric generators (RTG) in northwest Russia

    SciTech Connect

    Hosseini, A.; Standring, W.J.F.; Brown, J.E.; Dowdall, M.; Amundsen, I.B.

    2007-07-01

    This article presents some results from assessment work conducted as part of a joint Norwegian-Russian project to decommission radioisotope thermoelectric generators (RTG) in Northwest Russia. Potential worst case accident scenarios, based on the decommissioning procedures for RTGs, were assessed to study possible radiation effects to the environment. Close contact with exposed RTG sources will result in detrimental health effects. However, doses to marine biota from ingestion of radioactivity under the worst-case marine scenario studied were lower than threshold limits given in IAEA literature. (authors)

  6. Action Memorandum for General Decommissioning Activities under the Idaho Cleanup Project

    SciTech Connect

    S. L. Reno

    2006-10-26

    This Action Memorandum documents the selected alternative to perform general decommissioning activities at the Idaho National Laboratory (INL) under the Idaho Cleanup Project (ICP). Preparation of this Action Memorandum has been performed in accordance with the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), as amended by the "Superfund Amendments and Reauthorization Act of 1986", and in accordance with the "National Oil and Hazardous Substances Pollution Contingency Plan". An engineering evaluation/cost analysis (EE/CA) was prepared and released for public comment and evaluated alternatives to accomplish the decommissioning of excess buildings and structures whose missions havve been completed.

  7. Lessons learned from decommissioning of a research lab and how to apply these on upcoming decommissioning projects at the Studsvik site

    SciTech Connect

    Ellmark, Christoffer; Eriksson, Anders; Lindberg, Maria

    2007-07-01

    Available in abstract form only. Full text of publication follows: The clearance of material and release of buildings for unconditional use are crucial factors for the waste amounts coming from decommissioning of nuclear facilities. The possibilities for clearance is also very much dependent on the regulatory body's ability to put in place the correct regulations or legislations. During the last decade the development of new guidelines for decommissioning has taken place. The implementation of these guidelines on a national level has not been fast but in Sweden it is on its way. This paper will describe the Swedish situation from the point of view of a decommissioner, i.e. an organization in need of clear and long term regulations. (authors)

  8. Fiscal years 1993 and 1994 decontamination and decommissioning activities photobriefing book for the Argonne National Laboratory-East Site, Technology Development Division, Decontamination and Decommissioning Projects Department

    SciTech Connect

    1995-12-31

    This photobriefing book describes the ongoing decontamination and decommissioning projects at the Argonne National Laboratory (ANL)-East Site near Lemont, Illinois. The book is broken down into three sections: introduction, project descriptions, and summary. The introduction elates the history and mission of the Decontamination and Decommissioning (D and D) Projects Department at ANL-East. The second section describes the active ANL-East D and D projects, giving a project history and detailing fiscal year (FY) 1993 and FY 1994 accomplishments and FY 1995 goals. The final section summarizes the goals of the D and D Projects Department and the current program status. The D/D projects include the Experimental Boiling Water Reactor, Chicago Pile-5 Reactor, that cells, and plutonium gloveboxes. 73 figs.

  9. Interactions between geomorphology and ecosystem processes in travertine streams: Implications for decommissioning a dam on Fossil Creek, Arizona

    NASA Astrophysics Data System (ADS)

    Marks, Jane C.; Parnell, Roderic; Carter, Cody; Dinger, Eric C.; Haden, G. Allen

    2006-07-01

    Travertine deposits of calcium carbonate can dominate channel geomorphology in streams where travertine deposition creates a distinct morphology characterized by travertine terraces, steep waterfalls, and large pools. Algae and microorganisms can facilitate travertine deposition, but how travertine affects material and energy flow in stream ecosystems is less well understood. Nearly a century of flow diversion for hydropower production has decimated the natural travertine formations in Fossil Creek, Arizona. The dam will be decommissioned in 2005. Returning carbonate-rich spring water to the natural stream channel should promote travertine deposition. How will the recovery of travertine affect the ecology of the creek? To address this question, we compared primary production, decomposition, and the abundance and diversity of invertebrates and fish in travertine and riffle/run reaches of Fossil Creek, Arizona. We found that travertine supports higher primary productivity, faster rates of leaf litter decomposition, and higher species richness of the native invertebrate assemblage. Observations from snorkeling in the stream indicate that fish density is also higher in the travertine reach. We postulate that restoring travertine to Fossil Creek will increase stream productivity, rates of litter processing, and energy flow up the food web. Higher aquatic productivity could fundamentally shift the nature of the stream from a sink to a source of energy for the surrounding terrestrial landscape.

  10. 26 CFR 1.468A-0T - Nuclear decommissioning costs; table of contents.

    Code of Federal Regulations, 2010 CFR

    2010-04-01

    ... 26 Internal Revenue 6 2010-04-01 2010-04-01 false Nuclear decommissioning costs; table of contents... (CONTINUED) INCOME TAX (CONTINUED) INCOME TAXES Taxable Year for Which Deductions Taken § 1.468A-0T Nuclear...) Definitions. (c) Special rules applicable to certain experimental nuclear facilities. § 1.468A-2TTreatment...

  11. 10 CFR 50.75 - Reporting and recordkeeping for decommissioning planning.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... parent company whose subsidiary is an owner or operator of a foreign or domestic nuclear power plant... more nuclear power plants. (B) Is obligated at all times to adhere to a standard of care set forth in... assessment of the major factors that could affect the cost to decommission. (4) Each non-power...

  12. Evaluation of Dam Decommissioning in an Ice-Affected River: Case Study

    DTIC Science & Technology

    2007-09-01

    Abdul-Mohsen 2005 and Kuby et al. 2005). Conyngham et al. (2006) provide an overview of the ecological and engi- neering aspects of dam decommissioning...2007) CRREL Ice Jam Database (http://www.crrel.usace.army.mil/ierd/ijdb/), accessed March 2007. Kuby , M.J., W.F. Fagan, C.S. ReVelle, W.L. Graf (2005

  13. 30 CFR 285.906 - What must my decommissioning application include?

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 30 Mineral Resources 2 2010-07-01 2010-07-01 false What must my decommissioning application include? 285.906 Section 285.906 Mineral Resources MINERALS MANAGEMENT SERVICE, DEPARTMENT OF THE INTERIOR OFFSHORE RENEWABLE ENERGY ALTERNATE USES OF EXISTING FACILITIES ON THE OUTER CONTINENTAL...

  14. 30 CFR 285.907 - How will MMS process my decommissioning application?

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 30 Mineral Resources 2 2010-07-01 2010-07-01 false How will MMS process my decommissioning application? 285.907 Section 285.907 Mineral Resources MINERALS MANAGEMENT SERVICE, DEPARTMENT OF THE INTERIOR OFFSHORE RENEWABLE ENERGY ALTERNATE USES OF EXISTING FACILITIES ON THE OUTER CONTINENTAL...

  15. 30 CFR 285.908 - What must I include in my decommissioning notice?

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 30 Mineral Resources 2 2010-07-01 2010-07-01 false What must I include in my decommissioning notice? 285.908 Section 285.908 Mineral Resources MINERALS MANAGEMENT SERVICE, DEPARTMENT OF THE INTERIOR OFFSHORE RENEWABLE ENERGY ALTERNATE USES OF EXISTING FACILITIES ON THE OUTER CONTINENTAL...

  16. 30 CFR 285.905 - When must I submit my decommissioning application?

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 30 Mineral Resources 2 2010-07-01 2010-07-01 false When must I submit my decommissioning application? 285.905 Section 285.905 Mineral Resources MINERALS MANAGEMENT SERVICE, DEPARTMENT OF THE INTERIOR OFFSHORE RENEWABLE ENERGY ALTERNATE USES OF EXISTING FACILITIES ON THE OUTER CONTINENTAL...

  17. 30 CFR 585.906 - What must my decommissioning application include?

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... propose to leave in place, as provided in § 585.909. (c) A proposed decommissioning schedule for your... conducted in the vicinity of the structure and recent observations of turtles or marine mammals at the structure site. (i) Mitigation measures you will use to protect archaeological and sensitive...

  18. 30 CFR 585.906 - What must my decommissioning application include?

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... to remove or propose to leave in place, as provided in § 585.909. (c) A proposed decommissioning... conducted in the vicinity of the structure and recent observations of turtles or marine mammals at the structure site. (i) Mitigation measures you will use to protect archaeological and sensitive...

  19. 30 CFR 585.906 - What must my decommissioning application include?

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... propose to leave in place, as provided in § 585.909. (c) A proposed decommissioning schedule for your... conducted in the vicinity of the structure and recent observations of turtles or marine mammals at the structure site. (i) Mitigation measures you will use to protect archaeological and sensitive...

  20. 10 CFR 72.30 - Financial assurance and recordkeeping for decommissioning.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Financial assurance and recordkeeping for decommissioning. 72.30 Section 72.30 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER...

  1. 30 CFR 250.1751 - How do I decommission a pipeline in place?

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... payment of the service fee listed in § 250.125. Your application must include the following information... 30 Mineral Resources 2 2014-07-01 2014-07-01 false How do I decommission a pipeline in place? 250.1751 Section 250.1751 Mineral Resources BUREAU OF SAFETY AND ENVIRONMENTAL ENFORCEMENT, DEPARTMENT...

  2. 30 CFR 250.1751 - How do I decommission a pipeline in place?

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... payment of the service fee listed in § 250.125. Your application must include the following information... 30 Mineral Resources 2 2012-07-01 2012-07-01 false How do I decommission a pipeline in place? 250.1751 Section 250.1751 Mineral Resources BUREAU OF SAFETY AND ENVIRONMENTAL ENFORCEMENT, DEPARTMENT...

  3. THE SCIENCE OF REMEDIATION, ABATEMENT, AND DECOMMISSIONING OF CATASTROPHIC (AND LESSER) EVENTS

    EPA Science Inventory

    This is a brief overview of some of the activities commonly involved in remediation, abatement, and decommissioning of areas affected by significant events whether natural or man-made. Some examples from the EPA's post-Katrina and anthrax responses are used to demonstrate the sc...

  4. 10 CFR 40.36 - Financial assurance and recordkeeping for decommissioning.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... decommissioning. (c) * * * (5) If, in surveys made under 10 CFR 20.1501(a), residual radioactivity in the facility... containing residual radioactivity that will require remediation; and (D) An adequate contingency factor. (ii... producing additional residual radioactivity in onsite subsurface material; (ii) Waste inventory...

  5. Allowable Residual Contamination Levels in soil for decommissioning the Shippingport Atomic Power Station site

    SciTech Connect

    Kennedy, W.E. Jr.; Napier, B.A.; Soldat, J.K.

    1983-09-01

    As part of decommissioning the Shippingport Atomic Power Station, a fundamental concern is the determination of Allowable Residual Contamination Levels (ARCL) for radionuclides in the soil at the site. The ARCL method described in this report is based on a scenario/exposure-pathway analysis and compliance with an annual dose limit for unrestricted use of the land after decommissioning. In addition to naturally occurring radionuclides and fallout from weapons testing, soil contamination could potentially come from five other sources. These include operation of the Shippingport Station as a pressurized water reactor, operations of the Shippingport Station as a light-water breeder, operation of the nearby Beaver Valley reactors, releases during decommissioning, and operation of other nearby industries, including the Bruce-Mansfield coal-fired power plants. ARCL values are presented for 29 individual radionculides and a worksheet is provided so that ARCL values can be determined for any mixture of the individual radionuclides for any annual dose limit selected. In addition, a worksheet is provided for calculating present time soil concentration value that will decay to the ARCL values after any selected period of time, such as would occur during a period of restricted access. The ARCL results are presented for both unconfined (surface) and confined (subsurface) soil contamination. The ARCL method and results described in this report provide a flexible means of determining unrestricted-use site release conditions after decommissioning the Shippingport Atomic Power Station.

  6. 30 CFR 250.255 - What decommissioning information must accompany the DPP or DOCD?

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 30 Mineral Resources 2 2010-07-01 2010-07-01 false What decommissioning information must accompany the DPP or DOCD? 250.255 Section 250.255 Mineral Resources MINERALS MANAGEMENT SERVICE, DEPARTMENT OF... Information Contents of Development and Production Plans (dpp) and Development Operations...

  7. Decommissioning - An approach to predict the amount of radioactive waste arisings

    SciTech Connect

    Kugel, K.; Brennecke, P.; Koch, W.

    2007-07-01

    In the next decades many facilities are going to be decommissioned in Germany. On the basis of the agreement between the utilities and the Federal Government on the phase out of nuclear energy use for commercial electricity generation predictions can be made on the schedule of the shut down of nuclear installations in Germany and a prognosis might be given for the complete amount of decommissioning waste that will arise. 17 nuclear power plants and other nuclear installations are to be shut down and decommissioned within the next 2 decades. An approach for the prediction of the amount of radioactive waste and an overview on the underlying assumptions is given. The prognosis for the expected radioactive waste in Germany depends on several assumptions. Utilities in Germany expect approx. 5000 m{sup 3} of radioactive waste with negligible heat-generation from decommissioning per reactor. New inquiries seem to indicate that less radioactive waste may arise due to new techniques in decontamination and conditioning. Nevertheless, there will be limits due to costs and physical properties. (authors)

  8. 10 CFR 50.75 - Reporting and recordkeeping for decommissioning planning.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... administrative costs (including taxes) and other incidental expenses of the fund (including legal, accounting... administrative costs (including taxes) and other incidental expenses of the fund (including legal, accounting... certification may be based on a cost estimate for decommissioning the facility. As part of the certification,...

  9. 75 FR 8147 - Notice of Consideration of Amendment Request for Decommissioning of Analytical Bio-Chemistry...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-02-23

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Notice of Consideration of Amendment Request for Decommissioning of Analytical Bio-Chemistry...-Chemistry Laboratories, Inc. (the Licensee) pursuant to 10 CFR part 30. By application dated October...

  10. 10 CFR 40.36 - Financial assurance and recordkeeping for decommissioning.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 1 2011-01-01 2011-01-01 false Financial assurance and recordkeeping for decommissioning. 40.36 Section 40.36 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF SOURCE MATERIAL... licenses authorizing the receipt, possession, and use of source material for uranium or thorium milling,...

  11. 10 CFR 40.36 - Financial assurance and recordkeeping for decommissioning.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 1 2010-01-01 2010-01-01 false Financial assurance and recordkeeping for decommissioning. 40.36 Section 40.36 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF SOURCE MATERIAL... licenses authorizing the receipt, possession, and use of source material for uranium or thorium milling,...

  12. Radionuclide characterization of reactor decommissioning waste and spent fuel assembly hardware

    SciTech Connect

    Robertson, D.E.; Thomas, C.W.; Wynhoff, N.L.; Hetzer, D.C. )

    1991-01-01

    This study is providing the NRC and licensees with a more comprehensive and defensible data base and regulatory assessment of the radiological factors associated with reactor decommissioning and disposal of wastes generated during these activities. The objectives of this study are being accomplished during a two-phase sampling, measurement, and assessment program involving the actual decommissioning of Shippingport Station and the detailed analysis of neutron-activated materials from commercial reactors. Radiological characterization studies at Shippingport have shown that neutron activation products, dominated by {sup 60}Co, comprised the residual radionuclide inventory. Fission products and transuranic radionuclides were essentially absent. Waste classification assessments have shown that all decommissioning materials (except reactor pressure vessel internals) could be disposed of as Class A waste. Measurements and assessments of spent fuel assembly hardware have shown that {sup 63}Ni, {sup 59}Ni, and {sup 94}Nb sometimes greatly exceed the 10CFR61 Class C limit for some components, and thus would require disposal in a high level waste repository. These measurements are providing the basis for an assessment of the disposal options for these types of highly radioactive materials. Comparisons of predicted (calculated) activation product concentrations with the empirical data are providing as assessment of the accuracy of calculational methods. Work is continuing on radiological characterization of spent PWR and BWR control rod assemblies. Additional work is planned on current issues/problems relating to reactor decommissioning. These efforts will be reported on in future supplements to this report. 20 refs., 23 figs., 34 tabs.

  13. Radiological Surveys Performed in Support of the Demolition and Bulk Disposal Decommissioning Method

    SciTech Connect

    Yetter, R.F.; Newson, C.T.

    2006-07-01

    Connecticut Yankee Atomic Power Company is decommissioning the Haddam Neck Plant using the 'Demolition and Bulk Disposal' method, or commonly referred to as 'Rip and Ship'. In general, completing the project using this method entails the removal of all irradiated fuel and highly contaminated systems and components, and the subsequent demolition of the above ground portions of most site structures. Since most structures are removed from site, cost and time savings are realized by virtually eliminating the need for remediation. However, this method of decommissioning creates more waste, both radiological and non-radiological, which must be segregated, packaged and disposed of properly. Prior to demolition, various types of radiological surveys must be performed and work controls put into place to minimize the spread of contamination to other areas of the site, and to prevent the inadvertent release of radioactive materials from the site. This paper will discuss the various types of radiological surveys performed, and controls implemented, in support of the demolition and bulk material disposal decommissioning method, with the emphasis on pre-demolition surveys. Details will be provided on the release criteria, survey design, survey implementation and data analysis on each of the various surveys, as well as a discussion on the controls implemented to prevent the various wastes from inadvertently being shipped to an inappropriate disposal facility. This paper will also strive to provide lessons learned for future projects that utilize the demolition and bulk disposal decommissioning method. (authors)

  14. 78 FR 38739 - Standard Format and Content for Post-Shutdown Decommissioning Activities Report

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-06-27

    ..., DG-1272, in the Federal Register on December 19, 2012 (77 FR 75198), for a 60-day public comment... COMMISSION Standard Format and Content for Post-Shutdown Decommissioning Activities Report AGENCY: Nuclear... (NRC) is issuing Revision 1 of Regulatory Guide (RG) 1.185, ``Standard Format and Content for...

  15. 10 CFR 72.130 - Criteria for decommissioning.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER THAN CLASS C WASTE General Design.... Provisions must be made to facilitate decontamination of structures and equipment, minimize the quantity...

  16. 10 CFR 72.130 - Criteria for decommissioning.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER THAN CLASS C WASTE General Design.... Provisions must be made to facilitate decontamination of structures and equipment, minimize the quantity...

  17. 10 CFR 72.130 - Criteria for decommissioning.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER THAN CLASS C WASTE General Design.... Provisions must be made to facilitate decontamination of structures and equipment, minimize the quantity...

  18. 10 CFR 72.130 - Criteria for decommissioning.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER THAN CLASS C WASTE General Design.... Provisions must be made to facilitate decontamination of structures and equipment, minimize the quantity...

  19. Decommissioning of the secondary containment of the steam generating heavy water reactor at UKAEA-Winfrith

    SciTech Connect

    Miller, Keith; Cornell, Rowland; Parkinson, Steve; McIntyre, Kevin; Staples, Andy

    2007-07-01

    Available in abstract form only. Full text of publication follows: The Winfrith SGHWR was a prototype nuclear power plant operated for 23 years by the United Kingdom Atomic Energy Authority (UKAEA) until 1990 when it was shut down permanently. The current Stage 1 decommissioning contract is part of a multi-stage strategy. It involves the removal of all the ancillary plant and equipment in the secondary containment and non-containment areas ahead of a series of contracts for the decommissioning of the primary containment, the reactor core and demolition of the building and all remaining facilities. As an outcome of a competitive tending process, the Stage 1 decommissioning contract was awarded to NUKEM with operations commencing in April 2005. The decommissioning processes involved with these plant items will be described with some emphasis of the establishment of multiple work-fronts for the production, recovery, treatment and disposal of mainly tritium-contaminated waste arising from its contact with the direct cycle reactor coolant. The means of size reduction of a variety of large, heavy and complex items of plant made from a range of materials will also be described with some emphasis on the control of fumes during hot cutting operations and establishing effective containments within a larger secondary containment structure. Disposal of these wastes in a timely and cost-effective manner is a major challenge facing the decommissioning team and has required the development of a highly efficient means of packing the resultant materials into mainly one-third height ISO containers for disposal as LLW. Details of the quantities of LLW and exempt wastes handled during this process will be given with a commentary about the difficulty in segregating these two waste streams efficiently. (authors)

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

    SciTech Connect

    Sullivan T.

    2014-06-09

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

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

    SciTech Connect

    Sullivan, T.

    2014-09-24

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

  2. French Atomic Energy Commission Decommissioning Programme and Feedback Experience - 12230

    SciTech Connect

    Guiberteau, Ph.; Nokhamzon, J.G.

    2012-07-01

    Since the French Atomic and Alternatives Energy Commission (CEA) was founded in 1945 to carry out research programmes on use of nuclear, and its application France has set up and run various types of installations: research or prototypes reactors, process study or examination laboratories, pilot installations, accelerators, nuclear power plants and processing facilities. Some of these are currently being dismantled or must be dismantled soon so that the DEN, the Nuclear Energy Division, can construct new equipment and thus have available a range of R and D facilities in line with the issues of the nuclear industry of the future. Since the 1960's and 1970's in all its centres, the CEA has acquired experience and know-how through dismantling various nuclear facilities. The dismantling techniques are nowadays operational, even if sometimes certain specific developments are necessary to reduce the cost of operations. Thanks to availability of techniques and guarantees of dismantling programme financing now from two dedicated funds, close to euro 15,000 M for the next thirty years, for current or projected dismantling operations, the CEA's Nuclear Energy Division has been able to develop, when necessary, its immediate dismantling strategy. Currently, nearly thirty facilities are being dismantled by the CEA's Nuclear Energy Division operational units with industrial partners. Thus the next decade will see completion of the dismantling and radioactive clean-up of the Grenoble site and of the facilities on the Fontenay-aux-Roses site. By 2016, the dismantling of the UP1 plant at Marcoule, the largest dismantling work in France, will be well advanced, with all the process equipment dismantled. After an overview of the French regulatory framework, the paper will describe the DD and R (Decontamination Decommissioning and Remediation) strategy, programme and feedback experience inside the CEA's Nuclear Energy Division. A special feature of dismantling operations at the CEA

  3. Photometric Studies of Rapidly Spinning Decommissioned GEO Satellites

    NASA Astrophysics Data System (ADS)

    Ryan, W.; Ryan, E.

    A satellites general characteristics can be substantially influenced by changes in the space environment. Rapidly spinning decommissioned satellites provide an excellent opportunity to study the rotation-dependent physical processes that affect a resident space objects (RSO) spin kinematics over time. Specifically, inactive satellites at or near geosynchronous Earth-orbit (GEO) provide easy targets for which high quality data can be collected and analyzed such that small differences can be detected under single-year or less time frames. Previous workers have shown that the rotational periods of defunct GEOs have been changing over time [1]. Further, the Yarkovsky-OKeefe-Radzievskii-Paddak (YORP) effect, a phenomenon which has been well-studied in the context of the changing the spin states of asteroids, has recently been suggested to be the cause of secular alterations in the rotational period of inactive satellites [2]. Researchers at the Magdalena Ridge Observatory 2.4-meter telescope (operated by the New Mexico Institute of Mining and Technology) have been investigating the spins states of retired GEOs and other high altitude space debris since 2007 [3]. In this current work, the 2.4-meter telescope was used to track and observe the objects typically over a one- to two-hour period, repeated several times over the course of weeks. When feasible, this is then repeated on a yearly basis. Data is taken with a 1 second cadence, nominally in groups of three 600 second image sets. With the current equipment, the cadence of the image sequences is very precise while the start time is accurate only to the nearest second. Therefore, periods are determined individually using each image sequence. Repeatability of the period determination for each of these sequences is typically on the order of 0.01 second or better for objects where a single period is identified. Spin rate periods determined from the GEO light curves collected thus far have been found to range from ~3 sec to

  4. Decommissioning and Dismantling of the Floating Maintenance Base 'Lepse' - 13316

    SciTech Connect

    Field, D.; Mizen, K.

    2013-07-01

    The Lepse was built in Russia in 1934 and commissioned as a dry cargo ship. In 1961 she was re-equipped for use as a nuclear service ship (NSS), specifically a floating maintenance base (FMB), to support the operation of the civilian nuclear fleet (ice-breakers) of the USSR. In 1988 Lepse was taken out of service and in 1990 she was re-classified as a 'berth connected ship', located at a berth near the port of Murmansk under the ownership of Federal State Unitary Enterprise (FSUE) Atomflot. Lepse has special storage facilities for spent nuclear fuel assemblies (SFA) that have been used to store several hundred SFAs for nearly 40 years. High and intermediate-level liquid radioactive waste (LRW) is also present in the spent nuclear fuel assembly storage channels, in special tanks and also in the SFA cooling circuit. Many of the SFAs stored in Lepse are classified as damaged and cannot be removed using standard procedures. The removal of the SFA and LRW from the Lepse storage facilities is a hazardous task and requires specially designed tools, equipment and an infrastructure in which these can be deployed safely. Lepse is a significant environmental hazard in the North West of Russia. Storing spent nuclear fuel and high-level liquid radioactive waste on board Lepse in the current conditions is not acceptable with respect to Russian Federation health, safety and environmental standards and with international best practice. The approved concept design for the removal of the SFA and LRW and dismantling of Lepse requires that the ship be transported to Nerpa shipyard where specialist infrastructure will be constructed and equipment installed. One of the main complexities of the Project lies within the number of interested stakeholders involved in the Project. The Lepse project has been high focus on the international stage for many years with previous international efforts failing to make significant progress towards the objective of decommissioning Lepse. The Northern

  5. Facilitating Organizational Change.

    ERIC Educational Resources Information Center

    1999

    The first of the three papers in this symposium, "Conflicts that Arise in Small Group Facilitation: A Descriptive Study of Accounts, Actions, Outcomes, and Assessments" (Judith A. Kolb, William J. Rothwell), contains self-report verbatim accounts contributed by facilitators and the results of a literature review on small group conflict.…

  6. Evaluator or Facilitator.

    ERIC Educational Resources Information Center

    Bolding, James T.

    1978-01-01

    In American schools, the classroom teacher must act in two conflicting capacities: as a facilitator of learning and as an evaluator of his own facilitating activities. To avoid problems inherent in this, the evaluator role could be assigned elsewhere, as in the Boy Scouts' merit badge system. (SJL)

  7. Decommissioning the physics laboratory, building 777-10A, at the Savannah River Site (SRS)

    SciTech Connect

    Musall, John C.; Cope, Jeff L.

    2008-01-15

    SRS recently completed a four year mission to decommission {approx}250 excess facilities. As part of that effort, SRS decommissioned a 48,000 ft{sup 2} laboratory that housed four low-power test reactors, formerly used by SRS to determine reactor physics. This paper describes and reviews the decommissioning, with a focus on component segmentation and handling (i.e. hazardous material removal, demolition, and waste handling). The paper is intended to be a resource for engineers, planners, and project managers, who face similar decommissioning challenges. Building 777-10A, located at the south end of SRS's A/M-Area, was built in 1953 and had a gross area of {approx}48,000 ft{sup 2}. Building 777-10A had two main areas: a west wing, which housed four experimental reactors and associated equipment; and an east wing, which housed laboratories, and shops, offices. The reactors were located in two separate areas: one area housed the Process Development Pile (PDP) reactor and the Lattice Test Reactor (LTR), while the second area housed the Standard Pile (SP) and the Sub-critical Experiment (SE) reactors. The west wing had five levels: three below and three above grade (floor elevations of -37', -28', -15', 0', +13'/+16' and +27' (roof elevation of +62')), while the east wing had two levels: one below and one above grade (floor elevations of -15' and 0' (roof elevation of +16')). Below-grade exterior walls were constructed of reinforced concrete, {approx}1' thick. In general, above-grade exterior walls were steel frames covered by insulation and corrugated, asbestos-cement board. The two interior walls around the PDP/LTR were reinforced concrete {approx}5' thick and {approx}30' high, while the SP/SE reactors resided in a reinforced, concrete cell with 3.5'-6' thick walls/roof. All other interior walls were constructed of metal studs covered with either asbestos-cement or gypsum board. In general, the floors were constructed of reinforced concrete on cast-in-place concrete

  8. Trip report: European Communities 1989 International Conference on Decommissioning of Nuclear Installations, Brussels, Belgium, October 24-27, 1989

    SciTech Connect

    Rankin, W.N.

    1989-01-01

    The European community is conducting research on the decommissioning of nuclear installations. The prime objective is to develop effective techniques to ensure the protection of man and his environment against the potential hazards of nuclear installations that have been shut down. The results of the 1979--1983 research program were presented in a conference held in Luxembourg. This program was primarily concerned with decommissioning nuclear power plants. The 1984--1988 program was extended to all types of nuclear installations. Fuel fabrication, enrichment and reprocessing plants, and research and development facilities having fulfilled their useful purposes are also awaiting decommissioning. This Program has produced numerous scientific and technical achievements. Great progress has in particular been achieved in the reduction of metal waste arising from decommissioning, due to advances in areas such as the development of aggressive decontamination procedures and of techniques for melting and recycling low-level radioactive waste metal.

  9. Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 13: Part 2, Indexes. Environmental Restoration Program

    SciTech Connect

    Goins, L.F.; Webb, J.R.; Cravens, C.D.; Mallory, P.K.

    1992-09-01

    This is part 2 of a bibliography on nuclear facility decommissioning and site remedial action. This report contains indexes on the following: authors, corporate affiliation, title words, publication description, geographic location, subject category, and key word.

  10. Overview of Remote Handling Equipment Used for the NPP A1 Decommissioning - 12141

    SciTech Connect

    Kravarik, K.; Medved, J.; Pekar, A.; Stubna, M.; Michal, V.; Vargovcik, L.

    2012-07-01

    The first Czechoslovak NPP A1 was in operation from 1972 to 1977 and it was finally shutdown due to an accident (level 4 according to the INES). The presence of radioactive, toxic or hazardous materials limits personnel access to facilities and therefore it is necessary to use remote handling technologies for some most difficult characterization, retrieval, decontamination and dismantling tasks. The history of remote handling technologies utilization started in nineties when the spent nuclear fuel, including those fuel assemblies damaged during the accident, was prepared for the transport to Russia. Subsequent significant development of remote handling equipment continued during implementation of the NPP A1 decommissioning project - Stage I and ongoing Stage II. Company VUJE, Inc. is the general contractor for both mentioned stages of the decommissioning project. Various remote handling manipulators and robotics arms were developed and used. It includes remotely controlled vehicle manipulator MT-15 used for characterisation tasks in hostile and radioactive environment, special robust manipulator DENAR-41 used for the decontamination of underground storage tanks and multi-purposes robotics arms MT-80 and MT-80A developed for variety of decontamination and dismantling tasks. The heavy water evaporator facility dismantling is the current task performed remotely by robotics arm MT-80. The heavy water evaporator is located inside the main production building in the room No. 220 where loose surface contamination varies from 10 Bq/cm{sup 2} to 1x10{sup 3} Bq/cm{sup 2}, dose rate is up to 1.5 mGy/h and the feeding pipeline contained liquid RAW with high tritium content. Presented manipulators have been designed for broad range of decommissioning tasks. They are used for recognition, sampling, waste retrieval from large underground tanks, decontamination and dismantling of technological equipments. Each of the mentioned fields claims specific requirements on design of

  11. Decommissioning of the secondary containment of the steam generating heavy water reactor at UKAEA Winfrith

    SciTech Connect

    Miller, K.D.; Cornell, R.M.; Parkinson, S.J.; McIntyre, K.; Staples, A.

    2007-07-01

    The Winfrith SGHWR was a prototype nuclear power plant operated for 23 years by the United Kingdom Atomic Energy Authority (UKAEA) until 1990 when it was shut down permanently. The current Stage 1 decommissioning contract is part of a multi-stage strategy. It involves the removal of all the ancillary plant and equipment in the secondary containment and non-containment areas ahead of a series of contracts for the decommissioning of the primary containment, the reactor core and demolition of the building and ail remaining facilities. As an outcome of a competitive tending process, the Stage 1 decommissioning contract was awarded to NUKEM with operations commencing in April 2005. The decommissioning processes involved with these plant items will be described with some emphasis of the establishment of multiple work-fronts for the production, recovery, treatment and disposal of mainly tritium-contaminated waste arising from its contact with the direct cycle reactor coolant. The means of size reduction of a variety of large, heavy and complex items of plant made from a range of materials will also be described with some emphasis on the control of fumes during hot cutting operations and establishing effective containments within a larger secondary containment structure. Disposal of these wastes in a timely and cost-effective manner is a major challenge facing the decommissioning team and has required the development of a highly efficient means of packing the resultant materials into mainly one-third height IS0 containers for disposal as LLW. Details of the quantities of LLW and exempt wastes handled during this process will be given with a commentary about the difficulty in segregating these two waste streams efficiently. The paper sets out to demonstrate the considerable progress that has been made with these challenging decommissioning operations at the SGHWR plant and to highlight some of the techniques and processes that have contributed to the overall success of the

  12. Decommissioning of the Hematite Former Fuel Cycle Facility using a decision flow logic based work control process

    SciTech Connect

    Anderson, Keith D.

    2013-07-01

    The remediation and decommissioning of the Hematite Former Fuel Cycle Facility (FFCF), the Hematite Facility, is currently being carried out by Westinghouse Electric Company LLC under the Hematite Decommissioning Project (HDP). The Hematite Facility is located near the town of Hematite, Missouri, USA. The Hematite Facility consists of 228 acres of land with primary operations historically being conducted within the central portion of the property that is roughly 10 acres including Burial Pits and the Site Pond area. Decommissioning and remediation activities are being performed with the eventual objective of the release of the property. Primary contaminants include the legacy disposal and contamination of natural and enriched uranium from the nuclear fuel cycle, as well as chemicals used during the facility operations. Two major regulatory bodies, the U.S. Nuclear Regulatory Commission (NRC) and the Missouri Department of Natural Resources (MDNR), provide critical roles in the approval and oversight of the current regulatory path to remediation, decommissioning and eventual release. Further, remediation and decommissioning activities are performed under the implementing policies, plans, and procedures under the Hematite Decommissioning Plan (DP) and the Record of Decision (ROD). Remediation and decommissioning tasks at the Hematite Former Fuel Cycle Facility, referred to as the Hematite Facility, are performed against a disciplined decision logic flow that applies accumulated technical and monitoring data to determine each step of the excavation, exhumation, and removal of wastes from the Burial Pits and the remaining Areas of Concern (AOC). Decision flow logic is based upon the nuclear criticality safety controls and threshold conditions, relative level of radioactive and chemical contamination, security protocol, and final waste stream disposition. The end result is to remediate the residual radioactive and chemical contamination to approved dose-based and risk

  13. Screening evaluation of radionuclide groundwater concentrations for the end state basement fill model Zion Nuclear Power Station decommissioning project

    SciTech Connect

    Sullivan T.

    2014-06-09

    ZionSolutions is in the process of decommissioning the Zion Nuclear Power Plant. The site contains two reactor Containment Buildings, a Fuel Building, an Auxiliary Building, and a Turbine Building that may be contaminated. The current decommissioning plan involves removing all above grade structures to a depth of 3 feet below grade. The remaining underground structures will be backfilled with clean material. The final selection of fill material has not been made.

  14. Decommissioning of Active Ventilation Systems in a Nuclear R and D Facility to Prepare for Building Demolition (Whiteshell Laboratories Decommissioning Project, Canada) - 13073

    SciTech Connect

    Wilcox, Brian; May, Doug; Howlett, Don; Bilinsky, Dennis

    2013-07-01

    Whiteshell Laboratories (WL) is a nuclear research establishment owned by the Canadian government and operated by Atomic Energy of Canada Limited (AECL) since the early 1960's. WL is currently under a decommissioning license and the mandate is to remediate the nuclear legacy liabilities in a safe and cost effective manner. The WL Project is the first major nuclear decommissioning project in Canada. A major initiative underway is to decommission and demolish the main R and D Laboratory complex. The Building 300 R and D complex was constructed to accommodate laboratories and offices which were mainly used for research and development associated with organic-cooled reactors, nuclear fuel waste management, reactor safety, advanced fuel cycles and other applications of nuclear energy. Building 300 is a three storey structure of approximately 16,000 m{sup 2}. In order to proceed with building demolition, the contaminated systems inside the building have to be characterized, removed, and the waste managed. There is a significant focus on volume reduction of radioactive waste for the WL project. The active ventilation system is one of the significant contaminated systems in Building 300 that requires decommissioning and removal. The active ventilation system was designed to manage hazardous fumes and radioactivity from ventilation devices (e.g., fume hoods, snorkels and glove boxes) and to prevent the escape of airborne hazardous material outside of the laboratory boundary in the event of an upset condition. The system includes over 200 ventilation devices and 32 active exhaust fan units and high efficiency particulate air (HEPA) filters. The strategy to remove the ventilation system was to work from the laboratory end back to the fan/filter system. Each ventilation duct was radiologically characterized. Fogging was used to minimize loose contamination. Sections of the duct were removed by various cutting methods and bagged for temporary storage prior to disposition

  15. Facilitating Understandings of Geometry.

    ERIC Educational Resources Information Center

    Pappas, Christine C.; Bush, Sara

    1989-01-01

    Illustrates some learning encounters for facilitating first graders' understanding of geometry. Describes some of children's approaches using Cuisenaire rods and teacher's intervening. Presents six problems involving various combinations of Cuisenaire rods and cubes. (YP)

  16. Health and environmental hazards of CdTe photovoltaic module production, use and decommissioning

    NASA Astrophysics Data System (ADS)

    Moskowitz, P. D.; Steinberger, H.; Thumm, W.

    Health and environmental (H&E) risks presented by CdTe photovoltaic module production, use and decommissioning have been reviewed and discussed by several authors. Several H&E concerns exist. The estimated risks are based on extrapolations of toxicity, environmental mobility, and bioavailability data for other inorganic cadmium compounds. Little information, however, is available about CdTe itself. In response to the increased interest in CdTe, Brookhaven National Laboratory (BNL) has been engaged in a cooperative research program with the National Institute of Environmental Health Sciences (NIEHS), the Fraunhofer Institute for Solid State Technology (IFT), and the GSF Institute of Chemical Ecology to develop fundamental toxicological and environmental data for CdTe. This paper describes the results of these studies, and their potential implications with respect to the H&E hazards presented by CdTe module production, use and decommissioning.

  17. Health and environmental hazards of CdTe photovoltaic module production, use and decommissioning

    SciTech Connect

    Moskowitz, P.D.; Steinberger, H.; Thumm, W.

    1995-02-01

    Health and environmental (H&E) risks presented by CdTe photovoltaic module production, use and decommissioning have been reviewed and discussed by several authors. Several H&E concerns exit. The estimated risks are based on extrapolations of toxicity, environmental mobility, and bioavailability data for other inorganic cadmium compounds. Little information, however, is available about CdTe itself. In response to the increased interest in CdTe, Brookhaven National Laboratory (BNL) has been engaged in a cooperative research program with the National Institute of Environmental Health Sciences (NIEHS), the Fraunhofer Institute for Solid State Technology (IFT), and the GSF Institute of Chemical Ecology to develop fundamental toxicological and environmental data for CdTe. This paper describes the results of these studies, and their potential implications with respect to the H&E hazards presented by CdTe module production, use and decommissioning.

  18. Study on the financing mechanism and management for decommissioning of nuclear installations in Malaysia

    NASA Astrophysics Data System (ADS)

    Saleh, Lydia Ilaiza; Ryong, Kim Tae

    2015-04-01

    The whole cycle of the decommissioning process development of repository requires the relevant bodies to have a financial system to ensure that it has sufficient funds for its whole life cycle (over periods of many decades). Therefore, the financing mechanism and management system shall respect the following status: the national position, institutional and legislative environment, technical capabilities, the waste origin, ownership, characteristics and inventories. The main objective of the studies is to focus on the cost considerations, alternative funding managements and mechanisms, technical and non-technical factors that may affect the repository life-cycle costs. As a conclusion, the outcomes of this paper is to make a good recommendation and could be applied to the national planners, regulatory body, engineers, or the managers, to form a financial management plan for the decommissioning of the Nuclear Installation.

  19. Challenges with Final Status Surveys at a Large Decommissioning Site - 13417

    SciTech Connect

    Downey, Heath; Collopy, Peter; Shephard, Eugene; Walter, Nelson; Conant, John

    2013-07-01

    As part of decommissioning a former nuclear fuel manufacturing site, one of the crucial final steps is to conduct Final Status Surveys (FSS) in order to demonstrate compliance with the release criteria. At this decommissioning site, the area for FSS was about 100 hectares (248 acres) and included varying terrain, wooded areas, ponds, excavations, buildings and a brook. The challenges in performing the FSS included determining location, identifying FSS units, logging gamma walkover survey data, determining sample locations, managing water in excavations, and diverting water in the brook. The approaches taken to overcome these challenges will be presented in the paper. The paper will present and discuss lessons learned that will aid others in the FSS process. (authors)

  20. Evaluation of decommissioning alternatives for the Pilot Plant Complex, Aberdeen Proving Ground

    SciTech Connect

    Rueda, J.; Zimmerman, R.E.

    1995-09-01

    This report presents an evaluation of four decommissioning alternatives for the Pilot Plant Complex (PPC), an inactive chemical weapons research, development, and production facility consisting of nine buildings located in the Edgewood Area of the Aberdeen Proving Ground in Maryland. Decommissioning the PPC involves six steps: (1) assessing existing conditions; (2) dismantling the aboveground portions of the buildings (including the floor slabs, paved roads, and sidewalks within the PPC); (3) reducing the size of the demolition debris and sealing the debris in containers for later testing and evaluation; (4) testing and evaluating the debris; (5) conducting site operation and maintenance activities; and (6) recycling or disposing of the debris with or without prior treatment, as appropriate.

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

    SciTech Connect

    Miles, T.L.; Liu, Y.

    1995-08-01

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

  2. Environmental Assessment for decommissioning the Strategic Petroleum Reserve Weeks Island Facility, Iberia Parish, Louisiana

    SciTech Connect

    1995-12-01

    The Strategic Petroleum Reserve (SPR) Weeks Island site is one of five underground salt dome crude oils storage facilities operated by the Department of Energy (DOE). It is located in Iberia Parish, Louisiana. The purpose of the proposed action is to decommission the Weeks Island crude oil storage after the oil inventory has been transferred to other SPR facilities. Water intrusion into the salt dome storage chambers and the development of two sinkholes located near the aboveground facilities has created uncertain geophysical conditions. This Environmental Assessment describes the proposed decommissioning operation, its alternatives, and potential environmental impacts. Based on this analyses, DOE has determined that the proposed action is not a major Federal action significantly affecting the quality of the human environment within the meaning of the National Environmental Policy Act (NEPA) and has issued the Finding of No Significant Impact (FONSI).

  3. 2016 Annual Inspection and Radiological Survey Results for the Piqua, Ohio, Decommissioned Reactor Site, July 2016

    SciTech Connect

    Zimmerman, Brian; Miller, Michele

    2016-07-01

    This report presents the findings of the annual inspection and radiological survey of the Piqua, Ohio, Decommissioned Reactor Site (site). The decommissioned nuclear power demonstration facility was inspected and surveyed on April 15, 2016. The site, located on the east bank of the Great Miami River in Piqua, Ohio, was in fair physical condition. There is no requirement for a follow-up inspection, partly because City of Piqua (City) personnel participated in a March 2016 meeting to address reoccurring safety concerns. Radiological survey results from 104 locations revealed no removable contamination. One direct beta activity reading in a floor drain on the 56-foot level (1674 disintegrations per minute [dpm]/100 square centimeters [cm2]) exceeded the minimum detectable activity (MDA). Beta activity has been detected in the past at this floor drain. The reading was well below the action level of 5000 dpm/100 cm2.

  4. Allowable residual contamination levels for decommissioning. Part 1. A description of the method

    SciTech Connect

    Napier, B.A.; Kennedy, W.E. Jr.

    1984-10-01

    This paper contains a description of the methods used in a study sponsored by UNC Nuclear Industries to determine Allowable Residual Contamination Levels (ARCL) for decommissioning facilities in the 100 Areas of the Hanford Site. The ARCL method is based on a scenario/exposure-pathway analysis and compliance with an annual dose limit for three specific modes of future use of the land and facilities. Thes modes of use are restricted, controlled, and unrestricted. The information on ARCL values for restricted and controlled use is intended to permit a full consideration of decommissioning alternatives. The analysis results in site-specific ARCL values that can be used for determining compliance with any annual dose limit selected. This flexibility permits proper consideration of field situations involving the radionuclide mixtures and physical conditions encountered. In addition, this method permits a full determination of as low as reasonably achievable (ALARA) conditions.

  5. Study on the financing mechanism and management for decommissioning of nuclear installations in Malaysia

    SciTech Connect

    Saleh, Lydia Ilaiza Ryong, Kim Tae

    2015-04-29

    The whole cycle of the decommissioning process development of repository requires the relevant bodies to have a financial system to ensure that it has sufficient funds for its whole life cycle (over periods of many decades). Therefore, the financing mechanism and management system shall respect the following status: the national position, institutional and legislative environment, technical capabilities, the waste origin, ownership, characteristics and inventories. The main objective of the studies is to focus on the cost considerations, alternative funding managements and mechanisms, technical and non-technical factors that may affect the repository life-cycle costs. As a conclusion, the outcomes of this paper is to make a good recommendation and could be applied to the national planners, regulatory body, engineers, or the managers, to form a financial management plan for the decommissioning of the Nuclear Installation.

  6. Recent achievements for In-situ measurement: applications to an actual decommissioning project

    SciTech Connect

    Lamadie, F.; Girones, P.; Le Goaller, C.; Mahe, C.; Kohler, J.Y.; Risser, M.A.

    2007-07-01

    Decommissioning a nuclear facility implies a policy of limiting the waste volume and its chemical - and especially radiological - toxicity. It is therefore important to determine the activity level contained in each component that will be dismantled. A variety of methods and analysis techniques are used for this purpose, ranging from simple dose rate measurements to {gamma} spectrometry and {gamma} imaging. The results of several measurement campaigns in a reactor currently in operation but for which decommissioning studies have now been undertaken are discussed. The measurements provide additional radiological data for the waste inventory, which is one of the first issues to be examined. This discussion focuses on the methods used ({gamma} imaging, in situ {gamma} spectrometry, etc.), the results obtained, and their implications for the project, as well as the technological and methodological innovations implemented during these campaigns. (authors)

  7. Characterization of Decommissioned PWR Vessel Internals Materials Samples: Material Certification, Fluence, and Temperature (Nonproprietary Version)

    SciTech Connect

    M. Krug; R. Shogan; A. Fero; M. Snyder

    2004-11-01

    Pressurized water reactor (PWR) cores, operate under extreme environmental conditions due to coolant chemistry, operating temperature, and neutron exposure. Extending the life of PWRs require detailed knowledge of the changes in mechanical and corrosion properties of the structural austenitic stainless steel components adjacent to the fuel. This report contains basic material characterization information of the as-installed samples of reactor internals material which were harvested from a decommissioned PWR.

  8. Decommissioning and Demolition of a Redundant UK Research Facility at AWE Aldermaston - 12453

    SciTech Connect

    Pritchard, Paul

    2012-07-01

    The redundant two-storey brick built research facility on the AWE Site at Aldermaston, UK is in the closing stages of decommissioning and demolition. The facility was used for a variety of purposes up to 1995 predominately involving the use of alpha-emitting isotopes. The two main areas of alpha-based contamination have been decommissioned with the removal of hot -boxes and fume cupboards on the ground floor and HEPA filter units and ventilation equipment on the first floor. Many of these activities were undertaken using both airline fed suits, (supplied via a free standing mobile unit), and full face respirators. Asbestos materials were located and cleared from the first floor by specialist contractor. All sections of active drain running from the building to the site active effluent disposal system were removed early in the program using established techniques with specialist monitoring equipment used to provide confidence in the data required for disposal of the decommissioning debris. In particular a dedicated High Resolution Gamma Spectrometer (radioactive materials scanning unit) was utilized to categorise waste drums and wrapped packages. The building has been decommissioned and the monitoring and sampling of the structure was completed in November 2011 - the results demonstrating that the building was clear of contamination in accordance with UK clearance and exemption requirements. The demolition plan was developed and implemented in December with site excavation of foundations and site clearance currently ongoing in preparation for final site backfill activities and project close. A number of useful lessons have been learnt during the operations and are set out at the rear of the main text. (authors)

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

    SciTech Connect

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

    2003-02-27

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

  10. Lead Paint Analyzer. Deactivation and Decommissioning Focus Area. OST Reference #2317

    SciTech Connect

    None, None

    1999-09-01

    The U.S. Department of Energy (DOE) continually seeks safer and more cost-effective technologies for use in decontamination and decommissioning (D&D) of nuclear facilities. To this end, the Deactivation and Decommissioning Focus Area (DDFA) of the DOE’s Office of Science and Technology (OST) sponsors Large-Scale Demonstration and Deployment Projects (LSDDP). At these LSDDPs, developers and vendors of improved or innovative technologies showcase products that are potentially beneficial to DOE’s projects, and to others in the D&D community. Benefits sought include decreased health and safety risks to personnel and the environment, increased productivity, and decreased cost of operation. The Idaho National Engineering and Environmental Laboratory (INEEL) LSDDP generated a list of statements defining specific needs or problems where improved technology could be incorporated into ongoing D&D tasks. One of the stated needs was for a Lead Paint Analyzer that would reduce costs and shorten schedules in DOE’s Decommissioning Project. The Niton 700 Series Multi-element Analyzer is a hand-held, battery-operated unit that uses x-ray fluorescence spectroscopy (XRF) to analyze 25 elements, including the presence of lead in paint. The baseline technologies consist of collecting field samples and sending the samples to a laboratory for analysis. This demonstration investigated the associated costs and the required time to take an analysis with the multi-element analyzer with respect to the baseline technology. The Niton 700 Series Multi-element Analyzer performs in situ real-time analyses to identify and quantify lead, chromium, cadmium, and other metals in lead-based paint. Benefits expected from using the multi-element spectrum analyzer include: Reduced cost; Easier use; Reduced schedules in DOE’s decommissioning projects.

  11. FRHAM-TEX{trademark} cool suit - OST reference No. 1854. Deactivation and decommissioning focus area

    SciTech Connect

    1998-02-01

    This paper describes a demonstration project for the FRHAM-TEX Cool Suit{trademark} manufactured by FRHAM Safety Products. It is a one-piece, disposable, breathable, waterproof coverall designed to permit moisture generated by the wearer to be transmitted outside the suit. The performance of this suit was compared to a Tyvek{reg_sign} suit as a baseline. The suit is proposed as safety ware for workers at decontamination and decommissioning projects.

  12. Nevada Test Site Decontamination and Decommissioning Program History, Regulatory Framework, and Lessons Learned

    SciTech Connect

    Michael R. Kruzic, Bechtel Nevada; Patrick S. Morris, Bechtel Nevada; Jerel G. Nelson, Polestar Applied Technology, Inc.

    2005-08-07

    Decontamination and Decommissioning (D&D) of radiologically and/or chemically contaminated facilities at the Nevada Test Site (NTS) are the responsibility of the Environmental Restoration (ER) Project. Facilities identified for D&D are listed in the Federal Facilities Agreement and Consent Order (FFACO) and closed under the Resource Conservation and Recovery Act process. This paper discusses the NTS D&D program, including facilities history, D&D regulatory framework, and valuable lessons learned.

  13. Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 12. Environmental Restoration Program

    SciTech Connect

    Not Available

    1991-09-01

    The 664 abstracted references on environmental restoration, nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the twelfth in a series of reports prepared annually for the US Department of Energy 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 Remedial Action Programs. Major sections are (1) Decontamination and Decommissioning 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) 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 key word. This report is a product of the Remedial Action Program Information Center (RAPIC), which selects, analyzes, and disseminates information on environmental restoration and remedial actions. RAPIC staff and resources are available to meet a variety of information needs. Contact the center at FTS 624-7764 or (615) 574-7764.

  14. Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 12

    SciTech Connect

    Owen, P. T.; Webb, J. R.; Knox, N. P.; Goins, L. F.; Harrell, R. E.; Mallory, P. K.; Cravens, C. D.

    1991-09-01

    The 664 abstracted references on environmental restoration, nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the twelfth in a series of reports prepared annually for the US Department of Energy 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 Remedial Action Programs. Major sections are (1) Decontamination and Decommissioning 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) 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 key word. This report is a product of the Remedial Action Program Information Center (RAPIC), which selects, analyzes, and disseminates information on environmental restoration and remedial actions. RAPIC staff and resources are available to meet a variety of information needs. Contact the center at FTS 624-7764 or (615) 574-7764.

  15. Lessons Learned Following the Successful Decommissioning of a Reaction Vessel Containing Lime Sludge and Technetium-99

    SciTech Connect

    Dawson, P. M.; Watson, D. D.; Hylko, J. M.

    2002-02-25

    This paper documents how WESKEM, LLC utilized available source term information, integrated safety management, and associated project controls to safely decommission a reaction vessel and repackage sludge containing various Resource Conservation and Recovery Act constituents and technetium-99 (Tc-99). The decommissioning activities were segmented into five separate stages, allowing the project team to control work related decisions based on their knowledge, experience, expertise, and field observations. The information and experience gained from each previous stage and rehearsals contributed to modifying subsequent entries, further emphasizing the importance of developing hold points and incorporating lessons learned. The hold points and lessons learned, such as performing detailed personal protective equipment (PPE) inspections during sizing and repackaging operations, and using foam-type piping insulation to prevent workers from cutting or puncturing their PPE on sharp edge s or small shards generated during sizing operations, minimized direct contact with the Tc-99. To prevent the spread of contamination, the decommissioning activities were performed inside a containment enclosure connected to negative air machines. After performing over 235 individual entries totaling over 285 project hours, only one first aid was recorded during this five-stage project.

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

    SciTech Connect

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

    2009-11-09

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

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

    SciTech Connect

    Farfan, E.

    2009-09-30

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

  18. Decommissioning and Closure of the Morsleben Deep Geological Repository - The Final Step

    SciTech Connect

    Ripkens, M.; Biurrun, E.

    2002-02-26

    In Germany, a deep geologic repository for low and intermediate-level waste has been in operation since 1971. This repository, which is located in the territory of former Eastern Germany, became a Federal Facility in the wake of German reunification in 1990. Since then, waste from all of Germany was disposed of until a stop ordered by BfS in 1998. The site is now in the process of being decommissioned and later closed down. This process includes updating the concept for guaranteeing appropriate waste isolation for as long as the waste remains a hazard. During the licensing procedure being currently conducted, in line with German requirements for repository sites, the site operator must provide convincing proof of the facility's long-term safety. Thereafter, implementation of the decommissioning and closure concept will follow. It is estimated that the licensing procedure will take until the year 2006. The decommissioning and closure process itself will require about 10 years. Reliable costs estimates are not yet available. This paper briefly covers the history of the Morsleben radioactive waste repository and provides a draft update on the status of the licensing procedure.

  19. Release and disposal of materials during decommissioning of Siemens MOX fuel fabrication plant at Hanau, Germany

    SciTech Connect

    Koenig, Werner; Baumann, Roland

    2007-07-01

    In September 2006, decommissioning and dismantling of the Siemens MOX Fuel Fabrication Plant in Hanau were completed. The process equipment and the fabrication buildings were completely decommissioned and dismantled. The other buildings were emptied in whole or in part, although they were not demolished. Overall, the decommissioning process produced approximately 8500 Mg of radioactive waste (including inactive matrix material); clearance measurements were also performed for approximately 5400 Mg of material covering a wide range of types. All the equipment in which nuclear fuels had been handled was disposed of as radioactive waste. The radioactive waste was conditioned on the basis of the requirements specified for the projected German final disposal site 'Schachtanlage Konrad'. During the pre-conditioning, familiar processes such as incineration, compacting and melting were used. It has been shown that on account of consistently applied activity containment (barrier concept) during operation and dismantling, there has been no significant unexpected contamination of the plant. Therefore almost all the materials that were not a priori destined for radioactive waste were released without restriction on the basis of the applicable legal regulations (chap. 29 of the Radiation Protection Ordinance), along with the buildings and the plant site. (authors)

  20. Decontamination and decommissioning of the uranium mill and processing plant at Seelingstaedt, Germany

    SciTech Connect

    Barnekow, Ulf; Bauroth, Matthias; Paul, Michael

    2007-07-01

    In Eastern Germany uranium mining lasted from 1946 till 1990 including a production of in total 220,000 t of uranium. The Seelingstaedt Uranium Mill and Processing Plant, located in Thuringia, Germany, was one of two large uranium mills owned by Wismut. The mill was erected by 1960 and covered an area of 93 ha. From 1961 till 1991 a total of about 110 million t of different types of uranium ores were milled and processed at the Seelingstaedt mill. The mill produced ca. 110,000 t of uranium (in yellow cake). Demolition of the buildings and industrial facilities of the Seelingstaedt mill and processing plant site are nearly completed. The site is being decommissioned with respect to after-use aiming at afforestation and grasslands allowing for a stable plant succession. Decommissioning includes excavation and relocation of contaminated materials, reshaping of the site and construction of ditches for granting a stable surface runoff as well construction of access and maintenance roads. About 85% of the demolition and relocation works have been completed till to date. Last decommissioning works shall be completed by 2015. The present paper presents experiences made and progress achieved till to date. (authors)

  1. Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 13: Part 1, Main text

    SciTech Connect

    Goins, L.F.; Webb, J.R.; Cravens, C.D.; Mallory, P.K.

    1992-09-01

    This publication contains 1035 abstracted references on environmental restoration, nuclear facility decommissioning, uranium mill tailings management, and site remedial actions. These citations constitute the thirteenth in a series of reports prepared annually for the US Department of Energy (DOE) Environmental Restoration programs. Citations to foreign and domestic literature of all types. There are 13 major sections of the publication, including: (1) DOE Decontamination and Decommissioning Program; (2) Nuclear Facilities Decommissioning; (3) DOE Formerly Utilized Sites Remedial Action Program; (4) DOE Uranium Mill Tailings Remedial Action Project; (5) Uranium Mill Tailings Management; (6) DOE Environmental Restoration Program; (7) DOE Site-Specific Remedial Actions; (8) Contaminated Site Restoration; (9) Remediation of Contaminated Soil and Groundwater; (10) Environmental Data Measurements, Management, and Evaluation; (11) Remedial Action Assessment and Decision-Making; (12) Technology Development and Evaluation; and (13) Environmental and Waste Management Issues. Bibliographic references are arranged in nine subject categories by geographic location and then alphabetically by first author, corporate affiliation, or publication title. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, subject category, and key word.

  2. Decontamination and decommissioning surveillance and maintenance report for FY 1991. Environmental Restoration Program

    SciTech Connect

    Burwinkle, T. W.; Cannon, T. R.; Ford, M. K.; Holder, Jr., L.; Clotfelter, O. K.; Faulkner, R. L.; Smith, D. L.; Wooten, H. O.

    1991-12-01

    The Decontamination and Decommissioning (D&D) Program has three distinct phases: (1) surveillance and maintenance (S&M); (2) decontamination and removal of hazardous materials and equipment (which DOE Headquarters in Washington, D.C., calls Phase I of remediation); and (3) decommissioning and ultimate disposal, regulatory compliance monitoring, and property transfer (which DOE Headquarters calls Phase II of remediation). A large part of D&D is devoted to S&M at each of the sites. Our S&M activities, which are performed on facilities awaiting decommissioning, are designed to minimize potential hazards to human health and the environment by: ensuring adequate containment of residual radioactive and hazardous materials; and, providing physical safety and security controls to minimize potential hazards to on-site personnel and the general public. Typically, we classify maintenance activities as either routine or special (major repairs). Routine maintenance includes such activities as painting, cleaning, vegetation control, minor structural repairs, filter changes, and building system(s) checks. Special maintenance includes Occupational Safety and Health Act facility upgrades, roof repairs, and equipment overhaul. Surveillance activities include inspections, radiological measurements, reporting, records maintenance, and security (as required) for controlling and monitoring access to facilities. This report summarizes out FY 1991 S&M activities for the Tennessee plant sites, which include the K-25 Site, the Gas Centrifuge facilities, ORNL, and the Y-12 Plant.

  3. Nuclear facility decommissioning and site remedial actions. Volume 1. A selected bibliography

    SciTech Connect

    Faust, R.A.; Fore, C.S.; Knox, N.P.

    1980-09-01

    This bibliography of 633 references represents the first in a series to be produced by the Remedial Actions Program Information Center (RAPIC) containing scientific, technical, economic, and regulatory information concerning the decommissioning of nuclear facilities. Major chapters selected for this bibliography are Facility Decommissioning, Uranium Mill Tailings Cleanup, Contaminated Site Restoration, and Criteria and Standards. The references within each chapter are arranged alphabetically by leading author, corporate affiliation, or title of the document. When the author is not given, the corporate affiliation appears first. If these two levels of authorship are not given, the title of the document is used as the identifying level. Indexes are provided for (1) author(s), (2) keywords, (3) title, (4) technology development, and (5) publication description. An appendix of 123 entries lists recently acquired references relevant to decommissioning of nuclear facilities. These references are also arranged according to one of the four subject categories and followed by author, title, and publication description indexes. The bibliography was compiled from a specialized data base established and maintained by RAPIC to provide information support for the Department of Energy's Remedial Actions Program, under the cosponsorship of its three major components: Surplus Facilities Management Program, Uranium Mill Tailings Remedial Actions Program, and Formerly Utilized Sites Remedial Actions Program. RAPIC is part of the Ecological Sciences Information Center within the Information Center Complex at Oak Ridge National Laboratory.

  4. Overview of the 1995 NATO ARW on nuclear submarine decommissioning and related problems

    SciTech Connect

    LeSage, L.G.

    1997-10-01

    The NATO Advanced Research Workshop on Nuclear Submarine Decommissioning and Related Problems was held in Moscow June 19--22, 1995. It was preceded by a visit to the Zvezdotchka Shipyard at Severodvinsk, a repair and maintenance yard for Russian nuclear submarines, for a subgroup of the workshop attendees. Most of the material in this paper is drawn directly form the workshop proceedings. Slightly less than 500 nuclear ships and submarines (the vast majority are submarines) have been constructed by the countries with nuclear navies. This includes approximately 250 by Russia, 195 by the United States, 23 by the United Kingdom, 11 by France and 6 by China. By the year 2000 it is expected that approximately one-half of these nuclear vessels will be removed from service and in various states of decommissioning. A newspaper account in June 1997 indicated that 156 Russian nuclear submarines had been removed from service. In August 1996 it was reported that 55 reactor compartment sections from US nuclear submarines were already in long-term storage at Hanford. Overall the dismantlement of nuclear submarines and the processing, storage and disposal of nuclear fuel, activated components and section of the hulls, and the liquid and solid radioactive and hazardous wastes is an enormous problem. This problem has been exacerbated by the accelerated decommissioning schedule associated with treaty obligations.

  5. Renewables-to-reefs? - Decommissioning options for the offshore wind power industry.

    PubMed

    Smyth, Katie; Christie, Nikki; Burdon, Daryl; Atkins, Jonathan P; Barnes, Richard; Elliott, Michael

    2015-01-15

    The offshore wind power industry is relatively new but increasing globally, hence it is important that the whole life-cycle is managed. The construction-operation-decommissioning cycle is likely to take 20-30 years and whilst decommissioning may not be undertaken for many years, its management needs to be addressed in both current and future marine management regimes. This can be defined within a Drivers-Activities-Pressures-State Changes-Impacts (on human Welfare)-Responses framework. This paper considers the main decommissioning options - partial or complete removal of all components. A SWOT analysis shows environmental and economic benefits in partial as opposed to complete removal, especially if habitat created on the structures has conservation or commercial value. Benefits (and repercussions) are defined in terms of losses and gains of ecosystem services and societal benefits. The legal precedents and repercussions of both options are considered in terms of the 10-tenets of sustainable marine management. Finally a 'renewables-to-reefs' programme is proposed.

  6. Fugitive emissions of methane from abandoned, decommissioned oil and gas wells.

    PubMed

    Boothroyd, I M; Almond, S; Qassim, S M; Worrall, F; Davies, R J

    2016-03-15

    This study considered the fugitive emissions of methane (CH4) from former oil and gas exploration and production wells drilled to exploit conventional hydrocarbon reservoirs onshore in the UK. This study selected from the 66% of all onshore wells in the UK which appeared to be properly decommissioned (abandoned) that came from 4 different basins and were between 8 and 79 years old. The soil gas above each well was analysed and assessed relative to a nearby control site of similar land use and soil type. The results showed that of the 102 wells considered 30% had soil gas CH4 at the soil surface that was significantly greater than their respective control. Conversely, 39% of well sites had significant lower surface soil gas CH4 concentrations than their respective control. We interpret elevated soil gas CH4 concentrations to be the result of well integrity failure, but do not know the source of the gas nor the route to the surface. Where elevated CH4 was detected it appears to have occurred within a decade of it being drilled. The flux of CH4 from wells was 364 ± 677 kg CO2eq/well/year with a 27% chance that the well would have a negative flux to the atmosphere independent of well age. This flux is low relative to the activity commonly used on decommissioned well sites (e.g. sheep grazing), however, fluxes from wells that have not been appropriately decommissioned would be expected to be higher.

  7. [Drug facilitated sexual assault].

    PubMed

    Alempijević, Djordje; Savić, Slobodan; Stojanović, Jovan; Spasić, Andjelka

    2007-01-01

    In line with the fact that there is little information regarding drug facilitated sexual assault in national medical literature, the authors aimed to prepare a review of the phenomenon based on available international references. Therefore we offered a definition of the concept of sexual assault, and rape in particular. Consent and ability for valid consent for sexual intercourse were defined as well. A review contains discussion about the basic elements of a concept of drug-facilitated sexual assault. There is also available information in regard to pharmacology of common data rape drugs, i.e. flunitrazepam, gamma-hydroxybutyrate (GHB), and ketamine. We indicate the utmost importance of prompt collecting of biological samples for toxicological screening in patients who are suspected victims of drug facilitated sexual assault.

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

    SciTech Connect

    1997-12-01

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

  9. Understanding Facilitation: Theory and Principles.

    ERIC Educational Resources Information Center

    Hogan, Christine

    This book introduces newcomers to the concept of facilitation, and it presents a critical analysis of established and current theory on facilitation for existing practitioners. The following are among the topics discussed: (1) emergence of the field of facilitation; (2) development of facilitation in management; (3) development of facilitation in…

  10. Recycling Of Uranium- And Plutonium-Contaminated Metals From Decommissioning Of The Hanau Fuel Fabrication Plant

    SciTech Connect

    Kluth, T.; Quade, U.; Lederbrink, F. W.

    2003-02-26

    Decommissioning of a nuclear facility comprises not only actual dismantling but also, above all, management of the resulting residual materials and waste. Siemens Decommissioning Projects (DP) in Hanau has been involved in this task since 1995 when the decision was taken to decommission and dismantle the Hanau Fuel Fabrication Plant. Due to the decommissioning, large amounts of contaminated steel scrap have to be managed. The contamination of this metal scrap can be found almost exclusively in the form of surface contamination. Various decontamination technologies are involved, as there are blasting and wiping. Often these methods are not sufficient to meet the free release limits. In these cases, SIEMENS has decided to melt the scrap at Siempelkamp's melting plant. The plant is licensed according to the German Radiation Protection Ordinance Section 7 (issue of 20.07.2001). The furnace is a medium frequency induction type with a load capacity of 3.2 t and a throughput of 2 t/h for steel melting. For safety reasons, the furnace is widely operated by remote handling. A highly efficient filter system of cyclone, bag filter and HEPA-filter in two lines retains the dust and aerosol activity from the off-gas system. The slag is solidified at the surface of the melt and gripped before pouring the liquid iron into a chill. Since 1989, in total 15,000 t have been molten in the plant, 2,000 t of them having been contaminated steel scrap from the decommissioning of fuel fabrication plants. Decontamination factors could be achieved between 80 and 100 by the high affinity of the uranium to the slag former. The activity is transferred to the slag up to nearly 100 %. Samples taken from metal, slag and dust are analyzed by gamma measurements of the 186 keV line of U235 and the 1001 keV line of Pa234m for U238. All produced ingots showed a remaining activity less than 1 Bq/g and could be released for industrial reuse.

  11. Suspended-sediment concentrations during dam decommissioning in the Elwha River, Washington

    USGS Publications Warehouse

    Curran, Christopher A.; Magirl, Christopher S.; Duda, Jeffrey J.

    2013-01-01

    In 2011, the National Park Service commenced the incremental removal of two century-old dams along the Elwha River, Washington, in order to restore ecological and sediment-delivery processes (U.S. Department of the Interior, 1996; Duda and others, 2008, 2011; Curran and others, 2009). Elwha Dam (32-m high; 8 km from the Strait of Juan de Fuca) was completed in 1913, and Glines Canyon Dam (64-m high; 22 km from the Strait of Juan de Fuca) was completed in 1927 (fig. 1). Elwha Dam formed Lake Aldwell and Glines Canyon Dam formed Lake Mills. During the decommissioning period, each dam was notched from the top down in progressive steps to allow a metered release of sediment to downstream river reaches (Randle and others, 1996; Randle and Bountry, 2010; Czuba and others, 2011). Throughout the project, decommissioning was periodically ceased (termed “deconstruction hold periods”) to reduce effects of increased sediment concentration on migrating fish or to accomplish sediment-transport management targets (U.S. Department of the Interior, 1996; Czuba and others, 2011). Dam decommissioning started in September 2011 with both dams. Elwha Dam was completely removed by April 2012, which permitted unregulated release of sediment trapped in Lake Aldwell. Lake Mills Reservoir ceased to exist in autumn 2012 as the prograding delta of sediment in the reservoir finally abutted the lowered Glines Canyon Dam structure. In cooperation with the U.S. Environmental Protection Agency and the National Park Service, the U.S. Geological Survey (USGS) was asked to measure turbidity and calculate suspended-sediment concentrations in the lower Elwha River during the dam-decommissioning and river-restoration project. During the project, USGS operated a turbidity sensor at a water-quality monitoring station in the lower Elwha River (fig. 1), which collected data at 15-min increments. The USGS also collected suspended-sediment samples from the lower Elwha River about 380 m downstream of the

  12. The Belgoprocess Strategy Relating to the Management of Materials from Decommissioning

    SciTech Connect

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

    2003-02-27

    Belgium started its nuclear program quite early. The first installations were constructed in the fifties, and presently, more than 55 % of the Belgian electricity production is provided by nuclear power plants. After 30 years of nuclear experience, Belgium started decommissioning of nuclear facilities in the eighties with two main projects: the BR3-PWR plant and the Eurochemic reprocessing plant. The BR3-decommissioning project is carried out at the Belgian Nuclear Research Centre, while the decommissioning of the former Eurochemic reprocessing plant is managed and operated by Belgoprocess n.v., which is also operating the centralized waste treatment facilities and the interim storage for Belgian radioactive waste. Some fundamental principles have to be considered for the management of materials resulting from the decommissioning of nuclear installations, equipment and/or components, mainly based on the guidelines of the ''IAEA-Safety Fundamentals. The Principles of Radioactive Waste Management. Safety Series No. 111-F, IAEA, Vienna, 1995'' with respect to radioactive waste management. Two of the fundamental principles indicated in this document are specifically dealing with the strategy for the management of materials from decommissioning, ''Generation of radioactive waste shall be kept to the minimum practicable'' (seventh principle), and ''Radioactive waste shall be managed in such a way that it will not impose undue burdens on future generations'' (fifth principle). Based on these fundamental principles, Belgoprocess has made a straightforward choice for a strategy with minimization of the amount of materials to be managed as radioactive waste. This objective is obtained through the use of advanced decontamination techniques and the unconditional release of decontaminated materials. Unconditionally released materials are recycled, such as i.e., metal materials that are removed to conventional melting facilities, or are removed to conventional industrial

  13. Facilitation of Adult Development

    ERIC Educational Resources Information Center

    Boydell, Tom

    2016-01-01

    Taking an autobiographical approach, I tell the story of my experiences facilitating adult development, in a polytechnic and as a management consultant. I relate these to a developmental framework of Modes of Being and Learning that I created and elaborated with colleagues. I connect this picture with a number of related models, theories,…

  14. Facilitator's Guide: Censorship Workshop.

    ERIC Educational Resources Information Center

    Layden, Kent

    To help leaders or "facilitators" of a series of simulation exercises on controversial issues for school board members, this guide describes how the simulations work and provides some of the materials required for the simulation exercise on censorship and book banning. After defining simulation or gaming exercises, the author notes the…

  15. Facilitating Distance Education.

    ERIC Educational Resources Information Center

    Rossman, Mark H., Ed.; Rossman, Maxine E., Ed.

    1995-01-01

    This collection of articles on distance learning reflects the perspectives and concerns of the learner and the facilitator of learning in distance education setting. Eight chapters are included: (1) "The Evolution and Advantages of Distance Education" (John E. Cantelon) traces the history of distance education and demonstrates how it transcends…

  16. Facilitative Strategies in Action.

    ERIC Educational Resources Information Center

    Fuller, Thara M. A.; Haugabrook, Adrian K.

    2001-01-01

    Describes campus-based strategies to facilitate collaboration by examining the process of restructuring a division of student affairs as an educational partner with academic affairs. Describes three collaborative efforts at the University of Massachusetts Boston: the Beacon Leadership Project, the Diversity Research Initiative, and the Beacon…

  17. The Inclusion Facilitator's Guide

    ERIC Educational Resources Information Center

    Jorgensen, Cheryl M.; Schuh, Mary C.; Nisbet, Jan

    2005-01-01

    Inclusion facilitators are educators who do more than teach children with disabilities--they advocate for change in schools and communities, sparking a passion for inclusion in teachers, administrators, and families and giving them the practical guidance they need to make it work. This is an essential new role in today's schools, and this guide…

  18. Program Facilitates Distributed Computing

    NASA Technical Reports Server (NTRS)

    Hui, Joseph

    1993-01-01

    KNET computer program facilitates distribution of computing between UNIX-compatible local host computer and remote host computer, which may or may not be UNIX-compatible. Capable of automatic remote log-in. User communicates interactively with remote host computer. Data output from remote host computer directed to local screen, to local file, and/or to local process. Conversely, data input from keyboard, local file, or local process directed to remote host computer. Written in ANSI standard C language.

  19. Revised analyses of decommissioning for the reference pressurized Water Reactor Power Station. Volume 2, Effects of current regulatory and other considerations on the financial assurance requirements of the decommissioning rule and on estimates of occupational radiation exposure: Appendices, Final report

    SciTech Connect

    Konzek, G.J.; Smith, R.I.; Bierschbach, M.C.; McDuffie, P.N.

    1995-11-01

    With the issuance of the final Decommissioning Rule (July 27, 1998), owners and operators of licensed nuclear power plants are required to prepare, and submit to the US Nuclear Regulatory Commission (NRC) for review, decommissioning plans and cost estimates. The NRC staff is in need of bases documentation that will assist them in assessing the adequacy of the licensee submittals, from the viewpoint of both the planned actions, including occupational radiation exposure, and the probable costs. The purpose of this reevaluation study is to provide some of the needed bases documentation. This report contains the results of a review and reevaluation of the 1978 PNL decommissioning study of the Trojan nuclear power plant (NUREG/CR-0130), including all identifiable factors and cost assumptions which contribute significantly to the total cost of decommissioning the nuclear power plant for the DECON, SAFSTOR, and ENTOMB decommissioning alternatives. These alternatives now include an initial 5--7 year period during which time the spent fuel is stored in the spent fuel pool, prior to beginning major disassembly or extended safe storage of the plant. Included for information (but not presently part of the license termination cost) is an estimate of the cost to demolish the decontaminated and clean structures on the site and to restore the site to a ``green field`` condition. This report also includes consideration of the NRC requirement that decontamination and decommissioning activities leading to termination of the nuclear license be completed within 60 years of final reactor shutdown, consideration of packaging and disposal requirements for materials whose radionuclide concentrations exceed the limits for Class C low-level waste (i.e., Greater-Than-Class C), and reflects 1993 costs for labor, materials, transport, and disposal activities.

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

    SciTech Connect

    J. P. Floerke

    2007-02-05

    Test Area North (TAN) -607, the Technical Support Facility, is located at the north end of the Idaho National Laboratory (INL) Site. U.S. Department of Energy Idaho Operations Office (DOE-ID) is proposing to decommission the northern section of the TAN-607 facility, hereinafter referred to as TAN-607 Hot Shop Area, under a Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) non-time-critical removal action (NTCRA). Despite significant efforts by the United States (U.S.) Department of Energy (DOE) to secure new business, no future mission has been identified for the TAN-607 Hot Shop Area. Its disposition has been agreed to by the Idaho State Historical Preservation Office documented in the Memorandum of Agreement signed October 2005 and it is therefore considered a surplus facility. A key element in DOE's strategy for surplus facilities is decommissioning to the maximum extent possible to ensure risk and building footprint reduction and thereby eliminating operations and maintenance cost. In addition, the DOE's 2006 Strategic Plan is ''complete cleanup of the contaminated nuclear weapons manufacturing and testing sites across the United States. DOE is responsible for the risk reduction and cleanup of the environmental legacy of the Nation's nuclear weapons program, one of the largest, most diverse, and technically complex environmental programs in the world. The Department will successfully achieve this strategic goal by ensuring the safety of the DOE employees and U.S. citizens, acquiring the best resources to complete the complex tasks, and managing projects throughout the United States in the most efficient and effective manner.'' TAN-607 is designated as a historical Signature Property by DOE Headquarters Advisory Council on Historic Preservation and, as such, public participation is required to determine the final disposition of the facility. The decommissioning action will place the TAN-607 Hot Shop Area in a final configuration that

  1. 30 CFR 285.529 - Can I use a lease- or grant-specific decommissioning account to meet the financial assurance...

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... Assurance Requirements Requirements for Financial Assurance Instruments § 285.529 Can I use a lease- or... 30 Mineral Resources 2 2010-07-01 2010-07-01 false Can I use a lease- or grant-specific decommissioning account to meet the financial assurance requirements related to decommissioning? 285.529...

  2. Characterization of the Hanford 300 area burial grounds. Final report: decontamination and decommissioning

    SciTech Connect

    Phillips, S.J.; Ames, L.L.; Fitzner, R.E.; Gee, G.W.; Sandness, G.A.; Simmons, C.S.

    1980-01-01

    Pacific Northwest Laboratory conducted a series of investigations at the Hanford Site to develop technologies for characterizing and monitoring radioactive waste burial facilities that could be used in determining appropriate decommissioning alternatives. Specific objectives were to develop unique functional geophysics, geochemical, soil physics, numerical modeling, and biological methodologies needed to better characterize and monitor buried radioactive waste disposal sites. To meet these objectives the project was divided into four tasks: Task I, Geophysical Evaluation - Geophysical surveys were taken to locate and define the gross composition of waste materials. Task II, Geochemical Analysis - The interaction of disposed radionuclides with geologic media was analyzed through an integrated radiochemical procedure. Task III, Fluid Transport and Modeling - Computer modeling of water migration in partially saturated groundwater systems was verified with actual data collected at a field test facility used to monitor micrometeorological and geohydrological energy and mass transfer factors. Task IV, Biological Transport - Several biological organisms were evaluated for potential radionuclide uptake and transport. Along with the four tasks, the project included a review of pertinent literature and regulatory issues that might affect the alternatives selected. Surveys were taken of the surrounding area and specific sites and operations. The overall results indicated that the 300 Area Burial Grounds have been adequate in containing radioactive waste. Based on the results of the project, the alternatives identified for decommissioning these sites are exhumation and translocation, entombment, perpetual care, and abandonment. Perpetual care (currently used) appears to be the best decommissioning alternative for these burial grounds at this time. However, another alternative may be selected depending on future waste management policies, plans, or activities.

  3. Adapting Dismantling and Decommissioning Strategies to a Variety of Nuclear Fuel Cycle Facilities - 12237

    SciTech Connect

    Chambon, Frederic; Clement, Gilles

    2012-07-01

    AREVA has accumulated over 20 years of experience in managing and operating fuel cycle facilities Decontamination and Decommissioning (D and D) projects of many different types and a variety of scales, both as facility owner (at La Hague for example) and as prime contractor to external customers such as the French Atomic Energy Commission (at Marcoule). A specific Business Unit was created in 2008 to capitalize on this experience and to concentrate - in one division - the specific skills required to be successful and cost effective in decommissioning projects. Indeed one of the key lessons learned in the past decades is that decommissioning is a significantly different business as compared to normal operations of a nuclear facility. Almost all the functions of a project need to be viewed from a different angle, challenged and adapted consequently in order to optimize costs and schedule. Three examples follow to illustrate the point: Safety management needs to take into account the ever changing configuration of a plant under D and D (a quite new situation for the authorities). Production of waste is significantly different in term of volume, activities, conditioning and disposal path. Technology is important but technical issues are often less critical than good management and planning. Further examples and lessons learned are developed through reviewing the projects experience basis. AREVA has a long and vast experience in the cleanup and dismantling of a number of very large and complex nuclear facilities. This effort focused initially on AREVA's own plants and is expanding now to other customers. The setup of a specific Business Unit in 2008 to takeover this business allowed concentration of the skills and the lessons learned in a dedicated division so as to provide the best means to optimize safety, performance, costs and schedules. Indeed transitioning from operations to D and D of a nuclear facility is a quantum leap. The assistance from specialized teams can

  4. Nuclear Rocket Facility Decommissioning Project: Controlled Explosive Demolition of Neutron Activated Shield Wall

    SciTech Connect

    Michael R. Kruzic

    2007-09-16

    Located in Area 25 of the Nevada Test Site (NTS), the Test Cell A (TCA) Facility was used in the early to mid-1960s for the testing of nuclear rocket engines, as part of the Nuclear Rocket Development Program, to further space travel. Nuclear rocket testing resulted in the activation of materials around the reactors and the release of fission products and fuel particles in the immediate area. Identified as Corrective Action Unit 115, the TCA facility was decontaminated and decommissioned (D&D) from December 2004 to July 2005 using the Streamlined Approach for Environmental Restoration (SAFER) process, under the ''Federal Facility Agreement and Consent Order''. The SAFER process allows environmental remediation and facility closure activities (i.e., decommissioning) to occur simultaneously provided technical decisions are made by an experienced decision maker within the site conceptual site model, identified in the Data Quality Objective process. Facility closure involved a seven-step decommissioning strategy. Key lessons learned from the project included: (1) Targeted preliminary investigation activities provided a more solid technical approach, reduced surprises and scope creep, and made the working environment safer for the D&D worker. (2) Early identification of risks and uncertainties provided opportunities for risk management and mitigation planning to address challenges and unanticipated conditions. (3) Team reviews provided an excellent mechanism to consider all aspects of the task, integrated safety into activity performance, increase team unity and ''buy-in'' and promoted innovative and time saving ideas. (4) Development of CED protocols ensured safety and control. (5) The same proven D&D strategy is now being employed on the larger ''sister'' facility, Test Cell C.

  5. Allowable residual-contamination levels for decommissioning facilities in the 100 areas of the Hanford Site

    SciTech Connect

    Kennedy, W.E. Jr.; Napier, B.A.

    1983-07-01

    This report contains the results of a study sponsored by UNC Nuclear Industries to determine Allowable Residual Contamination Levels (ARCL) for five generic categories of facilities in the 100 Areas of the Hanford Site. The purpose of this study is to provide ARCL data useful to UNC engineers in conducting safety and cost comparisons for decommissioning alternatives. The ARCL results are based on a scenario/exposure-pathway analysis and compliance with an annual dose limit for three specific modes of future use of the land and facilities. These modes of use are restricted, controlled, and unrestricted. The information on ARCL values for restricted and controlled use provided by this report is intended to permit a full consideration of decommissioning alternatives. ARCL results are presented both for surface contamination remaining in facilities (in dpm/100 cm/sup 2/), and for unconfined surface and confined subsurface soil conditions (in pCi/g). Two confined soil conditions are considered: contamination at depths between 1 and 4 m, and contamination at depths greater than or equal to 5 m. A set of worksheets are presented in an appendix for modifying the ARCL values to accommodate changes in the radionuclide mixture or concentrations, to consider the impacts of radioactive decay, and to predict instrument responses. Finally, a comparison is made between the unrestricted release ARCL values for the 100 Area facilities and existing decommissioning and land disposal regulations. For surface contamination, the comparison shows good agreement. For soil contamination, the comparison shows good agreement if reasonable modification factors are applied to account for the differences in modeling soil contamination and licensed low-level waste.

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

    SciTech Connect

    1980-06-01

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

  7. SAVANNAH RIVER SITE R-REACTOR DISASSEMBLY BASIN IN-SITU DECOMMISSIONING -10499

    SciTech Connect

    Langton, C.; Serrato, M.; Blankenship, J.; Griffin, W.

    2010-01-04

    The US DOE concept for facility in-situ decommissioning (ISD) is to physically stabilize and isolate intact, structurally sound facilities that are no longer needed for their original purpose, i.e., generating (reactor facilities), processing(isotope separation facilities) or storing radioactive materials. The 105-R Disassembly Basin is the first SRS reactor facility to undergo the in-situ decommissioning (ISD) process. This ISD process complies with the 105-R Disassembly Basin project strategy as outlined in the Engineering Evaluation/Cost Analysis for the Grouting of the R-Reactor Disassembly Basin at the Savannah River Site and includes: (1) Managing residual water by solidification in-place or evaporation at another facility; (2) Filling the below grade portion of the basin with cementitious materials to physically stabilize the basin and prevent collapse of the final cap - Sludge and debris in the bottom few feet of the basin will be encapsulated between the basin floor and overlying fill material to isolate it from the environment; (3) Demolishing the above grade portion of the structure and relocating the resulting debris to another location or disposing of the debris in-place; and (4) Capping the basin area with a concrete slab which is part of an engineered cap to prevent inadvertent intrusion. The estimated total grout volume to fill the 105-R Reactor Disassembly Basin is 24,384 cubic meters or 31,894 cubic yards. Portland cement-based structural fill materials were designed and tested for the reactor ISD project, and a placement strategy for stabilizing the basin was developed. Based on structural engineering analyses and material flow considerations, maximum lift heights and differential height requirements were determined. Pertinent data and information related to the SRS 105-R Reactor Disassembly Basin in-situ decommissioning include: regulatory documentation, residual water management, area preparation activities, technology needs, fill material

  8. Technology, safety and costs of decommissioning reference nuclear fuel cycle facilities

    SciTech Connect

    Elder, H.K.

    1986-05-01

    The radioactive wastes expected to result from decommissioning nuclear fuel cycle facilities are reviewed and classified in accordance with 10 CFR 61. Most of the wastes from the MOX plant (exclusive of the lagoon wastes) will require interim storage (11% Class A 49 m/sup 3/; 89% interim storage, 383 m/sup 3/). The MOX plant lagoon wastes are Class A waste (2930 m/sup 3/). All of the wastes from the U-Fab and UF/sub 6/ plants are designated as Class A waste (U-Fab 1090 m/sup 3/, UF/sub 6/ 1259 m/sup 3/).

  9. Decommissioning the Fuel Process Building, a Shift in Paradigm for Terminating Safeguards on Process Holdup

    SciTech Connect

    Ivan R. Thomas

    2010-07-01

    INMM Abstract 51st Annual Meeting Decommissioning the Fuel Process Building, a Shift in Paradigm for Terminating Safeguards on Process Holdup The Fuel Process Building at the Idaho Nuclear Technology and Engineering Center (INTEC) is being decommissioned after nearly four decades of recovering high enriched uranium from various government owned spent nuclear fuels. The separations process began with fuel dissolution in one of multiple head-ends, followed by three cycles of uranium solvent extraction, and ending with denitration of uranyl nitrate product. The entire process was very complex, and the associated equipment formed an extensive maze of vessels, pumps, piping, and instrumentation within several layers of operating corridors and process cells. Despite formal flushing and cleanout procedures, an accurate accounting for the residual uranium held up in process equipment over extended years of operation, presented a daunting safeguards challenge. Upon cessation of domestic reprocessing, the holdup remained inaccessible and was exempt from measurement during ensuing physical inventories. In decommissioning the Fuel Process Building, the Idaho Cleanup Project, which operates the INTEC, deviated from the established requirements that all nuclear material holdup be measured and credited to the accountability books and that all nuclear materials, except attractiveness level E residual holdup, be transferred to another facility. Instead, the decommissioning involved grouting the process equipment in place, rather than measuring and removing the contained holdup for subsequent transfer. The grouting made the potentially attractiveness level C and D holdup even more inaccessible, thereby effectually converting the holdup to attractiveness level E and allowing for termination of safeguards controls. Prior to grouting the facility, the residual holdup was estimated by limited sampling and destructive analysis of solutions in process lines and by acceptable knowledge

  10. Decontamination and decommissioning of the BORAX-V leach pond. Final report

    SciTech Connect

    Smith, D.L.

    1985-01-01

    This report describes the decontamination and decommissioning (D and D) of the BORAX-V leach pond located at the Idaho National Engineering Laboratory (INEL). The leach pond became radioactively contaminated from the periodic discharge of low-level liquid waste during operation of the Boiling Water Reactor Experiments (BORAX) from 1954 to 1964. This report describes work performed to accomplish the D and D objectives of stabilizing the leach pond and preventing the spread of contamination. D and D of the BORAX-V leach pond consisted to backfilling the pond with clean soil, grading and seeding the area, and erecting a permanent marker to identify very low-level subsurface contamination.

  11. ASTM STANDARD GUIDE FOR EVALUATING DISPOSAL OPTIONS FOR REUSE OF CONCRETE FROM NUCLEAR FACILITY DECOMMISSIONING

    SciTech Connect

    Phillips, Ann Marie; Meservey, Richard H.

    2003-02-27

    Within the nuclear industry, many contaminated facilities that require decommissioning contain huge volumes of concrete. This concrete is generally disposed of as low-level waste at a high cost. Much of the concrete is lightly contaminated and could be reused as roadbed, fill material, or aggregate for new concrete, thus saving millions of dollars. However, because of the possibility of volumetric contamination and the lack of a method to evaluate the risks and costs of reusing concrete, reuse is rarely considered. To address this problem, Argonne National Laboratory-East (ANL-E) and the Idaho National Engineering and Environmental Laboratory teamed to write a ''concrete protocol'' to help evaluate the ramifications of reusing concrete within the U.S. Department of Energy (DOE). This document, titled the Protocol for Development of Authorized Release Limits for Concrete at U.S. Department of Energy Site (1) is based on ANL-E's previously developed scrap metal recycle protocols; on the 10-step method outlined in DOE's draft handbook, Controlling Release for Reuse or Recycle of Property Containing Residual Radioactive Material (2); and on DOE Order 4500.5, Radiation Protection of the Public and the Environment (3). The DOE concrete protocol was the basis for the ASTM Standard Guide for Evaluating Disposal Options for Concrete from Nuclear Facility Decommissioning, which was written to make the information available to a wider audience outside DOE. The resulting ASTM Standard Guide is a more concise version that can be used by the nuclear industry worldwide to evaluate the risks and costs of reusing concrete from nuclear facility decommissioning. The bulk of the ASTM Standard Guide focuses on evaluating the dose and cost for each disposal option. The user calculates these from the detailed formulas and tabulated data provided, then compares the dose and cost for each disposal option to select the best option that meets regulatory requirements. With this information

  12. Industrial Hygiene Concerns during the Decontamination and Decommissioning of the Tokamak Fusion Test Reactor

    SciTech Connect

    M.E. Lumia; C.A. Gentile

    2002-01-18

    A significant industrial hygiene concern during the Decontamination and Decommissioning (D and D) of the Tokamak Fusion Test Reactor (TFTR) was the oxidation of the lead bricks' surface, which were utilized for radiation shielding. This presented both airborne exposure and surface contamination issues for the workers in the field removing this material. This paper will detail the various protection and control methods tested and implemented to protect the workers, including those technologies deployed to decontaminate the work surfaces. In addition, those techniques employed to recycle the lead for additional use at the site will be discussed.

  13. Nuclear Rocket Facility Decommissioning Project: Controlled Explosive Demolition of Neutron-Activated Shield Wall

    SciTech Connect

    Michael R. Kruzic

    2008-06-01

    Located in Area 25 of the Nevada Test Site (NTS), the Test Cell A (TCA) Facility (Figure 1) was used in the early to mid-1960s for testing of nuclear rocket engines, as part of the Nuclear Rocket Development Program, to further space travel. Nuclear rocket testing resulted in the activation of materials around the reactors and the release of fission products and fuel particles. The TCA facility, known as Corrective Action Unit 115, was decontaminated and decommissioned (D&D) from December 2004 to July 2005 using the Streamlined Approach for Environmental Restoration (SAFER) process, under the Federal Facility Agreement and Consent Order. The SAFER process allows environmental remediation and facility closure activities (i.e., decommissioning) to occur simultaneously, provided technical decisions are made by an experienced decision maker within the site conceptual site model. Facility closure involved a seven-step decommissioning strategy. First, preliminary investigation activities were performed, including review of process knowledge documentation, targeted facility radiological and hazardous material surveys, concrete core drilling and analysis, shield wall radiological characterization, and discrete sampling, which proved to be very useful and cost-effective in subsequent decommissioning planning and execution and worker safety. Second, site setup and mobilization of equipment and personnel were completed. Third, early removal of hazardous materials, including asbestos, lead, cadmium, and oil, was performed ensuring worker safety during more invasive demolition activities. Process piping was to be verified void of contents. Electrical systems were de-energized and other systems were rendered free of residual energy. Fourth, areas of high radiological contamination were decontaminated using multiple methods. Contamination levels varied across the facility. Fixed beta/gamma contamination levels ranged up to 2 million disintegrations per minute (dpm)/100

  14. Task 21 - Development of Systems Engineering Applications for Decontamination and Decommissioning Activities

    SciTech Connect

    Erickson, T.A.

    1998-11-01

    The objectives of this task are to: Develop a model (paper) to estimate the cost and waste generation of cleanup within the Environmental Management (EM) complex; Identify technologies applicable to decontamination and decommissioning (D and D) operations within the EM complex; Develop a database of facility information as linked to project baseline summaries (PBSs). The above objectives are carried out through the following four subtasks: Subtask 1--D and D Model Development, Subtask 2--Technology List; Subtask 3--Facility Database, and Subtask 4--Incorporation into a User Model.

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

    SciTech Connect

    Soo, P.; Roberts, T.C.

    1995-07-01

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

  16. Environmental Assessment for decontaminating and decommissioning the General Atomics Hot Cell Facility. Final [report

    SciTech Connect

    1995-08-01

    This EA evaluates the proposed action to decontaminate and decommission GA`s hot cell facility in northern San Diego, CA. This facility has been used for DOE and commercial nuclear R&D for > 30 years. About 30,000 cubic feet of decontamination debris and up to 50,000 cubic feet of contaminated soil are to be removed. Low-level radioactive waste would be shipped for disposal. It was determined that the proposal does not constitute a major federal action significantly affecting the human environment according to NEPA; therefore, a finding of no significant impact is made, and an environmental impact statement is not required.

  17. Hydrazine Blending and Storage Facility Wastewater Treatment and Decommissioning Assessment. Version 3.1

    DTIC Science & Technology

    1988-06-01

    Administrative QA/QC Plan and Health and Satety Plan 7ersonnel ........................ ... 3-63 3.6 QUALITY ASSURANCE/QUALITY CONTROL PLAN...Specific ContractorQuality Control Plan (CQCP) for Sampling and Analysis . . . 3-64 3.6,2 QA/QC Plan for Decommissioning Activities 3-65 3.7 HEALTH AND...connectors, the control panel of the mixing and blending area, and the electrical outlet north of Tank HAS-i as sites of potential hydrazine or UDMH

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

    SciTech Connect

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

    1980-06-01

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

  19. Experience of the nuclear reactors (environmental impact assessment for decommissioning) regulations 1999, as amended, in Great Britain

    SciTech Connect

    Brown, Sarah; Mattress, Elaine; Nettleton, Jo

    2007-07-01

    Available in abstract form only. Full text of publication follows: In Great Britain, the Nuclear Reactors (Environmental Impact Assessment for Decommissioning) Regulations 1999 as amended 2006 (EIADR) requires assessment of the potential environmental impacts of projects to decommission nuclear power stations and reactors. The Health and Safety Executive (HSE) is the competent authority for EIADR. The EIADR implement European Council Directive 85/337/EEC (the EIA Directive) as amended by Council Directive 97/11/EC and Council Directive 2003/35/EC the (Public Participation Directive). The purpose of the EIADR is to assess environmental effects of nuclear reactor decommissioning projects, involve the public through consultation, and make the decision-making process open and transparent. Under the regulations, any licensee wishing to begin to decommission or dismantle a nuclear power station, or other civil nuclear reactor, must apply to HSE for consent to carry out the decommissioning project, undertake an environmental impact assessment and prepare an environmental statement that summarises the environmental effects of the project. HSE will consult on the environmental statement. So far under the EIADR there have been six consents granted for decommissioning projects for Magnox Power Stations. These stations have been required as a condition of consent to submit an Environmental Management Plan on an annual basis. This allows the project to be continually reviewed and assessed to ensure that the licensee can provide detail as agreed during the review of the environmental statement and that any changes to mitigation measures are detailed. This paper summarises the EIADR process, giving particular emphasis to public participation and the decision making process, and discusses HSE's experience of EIADR with reference to specific environmental issues raised by stakeholders and current developments. (authors)

  20. REVIEW OF INDUSTRIES AND GOVERNMENT AGENCIES FOR TECHNOLOGIES APPLICABLE TO DEACTIVATION AND DECOMMISSIONING OF NUCLEAR WEAPONS FACILITIES

    SciTech Connect

    Reilkoff, T. E.; Hetland, M. D.; O'Leary, E. M.

    2002-02-25

    The Deactivation and Decommissioning Focus Area's (DDFA's) mission is to develop, demonstrate, and deploy improved deactivation and decommissioning (D&D) technologies. This mission requires that emphasis be continually placed on identifying technologies currently employed or under development in other nuclear as well as nonnuclear industries and government agencies. In support of DDFA efforts to clean up the U.S. Department of Energy's (DOE's) radiologically contaminated surplus facilities using technologies that improve worker safety, reduce costs, and accelerate cleanup schedules, a study was conducted to identify innovative technologies developed for use in nonnuclear arenas that are appropriate for D&D applications.

  1. An analytical approach to γ-ray self-shielding effects for radioactive bodies encountered nuclear decommissioning scenarios.

    PubMed

    Gamage, K A A; Joyce, M J

    2011-10-01

    A novel analytical approach is described that accounts for self-shielding of γ radiation in decommissioning scenarios. The approach is developed with plutonium-239, cobalt-60 and caesium-137 as examples; stainless steel and concrete have been chosen as the media for cobalt-60 and caesium-137, respectively. The analytical methods have been compared MCNPX 2.6.0 simulations. A simple, linear correction factor relates the analytical results and the simulated estimates. This has the potential to greatly simplify the estimation of self-shielding effects in decommissioning activities.

  2. Gamma dose rate estimation and operation management suggestions for decommissioning the reactor pressure vessel of HTR-PM

    SciTech Connect

    Sheng Fang; Hong Li; Jianzhu Cao; Wenqian Li; Feng Xie; Jiejuan Tong

    2013-07-01

    China is now designing and constructing a high temperature gas cooled reactor-pebble bed module (HTR-PM). In order to investigate the future decommissioning approach and evaluate possible radiation dose, gamma dose rate near the reactor pressure vessel was calculated for different cooling durations using QAD-CGA program. The source term of this calculation was provided by KORIGEN program. Based on the calculated results, the spatial distribution and temporal changes of gamma dose rate near reactor pressure vessel was systematically analyzed. A suggestion on planning decommissioning operation of reactor pressure vessel of HTRPM was given based on calculated dose rate and the Chinese Standard GB18871-2002. (authors)

  3. Nuclear facility decommissioning and site remedial actions: a selected bibliography. Volume 5

    SciTech Connect

    Owen, P.T.; Knox, N.P.; Chilton, B.D.; Baldauf, M.F.

    1984-09-01

    This bibliography of 756 references with abstracts on the subject of nuclear facility decommissioning, uranium mill tailings management, and site remedial actions is the fifth in a series of annual reports prepared for the US Department of Energy, Division of Remedial Action Projects. Foreign as well as domestic literature of all types - technical reports, progress reports, journal articles, conference papers, symposium proceedings, theses, books, patents, legislation, and research project descriptions - has been included in this publication. The bibliography contains scientific (basic research as well as applied technology), economic, regulatory, and legal literature pertinent to the US Department of Energy's Remedial Action Program. Major chapters are: (1) Surplus Facilities Management Program; (2) Nuclear Facilities Decommissioning; (3) Formerly Utilized Sites Remedial Action Program; (4) Uranium Mill Tailings Remedial Action Program; (5) Grand Junction Remedial Action Program; (6) Uranium Mill Tailings Management; and (7) Technical Measurements Center. Chapter sections for chapters 1, 2, 4, and 6 include Design, Planning, and Regulations; Environmental Studies and Site Surveys; Decontamination Studies; Dismantlement and Demolition; Site Stabilization and Reclamation; Waste Disposal; Remedial Action Experience; and General Studies. The references within each chapter or section are arranged alphabetically by leading author. References having no individual author are arranged by corporate author or by title. Indexes are provided for the categories of author, corporate affiliation, title, publication description, geographic location, and keywords. The Appendix contains a list of frequently used acronyms.

  4. Thermal aging of some decommissioned reactor components and methodology for life prediction

    SciTech Connect

    Chung, H.M.

    1989-03-01

    Since a realistic aging of cast stainless steel components for end-of-life or life-extension conditions cannot be produced, it is customary to simulate the thermal aging embrittlement by accelerated aging at /approximately/400/degree/C. In this investigation, field components obtained from decommissioned reactors have been examined after service up to 22 yr to provide a benchmark of the laboratory simulation. The primary and secondary aging processes were found to be identical to those of the laboratory-aged specimens, and the kinetic characteristics were also similar. The extent of the aging embrittlement processes and other key factors that are known to influence the embrittlement kinetics have been compared for the decommissioned reactor components and materials aged under accelerated conditions. On the basis of the study, a mechanistic understanding of the causes of the complex behavior in kinetics and activation energy of aging (i.e., the temperature dependence of aging embrittlement between the accelerated and reactor-operating conditions) is presented. A mechanistic correlation developed thereon is compared with a number of available empirical correlations to provide an insight for development of a better methodology of life prediction of the reactor components. 18 refs., 18 figs., 5 tabs.

  5. Summary of comments received on staff draft proposed rule on radiological criteria for decommissioning

    SciTech Connect

    Caplin, J.; Page, G.; Smith, D.; Wiblin, C.

    1994-08-01

    The Nuclear Regulatory Commission (NRC) is conducting an enhanced participatory rulemaking to establish radiological criteria for the decommissioning of NRC licensed facilities. The NRC obtained comments on the scope, issues, and approaches through a series of workshops (57 FR 58727), Generic Environmental Impact Statement (GEIS) scoping meetings (58 FR 33570), a dedicated electronic bulletin board system (58 FR 37760), and written submissions. A summary of workshop and scope-meeting comments was published as NUREG/CR-6156. On February 2, 1994, the Commission published in the Federal Register (59 FR 4868) a notice that the NRC staff had prepared a ``staff draft`` proposed rule on radiological criteria for decommissioning. Copies of the staff draft were distributed to the Agreement States, participants in the earlier meetings, and other interested parties for comment. This report summarizes the comments identified from the 96 docketed letters received on the staff draft. No analysis or response is included in this report. The comments reflect a broad spectrum of viewpoints. Two subjects on which the commenters were in general agreement were (1) that the enhanced participatory rulemaking should proceed, and (2) that the forthcoming GEIS and guidance documents are needed for better understanding of the draft rule.

  6. Nuclear facility decommissioning and site remedial actions. Volume 6. A selected bibliography

    SciTech Connect

    Owen, P.T.; Michelson, D.C.; Knox, N.P.

    1985-09-01

    This bibliography of 683 references with abstracts on the subject of nuclear facility decommissioning, uranium mill tailings management, and site remedial actions is the sixth in a series of annual reports prepared for the US Department of Energy's Remedial Action Programs. Foreign as well as domestic literature of all types - technical reports, progress reports, journal articles, conference papers, symposium proceedings, theses, books, patents, legislation, and research project descriptions - has been included. The bibliography contains scientific (basic research as well as applied technology), economic, regulatory, and legal literature pertinent to the US Department of Energy's remedial action program. Major chapters are: (1) Surplus Facilities Management Program; (2) Nuclear Facilities Decommissioning; (3) Formerly Utilized Sites Remedial Action Program; (4) Facilities Contaminated with Natural Radioactivity; (5) Uranium Mill Tailings Remedial Action Program; (6) Grand Junction Remedial Action Program; (7) Uranium Mill Tailings Management; (8) Technical Measurements Center; and (9) General Remedial Action Program Studies. Chapter sections for chapters 1, 2, 5, and 7 include Design, Planning, and Regulations; Environmental Studies and Site Surveys; Health, Safety, and Biomedical Studies; Decontamination Studies; Dismantlement and Demolition; Site Stabilization and Reclamation; Waste Disposal; Remedial Action Experience; and General Studies. The references within each chapter or section are arranged alphabetically by leading author. References having no individual author are arranged by corporate affiliation or by publication description.

  7. Nuclear facility decommissioning and site remedial actions: A selected bibliography: Volume 8

    SciTech Connect

    Owen, P.T.; Michelson, D.C.; Knox, N.P.

    1987-09-01

    The 553 abstracted references on nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the eighth in a series of reports. Foreign and domestic literature of all types - technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions - has been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of energy's remedial action program. Major chapters are Surplus Facilities Management Program, Nuclear Facilities Decommissioning, Formerly Utilized Sites Remedial Action Program, Facilities Contaminated with Naturally Occurring Radionuclides, Uranium Mill Tailings Remedial Action Program, Uranium Mill Tailings Management, Technical Measurements Center, and General Remedial Action Program Studies. Chapter sections for chapters 1, 2, 5, and 6 include Design, Planning, and Regulations; Environmental Studies and Site Surveys; Health, Safety, and Biomedical Studies; Decontamination Studies; Dismantlement and Demolition; Site Stabilization and Reclamation; Waste Disposal; Remedial Action Experience; and General 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 word, publication description, geographic location, and keywords. The appendix contains a list of frequently used acronyms and abbreviations.

  8. Effects of road decommissioning on carbon stocks, losses, and emissions in north coastal California

    USGS Publications Warehouse

    Madej, Mary A.; Seney, Joseph; van Mantgem, Philip

    2013-01-01

    During the last 3 decades, many road removal projects have been implemented on public and private lands in the United States to reduce erosion and other impacts from abandoned or unmaintained forest roads. Although effective in decreasing sediment production from roads, such activities have a carbon (C) cost as well as representing a carbon savings for an ecosystem. We assessed the carbon budget implications of 30 years of road decommissioning in Redwood National Park in north coastal California. Road restoration techniques, which evolved during the program, were associated with various carbon costs and savings. Treatment of 425 km of logging roads from 1979 to 2009 saved 72,000 megagrams (Mg) C through on-site soil erosion prevention, revegetation, and soil development on formerly compacted roads. Carbon sequestration will increase in time as forests and soils develop more fully on the restored sites. The carbon cost for this road decommissioning work, based on heavy equipment and vehicle fuel emissions, short-term soil loss, and clearing of vegetation, was 23,000 Mg C, resulting in a net carbon savings of 49,000 Mg C to date. Nevertheless, the degree to which soil loss is a carbon sink or source in steep mountainous watersheds needs to be further examined. The ratio of carbon costs to savings will differ by ecosystem and road removal methodology, but the procedure outlined here to assess carbon budgets on restoration sites should be transferable to other systems.

  9. Progress report on decommissioning activities at the Fernald Environmental Management Project (FEMP) site

    SciTech Connect

    1998-07-01

    The Fernald Environmental Management Project (FEMP), is located about 18 miles northwest of Cincinnati, Ohio. Between 1953 and 1989, the facility, then called the Feed Material Production Center or FMPC, produced uranium metal products used in the eventual production of weapons grade material for use by other US Department of Energy (DOE) sites. In 1989, FMPC`s production was suspended by the federal government in order to focus resources on environmental restoration versus defense production. In 1992, Fluor Daniel Fernald assumed responsibility for managing all cleanup activities at the FEMP under contract to the DOE. In 1990, as part of the remediation effort, the site was divided into five operable units based on physical proximity of contaminated areas, similar amounts of types of contamination, or the potential for a similar technology to be used in cleanup activities. This report continues the outline of the decontamination and decommissioning (D and D) activities at the FEMP site Operable Unit 3 (OU3) and provides an update on the status of the decommissioning activities. OU3, the Facilities Closure and Demolition Project, involves the remediation of more than 200 uranium processing facilities. The mission of the project is to remove nuclear materials stored in these buildings, then perform the clean out of the buildings and equipment, and decontaminate and dismantle the facilities.

  10. Fixed-Price Subcontracting for Decontamination and Decommissioning of Small Facilities at Oak Ridge National Laboratory

    SciTech Connect

    Harper, M. A.; Julius, J. F. K.; McKenna, M. K.

    2002-02-26

    Abandoned facilities were decontaminated and decommissioned in preparation for final remediation of Solid Waste Storage Area (SWSA) 4 at Oak Ridge National Laboratory. The facilities varied in age from approximately 5 years to more than 40 years, with radiological conditions ranging from clean to highly contaminated with fission products. A fixed-price subcontract (FPSC) was awarded by the U.S. Department of Energy's (DOE's) Environmental Management (EM) Management and Integration (M&I) contractor for decontamination and decommissioning (D&D) of these facilities. Included in the FPSC scope were the following: preparation of pre-D&D regulatory documentation; demolition of surface structures to slab; stabilization of below-grade structures; waste management and disposal; and preparation of post-D&D regulatory documentation. Using stand-off techniques to the extent possible, building structures and ancillary equipment were prepared for demolition and demolished. A fixative coating system was used in conjunction with continuous water misting to control airborne contamination. Demolition waste consisted of two major streams: clean construction and demolition waste and low-level (radioactive) waste. The debris was size-reduced and packaged, again via remote means. At all times during the D&D, personnel safety, environmental compliance, and as low as reasonably achievable exposure considerations were paramount. Upon completion of D&D activities, each site was inspected and accepted by the M&I contractor. This project is a success story for fixed-price subcontracting of D&D work under DOE's M&I arrangement.

  11. Comments received on proposed rule on radiological criteria for decommissioning and related documents

    SciTech Connect

    Page, G.; Caplin, J.; Smith, D.

    1996-03-01

    The Nuclear Regulatory Commission (NRC) is conducting an enhanced participatory rulemaking to establish radiological criteria for the decommissioning of NRC-licensed facilities. As a part of this action, the Commission published in the Federal Register (59 FR 43200), on August 22, 1994, a proposed rule on radiological criteria for decommissioning, soliciting comments both on the rule as proposed and on certain specific items as identified in its supplementary statement of considerations. A draft Generic Environmental Impact Statement (GEIS) in support of the rule, also published in August 1994 as NUREG-1496, along with its Appendix A (NUREG-1501), were also made available for comment. A staff working draft on regulatory guidance (NUREG-1500)was also made available. This report summarizes the 1,309 comments on the proposed rule and supplementary items and the 311 comments on the GEIS as excerpted from 101 docketed letters received associated in the Federal/Register notice. Comments from two NRC/Agreement-States meetings are also summarized.

  12. Decontamination and decommissioning of the Kerr-McGee Cimarron Plutonium Fuel Plant

    SciTech Connect

    Not Available

    1994-05-01

    This final report is a summary of the events that completes the decontamination and decommissioning of the Cimarron Corporation`s Mixed Oxides Fuel Plant (formally Sequoyah Fuels Corporation and formerly Kerr-McGee Nuclear Corporation - all three wholly owned subsidiaries of the Kerr-McGee Corporation). Included are details dealing with tooling and procedures for performing the unique tasks of disassembly decontamination and/or disposal. That material which could not be economically decontaminated was volume reduced by disassembly and/or compacted for disposal. The contaminated waste cleaning solutions were processed through filtration and ion exchange for release or solidified with cement for L.S.A. waste disposal. The L.S.A. waste was compacted, and stabilized as required in drums for burial in an approved burial facility. T.R.U. waste packaging and shipping was completed by the end of July 1987. This material was shipped to the Hanford, Washington site for disposal. The personnel protection and monitoring measures and procedures are discussed along with the results of exposure data of operating personnel. The shipping containers for both T.R.U. and L.S.A. waste are described. The results of the decommissioning operations are reported in six reports. The personnel protection and monitoring measures and procedures are contained and discussed along with the results of exposure data of operating personnel in this final report.

  13. Characterization of decontamination and decommissioning wastes expected from the major processing facilities in the 200 Areas

    SciTech Connect

    Amato, L.C.; Franklin, J.D.; Hyre, R.A.; Lowy, R.M.; Millar, J.S.; Pottmeyer, J.A.; Duncan, D.R.

    1994-08-01

    This study was intended to characterize and estimate the amounts of equipment and other materials that are candidates for removal and subsequent processing in a solid waste facility when the major processing and handling facilities in the 200 Areas of the Hanford Site are decontaminated and decommissioned. The facilities in this study were selected based on processing history and on the magnitude of the estimated decommissioning cost cited in the Surplus Facilities Program Plan; Fiscal Year 1993 (Winship and Hughes 1992). The facilities chosen for this study include B Plant (221-B), T Plant (221-T), U Plant (221-U), the Uranium Trioxide (UO{sub 3}) Plant (224-U and 224-UA), the Reduction Oxidation (REDOX) or S Plant (202-S), the Plutonium Concentration Facility for B Plant (224-B), and the Concentration Facility for the Plutonium Finishing Plant (PFP) and REDOX (233-S). This information is required to support planning activities for current and future solid waste treatment, storage, and disposal operations and facilities.

  14. Summary of comments received from workshops on radiological criteria for decommissioning

    SciTech Connect

    Caplin, J.; Page, G.; Smith, D.; Wiblin, C.

    1994-01-01

    The Nuclear Regulatory Commission (NRC) is conducting an enhanced participatory rulemaking to establish radiological criteria for site cleanup and decommissioning of NRC-licensed facilities. Open public meetings were held during 1993 in Chicago, IL, San Francisco, CA, Boston, MA, Dallas, TX, Philadelphia, PA, Atlanta, GA, and Washington, DC. Interested parties were invited to provide input on the rulemaking issues before the NRC staff develops a draft proposed rule. This report summarizes 3,635 comments categorized from transcripts of the seven workshops and 1,677 comments from 100 NRC docketed letters from individuals and organizations. No analysis or response to the comments is included. The comments reflect a broad spectrum of viewpoints on the issues related to radiological criteria for site cleanup and decommissioning. The NRC also held public meetings on the scope of the Generic Environmental Impact Statement (GEIS) during July 1993. The GEIS meetings were held in Washington, DC., San Francisco, CA, Oklahoma City, OK, and Cleveland, OH. Related comments from these meetings were reviewed and comments which differed substantially from those from the workshops are also summarized in the body of the report. A summary of the comments from the GEIS scoping meetings is included as an Appendix.

  15. UNIQUE RADIOANALYTICAL PROTOCOLS FOR CHARACTERIZATION AND VERIFICATION DURING DECONTAMINATION AND DECOMMISSIONING

    SciTech Connect

    Diprete, C; David Diprete, D; Wooten Simpson, W

    2007-01-05

    In order to successfully decontaminate, deactivate and decommission surplus Department of Energy (DOE) facilities throughout the Savannah River Site (SRS), a variety of characterizations must be completed to sufficiently identify and quantify potential contaminants of concern. The ultimate goal is to rapidly and efficiently characterize, decontaminate (if necessary), and verify that the remnants meet specified limits established by either an industrial worker model or a groundwater model. To meet this end, the Savannah River National Laboratory (SRNL) developed a series of radioanalytical strategies and methodologies which can be used to characterize targeted facilities and prove that decontamination has been sufficient. To our knowledge, this is the first application of this novel methodology within the DOE complex. This methodology has been successfully utilized with nearly 1000 samples from over a dozen facilities. The application of this approach to just a single facility shortened the schedule by 30 days and resulted in non-labor dollar savings of over $60K. Cost savings for a second facility was determined to be $375K. Based on the success of this methodology at SRS, this approach will be valuable to other nuclear facilities in the USA and abroad involved with the decontamination and decommissioning process.

  16. A multi-attribute decision analysis for decommissioning offshore oil and gas platforms.

    PubMed

    Henrion, Max; Bernstein, Brock; Swamy, Surya

    2015-10-01

    The 27 oil and gas platforms off the coast of southern California are reaching the end of their economic lives. Because their decommissioning involves large costs and potential environmental impacts, this became an issue of public controversy. As part of a larger policy analysis conducted for the State of California, we implemented a decision analysis as a software tool (PLATFORM) to clarify and evaluate decision strategies against a comprehensive set of objectives. Key options selected for in-depth analysis are complete platform removal and partial removal to 85 feet below the water line, with the remaining structure converted in place to an artificial reef to preserve the rich ecosystems supported by the platform's support structure. PLATFORM was instrumental in structuring and performing key analyses of the impacts of each option (e.g., on costs, fishery production, air emissions) and dramatically improved the team's productivity. Sensitivity analysis found that disagreement about preferences, especially about the relative importance of strict compliance with lease agreements, has much greater effects on the preferred option than does uncertainty about specific outcomes, such as decommissioning costs. It found a near-consensus of stakeholders in support of partial removal and "rigs-to-reefs" program. The project's results played a role in the decision to pass legislation enabling an expanded California "rigs-to-reefs" program that includes a mechanism for sharing cost savings between operators and the state.

  17. Packaging, Transportation, and Disposal Logistics for Large Radioactively Contaminated Reactor Decommissioning Components

    SciTech Connect

    Lewis, Mark S.

    2008-01-15

    The packaging, transportation and disposal of large, retired reactor components from operating or decommissioning nuclear plants pose unique challenges from a technical as well as regulatory compliance standpoint. In addition to the routine considerations associated with any radioactive waste disposition activity, such as characterization, ALARA, and manifesting, the technical challenges for large radioactively contaminated components, such as access, segmentation, removal, packaging, rigging, lifting, mode of transportation, conveyance compatibility, and load securing require significant planning and execution. In addition, the current regulatory framework, domestically in Titles 49 and 10 and internationally in TS-R-1, does not lend itself to the transport of these large radioactively contaminated components, such as reactor vessels, steam generators, reactor pressure vessel heads, and pressurizers, without application for a special permit or arrangement. This paper addresses the methods of overcoming the technical and regulatory challenges. The challenges and disposition decisions do differ during decommissioning versus component replacement during an outage at an operating plant. During decommissioning, there is less concern about critical path for restart and more concern about volume reduction and waste minimization. Segmentation on-site is an available option during decommissioning, since labor and equipment will be readily available and decontamination activities are routine. The reactor building removal path is also of less concern and there are more rigging/lifting options available. Radionuclide assessment is necessary for transportation and disposal characterization. Characterization will dictate the packaging methodology, transportation mode, need for intermediate processing, and the disposal location or availability. Characterization will also assist in determining if the large component can be transported in full compliance with the transportation

  18. Revised analyses of decommissioning for the reference boiling water reactor power station. Effects of current regulatory and other considerations on the financial assurance requirements of the decommissioning rule and on estimates of occupational radiation exposure - appendices. Final report

    SciTech Connect

    Smith, R.I.; Bierschbach, M.C.; Konzek, G.J.; McDuffie, P.N.

    1996-07-01

    The NRC staff is in need of decommissioning bases documentation that will assist them in assessing the adequacy of the licensee submittals, from the viewpoint of both the planned actions, including occupational radiation exposure, and the probable costs. The purpose of this reevaluation study is to update the needed bases documentation. This report presents the results of a review and reevaluation of the PNL 1980 decommissioning study of the Washington Public Power Supply System`s Washington Nuclear Plant Two (WNP-2) located at Richland, Washington, including all identifiable factors and cost assumptions which contribute significantly to the total cost of decommissioning the plant for the DECON, SAFSTOR, and ENTOMB decommissioning alternatives. These alternatives now include an initial 5-7 year period during which time the spent fuel is stored in the spent fuel pool prior to beginning major disassembly or extended safe storage of the plant. Included for information (but not presently part of the license termination cost) is an estimate of the cost to demolish the decontaminated and clear structures on the site and to restore the site to a {open_quotes}green field{close_quotes} condition. This report also includes consideration of the NRC requirement that decontamination and decommissioning activities leading to termination of the nuclear license be completed within 60 years of final reactor shutdown, consideration of packaging and disposal requirements for materials whose radionuclide concentrations exceed the limits for Class C low-level waste (i.e., Greater-Than-Class C), and reflects 1993 costs for labor, materials, transport, and disposal activities. Sensitivity of the total license termination cost to the disposal costs at different low-level radioactive waste disposal sites, to different depths of contaminated concrete surface removal within the facilities, and to different transport distances is also examined.

  19. 30 CFR 250.1731 - Who is responsible for decommissioning an OCS facility subject to an Alternate Use RUE?

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... facility subject to an Alternate Use RUE? 250.1731 Section 250.1731 Mineral Resources BUREAU OF OCEAN... Facilities § 250.1731 Who is responsible for decommissioning an OCS facility subject to an Alternate Use RUE? (a) The holder of an Alternate Use RUE issued under part 285 of this subchapter is responsible...

  20. 78 FR 11688 - Notice of Issuance of Amendment to Facility License R-77 Incorporating a Decommissioning Plan for...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-02-19

    ... the Buffalo Materials Research Center Reactor at the State University of New York at Buffalo AGENCY... (NRC) has approved the State University of New York at Buffalo (UB) decommissioning plan (DP) by amendment to the Facility License R-77 for the Buffalo Materials Research Center (BMRC) reactor. FOR...

  1. 78 FR 78338 - Japan-U.S. Decommissioning and Remediation Fukushima Recovery Forum Tokyo, Japan February 18-19...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-12-26

    ..., including facility ] decommissioning, spent fuel storage, decontamination, and remediation of contaminated... fuel pools experienced beyond-design-basis accidents. The four reactors at the site (Units 1- 4) that received the brunt of the damage (of the six reactors at the site) also have integral spent fuel...

  2. 10 CFR 72.54 - Expiration and termination of licenses and decommissioning of sites and separate buildings or...

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... of sites and separate buildings or outdoor areas. 72.54 Section 72.54 Energy NUCLEAR REGULATORY... Expiration and termination of licenses and decommissioning of sites and separate buildings or outdoor areas... the expiration date if necessary, with respect to possession of licensed material until the...

  3. 77 FR 59680 - Request To Extend Time To Submit Decommissioning Plan; U.S. Department of the Army, Jefferson...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-09-28

    ..., Indiana, requesting to extend the time for submitting a decommissioning plan by 20 months. License No. SUB... documented in an amendment to NRC License No. SUB-1435. However, before approving the proposed amendment, the NRC will need to make the findings required by ] the Atomic Energy Act of 1954, as amended, and...

  4. 30 CFR 585.1018 - Who is responsible for decommissioning an OCS facility subject to an Alternate Use RUE?

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... ENERGY MANAGEMENT, DEPARTMENT OF THE INTERIOR OFFSHORE RENEWABLE ENERGY AND ALTERNATE USES OF EXISTING FACILITIES ON THE OUTER CONTINENTAL SHELF Rights of Use and Easement for Energy- and Marine-Related... issuance of the Alternate Use RUE, as well as for decommissioning obligations that accrue...

  5. 30 CFR 585.1018 - Who is responsible for decommissioning an OCS facility subject to an Alternate Use RUE?

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... ENERGY MANAGEMENT, DEPARTMENT OF THE INTERIOR OFFSHORE RENEWABLE ENERGY AND ALTERNATE USES OF EXISTING FACILITIES ON THE OUTER CONTINENTAL SHELF Rights of Use and Easement for Energy- and Marine-Related... issuance of the Alternate Use RUE, as well as for decommissioning obligations that accrue...

  6. 30 CFR 585.1018 - Who is responsible for decommissioning an OCS facility subject to an Alternate Use RUE?

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... ENERGY MANAGEMENT, DEPARTMENT OF THE INTERIOR OFFSHORE RENEWABLE ENERGY AND ALTERNATE USES OF EXISTING FACILITIES ON THE OUTER CONTINENTAL SHELF Rights of Use and Easement for Energy- and Marine-Related... issuance of the Alternate Use RUE, as well as for decommissioning obligations that accrue...

  7. 26 CFR 1.468A-5T - Nuclear decommissioning fund qualification requirements; prohibitions against self-dealing...

    Code of Federal Regulations, 2010 CFR

    2010-04-01

    ... nuclear power plants, but a single trust agreement may establish multiple funds for such purpose. Thus— (A... agreement; and (B) One or more funds that are to be used for the decommissioning of a nuclear power plant... nuclear power plant with respect to which an electing taxpayer possesses a qualifying interest....

  8. Fiscal year 1996 decontamination and decommissioning activities photobriefing book for the Argonne National Laboratory-East Site, Technology Development Division, Waste Management Program, Decontamination and Decommissioning Projects Department

    SciTech Connect

    1996-12-31

    The Photobriefing Book describes the Decontamination and Decommissioning (D and D) Program at the Argonne National Laboratory-East Site (ANL-E) near Lemont, Illinois. This book summarizes current D and D projects, reviews fiscal year (FY) 1996 accomplishments, and outlines FY 1997 goals. A section on D and D Technology Development provides insight on new technologies for D and D developed or demonstrated at ANL-E. Past projects are recapped and upcoming projects are described as Argonne works to accomplish its commitment to, ``Close the Circle on the Splitting of the Atom.`` Finally, a comprehensive review of the status and goals of the D and D Program is provided to give a snap-shot view of the program and the direction it`s taking as it moves into FY 1997. The D and D projects completed to date include: Plutonium Fuel Fabrication Facility; East Area Surplus Facilities; Experimental Boiling Water Reactor; M-Wing Hot Cell Facilities; Plutonium Gloveboxes; and Fast Neutron Generator.

  9. Task Integration Facilitates Multitasking

    PubMed Central

    de Oliveira, Rita F.; Raab, Markus; Hegele, Mathias; Schorer, Jörg

    2017-01-01

    The aim of this study was to investigate multi-task integration in a continuous tracking task. We were particularly interested in how manipulating task structure in a dual-task situation affects learning of a constant segment embedded in a pursuit-tracking task. Importantly, we examined if dual-task effects could be attributed to task integration by varying the structural similarity and difficulty of the primary and secondary tasks. In Experiment 1 participants performed a pursuit tracking task while counting high-pitched tones and ignoring low-pitched tones. The tones were either presented randomly or structurally 250 ms before each tracking turn. Experiment 2 increased the motor load of the secondary tasks by asking participants to tap their feet to the tones. Experiment 3 further increased motor load of the primary task by increasing its speed and having participants tracking with their non-dominant hand. The results show that dual-task interference can be moderated by secondary task conditions that match the structure of the primary task. Therefore our results support proposals of task integration in continuous tracking paradigms. We conclude that multi-tasking is not always detrimental for motor learning but can be facilitated through task-integration. PMID:28360878

  10. Task Integration Facilitates Multitasking.

    PubMed

    de Oliveira, Rita F; Raab, Markus; Hegele, Mathias; Schorer, Jörg

    2017-01-01

    The aim of this study was to investigate multi-task integration in a continuous tracking task. We were particularly interested in how manipulating task structure in a dual-task situation affects learning of a constant segment embedded in a pursuit-tracking task. Importantly, we examined if dual-task effects could be attributed to task integration by varying the structural similarity and difficulty of the primary and secondary tasks. In Experiment 1 participants performed a pursuit tracking task while counting high-pitched tones and ignoring low-pitched tones. The tones were either presented randomly or structurally 250 ms before each tracking turn. Experiment 2 increased the motor load of the secondary tasks by asking participants to tap their feet to the tones. Experiment 3 further increased motor load of the primary task by increasing its speed and having participants tracking with their non-dominant hand. The results show that dual-task interference can be moderated by secondary task conditions that match the structure of the primary task. Therefore our results support proposals of task integration in continuous tracking paradigms. We conclude that multi-tasking is not always detrimental for motor learning but can be facilitated through task-integration.

  11. Program Facilitates CMMI Appraisals

    NASA Technical Reports Server (NTRS)

    Sweetser, Wesley

    2005-01-01

    A computer program has been written to facilitate appraisals according to the methodology of Capability Maturity Model Integration (CMMI). [CMMI is a government/industry standard, maintained by the Software Engineering Institute at Carnegie Mellon University, for objectively assessing the engineering capability and maturity of an organization (especially, an organization that produces software)]. The program assists in preparation for a CMMI appraisal by providing drop-down lists suggesting required artifacts or evidence. It identifies process areas for which similar evidence is required and includes a copy feature that reduces or eliminates repetitive data entry. It generates reports to show the entire framework for reference, the appraisal artifacts to determine readiness for an appraisal, and lists of interviewees and questions to ask them during the appraisal. During an appraisal, the program provides screens for entering observations and ratings, and reviewing evidence provided thus far. Findings concerning strengths and weaknesses can be exported for use in a report or a graphical presentation. The program generates a chart showing capability level ratings of the organization. A context-sensitive Windows help system enables a novice to use the program and learn about the CMMI appraisal process.

  12. Can Decommissioned Oil Pads in Boreal Alberta BE Reclaimed to Carbon Accumulating Peatlands?

    NASA Astrophysics Data System (ADS)

    Wieder, R.; Vitt, D. H.; Mowbray, S.

    2010-12-01

    In northern Alberta where peatland ecosystems are a dominant landscape feature, construction of oil drilling pads and access roads is a major disturbance. Reclamation of decommissioned oil pads has been hampered by the lack of research. At two decommissioned oil pads at Shell Oil’s Peace River Complex (northeastern Alberta), initially constructed in a bog/fen complex, we established a field experiment to assess reclamation approaches that could lead to a system reflecting undisturbed peatland structure (vegetation composition) and function (net carbon accumulation). In the fall of 2007, mineral soil was removed from two decommissioned pads in areas approximately 100-m x 30-m creating a mineral surface at or near the surrounding bog water table level. We established the following treatments: pad (fertilized vs. unfertilized); water table position (at and 5-cm above the surrounding bog water level); texture (tilling soil amendments into the mineral soil or not); amendment (controls; commercial peat, peat that had been stockpiled in a farmer’s field; landscape fabric; slough hay (native species hay from harvested from local farms), aspen wood chips); planting (in 1-m x 1-m subplots within 2-m x 2-m amendment plots: no planting, 9 Carex aquatilis plants, 5 C. aquatilis and 4 Salix lutea plants; 3 C. aquatilis, 3 S. lutea and 3 Larix laricina seedlings). Treatments were nested (planting within amendment, within texture, within water table level, within pad), with 6 replicate 2-m x 2-m plots of each amendment within each pad x texture x water level combination. Net CO2 exchange was quantified under a range of PAR conditions from full sunlight to complete darkness in each 1-m x 1-m planting subplot repeatedly during the summers of 2008, 2009 and 2010 using closed chambers and infrared gas analyzers. Both dark respiration and maximum net ecosystem production (NEPSAT; net CO2 sequestration when PAR>1000 μmol m-2 s-1) exhibited year x planting interactions (p<0.0001 and

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

    SciTech Connect

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

    1980-06-01

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

  14. Final report of the decontamination and decommissioning of the BORAX-V facility turbine building

    SciTech Connect

    Arave, A.E.; Rodman, G.R.

    1992-12-01

    The Boiling Water Reactor Experiment (BORAX)-V Facility Turbine Building Decontamination and Decommissioning (D&D) Project is described in this report. The BORAX series of five National Reactor Testing Station (NRTS) reactors pioneered intensive work on boiling water reactor (BWR) experiments conducted between 1953 and 1964. Facility characterization, decision analyses, and D&D plans for the turbine building were prepared from 1979 through 1990. D&D activities of the turbine building systems were initiated in November of 1988 and completed with the demolition and backfill of the concrete foundation in March 1992. Due to the low levels of radioactivity and the absence of loose contamination, the D&D activities were completed with no radiation exposure to the workers. The D&D activities were performed in a manner that no radiological health or safety hazard to the public or to personnel at the Idaho National Engineering Laboratory (INEL) remain.

  15. Final report of the decontamination and decommissioning of the BORAX-V facility turbine building

    SciTech Connect

    Arave, A.E.; Rodman, G.R.

    1992-12-01

    The Boiling Water Reactor Experiment (BORAX)-V Facility Turbine Building Decontamination and Decommissioning (D D) Project is described in this report. The BORAX series of five National Reactor Testing Station (NRTS) reactors pioneered intensive work on boiling water reactor (BWR) experiments conducted between 1953 and 1964. Facility characterization, decision analyses, and D D plans for the turbine building were prepared from 1979 through 1990. D D activities of the turbine building systems were initiated in November of 1988 and completed with the demolition and backfill of the concrete foundation in March 1992. Due to the low levels of radioactivity and the absence of loose contamination, the D D activities were completed with no radiation exposure to the workers. The D D activities were performed in a manner that no radiological health or safety hazard to the public or to personnel at the Idaho National Engineering Laboratory (INEL) remain.

  16. Decommissioning strategy for liquid low-level radioactive waste surface storage water reservoir.

    PubMed

    Utkin, S S; Linge, I I

    2016-11-22

    The Techa Cascade of water reservoirs (TCR) is one of the most environmentally challenging facilities resulted from FSUE "PA "Mayak" operations. Its reservoirs hold over 360 mln m(3) of liquid radioactive waste with a total activity of some 5 × 10(15) Bq. A set of actions implemented under a special State program involving the development of a strategic plan aimed at complete elimination of TCR challenges (Strategic Master-Plan for the Techa Cascade of water reservoirs) resulted in considerable reduction of potential hazards associated with this facility. The paper summarizes the key elements of this master-plan: defining TCR final state, feasibility study of the main strategies aimed at its attainment, evaluation of relevant long-term decommissioning strategy, development of computational tools enabling the long-term forecast of TCR behavior depending on various engineering solutions and different weather conditions.

  17. Environmental assessment for Mound Plant decontamination and decommissioning projects, Mound Plant, Miamisburg, Ohio

    SciTech Connect

    1995-05-01

    The U.S. Department of Energy (DOE) has prepared an Environmental Assessment (EA) for seven decontamination and decommissioning (D&D) projects at the Mound Plant in Miamisburg, Ohio, that have not been previously addressed in the Final Environmental Impact Statement for the Mound Facility (June 1979). Based on the information presented in the EA, the DOE has determined that the proposed action is not a major Federal action significantly affecting the quality of the human environment within the meaning of the National Environmental Policy Act (NEPA) of 1969. Therefore, the preparation of an Environmental Impact Statement (EIS) is not required and the Department is issuing this Finding of No Significant Impact (FONSI).

  18. Available decontamination and decommissioning capabilities at the Savannah River Technology Center

    SciTech Connect

    Polizzi, L.M.; Norkus, J.K.; Paik, I.K.; Wooten, L.A.

    1992-08-19

    The Safety Analysis and Engineering Services Group has performed a survey of the Savannah River Technology Center (SRTC) technical capabilities, skills, and experience in Decontamination and Decommissioning (D D) activities. The goal of this survey is to enhance the integration of the SRTC capabilities with the technical needs of the Environmental Restoration Department D D program and the DOE Office of Technology Development through the Integrated Demonstration Program. This survey has identified technical capabilities, skills, and experience in the following D D areas: Characterization, Decontamination, Dismantlement, Material Disposal, Remote Systems, and support on Safety Technology for D D. This review demonstrates the depth and wealth of technical capability resident in the SRTC in relation to these activities, and the unique qualifications of the SRTC to supply technical support in the area of DOE facility D D. Additional details on specific technologies and applications to D D will be made available on request.

  19. Available decontamination and decommissioning capabilities at the Savannah River Technology Center

    SciTech Connect

    Polizzi, L.M.; Norkus, J.K.; Paik, I.K.; Wooten, L.A.

    1992-08-19

    The Safety Analysis and Engineering Services Group has performed a survey of the Savannah River Technology Center (SRTC) technical capabilities, skills, and experience in Decontamination and Decommissioning (D&D) activities. The goal of this survey is to enhance the integration of the SRTC capabilities with the technical needs of the Environmental Restoration Department D&D program and the DOE Office of Technology Development through the Integrated Demonstration Program. This survey has identified technical capabilities, skills, and experience in the following D&D areas: Characterization, Decontamination, Dismantlement, Material Disposal, Remote Systems, and support on Safety Technology for D&D. This review demonstrates the depth and wealth of technical capability resident in the SRTC in relation to these activities, and the unique qualifications of the SRTC to supply technical support in the area of DOE facility D&D. Additional details on specific technologies and applications to D&D will be made available on request.

  20. Nuclear Rocket Test Facility Decommissioning Including Controlled Explosive Demolition of a Neutron-Activated Shield Wall

    SciTech Connect

    Michael Kruzic

    2007-09-01

    Located in Area 25 of the Nevada Test Site, the Test Cell A Facility was used in the 1960s for the testing of nuclear rocket engines, as part of the Nuclear Rocket Development Program. The facility was decontaminated and decommissioned (D&D) in 2005 using the Streamlined Approach For Environmental Restoration (SAFER) process, under the Federal Facilities Agreement and Consent Order (FFACO). Utilities and process piping were verified void of contents, hazardous materials were removed, concrete with removable contamination decontaminated, large sections mechanically demolished, and the remaining five-foot, five-inch thick radiologically-activated reinforced concrete shield wall demolished using open-air controlled explosive demolition (CED). CED of the shield wall was closely monitored and resulted in no radiological exposure or atmospheric release.

  1. A DECONTAMINATION PROCESS FOR METAL SCRAPS FROM THE DECOMMISSIONING OF TRR

    SciTech Connect

    Wei, T.Y.; Gan, J.S.; Lin, K.M.; Chung, Z.J.

    2003-02-27

    A decontamination facility including surface condition categorizing, blasting, chemical/electrochemical cleaning, very low radioactivity measuring, and melting, is being established at INER. The facility will go into operation by the end of 2004. The main purpose is to clean the dismantled metal wastes from the decommissioning of Taiwan Research Reactor (TRR). The pilot test shows that over 70% of low level metal waste can be decontaminated to very low activity and can be categorized as BRC (below regulatory concern) waste. All the chemical decontamination technologies applied are developed by INER. In order to reduce the secondary wastes, chemical reagents will be regenerated several times with a selective precipitation method. The exhausted chemical reagent will be solidified with INER's patented process. The total secondary waste is estimated about 0.1-0.3 wt.% of the original waste. This decontamination process is accessed to be economic and feasible.

  2. Considerations, measurements and logistics associated with low-energy cyclotron decommissioning

    SciTech Connect

    Sunderland, J. J.; Erdahl, C. E.; Bender, B. R.; Sensoy, L.; Watkins, G. L.

    2012-12-19

    The University of Iowa's 20-year-old 17 MeV Scanditronix cyclotron underwent decommissioning in the summer of 2011. To satisfy local, state and federal regulations defining removal, transportation and long-term safe and environmentally secure disposal of the 22 ton activated cyclotron, a series of nuclear spectroscopic measurements were performed to characterize the nature and extent of proton and neutron activation of the 22-ton cyclotron, its associated targets, and the concrete wall that was demolished to remove the old cyclotron. Neutron activation of the concrete wall was minimal and below exempt concentrations resulting in standard landfill disposal. The cyclotron assessment revealed the expected array of short and medium-lived radionuclides. Subsequent calculations suggest that meaningful levels residual activity will have decayed virtually to background after 15 years, with the total residual activity of the entire cyclotron dropping below 37 MBq (1 mCi).

  3. Decontamination and decommissioning plan for processing contaminated NaK at the INEL

    SciTech Connect

    LaRue, D.M.; Dolenc, M.R.

    1986-09-01

    This decontamination and decommissioning (D D) plan describes the work elements and project management plan for processing four containers of contaminated sodium/potassium (NaK) and returning the Army Reentry Vehicle Facility Site (ARVFS) to a reusable condition. The document reflects the management plan for this project before finalizing the conceptual design and preliminary prototype tests of the reaction kinetics. As a result, the safety, environmental, and accident analyses are addressed as preliminary assessments before completion at a later date. ARVFS contains an earth-covered bunker, a cylindrical test pit and metal shed, and a cable trench connecting the two items. The bunker currently stores the four containers of NaK from the meltdown of the EBR-1 Mark II core. The D D project addressed in this plan involves processing the contaminated NaK and returning the ARVFS to potential reuse after cleanup.

  4. Decontamination and decommissioning plan for processing contaminated NaK at the INEL

    SciTech Connect

    LaRue, D.M.; Dolenc, M.R.

    1986-09-01

    This decontamination and decommissioning (D&D) plan describes the work elements and project management plan for processing four containers of contaminated sodium/potassium (NaK) and returning the Army Reentry Vehicle Facility Site (ARVFS) to a reusable condition. The document reflects the management plan for this project before finalizing the conceptual design and preliminary prototype tests of the reaction kinetics. As a result, the safety, environmental, and accident analyses are addressed as preliminary assessments before completion at a later date. ARVFS contains an earth-covered bunker, a cylindrical test pit and metal shed, and a cable trench connecting the two items. The bunker currently stores the four containers of NaK from the meltdown of the EBR-1 Mark II core. The D&D project addressed in this plan involves processing the contaminated NaK and returning the ARVFS to potential reuse after cleanup.

  5. (Technical exchange in robotics for reactor decommissioning between the USA and Japan)

    SciTech Connect

    Weisbin, C.R.

    1987-09-22

    Japan is one of the world leaders in artificial intelligence and robotics. A major collaborative program already exists between the ORNL CFRP effort in advanced teleoperations and the Japanese interest in remote handling for nuclear fuel reprocessing. The subject visit was stimulated by the Japanese to foster a broader exchange in the area of autonomous robotics and intelligent machines. Following a visit to CESAR approximately one year ago, JAERI proposed a similar initiative in intelligent autonomous machines. This effort (HASP) has been formally approved as a ten year program, and initiated in its first year with eight full-time researchers. Beginning next year, it is expected that this effort will grow to its maximum level of 25 researchers per year. Prospects for potential technical exchange in AI/robotics appear promising. Additional opportunities may exist in remote handling for reactor decommissioning.

  6. Decontamination as a precursor to decommissioning. Status report Task 2: process evaluation. [PWR; BWR

    SciTech Connect

    Divine, J.R.; Woodruff, E.M.; McPartland, S.A.; Zima, G.E.

    1983-05-01

    As part of the US Nuclear Regulatory Commission's program to reduce occupational exposure and waste volumes, the Pacific Northwest Laboratory is studying decontamination as a precursor to decommissioning. Eleven processes or solvents were examined for their behavior in decontaminating BWR carbon steel samples. The solvents included NS-1, a proprietary solvent of Dow Chemical Corporation, designed for BWR use, and AP-Citrox, a well-known, two-step process designed for PWR stainless steel; it was used to provide a reference for later comparison to other systems and processes. The decontamination factors observed in the tests performed in a small laboratory scale recirculating loop ranged from about 1 (no effect) to 222 (about 99.6% of the initial activity removed. Coordinated corrosion measurements were made using twelve chemical solvents and eight metal alloys found in a range of reactor types.

  7. Nuclear facility decommissioning and site remedial actions: A selected bibliography, Vol. 18. Part 2. Indexes

    SciTech Connect

    1997-09-01

    This bibliography contains 3638 citations with abstracts of documents relevant to environmental restoration, nuclear facility decontamination and decommissioning (D&D), uranium mill tailings management, and site remedial actions. This report is the eighteenth in a series of bibliographies prepared annually for the U.S. Department of Energy (DOE) Office of Environmental Restoration. 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 in Part 1 of the report. The bibliography contains scientific, technical, financial, and regulatory information that pertains to DOE environmental restoration programs. The citations are separated by topic into 16 sections, including (1) DOE Environmental Restoration Program; (2) DOE D&D Program; (3) Nuclear Facilities Decommissioning; (4) DOE Formerly Utilized Sites Remedial Action Programs; (5) NORM-Contaminated Site Restoration; (6) DOE Uranium Mill Tailings Remedial Action Project; (7) Uranium Mill Tailings Management; (8) DOE Site-Wide Remedial Actions; (9) DOE Onsite Remedial Action Projects; (10) Contaminated Site Remedial Actions; (11) DOE Underground Storage Tank Remediation; (12) DOE Technology Development, Demonstration, and Evaluations; (13) Soil Remediation; (14) Groundwater Remediation; (15) Environmental Measurements, Analysis, and Decision-Making; and (16) Environmental Management Issues. Within the 16 sections, the citations are sorted by geographic location. If a geographic location is not specified, the citations are sorted according to the document title. In Part 2 of the report, indexes are provided for author, author affiliation, selected title phrase, selected title word, publication description, geographic location, and keyword.

  8. Nuclear facility decommissioning and site remedial actions: A selected bibliography, volume 9

    SciTech Connect

    Owen, P.T.; Knox, N.P.; Michelson, D.C.; Turmer, G.S.

    1988-09-01

    The 604 abstracted references on nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the ninth in a series of reports prepared annually for the US Department of Energy's Remedial Action Programs. Foreign and domestic literature of all types--technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions--has 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. Subsections for sections 1, 2, 5, and 6 include: Design, Planning, and Regulations; Environmental Studies and Site Surveys; Health, Safety, and Biomedical Studies; Decontamination Studies; Dismantlement and Demolition; Site Stabilization and Reclamation; Waste Disposal; Remedial Action Experience; and General 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 word, publication description, geographic location, 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. RAPIC staff and resources are available to meet a variety of information needs. Contact the center at (615) 576-0568 or FTS 626-0568.

  9. Nuclear facility decommissioning and site remedial actions: a selected bibliography. Volume 4

    SciTech Connect

    Owen, P.T.; Knox, N.P.; Fielden, J.M.; Faust, R.A.

    1983-09-01

    This bibliography of 657 references with abstracts on the subject of nuclear facility decommissioning, uranium mill tailings management, and site remedial actions is the fourth in a series of annual reports prepared for the US Department of Energy, Division of Remedial Action Projects. Foreign as well as domestic documents of all types - technical reports, progress reports, journal articles, conference papers, symposium proceedings, theses, books, patents, legislation, and research project descriptions - have been references in this publication. The bibliography contains scientific (basic research as well as applied technology), economic, regulatory, and legal literature pertinent to the US Department of Energy's Remedial Action Program. Major chapters are: (1) Surplus Facilities Management Program; (2) Nuclear Facilities Decommissioning; (3) Formerly Utilized Sites Remedial Action Program; (4) Uranium Mill Tailings Remedial Action Program; (5) Grand Junction Remedial Action Program; and (6) Uranium Mill Tailings Management. Chapter sections for chapters 1 and 2 include: Design, Planning, and Regulations; Site Surveys; Decontamination Studies; Dismantlement and Demolition; Land Decontamination and Reclamation; Waste Disposal; and General studies. The references within each chapter or section are arranged alphabetically by leading author. References having no individual author are arranged by corporate author, or by title. Indexes are provided for the categories of author, corporate affiliation, title, publication description, geographic location, and keywords. Appendix A lists 264 bibliographic references to literature identified during this reporting period but not abstracted due to time constraints. Title and publication description indexes are given for this appendix. Appendix B defines frequently used acronyms, and Appendix C lists the recipients of this report according to their corporate affiliation.

  10. Excel Automatic Locking Scaffold. Deactivation and Decommissioning Focus Area. OST Reference #2320

    SciTech Connect

    None, None

    1999-09-01

    The United States Department of Energy (DOE) continually seeks safer and more cost-effective technologies for decontamination and decommissioning (D&D) of nuclear facilities. To this end, the Deactivation and Decommissioning Focus Area (DDFA) of the DOE’s Office of Science and Technology sponsors large-scale demonstration and deployment projects (LSDDPs). At these LSDDPs, developers and vendors of improved or innovative technologies showcase products that are potentially beneficial to the DOE’s projects and to others in the D&D community. Benefits sought include decreased health and safety risks to personnel and the environment, increased productivity, and decreased cost of operation. The Idaho National Engineering and Environmental Laboratory (INEEL) LSDDP generated a list of need statements defining specific needs or problems where improved technologies could be incorporated into ongoing D&D tasks. Although not addressed explicitly, the use of scaffolds is needed in several of the listed needs, including characterization, demolition, and asbestos abatement. In these areas, scaffold towers are used to access areas that are not accessible using mechanical methods such as manlifts or mechanical platforms. In addition, the work requires more mobility than what can be achieved using ladders. Because of the wide use of scaffold on D&D projects, a need exists for a safer to use, faster to set up, and overall cheaper scaffold system. This demonstration investigated the feasibility of using the Excel Automatic Locking Scaffold (innovative technology) to access areas where tube and clamp scaffold (baseline) is currently being used on D&D activities. Benefits expected from using the innovative technology include: Decreased exposure to radiation, chemical, and/or physical hazards during scaffold erection and dismantlement; Increased safety; Easier use; Shorten D&D Schedule; Reduced cost of operation; Excel Scaffold is compatible with tube and clamp scaffold. This report

  11. Completion of the decommissioning of a former active handling building at UKAEA Winfrith

    SciTech Connect

    Brown, N.; Parkinson, S.J.; Cornell, R.M.; Staples, A.T.

    2007-07-01

    Since July 2000, NUKEM Limited has been carrying out the full decommissioning of a former Active Handling Building A59 at Winfrith in Dorset under contract from the nuclear site licence holder, UKAEA. Work has generally centred upon clearance and decontamination of the two heavily shielded suites of caves originally used to carry out remote examination of irradiated nuclear fuel elements although a number of other supporting facilities are also involved. This work has proceeded successfully to completion following extensive decontamination of the caves and associated facilities and has been followed by the recent demolition of the main containment building structure. This has permitted a start to be made on the demolition of the two heavily shielded suites of caves which is to be followed by removal of the building slab and restoration of the site. This paper reviews some of the significant tasks undertaken during the past year in preparation for the building and cave line demolition operations. It also reviews the building structure removal and recent progress made with the demolition of the two heavily reinforced concrete cave lines. The procedure used for monitoring the concrete debris from the cave lines has had to be revised during these operations and the reasons for this and a temporary delay in the cave line demolition will be discussed in the context of the remaining sections of the programme. This decommissioning programme has been achieved throughout by the employment of a non-adversarial team working approach between client and contractor. This has been instrumental in developing cost-effective and safe solutions to a range of problems during the programme, demonstrating the worth of adopting this co-operative approach for mutual benefit. (authors)

  12. Accelerating the Whiteshell Laboratories Decommissioning Through the Implementation of a Projectized and Delivery-Focused Organization - 13074

    SciTech Connect

    Wilcox, Brian; Mellor, Russ; Michaluk, Craig

    2013-07-01

    Whiteshell Laboratories (WL) is a nuclear research site in Canada that was commissioned in 1964 by Atomic Energy of Canada Limited. It covers a total area of approximately 4,375 hectares (10,800 acres) and includes the main campus site, the Waste Management Area (WMA) and outer areas of land identified as not used for or impacted by nuclear development or operations. The WL site employed up to 1100 staff. Site activities included the successful operation of a 60 MW organic liquid-cooled research reactor from 1965 to 1985, and various research programs including reactor safety research, small reactor development, fuel development, biophysics and radiation applications, as well as work under the Canadian Nuclear Fuel Waste Management Program. In 1997, AECL made a business decision to discontinue research programs and operations at WL, and obtained government concurrence in 1998. The Nuclear Legacy Liabilities Program (NLLP) was established in 2006 by the Canadian Government to remediate nuclear legacy liabilities in a safe and cost effective manner, including the WL site. The NLLP is being implemented by AECL under the governance of a Natural Resources Canada (NRCan)/AECL Joint Oversight Committee (JOC). Significant progress has since been made, and the WL site currently holds the only Canadian Nuclear Safety Commission (CNSC) nuclear research site decommissioning license in Canada. The current decommissioning license is in place until the end of 2018. The present schedule planned for main campus decommissioning is 30 years (to 2037), followed by institutional control of the WMA until a National plan is implemented for the long-term management of nuclear waste. There is an impetus to advance work and complete decommissioning sooner. To accomplish this, AECL has added significant resources, reorganized and moved to a projectized environment. This presentation outlines changes made to the organization, the tools implemented to foster projectization, and the benefits

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

    SciTech Connect

    Bierschbach, M.C.

    1994-12-01

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

  14. Rapid Recovery of Chironomidae (Diptera) in Little Mill Creek (Kansas, U.S.A.) After the Decommissioning of a Waste Water Treatment Plant

    NASA Astrophysics Data System (ADS)

    Bouchard, R. W.; Ferrington, L. C.

    2005-05-01

    In June 1995 the Lenexa Waste Water Treatment Plant was decommissioned, providing an opportunity to study recovery of Chironomidae community structure in Little Mill Creek. Using pupal exuviae, weekly changes in the species richness and composition of Chironomidae emerging upstream and downstream of the effluent outfall was evaluated from two weeks before decommissioning to eight weeks post-decommissioning. Chironomidae emergence was clearly different between upstream and downstream sites both before and shortly after effluent input ceased. Before decommissioning, sites immediately downstream of the effluent had low species richness and were dominated by Chironomus riparius (Meigen) and other tolerant taxa, with some recovery at sites farther downstream. Two weeks after decommissioning, only sites immediately downstream of the former effluent were clearly impacted, but effects were reduced compared to pre-recovery collections. At five weeks post-decommissioning, species richness was only slightly lower at the sites immediately downstream of the former effluent and the composition of common species (i.e., >5% of relative abundance) was similar between upstream and downstream sites. Rapid recovery of chironomid emergence below the sewage effluent likely resulted from both colonization of drifting larvae from upstream sources and adult dispersal and oviposition, indicating rapid responses in emergence as water quality conditions improved.

  15. Facilitating Dialogues about Racial Realities

    ERIC Educational Resources Information Center

    Quaye, Stephen John

    2014-01-01

    Background/Context: Facilitating dialogues about racial issues in higher education classroom settings continues to be a vexing problem facing postsecondary educators. In order for students to discuss race with their peers, they need skilled facilitators who are knowledgeable about racial issues and able to support students in these difficult…

  16. Facilitated Communication in Mainstream Schools.

    ERIC Educational Resources Information Center

    Remington-Gurney, Jane; Crossley, Rosemary

    Facilitated communication is described as a method of training communication partners or facilitators to provide physical assistance to communication aid users, to help them overcome physical and emotional problems in using their aids. In Melbourne (Victoria, Australia), the DEAL (Dignity, Education and Language) Centre has identified 96 people…

  17. A Manual for Group Facilitators.

    ERIC Educational Resources Information Center

    Auvine, Brian; And Others

    This resource manual presents guidelines and effective techniques for people who want to acquire group facilitation skills. It is a valuable resource for anyone planning or presenting a workshop; trainers or teachers interested in innovative classroom techniques; and anyone involved in a group as leader, facilitator, or participant. The manual…

  18. Decommissioning of eight surplus production reactors at the Hanford Site, Richland, Washington. Addendum (Final Environmental Impact Statement)

    SciTech Connect

    Not Available

    1992-12-01

    The first section of this volume summarizes the content of the draft environmental impact statement (DEIS) and this Addendum, which together constitute the final environmental impact statement (FEIS) prepared on the decommissioning of eight surplus plutonium production reactors at Hanford. The FEIS consists of two volumes. The first volume is the DEIS as written. The second volume (this Addendum) consists of a summary; Chapter 9, which contains comments on the DEIS and provides DOE`s responses to the comments; Appendix F, which provides additional health effects information; Appendix K, which contains costs of decommissioning in 1990 dollars; Appendix L, which contains additional graphite leaching data; Appendix M, which contains a discussion of accident scenarios; Appendix N, which contains errata; and Appendix 0, which contains reproductions of the letters, transcripts, and exhibits that constitute the record for the public comment period.

  19. Closure plan for the decommissioned high explosives rinse-water lagoons at Lawrence Livermore National Laboratory Site 300

    SciTech Connect

    Carpenter, D.W.; Lamarre, A.L.; Crow, N.B.; Swearengen, P.M.

    1988-05-31

    The High Explosives (HE) Process Area is a major facility at Lawrence Livermore National Laboratory (LLNL) Site 300. Within the Process Area, rinse water from various buildings formerly was discharged to nine relatively small, unlined lagoons where it was disposed of by evaporation and infiltration. In 1985, LLNL decommissioned these lagoons and diverted the rinse waters to two doubly lined surface impoundments. LLNL conducted the hydrogeologic investigations required to support the permanent closure of the none decommissioned lagoons. These studies included drilling ground water monitoring wells and extensively collecting soil and rock samples, which were analyzed for EPA toxic metals, HE compounds, and purgeable and extractable priority organic pollutants. On October 26, 1987, the RWQCB requested that we prepare a comprehensive report to summarize and discuss the findings of the LLNL HE Process Area Investigation. This report is our response to the Board's request. 22 refs., 19 figs. , 45 tabs.

  20. Radionuclide characterization at US commercial light-water reactors for decommissioning assessment: Distributions, inventories, and waste disposal considerations

    SciTech Connect

    Abel, K.H.; Robertson, D.E.; Thomas, C.W.

    1992-09-01

    A continuing research program, conducted by Pacific Northwest Laboratory for the US Nuclear Regulatory Commission, characterizing radionuclide concentrations associated with US light-water reactors has been conducted for more than a decade. The research initially focused upon sampling and analytical measurements for the purpose of establishing radionuclide distributions and inventories for decommissioning assessment, since very little empirical data existed. The initial phase of the research program examined radionuclide concentrations and distributions external to the reactor vessel at seven US light water reactors. Later stages of the research program have examined the radionuclide distributions in the highly radioactive reactor internals and fuel assembly. Most recently, the research program is determining radionuclide concentrations in these highly radioactive components and comparing empirical results with those derived from the several nonempirical methodologies employed to estimate radionuclide inventories for disposal classification. The results of the research program to date are summarized, and their implications and significance for the decommissioning process are noted.

  1. Evaluate the radioactivity along the central thimble hole of a decommissioned heavy water research reactor using TLD approach.

    PubMed

    Lee, Lun-Hui; Sher, Hai-Feng; Lu, I-Hsin; Pan, Lung-Kwang

    2012-04-01

    The radioactivity along the central thimble hole of a decommissioned heavy water research reactor, TRR, was evaluated using TLD approach. The decay radionuclide was verified to be Co-60. The dose along the TRR central thimble hole was detected and revised by performing an unfolding analysis. The revised data reduced to 70-90% of the original data (for example, the maximum dose rate was reduced from 6447 to 4831 mSv/h,) and were more reliable.

  2. Portable instrumentation for quantitatively measuring radioactive contamination levels and for monitoring the effectiveness of decontamination and decommissioning activities

    SciTech Connect

    Brodzinski, R.L.

    1983-06-01

    Two completely portable high-resolution germanium diode spectrometer systems are described. These detectors are capable of measuring transuranics, activation products, and fission products, including /sup 90/Sr, at sensitivities below the uncontrolled release criteria. The detectors measure x-rays, gamma-rays, or bremsstrahlung radiation as required and have been calibrated for a variety of decontamination and decommissioning scenarios. A description of a new technology for the in-situ determination of /sup 90/Sr is given.

  3. Using probabilistic criteria in an assessment of the potential radiological consequences of the decommissioning of a nuclear research reactor

    SciTech Connect

    Wallner, Christian; Rall, Anna-Maria; Thummerer, Severin

    2013-07-01

    In order to assess the risk of radiological consequences of incidents and accidents in nuclear facilities it is important to contemplate their frequency of occurrence. It has to be shown that incidents and accidents occur sufficiently seldom according to their radiological consequences i. e. the occurrence frequency of radiological doses has to be limited. This is even demanded by the German radiation protection ordinance (StrlSchV), which says that in nuclear facilities other than nuclear power plants (NPP) in operation and for decommissioning, the occurrence frequency of incidents and accidents shall be contemplated in order to prove the design of safety measures and safety installations. Based on the ideas of the ICRP64, we developed a risk based assessment concept for nuclear facilities, which fulfils the requirements of the German regulations concerning dose limits in normal operation and design basis accidents. The general use of the concept is dedicated to nuclear facilities other than nuclear power plants (NPP) in operation and for decommissioning, where the regulation of risk assessment is less sophisticated. The concept specifies occurrence frequency limits for radiation exposure dose ranges, i. e. the occurrence frequency of incidents and accidents has to be limited according to their radiological effects. To apply this concept, scenarios of incidents and accidents are grouped in exposition classes according to their resulting potential effective dose to members of the general public. The occurrence frequencies of the incidents and accidents are summarized in each exposition class whereas the sum must not exceed the frequency limits mentioned above. In the following we introduce the application of this concept in the assessment of the potential radiological consequences of the decommissioning of a nuclear research reactor. We carried out this assessment for the licensing process of the decommissioning on behalf of German authorities. (authors)

  4. Environmental Problems Associated with Decommissioning of Chernobyl Power Plant Cooling Pond

    NASA Astrophysics Data System (ADS)

    Foley, T. Q.; Oskolkov, B. Y.; Bondarkov, M. D.; Gashchak, S. P.; Maksymenko, A. M.; Maksymenko, V. M.; Martynenko, V. I.; Jannik, G. T.; Farfan, E. B.; Marra, J. C.

    2009-12-01

    Decommissioning of nuclear power plants and other nuclear fuel cycle facilities associated with residual radioactive contamination is a fairly pressing issue. Significant problems may result from decommissioning of cooling ponds. The Chernobyl Nuclear Power Plant (ChNPP) Cooling Pond is one of the largest self-contained bodies of water in the Chernobyl Region and Ukrainian Polesye with a water surface area of 22.9 km2. The major hydrological feature of the ChNPP Cooling Pond is that its water level is 6-7 m higher than the water level in the Pripyat River and water losses due to seepage and evaporation are replenished by pumping water from the Pripyat River. In 1986, the accident at the ChNPP #4 Reactor Unit significantly contaminated the ChNPP Cooling Pond. According to the 2001 data, the total radionuclide inventory in the ChNPP Cooling Pond bottom deposits was as follows: 16.28 ± 2.59 TBq for 137Cs; 2.4 ± 0.48 TBq for 90Sr, and 0.00518 ± 0.00148 TBq for 239+240Pu. Since ChNPP is being decommissioned, the ChNPP Cooling Pond of such a large size will no longer be needed and cost effective to maintain. However, shutdown of the water feed to the Pond would expose the contaminated bottom deposits and change the hydrological features of the area, destabilizing the radiological and environmental situation in the entire region in 2007 - 2008, in order to assess potential consequences of draining the ChNPP Cooling Pond, the authors conducted preliminary radio-ecological studies of its shoreline ecosystems. The radioactive contamination of the ChNPP Cooling Pond shoreline is fairly variable and ranges from 75 to 7,500 kBq/m2. Three areas with different contamination levels were selected to sample soils, vegetation, small mammals, birds, amphibians, and reptilians in order to measure their 137Cs and 90Sr content. Using the ERICA software, their dose exposures were estimated. For the 2008 conditions, the estimated dose rates were found to be as follows: amphibians - 11

  5. Concrete crushing and sampling, a methodology and technology for the unconditional release of concrete material from decommissioning

    SciTech Connect

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

    2007-07-01

    Belgoprocess started the industrial decommissioning of the main process building of the former Eurochemic reprocessing plant in 1990, after completion of a pilot project. Two small storage buildings for final products from reprocessing were dismantled to verify the assumptions made in a previous paper study on decommissioning, to demonstrate and develop dismantling techniques and to train personnel. Both buildings were emptied and decontaminated to background levels. They were demolished and the remaining concrete debris was disposed of as industrial waste and green field conditions restored. Currently, the decommissioning operations carried out at the main building have made substantial progress. They are executed on an industrial scale. In view of the final demolition of the building, foreseen to start in the middle of 2008, a clearance methodology for the concrete from the cells into the Eurochemic building has been developed. It considers at least one complete measurement of all concrete structures and the removal of all detected residual radionuclides. This monitoring sequence is followed by a controlled demolition of the concrete structures and crushing of the resulting concrete parts to smaller particles. During the crushing operations, metal parts are separated from the concrete and representative concrete samples are taken. The frequency of sampling meets the prevailing standards. In a further step, the concrete samples are milled, homogenised, and a smaller fraction is sent to the laboratory for analyses. The paper describes the developed concrete crushing and sampling methodology. (authors)

  6. Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 13: Part 1, Main text. Environmental Restoration Program

    SciTech Connect

    Goins, L.F.; Webb, J.R.; Cravens, C.D.; Mallory, P.K.

    1992-09-01

    This publication contains 1035 abstracted references on environmental restoration, nuclear facility decommissioning, uranium mill tailings management, and site remedial actions. These citations constitute the thirteenth in a series of reports prepared annually for the US Department of Energy (DOE) Environmental Restoration programs. Citations to foreign and domestic literature of all types. There are 13 major sections of the publication, including: (1) DOE Decontamination and Decommissioning Program; (2) Nuclear Facilities Decommissioning; (3) DOE Formerly Utilized Sites Remedial Action Program; (4) DOE Uranium Mill Tailings Remedial Action Project; (5) Uranium Mill Tailings Management; (6) DOE Environmental Restoration Program; (7) DOE Site-Specific Remedial Actions; (8) Contaminated Site Restoration; (9) Remediation of Contaminated Soil and Groundwater; (10) Environmental Data Measurements, Management, and Evaluation; (11) Remedial Action Assessment and Decision-Making; (12) Technology Development and Evaluation; and (13) Environmental and Waste Management Issues. Bibliographic references are arranged in nine subject categories by geographic location and then alphabetically by first author, corporate affiliation, or publication title. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, subject category, and key word.

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

    SciTech Connect

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

    2000-02-28

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

  8. Management of radiological safety--lessons learnt and issues arising from the decommissioning of Berkeley power station.

    PubMed

    Spooner, K

    1999-06-01

    Berkeley Power Station was a world leader when in June 1962 it became the UK's first commercial nuclear power station to produce electricity for the National Grid. Berkeley then stood at the leading edge of nuclear technology. After 27 years of successful operation and the supply of nearly 40 billion units of electricity, Berkeley ceased generation in March 1989. Just as it was at start-up, Berkeley is continuing to lead the way as the UK's first commercial nuclear power station to be decommissioned. A three-stage decommissioning process is under way to safely dismantle the plant and eventually return the site to its original 'green field' state. Stage 1 of this process is well advanced. To set the scene, and for general interest, this paper first provides some background to the development of the decommissioning strategy and a brief summary of the progress to date. Recognising the specific interest of the reader, the paper then focuses on the radiological aspects of the work carried out, specifically the hazards, the risk assessment process and the ALARP performance. Finally, and in some detail, the paper reports on the important lessons learnt and discusses one of the issues arising.

  9. Financial Planning as a Tool for Efficient and Timely Decommissioning of Nuclear Research Facilities

    SciTech Connect

    Cato, Anna; Lindskog, Staffan; Sjoeblom, Rolf

    2008-01-15

    It is generally recognized in the technical and economical literature that reliable cost evaluations with adequate estimates also of the errors and uncertainties involved are necessary in order for rational and appropriate management decisions to be made on any major plant investment. Such estimates are required for the selection of technologies to be applied and for selection to be made between alternative technologies and designs as well as for the overall financing issues including the one of whether to go ahead with the project. Inadequacies in the cost calculations typically lead to suboptimal decisions and ultimately substantial overruns and/or needs for retrofits. Actually, a very strict discipline has to be applied with adaptation of the approach used with regard to the stage of the planning. Deviations from the expected tend to raise the estimated cost much more frequently than they lower it. The same rationale applies to planning and cost calculations for decommissioning of nuclear research facilities. There are, however, many reasons why such estimations may be very treacherous to carry out. This will be dealt with in the following. The knowledge base underlying the present paper has been developed and accumulated as a result of the research that the Swedish Nuclear Power Inspectorate (SKI) has carried out in support of its regulatory oversight over the Swedish system of finance. The findings are, however, equally applicable and appropriate for implementers in their planning, decision, monitoring and evaluation activities. In the nineteen fifties and sixties, Sweden had a comprehensive program for utilization of nuclear power including uranium mining, fuel fabrication, reprocessing and domestically developed heavy water reactors. Examples of facilities are presented in Figures 1-5. Eventually, the development work lead to the present nuclear program with ten modern light water reactors in operation at present. According to Swedish law, those who benefit

  10. Facility Decontamination and Decommissioning Program Surveillance and Maintenance Plan, Revision 2

    SciTech Connect

    Poderis, Reed J.; King, Rebecca A.

    2013-09-30

    This Surveillance and Maintenance (S&M) Plan describes the activities performed between deactivation and final decommissioning of the following facilities located on the Nevada National Security Site, as documented in the Federal Facility Agreement and Consent Order under the Industrial Sites program as decontamination and decommissioning sites: ? Engine Maintenance, Assembly, and Disassembly (EMAD) Facility: o EMAD Building (Building 25-3900) o Locomotive Storage Shed (Building 25-3901) ? Test Cell C (TCC) Facility: o Equipment Building (Building 25-3220) o Motor Drive Building (Building 25-3230) o Pump Shop (Building 25-3231) o Cryogenic Lab (Building 25-3232) o Ancillary Structures (e.g., dewars, water tower, piping, tanks) These facilities have been declared excess and are in various stages of deactivation (low-risk, long-term stewardship disposition state). This S&M Plan establishes and implements a solid, cost-effective, and balanced S&M program consistent with federal, state, and regulatory requirements. A graded approach is used to plan and conduct S&M activities. The goal is to maintain the facilities in a safe condition in a cost-effective manner until their final end state is achieved. This plan accomplishes the following: ? Establishes S&M objectives and framework ? Identifies programmatic guidance for S&M activities to be conducted by National Security Technologies, LLC, for the U.S. Department of Energy, National Nuclear Security Administration Nevada Field Office (NNSA/NFO) ? Provides present facility condition information and identifies hazards ? Identifies facility-specific S&M activities to be performed and their frequency ? Identifies regulatory drivers, NNSA/NFO policies and procedures, and best management practices that necessitate implementation of S&M activities ? Provides criteria and frequencies for revisions and updates ? Establishes the process for identifying and dispositioning a condition that has not been previously identified or

  11. Development of a Semi-Autonomous Underwater Vehicle for Intervention Missions (SAUVIM Phase III-B)

    DTIC Science & Technology

    2009-03-20

    Aquarium Research Institute (MBARI). Current and past research includes texture-based vision processing for feedback control and real-time mosaicking...vastness and complexity of the LN material . The LN group was trying to devise a hybrid localization and navigation methodology that will suffice in...of composite materials in reduction of weight, size and strength. Using these results, a scaled model prototype using AS4/PEEK has been fabricated

  12. Development of a Semi-Autonomous Underwater Vehicle for Intervention Missions (SAUVIM Phase III-C)

    DTIC Science & Technology

    2010-01-28

    capable underwater vehicle which operates in a test tank at the Monterey Bay Aquarium Research Institute (MBARI). Current and past research includes...Platform (MCTP). Also, a Localization and Navigation (LN) group was spun-off the LLC group due to the vastness and complexity of the LN material ...thorough analysis and comparison of the Ti-6Al-4V, AS4/Epoxy, and AS4/PEEK pressure vessels manifest the advantage of composite materials in reduction of

  13. Deployment of Shaped Charges by a Semi-Autonomous Ground Vehicle

    DTIC Science & Technology

    2007-06-01

    This research developed a platform that can autonomously navigate GPS waypoints, avoid obstacles , and provide remote user controls for an onboard...static and mobile obstacles as well handling most surfaces with minor slopes. BigFoot continues to be somewhat limited by communications range and...destroy IEDs. This research developed a platform that can autonomously navigate GPS waypoints, avoid obstacles , and provide remote user controls for an

  14. Bacterial cell wall biogenesis is mediated by SEDS and PBP polymerase families functioning semi-autonomously

    PubMed Central

    Cho, Hongbaek; Wivagg, Carl N.; Kapoor, Mrinal; Barry, Zachary; Rohs, Patricia D.A.; Suh, Hyunsuk; Marto, Jarrod A.; Garner, Ethan C.; Bernhardt, Thomas G.

    2016-01-01

    Multi-protein complexes organized by cytoskeletal proteins are essential for cell wall biogenesis in most bacteria. Current models of the wall assembly mechanism assume class A penicillin-binding proteins (aPBPs), the targets of penicillin-like drugs, function as the primary cell wall polymerases within these machineries. Here, we use an in vivo cell wall polymerase assay in Escherichia coli combined with measurements of the localization dynamics of synthesis proteins to investigate this hypothesis. We find that aPBP activity is not necessary for glycan polymerization by the cell elongation machinery as is commonly believed. Instead, our results indicate that cell wall synthesis is mediated by two distinct polymerase systems, SEDS-family proteins working within the cytoskeletal machines and aPBP enzymes functioning outside of these complexes. These findings thus necessitate a fundamental change in our conception of the cell wall assembly process in bacteria. PMID:27643381

  15. Improvised Explosive Devise Placement Detection from a Semi-Autonomous Ground Vehicle

    DTIC Science & Technology

    2006-12-01

    The sonar is a basic ultrasonic sensor. The transmitter emits an ultrasonic pulse or energy (at a frequency of 40 kHz) [Ref. 9]. An object within...the beam pattern then reflects that energy uniformly within a solid angle (this angle may approach 180 degrees). The frequency of the reflected...two WAAS satellites in operation (one over the Atlantic and one over the Pacific Oceans ) [Ref. 17]. The two satellites work in conjunction with

  16. Remote Operators Prefer Goal-based Semi-Autonomous Algorithms (PREPRINT)

    DTIC Science & Technology

    2011-04-18

    Hutchinson, S., G. Hager, and P. Corke, A tutorial on visual servo control. IEEE transactions on robotics and automation, 1996. 12(5): p. 651-670...robot manipulators. IEEE Transactions on Robotics and Automation, 1996. 12(5): p. 684-696. 13. Espiau, B., Effect of camera calibration errors on...1/2 D visual servoing. IEEE Transactions on Robotics and Automation, 1999. 15(2): p. 238-250. 19. Bowditch, N., Dead Reckoning. The American

  17. Development of a Semi-Autonomous Underwater Vehicle for Intervention Missions

    DTIC Science & Technology

    2007-11-02

    E 60 IP - C AR R IE R JR 3 BO AR D M AT R IX M D - AD D AI O R ES O LV ER R EF ER EN C ES R ES O LV ER IN PU T VME Rack Batteries Batteries...center level of the frame. Batteries, ballast and arm stowage space occupy the lower section of the frame as one proceeds from aft to the bow...drive systems, twin spur gear and rack designs. The design eventually chosen must deal with stirred up grit and sand, extensive seawater exposure, as

  18. Semi-autonomous robots for reactor containments. Annual summary report, [1993--1994

    SciTech Connect

    Not Available

    1994-05-06

    During 1993, the activity at the University was split into two primary groups. One group provided direct support for the development and testing of the RVIR vehicle. This effort culminated in a demonstration of the vehicle at ORNL during December. The second group of researchers focused attention on pushing the technology forward in the areas of radiation imaging, navigation, and sensing modalities. A major effort in technology transfer took place during this year. All of these efforts reflected in the periodic progress reports which are attached. During 1994, our attention will change from the Nuclear Energy program to the Environmental Restoration and Waste Management office. The immediate needs of the Robotics Technology Development Program within the Office of Technology Development of EM drove this change in target applications. The University will be working closely with the national laboratories to further develop and transfer existing technologies to mobile platforms which are currently being designed and employed in seriously hazardous environments.

  19. Semi-autonomous liquid handling via on-chip pneumatic digital logic.

    PubMed

    Nguyen, Transon V; Duncan, Philip N; Ahrar, Siavash; Hui, Elliot E

    2012-10-21

    This report presents a liquid-handling chip capable of executing metering, mixing, incubation, and wash procedures largely under the control of on-board pneumatic circuitry. The only required inputs are four static selection lines to choose between the four machine states, and one additional line for power. State selection is simple: constant application of vacuum to an input causes the device to execute one of its four liquid handling operations. Programmed control of 31 valves, including fast coordinated cycling for peristaltic pumping, is accomplished by pneumatic digital logic circuits built out of microfluidic valves and channels rather than electronics, eliminating the need for the off-chip control machinery that is typically required for integrated microfluidics.

  20. Development of Cursor-on-Target Control for Semi-Autonomous Unmanned Aircraft Systems

    DTIC Science & Technology

    2007-06-01

    on what the brain perceives, psychologist are also studying “unconscious inference,” which are assumptions the brain believes ( Purves , 2007). This...19, Providence, Rhode Island, August 2004. Purves , Dale “The answer indicated by perceptual evidence,” Laboratory of Dale Purves , Center for