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Sample records for island tmi unit

  1. TMI-2 [Three Mile Island Unit 2] licensing history

    International Nuclear Information System (INIS)

    Byrne, J.J.

    1988-01-01

    Three Mile Island (TMI), which is located in central Pennsylvania near Harrisburg, is the site of the TMI-2 accident, the most significant nuclear accident in US commercial nuclear power. Since the accident on March 28, 1979, TMI-2 has been undergoing cleanup activities designed to place the plant in a safe, stable, and secure postaccident configuration. At the completion of the cleanup program, TMI-2 will be placed in such a configuration, termed postdefueling monitored storage (PDMS), by the licensee, GPU Nuclear Corporation. The purpose of this paper is to provide a brief overview of the TMI-2 licensing history and to describe its impact on the regulatory process

  2. Implementation of remote equipment at TMI-2 [Three Mile Island Unit 2

    International Nuclear Information System (INIS)

    Giefer, D.; Jeffries, A.B.

    1988-01-01

    Each of the remote vehicles in use, or planned for use, at Three Mile Island Unit 2 (TMI-2) during the period from 1984 to the present had certain distinct common features. These were proven to be desirable for remote application in the TMI-2 environment. Proper implementation requires consideration of the following: control systems, rigging systems, power supplies, operator/support interface, maintenance concerns, viewing systems, contamination control, and communications. Design and component fabrication of these features allowed deployment of each of the remote devices. This paper discusses these systems and their impact for the use of remote mobile equipment at TMI-2. In most cases, the means of implementation dictated the design features of the devices

  3. A guide to technical information regarding TMI-2 [Three Mile Island Unit 2

    International Nuclear Information System (INIS)

    Aucliar, K.D.; Epler, J.

    1988-01-01

    A considerable amount of information has been obtained and documented concerning the March 1979 accident and its consequences at the Three Mile Island Unit 2 (TMI-2) nuclear generating station. The information has been essential in (a) understanding the nature, progression, and extent of the damage from the accident; (b) assessing the effects of this damage on the plant's facilities, systems, equipment, and surrounding environment; and (c) planning, preparation, performance, and evaluation of the accident recovery activities. The composite of all of this literature is the technical information available at TMI-2. The issues raised by the accident are far-reaching and complex, and the technical information has usefulness beyond its application at TMI-2. Issues raised as a result of the accident pose questions that are technical, legal, financial, and political in nature. However, because the quantity of information is vast, this paper focuses on the technical data generated as a result of the TMI-2 accident recovery activities. Most of the written information generated during the TMI-2 recovery program was provided to meet the needs of the various key participants in the recovery. The informational needs of these groups varied widely; consequently, their motivation for record retention, content, and structure revolved around serving those needs. This paper provides some guidance to those researchers interested in investigating technical data as it relates to TMI-2

  4. TMI-2 [Three Mile Island Unit 2] reactor building dose reduction task force

    International Nuclear Information System (INIS)

    Daniels, R.S.

    1988-01-01

    In late October 1982, the director of Three Mile Island Unit 2 (TMI-2) created the dose reduction task force with the objective of identifying the principal radiological sources in the reactor building and recommending actions to minimize the dose to workers on labor-intensive projects. Members of the task force were drawn form various groups at TMI. Findings and recommendations were presented to the US Nuclear Regulatory Commission in a briefing on November 18, 1982. The task force developed a three-step approach toward dose reduction. Step 1 identified the radiological sources. Step 2 modeled the source and estimated its contribution to the general area dose rates. Step 3 recommended actions to achieve dose reductions consistent with general exposure rate goals

  5. Post-accident TMI-2 (Three Mile Island-Unit 2) decontamination and defueling

    International Nuclear Information System (INIS)

    Hofstetter, K.J.; Baston, V.F.

    1986-01-01

    Following the accident at Three Mile Island-Unit 2 (TMI-2), a substantial quantity of fission products was distributed throughout various plant systems and areas. The control of further migration of these radionuclides was accomplished by various physical and chemical means. The decontamination and defueling activities have proceeded within specific regulatory, administrative, and hardware restrictions. A summary of the post-accident status of the plant systems, the decontamination methods used, and the end-point criteria will be discussed. The hardware installed or utilized to perform the cleanup operations will be described. The methods and progress of defueling will also be presented. The development of detailed water chemistry requirements and their effects on systems and decontamination efforts are discussed. The planning, scheduling, and performance of specific recovery tasks are presented along with a general overview of water and chemical management at TMI-2

  6. Programmatic changes due to TMI-2 [Three Mile Island Unit 2]: Accident planning

    International Nuclear Information System (INIS)

    Wingert, V.L.

    1988-01-01

    The focus of the paper is lessons learned for emergency planning and preparedness form the Three Mile Island Unit 2 (TMI-2) accident. The lessons learned are examined from two perspectives: (a) lessons learned that have resulted in programmatic changes, and (b) lessons learned that have not been adequately addressed. There is no doubt that the TMI-2 accident is the pivotal event that caused a major rethinking of the pre-TMI emergency preparedness posture and led to a fundamentally different approach to emergency preparedness for commercial nuclear power plant accidents. While this new approach has evolved into a comprehensive, systematic, and even prototypical national program, it has also generated new problems: escalating costs for state and local governments and leveraging of the federal licensing process by state and local governments who do not want specific nuclear power plants to operate. A discussion of the primary lessons learned on emergency preparedness is presented under the following topics: beyond defense-in-depth, predetermined action, mandatory emergency planning and preparedness, and federal coordination

  7. Criteria development of remotely controlled mobile devices for TMI-2 [Three Mile Island Unit 2

    International Nuclear Information System (INIS)

    Fillnow, R.; Bengel, P.; Giefer, D.

    1988-01-01

    Since 1982, GPU Nuclear Corporation has used a series of remote mobile devices for data collection and cleanup of highly contaminated areas in the Three Mile Island Unit 2 (TMI-2) nuclear facilities. This paper describes these devices and the general criteria established for their design. Until 1984, the remote equipment used at TMI was obtained from industry sources. This included devices called SISI, FRED, and later LOUIE-1. Following 1984, the direction was to obtain custom-made devices to assure a design that would be more appropriate for the TMI-2 environment. Along with this approach came more detailed criteria and a need for a thorough understanding of the task to be accomplished by the devices. The following families of equipment resulted: (1) remote reconnaissance vehicles (RRVs), (2) the LOUIE family, and (3) remote working vehicle (RWV) family

  8. Characterization of fuel distributions in the Three-Mile Island Unit 2 (TMI-2) reactor system by neutron and gamma-ray dosimetry

    International Nuclear Information System (INIS)

    Gold, R.; Roberts, J.H.; Ruddy, F.H.; Preston, C.C.; McNeece, J.P.; Kaiser, B.J.; McElroy, W.N.

    1984-04-01

    The resolution of technical issues generated by the accident at Three-Mile Island Unit 2 (TMI-2) will inevitably be of long range benefit. Determination of the fuel debris dispersal in the TMI-2 reactor system represents a major technical issue. In reactor recovery operations, such as for the safe handling and final disposal of TMI-2 waste, quantitative fuel assessments are being conducted throughout the reactor core and primary coolant system

  9. Technology transfer and radioactive waste management at TMI-2 [Three Mile Island Unit 2

    International Nuclear Information System (INIS)

    Saunders, J.R.

    1988-01-01

    The accident that occurred on March 28, 1979, at the Three Mile Island Unit 2 (TMI-2) nuclear generating station caused extensive damage to the reactor core and created high radiation contamination levels throughout the facility. The electric power industry, regulators, and government agencies were faced with one of the most technically challenging recovery situations ever encountered in this country. But it was also realized that this adversity presented opportunities for the advancement of state-of-the-art technologies as well as the potential to produce information that could enhance nuclear power plant safety and reliability. Perhaps one of the more significant aspects of the TMI-2 recovery has been the advancement of radioactive waste management technology. The high levels and unusual nature of the TMI-2 radioactive waste necessitated the development of innovative techniques for processing, packaging, shipping, and disposal. The investment in research was rewarded with large volume reductions and associated cost savings. It is anticipated that the TMI-2 radioactive waste management technology will make major contributions to the design of new systems to meet this growing need. The following areas appear particularly suited for this purpose: volume reduction, high-integrity containers, and selective isotope removal

  10. Quality assurance in the removal and transport of the TMI-2 [Three Mile Island Unit 2] core

    International Nuclear Information System (INIS)

    Hayes, G.R.; Marsden, J.F.

    1988-01-01

    The March 1979 accident at Three Mile Island Unit 2 (TMI-2) damaged the core of the reactor. One of the major cleanup activities involves removal of the damaged core from the reactor and transporting it from the TMI-2 site near Middletown, Pennsylvania, to the Idaho National Engineering Laboratory (INEL) near Idaho Falls, Idaho. Removal and transport of the damaged core necessitated the development of much specialized equipment. This paper focuses on the role quality assurance (QA) played in the design, fabrication, acceptance, and use of three important pieces of core debris removal and transportation equipment: (1) the core boring machine, (2) the fuel debris canisters, (3) the NuPac 125-B rail cask and handling equipment

  11. Characterization of fuel distribution in the Three Mile Island Unit 2 (TMI-2) reactor system by neutron and gamma-ray dosimetry

    International Nuclear Information System (INIS)

    Gold, R.; Roberts, J.H.; Ruddy, F.H.; Preston, C.C.; McNeece, J.P.; Kaiser, B.J.; McElroy, W.N.

    1984-01-01

    Neutron and gamma-ray dosimetry are being used for nondestructive assessment of the fuel distribution throughout the Three Mile Island Unit 2 (TMI-2) reactor core region and primary cooling system. The fuel content of TMI-2 makeup and purification Demineralizer A has been quantified with Si(Li) continuous gamma-ray spectrometry and solid-state track recorder (SSTR) neutron dosimetry. For fuel distribution characterization in the core region, results from SSTR neutron dosimetry exposures in the TMI-2 reactor cavity are presented. These SSTR results are consistent with the presence of a significant amount of fuel debris, equivalent to several fuel assemblies or more, lying at the bottom of the reactor vessel. (Auth.)

  12. Personnel contamination protection techniques applied during the TMI-2 [Three Mile Island Unit 2] cleanup

    International Nuclear Information System (INIS)

    Hildebrand, J.E.

    1988-01-01

    The severe damage to the Three Mile Island Unit 2 (TMI-2) core and the subsequent discharge of reactor coolant to the reactor and auxiliary buildings resulted in extremely hostile radiological environments in the TMI-2 plant. High fission product surface contamination and radiation levels necessitated the implementation of innovative techniques and methods in performing cleanup operations while assuring effective as low as reasonably achievable (ALARA) practices. The approach utilized by GPU Nuclear throughout the cleanup in applying protective clothing requirements was to consider the overall health risk to the worker including factors such as cardiopulmonary stress, visual and hearing acuity, and heat stress. In applying protective clothing requirements, trade-off considerations had to be made between preventing skin contaminations and possibly overprotecting the worker, thus impacting his ability to perform his intended task at maximum efficiency and in accordance with ALARA principles. The paper discusses the following topics: protective clothing-general use, beta protection, skin contamination, training, personnel access facility, and heat stress

  13. Restarting TMI unit one: social and psychological impacts

    International Nuclear Information System (INIS)

    Sorensen, J.; Soderstrom, J.; Bolin, R.; Copenhaver, E.; Carnes, S.

    1983-12-01

    A technical background is provided for preparing an environmental assessment of the social and psychological impacts of restarting the undamaged reactor at Three Mile Island (TMI). Its purpose is to define the factors that may cause impacts, to define what those impacts might be, and to make a preliminary assessment of how impacts could be mitigated. It does not attempt to predict or project the magnitude of impacts. Four major research activities were undertaken: a literature review, focus-group discussions, community profiling, and community surveys. As much as possible, impacts of the accident at Unit 2 were differentiated from the possible impacts of restarting Unit 1. It is concluded that restart will generate social conflict in the TMI vicinity which could lead to adverse effects. Furthermore, between 30 and 50 percent of the population possess characteristics which are associated with vulnerability to experiencing negative impacts. Adverse effects, however, can be reduced with a community-based mitigation strategy

  14. Restarting TMI unit one: social and psychological impacts

    Energy Technology Data Exchange (ETDEWEB)

    Sorensen, J.; Soderstrom, J.; Bolin, R.; Copenhaver, E.; Carnes, S.

    1983-12-01

    A technical background is provided for preparing an environmental assessment of the social and psychological impacts of restarting the undamaged reactor at Three Mile Island (TMI). Its purpose is to define the factors that may cause impacts, to define what those impacts might be, and to make a preliminary assessment of how impacts could be mitigated. It does not attempt to predict or project the magnitude of impacts. Four major research activities were undertaken: a literature review, focus-group discussions, community profiling, and community surveys. As much as possible, impacts of the accident at Unit 2 were differentiated from the possible impacts of restarting Unit 1. It is concluded that restart will generate social conflict in the TMI vicinity which could lead to adverse effects. Furthermore, between 30 and 50 percent of the population possess characteristics which are associated with vulnerability to experiencing negative impacts. Adverse effects, however, can be reduced with a community-based mitigation strategy.

  15. What actually happened at TMI-2

    International Nuclear Information System (INIS)

    Duco, J.

    1989-08-01

    The 1979 Three Mile Island Unit 2 (TMI-2; USA) accident is evaluated. The reactor core is damaged and the released fission products contaminated the reactor building and the secondary buildings. The radiation dose on the TMI-2 personnel is about 4694 man-rem, from 1979 to 1987. The main steps of the accident and the TMI-2 decontamination actions are described. The accident showed the importance of the reactor vessel's water re-filling as soon as possible during accident [fr

  16. TMI cable tracer operation and maintenance manual for assembly 417910

    International Nuclear Information System (INIS)

    Sumstine, R.L.

    1983-11-01

    This manual provides technical information and instructions to operate and maintain the cable tracer designed for the Three Mile Island (TMI) Unit 2 Reactor Building. The TMI cable tracer was developed to allow TMI personnel to trace cables in cable trays that may be tested or sectioned for destructive examination

  17. Preparations to load, transport, receive, and store the damaged TMI-2 [Three Mile Island] reactor core

    International Nuclear Information System (INIS)

    Reno, H.W.; Schmitt, R.C.; Quinn, G.J.; Ayers, A.L. Jr.; Lilburn, B.J. Jr.; Uhl, D.L.

    1986-03-01

    The March 1979 incident at the Three Mile Island Nuclear Power Station (TMI) which damaged the core of the Unit 2 reactor resulted in numerous scientific and technical challenges. Some of those challenges involve removing, packaging, and transporting the core debris to the Idaho National Engineering Laboratory (INEL) for storage, examination, and preparation for final disposal. This paper highlights preparations for transporting the core debris from TMI to INEL and receiving and storing that material at INEL. Issues discussed include interfacing of equipment and facilities at TMI, loading operations, transportation activities using a newly designed cask, receiving and storing operations at INEL, and criticality control during storage. Key to the transportation effort was designing, testing, fabricating, and licensing two rail casks which individually provide double containment of the damaged fuel. 27 figs

  18. TMI-2 core examination plan

    International Nuclear Information System (INIS)

    Carlson, J.O.

    1984-07-01

    The role of the Three Mile Island Unit 2 (TMI-2) core examination in the resolution of major nuclear safety issues is delineated in this plan. Relevant data needs are discussed, and approaches for recovering data from the TMI-2 plant are identified. Specific recommendations and justifications are provided for in situ documentation and off-site artifact examination activities. The research and development program is being managed by EG and G Idaho, Inc

  19. Heat stress control in the TMI-2 [Three Mile Island Unit 2] defueling and decontamination activities

    International Nuclear Information System (INIS)

    Schork, J.S.; Parfitt, B.A.

    1988-01-01

    During the initial stages of the Three Mile Island Unit 2 (TMI-2) defueling and decontamination activities for the reactor building, it was realized that the high levels of loose radioactive contamination would require the use of extensive protective clothing by entry personnel. While there was no doubt that layered protective clothing protects workers from becoming contaminated, it was recognized that these same layers of clothing would impose a very significant heat stress burden. To prevent the potentially serious consequences of a severe reaction to heat stress by workers in the hostile environment of the TMI-2 reactor building and yet maintain the reasonable work productivity necessary to perform the recovery adequately, an effective program of controlling worker exposure to heat stress had to be developed. Body-cooling devices produce a flow of cool air, which is introduced close to the skin to remove body heat through convection and increased sweat evaporation. The cooling effect produced by the Vortex tube successfully protected the workers from heat stress, however, there were several logistical and operational problems that hindered extensive use of these devices. The last type of cooling garment examined was the frozen water garment (FWG) developed by Elizier Kamon at the Pennsylvania State University as part of an Electric Power Research Institute research grant. Personal protection, i.e., body cooling, engineering controls, and administrative controls, have been implemented successfully

  20. TMI-2 core examination

    International Nuclear Information System (INIS)

    Hobbins, R.R.; MacDonald, P.E.; Owen, D.E.

    1983-01-01

    The examination of the damaged core at the Three Mile Island Unit 2 (TMI-2) reactor is structured to address the following safety issues: fission product release, transport, and deposition; core coolability; containment integrity; and recriticality during severe accidents; as well as zircaloy cladding ballooning and oxidation during so-called design basis accidents. The numbers of TMI-2 components or samples to be examined, the priority of each examination, the safety issue addressed by each examination, the principal examination techniques to be employed, and the data to be obtained and the principal uses of the data are discussed in this paper

  1. Computer code calculations of the TMI-2 accident: initial and boundary conditions

    International Nuclear Information System (INIS)

    Behling, S.R.

    1985-05-01

    Initial and boundary conditions during the Three Mile Island Unit 2 (TMI-2) accident are described and detailed. A brief description of the TMI-2 plant configuration is given. Important contributions to the progression of the accident in the reactor coolant system are discussed. Sufficient information is provided to allow calculation of the TMI-2 accident with computer codes

  2. 78 FR 77726 - Exelon Generation Company, LLC Three Mile Island Nuclear Station, Unit 1

    Science.gov (United States)

    2013-12-24

    ... Three Mile Island Nuclear Station, Unit 1 AGENCY: Nuclear Regulatory Commission. ACTION: Exemption... License No. DPR-50, which authorizes operation of the Three Mile Island Nuclear Station, Unit 1 (TMI-1... Facility Operating License No. DPR-50, which authorizes operation of the Three Mile Island Nuclear Station...

  3. 75 FR 36700 - Exelon Generation Company, LLC; Three Mile Island Nuclear Station, Unit 1; Environmental...

    Science.gov (United States)

    2010-06-28

    ...; Three Mile Island Nuclear Station, Unit 1; Environmental Assessment and Finding of No Significant Impact... Company, LLC (the licensee), for operation of Three Mile Island Nuclear Station, Unit 1 (TMI-1), located... Three Mile Island Nuclear Station, Units 1 and 2, NUREG-0552, dated December 1972, and Generic...

  4. 78 FR 49553 - Three Mile Island, Unit 2; Post Shutdown Decommissioning Activities Report

    Science.gov (United States)

    2013-08-14

    ... NUCLEAR REGULATORY COMMISSION [Docket No. 50-320; NRC-2013-0183] Three Mile Island, Unit 2; Post Shutdown Decommissioning Activities Report AGENCY: Nuclear Regulatory Commission. ACTION: Notice of receipt... Shutdown Decommissioning Activity Report (PSDAR) for Three Mile Island, Unit 2 (TMI-2). The PSDAR provides...

  5. TMI-2 [Three Mile Island Unit 2] primary coolant mass flowrate data report

    International Nuclear Information System (INIS)

    McCormick, R.D.

    1986-12-01

    This is a report on the preparation of data from the TMI-2 primary coolant mass flowrate meters for inclusion into the TMI Data Base. The sources of the as-recorded data are discussed, and a description of the instrument is given. An explanation is given of how corrections were made to the as-recorded data and how the uncertainties were calculated. The identifiers attached to each data set in the TMI Data Base are given

  6. Nondestructive techniques for assaying fuel debris in piping at Three Mile Island Unit 2

    International Nuclear Information System (INIS)

    Vinjamuri, K.; McIsaac, C.V.; Beller, L.S.; Isaacson, L.; Mandler, J.W.; Hobbins, R.R. Jr.

    1981-11-01

    Four major categories of nondestructive techniques - ultrasonic, passive gamma ray, infrared detection, and remote video examination - have been determined to be feasible for assaying fuel debris in the primary coolant system of the Three Mile Island Unit 2 (TMI-2) Reactor. Passive gamma ray detection is the most suitable technique for the TMI-2 piping; however, further development of this technique is needed for specific application to TMI-2

  7. Regional Power Authority urged for TMI operations

    International Nuclear Information System (INIS)

    Anon.

    1981-01-01

    If the Three Mile Island (TMI) unit 1 returns to service, state ownership with a Regional Power Authority to oversee its operation and complete the cleanup of unit 2 would benefit ratepayers and avoid lengthy lawsuits, according to an Arthur Young and Company report to the New Jersey Board of Utilities. The report rejects continued ownership by General Public Utilities (GPU), merger, divestiture, and other options. It also outlines several conditions necessary for a Regional Power Authority: adequate rate relief, restart of TMI-1, congressional tax exemption, and approval by the GPU board and stockholders. The report recommends that Jersey Central divest itself of GPU to avoid financial disaster if GPU should declare bankruptcy, but it advises maintaining the flexibility to exercise long-term options

  8. TMI-2 [Three Mile Island Nuclear Power Station] fuel canister and core sample handling equipment used in INEL hot cells

    International Nuclear Information System (INIS)

    McConnell, J.W. Jr.; Shurtliff, W.T.; Lynch, R.J.; Croft, K.M.; Whitmill, L.J.; Allen, S.M.

    1987-01-01

    This paper describes the specialized remote handling equipment developed and used at the Idaho National Engineering Laboratory (INEL) to handle samples obtained from the core of the damaged Unit 2 reactor at Three Mile Island Nuclear Power Station (TM-2). Samples of the core were removed, placed in TMI-2 fuel canisters, and transported to the INEL. Those samples will be examined as part of the analysis of the TMI-2 accident. The equipment described herein was designed for removing sample materials from the fuel canisters, assisting with initial examination, and processing samples in preparation for detailed examinations. The more complex equipment used microprocessor remote controls with electric motor drives providing the required force and motion capabilities. The remaining components were unpowered and manipulator assisted

  9. Qualification of Daiichi Units 1, 2, and 3 Data for Severe Accident Evaluations - Process and Illustrative Examples from Prior TMI-2 Evaluations

    Energy Technology Data Exchange (ETDEWEB)

    Rempe, Joy Lynn [Idaho National Lab. (INL), Idaho Falls, ID (United States); Knudson, Darrell Lee [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2014-09-01

    The accidents at the Three Mile Island Unit 2 (TMI-2) Pressurized Water Reactor (PWR) and the Daiichi Units 1, 2, and 3 Boiling Water Reactors (BWRs) provide unique opportunities to evaluate instrumentation exposed to severe accident conditions. Conditions associated with the release of coolant and the hydrogen burn that occurred during the TMI-2 accident exposed instrumentation to harsh conditions, including direct radiation, radioactive contamination, and high humidity with elevated temperatures and pressures. As part of a program initiated in 2012 by the Department of Energy Office of Nuclear Energy (DOE-NE), a review was completed to gain insights from prior TMI-2 sensor survivability and data qualification efforts. This initial review focused on the set of sensors deemed most important by post-TMI-2 instrumentation evaluation programs. Instrumentation evaluation programs focused on data required by TMI-2 operators to assess the condition of the reactor and containment and the effect of mitigating actions taken by these operators. In addition, prior efforts focused on sensors providing data required for subsequent forensic evaluations and accident simulations. To encourage the potential for similar activities to be completed for qualifying data from Daiichi Units 1, 2, and 3, this report provides additional details related to the formal process used to develop a qualified TMI-2 data base and presents data qualification details for three parameters: primary system pressure; containment building temperature; and containment pressure. As described within this report, sensor evaluations and data qualification required implementation of various processes, including comparisons with data from other sensors, analytical calculations, laboratory testing, and comparisons with sensors subjected to similar conditions in large-scale integral tests and with sensors that were similar in design to instruments easily removed from the TMI-2 plant for evaluations. As documented

  10. Plan for shipment, storage, and examination of TMI-2 fuel

    International Nuclear Information System (INIS)

    Quinn, G.J.; Engen, I.A.; Tyacke, M.J.; Reno, H.W.

    1984-05-01

    This Plan addresses the preparation and shipment of core debris from Three Mile Island Unit 2 (TMI-2) to the Idaho National Engineering Laboratory (INEL) for receipt, storage, and examination. The Manager of the Nuclear Materials Evaluation Programs Division of EG and G Idaho, Inc. will manage two separate but integrated programs, one located at TMI (Part 1) and the other at INEL (Part 2). The Technical Integration Office (at TMI) is responsible for developing and implementing Part 1, TMI-2 Core Shipment Program. That portion of the Plan establishes coordination between TMI and INEL (and others) for shipment of core debris, and it provides the coordination by which handling systems at both locations are designed, constructed, or modified to establish and maintain system compatibility. The Technical Support Branch (at INEL) is responsible for developing and implementing Part 2, Core Activities Program. That portion of the Plan details operational and examination activities at INEL, as well as defines core-related activities planned at other DOE laboratories

  11. Preparations to receive and store the TMI-2 core debris

    International Nuclear Information System (INIS)

    Ayers, A.L.R. Jr.; Lilburn, B.J. Jr.

    1986-01-01

    The March 1979 accident at Unit 2 of Three Mile Island Nuclear Power Station (TMI-2) resulted in considerable damage to the core of the reactor. The core debris will be packaged in canisters and transported by rail cask to the Idaho National Engineering Laboratory (INEL) for storage, examination, and preparation for final disposal. A significant part of recovering from the TMI-2 accident involves receiving and storing the TMI-2 core debris canisters at INEL. This paper highlights preparations for receiving the rail cask at INEL, unloading canisters from the cask in the Hot Shop of Test Area North Building 607, and storing/monitoring those canisters in the Water Pit for up to 30 years

  12. Thermal-hydraulic analysis of the Three Mile Island Unit 2 reactor accident with THALES code

    International Nuclear Information System (INIS)

    Hashimoto, Kazuichiro; Soda, Kunihisa

    1991-10-01

    The OECD Nuclear Energy Agency (NEA) has established a Task Group in the Committee on the Safety of Nuclear Installations (CSNI) to perform an analysis of Three Mile Island Unit 2 (TMI-2) accident as a standard problem to benchmark severe accident computer codes and to assess the capability of the codes. The TMI-2 Analysis Exercise was performed at the Japan Atomic Energy Research Institute (JAERI) using the THALES (Thermal-Hydraulic Analysis of Loss-of-Coolant, Emergency Core Cooling and Severe Core Damage) - PM1/TMI code. The purpose of the analysis is to verify the capability of THALES-PM1/TMI code to describe accident progression in the actual plant. The present paper describes the final result of the TMI-2 Analysis Exercise performed at JAERI. (author)

  13. Transporting fuel debris from TMI-2 to INEL

    International Nuclear Information System (INIS)

    Quinn, G.J.; Burton, H.M.; Bixby, W.W.; McIntosh, T.W.; McGoff, O.J.; Barkonic, R.J.; Henrie, J.O.

    1986-06-01

    Transportation of the damaged fuel from Unit 2 of Three Mile Island (TMI-2) presented noteworthy technical challenges involving complex institutional issues. The program resulted from both a need to package and remove the accident debris and also the opportunity to receive and study damaged core components. These combined to establish the safe transport of the TMI-2 fuel debris as a high priority for many diverse organizations. The capability of the sending and receiving facilities to handle spent fuel transport casks in the most cost-effective manner was assessed and resulted in the development by Nuclear Packaging Inc. (NuPac) of the NuPac 125-B rail cask. This paper reviews the technical challenges in preparation of the TMI-2 core debris for transport from TMI-2 to the Idaho National Engineering Laboratory (INEL) and receipt and storage of that material at INEL. Challenges discussed include design and testing of fuel debris canisters; design, fabrication and licensing of a new rail cask for spent fuel transport; cask loading operations, equipment and facilities at TMI-2; transportation logistics; and, receipt, storage and core examination operations at INEL. 10 refs

  14. TMI-2 Vessel Investigation Project integration report

    International Nuclear Information System (INIS)

    Wolf, J.R.; Rempe, J.L.; Stickler, L.A.; Korth, G.E.; Diercks, D.R.; Neimark, L.A.; Akers, D.W.; Schuetz, B.K.; Shearer, T.L.; Chavez, S.A.; Thinnes, G.L.; Witt, R.J.; Corradini, M.L.; Kos, J.A.

    1994-03-01

    The Three Mile Island Unit 2 (TMI-2) Vessel Investigation Project (VIP) was an international effort that was sponsored by the Nuclear Energy Agency of the Organization for Economic Cooperation and Development. The primary objectives of the VIP were to extract and examine samples from the lower head and to evaluate the potential modes of failure and the margin of structural integrity that remained in the TMI-2 reactor vessel during the accident. This report presents a summary of the major findings and conclusions that were developed from research during the VIP. Results from the various elements of the project are integrated to form a cohesive understanding of the vessel's condition after the accident

  15. TMI-2 Vessel Investigation Project integration report

    Energy Technology Data Exchange (ETDEWEB)

    Wolf, J. R.; Rempe, J. L.; Stickler, L. A.; Korth, G. E.; Diercks, D. R.; Neimark, L. A.; Akers, D W; Schuetz, B. K.; Shearer, T L; Chavez, S. A.; Thinnes, G. L.; Witt, R. J.; Corradini, M L; Kos, J. A. [EG and G Idaho, Inc., Idaho Falls, ID (United States)

    1994-03-01

    The Three Mile Island Unit 2 (TMI-2) Vessel Investigation Project (VIP) was an international effort that was sponsored by the Nuclear Energy Agency of the Organization for Economic Cooperation and Development. The primary objectives of the VIP were to extract and examine samples from the lower head and to evaluate the potential modes of failure and the margin of structural integrity that remained in the TMI-2 reactor vessel during the accident. This report presents a summary of the major findings and conclusions that were developed from research during the VIP. Results from the various elements of the project are integrated to form a cohesive understanding of the vessel`s condition after the accident.

  16. TMI-2 in-vessel hydraulic systems utilize high water and high boron content fluids

    International Nuclear Information System (INIS)

    Baston, V.F.; Hofstetter, K.J.; Hofman, L.A.; Gallagher, R.E.

    1987-01-01

    Choice of a hydraulic fluid for use in the Three Mile Island Unit 2 (TMI-2) reactor vessel defueling equipment required consideration of the following constraints for the hydraulic fluid given an accidental spill into the reactor coolant system (RCS). The TMI-2 RCS hydraulic fluid utilized in the hydraulic operations utilized a solution composition of 95 wt% water and 5 wt% of the above base fluid. The TMI-2 hydraulic system utilizes pressures up to 3500 psi. The selected hydraulic fluid has been in use since December 1986 with minimal operational difficulties

  17. TMI-2 Vessel Investigation Project Metallurgical Program

    International Nuclear Information System (INIS)

    Diercks, D.R.; Neimark, L.A.

    1990-01-01

    The TMI-2 [Three Mile Island unit 2] Vessel Investigation Project Metallurgical Program at Argonne National Laboratory is a part of the international TMI-2 Vessel Investigation Project being conducted jointly by the U.S. Nuclear Regulatory Commission and the Organization for Economic Co-operation and Development (OECD). The overall project consists of three phases, namely (1) recovery of material samples from the lower head of the TMI-2 reactor, (2) examination and analysis of the lower head samples and the preparation and testing of archive material subjected to a similar thermal history, and (3) procurement, examination, and analysis of companion core material located adjacent to or near the lower head material. The specific objectives of the ANL Metallurgical Program, which accounts for a major portion of Phase 2, are to prepare metallographic and mechanical test specimen blanks from the TMI-2 lower head material, prepare similar test specimen blanks from suitable archive material subjected to the appropriate thermal processing, determine the mechanical properties of the lower vessel head and archive materials under the conditions of the core-melt accident, and assess the lower head integrity and margin-to-failure during the accident. The ANL work consists of three tasks: (1) archive materials program, (2) fabrication of metallurgical and mechanical test specimens from the TMI-2 pressure vessel samples, and (3) mechanical property characterization of TMI-2 lower pressure vessel head and archive material

  18. Comparison of implementation of selected TMI action plan requirements on operating plants designed by Babcock and Wilcox

    International Nuclear Information System (INIS)

    Thoma, J.O.

    1984-05-01

    This report provides the results of a study conducted by the US Nuclear Regulatory Commission staff to compare the degree to which eight Babcock and Wilcox (B and W) designed licensed nuclear power plants have complied with the requirements in NUREG-0737, Clarification of TMI Action Plan Requirements. The eight licensed operating plants examined are as follows: Arkansas Nuclear One Unit 1 (ANO-1), Crystal River Unit 3, Davis Besse, Oconee Units 1, 2, and 3, Rancho Seco, and Three Mile Island Unit 1 (TMI-1). The purpose of this audit was to establish the progress of the TMI-1 licensee, General Public Utilities (GPU) Nuclear Corporation, in completing the long-term requirements in NUREG-0737 relative to the other B and W licensees examined

  19. Severe accident management: radiation dose control, Fukushima Daiichi and TMI-2 nuclear plant accidents

    International Nuclear Information System (INIS)

    Shaw, Roger

    2014-01-01

    This presentation presents valuable dose information related to the Fukushima Daiichi and Three Mile Island Unit 2 (TMI-2) Nuclear Plant accidents. Dose information is provided for what is well known for TMI-2, and what is available for Fukushima Daiichi. Particular emphasis is placed on the difference between the type of reactors involved, overarching plant damage issues, and radiation worker dose outcomes. For TMI-2, more in depth dose data is available for the accident and the subsequent recovery efforts. The comparisons demonstrate the need to understand the wide variation in potential dose management measures and outcomes for severe reactor accidents. (author)

  20. TMI-2 auxiliary building elevator shaft and pit decontamination

    Energy Technology Data Exchange (ETDEWEB)

    Bengel, T.G.

    1986-01-01

    Decontamination of the elevator pit and shaft in the auxiliary building at Three Mile Island Unit 2 (TMI-2) was performed to remove high radiation and contamination levels which prevented personnel from utilizing the elevator. The radiation and contamination levels in the TMI-2 auxiliary building elevator shaft have been reduced to the point where plant personnel are again permitted to ride in the elevator without a radiation work permit, with the exception of access to the 281-ft (basement) level. Based on the declassification and expanded use of the elevator, the task goal has been met. The tax expended 16.16 man-rem and 621 man-hours.

  1. Research and development activities on Three Mile Island Unit Two. Annual report for 1985

    International Nuclear Information System (INIS)

    1986-04-01

    The year 1985 was significant in the cleanup of Three Mile Island Unit 2 (TMI-2). Major milestones in the project included lifting the plenum assembly from the reactor vessel and the start of operations to remove the damaged fuel from the reactor. This report summarizes these milestones and other TMI-2 related cleanup, research, and development activities. Other major topics include the following: waste immobilization and management; fuel shipping cask delivery and testing; sample acquisition and evaluation; and decontamination and dose reduction. 26 figs.

  2. Flowsheet development studies for the decontamination of high-activity-level water at Three Mile Island Unit 2

    International Nuclear Information System (INIS)

    Collins, E.D.; Bigelow, J.E.; Campbell, D.O.; King, L.J.; Knauer, J.B.

    1980-01-01

    Several chemical processing flowsheets were considered for the decontamination of high-activity-level water at the Three Mile Island (TMI) Unit 2. A zeolite ion exchange process was evaluated and recommended for absorption of the bulk of the highly radioactive cesium and strontium. Standard organic ion-exchange resins were selected to remove the remaining traces of radioactive nuclides (except tritium which cannot be removed by any practical process). Process conditions were evaluated using both synthetic, tracer-level solutions and samples of actual, high-activity level water from TMI Unit 2

  3. A comparison of measured radionuclide release rates from Three Mile Island Unit-2 core debris for different oxygen chemical potentials

    International Nuclear Information System (INIS)

    Baston, V.F.; Hofstetter, K.J.; Ryan, R.F.

    1987-01-01

    Chemical and radiochemical analyses of reactor coolant samples taken during defueling of the Three Mile Island Unit-2 (TMI-2) reactor provide relevant data to assist in understanding the solution chemistry of the radionuclides retained within the TMI-2 reactor coolant system. Hydrogen peroxide was added to various plant systems to provide disinfection for microbial contamination and has provided the opportunity to observe radionuclide release under different oxygen chemical potentials. A comparison of the radionuclide release rates with and without hydrogen peroxide has been made for these separate but related cases, i.e., the fuel transfer canal and connecting spent-fuel pool A with the TMI-2 reactor plenum in the fuel transfer canal, core debris grab sample laboratory experiments, and the reactor vessel fluid and associated core debris. Correlation and comparison of these data indicate a physical parameter dependence (surface-to-volume ratio) affecting all radionuclide release; however, selected radionuclides also demonstrate a chemical dependence release under the different oxygen chemical potentials. Chemical and radiochemical analyses of reactor coolant samples taken during defueling of the Three Mile Island Unit-2 (TMI-2) reactor provide relevant data to assist in understanding the solution chemistry of the radionuclides retained within the TMI-2 reactor coolant system

  4. GPU seeks new funding for TMI cleanup

    International Nuclear Information System (INIS)

    Utroska, D.

    1982-01-01

    General Public Utilities (GPU) wants approval for annual transfer of money from base rate increases in other accounts to pay for the cleanup at Three Mile Island (TMI) until TMI-1 returns to service or the public utility commission takes further action. This proposal confirms fears of a delay in TMI-1 startup and demonstrates that the January negotiated settlement will produce little funding for TMI-2 cleanup. A review of the settlement terms outlines the three-step process for base rate increases and revenue adjustments after the startup of TMI-1, and points out where controversy and delays due to psychological stress make a new source of money essential. GPU thinks customer funding will motivate other parties to a broad-based cost-sharing agreement

  5. Preliminary results of the TMI-2 radioactive iodine mass balance study

    International Nuclear Information System (INIS)

    Pelletier, C.A.; Cox, T.E.; Reeder, D.L.; Vollique, P.G.; Thomas, C.D.

    1982-01-01

    Analysis of samples taken from the Three Mile Island Unit 2 (TMI-2) reactor building following the 1979 accident indicates the fraction of the radioactive iodine (radioiodine) inventory in the core released to the uilding atmosphere is smaller tan assumed in Regulatory Guide 1.4. This summary presents analytical results supporting this conclusion

  6. The TMI-2 remote technology program

    International Nuclear Information System (INIS)

    Bengel, P.R.

    1986-01-01

    Since the accident at Three Mile Island Unit 2 (TMI-2), an aggressive approach has been pursued in developing the tools needed for the recovery of the plant. The plant's owner has embarked on a systematic program to develop remote equipment. The program developed conceptual and then physical equipment. The remote reconnaissance vehicles (RRVs) and the remote working vehicle (RWV) span the requirements of the recovery program from the ability to perform radiological and video surveys to heavy-duty decontamination and demolition work. 4 figs

  7. Instrumentation Performance during the TMI-2 Accident

    International Nuclear Information System (INIS)

    Rempe, Joy L.; Knudson, Darrell L.

    2013-06-01

    The accident at the Three Mile Island Unit 2 (TMI- 2) reactor provided a unique opportunity to evaluate sensors exposed to severe accident conditions. Conditions associated with the release of coolant and the hydrogen burn that occurred during this accident exposed instrumentation to harsh conditions, including direct radiation, radioactive contamination, and high humidity with elevated temperatures and pressures. As part of a program initiated by the Department of Energy Office of Nuclear Energy (DOE-NE), a review was completed to gain insights from prior TMI-2 sensor survivability and data qualification efforts. This new effort focused upon a set of sensors that provided critical data to TMI-2 operators for assessing the condition of the plant and the effects of mitigating actions taken by these operators. In addition, the effort considered sensors providing data required for subsequent accident simulations. Over 100 references related to instrumentation performance and post-accident evaluations of TMI-2 sensors and measurements were reviewed. Insights gained from this review are summarized within this paper. As noted within this paper, several techniques were invoked in the TMI-2 post-accident program to evaluate sensor survivability status and data qualification, including comparisons with data from other sensors, analytical calculations, laboratory testing, and comparisons with sensors subjected to similar conditions in large-scale integral tests and with sensors that were similar in design but more easily removed from the TMI-2 plant for evaluations. Conclusions from this review provide important insights related to sensor survivability and enhancement options for improving sensor performance. In addition, this paper provides recommendations related to sensor survivability and the data evaluation process that could be implemented in upcoming Fukushima Daiichi recovery efforts. (authors)

  8. Program plan for shipment, receipt, and storage of the TMI-2 core. Revision 1

    International Nuclear Information System (INIS)

    Quinn, G.J.; Reno, H.W.; Schmitt, R.C.

    1985-01-01

    This plan addresses the preparation and shipment of core debris from Three Mile Island Unit 2 (TMI-2) to the Idaho National Engineering Laboratory (INEL) and receipt and storage of that core debris. The Manager of the Nuclear Materials Evaluation Programs Division of EG and G Idaho, Inc. will manage two separate but integrated programs, one located at TMI (Part 1) and the other at INEL (Part 2). The Technical Integration Office (at TMI) is responsible for developing and implementing Part 1, TMI-2 Core Shipment Program. The Technical Support Branch (at INEL) is responsible for developing and implementing Part 2, TMI-2 Core Receipt and Storage. The plan described herein is a revision of a previous document entitled Plan for Shipment, Storage, and Examination of TMI-2 Fuel. This revision was required to delineate changes, primarily in Part 2, Core Activities Program, of the previous document. That part of the earlier document related to core examination was reidentified in mid-FY-1984 as a separate trackable entity entitled Core Sample Acquisition and Examination Project, which is not included here

  9. Task plan for the US Department of Energy TMI-2 programs

    International Nuclear Information System (INIS)

    1982-10-01

    The Task Plan for the US Department of Energy (DOE) Three Mile Island (TMI) Unit 2 Programs identifies the tasks to be planned and administered by the DOE Technical Integration Office (TIO) in a manner which will maximize the use of available resources, obtain the maximum benefit from the opportunities associated with the TMI-2 cleanup effort, and retrieve generically useful information for addressing some of the key problems and issues facing the nuclear power industry. The Plan identifies tasks in three major program areas where DOE has assumed implementation responsibility. The DOE TMI-2 Programs are: Data Acquisition Program, Waste Immobilization Program, and Reactor Evaluation Program. The plan is intended to serve as a management overview by defining the task objective, benefits, and work scope with respect to prioritization of tasks and utilization of resources

  10. Tellurium chemistry, tellurium release and deposition during the TMI-2 accident

    International Nuclear Information System (INIS)

    Vinjamuri, K.; Sallach, R.A.; Osetek, D.J.; Hobbins, R.R.; Akers, D.W.

    1985-01-01

    This paper presents the chemistry and estimated behavior of tellurium during and after the accident at Three Mile Island Unit-2. The discussion of tellurium behavior is based on all available measurement data for /sup 129m/Te, 132 Te, stable tellurium ( 126 Te, 128 Te, and 130 Te), and best estimate calculations of tellurium release and transport. Results from Oak Ridge National Laboratory (ORNL) tests, Power Burst Facility (PBF) Severe Fuel Damage Tests at Idaho National Engineering Laboratory (INEL) and SASCHA tests from Karlsruhe, W. Germany are compared with calculated release fractions and samples taken from TMI Unit-2. It is concluded that very little tellurium was released and transported from the TMI-2 core, probably as a result of holdup by zircaloy cladding and other structural materials. 37 refs., 12 figs., 4 tabs

  11. Tellurium chemistry, tellurium release and deposition during the TMI-2 accident

    International Nuclear Information System (INIS)

    Vinjamuri, K.; Sallach, R.A.; Osetek, D.J.; Hobbins, R.R.; Akers, D.W.

    1985-08-01

    This report presents the chemistry and estimated behavior of tellurium during and after the accident at Three Mile Island Unit-2. The discussion of tellurium behavior is based on all available measurement data for /sup 129 m/Te, 132 Te, stable tellurium ( 126 Te, 128 Te, and 130 Te), and best estimate calculations of tellurium release and transport. Results from Oak Ridge National Laboratory (ORNL) tests, Power Burst Facility (PBF) Severe Fuel Damage Tests at Idaho National Engineering Laboratory (INEL) and SASCHA tests from Karlsruhe, W. Germany are compared with calculated release fractions and samples taken from TMI Unit-2. It is concluded that very little tellurium was released and transported from the TMI-2 core, probably as a result of holdup by zircaloy cladding and other structural materials. 39 refs., 24 figs., 17 tabs

  12. TMI-2 Vessel Investigation Project (VIP) Metallurgical Program

    International Nuclear Information System (INIS)

    Diercks, D.R.; Neimark, L.A.

    1991-01-01

    The Three Mile Island Unite 2 (TMI-2) Vessel Investigation Project Metallurgical Program is a part of the international TMI-2 Vessel Investigation Project being conducted jointly by the U.S. Nuclear Regulatory Commission and the Organization for Economic Cooperation and Development. The objectives of the metallurgical program are to deduce the temperatures of, determine the mechanical properties of, and assess the integrity of the TMI-2 lower head during the loss-of-coolant accident. Fifteen samples have been removed from the lower head and are being examined. In addition, archive material from the lower head of the Midland nuclear reactor has been procured for conducting supplemental metallurgical evaluations and mechanical property determinations. Evaluations of the microstructure and mechanical properties of the as-received archive material have been completed, and a series of heat treatment experiments has been conducted to develop standard microstructures to be compared with those present in the TMI-2 samples. Results have been obtained from examinations of two of the fifteen TMI-2 lower head samples. These results indicate that one of these two samples, which contained cracks in the weld cladding extending ∼3 mm into the underlying base metal, apparently reached temperatures on the order of 1000 to 1100C during the accident. A preliminary examination of the core debris deposited on this sample has been performed. The other sample, from an area away from the region of core relocation, did not exceed 727C during the accident

  13. TMI-2 Technical Information and Examination Program. 1984 annual report

    International Nuclear Information System (INIS)

    Hess, C.J.

    1985-04-01

    In 1984, the US Department of Energy's Technical Information and Examination Program entered its fifth year of research and development work at Three Mile Island Unit 2 (TMI-2) and at the Idaho National Engineering Laboratory and other supporting laboratories. The work concentrated on six major areas: waste immobilization, reactor evaluation, data acquisition, information and industry coordination, core activities, and EPICOR II and waste research and disposition

  14. Historical summary of the fuel and waste handling and disposition activities of the TMI-2 Information and Examination Program (1980-1988)

    International Nuclear Information System (INIS)

    Reno, H.W.; Schmitt, R.C.

    1988-10-01

    This report is a historical summary of the major activities conducted by the TMI-2 Information and Examination Program in managing fuel and special radioactive wastes resulting from the accident at the Unit 2 reactor of the Three Mile Island Nuclear Power Station (TMI-2). The activities often required the development and use of advanced handling, processing, and/or disposal technologies for those wastes

  15. TMI-2 information and examination program 1981 annual report

    International Nuclear Information System (INIS)

    1982-04-01

    The Department of Energy's Technical Information and Examination Program at Three Mile Island Unit 2 continued the research and development work begun on the Island in 1979. The work concentrated in seven major areas: instrumentation and electrical components; radiation and environment; off-site core examination; radioactive waste technology development; configuration and document control; waste immobilization; and reactor evaluation. Research and development work associated with the program aims toward communicating applicable information to the nuclear community. The program seeks to assist in resolving specific problems at TMI-2 and to stimulate interest in specific work activities, thus ensuring that the entire nuclear industry avails itself of the maximum amount of information possible

  16. Analysis of steam-generator tube-rupture events combined with auxiliary-feedwater control-system failure for Three Mile Island-Unit 1 and Zion-Unit 1 pressurized water reactors

    International Nuclear Information System (INIS)

    Nassersharif, B.

    1986-01-01

    A steam-generator tube-rupture (SGTR) event combined with loss of all offsite alternating-current power and failure of the auxiliary-feedwater (AFW) control system has been investigated for the Three Mile Island-Unit 1 (TMI-1) and Zion-Unit 1 (Zion-1) pressurized water reactors. The Transient Reactor Analysis Code was used to simulate the accident sequence for each plant. The objectives of the study were to predict the plant transient response with respect to tube-rupture flow termination, extent of steam generator overfill, and thermal-hydraulic conditions in the steam lines. Two transient cases were calculated: (1) a TMI-1 SGTR and runaway-AFW transient, and (2) a Zion-1 SGTR and runaway-AFW transient. Operator actions terminated the tube-rupture flow by 1342 s (22.4 min) and 1440 s (24.0 min) for TMI-1 and Zion-1, respectively, but AFW injection was continued. The damaged steam generator (DSG) overfilled by 1273 s (21.2 min) for the TMI-1 calculation and by 1604 s (26.7 min) for the Zion-1 calculation. The DSG steam lines were completely filled by 1500 s (25 min) and 2000 s (33.3 min) for TMI-1 and Zion-1, respectively. The maximum subcooling in the steam lines was approx.63 K (approx.113 0 F) for TMI-1 and approx.44 K (approx.80 0 F) for Zion-1

  17. GPU v. B and W lawsuit review and its effect on TMI-1 (Docket 50-289)

    International Nuclear Information System (INIS)

    1983-09-01

    This report documents a review by the Nuclear Regulatory Commission (NRC) staff of the General Public Utilities Corporation, et al. v. the Babcock and Wilcox Company, et al. (GPU v. B and W) lawsuit record to assess whether any of the staff's previous conclusions or their principal bases presented at the Three Mile Island Unit 1 (TMI-1) restart hearing, supporting restart of TMI-1, should be amended in light of the information contained in the lawsuit record. Details of the lawsuit record are provided in the appendices contained in Volume II of this report

  18. GPU v. B and W lawsuit review and its effect on TMI-1 (Docket 50-289)

    Energy Technology Data Exchange (ETDEWEB)

    1983-09-01

    This report documents a review by the Nuclear Regulatory Commission (NRC) staff of the General Public Utilities Corporation, et al. v. the Babcock and Wilcox Company, et al. (GPU v. B and W) lawsuit record to assess whether any of the staff's previous conclusions or their principal bases presented at the Three Mile Island Unit 1 (TMI-1) restart hearing, supporting restart of TMI-1, should be amended in light of the information contained in the lawsuit record. Details of the lawsuit record are provided in the appendices contained in Volume II of this report.

  19. Summary Report of Commercial reactor Criticality Data for Three Mile Island Unit 1

    International Nuclear Information System (INIS)

    Larry B. Wimmer

    2001-01-01

    The objective of the ''Summary Report of Commercial Reactor Criticality Data for Three Mile Island Unit I'' is to present the CRC data for the TMI-1 reactor. Results from the CRC evaluations will support the development and validation of the neutronics models used for criticality analyses involving commercial spent nuclear fuel. These models and their validation are discussed in the ''Disposal Criticality Analysis Methodology Topical Report'' (YMP 2000)

  20. Historical summary of the Three Mile Island Unit 2 core debris transportation campaign

    Energy Technology Data Exchange (ETDEWEB)

    Schmitt, R.C.; Tyacke, M.J. [EG and G Idaho, Inc., Idaho Falls, ID (United States); Quinn, G.J. [Wastren, Inc., Germantown, MD (United States)

    1993-03-01

    Transport of the damaged core materials from the Unit 2 reactor of the Three Mile Island Nuclear Power Station (TMI-2) to the Idaho National Engineering Laboratory (INEL) for examination and storage presented many technical and institutional challenges, including assessing the ability to transport the damaged core; removing and packaging core debris in ways suitable for transport; developing a transport package that could both meet Federal regulations and interface with the facilities at TMI-2 and the INEL; and developing a transport plan, support logistics, and public communications channels suited to the task. This report is a historical summary of how the US Department of Energy addressed those challenges and transported, received, and stored the TMI-2 core debris at the INEL. Subjects discussed include preparations for transport, loading at TMI-2, institutional issues, transport operations, receipt and storage at the INEL, governmental inquiries/investigations, and lessons learned. Because of public attention focused on the TMI-2 Core Debris Transport Program, the exchange of information between the program and public was extensive. This exchange is a focus for parts of this report to explain why various operations were conducted as they were and why certain technical approaches were employed. And, because of that exchange, the program may have contributed to a better public understanding of such actions and may contribute to planning and execution of similar future actions.

  1. Historical summary of the Three Mile Island Unit 2 core debris transportation campaign

    International Nuclear Information System (INIS)

    Schmitt, R.C.; Tyacke, M.J.; Quinn, G.J.

    1993-03-01

    Transport of the damaged core materials from the Unit 2 reactor of the Three Mile Island Nuclear Power Station (TMI-2) to the Idaho National Engineering Laboratory (INEL) for examination and storage presented many technical and institutional challenges, including assessing the ability to transport the damaged core; removing and packaging core debris in ways suitable for transport; developing a transport package that could both meet Federal regulations and interface with the facilities at TMI-2 and the INEL; and developing a transport plan, support logistics, and public communications channels suited to the task. This report is a historical summary of how the US Department of Energy addressed those challenges and transported, received, and stored the TMI-2 core debris at the INEL. Subjects discussed include preparations for transport, loading at TMI-2, institutional issues, transport operations, receipt and storage at the INEL, governmental inquiries/investigations, and lessons learned. Because of public attention focused on the TMI-2 Core Debris Transport Program, the exchange of information between the program and public was extensive. This exchange is a focus for parts of this report to explain why various operations were conducted as they were and why certain technical approaches were employed. And, because of that exchange, the program may have contributed to a better public understanding of such actions and may contribute to planning and execution of similar future actions

  2. Clarification of TMI action plan requirements. Technical report

    International Nuclear Information System (INIS)

    1980-11-01

    This document, NUREG-0737, is a letter from D.G. Eisenhut, Director of the Division of Licensing, NRR, to licensees of operating power reactors and applicants for operating licenses forwarding post-TMI requirements which have been approved for implementation. Following the accident at Three Mile Island Unit 2, the NRC staff developed the Action Plan, NUREG-0660, to provide a comprehensive and integrated plan to improve safety at power reactors. Specific items from NUREG-0660 have been approved by the Commission for implementation at reactors. In this NRC report, these specific items comprise a single document which includes additional information about schedules, applicability, method of implementation review, submittal dates, and clarification of technical positions. It should be noted that the total set of TMI-related actions have been collected in NUREG-0660, but only those items that the Commission has approved for implementation to date are included in this document, NUREG-0737

  3. Three Mile Island ambient-air-temperature sensor measurements

    International Nuclear Information System (INIS)

    Fryer, M.O.

    1983-01-01

    Data from the ambient-air-temperature sensors in Three Mile Island-Unit 2 (TMI-2) reactor containment building are analyzed. The data were for the period of the hydrogen burn that was part of the TMI-2 accident. From the temperature data, limits are placed on the duration of the hydrogen burn

  4. Lessons learned from the Three Mile Island Unit 2 Advisory Panel

    International Nuclear Information System (INIS)

    Lach, D.; Bolton, P.; Durbin, N.; Harty, R.

    1994-08-01

    In response to public concern about the cleanup of the Three Mile Island, Unit 2 (TMI-2) facility after an accident on March 28, 1979 involving a loss of reactor coolant and subsequent damage to the reactor fuel, twelve citizens were asked to serve on an independent Advisory Panel to consult with the Nuclear Regulatory Commission (NRC) on the decontamination and cleanup of the facility. The panel met 78 times over a period of thirteen years, holding public meetings in the vicinity of TMI-2 and meeting regularly with NRC Commissioners in Washington, DC. This report describes the results of a project designed to identify and describe the lessons learned from the Advisory Panel and place those lessons in the context of what we generally know about citizen advisory groups. A summary of the empirical literature on citizen advisory panels is followed by a brief history of the TMI-2 Advisory Panel. The body of the report contains the analysis of the lessons learned, preliminary conclusions about the effectiveness of the Panel, and implications for the NRC in the use of advisory panels. Data for the report include meeting transcripts and interviews with past and present Panel participants

  5. Examinations of fuel debris samples from Three Mile Island Unit 2

    International Nuclear Information System (INIS)

    Nagase, Fumihisa

    2012-01-01

    In the accident at the Fukushima-Daiichi nuclear power plants, fuels were molten due to loss of coolant and heat-up of the reactor core. Information on properties of molten fuels (debris) is important to analyze progress of the accident, estimate the status inside the damaged reactors and work on a plan for debris removal. Extensive examinations for properties of debris have been conducted after the accident at the Three Mile Island Unit 2 in 1979. The Japan Atomic Energy Agency conducted a part of the examinations in the frame of the OECD/NEA Three Mile Island Vessel Investigation Program. This issue report outline and main results of the TMI-2 debris examination programs. (author)

  6. Criticality safety for TMI-2 canister storage at INEL

    International Nuclear Information System (INIS)

    Jones, R.R.; Briggs, J.B.; Ayers, A.L. Jr.

    1986-01-01

    Canisters containing Three Mile Island Unit 2 (TMI-2) core debris will be researched, stored, and prepared for final disposition at the Idaho National Engineering Laboratory (INEL). The canisters will be placed into storage modules and assembled into a storage rack, which will be located in the Test Area North (TAN) storage pool. Criticality safety calculations were made (a) to ensure that the storage rack is safe for both normal and accident conditions and (b) to determine the effects of degradation of construction materials (Boraflex and polyethylene) on criticality safety

  7. TMI-2 Technical Information and Examination Program. 1982 annual report

    International Nuclear Information System (INIS)

    1983-04-01

    The Department of Energy's Technical Information and Examination Program at Three Mile Island Unit 2 continued the research and development work begun on the island in 1980. The work concentrated in seven major areas: instrumentation and electrical components, radiation and environment, core activities, information and industry coordination, configuration and document control, waste immobilization, and reactor evaluation. The program assists in resolving specific problems at TMI-2 while developing techniques and broadening understanding of accident consequences to improve the overall safety and reliability of nuclear power. The Technical Information and Examination Program aims to communicate applicable information to the nuclear power industry to ensure that the industry can avail itself of the maximum amount of information possible

  8. TMI-2 Technical Information and Examination Program 1983 annual report

    International Nuclear Information System (INIS)

    Scardena, D.E.

    1984-04-01

    The Department of Energy's Technical Information and Examination Program at Three Mile Island Unit 2 continued the research and development work begun on the Island in 1980. The work concentrated in six major areas: waste immobilization, reactor evaluation, data acquisition, information and industry coordination, core activities, and EPICOR II and waste research and disposition. The program assists in resolving specific problems at TMI-2 while developing techniques and broadening understanding of accident consequences to improve the overall safety and reliability of nuclear power. The Technical Information and Examination Program aims to communicate applicable information to the nuclear power industry to ensure that the industry can avail itself to the maximum amount of information possible

  9. US Department of Energy Three Mile Island research and development program: Annual report, 1986

    Energy Technology Data Exchange (ETDEWEB)

    None

    1987-04-01

    Defueling of the Three Mile Island Unit 2 (TMI-2) reactor continued through 1986. This report summarizes this work and other TMI-2 related cleanup, research, and development activities. Other major topics include: core stratification sampling and other data acquisition tasks, the fuel shipping program, waste immobilization and management, decontamination and dose reduction, and future uses and applications of TMI-2 data.

  10. US Department of Energy Three Mile Island research and development program: Annual report, 1986

    International Nuclear Information System (INIS)

    1987-04-01

    Defueling of the Three Mile Island Unit 2 (TMI-2) reactor continued through 1986. This report summarizes this work and other TMI-2 related cleanup, research, and development activities. Other major topics include: core stratification sampling and other data acquisition tasks, the fuel shipping program, waste immobilization and management, decontamination and dose reduction, and future uses and applications of TMI-2 data

  11. The cleanup of Three Mile Island Unit 2: A technical history, 1979--1990

    International Nuclear Information System (INIS)

    Holton, W.C.; Negin, C.A.; Owrutsky, S.L.

    1990-09-01

    The Electric Power Research Institute has sponsored a technical history project to ensure that the logic and consequences of decisions made during the Three Mile Island Unit 2 (TMI-2) cleanup are available for recovery from an accident involving damaged fuel and fission product release. The objectives of the history project are to identify the major questions and challenges facing management; describe the influencing factors and the options available; and present the final decisions and their consequences. This history of decision-making is intended to assist a project manager who must respond to a fuel damage accident, even if the scale is much smaller than TMI-2. The history has focused on decisions related to seven major aspects of the cleanup: cleanup management, postaccident stabilization, personnel protection, data acquisition, radioactive waste management, decontamination, and defueling. A detailed chronology and extensive bibliography accompany the text

  12. US Department of Energy Three Mile Island Research and Development Program: 1987 annual report

    International Nuclear Information System (INIS)

    1988-04-01

    Defueling of the Three Mile Island Unit 2 (TMI-2) reactor continued through 1987. This report summarizes this work and other TMI-2 related cleanup, research, and development activities. Other major topics include: Waste immobilization; Core transportation, receipt, and storage; Abnormal waste; Accident Evaluation and Technical Integration Programs; and Future uses and applications of TMI-2 data. While the technology being developed is of direct benefit to the recovery operations at TMI-2, it will also benefit the entire nuclear power industry

  13. Electrometallurgical treatment of TMI-2 fuel debris

    International Nuclear Information System (INIS)

    Karell, E.J.; Gourishankar, K.V.; Johnson, G.K.

    1997-01-01

    Argonne National Laboratory (ANL) has developed an electrometallurgical treatment process suitable for conditioning DOE oxide spent fuel for long-term storage or disposal. The process consists of an initial oxide reduction step that converts the actinide oxides to a metallic form, followed by an electrochemical separation of uranium from the other fuel constituents. The final product of the process is a uniform set of stable waste forms suitable for long-term storage or disposal. The suitability of the process for treating core debris from the Three Mile Island-2 (TMI-2) reactor is being evaluated. This paper reviews the results of preliminary experimental work performed using simulated TMI-2 fuel debris

  14. TMI-2 RCS activity and solids loading from aggressive defueling techniques

    International Nuclear Information System (INIS)

    Baston, V.F.; Hofstetter, K.J.

    1987-01-01

    One of the tasks performed in support of defueling operations has involved mechanical degradation of resolidified material (core crust layer) utilizing the core drilling equipment. Prior to actual drilling operations, an engineering estimate was made for the anticipated increase in radioactivity and particulate loading to the Three Mile Island Unit 2 (TMI-2) reactor coolant system (RCS). Predictions for RCS activity and particulate loading increases were important to evaluate the cleanup requirements for the defueling water cleanup system to minimize both the dose rates for defueling personnel and water turbidity

  15. Risk perception in an interest group context: an examination of the TMI restart issue

    International Nuclear Information System (INIS)

    Soderstrom, E.J.; Sorensen, J.H.; Copenhaver, E.D.; Carnes, S.A.

    1984-01-01

    Human response to environmental hazards and risks has been the subject of considerable research by social scientists. Work has traditionally focused on either individual response to the risks of an ongoing or future threat (hazards research), or group and organizational response to a specific disaster event (disaster research). As part of a larger investigation of the restart of the Unit 1 reactor at Three Mile Island (TMI), the response of interest groups active in the restart issue to the continued threat of TMI and to future risks due to restart was examined. After reviewing the restart issue in general, the local dimensions of the restart issue from interest group perspectives are discussed. A method for defining appropriate issues at the community level is reviewed. Differences in the perceived local impacts of alternative decisions, and systems of beliefs associated with differing perceptions are discussed. Finally, the implications of interest group versus individual perceptions of local issues for decision making about TMI, in particular, and about technological hazards management, in general, are discussed. Associated implications for determining socially acceptable risk levels are identified

  16. MELCOR analysis of the TMI-2 accident

    International Nuclear Information System (INIS)

    Boucheron, E.A.

    1990-01-01

    This paper describes the analysis of the Three Mile Island-2 (TMI-2) standard problem that was performed with MELCOR. The MELCOR computer code is being developed by Sandia National Laboratories for the Nuclear Regulatory Commission for the purpose of analyzing severe accident in nuclear power plants. The primary role of MELCOR is to provide realistic predictions of severe accident phenomena and the radiological source team. The analysis of the TMI-2 standard problem allowed for comparison of the model predictions in MELCOR to plant data and to the results of more mechanistic analyses. This exercise was, therefore valuable for verifying and assessing the models in the code. The major trends in the TMI-2 accident are reasonably well predicted with MELCOR, even with its simplified modeling. Comparison of the calculated and measured results is presented and, based on this comparison, conclusions can be drawn concerning the applicability of MELCOR to severe accident analysis. 5 refs., 10 figs., 3 tabs

  17. TMI-2 reactor vessel head removal

    International Nuclear Information System (INIS)

    Bengel, P.R.; Smith, M.D.; Estabrook, G.A.

    1985-09-01

    This report describes the safe removal and storage of the Three Mile Island Unit 2 (TMI-2) reactor vessel head. The head was removed in July 1984 to permit the removal of the plenum and the reactor core, which were damaged during the 1979 accident. From July 1982, plans and preparations were made using a standard head removal procedure modified by the necessary precautions and changes to account for conditions caused by the accident. After data acquisition, equipment and structure modifications, and training, the head was safely removed and stored; and the internals indexing fixture and a work platform were installed on top of the vessel. Dose rates during and after the operation were lower than expected; lessons were learned from the operation which will be applied to the continuing fuel removal operations activities

  18. TMI defueling project fuel debris removal system

    International Nuclear Information System (INIS)

    Burdge, B.

    1992-01-01

    The three mile Island Unit 2 (TMI-2) pressurized water reactor loss-of-coolant accident on March 28, 1979, presented the nuclear community with many challenging remediation problems; most importantly, the removal of the fission products within the reactor containment vessel. To meet this removal problem, an air-lift system (ALS) can be used to employ compressed air to produce the motive force for transporting debris. Debris is separated from the transport stream by gravity separation. The entire method does not rely on any moving parts. Full-scale testing of the ALS at the Idaho National Engineering Laboratory (INEL) has demonstrated the capability of transporting fuel debris from beneath the LCSA into a standard fuel debris bucket at a minimum rate of 230 kg/min

  19. NRC plan for cleanup operations at Three Mile Island Unit 2

    International Nuclear Information System (INIS)

    Lo, R.; Snyder, B.J.

    1980-07-01

    The NRC plan defines the functional role of the NRC in cleanup operations at Three Mile Island Unit 2 to assure that agency regulatory responsibilities and objectives will be fulfilled. The plan outlines NRC functions in TMI-2 cleanup operations in the following areas: (1) the functional relationship of NRC to other government agencies, the public, and the licensee to coordinate activities, (2) the functional roles of these organizations in cleanup operations, (3) the NRC review and decision-making procedure for the licensee's proposed cleanup operation, (4) the NRC/licensee estimated schedule of major actions, and (5) NRC's functional role in overseeing implementation of approved licensee activities

  20. Unauthorized forced entry into the protected area at Three Mile Island Unit 1 on February 7, 1993

    International Nuclear Information System (INIS)

    1993-04-01

    On February 7, 1993, at 6:53 a.m. Eastern Standard Time (EST) an intruder drove into tile site owner-controlled area, through a gate into the protected area of Three Mile Island Nuclear Generating Station, Unit I (TMI-1) and crashed through a roll-up door on the Turbine Building. TMI Security reported this event to the US Nuclear Regulatory Commission's (NRC's) Headquarters operations officer and declared a Security Emergency upon determining that the protected area of the plant had been compromised. At 7:23 a.m., the TMI-1 shift supervisor officially notified the NRC Headquarters operations officer that he had declared a Site Area Emergency effective at 7:05 a.m. Upon considering the possible significance to physical security and the regulatory questions that could result from the event, the NRC Executive Director for Operations established an incident investigation team to determine what happened and make appropriate findings and conclusions. In this report the team described the event and the response to the event, evaluated the regulatory requirements, and presented the team's findings and conclusions

  1. Three Mile Island epidemiologic radiation dose assessment revisited: 25 years after the accident.

    Science.gov (United States)

    Field, R William

    2005-01-01

    Over the past 25 years, public health concerns following the Three Mile Island (TMI) accident prompted several epidemiologic investigations in the vicinity of TMI. One of these studies is ongoing. This commentary suggests that the major source of radiation exposure to the population has been ignored as a potential confounding factor or effect modifying factor in previous and ongoing TMI epidemiologic studies that explore whether or not TMI accidental plant radiation releases caused an increase in lung cancer in the community around TMI. The commentary also documents the observation that the counties around TMI have the highest regional radon potential in the United States and concludes that radon progeny exposure should be included as part of the overall radiation dose assessment in future studies of radiation-induced lung cancer resulting from the TMI accident.

  2. Three Mile Island epidemiologic radiation dose assessment revisited: 25 years after the accident

    International Nuclear Information System (INIS)

    Field, R. W.

    2005-01-01

    Over the past 25 years, public health concerns following the Three Mile Island (TMI) accident prompted several epidemiologic investigations in the vicinity of TMI. One of these studies is ongoing. This commentary suggests that the major source of radiation exposure to the population has been ignored as a potential confounding factor or effect modifying factor in previous and ongoing TMI epidemiologic studies that explore whether or not TMI accidental plant radiation releases caused an increase in lung cancer in the community around TMI. The commentary also documents the observation that the counties around TMI have the highest regional radon potential in the United States and concludes that radon progeny exposure should be included as part of the overall radiation dose assessment in future studies of radiation-induced lung cancer resulting from the TMI accident. (authors)

  3. TMI-2 - A Case Study for PWR Instrumentation Performance during a Severe Accident

    Energy Technology Data Exchange (ETDEWEB)

    Joy L. Rempe; Darrell L. Knudson

    2014-05-01

    The accident at the Three Mile Island Unit 2 (TMI-2) reactor provided a unique opportunity to evaluate sensors exposed to severe accident conditions. Conditions associated with the release of coolant and the hydrogen burn that occurred during this accident exposed instrumentation to harsh conditions, including direct radiation, radioactive contamination, and high humidity with elevated temperatures and pressures. As part of a program initiated in 2012 by the Department of Energy Office of Nuclear Energy (DOE-NE), a review was completed to gain insights from prior TMI-2 sensor survivability and data qualification efforts. This new effort focussed upon a set of sensors that provided critical data to TMI-2 operators for assessing the condition of the plant and the effects of mitigating actions taken by these operators. In addition, the effort considered sensors providing data required for subsequent accident simulations. Over 100 references related to instrumentation performance and post-accident evaluations of TMI-2 sensors and measurements were reviewed. Insights gained from this review are summarized within this report. For each sensor, a description is provided with the measured data and conclusions related to the sensor’s survivability, and the basis for conclusions about its survivability. As noted within this document, several techniques were invoked in the TMI-2 post-accident evaluation program to assess sensor status, including comparisons with data from other sensors, analytical calculations, laboratory testing, and comparisons with sensors subjected to similar conditions in large-scale integral tests and with sensors that were similar in design but more easily removed from the TMI-2 plant for evaluations. Conclusions from this review provide important insights related to sensor survivability and enhancement options for improving sensor performance. In addition, this document provides recommendations related to the sensor survivability and data evaluation

  4. TMI-2 - A Case Study for PWR Instrumentation Performance during a Severe Accident

    Energy Technology Data Exchange (ETDEWEB)

    Joy L. Rempe; Darrell L. Knudson

    2013-03-01

    The accident at the Three Mile Island Unit 2 (TMI-2) reactor provided a unique opportunity to evaluate sensors exposed to severe accident conditions. Conditions associated with the release of coolant and the hydrogen burn that occurred during this accident exposed instrumentation to harsh conditions, including direct radiation, radioactive contamination, and high humidity with elevated temperatures and pressures. As part of a program initiated in 2012 by the Department of Energy Office of Nuclear Energy (DOE-NE), a review was completed to gain insights from prior TMI-2 sensor survivability and data qualification efforts. This new effort focussed upon a set of sensors that provided critical data to TMI-2 operators for assessing the condition of the plant and the effects of mitigating actions taken by these operators. In addition, the effort considered sensors providing data required for subsequent accident simulations. Over 100 references related to instrumentation performance and post-accident evaluations of TMI-2 sensors and measurements were reviewed. Insights gained from this review are summarized within this report. For each sensor, a description is provided with the measured data and conclusions related to the sensor’s survivability, and the basis for conclusions about its survivability. As noted within this document, several techniques were invoked in the TMI-2 post-accident evaluation program to assess sensor status, including comparisons with data from other sensors, analytical calculations, laboratory testing, and comparisons with sensors subjected to similar conditions in large-scale integral tests and with sensors that were similar in design but more easily removed from the TMI-2 plant for evaluations. Conclusions from this review provide important insights related to sensor survivability and enhancement options for improving sensor performance. In addition, this document provides recommendations related to the sensor survivability and data evaluation

  5. Data integrity review of Three Mile Island Unit 2. Hydrogen burn data. Volume 3

    International Nuclear Information System (INIS)

    Jacoby, J.K.; Nelson, R.A.; Nalezny, C.L.; Averill, R.H.

    1983-09-01

    About 10 hours after the March 28, 1979 loss-of-coolant accident began at Three Mile Island Unit 2 (TMI-2), a hydrogen burn occurred inside the Reactor Building. This report reviews and presents data from 16 channels of resistance temperature detectors (RTDs), 2 steam generator pressure transmitters, 16 Reactor Building pressure switches, 2 channels of Reactor Building pressure measurements, and measurements of Reactor Building hydrogen, oxygen, and nitrogen concentrations with regard to their usefulness for determining the extent of the burn and the resulting pressure and temperature excursions inside the building

  6. Final programmatic environmental impact statement related to decontamination and disposal of radioactive wastes resulting from March 28, 1979 accident, Three Mile Island Nuclear Station, Unit 2, Docket No. 50-320

    International Nuclear Information System (INIS)

    1981-03-01

    The appendices included in this report include the following: Comments on the Draft Programmatic Environmental Impact Statement (A-1); Commission's Statement of Policy and Notice of Intent to Prepare a Programmatic Environmental Impact Statement (B-1); 'Final Environmental Assessment for Decontamination of the Three Mile Island Unit 2 Reactor Building Atmosphere, Final NRC Staff Report,' US Nuclear Regulatory Commission, NUREG-0662, May 1980 (C-1); 'Environmental Assessment for Use of EPICOR-Il at Three Mile Island Unit 2,' US Nuclear Regulatory Commission, NUREG-0591, October 3, 1979 (D-1); Fish and Fisheries of York Haven Pond and Conowingo Pond of the Susquehanna River and Upper Chesapeake Bay (E1); Reuse of Accident Water (F-1); Engineering Considerations for Treatment of TMI-2 Accident-Generated Liquid Waste G-1); Engineering Considerations Related to Immobilization of Radioactive Wastes (H-1); Justification for Radiation Fields Used in Section 6 I-1); Economic Cost Basis (K-1); Average Individual Quarterly Dose Limits Used in Determinations of Work Force Estimates (L-1); 'Long-Term Environmental Radiation Surveillance Plan for Three Mile Island,' US Environmental Protection Agency, 1981 (M-1); Occupational Radiation Exposure during Onsite Waste Handling (N-1); Decontamination Status of Auxiliary and Fuel Handling Buildings (0-1); Chemical Systems for Decontamination of Primary System Components (P-1); Onsite Storage Facility (Q-1); Proposed Additions to Technical Specifications for TMI-2 Cleanup Program (R-1); Calculations of Discharge of Processed Accident Water to the Atmosphere (S-1); The Behavior of Sorbable Radionuclides in the Susquehanna River and Chesapeake Bay (T-1); Decommissioning of TMI-2 (U-1); Assessment of Groundwater Liquid Pathway from Leakage of Containment Water at Three Mile Island, Unit 2 (V-1); Calculation Models and Parameters Used in Estimating Doses, and Interpretation of Model Results (W-1); Contributors to the PEIS X-1); Scheduled

  7. Lessons learned from Three Mile Island (TMI), USNRC long-term trends, industry response

    International Nuclear Information System (INIS)

    Szalay, R.A.

    1981-01-01

    Studies resulting from Three Mile Island (TMI) showed that corrections were needed in information processing, operator training and procedures, and certain aspects of the safety review process. These have been undertaken by industry and NRC and the results are positive. New safety instructions have been set up. The Nuclear Safety Analysis Center (NSAC) is providing a focus for analysis of issues which have generic elements affecting a number of plants of similar or related design. The Institute of Nuclear Power Operations (INPO) is setting industry standards for training and certification of operators and supervisory personnel, and for training of the managerial chain which oversees safety practices. Changes in procedures and in some design features called for in the recommendations of the NRC Lessons Learned Task Force (NUREG-0578) have been simplemented by utilities. Other requirements included in the NRC Action Plan (NUREG-0660) and its companion document clarification of TMI Action Plan Requirements (NUREG-0737), are also being addressed. Improved operator training and emergency procedures provide a continuing opportunity to make safety gains. Problems remain to be faced in the regulatory and political arenas. The long-term licensing trend will be affected by the manner in which degraded core issues and the development of a safety goal proceed. The Industry Degraded Core Rulemaking (IDCOR) program has been undertaken to develop the nuclear industry's position in anticipation of an impending rulemaking. Both industry and NRC are working on the development of a safety goal and standard risk assessment methodology. (AF)

  8. GPU credit reduced, tie to TMI-1 cheating discounted

    International Nuclear Information System (INIS)

    Utroska, D.

    1981-01-01

    The recent reduction of credit available to General Public Utilities (GPU) Nuclear may be linked to a cheating incident involving two reactor operators at the Three Mile Island-1 (TMI-1) reactor. The incident caused the Nuclear Regulatory Commission to reopen the managerial portion of the restart hearings and may delay the restart. The delay and the lower credit line will worsen GPU's financial position. Banks claim that misgivings about TMI-1 influence them more than the cheating, although GPU had been gradually improving its financial situation since the TMI-2 accident. The new agreement gives GPU $150 million in immediate credit, but lowers the interim ceiling from $292 million to $200 million. A spokesman from the Office of Management and Budget acknowledges that administration plans to limit the federal role to research and development softened under political pressure

  9. Core Activities Program. TMI-2 Core Receipt and Storage Project Plan

    International Nuclear Information System (INIS)

    Ayers, A.L. Jr.

    1984-12-01

    The TMI-2 Core Receipt and Storage Project is funded by the US Department of Energy and managed by the Technical Support Branch of EG and G Idaho, Inc. at the Idaho National Engineering Laboratory (INEL). As part of the Core Activities Program, this project will include: (a) preparations for receipt and storage of the Three Mile Island Unit 2 core debris at INEL; and (b) receipt and storage operations. This document outlines procedures; project management; safety, environment, and quality; safeguards and security; deliverables; and cost and schedule for the receipt and storage activities at INEL

  10. Assessment of damage potential to the TMI-2 lower head due to thermal attack by core debris

    International Nuclear Information System (INIS)

    Cronenberg, A.W.; Behling, S.R.; Broughton, J.M.

    1986-06-01

    Camera inspection of the Three Mile Island Unit 2 (TMI-2) inlet plenum region has shown that approximately 10 to 20 percent of the core material loading may have relocated to the lower plenum. Although vessel integrity was maintained, a question of primary concern is ''how close to vessel failure'' did this accident come. This report summarizes the results of thermal analyses aimed at assessing damage potential to the TMI-2 lower head and attached instrument penetration tubes due to thermal attack by hot core debris. Results indicate that the instrument penetration nozzles could have experienced melt failure at localized hot spot regions, with attendant debris drainage and plugging of the instrument lead tubes. However, only minor direct thermal attack of the vessel liner is predicted

  11. Three Mile Island accident technical support

    International Nuclear Information System (INIS)

    Long, R.L.; Crimmins, T.M.; Lowe, W.W.

    1981-01-01

    A large number of technical support personnel were required to respond to the Three Mile Island Unit 2 (TMI-2) accident of March 28, 1979. Under the leadership of General Public Utilities personnel, onsite (round-the-clock shift) technical support began the evening of March 29 and within a week the TMI Recovery Organization incorporated all of the essential technical capability to implement the Base Plan for Cooldown, manage the radioactive waste problem, and begin the steps toward long-range plant recovery. These steps toward recovery are described in some detail. 1 refs

  12. TMI-2 VIP Metallurgical Program

    International Nuclear Information System (INIS)

    Diercks, D.R.; Neimark, L.A.

    1991-01-01

    The objectives of the TMI-2 VIP Metallurgical Program are to conduct metallurgical examinations and mechanical-property tests on samples of material removed from the lower head of the TMI-2 nuclear reactor in order to deduce the temperatures, determine the mechanical properties, and assess the integrity of the TMI-2 lower head during the loss-of-coolant accident. The TMI-2 Vessel Investigation Project Metallurgical Program is a part of the international TMI-2 Vessel Investigation Project being conducted jointly by the US Nuclear Regulatory Commission and the Organization for Economic Co-operation and Development. Participants in the international project include the US, Japan, the Federal Republic of Germany (FRG), Finland, France, Italy, Spain, Sweden, Switzerland, and the United Kingdom (UK). Fifteen samples have been removed from the lower head and are being examined. Mechanical tests will be conducted on specimens cut from these lower head samples. In addition, archive material from the lower head of the Midland nuclear reactor has been procured for conducting supplemental metallurgical evaluations and mechanical-property determinations. The information obtained from these examinations and tests, supplemented by results obtained from parallel examinations of instrument nozzles, guide tubes, and core debris at Argonne National Laboratory and the Idaho National Engineering Laboratory will be used to deduce a scenario for the loss-of-coolant accident and assess the integrity of the lower head during the accident

  13. A summary of the Three Mile Island accident: from zero hour to lessons for the future

    International Nuclear Information System (INIS)

    Oliveira, L.F.S. de; Oliveira Barroso, A.C. de

    The accident that occured at the Three Mile Island nuclear power plant, unit 2 (TMI-2) in March 1979 is analysed. The main events that occured during the accident are described in detail. The main project features of TMI-2 and Angra-1 nuclear power plant, Brazil are compared and analysed. (L.F.S.) [pt

  14. Lessons learned at TMI: cleanup for respiratory protection

    International Nuclear Information System (INIS)

    Parfitt, B.A.; Gee, E.F.

    1987-01-01

    The March 28, 1979, accident at Three Mile Island Unit 2 (TMI-2) presented GPU Nuclear with technical challenges unprecedented in the nuclear power industry. Among these challenges were a myriad of health physics problems that had to be solved to ensure a radiologically safe environment for workers performing cleanup activities. The application of the as-low-as-reasonably-achievable (ALARA) philosophy has been a fundamental aspects in protecting cleanup workers. The unique conditions produced by the accident, however, have necessitated novel and innovative approaches in making this philosophy effective. The option to use respirators is based on which method will result in the lowest radiation dose to the worker. Inherent to this program has been the training of workers to overcome the perception that any internal contamination is of foremost concern and is orders of magnitude greater in biological effect than an identical external dose. It is, of course, the total dose (internal dose plus external dose) that must be minimized to implement a true ALARA philosophy. The need for considering the total radiation dose when making decisions to use respirators has been clear during the TMI-2 cleanup. Prescribing respirators is not always good for the ALARA concept

  15. Neutron dosimetry in the Three-Mile Island Unit 2 reactor cavity with solid-state track recorders

    International Nuclear Information System (INIS)

    Gold, R.; Roberts, J.H.; Ruddy, F.H.; Preston, C.C.; McElroy, W.N.; Rao, S.V.; Greenborg, J.; Fricke, V.R.

    1986-01-01

    Solid-state track recorder (SSTR) neutron dosimetry has been conducted in the Three-Mile Island Unit 2 (TMI-2) reactor cavity, for nondestructive assessment of the fuel distribution. Two axial stringers were deployed in the annular gap with 17 SSTR dosimeters located on each stringer. SSTR experimental results reveal that neutron streaming, upward from the bottom of the reactor cavity region, dominates the observed neutron intensity. These absolute thermal neutron flux observations are consistent with the presence of a significant amount of fuel debris lying at the bottom of the reactor vessel. A conservative lower bound estimated from these SSTR data implies that at least 2 tonnes of fuel, which is roughly 4 fuel assemblies, is lying at the bottom of the vessel. This existence of significant neutron streaming also explains the high count rate observed with the source range monitors that are located in the TMI-2 reactor cavity. (author)

  16. Solid-state track recorder neutron dosimetry in the Three-Mile Island Unit-2 reactor cavity

    International Nuclear Information System (INIS)

    Gold, R.; Roberts, J.H.; Ruddy, F.H.; Preston, C.C.; McElroy, W.N.

    1985-04-01

    Solid-state track recorder (SSTR) neutron dosimetry has been conducted in the Three-Mile Island Unit (TMI-2) reactor cavity (i.e., the annular gap between the pressure vessel and the biological shield) for nondestructive assessment of the fuel distribution. Two axial stringers were deployed in the annular gap with 17 SSTR dosimeters located on each stringer. SSTR experimental results reveal that neutron streaming, upward from the bottom of the reactor cavity region, dominates the observed neutron intensity. These absolute thermal neutron flux observations are consistent with the presence of a significant amount of fuel debris lying at the bottom of the reactor vessel. A conservative lower bound estimated from these SSTR data implies that there are at least 2 tonnes of fuel, which is roughly 4 fuel assemblies, at the bottom of the vessel. The existence of significant neutron streaming also explains the high count rate observed with the source range monitors (SRMs) that are located in the TMI-2 reactor cavity

  17. Lessons learned from hydrogen generation and burning during the TMI-2 event

    International Nuclear Information System (INIS)

    Henrie, J.O.; Postma, A.K.

    1987-05-01

    This document summarizes what has been learned from generation of hydrogen in the reactor core and the hydrogen burn that occurred in the containment building of the Three Mile Island Unit No. 2 (TMI-2) nuclear power plant on March 28, 1979. During the TMI-2 loss-of-coolant accident (LOCA), a large quantity of hydrogen was generated by a zirconium-water reaction. The hydrogen burn that occurred 9 h and 50 min after the initiation of the TMI-2 accident went essentially unnoticed for the first few days. Even through the burn increased the containment gas temperature and pressure to 1200 0 F (650 0 C) and 29 lb/in 2 (200 kPa) gage, there was no serious threat to the containment building. The processes, rates, and quantities of hydrogen gas generated and removed during and following the LOCA are described in this report. In addition, the methods which were used to define the conditions that existed in the containment building before, during, and after the hydrogen burn are described. The results of data evaluations and engineering calculations are presented to show the pressure and temperature histories of the atmosphere in various containment segments during and after the burn. Material and equipment in reactor containment buildings can be protected from burn damage by the use of relatively simple enclosures or insulation

  18. Characterization of the Three Mile Island Unit-2 reactor building atmosphere prior to the reactor building purge

    International Nuclear Information System (INIS)

    Hartwell, J.K.; Mandler, J.W.; Duce, S.W.; Motes, B.G.

    1981-05-01

    The Three Mile Island Unit-2 reactor building atmosphere was sampled prior to the reactor building purge. Samples of the containment atmosphere were obtained using specialized sampling equipment installed through penetration R-626 at the 358-foot (109-meter) level of the TMI-2 reactor building. The samples were subsequently analyzed for radionuclide concentration and for gaseous molecular components (O 2 , N 2 , etc.) by two independent laboratories at the Idaho National Engineering Laboratory (INEL). The sampling procedures, analysis methods, and results are summarized

  19. Neutron dosimetry in the Three-Mile Island Unit 2 reactor cavity with solid-state track recorders

    International Nuclear Information System (INIS)

    Gold, R.; Roberts, J.H.; Ruddy, F.H.; Preston, C.C.; McElroy, W.N.; Rao, S.V.; Greenborg, J.; Fricke, V.R.

    1985-01-01

    Solid-state track recorder (SSTR) neutron dosimetry has been conducted in the Three-Mile Island Unit 2 (TMI-2) reactor cavity (i.e., the annular gap between the pressure vessel and the biological shield) for nondestructive assessment of the fuel distribution. Two axial stringers were deployed in the annular gap with 17 SSTR dosimeters located on each stringer. SSTR experimental results reveal that neutron streaming, upward from the bottom of the reactor cavity region, dominates the observed neutron intensity. These absolute thermal neutron flux observations are consistent with the presence of a significant amount of fuel debris lying at the bottom of the reactor vessel. A conservative lower bound estimated from these SSTR data implies that at least 2 tonnes of fuel, which is roughly 4 fuel assemblies, is lying at the bottom of the vessel. The existence of significant neutron streaming also explains the high count rate observed with the source range monitors (SRMs) that are located in the TMI-2 reactor cavity

  20. TMI-2 instrument nozzle examinations at Argonne National Laboratory, February 1991--June 1993

    Energy Technology Data Exchange (ETDEWEB)

    Neimark, L.A.; Shearer, T.L.; Purohit, A.; Hins, A.G.

    1994-06-01

    The accident at the Three Mile Island Unit 2 (TMI-2) reactor in March 1979 resulted in the relocation of approximately 19,000 kg of molten core material to the lower head of the reactor vessel. This material caused extensive damage to the instrument guide tubes and nozzles and was suspected of having caused significant metallurgical changes in the condition of the lower head itself. These changes and their effect on the margin-to-failure of the lower head became the focal point of an investigation co-sponsored by the United States Nuclear Regulatory Commission (NRC) and the Organization for Economic Co-operation and Development (OECD). The TMI-2 Vessel Investigation Project (VIP) was formed to determine the metallurgical state of the vessel at the lower head and to assess the margin-to-failure of the vessel under the conditions existing during the accident. This report was prepared under the auspices of the OECD/NEA Three Mile Island Vessel Investigation Project. Under the auspices of the VIP, specimens of the reactor vessel were removed in February 1990 by MPR Associates, Inc. In addition to these specimens, fourteen instrument nozzle segments and two segments of instrument guide tubes were retrieved for metallurgical evaluation. The purpose of this evaluation was to provide additional information on the thermal conditions on the lower head that would influence the margin-to-failure, and to provide insight into the progression of the accident scenario, specifically the movement of the molten fuel across the lower head.

  1. TMI-2 Lessons Learned Task Force. Final report

    International Nuclear Information System (INIS)

    1979-10-01

    In its final report reviewing the Three Mile Island accident, the TMI-2 Lessons Learned Task Force has suggested change in several fundamental aspects of basic safety policy for nuclear power plants. Changes in nuclear power plant design and operations and in the regulatory process are discussed in terms of general goals. The appendix sets forth specific recommendations for reaching these goals

  2. Digital TMI

    Science.gov (United States)

    Rios, Joseph

    2012-01-01

    Presenting the current status of the Digital TMI project to visiting members of the FAA Command Center. Digital TMI is an effort to store national-level traffic management initiatives in a standards-compliant manner. Work is funded by the FAA.

  3. TMI-2 core bore acquisition summary report

    International Nuclear Information System (INIS)

    Tolman, E.L.; Smith, R.P.; Martin, M.R.; McCardell, R.K.; Broughton, J.M.

    1986-09-01

    Core bore samples were obtained from the severely damaged TMI-2 core during July and August, 1986. A description of the TMI-2 core bore drilling unit used to obtain samples; a summary and discussion of the data from the ten core bore segments which were obtained; and the initial results of analysis and evaluation of these data are presented in this report. The impact of the major findings relative to our understanding of the accident scenario is also discussed

  4. The TMI regenerable solid oxide fuel cell

    Science.gov (United States)

    Cable, Thomas L.

    1995-04-01

    Energy storage and production in space requires rugged, reliable hardware which minimizes weight, volume, and maintenance while maximizing power output and usable energy storage. These systems generally consist of photovoltaic solar arrays which operate during sunlight cycles to provide system power and regenerate fuel (hydrogen) via water electrolysis; during dark cycles, hydrogen is converted by the fuel cell into system. The currently preferred configuration uses two separate systems (fuel cell and electrolyzer) in conjunction with photovoltaic cells. Fuel cell/electrolyzer system simplicity, reliability, and power-to-weight and power-to-volume ratios could be greatly improved if both power production (fuel cell) and power storage (electrolysis) functions can be integrated into a single unit. The Technology Management, Inc. (TMI), solid oxide fuel cell-based system offers the opportunity to both integrate fuel cell and electrolyzer functions into one unit and potentially simplify system requirements. Based an the TMI solid oxide fuel cell (SOPC) technology, the TMI integrated fuel cell/electrolyzer utilizes innovative gas storage and operational concepts and operates like a rechargeable 'hydrogen-oxygen battery'. Preliminary research has been completed on improved H2/H2O electrode (SOFC anode/electrolyzer cathode) materials for solid oxide, regenerative fuel cells. Improved H2/H2O electrode materials showed improved cell performance in both fuel cell and electrolysis modes in reversible cell tests. ln reversible fuel cell/electrolyzer mode, regenerative fuel cell efficiencies (ratio of power out (fuel cell mode) to power in (electrolyzer model)) improved from 50 percent (using conventional electrode materials) to over 80 percent. The new materials will allow the TMI SOFC system to operate as both the electrolyzer and fuel cell in a single unit. Preliminary system designs have also been developed which indicate the technical feasibility of using the TMI SOFC

  5. Interim status report of the TMI personnel-dosimetry project

    International Nuclear Information System (INIS)

    Rich, B.L.; Alvarez, J.L.; Adams, S.R.

    1981-06-01

    The current 2-chip TLD personnel dosimeter in use at Three Mile Island (TMI) has been shown inadequate for the anticipated high beta/gamma fields during TMI recovery operations in some areas. This project surveyed the available dosimeter systems, set up an Idaho National Engineering Laboratory (INEL) prototype system, and compared this system with those commercial systems that could be made immediately available for comparison. Of the systems tested, the new INEL personnel dosimeter was found to produce the most accurate results for use in recovery operations at TMI-2. The other multiple-chip or multiple-filter systems were found less desirable at present. The most prominent deficiencies in the INEL dosimeter stem from the fact that it lacks a completely automated reader and its x-ray and thermal neutron responses require additional development. A automated prototype reader system may be in operation by the end of CY-1981. Three alternatives for operational dosimetry are discussed. A combination of a modified version of the presently used Harshaw 2-chip dosimeter and the INEL dosimeter is recommended

  6. Characteristics of severely damaged fuel from PBF tests and the TMI-2 accident

    International Nuclear Information System (INIS)

    Osetek, D.J.; Cook, B.A.; Dallman, R.J.; Broughton, J.M.

    1986-01-01

    As a result of the TMI-2 reactor accident, the US Nuclear Regulatory Commission initiated a research program to investigate phenomena associated with severe fuel damage accidents. This program is sponsored by several countries and includes in-pile and out-of-pile experiments, separate effects studies, and computer code development. The principal in-pile testing portion of the program includes four integral severe fuel damage (SFD) tests in the Power Burst Facility (PBF) at the Idaho National Engineering Laboratory (INEL). The INEL is also responsible for examining the damaged core in the Three Mile Island-Unit 2 (TMI-2) reactor, which offers the unique opportunity to directly compare the findings of an experimental program to those of an actual reactor accident. The principal core damage phenomena which can occur during a severe accident are discussed, and examples from the INEL research programs are used to illustrate the characteristics of these phenomena. The preliminary results of the programs are presented, and their impact on plant operability during severe accidents is discussed

  7. Site dose calculations for the INEEL/TMI-2 storage facility

    International Nuclear Information System (INIS)

    Jones, K.B.

    1997-01-01

    The U.S. Department of Energy (DOE) is licensing an independent spent-fuel storage installation (ISFSI) for the Three Mile Island unit 2 (TMI-2) core debris to be constructed at the Idaho Chemical Processing Plant (ICPP) site at the Idaho National Engineering and Environmental Laboratory (INEEL) using the NUHOMS spent-fuel storage system. This paper describes the site dose calculations, performed in support of the license application, that estimate exposures both on the site and for members of the public. These calculations are unusual for dry-storage facilities in that they must account for effluents from the system in addition to skyshine from the ISFSI. The purpose of the analysis was to demonstrate compliance with the 10 CFR 20 and 10 CFR 72.104 exposure limits

  8. US Department of Energy Three Mile Island research and development program. 1985 annual report

    International Nuclear Information System (INIS)

    Brown, G.R.

    1986-04-01

    In 1985, the US Department of Energy's Three Mile Island Research and Development Program at Three Mile Island Unit 2 (TMI-2), the Idaho National Engineering Laboratory, and other supporting laboratories, concentrated on three major areas: fuel and waste handling and disposition, accident evaluation, and reactor evaluation. While the general technology being developed is of direct benefit to the recovery operations at TMI-2, this technology will be of generic benefit to the entire nuclear power industry. Others engaged in research and development, design, construction, operation, maintenance, and regulation of nuclear plants will have access to this technology to enhance plant safety and reliability

  9. The TMI-2 SNM accountability program

    International Nuclear Information System (INIS)

    Schork, J.S.; Rogan, R.E.; Deininger, F.W.; Weaver, W.W.

    1988-01-01

    This paper describes the Special Nuclear Material (SNM) Accountability Program for Three Mile Isaland Unit 2. The TMI-2 SNM Accountability Program is uniquely designed to inventory and control the SNM borne by the fuel materials that were distributed throughout the Reactor Vessel and connected Reactor Coolant System piping as a result of the March, 1979 accident. The current knowledge of fuel (SNM) quantities and locations as a result of the TMI-2 accident is reviewed. The inventory and control of fuel debris canisters, core debris samples, water process filters, ion exchnagers and radioactive waste that contain SNM is discussed. In addition, the methods and techniques for performing the Post-Defueling Survey of residual SNM quantities at the end of defueling activities are described. The integration of the Waste Management (shipping), Defueling (packaging), Radiological Controls and Data Management and Analysis Departments support is addressed. Finally, the contractual transfer of TMI-2 fuel debris ownership from GPU Nuclear to the Department of Energy is reviewed

  10. TMI-2 core examination plan

    International Nuclear Information System (INIS)

    Owen, D.E.; MacDonald, P.E.; Hobbins, R.R.; Ploggr, S.A.

    1982-01-01

    The Three Mile Island (TMI-2) core examination is divided into four stages: (1) before removing the head; (2) before removing the plenum; (3) during defueling; and (4) offsite examinations. Core examinations recommended during the first three stages are primarily devoted to documenting the post-accident condition of the core. The detailed analysis of core damage structures will be performed during offsite examinations at government and commercial hot cell facilities. The primary objectives of these examinations are to enhance the understanding of the degraded core accident sequence, to develop the technical bases for reactor regulations, and to improve LWR design and operation

  11. Thermal and stress analyses of the reactor pressure vessel lower head of the Three Mile Island Unit 2

    International Nuclear Information System (INIS)

    Hashimoto, K.; Onizawa, K.; Kurihara, R.; Kawasaki, S.; Soda, K.

    1992-01-01

    Thermal and stress analyses were performed using the finite element analysis code ABAQUS to clarify the factors which caused tears in the stainless steel liner of the reactor pressure vessel lower head of the Three Mile Island Unit 2 (TMI-2) reactor pressure vessel during the accident on 28 March 1979. The present analyses covered the events which occurred after approximately 20 tons of molten core material were relocated to the lower head of the reactor pressure vessel. They showed that the tensile stress was highest in the case where the relocated core material consisting of homogeneous UO 2 debris was assumed to attack the lower head and the debris was then quenched. The peak tensile stress was in the vicinity of the welded zone of the penetration nozzle. This result agrees with the findings from the examination of the TMI-2 reactor pressure vessel that major tears in the stainless steel liner were observed around two penetration nozzles of the lower head. (author)

  12. Investigation of hydrogen-burn damage in the Three Mile Island Unit 2 reactor building

    International Nuclear Information System (INIS)

    Alvares, N.J.; Beason, D.G.; Eidem, G.R.

    1982-06-01

    About 10 hours after the March 28, 1979 Loss-of-Coolant Accident began at Three Mile Island Unit 2, a hydrogen deflagration of undetermined extent occurred inside the reactor building. Examinations of photographic evidence, available from the first fifteen entries into the reactor building, yielded preliminary data on the possible extent and range of hydrogen burn damage. These data, although sparse, contributed to development of a possible damage path and to an estimate of the extent of damage to susceptible reactor building items. Further information gathered from analysis of additional photographs and samples can provide the means for estimating hydrogen source and production rate data crucial to developing a complete understanding of the TMI-2 hydrogen deflagration. 34 figures

  13. The Three Mile Island crisis

    International Nuclear Information System (INIS)

    Houts, P.S.; Cleary, P.D.; Hu, T.W.

    1988-01-01

    Since the March 1979 accident at the Three Mile Island (TMI) nuclear power plant, many studies have assessed its impacts. Compiled and summarized in this book are the results of five related surveys, all aimed at the scientific assessment of the psycho-socio-economic behavior of the residents around the TMI facility. These studies are based on a randomly selected, large sample of the population (with telephones) around TMI

  14. Three Mile Island accident

    International Nuclear Information System (INIS)

    Barre, B.; Olivier, E.; Roux, J.P.; Pelle, P.

    2010-01-01

    Deluded by equivocal instrumentation signals, operators at TMI-2 (Three Mile Island - unit 2) misunderstood what was going on in the reactor and for 2 hours were taking inadequate decisions that turned a reactor incident into a major nuclear event that led to the melting of about one third of the core. The TMI accident had worldwide impacts in the domain of nuclear safety. The main consequences in France were: 1) the introduction of the major accident approach and the reinforcement of crisis management; 2) the improvement of the reactor design, particularly that of the pressurizer valves; 3) the implementation of safety probabilistic studies; 4) a better taking into account of the feedback experience in reactor operations; and 5) a better taking into account of the humane factor in reactor safety. (A.C.)

  15. Evaluation of the Three Mile Island accident in the context of WASH-1400

    International Nuclear Information System (INIS)

    Burns, R.D. III.

    1980-01-01

    The accident at unit 2 of the Three Mile Island nuclear station (TMI-2) on March 28, 1979, occurred after approximately 400 reactor years (RY) of commercial nuclear reactor operation in the US. The purpose of work summarized here was to evaluate the probability statements in the WASH-1400 reactor safety study (RSS) in view of the TMI-2 event and to estimate the likely public impact of TMI-2. The RSS probability estimate for such a release was found to be consistent with the fact that the TMI-2 accident occurred. The expected health effects are consistent with those for a low-level category of radioactivity release as described in the RSS and they are immeasurably small. However, the public perception of the health effects of the release is likely to be much more severe than the estimated health effects

  16. Estimates of durability of TMI-2 core debris canisters and cask liners

    International Nuclear Information System (INIS)

    Johnson, A.B. Jr.; Lund, A.L.; Pednekar, S.P.

    1994-04-01

    Core debris from the Three Mile Island-2 (TMI-2) reactor is currently stored in stainless steel canisters. The need to maintain the integrity of the TMI-2 core debris containers through the period of extended storage and possibly into disposal prompted this assessment. In the assessment, corrosion-induced degradation was estimated for two materials: type 304L stainless steel (SS) canisters that contain the core debris, and type 1020 carbon steel (CS) liners in the concrete casks planned for containing the canisters from 2000 AD until the TMI-2 core debris is placed in a repository. Three environments were considered: air-saturated water (with 2 ppM Cl - ) at 20 degree C, and air at 20 degree C with two relative humidities (RHs), 10 and 40%. Corrosion mechanisms assessed included general corrosion (failure criterion: 50% loss of wall thickness) and localized attack (failure criterion: through-wall pinhole penetration). Estimation of carbon steel corrosion after 50 y also was requested

  17. Who pays the costs of industrial accidents like Three Mile Island

    International Nuclear Information System (INIS)

    Doub, W.O.; Shoemaker, J.R.

    1985-01-01

    The accident at Three Mile Island (TMI) nuclear unit 2 generating plant in Pennsylvania provides a case study on how losses resulting from large industrial accidents are allocated in society. TMI demonstrated that industry regulation, no matter how pervasive, can fail to prevent social harm, and that there are often costs beyond personal injuries and property damage. Although the Price-Anderson Act compensated the public, other insurance was inadequate to cover the losses of shareholders and ratepayers. When the $300 million property insurance proved inadequate, the industry raised property damage insurance to $1 billion and replacement power insurance to $250 million

  18. Simulation of the Three Mile Island transient in Semiscale

    International Nuclear Information System (INIS)

    Larson, T.K.; Loomis, G.G.; Shumway, R.W.

    1979-07-01

    This report presents the results of a preliminary review and analysis of the data obtained from eight simulations of the Three Mile Island Unit 2 Nuclear Power Generating Station transient (March 28, 1979) that have been conducted in the Semiscale Mod-3 System. The Semiscale simulations of the Three Mile Island (TMI) transient were basically conducted from the same sequence of events as those recorded in the plant. System initial conditions representative of those in the TMI system were established and the transient was initiated by terminating steam generator feedwater and steam valve flow. The steam generator secondaries were drained to control primary to secondary heat transfer. The pressurizer power operated relief valve, pressurizer code safety valve, and core power trip were operated on system pressure. High pressure safety injection was activated for about one minute during the Semiscale simulations. In addition, both primary loop coolant pumps were shut off in the Semiscale simulation at the same time that the Three Mile Island loop 2A pump was shut off

  19. Calibration of SSTR neutron dosimetry for TMI-2 applications

    International Nuclear Information System (INIS)

    Gold, R.; Ruddy, F.H.; Roberts, J.H.; Preston, C.C.; Ulseth, J.A.; McElroy, W.N.; Leitz, F.J.; Hayward, B.R.; Schmittroth, F.A.

    1982-01-01

    Application of neutron dosimetry for assessment of fuel distribution throughout the Three Mile Island-2 (TMI-2) reactor-core region and the primary-coolant system is advanced. Neutron dosimetry in the reactor cavity, i.e. the cavity between the pressure vessel and the biological shield, could provide data for the assessment of the core fuel distribution. A more immediate task entails locating and quantifying the amount of fuel debris in the ex-core primary coolant system; in the range of 1 to 1000 kg. Solid-state track-recorder (SSTR) neutron dosimetry is considered for such exploratory scoping experiments at TMI-2. The sensitivity of mica- 235 U (asymptotically thick) SSTR has been ascertained for such environments. It has been demonstrated that the SSTR method has adequate sensitivity to properly respond and detect fuel quantities of the order of 1 kg in the ex-core primary coolant system. 21 figures

  20. Situation at TMI unit 2 after the accident of March 28, 1979. Radiation protection aspects

    International Nuclear Information System (INIS)

    Chevalier, C.

    1983-01-01

    After a brief flashback on the chronology of the accident that occurred on TMI unit 2, the author, who took part in the first operations of diagnosis on the spot, gives an outlook of the situation at the end of 1981. The damages are considerable, and, in spite of the progression of decontamination works, the obstacles, mainly administrative and financial, do not allow, four years after the event, to give a serious forecast on the repairing of the damaged reactor [fr

  1. TMI-2 [Three Mile Island] fission product inventory program: FY-85 status report

    International Nuclear Information System (INIS)

    Langer, S.; Croney, S.T.; Akers, D.W.; Russell, M.L.

    1986-11-01

    This report presents the status of the TMI-2 fission product inventory program through May 1985. The fission product inventory program is an assessment of the location of fission products distributed in the plant as a result of the TMI-2 accident. Included in this report are principal results of samples from the reactor building where most of the mobile fission products (i.e., radiocesium and iodine) are expected to be found. The data are now complete enough for most reactor components; therefore, it is possible to direct the balance of the examination and sampling program to areas and components where it is likely to be most productive. Those areas are the reactor core and the reactor building basement, with emphasis on the currently unsampled portions of the core

  2. TMI-1 restart: an evaluation of the licensee's management integrity as it affects restart of Three Mile Island Nuclear Station (Unit 1 Docket 50-289). Supplement 5

    International Nuclear Information System (INIS)

    1984-07-01

    Supplement 5 to the Safety Evaluation Report (SER) on TMI-1 Restart documents the review by the Nuclear Regulatory Commission (NRC) staff of nine investigations conducted by the NRC Office of Investigations into matters identified as relevant and material to an evaluation of the licensee's management integrity. The staff has included, as part of its evaluation, materials from its review of the GPU v. B and W lawsuit record (NUREG-1020LD, GPU, v. B and W Lawsuit Review and Its Effect on TMI-1) as well as other relevant materials developed since the close of the record in the TMI-1 Restart proceeding. In developing its position on General Public Utilities Nuclear Corporation's character (i.e., management integrity), the staff evaluated matters that cast doubt on the licensee's character, individually and collectively; considered the remedial actions taken by the licensee; and balanced past improper conduct of the licensee against its subsequent record of remedial actions and performance and record of current senior management of the licensee. The staff concluded that, while the past improper conduct was grave, the remedial actions taken, the subsequent record of performance, and the record of current senior management support a finding that GPUN can and will operate TMI-1 without undue risk to the health and safety of the public

  3. Detailed analysis of the TMI-2 accident scenario by using MARS/SCDAP

    International Nuclear Information System (INIS)

    Park, Rae Joon; Lee, Young Jin; Chung, Bub Dong

    2009-01-01

    As part of a benchmark analysis, the Three Mile Island Unit 2 (TMI-2) accident has been analyzed by using the MARS/SCDAP computer code. This analysis has been performed to estimate the efficiency of the MARS/SCDAP computer code and the predictive qualities of its models from an initiating event to a severe accident. The MARS/SCDAP results have shown that a reduction feed water to the steam generator caused the coolant to expand and initially increased the reactor coolant system (RCS) pressure. The pilot-operated relief valve (PORV) opened when the pressure reached 15.7 MPa, with a reactor scram occurring when the pressure reached 16.3 MPa. The PORV failed to close as the RCS pressure decreased, initiating a small break loss of coolant accident. The emergency core cooling was reduced by operators who thought that the pressurizer liquid level indicated a nearly full RCS, while coolant continued to be lost from the PORV. After an initial decrease in the RCS pressure, the pressurizer pressure remained at approximately 7 MPa. After a pump termination at 6,000 seconds, the liquid level in the reactor vessel decreased, which resulted in a core uncovery. Continued core degradation with a coolant boiling caused the pressurizer pressure to increase. The MARS/SCDAP results are very similar to the TMI-2 data

  4. Three-Mile Island Program

    International Nuclear Information System (INIS)

    Malinauskas, A.P.

    1983-01-01

    Activities associated with the Three-Mile Island (TMI) Program were of two types. One involved providing technical review and guidance for specific recovery efforts at TMI, whereas the second was concerned more directly with providing technical assistance to recovery operations through detailed analyses and experimental activities. The work was divided into four elements: Task I - coordination of and participation in the operation of the Technical Advisory Group (TAG) for the cleanup of aqueous streams at TMI; Task II - participation in the Technical Assistance and Advisory Group (TAAG) on TMI operations; Task III - chemical development and other technical support to TMI recovery operations; and Task IV - development of inorganic sorbents for the decontamination of aqueous streams. At the program review that was conducted approximately mid-fiscal year, it was decided to curtail the Task IV activities in favor of studies of more-urgent problems. Technical progress for each of the tasks of this program is presented

  5. Drop tests of the Three Mile Island knockout canister

    International Nuclear Information System (INIS)

    Box, W.D.; Aaron, W.S.; Shappert, L.B.; Childress, P.C.; Quinn, G.J.; Smith, J.V.

    1987-01-01

    A type of Three Mile Island Unit 2 (TMI-2) defueling canister, called a ''knockout'' canister, was subjected to a series of drop tests at the Oak Ridge National Laboratory's Drop Test Facility. These tests confirmed the structural integrity of internal fixed neutron poisons in support of a request for NRC licensing of this type of canister for the shipment of TMI-2 reactor fuel debris to the Idaho National Engineering Laboratory (INEL) for the Core Examination R and D Program. This report presents the data generated and the results obtained from a series of four drop tests that included two drops with the test assembly in the vertical position and two drops with the assembly in the horizontal position

  6. Evaluation of the Three Mile Island Unit 2 reactor building decontamination process

    Energy Technology Data Exchange (ETDEWEB)

    Dougherty, D.; Adams, J. W.

    1983-08-01

    Decontamination activities from the cleanup of the Three Mile Island Unit 2 Reactor Building are generating a variety of waste streams. Solid wastes being disposed of in commercial shallow land burial include trash and rubbish, ion-exchange resins (Epicor-II) and strippable coatings. The radwaste streams arising from cleanup activities currently under way are characterized and classified under the waste classification scheme of 10 CFR Part 61. It appears that much of the Epicor-II ion-exchange resin being disposed of in commerical land burial will be Class B and require stabilization if current radionuclide loading practices continue to be followed. Some of the trash and rubbish from the cleanup of the reactor building so far would be Class B. Strippable coatings being used at TMI-2 were tested for leachability of radionuclides and chelating agents, thermal stability, radiation stability, stability under immersion and biodegradability. Actual coating samples from reactor building decontamination testing were evaluated for radionuclide leaching and biodegradation.

  7. Evaluation of the Three Mile Island Unit 2 reactor building decontamination process

    International Nuclear Information System (INIS)

    Dougherty, D.; Adams, J.W.

    1983-08-01

    Decontamination activities from the cleanup of the Three Mile Island Unit 2 Reactor Building are generating a variety of waste streams. Solid wastes being disposed of in commercial shallow land burial include trash and rubbish, ion-exchange resins (Epicor-II) and strippable coatings. The radwaste streams arising from cleanup activities currently under way are characterized and classified under the waste classification scheme of 10 CFR Part 61. It appears that much of the Epicor-II ion-exchange resin being disposed of in commerical land burial will be Class B and require stabilization if current radionuclide loading practices continue to be followed. Some of the trash and rubbish from the cleanup of the reactor building so far would be Class B. Strippable coatings being used at TMI-2 were tested for leachability of radionuclides and chelating agents, thermal stability, radiation stability, stability under immersion and biodegradability. Actual coating samples from reactor building decontamination testing were evaluated for radionuclide leaching and biodegradation

  8. Three Mile Island technical information and examination program instrumentation and electrical summary report

    International Nuclear Information System (INIS)

    Meininger, R.D.

    1985-07-01

    This report summarizes the investigations on instrumentation and electrical systems that were subjected to a loss-of-coolant accident environment during and following the accident at Three Mile Island Unit-2 (TMI-2) on March 28, 1979. The report is a summary of information previously published in GEND-INF reports, plus current knowledge of the investigators

  9. Evaluation of nuclear facility decommissioning projects. Three Mile Island Unit 2 reactor building decontamination. Summary status report. Volume 2

    International Nuclear Information System (INIS)

    Doerge, D.H.; Miller, R.L.; Scotti, K.S.

    1986-05-01

    This document summarizes information relating to decontamination of the Three Mile Island Unit 2 (TMI-2) reactor building. The report covers activities for the period of June 1, 1979 through March 29, 1985. The data collected from activity reports, reactor containment entry records, and other sources were entered into a computerized data system which permits extraction/manipulation of specific information which can be used in planning for recovery from an accident similar to that experienced at TMI-2 on March 28, 1979. This report contains summaries of man-hours, manpower, and radiation exposures incurred during decontamination of the reactor building. Support activities conducted outside of radiation areas are excluded from the scope of this report. Computerized reports included in this document are: a chronological summary listing work performed relating to reactor building decontamination for the period specified; and summary reports for each major task during the period. Each task summary is listed in chronological order for zone entry and subtotaled for the number of personnel entries, exposures, and man-hours. Manually-assembled table summaries are included for: labor and exposures by department and labor and exposures by major activity

  10. Thermal hydraulic features of the TMI accident

    International Nuclear Information System (INIS)

    Tolman, B.

    1985-01-01

    The TMI-2 accident resulted in extensive core damage and recent data confirms that the reactor vessel was challenged from molten core materials. A hypothesized TMI accident sencario is presented that consistently explains the TMI data and is also consistent with research findings from independent severe fuel damage experiements. The TMI data will prove useful in confirming our understanding of severe core damage accidents under realistic reactor systems conditions. This understanding will aid in addressing safety and regulatory issues related to severe core damage accidents in light water reactors

  11. Post-accident cleanup of radioactivity at the Three Mile Island Nuclear Power Station

    International Nuclear Information System (INIS)

    Brooksbank, R.E.; Armento, W.J.

    1980-02-01

    The technical staff of the President's Commission on the Accident at Three Mile Island (TMI) requested that Oak Ridge National Laboratory (ORNL) prepare documentation concerned with the cleanup of radioactivity on the Three Mile Island site following the March 28, 1979 accident. The objective of this report is to provide information in a summarized form, which will be of direct usefulness to the commissioners. The information contained herein includes discussion of on-site assistance and accomplishments following the accident, flowsheet development for the TMI recovery team (by the Technical Advisory Group), and the numerous reports already generated on the TMI cleanup and recovery

  12. Transporting TMI-2 [Three Mile Island Unit 2] core debris to INEL: Public safety and public response

    International Nuclear Information System (INIS)

    Schmitt, R.C.; Reno, H.W.; Young, W.R.; Hamric, J.P.

    1987-01-01

    This paper describes the approach taken by the US Department of Energy (DOE) to ensure that public safety is maintained during transport of core debris from the Unit-2 reactor at the Three Mile Island Nuclear Power Station near Harrisburg, PA, to the Idaho National Engineering Laboratory near Idaho Falls, ID. It provides up-to-date information about public response to the transport action and discusses DOE's position on several institutional issues. The authors advise that planners of future transport operations be prepared for a multitude of comments from all levels of federal, state, and local governments, special interest groups, and private citizens. They also advise planners to keep meticulous records concerning all informational transactions

  13. Evaluation of zeolite mixtures for decontamination of high-activity-level water in the Submerged Demineralizer System (SDS) flowsheet at the Three Mile Island Nuclear Power Station, Unit 2

    International Nuclear Information System (INIS)

    King, L.J.; Campbell, D.O.; Collins, E.D.; Knauer, J.B.; Wallace, R.M.

    1983-01-01

    Mixtures of Linde Ionsiv IE-96 and Ionsiv A-51 zeolites were evaluated for use in the Submerged Demineralizer System (SDS) that was installed at the Three Mile Island Nuclear Power Station, Unit 2 (TMI-2) for decontaminating approx. 3000 m 3 (approx. 700,000 gal) of high-activity-level water in the containment building sump. Small-scale, tracer-level column tests were made using various mixtures of the zeolites to evaluate the capability for simultaneous removal of cesium and strontium. A column loading test was made in a hot cell using a mixture of equal parts of the zeolites to evaluate the performance of the mixture in removing cesium and strontium from a sample of TMI-2 sump water. A computerized mathematical model of the mixed-bed SDS system was used to evaluate the test data in order to select a zeolite mixture and predict system performance

  14. Evaluation of nuclear facility decommissioning projects. Three Mile Island Unit 2 reactor defueling and disassembly. Summary status report. Volume 3

    International Nuclear Information System (INIS)

    Doerge, D.H.; Miller, R.L.; Scotti, K.S.

    1986-05-01

    This document summarizes information relating to the preparations for defueling the Three Mile Island Unit 2 (TMI-2) reactor and disassembly activities being performed concurrently with decontamination of the facility. Data have been collected from activity reports, reactor containment entry records, and other sources and entered in a computerized data sysem which permits extraction/manipulation of specific data which can be used in planning for recovery from a loss of coolant event similar to that experienced at TMI-2 on March 28, 1979. This report contains summaries of man-hours, manpower, and radiation exposures incurred during the period of April 23, 1979 to April 16, 1985, in the completion of activities related to preparation for reactor defueling. Support activities conducted outside of radiation areas are not included within the scope of this report. Computerized reports included in this document are: A chronological summary listing work performed for the period; and summary reports for each major task undertaken in connection with the specific scope of this report. Presented in chronological order for the referenced time period. Manually-assembled table summaries are included for: Labor and exposures by department; and labor and exposures by major activity

  15. Three Mile Island zeolite vitirification demonstration program

    International Nuclear Information System (INIS)

    Siemens, D.H.; Knowlton, D.E.; Shupe, M.W.

    1981-06-01

    The cleanup of the high-activity-level water at Three Mile Island (TMI) provides an opportunity to further develop waste management technology. Approximately 790,000 gallons of high-activity-level water at TMI's Unit-2 Nuclear Power Station will be decontaminated at the site using the submerged demineralizer system (SDS). In the SDS process, the cesium and strontium in the water are sorbed onto zeolite that is contained within metal liners. The Department of Energy has asked the Pacific Northwest Laboratory (PNL) to take a portion of the zeolite from the SDS process and demonstrate, on a production scale, that this zeolite can be vitrified using the in-can melting process. This paper is a brief overview of the TMI zeolite vitrification program. The first section discusses the formulation of a glass suitable for immobilizing SDS zeolite. The following section describes a feed system that was developed to feed zeolite to the in-can melter. It also describes the in-can melting process and the government owned facilities in which the demonstrations will take place. Finally, the schedule for completing the program activities is outlined

  16. TMI-2 lessons have been learned

    International Nuclear Information System (INIS)

    Long, R.L.

    1994-01-01

    This paper is an introduction to the more detailed papers which are presented in this session titled ''Advanced Light Water Reactors -- 15 Years After TMI.'' Many of the advances in the design, operation and maintenance of nuclear power plants are the direct result of applying lessons learned from the 1979 TMI-2 accident. The authors believe the ''reality awakening'' which occurred following the accident should never be forgotten. Thus, this paper briefly reviews the TMI-2 accident and identifies the broad lessons learned following the accident. Then it describes briefly some indicators which show the very impressive improvements in nuclear power plant performance that have occurred over the past 10-15 years. This sets the stage for Dr. Ransom's paper which shows the continuing need for nuclear power, Dr. Beckjord's paper which describes the ''final'' TMI-2 research project and the subsequent papers which focus on advanced light water reactor developments

  17. Local Coverage of Three Mile Island during 1981-82.

    Science.gov (United States)

    Friedman, Sharon M.

    Local newspaper coverage of the Three Mile Island (TMI) nuclear power plant accident was examined in a study to determine what changes, if any, were made by local media and what lessons they had learned from it. Data were collected through interviews with 21 media representatives. TMI coverage in the six newspapers was examined using each…

  18. Decontamination barrier on TMI-2 leadscrew

    International Nuclear Information System (INIS)

    Baston, V.F.; Hofstetter, K.J.; Bain, G.M.; Haynerg, G.O.

    1985-01-01

    The first major component removed from the TMI-2 Reactor Vessel that has had extensive analytical examination (i.e. radiochemical, metallography, surface chemical analyses, etc.) is the H-8 leadscrew. These analyses indicate adherent cesium activity that is important to the decontamination efforts for TMI-2

  19. Post TMI-2 view on the responsibilities of nuclear engineering educators

    International Nuclear Information System (INIS)

    Long, R.L.

    1980-01-01

    The Three Mile Island (TMI) accident of March 28, 1979 was the result of a complex set of interactions involving design deficiencies, equipment failure and human error. Nuclear engineering educators may need to accept responsibility for some of the underlying, industry-wide causes leading to the event. The many detailed investigations and recommendations following the accident are certain to have a significant impact on nuclear engineering education. Areas of impact include changes in curricula, increased demand for graduates, heavier involvement in utility staff training and education, and new approaches to university, industry, and societal interactions

  20. Chronic Stress and Three Mile Island: Toxic Exposure and Uncertainty.

    Science.gov (United States)

    Davidson, Laura M.; And Others

    Although many researchers expected the psychological effects of the accident at the Three Mile Island (TMI) nuclear plant to be short-lived, area residents continued to show elevated levels of stress. To examine stress levels of TMI residents 28 months after the accident, 141 subjects were chosen from nearby areas, and from a town 80 miles away.…

  1. Electric-utility returns and risk in the light of Three Mile Island

    International Nuclear Information System (INIS)

    Brooks, L.D.; D'Souza, R.E.

    1982-01-01

    The impact of the Three Mile Island nuclear-generating-unit failure on the performance of nuclear-dependent electric utilities is examined in this article. A comparative examination of the time series of abnormal returns and risk measures on nuclear-dependent utilities and nondependent utilities prior to the TMI incident, at the time of the incident, and subsequent to it was performed by the authors. The results are consistent with a hypothesis that investors associate a decline in future profitability or increased risk with nuclear-associated utilities. However, the more-objective measures indicate a clear reduction in risk for nuclear-associated utilities since the TMI incident, both in relation to the market as a whole and in relation to electric utilities which are not nuclear-associated. 4 references, 1 figure, 3 tables

  2. Accountability study for TMI-2 fuel

    International Nuclear Information System (INIS)

    Goris, P.; Scott, D.D.

    1981-05-01

    The TMI-2 accountability study considers problems of identifying, measuring, and accounting for TMI-2 fuel in the resident condition, as it is removed from the reactor, during subsequent cleanup, and during post-removal examinations. The goal is to identify methods and procedures which will provide a verifiable material balance equating to the pre-accident balance

  3. Utilization of medical care following the Three Mile Island crisis

    International Nuclear Information System (INIS)

    Houts, P.S.; Hu, T.W.; Henderson, R.A.; Cleary, P.D.; Tokuhata, G.

    1984-01-01

    Four studies are reported on how utilization of primary health care was affected by the Three Mile Island (TMI) crisis and subsequent distress experienced by persons living in the vicinity of the plant. The studies concerned: 1) Blue Cross-Blue Shield records of claims by primary care physicians in the vicinity of TMI; 2) utilization rates in a family practice located near the facility; 3) interviews with persons living within five miles of TMI following the crisis; and 4) responses to a questionnaire by primary care physicians practicing within 25 miles of TMI. All four studies indicated only slight increases in utilization rates during the year following the crisis. One study found that persons who were upset during the crisis tended to be high practice utilizers both before and after the crisis. These results suggest that, while patterns of physician utilization prior to the TMI crisis predicted emotional response during the crisis, the impact of the TMI crisis on subsequent physician utilization was small

  4. Utilization of medical care following the Three Mile Island crisis.

    Science.gov (United States)

    Houts, P S; Hu, T W; Henderson, R A; Cleary, P D; Tokuhata, G

    1984-02-01

    Four studies are reported on how utilization of primary health care was affected by the Three Mile Island (TMI) crisis and subsequent distress experienced by persons living in the vicinity of the plant. The studies concerned: 1) Blue Cross-Blue Shield records of claims by primary care physicians in the vicinity of TMI; 2) utilization rates in a family practice located near the facility; 3) interviews with persons living within five miles of TMI following the crisis; and 4) responses to a questionnaire by primary care physicians practicing within 25 miles of TMI. All four studies indicated only slight increases in utilization rates during the year following the crisis. One study found that persons who were upset during the crisis tended to be high practice utilizers both before and after the crisis. These results suggest that, while patterns of physician utilization prior to the TMI crisis predicted emotional response during the crisis, the impact of the TMI crisis on subsequent physician utilization was small.

  5. TMI-2 Vessel Investigation Project (VIP) Metallurgical Program

    International Nuclear Information System (INIS)

    Diercks, D.R.; Neimark, L.A.

    1990-06-01

    The TMI-2 Vessel Investigation Project (VIP) Metallurgical Program is a part of the international TMI-2 Vessel Investigation Project being conducting jointly by the US Nuclear Regulatory Commission and the Organization for Economic Co-operation and Development (OECD). The overall project consists of three phases, namely (1) recovery of material samples from the lower head of the TMI-2 reactor, (2) examination and analysis of the lower head samples and the preparation and testing of archive material subjected to a similar thermal history, and (3) procurement, examination, and analysis of companion core material located adjacent to or near the lower head material. The specific objectives of the ANL Metallurgical Program, which comprises a major portion of Phase 2, are to prepare metallographic and mechanical test specimen blanks from the TMI-2 lower head material, prepare similar test specimen blanks from suitable archive material subjected to the appropriate thermal processing, determine the mechanical properties of the lower vessel head and archive materials under the conditions of the core-melt accident, and assess the lower head integrity and margin-to-failure during the accident. The ANL work consists of three tasks: (1) archive materials program, (2) fabrication of metallurgical and mechanical test specimens from the TMI-2 pressure vessel samples, and (3) mechanical property characterization of TMI-2 lower pressure vessel head and archive material

  6. Lessons learned? Selected public acceptance case studies since Three Mile Island

    Energy Technology Data Exchange (ETDEWEB)

    Blee, D. [NAC International, Atlanta Corporate Headquarters, Atlanta, GA (United States)

    2001-02-01

    This paper will present an overview of the present situation, some recent polling survey information, and then look at lessons learned in terms of selected case studies and some global issues over the 22 years since the Three Mile Island (TMI) accident. That is quite an ambitious topic but there are some important lessons we can learn from the post-TMI era. (author)

  7. Changes in uranium plant community leaders' attitudes toward nuclear power: before and after TMI

    International Nuclear Information System (INIS)

    Winfield-Laird, I.; Hastings, M.; Cawley, M.E.

    1982-01-01

    The results of an investigation of the reactions of community leaders in nuclear power plant host communities toward nuclear power following the accident at Three Mile Island (TMI) are reported. Public and private sector officials were surveyed in ten general areas covering their attitudes toward and the continued use of nuclear power as compared to other fuel types, and the reassessment of the local plant impact on different community groups and aspects of community life. Information is compared with findings from a similar study conducted with the same community leaders prior to the TMI accident. The results indicate that community leaders' attitudes remained highly favorable toward the continued use of nuclear power. Three-fourths of the sample indicated that they would probably or definitely allow the continued use of nuclear power as compared to other fuel types, and the reassessment of the local majority still view the plant presence as having a positive impact on their communities. (author)

  8. TMI-2 core debris analysis

    International Nuclear Information System (INIS)

    Cook, B.A.; Carlson, E.R.

    1985-01-01

    One of the ongoing examination tasks for the damaged TMI-2 reactor is analysis of samples of debris obtained from the debris bed presently at the top of the core. This paper summarizes the results reported in the TMI-2 Core Debris Grab Sample Examination and Analysis Report, which will be available early in 1986. The sampling and analysis procedures are presented, and information is provided on the key results as they relate to the present core condition, peak temperatures during the transient, temperature history, chemical interactions, and core relocation. The results are then summarized

  9. Radiation and health effects. A report on the TMI-2 accident and related health studies

    International Nuclear Information System (INIS)

    1986-08-01

    On March 28, 1979, the Unit 2 reactor at the Three Mile Island (TMI) Nuclear Station was severely damaged by an accident. Radioactivity was discharged to the environment resulting in a small amount of radiation exposure to the public. Continuing concerns by some members of the communities around TMI about the potential radiation-induced health effects prompted GPU Nuclear Corporation to examine the information gathered from the accident investigation in the context of our current knowledge of radiation and its effects on human health. Although this report deals with technical matters, the information is presented in a manner that can be understood by those who do not have scientific backgrounds. This report is divided into three major sections. The first section provides an overview of the past 80 years of relevant research on the subject of radiation and its effects on human health. During that time, scientists and physicians throughout the world have studied hundreds of thousands of individuals exposed to radiation from medical and occupational sources and from nuclear weapons explosions. Epidemiologic studies of humans, such as the Japanese survivors of the atomic bomb, have established that following exposure to large doses of radiation, certain health effects, including cancer, can be observed. Radiation-induced health effects from low doses of radiation, such as those associated with the TMI-2 accident, appear infrequently, if at all, and are identical and, therefore, indistinguishable from similar health effects which occur normally. For example, cancers induced by radiation are indistinguishable from those occurring spontaneously or normally. It is not possible, therefore, for scientists to determine directly whether radiation-induced health effects at low doses occur at all; such observations can only be inferred by statistical methods. The second section of this report provides a brief description of the TMI-2 accident. Most of the radioactivity from the

  10. Impact of the Three Mile Island accident on research and development programs

    International Nuclear Information System (INIS)

    Zammite, R.

    1989-10-01

    The influence of the Three Mile Island (TMI) accident, on the evolution of the nuclear safety engineering concepts, are analyzed. An overview of the nuclear safety studies performed before and after the accident is presented. Before the TMI accident, the research programs were mainly centered on dimensional problems involving factors, such as explosions and earthquakes. The TMI accident demonstrated that the fusion of the reactor's core could actually hoppen. It was also realized that the safety of nuclear power plants depended on accurate research programs, also extended to factors beyond dimensional analysis [fr

  11. Users Manual for TMY3 Data Sets (Revised)

    Energy Technology Data Exchange (ETDEWEB)

    Wilcox, S.; Marion, W.

    2008-05-01

    This users manual describes how to obtain and interpret the data in the Typical Meteorological Year version 3 (TMY3) data sets. These data sets are an update to the TMY2 data released by NREL in 1994.

  12. TMI-2 core boring machine

    International Nuclear Information System (INIS)

    Croft, K.M.; Helbert, H.J.; Laney, W.M.

    1986-01-01

    An important and essential aspect of the TMI-2 defueling effort is to determine what occurred in the core region during the accident. Remote cameras and probes only portray a portion of the overall picture. What lies beneath the rubble bed and solidified sublayer is, as yet, unknown. This paper discusses the TMI-2 Core Boring Machine, which has been developed to drill into the damaged core of the TMI-2 reactor and extract stratified samples of the core. This machine, its unique support structure, positioning and leveling systems, and specially designed drill bits, combine to provide a unique mechanical system. In addition, the machine is controlled by a microprocessor; which actually controls the drilling operation, allowing relatively inexperienced operators to drill the core samples. A data acquisition system is data integral with the controlling system and collects data relative to system conditions and monitored parameters during drilling. Data obtained during the actual drilling operations are collected in a data base which will be used for actual mapping of the core region, identifying materials and stratification levels that are present

  13. Technology transfer at Three Mile Island Unit 2

    International Nuclear Information System (INIS)

    Burton, H.M.; Bixby, W.W.

    1982-01-01

    The Department of Energy (DOE) formulated a program at TMI-2 in concert with the Coordination Agreement. The DOE TME-2 Information and Examination Program (TI and EP) aims to fulfill three general objectives. First, the TI and EP aims to obtain information from the TMI-2 accidient for resolving specific safety and licensing concerns; modifying applicable standards, specifications, and regulations; and defining changes in design, maintenance, operation, and personnel training. Second, the TI and EP uses TMI-2 information to advance technology in decontamination work; radioactive waste immobilization and disposal; system requalification; damaged fuel handling; and plant, reactor, and safety engineering. Finally, the TI and EP distributes the information gained from the Program to others that are engaged in research and development, design, construction, operation, maintenance, and regulation of nuclear power plants

  14. Adrenal cortical response to stress at Three Mile Island.

    Science.gov (United States)

    Schaeffer, M A; Baum, A

    1984-01-01

    The present study examined the relationship between biochemical, psychologic, and behavioral components of chronic stress associated with living near the damaged nuclear power plant at Three Mile Island (TMI). Relative to control subjects, TMI subjects had higher levels of urinary cortisol, which correlated significantly with urinary catecholamines, self-report of physical and mental symptoms, and decrements in task performance. Further, it was found that males had higher urinary cortisol levels than females at TMI, while at the control sites, levels of cortisol were comparable between males and females. Finally, no significant relationship between coping style and urinary cortisol was detected. Levels of stress response among TMI are residents, though significantly greater than control subjects, were within normal ranges and thus should be considered subclinical in intensity. Their persistence over 17 months, however, suggests some cause for concern.

  15. Adrenal cortical response to stress at Three Mile Island

    International Nuclear Information System (INIS)

    Schaeffer, M.A.; Baum, A.

    1984-01-01

    The present study examined the relationship between biochemical, psychologic, and behavioral components of chronic stress associated with living near the damaged nuclear power plant at Three Mile Island (TMI). Relative to control subjects, TMI subjects had higher levels of urinary cortisol, which correlated significantly with urinary catecholamines, self-report of physical and mental symptoms, and decrements in task performance. Further, it was found that males had higher urinary cortisol levels than females at TMI, while at the control sites, levels of cortisol were comparable between males and females. Finally, no significant relationship between coping style and urinary cortisol was detected. Levels of stress response among TMI are residents, though significantly greater than control subjects, were within normal ranges and thus should be considered subclinical in intensity. Their persistence over 17 months, however, suggests some cause for concern

  16. Technical evaluation report, TMI action NUREG-0737 (II.D.1), relief and safety valve testing, Comanche Peak, Unit 2, Docket No. 50-446

    International Nuclear Information System (INIS)

    Fineman, C.P.

    1993-01-01

    In the past, safety and relief valves installed in the primary coolant system of light water reactors have performed improperly. As a result, the authors of NUREG-0578 (TMI-2 Lessons Learned Task Force Status Report and Short-Term Recommendations) and, subsequently, NUREG-0737 (Clarification of TMI Action Plan Requirements) recommended development and completion of programs to do two things. First, the programs should reevaluate the functional performance capabilities of pressurized water reactor safety, relief, and block valves. Second, they should verify the integrity of the pressurizer safety and relief valve piping systems for normal, transient, and accident conditions. This report documents the review of those programs by EG ampersand G Idaho, Inc. Specifically, this report documents the review of the Comanche Peak, Unit 2, Applicant response to the requirement of NUREG-0578 and NUREG-0737. This review found the Applicant provided an acceptable response reconfirming they met General Design Criteria 14, 15 and 30 of Appendix A to 10 CFR 50 for the subject equipment

  17. Radiation and health effects. A report on the TMI-2 accident and related health studies

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1986-08-01

    On March 28, 1979, the Unit 2 reactor at the Three Mile Island (TMI) Nuclear Station was severely damaged by an accident. Radioactivity was discharged to the environment resulting in a small amount of radiation exposure to the public. Continuing concerns by some members of the communities around TMI about the potential radiation-induced health effects prompted GPU Nuclear Corporation to examine the information gathered from the accident investigation in the context of our current knowledge of radiation and its effects on human health. Although this report deals with technical matters, the information is presented in a manner that can be understood by those who do not have scientific backgrounds. This report is divided into three major sections. The first section provides an overview of the past 80 years of relevant research on the subject of radiation and its effects on human health. During that time, scientists and physicians throughout the world have studied hundreds of thousands of individuals exposed to radiation from medical and occupational sources and from nuclear weapons explosions. Epidemiologic studies of humans, such as the Japanese survivors of the atomic bomb, have established that following exposure to large doses of radiation, certain health effects, including cancer, can be observed. Radiation-induced health effects from low doses of radiation, such as those associated with the TMI-2 accident, appear infrequently, if at all, and are identical and, therefore, indistinguishable from similar health effects which occur normally. For example, cancers induced by radiation are indistinguishable from those occurring spontaneously or normally. It is not possible, therefore, for scientists to determine directly whether radiation-induced health effects at low doses occur at all; such observations can only be inferred by statistical methods. The second section of this report provides a brief description of the TMI-2 accident. Most of the radioactivity from the

  18. Peer review of the Three Mile Island Unit 2 Vessel Investigation Project metallurgical examinations

    Energy Technology Data Exchange (ETDEWEB)

    Bohl, R.W.; Gaydos, R.G.; Vander Voort, G.F.; Diercks, D.R. [Argonne National Lab., IL (United States)

    1994-07-01

    Fifteen samples recovered from the lower head of the Three Mile Island (TMI) Unit 2 nuclear reactor pressure vessel were subjected to detailed metallurgical examinations by the Idaho National Engineering Laboratory (INEL), with supporting work carried out by Argonne National Laboratory (ANL) and several of the European participants. These examinations determined that a portion of the lower head, a so-called elliptical ``hot spot`` measuring {approx}0.8 {times} 1 m, reached temperatures as high as 1100{degrees}C during the accident and cooled from these temperatures at {approx}10--100{degrees}C/min. The remainder of the lower head was found to have remained below the ferrite-toaustenite transformation temperature of 727{degrees}C during the accident. Because of the significance of these results and their importance to the overall analysis of the TMI accident, a panel of three outside peer reviewers, Dr. Robert W. Bohl, Mr. Richard G. Gaydos, and Mr. George F. Vander Voort, was formed to conduct an independent review of the metallurgical analyses. After a thorough review of the previous analyses and examination of photo-micrographs and actual lower head specimens, the panel determined that the conclusions resulting from the INEL study were fundamentally correct. In particular, the panel reaffirmed that four lower head samples attained temperatures as high as 1100{degrees}C, and perhaps as high as 1150--1200{degrees}C in one case, during the accident. They concluded that these samples subsequently cooled at a rate of {approx}50--125{degrees}C/min in the temperature range of 600--400{degrees}C, in good agreement with the original analysis. The reviewers also agreed that the remainder of the lower head samples had not exceeded the ferrite-to-austenite transformation temperature during the accident and suggested several refinements and alternative procedures that could have been employed in the original analysis.

  19. Peer review of the Three Mile Island Unit 2 Vessel Investigation Project metallurgical examinations

    International Nuclear Information System (INIS)

    Bohl, R.W.; Gaydos, R.G.; Vander Voort, G.F.; Diercks, D.R.

    1994-07-01

    Fifteen samples recovered from the lower head of the Three Mile Island (TMI) Unit 2 nuclear reactor pressure vessel were subjected to detailed metallurgical examinations by the Idaho National Engineering Laboratory (INEL), with supporting work carried out by Argonne National Laboratory (ANL) and several of the European participants. These examinations determined that a portion of the lower head, a so-called elliptical ''hot spot'' measuring ∼0.8 x 1 m, reached temperatures as high as 1100 degrees C during the accident and cooled from these temperatures at ∼10--100 degrees C/min. The remainder of the lower head was found to have remained below the ferrite-toaustenite transformation temperature of 727 degrees C during the accident. Because of the significance of these results and their importance to the overall analysis of the TMI accident, a panel of three outside peer reviewers, Dr. Robert W. Bohl, Mr. Richard G. Gaydos, and Mr. George F. Vander Voort, was formed to conduct an independent review of the metallurgical analyses. After a thorough review of the previous analyses and examination of photo-micrographs and actual lower head specimens, the panel determined that the conclusions resulting from the INEL study were fundamentally correct. In particular, the panel reaffirmed that four lower head samples attained temperatures as high as 1100 degrees C, and perhaps as high as 1150--1200 degrees C in one case, during the accident. They concluded that these samples subsequently cooled at a rate of ∼50--125 degrees C/min in the temperature range of 600--400 degrees C, in good agreement with the original analysis. The reviewers also agreed that the remainder of the lower head samples had not exceeded the ferrite-to-austenite transformation temperature during the accident and suggested several refinements and alternative procedures that could have been employed in the original analysis

  20. TmiRUSite and TmiROSite scripts: searching for mRNA fragments with miRNA binding sites with encoded amino acid residues.

    Science.gov (United States)

    Berillo, Olga; Régnier, Mireille; Ivashchenko, Anatoly

    2014-01-01

    microRNAs are small RNA molecules that inhibit the translation of target genes. microRNA binding sites are located in the untranslated regions as well as in the coding domains. We describe TmiRUSite and TmiROSite scripts developed using python as tools for the extraction of nucleotide sequences for miRNA binding sites with their encoded amino acid residue sequences. The scripts allow for retrieving a set of additional sequences at left and at right from the binding site. The scripts presents all received data in table formats that are easy to analyse further. The predicted data finds utility in molecular and evolutionary biology studies. They find use in studying miRNA binding sites in animals and plants. TmiRUSite and TmiROSite scripts are available for free from authors upon request and at https: //sites.google.com/site/malaheenee/downloads for download.

  1. TMI-2 and its impact on the regulatory process

    International Nuclear Information System (INIS)

    Israel, S.

    1979-01-01

    In response to TMI-2, several task forces were formed at NRC to evaluate the weaknesses in plant design and operation and make recommendations to assure that a similar event would not occur at other operating plants. This paper discusses the recommendations made in the areas of emergency preparedness and other systems and instrumentation. We believe the implementation of these recommendations will significantly improve nuclear power plant safety in the United States. (author)

  2. TMI-2 as a major experiment

    International Nuclear Information System (INIS)

    Kinter, E.E.

    1994-01-01

    This paper shows how TMI-2 accident changed profoundly the nuclear research perspective with a large-scale core damaging accident which provided an opportunity to compare theory and computer codes to an enormous set of benchmark data. The vessel sample gathering and study programs were unusually successful. The TMI-2 events appeared to dramatically challenge not only the engineering designs and safety calculations, but also the institutional arrangements between industry, state, ..., causing the establishment of the INPO, changes in management relationships, etc

  3. TMI-2 fuel-recovery plant. Feasibility study

    International Nuclear Information System (INIS)

    Evans, D.L.

    1982-12-01

    This project is a feasibility study for constructing a TMI-2 core Fuel Recovery Plant at the Idaho National Engineering Laboratory (INEL). The primary objectives of the Fuel Recovery Plant (FRP) are to recover and account for the fuel and to process, isolate, and package the waste material from the TMI-2 core. This feasibility study is predicated on a baseline plant and covers its design, fabrication, installation, testing and operation. Alternative methods for the disposal of the TMI-2 core have also been considered, but not examined in detail for their feasibility. The FRP will receive TMI-2 fuel in canisters. The fuel will vary from core debris to intact fuel assemblies and include some core structural materials. The canister contents will be shredded and subsequently fed to a dissolver. Uranium, plutonium, fission products, and some core structural material will be dissolved. The uranium will be separated by solvent extraction and solidified by calcination. The plutonium will also be separated by solvent extraction and routed to the Plutonium Extraction Facility. The wastes will be packaged for further treatment, temporary storage or permanent disposal

  4. Venting krypton-85 from the Three Mile Island Unit 2 reactor building

    International Nuclear Information System (INIS)

    Burton, H.M.

    1981-01-01

    To permit the less restricted access to the reactor building necessary to maintain instrumentation and equipment, and to proceed towad the total decontamination of the facility, General Public Utilities, operators of the facility referred to hereafter as GPU, asked the United States Nuclear Regulatory Commission, or NRC, for permission to remove the 85 Kr from the reactor building by venting it to the environment. GPU supported their request with the Safety Analysis and Environmental Assessment Report on the proposed reactor building venting plan. On June 12, 1980, after seven months of licensing deliberations and numerous public hearings, the NRC granted GPU's request. The actual venting took place between June 28 and July 11, 1980. This report presents an overview of the detailed effort involved in the TMI-2 reactor building venting program. The findings reported here are condensed from a published report entitled TMI-2 Reactor Building Purge--Kr-85 Venting

  5. Three Mile Island unit 2 vessel investigation project. Conclusions and significance

    International Nuclear Information System (INIS)

    Beckjord, E.S.

    1994-01-01

    At the conclusion of the TMI-2 Vessel Investigation Project, additional insights about the accident have been gained, specifically in the area of reactor vessel integrity and the conditions of the lower head of the reactor vessel. This paper discusses three topics: the evolving views about the TMI-2 accident scenario over time, the technical conclusions of the TMI-2 VIP (recovery of samples from the vessel lower head), and the broad significance of these findings (accident management). 4 refs

  6. International experience in the implementation of the lessons learned from the Three Mile Island incident

    International Nuclear Information System (INIS)

    1983-08-01

    This document consists of two parts and an Appendix. Part I provides a summary of worldwide experiences and subsequent recommendations regarding the implementation of the Three Mile Island-Unit 2 incident lessons learned. Part II gives in a summary fashion, specific responses and actions of the mentioned countries and international organizations as categorized into ten (10) subject areas. The Appendix, on the other hand, contains examples of the experiences of Brazil, Germany (F.R.), Hungary, and the Philippines, on the implementation of TMI lessons learned. This document should be useful to countries with nuclear power development programmes in that it provides a means for comparison of their actions with others. For countries which are embarking on their first nuclear power project, the document should provide a useful reference for specific TMI-related issues that need to be considered in their nuclear programmes

  7. Processes, Techniques, and Successes in Welding the Dry Shielded Canisters of the TMI-2 Reactor Core Debris

    International Nuclear Information System (INIS)

    Zirker, L.R.; Rankin, R.A.; Ferrell, L.J.

    2002-01-01

    The Idaho National Engineering and Environmental Laboratory (INEEL) is operated by Bechtel-BWXT Idaho LLC (BBWI), which recently completed a very successful $100 million Three-Mile Island-2 (TMI-2) program for the Department of Energy (DOE). This complex and challenging program used an integrated multidisciplinary team approach that loaded, welded, and transported an unprecedented 25 dry shielded canisters (DSC) in seven months, and did so ahead of schedule. The program moved over 340 canisters of TMI-2 core debris that had been in wet storage into a dry storage facility at the INEEL. The main thrust of this paper is relating the innovations, techniques, approaches, and lessons learned associated to welding of the DSC's. This paper shows the synergism of elements to meet program success and shares these lessons learned that will facilitate success with welding of dry shielded canisters in other DOE complex dry storage programs

  8. Longitudinal study of appraisal at Three Mile Island: implications for life event research.

    Science.gov (United States)

    Goldsteen, R; Schorr, J K; Goldsteen, K S

    1989-01-01

    This study tests a path model which indicates the occurrence of appraisal following the accident at Three Mile Island (TMI). The model posits a causal relationship between trust in TMI-related authorities, perceived danger, perceived harm to health, and psychological distress. The implications of the findings for life event research are discussed in terms of the etiological significance of meaning, event consequences, and control.

  9. TMI-2 analysis using SCDAP/RELAP5/MOD3.1

    International Nuclear Information System (INIS)

    Hohorst, J.K.; Polkinghorne, S.T.; Siefken, L.J.; Allison, C.M.; Dobbe, C.A.

    1994-11-01

    SCDAP/RELAP5/MOD3.1, an integrated thermal hydraulic analysis code developed primarily to simulate severe accidents in nuclear power plants, was used to predict the progression of core damage during the TMI-2 accident. The version of the code used for the TMI-2 analysis described in this paper includes models to predict core heatup, core geometry changes, and the relocation of molten core debris to the lower plenum of the reactor vessel. This paper describes the TMI-2 input model, initial conditions, boundary conditions, and the results from the best-estimate simulation of Phases 1 to 4 of the TMI-2 accident as well as the results from several sensitivity calculations

  10. TMI-2 Lessons Learned Task Force status report and short-term recommendations

    International Nuclear Information System (INIS)

    1979-07-01

    Review of the Three Mile Island accident by the TMI-2 Lessons Learned Task Force has disclosed a number of actions in the areas of design and analysis and plant operations that the Task Force recommends be required in the short term to provide substantial additional protection which is required for the public health and safety. All nuclear power plants in operation or in various stages of construction or licensing action are affected to varying degrees by the specific recommendations. The Task Force is continuing work in areas of general safety criteria, systems design requirements, nuclear power plant operations, and nuclear power plant licensing

  11. Three Mile Island nuclear reactor accident of March 1979. Environmental radiation data: Update. A report to the President's Commission on the Accident at Three Mile Island

    International Nuclear Information System (INIS)

    Bretthauer, E.W.; Grossman, R.F.; Thome, D.J.; Smith, A.E.

    1981-03-01

    This report contains a listing of environmental radiation monitoring data collected in the vicinity of Three Mile Island (TMI) following the March 28, 1979 accident. These data were collected by the EPA, NRC, DOE, HHS, the Commonwealth of Pennsylvania, or the Bethlehem Steel Corporation. The original report was printed in September 1979 and the update was released in December 1979. Also included in this update is a listing of whole-body counting data obtained by the NRC to assess the quantity of internally deposited radionuclides in TMI workers and volunteer residents within a three-mile-radius of TMI. No reactor-related radionuclides were identified in any of the whole-body counting data

  12. Frequency probabilistic analysis of a small break LOCA due to a power operated relief valve (PORV) for Angra-1 pre-TMI and post-TMI

    International Nuclear Information System (INIS)

    Onusic Junior, J.

    1986-01-01

    After the TMI event efforts were aimed towards improvements in the operational and administrative procedures related to the power operated relief valves (PORVs) in order to decrease the probability of a small-break loss-of-coolant accident (LOCA) caused by stuck-open power operated relief valve. This paper presents a frequency probabilistic analysis of a small break LOCA due to a stuck open PORV and safety valve to the Angra I nuclear power plant in operating conditions pre-TMI and post-TMI. (Author) [pt

  13. TMI-2 accident evaluation program sample acquisition and examination plan. Executive summary

    International Nuclear Information System (INIS)

    Russell, M.L.; McCardell, R.K.; Broughton, J.M.

    1985-12-01

    The purpose of the TMI-2 Accident Evaluation Program Sample Acquisition and Examination (TMI-2 AEP SA and E) program is to develop and implement a test and inspection plan that completes the current-condition characterization of (a) the TMI-2 equipment that may have been damaged by the core damage events and (b) the TMI-2 core fission product inventory. The characterization program includes both sample acquisitions and examinations and in-situ measurements. Fission product characterization involves locating the fission products as well as determining their chemical form and determining material association

  14. TMI-2 core-examination program: INEL facilities readiness study

    International Nuclear Information System (INIS)

    McLaughlin, T.B.

    1983-02-01

    This report reviews the capability and readiness of remote handling facilities at the Idaho National Engineering Laboratory (INEL) to receive, and store the TMI-2 core, and to examine and analyze TMI-2 core samples. To accomplish these objectives, the facilities must be able to receive commercial casks, unload canisters from the casks, store the canisters, open the canisters, handle the fuel debris and assemblies, and perform various examinations. The report identifies documentation, including core information, necessary to INEL before receiving the entire TMI-2 core. Also identified are prerequisites to INEL's receipt of the first canister: costs, schedules, and a preliminary project plan for the tasks

  15. Thyroid cancer characteristics in the population surrounding Three Mile Island.

    Science.gov (United States)

    Goyal, Neerav; Camacho, Fabian; Mangano, Joseph; Goldenberg, David

    2012-06-01

    To determine differences in disease characteristics between the thyroid cancer populations in the area around the Three Mile Island (TMI) nuclear power plant and the rest of the state of Pennsylvania. Retrospective cross-sectional study. Data from the Pennsylvania Cancer Registry from 1985 to 2008 were reviewed and information regarding age at diagnosis, sex, race, residential status, county of residence, thyroid pathology, thyroid surgery, and staging was recorded. Dauphin, Lancaster, and York counties were defined as the TMI area. Records of 26,357 thyroid cancer patients were reviewed, with 2,611 patients within the TMI area. A higher proportion of papillary thyroid cancer (P < .001) and lower proportion of follicular thyroid cancer (P < .001) were noted in the TMI area population. Thyroid cancer cases from the TMI area were found to be more likely to be diagnosed before the age of 65 years (P < .001), be Pennsylvania born (P < .001), be well differentiated (P < .001), be <10 mm in size (P < .001), and be localized without spread (P < .001). Although the TMI area shows a higher incidence of thyroid cancer as compared to the rest of the state, this was not statistically significant. The TMI population showed a higher proportion of papillary thyroid cancer and less aggressive pathology and earlier diagnosis compared to the rest of Pennsylvania. No statistically significant difference in thyroid cancer incidence was noted. Overall, the study does not show a clear link with more advanced thyroid cancer and proximity to the TMI nuclear reactors. Copyright © 2012 The American Laryngological, Rhinological, and Otological Society, Inc.

  16. African Journals Online: United States Minor Outlying Islands

    African Journals Online (AJOL)

    African Journals Online: United States Minor Outlying Islands. Home > African Journals Online: United States Minor Outlying Islands. Log in or Register to get access to full text downloads. Username, Password, Remember me, or Register · Browse By Category · Browse Alphabetically · Browse By Country · List All Titles ...

  17. The legacy of Three Mile Island: Implications for today's U.S. Department of Energy challenges

    International Nuclear Information System (INIS)

    Coe, R.P.; Conaway, W.T.; Williams, M.S.

    1996-01-01

    Over the course of the 16 year period following the accident at Three Mile Island-Unit-2, much has been learned and volumes have been written regarding the cause and massive cleanup activities of the incident. Because of these Lessons Learned, important changes have been made and the US commercial nuclear industry is safer and more reliable as a result. It is important to recognize that two major sources of information emerged from this event. First and foremost were the important safety issues that required immediate answers and the addition of the modifications to plants that these answers generated. Second and of considerable significance to the US Department of energy (US DOE) in today's post-cold war environment are the frequently hard-won lessons involved with the recovery, clean-up, and defueling of TMI-2 and its unprecedented transition into long-term, monitored storage. While the commercial industry, regulatory authorities, and the public saw an immediate need for instituting the important safety lessons from TMI-2, these new systems, improved training and operating practices have paid off in increased reliability and extended operations. However, there was no such immediate application for the second source of information, that being the application of the deactivation and long-term storage technology learned at TMI-2 to a current condition. The tasks and methods used in the TMI-2 recovery have strong parallels in the present-day DOE cleanup program

  18. Safety culture and the accident at Three Mile Island

    International Nuclear Information System (INIS)

    Erp, Jan B. van

    2002-01-01

    Prior to the accident at Three Mile Island, little attention was being paid to the human role in the safe operation of civilian nuclear power plants. The investigation of the TMI accident showed that its root causes were primarily human-related. The Kemeny Report on the TMI accident does not use the term 'safety culture'; however, it fully identifies all relevant aspects of safety culture. It was only after the accident at Chernobyl that the term 'safety culture' came into widespread use. However, it should be noted that, during the years after TMI and before Chernobyl, already major changes had been instituted concerning human factors and human reliability in the civilian nuclear energy programs of many countries. Greater credit should be given to the remarkable insights developed by the Kemeny Commission as contained in the Kemeny Report. (author)

  19. TMI-2 source and intermediate range neutron flux monitors data report

    International Nuclear Information System (INIS)

    McCormick, R.D.

    1986-03-01

    This is a report on the preparation of data from the TMI-2 excore source and intermediate range neutron flux monitors for inclusion into the TMI Data Base. The sources of the as-recorded data are discussed as well as the process of transforming these data into digital form. The corrections to the as-recorded data are given and the data quality classification and uncertainty are established. The identifiers attached to each data set in the TMI Data Base are given

  20. GHRSST Level 3P USA Remote Sensing Systems TMI SST:1

    Data.gov (United States)

    National Aeronautics and Space Administration — Version-3b TMI Ocean Products, in November 1997, the TMI radiometer with a 10.7 GHz channel was launched aboard the TRMM satellite.The important feature of microwave...

  1. TmiRUSite and TmiROSite scripts: searching for mRNA fragments with miRNA binding sites with encoded amino acid residues

    OpenAIRE

    Berillo, Olga; Régnier, Mireille; Ivashchenko, Anatoly

    2014-01-01

    microRNAs are small RNA molecules that inhibit the translation of target genes. microRNA binding sites are located in the untranslated regions as well as in the coding domains. We describe TmiRUSite and TmiROSite scripts developed using python as tools for the extraction of nucleotide sequences for miRNA binding sites with their encoded amino acid residue sequences. The scripts allow for retrieving a set of additional sequences at left and at right from the binding site. The scripts presents ...

  2. Risk cognition and the public: case of Three Mile Island

    International Nuclear Information System (INIS)

    Cutter, S.L.

    1984-01-01

    Residents of within 50 miles of the nuclear power plant at Three Mile Island (TMI), Pennsylvania, were surveyed in 1979, 1980, and 1982 to assess their general attitudes toward nuclear power, to assess their individual coping responses to the March 1979 accident, and to monitor changes in attitudes over the three-year period. Most respondents feel that future accidents like TMI will occur one or twice more in their lifetimes, that operating nuclear power stations should have improved safeguards and should continue operating, and that major insitutions - government and utility companies - are experiencing a continued erosion of public trust

  3. Impact of the accident at the Three Mile Island on the behavior and well-being of nuclear workers. Part II. Job tension, psychophysiological symptoms, and indices of distress

    International Nuclear Information System (INIS)

    Kasl, S.V.; Chisholm, R.F.; Eskenazi, B.

    1981-01-01

    Three Mile Island (TMI) workers experienced much greater job tension and lower occupational self-esteem (supervisors only) in comparison with workers interviewed at the Peach Bottom Plant. At the time of the accident, TMI workers reported experiencing more periods of anger, extreme worrry and extreme upset, and more psychophysiological symptoms. Six months after the accident, some persistence of these feelings and symptoms was evident. Demoralization was greater primarily among TMI non-supervisory workers. The impact of the accident was not greater among TMI workers living closer to the plant. Presence of a preschool child at home enhanced the impact of the accident, but primarily among TMI supervisors. 39 references, 17 tables

  4. Disposal demonstration of a high integrity container (HIC) containing an EPICOR-II prefilter from Three Mile Island

    International Nuclear Information System (INIS)

    McConnell, J.W. Jr.; Tyacke, M.J.; Schmitt, R.C.; Reno, H.W.

    1985-02-01

    A high integrity container (HIC) was developed, tested, and certified for use in disposing of unusual low-level radioactive waste from Three Mile Island Unit 2 (TMI-2). The work was coordinated by EG and G Idaho, Inc. and funded by the US Department of Energy. A disposal demonstration using an HIC containing an EPICOR-II prefilter from TMI-2 was completed at the commercial disposal facility in the State of Washington. A Certification of Compliance was issued by the Department of Social and Health Services of the State of Washington to use the HIC in disposing of up to 50 EPICOR-II prefilters. That Certification of Compliance was issued after rigorous review of the HIC design and test program by the State and by the US Nuclear Regulatory Commission. This report describes the processes of loading, transporting, and disposing of the demonstration HIC and briefly describes the design, testing, and approval effort leading up to the demonstration

  5. Evacuation decision-making at Three Mile Island

    International Nuclear Information System (INIS)

    Zeigler, D.J.; Johnson, J.H. Jr.

    1987-01-01

    During the emergency at the Three Mile Island generating station in the United States, evacuation became a common adaptive response among the local population. The planning for nuclear emergencies in the US has proceeded as if there were no significant differences between nuclear and other types of disasters requiring evacuation. In the United Kingdom, emergency planning for a new generation of pressurized water reactors, about which there is legitimate safety concern, has been influenced not at all by the experience with the Three Mile Island PWR in 1979. The TMI accident has been the US's most serious experience with a nuclear plant accident and therefore is an appropriate analogy for predicting the evacuation response to future nuclear emergencies. In this light, the authors accept the need to develop models that will enable them to predict the magnitude of the evacuation shadow phenomenon around other nuclear power sites and estimate its impact on our plans to remove the threatened population from the hazard zone in the minimum amount of time. Rather than depend on education and information control to stifle evacuation response, the authors believe that evacuation plans need to build on people's natural behavioural inclinations to protect themselves in response to the nuclear hazard

  6. Technical evaluation report TMI action: NUREG-0737 (II.D.1) relief and safety valve testing,. Diablo Canyon Units 1 and 2 (Docket Nos. 50-275, 50-323)

    International Nuclear Information System (INIS)

    Miller, G.K.; Magleby, H.L.; Nalezny, C.L.

    1984-07-01

    Light water reactor operators have experienced a number of occurrences of improper performance of safety and relief valves installed in their primary coolant systems. Because of this, the authors of NUREG-0578 (TMI-2 Lessons Learned Task Status Report and Short-Term Recommendations) and subsequently NUREG-0737 (Clarification of TMI Action Plan Requirements) recommended that programs be developed and completed which would reevaluate the functional performance capabilities of Pressurized Water Reactor (PWR) safety, relief, and block valves and which would verify the integrity of the piping systems for normal, transient and accident conditions. This report provides the results of the review of these programs and their results by the Nuclear Regulatory Commission (NRC) and their consultant, EG and G Idaho, Inc. Specifically, this report has examined the response of the Licensee for Diablo Canyon Units 1 and 2, to the requirements of NUREG-0578 and NUREG-0737 and finds that the Licensee has provided an acceptable response, reconfirming that the General Design Criteria 14, 15 and 30 of Appendix A to 10 CRF 50 have been met. 18 refs

  7. Three Mile Island nuclear reactor accident of March 1979. Environmental radiation data: Volume I. A report to the President's Commission on the Accident at Three Mile Island

    International Nuclear Information System (INIS)

    Bretthauer, E.W.; Grossman, R.F.; Thome, D.J.; Smith, A.E.

    1981-03-01

    This report contains a listing of environmental radiation monitoring data collected in the vicinity of Three Mile Island (TMI) following the March 28, 1979 accident. These data were collected by the EPA, NRC, DOE, HHS, the Commonwealth of Pennsylvania, or the Bethlehem Steel Corporation. The original report was printed in September 1979 and the update was released in December 1979. Volume 1 consists of the following 5 tables: Table 1-Measurements made by principal participants; Table 2-Cross-check program instituted by US Environmental Protection Agency (EPA) for iodine-131 in milk. Table 3-Comparison of EPA and US Nuclear Regulatory Commission (NRC) air data collected at the Three Mile Island (TMI) Observation Center; Table 4-Summary of EPA Environmental Monitoring Systems Laboratory-Las Vegas (EMSL-LV) and EPA Eastern Environmental Radiation Facility-Montgomery (EERF-Montgomery) sampling and analytical procedures; Table 5-Computer printout of environmental data collected by EPA

  8. TMI-related requirements for new operating licenses. Technical report

    International Nuclear Information System (INIS)

    1980-06-01

    There are four types of TMI-related requirements and actions approved by the Commission for new operating licenses: (1) those required to be completed by a license applicant prior to receiving a fuel-loading and low-power testing license, (2) those required to be completed by a license applicant prior to receiving a license to operate at appreciable power levels up to full power, (3) those the NRC will take prior to issuing a fuel-loading and low-power testing or a full-power operating license, and (4) those required to be completed by a licensee prior to a specified date. In this report, only those dated requirements that have already been issued are of interest. Other dated requirements are expected to be issued in the future as work progresses in accordance with the TMI Action Plan. This report summarizes the several parts of the list of TMI-related requirements approved by the Commission for new operating licenses

  9. Physical inventory verification exercise at a light-water reactor facility

    International Nuclear Information System (INIS)

    Bosler, G.E.; Menlove, H.O.; Halbig, J.K.

    1986-04-01

    A simulated physical inventory verification exercise was performed at the Three Mile Island (TMI) Unit 1 reactor. Inspectors from the Internatinal Atomic Energy Agency made measurements on fresh- and spent-fuel assemblies and verified the special nuclear material inventory at TMI. Simulated inspection log sheets and computerized inspection reports were prepared

  10. The TMI-2 core relocation: Heat transfer and mechanism

    International Nuclear Information System (INIS)

    Epstein, M.; Fauske, H.K.

    1987-07-01

    It is postulated that the collapse of the upper debris bed was the main cause of core failure and core material relocation during the TMI-2 accident. It is shown that this mechanism of core relocation can account for the timescale(s) and energy transfer rate inferred from plant instrumentation. Additional analysis suggests that the water in the lower half of the reactor vessel was subcooled at the onset of relocation, as subcooling serves to explain the final coolable configuration at the bottom of the TMI vessel

  11. Chronic stress, catecholamines, and sleep disturbance at Three Mile Island

    International Nuclear Information System (INIS)

    Davidson, L.M.; Fleming, R.; Baum, A.

    1987-01-01

    The present study was concerned with the relationship between chronic stress and sleep disturbance. Previous research has provided evidence of chronic stress responding among people living near the Three Mile Island nuclear generating facility. Compared to control subjects, the TMI group has exhibited greater symptom reporting, poorer performance on behavioral measures of concentration, and elevated levels of urinary norepinephrine and epinephrine. Other research has suggested a relationship between arousal and insomnia. The extent to which stress and sleep disturbances were experienced by residents at TMI was examined and compared to levels of stress and sleep disturbance among a group of control subjects. The relationship between stress and sleep disturbances was also examined. Results indicated that TMI area residents exhibited more stress than the controls and reported greater disturbance of sleep. Modest relationships among stress and sleep measures suggested that the symptoms of stress measured in this study were not primary determinants of sleep problems

  12. Chronic stress, catecholamines, and sleep disturbance at Three Mile Island.

    Science.gov (United States)

    Davidson, L M; Fleming, R; Baum, A

    1987-01-01

    The present study was concerned with the relationship between chronic stress and sleep disturbance. Previous research has provided evidence of chronic stress responding among people living near the Three Mile Island nuclear generating facility. Compared to control subjects, the TMI group has exhibited greater symptom reporting, poorer performance on behavioral measures of concentration, and elevated levels of urinary norepinephrine and epinephrine. Other research has suggested a relationship between arousal and insomnia. The extent to which stress and sleep disturbances were experienced by residents at TMI was examined and compared to levels of stress and sleep disturbance among a group of control subjects. The relationship between stress and sleep disturbances was also examined. Results indicated that TMI area residents exhibited more stress than the controls and reported greater disturbance of sleep. Modest relationships among stress and sleep measures suggested that the symptoms of stress measured in this study were not primary determinants of sleep problems.

  13. Status of the TMI SOFC system

    Energy Technology Data Exchange (ETDEWEB)

    Ruhl, R.C.; Petrik, M.A.; Cable, T.L. [Technology Management, Inc., Cleveland, OH (United States)

    1996-12-31

    TMI has completed preliminary engineering designs for complete 20kW SOFC systems modules for stationary distributed generation applications using pipeline natural gas [sponsored by Rochester Gas and Electric (Rochester, New York) and EPRI (Palo Alto, California)]. Subsystem concepts are currently being tested.

  14. Nuclear-reactor accidents: Chernobyl, TMI, and Windscale. January 1974-September 1988 (Citations from Pollution Abstracts). Report for January 1974-September 1988

    International Nuclear Information System (INIS)

    1988-11-01

    This bibliography contains citations concerning studies and measurements of the radiological consequences of nuclear-reactor accidents. The citations cover specifically the Chernobyl reactor in the USSR, the Three Mile Island (TMI) reactor in the US, and the Windscale reactor in the UK. Included are detection and monitoring of the fallout, the resultant runoff into rivers, lakes, and the sea, the radiation effects on people, and the transfrontier radioactive contamination of the environment. (Contains 105 citations fully indexed and including a title list.)

  15. the accident at Three Mile Island

    International Nuclear Information System (INIS)

    Torrey, L.

    1979-01-01

    The recently published final report of the President's Commision on the accident at Three Mile Island (TMI) is considered. In the report the power utilities and the US Nuclear Regulatory Commission (NRC) are severely criticised for being 'unable to provide an acceptable level of safety in nuclear power' which is reflected in the operators lack of training and understanding in depth. The 44 recommendations of the Commission include the abolition of the NRC, periodic renewal of operating licences, the siting of all future nuclear power plants away from large population centres, emergency response procedures to be improved and the revamping of warning display panels in control rooms. The commission also evaluated the severity of the accident and endeavoured to determine how close TMI came to a total catastrophic meltdown. The role of the media in the accident was also considered. (UK)

  16. Metallurgical examination of, and resin transfer from, Three Mile Island prefilter liners

    Energy Technology Data Exchange (ETDEWEB)

    McConnell, Jr, J W; Spaletta, H W

    1984-08-01

    Metallurgical examinations were performed on two EPICOR-II prefilter liners at the Idaho National Engineering Laboratory (INEL) to determine conditions of the liners and identify the minimum expected lifetime of those and other liners stored at INEL. The research work was accomplished by EG and G Idaho, Inc. for the EPICOR-II Research and Disposition Program, which is funded by the US Department of Energy. The EPICOR-II prefilter liners were used to filter radionuclides from contaminated water during cleanup of Three Mile Island Unit 2 (TMI-2). The liners were constructed of carbon steel with a phenolic protective coating and contained organic and inorganic ion-exchange filtration media. Program plans call for interim storage of EPICOR-II prefilters at INEL for up to ten years, before final disposal in high integrity containers at the Hanford, Washington commercial disposal site. This report describes the (a) resin transfer process used to empty liners for examination, (b) removal of metallographic sections from those liners, (c) specimen preparation, and (d) findings from metallographic examination of those specimens. A minimum lifetime for the liners is determined and recommendations are given for storage of wastes from future TMI-2 activities.

  17. Metallurgical examination of, and resin transfer from, Three Mile Island prefilter liners

    International Nuclear Information System (INIS)

    McConnell, J.W. Jr.; Spaletta, H.W.

    1984-08-01

    Metallurgical examinations were performed on two EPICOR-II prefilter liners at the Idaho National Engineering Laboratory (INEL) to determine conditions of the liners and identify the minimum expected lifetime of those and other liners stored at INEL. The research work was accomplished by EG and G Idaho, Inc. for the EPICOR-II Research and Disposition Program, which is funded by the US Department of Energy. The EPICOR-II prefilter liners were used to filter radionuclides from contaminated water during cleanup of Three Mile Island Unit 2 (TMI-2). The liners were constructed of carbon steel with a phenolic protective coating and contained organic and inorganic ion-exchange filtration media. Program plans call for interim storage of EPICOR-II prefilters at INEL for up to ten years, before final disposal in high integrity containers at the Hanford, Washington commercial disposal site. This report describes the (a) resin transfer process used to empty liners for examination, (b) removal of metallographic sections from those liners, (c) specimen preparation, and (d) findings from metallographic examination of those specimens. A minimum lifetime for the liners is determined and recommendations are given for storage of wastes from future TMI-2 activities

  18. Sampling and examination methods used for TMI-2 samples

    International Nuclear Information System (INIS)

    Marley, A.W.; Akers, D.W.; McIsaac, C.V.

    1988-01-01

    The purpose of this paper is to summarize the sampling and examination techniques that were used in the collection and analysis of TMI-2 samples. Samples ranging from auxiliary building air to core debris were collected and analyzed. Handling of the larger samples and many of the smaller samples had to be done remotely and many standard laboratory analytical techniques were modified to accommodate the extremely high radiation fields associated with these samples. The TMI-2 samples presented unique problems with sampling and the laboratory analysis of prior molten fuel debris. 14 refs., 8 figs

  19. Three Mile Island and Chernobyl: what happened. What did not

    International Nuclear Information System (INIS)

    Rasmussen, N.C.

    1994-01-01

    Three Mile Island (TMI) melted 20 tons of fuel and Chernobyl melted 190 tons of fuel. Contrary to some prior predictions, the fuel at TMI collected in the bottom head but did not melt through the vessel. At Chernobyl, about 130 tons of fuel remained in the reactor cavity after the explosion. It took nine days for this fuel to melt through 6 m of serpentine gravel after which it quickly spread on the floor below the reactor and solidified. It caused no damage to piping or building structures. Again, this was much less damage than expected. Information from these two events should be used to see if more realistic models of core melt can be developed

  20. The impact of the accident at the Three Mile Island on the behavior and well-being of nuclear workers; Part I: perceptions and evaluations, behavioral responses, and work-related attitudes and feelings.

    Science.gov (United States)

    Kasl, S V; Chisholm, R F; Eskenazi, B

    1981-05-01

    In order to assess the impact of the accident at the Three Mile Island (TMI), telephone interviews were conducted six months later with 324 nuclear workers assigned to TMI and 298 workers assigned to a comparison plant at Peach Bottom (PB). Examination of PB-TMI differences, stratified by supervisory status, revealed the following: Part I: TMI workers reported greater exposure to radiation at the time of the accident and felt that their health had been thereby endangered. TMI workers experienced more uncertainty and conflict at the time of the accident. Coping responses such as seeing a doctor, taking drugs, and increasing alcohol consumption were quite infrequent. Leaving the area was more common; however, over 40 per cent of TMI workers wished to leave but did not do so because of work obligations. TMI workers reported much lower job satisfaction and much greater uncertainty about their job future.

  1. Experimenting with sodar in support of emergency preparedness at Three Mile Island-1

    International Nuclear Information System (INIS)

    Heck, W.J.

    1989-01-01

    In November 1988 at Three Mile Island Unit 1 (TMI-1), GPU Nuclear successfully completed the annual drill-for-grade that, from a modeling point of view, broke new ground for this plant. The meteorological and modeling aspects of the drill scenario were unprecedented for two reasons. First, the plume was buoyant and rose far above the height of the meteorological tower located at TMI. Second, the wind direction data from the meteorological tower were not representative of the wind direction at plume height. In the drill scenario, the buoyant plume resulted from a steam generator tube rupture where the steam ejects directly into the atmosphere via safety relief valves. Plume modeling indicated that the plume would rise to 400 ft, given the scenario meteorology. Wind data from the on-site meteorological tower, however, was only available up to 150 ft. Comparisons of sodar and tower winds were made for various weather conditions. Sodar results were studied in detail during light, moderate, and high winds; various wind directions; occurrences of rain and snow; and by time of day to determine effects of diurnal meteorological conditions on sodar performance

  2. Probabilistic Dose Assessment from SB-LOCA Accident in Ujung Lemahabang Using TMI-2 Source Term

    Directory of Open Access Journals (Sweden)

    Sunarko

    2017-01-01

    Full Text Available Probabilistic dose assessment and mapping for nuclear accident condition are performed for Ujung Lemahabang site in Muria Peninsula region in Indonesia. Source term is obtained from Three-Mile Island unit 2 (TMI-2 PWR-type SB-LOCA reactor accident inverse modeling. Effluent consisted of Xe-133, Kr-88, I-131, and Cs-137 released from a 50 m stack. Lagrangian Particle Dispersion Method (LPDM and 3-dimensional mass-consistent wind field are employed to obtain surface-level time-integrated air concentration and spatial distribution of ground-level total dose in dry condition. Site-specific meteorological data is obtained from hourly records obtained during the Site Feasibility Study period in Ujung Lemahabang. Effluent is released from a height of 50 meters in uniform rate during a 6-hour period and the dose is integrated during this period in a neutrally stable atmospheric condition. Maximum dose noted is below regulatory limit of 1 mSv and radioactive plume is spread mostly to the W-SW inland and to N-NE from the proposed plant to Java Sea. This paper has demonstrated for the first time a probabilistic analysis method for assessing possible spatial dose distribution, a hypothetical release, and a set of meteorological data for Ujung Lemahabang region.

  3. Review of light water reactor safety through the Three Mile Island accident

    International Nuclear Information System (INIS)

    Phung, D.L.

    1984-05-01

    This review of light water reactor safety through the Three Mile Island accident has the purpose of establishing the baseline over which safety achievement post-TMI is assessed, and the need for new reactor designs and business direction is judged. Five major areas of reactor safety pre-TMI are examined: (1) safety philosophy and institutions, (2) reactor design criteria, (3) operational problems, (4) the Rasmussen reactor safety study, and (5) the TMI accident and repercussions. Although nuclear power has made spectacular achievements over the period pre-TMI and although TMI is technically a minor accident, this review concludes that there were basic flaws in the technology and in the manner safety philosophy was conceived and carried out. These flaws included (1) a reactor design that has high core power density, low heat capacity, and low system tolerance to upsets, (2) reactor deployment that had been expedited without extensive operational experience, (3) rules and regulations that had to play catch-up with commercial reactor development, (4) an industry that was fragmented, short-sighted, and tended to rely on the Nuclear Regulatory Commission for safety guidance, (5) information that was not effectively shared, and (6) attention that was inadequate to the human aspects of reactor operation and to public reaction to the specter of a reactor accident, major or minor

  4. TMI-2 quick look examination

    International Nuclear Information System (INIS)

    Franz, W.A.; Rider, R.L.; Austin, W.A.; Cole, N.

    1982-01-01

    The purpose of this work, conducted under the Department of Energy's Reactor Evaluation Program, was to gain the earliest possible access to the TMI-2 reactor vessel and to determine the condition of the plenum assembly and the reactor core. Completion of this examination has also provided substantial progress towards removal of the reactor vessel head and eventual defueling. Two methods were developed for gaining through-head access. The first involves removal of an entire CRDM, providing a 6.8-cm-diameter access through the nozzle. In case normal uncoupling proved unsuccessful, contingency techniques were developed to disconnect the leadscrew. Two contingency procedures, one ex-head and one in-head, were developed. A second technique for through-head access, the so-called Quick Look technique, was developed at the suggestion of the Technical Assessment and Advisory Group (TAAG), a group of senior technical people funded by DOE to advise GPU Nuclear on the TMI-2 recovery. This simplified method involves uncoupling and removing a CRDM leadscrew by basically normal methods and inserting a Closed Circuit Television (CCTV) camera directly through the space vacated by the leadscrew

  5. Impact of the accident at TMI-2 on new safety regulations

    International Nuclear Information System (INIS)

    Collins, J.T.

    1981-01-01

    The Nuclear Regulatory Commission (NRC) has been very busy, since the accident, looking into the causes surrounding the events that occurred on the morning of March 28, 1979. To date, the Commission has implemented the Short-Term Lessons Learned and has provided a schedule for implementing the Long-Term Lessons Learned. Some of these requirements have resulted in delays in licensing of new plants and the temporary shutdown of some operating plants. However, the NRC believes these new requirements are essential to increase the safety of nuclear power plants and to protect the health and safety of the public. Although the accident occurred almost 19 months ago, the cleanup of TMI-2 continues and will continue for the next 5 to 7 years. As the cleanup progresses and ultimately the fuel removed, the Commission will continue to learn from the information generated by this program. This information will be factored into the licensing process. If nuclear power is to remain a viable option as a source of electrical power in the United States, then NRC must continue to assure the general public that these plants can be operated safely from the lessons learned at TMI and that systems required to mitigate the consequences of accidents will indeed perform their intended functions

  6. The impact of the accident at the Three Mile Island on the behavior and well-being of nuclear workers. Part I. Perceptions and evaluations, behavioral responses, and work-related attitudes and feelings

    International Nuclear Information System (INIS)

    Kasl, S.V.; Chisholm, R.F.; Eskenazi, B.

    1981-01-01

    In order to assess the impact of the accident at the Three Mile Island (TMI), telephone interviews were conducted six months later with 324 nuclear workers assigned to TMI and 298 workers assigned to a comparison plant at Peach Bottom (PB). Examination of PB-TMI differences, stratified by supervisory status, revealed that: (1) TMI workers reported greater exposure to radiation at the time of the accident and felt that their health had been thereby endangered; (2) TMI workers experienced more uncertainty and conflict at the time of the accident; (3) coping responses such as seeing a doctor, taking drugs, and increasing alcohol consumption were quite infrequent; (4) leaving the area was more common; however, over 40% of TMI workers wished to leave but did not do so because of work obligations; and (5) TMI workers reported much lower job satisfaction and much greater uncertainty about thier job future. 139 references, 8 tables

  7. Justifications of policy-error correction: a case study of error correction in the Three Mile Island Nuclear Power Plant Accident

    International Nuclear Information System (INIS)

    Kim, Y.P.

    1982-01-01

    The sensational Three Mile Island Nuclear Power Plant Accident of 1979 raised many policy problems. Since the TMI accident, many authorities in the nation, including the President's Commission on TMI, Congress, GAO, as well as NRC, have researched lessons and recommended various corrective measures for the improvement of nuclear regulatory policy. As an effort to translate the recommendations into effective actions, the NRC developed the TMI Action Plan. How sound are these corrective actions. The NRC approach to the TMI Action Plan is justifiable to the extent that decisions were reached by procedures to reduce the effects of judgmental bias. Major findings from the NRC's effort to justify the corrective actions include: (A) The deficiencies and errors in the operations at the Three Mile Island Plant were not defined through a process of comprehensive analysis. (B) Instead, problems were identified pragmatically and segmentally, through empirical investigations. These problems tended to take one of two forms - determinate problems subject to regulatory correction on the basis of available causal knowledge, and indeterminate problems solved by interim rules plus continuing study. The information to justify the solution was adjusted to the problem characteristics. (C) Finally, uncertainty in the determinate problems was resolved by seeking more causal information, while efforts to resolve indeterminate problems relied upon collective judgment and a consensus rule governing decisions about interim resolutions

  8. TMI-2 spent fuel shipping

    International Nuclear Information System (INIS)

    Quinn, G.J.; Burton, H.M.

    1985-01-01

    TMI-2 failed fuel will be shipped to the Idaho National Engineering Laboratory for use in the DOE Core Examination Program. The fuel debris will be loaded into three types of canisters during defueling and dry loaded into a spent fuel shipping cask. The cask design accommodates seven canisters per cask and has two separate containment vessels with ''leaktight'' seals. Shipments are expectd to begin in early 1986

  9. Drop tests of the Three Mile Island knockout canister

    International Nuclear Information System (INIS)

    Box, W.D.; Aaron, W.S.; Shappert, L.B.; Childress, P.C.; Quinn, G.J.; Smith, J.V.

    1986-09-01

    A type of Three Mile Island Unit 2 (TMI-2) defueling canister, called a ''knockout'' canister, was subjected to a series of drop tests at the Oak Ridge National Laboratory's Drop Test Facility. These tests were designed to confirm the structural integrity of internal fixed neutron poisons in support of a request for NRC licensing of this type of canister for the shipment of TMI-2 reactor fuel debris to the Idaho National Engineering Laboratory (INEL) for the Core Examination R and D Program. Work conducted at the Oak Ridge National Laboratory included (1) precise physical measurements of the internal poison rod configuration before assembly, (2) canister assembly and welding, (3) nondestructive examination (an initial hydrostatic pressure test and an x-ray profile of the internals before and after each drop test), (4) addition of a simulated fuel load, (5) instrumentation of the canister for each drop test, (6) fabrication of a cask simulation vessel with a developed and tested foam impact limiter, (7) use of refrigeration facilities to cool the canister to well below freezing prior to three of the drops, (8) recording the drop test with still, high-speed, and normal-speed photography, (9) recording the accelerometer measurements during impact, (10) disassembly and post-test examination with precise physical measurements, and (11) preparation of the final report

  10. Analysis of the TMI-2 source range detector response

    International Nuclear Information System (INIS)

    Carew, J.F.; Diamond, D.J.; Eridon, J.M.

    1980-01-01

    In the first few hours following the TMI-2 accident large variations (factors of 10-100) in the source range (SR) detector response were observed. The purpose of this analysis was to quantify the various effects which could contribute to these large variations. The effects evaluated included the transmission of neutrons and photons from the core to detector and the reduction in the multiplication of the Am-Be startup sources, and subsequent reduction in SR detector response, due to core voiding. A one-dimensional ANISN slab model of the TMI-2 core, core externals, pressure vessel and containment has been constructed for calculation of the SR detector response and is presented

  11. Impact of Three Mile Island on the nuclear community and the future of nuclear power

    International Nuclear Information System (INIS)

    Baron, S.

    1980-01-01

    The Three Mile Island incident has already impacted on the future of nuclear power specifically and on the energy crisis generally. The resultant NRC's de facto moratorium on the licensing of commercial nuclear power plants will increase the use of oil, raise the cost of electric power, and may create power shortages. On the positive side, TMI may have been beneficial in that it has precipitated a searching reassessment and improvement of nuclear power safety and practices-TMI not withstanding, the rate of nuclear power expansion must increase; otherwise the energy crisis will deepen in the years to come

  12. Siren system designed for Three Mile Island

    International Nuclear Information System (INIS)

    Lee, V.M.

    1984-01-01

    Since the Three Mile Island (TMI) incident in 1979, the Federal Emergency Management Agency (FEMA) and Nuclear Regulatory Commission (NRC) guidelines require utilities operating nuclear reactors to warn all civilian populations within a 10-mile radius by audible alarms in the event of a nuclear plant emergency. The case history presented involves the planning and implementation of a suitable siren-alarm system by General Public Utilities and its consultant firm. 1 figure

  13. Radiation effects on resins and zeolites at Three Mile Island Unit II

    International Nuclear Information System (INIS)

    Reilly, J.K.; Grant, P.J.; Quinn, G.J.; Hofstetter, K.J.

    1984-01-01

    Radiation effects on resin and zeolite used in the waste cleanup at Three Mile Island Unit II have been examined both experimentally and in-situ. Hydrogen and organic gases are generated due to absorbed radiation as a function of resin material, curie loading and residual water content. Significant oxygen scavaging was demonstrated in the organic resin liners. Hydrogen and oxygen gases in near stoichiometric quantities are generated from irradiation of residual water in inorganic zeolites. Gas generation was determined to be directly proportional to curie content but correlates poorly with residual water content in zeolite vessels. Results of the gas generation analyses of EPICOR II liners show that vessels with less than 166 curies had almost no hydrogen generated during two years of storage and therefore did not require safety measures for shipment or storage. Experimental measurements done at research laboratories predicted similar results associated with hydrogen gas generation and oxygen depletion. X-ray diffraction examinations and ion exchange capacity measurements indicated no evidence of irradiation effects on the structure or cesium exchange capacity for zeolites exposed to 10 10 rads. Darkening and damage of organic resin due to radiation has been identified. Breaking and agglomeration of the purification demineralizer resin is believed to be the result of temperature effects. No damage was identified from radiation effects on zeolite. Organic and inorganic sorbents used in the processing of contaminated waters at TMI-2 have been shown to be effective in maintaining long-term stability under high radiation conditions. The effects of radiolytic degradation have been shown by direct measurements and simulation tests and are of use in their general application throughout the industry

  14. Emotional, Behavioral, and Physiological Effects of Chronic Stress at Three Mile Island.

    Science.gov (United States)

    Baum, Andrew; And Others

    1983-01-01

    Evaluated the psychophysiological impact of Three Mile Island on nearby residents (N=38) compared to people living near an undamaged nuclear plant (N=32), a coal-fired plant (N=24) and a control group. Results indicated that residents of the TMI area exhibited more symptoms of stress a year after the accident. (WAS)

  15. Three Mile Island telephone survey: preliminary report on procedures and findings

    International Nuclear Information System (INIS)

    Flynn, C.B.

    1979-10-01

    This report describes the methodology used in, and the results of, a telephone survey conducted in the vicinity of the Three Mile Island nuclear power plant. The survey is part of a study of the socioeconomic impacts of nuclear power plant construction and operation at Three Mile Island, and eleven other nuclear power plant sites. The survey covers the areas of evacuation behavior, information processing, short-term accident effects, continuing effects of the accident, and respondent's evaluation of TMI and nuclear power in general. Approximately 1500 households in the vicinity of the Three Mile Island nuclear power plant participated in the survey, which was conducted in July and August 1979

  16. Three Mile Island nuclear reactor accident of March 1979. Environmental radiation data: Volume III. A report to the President's Commission on the Accident at Three Mile Island

    International Nuclear Information System (INIS)

    Bretthauer, E.W.; Grossman, R.F.; Thome, D.J.; Smith, A.E.

    1981-03-01

    This report contains a listing of environmental radiation monitoring data collected in the vicinity of Three Mile Island (TMI) following the March 28, 1979 accident. These data were collected by the EPA, NRC, DOE, HHS, the Commonwealth of Pennsylvania, or the Bethlehem Steel Corporation. This volume consists of Table 9 Computer printout of environmental data collected NRC

  17. Nuclear accidents. Three mile Island (United States)

    International Nuclear Information System (INIS)

    Duco, J.

    2004-01-01

    This paper describes the accident of Three Miles Island power plant which occurred the 28 march 1979 in the United States. The accident scenario, the consequences and the reactor core and vessel, after the accident, are analyzed. (A.L.B.)

  18. The Three Mile Island Population Registry.

    Science.gov (United States)

    Goldhaber, M K; Tokuhata, G K; Digon, E; Caldwell, G G; Stein, G F; Lutz, G; Gur, D

    1983-01-01

    Shortly after the March 28, 1979, accident at the Three Mile Island (TMI) nuclear plant outside Harrisburg, Pa., the Pennsylvania Department of Health, in conjunction with the Centers for Disease Control and the U.S. Bureau of the Census, conducted a census of the 35,930 persons residing within 5 miles of the plant. With the help of 150 enumerators, demographic and health-related information was collected on each person to provide baseline data for future short- and long-term epidemiologic studies of the effects of the accident. Individual radiation doses were estimated on the basis of residential location and the amount of time each person spent in the 5-mile area during the 10 days after the accident. Health and behavioral resurveys of the population will be conducted approximately every 5 years. Population-mobility, morbidity, and mortality will be studied yearly by matching the TMI Population Registry with postal records, cancer registry records, and death certificate data. Because the radiation dose from TMI was extremely small, any increase in morbidity or mortality attributable to the accident would be so small as not to be measurable by present methods; however, adverse health effects as a result of psychological stress may occur. Also, a temporary increase in reporting of disease could occur because of increased surveillance and attention to health.

  19. Technical evaluation report TMI action - NUREG-0737 (II.D.1) relief and safety valve testing for Clinton Power Station Unit 1. (Docket No. 50-461)

    International Nuclear Information System (INIS)

    Burr, T.K.; Magleby, H.L.

    1985-05-01

    Light water reactors operators have experienced a number of occurrences of improper performance by safety and relief valves installed in their primary coolant systems. Because of this, the authors of NUREG-0578 (TMI-2 Lessons Learned Task Force Status Report and Short-Term Recommendations) recommended that programs be developed and completed which would reevaluate the performance capabilities of BWR safety and relief valves. This report has examined the response of the Licensee for the Clinton Power Station, Unit 1 to the requirements of NUREG-0578 and subsequently NUREG-0737 and finds that the Licensee has provided an acceptable response, reconfirming that the General Design Criteria 14, 15 and 30 of Appendix A to 10 CFR-50 have been met

  20. Instructor development program at Three Mile Island

    International Nuclear Information System (INIS)

    Irizarry, C.A.; Jones, J.W.; Knief, R.

    1981-01-01

    The Three Mile Island (TMI) Training Department has prepared and conducted Instructor Development Programs which have upgraded the capabilities of its instructors and provided more uniformity among its diverse efforts. The week-long course was prepared in-house by a staff that combined college teaching experience in both education and technical subjects with strong background in industrial training. Through the first two offerings of the course, twenty-five individuals have participated and eight have served on the course staff

  1. Present status of TMI-2 plant and results of its research

    International Nuclear Information System (INIS)

    Sasaki, Sadaaki; Yokomi, Michiro.

    1987-01-01

    In the accident occurred in the TMI-2 plant on March 28, 1979, the damage was caused in the reactor core, but there scarcely was the effect on the health and safety of general public around the power station. But in USA, it was decided to collect the data on the fuel, decontamination, waste management and so on of this plant and to advance the survey and research on the safety by the analysis and evaluation of the course of the accident mainly by GPUN, EPRI, NRC and DOE. Also in Japan, it was judged that the participation in this research would be useful for improving the reliability of Japanese nuclear power plants hereafter, and the Japan-USA agreement on TMI-2 research and development project was concluded on April 16, 1984. The activity plan in TMI-2 is divided into three stages. Phase 1 is the stage of stabilization, Phase 2 is the stage of taking fuel out, and Phase 3 is the stage of cleaning. At present, Phase 2 - 3 are in progress, and the taking-out and transport of fuel and decontamination are carried out. After finishing Phase 3, the TMI-2 plant is placed in the state of monitoring and preservation, which is scheduled in September, 1988. The final disposal of the plant will be determined thereafter. Decontamination, treatment of contaminated water and wastes, taking-out and transport of fuel, state of the reactor core and others are reported. (Kako, I.)

  2. Three Mile Island Unit 1 Main Steam Line Break Three-Dimensional Neutronics/Thermal-Hydraulics Analysis: Application of Different Coupled Codes

    International Nuclear Information System (INIS)

    D'Auria, Francesco; Moreno, Jose Luis Gago; Galassi, Giorgio Maria; Grgic, Davor; Spadoni, Antonino

    2003-01-01

    A comprehensive analysis of the double ended main steam line break (MSLB) accident assumed to occur in the Babcock and Wilcox Three Mile Island Unit 1 (TMI-1) has been carried out at the Dipartimento di Ingegneria Meccanica, Nucleare e della Produzione of the University of Pisa, Italy, in cooperation with the University of Zagreb, Croatia. The overall activity has been completed within the framework of the participation in the Organization for Economic Cooperation and Development-Committee on the Safety of Nuclear Installations-Nuclear Science Committee pressurized water reactor MSLB benchmark.Thermal-hydraulic system codes (various versions of Relap5), three-dimensional (3-D) neutronics codes (Parcs, Quabbox, and Nestle), and one subchannel code (Cobra) have been adopted for the analysis. Results from the following codes (or code versions) are assumed as reference:1. Relap5/mod3.2.2, beta version, coupled with the 3-D neutron kinetics Parcs code parallel virtual machine (PVM) coupling2. Relap5/mod3.2.2, gamma version, coupled with the 3-D neutron kinetics Quabbox code (direct coupling)3. Relap5/3D code coupled with the 3-D neutron kinetics Nestle code.The influence of PVM and of direct coupling is also discussed.Boundary and initial conditions of the system, including those relevant to the fuel status, have been supplied by Pennsylvania State University in cooperation with GPU Nuclear Corporation (the utility, owner of TMI) and the U.S. Nuclear Regulatory Commission. The comparison among the results obtained by adopting the same thermal-hydraulic nodalization and the coupled code version is discussed in this paper.The capability of the control rods to recover the accident has been demonstrated in all the cases as well as the capability of all the codes to predict the time evolution of the assigned transient. However, one stuck control rod caused some 'recriticality' or 'return to power' whose magnitude is largely affected by boundary and initial conditions

  3. Use of the submerged demineralizer system at Three Mile Island

    International Nuclear Information System (INIS)

    Hofstetter, K.J.; Hitz, C.G.

    1983-01-01

    The Submerged Demineralizer System (SDS) has been used at Three Mile Island-Unit 2 (TMI-2) to process more than 1.5 million gallons of water contaminated as a result of the March, 1979 accident. The SDS has processed approximately 315,000 gallons of water accumulated in tanks in the Auxiliary Building, approximately 650,000 gallons of water that existed in the Reactor Containment Building basement, approximately 90,000 gallons of primary reactor coolant (processed in a bleed and feed mode) and approximately 169,000 gallons of water used in the large scale decontamination of the Reactor Building. During its operation, the SDS has immobilized approximately 340,000 curies of the principal fission products 137 Cs, 134 Cs and 90 Sr on inorganic media (zeolite). Processing summaries and performance evaluations are presented. 12 references, 1 figure, 6 tables

  4. TRMM MICROWAVE IMAGER (TMI) WENTZ OCEAN PRODUCTS V3

    Data.gov (United States)

    National Aeronautics and Space Administration — The TRMM Microwave Imager (TMI) is a 5-channel, dual-polarized, passive microwave radiometer. Microwave radiation is emitted by the Earth's surface and by water...

  5. Financial implications of the accident at Three Mile Island. Oversight hearings before the Committee on Interior and Insular Affairs, House of Representatives, Ninety-Seventh Congress, First Session on financial implications of the accident at Three Mile Island, hearings held in Washington, DC, May 4-5, 1981

    International Nuclear Information System (INIS)

    Anon.

    1981-01-01

    Five panel presentations and a total of 21 witnesses testified at a two-day hearing May 4-5, 1981, in Washington, DC, on the financial consequences of the Three Mile Island (TMI) accident and the economic issues of the cleanup. The committee's goal was to listen to recommendations for government response and to determine the government's proper role and whether legislation is necessary to fulfill that role. Another issue under consideration was the restart of the undamaged unit one. The hearing record includes testimony of witnesses representing the nuclear power industry, environmental groups, and the financial and insurance industries and three appendices with additional materials

  6. Quality Assurance in the removal and transport of the TMI-2 core

    International Nuclear Information System (INIS)

    Hayes, G.R.; Marsden, J.F.

    1988-01-01

    EG ampersand G Idaho, acting on behalf of the US Department of Energy (DOE), is cooperating with the owner of the TMI-2 plant, General Public Utilities Nuclear (GPUN), in the removal and transport of the damaged TMI-2 core to the Idaho National Engineering Laboratory (INEL) near Idaho Falls, Idaho. Quality Assurance (QA) played an important role in the removal and transport of the damaged TMI-2 core. To illustrate, the authors have chosen to discuss some of the important quality assurance techniques utilized in the design, fabrication, acceptance, and use of the three different types of equipment; the core boring machine, the core debris canisters, and the transport casks. Rather than a thorough discussion of the QA aspects of each task, the authors have purposely chosen to present only the key applications of quality assurance principles and methodology unique to each piece of equipment. The intent of this approach is to effectively communicate the importance of ''task teamwork'' in QA

  7. A Brief Review of Past INL Work Assessing Radionuclide Content in TMI-2 Melted Fuel Debris: The Use of 144Ce as a Surrogate for Pu Accountancy

    Energy Technology Data Exchange (ETDEWEB)

    D. L. Chichester; S. J. Thompson

    2013-09-01

    This report serves as a literature review of prior work performed at Idaho National Laboratory, and its predecessor organizations Idaho National Engineering Laboratory (INEL) and Idaho National Engineering and Environmental Laboratory (INEEL), studying radionuclide partitioning within the melted fuel debris of the reactor of the Three Mile Island 2 (TMI-2) nuclear power plant. The purpose of this review is to document prior published work that provides supporting evidence of the utility of using 144Ce as a surrogate for plutonium within melted fuel debris. When the TMI-2 accident occurred no quantitative nondestructive analysis (NDA) techniques existed that could assay plutonium in the unconventional wastes from the reactor. However, unpublished work performed at INL by D. W. Akers in the late 1980s through the 1990s demonstrated that passive gamma-ray spectrometry of 144Ce could potentially be used to develop a semi-quantitative correlation for estimating plutonium content in these materials. The fate and transport of radioisotopes in fuel from different regions of the core, including uranium, fission products, and actinides, appear to be well characterized based on the maximum temperature reached by fuel in different parts of the core and the melting point, boiling point, and volatility of those radioisotopes. Also, the chemical interactions between fuel, fuel cladding, control elements, and core structural components appears to have played a large role in determining when and how fuel relocation occurred in the core; perhaps the most important of these reaction appears to be related to the formation of mixed-material alloys, eutectics, in the fuel cladding. Because of its high melting point, low volatility, and similar chemical behavior to plutonium, the element cerium appears to have behaved similarly to plutonium during the evolution of the TMI-2 accident. Anecdotal evidence extrapolated from open-source literature strengthens this logical feasibility for

  8. Accidents with damage to nuclear core. A perspective for TMI-2

    International Nuclear Information System (INIS)

    Alonso, A.

    1980-01-01

    The most direct consequence of the TMI-2 accident was the destruction of substantial fraction of the fuel element cladding. With the aim of given a certain perspective to that accident, an analysis is made of the causes by which the fuel element clad may lose its integrity. The Windscale, SL-1 and Enrico Fermi accidents constitute important examples to that end. These accidents are analyzed giving special emphasis to those aspects which apear later on at TMI-2. The general consequences of the latter are examined with a certain details, including the social, institutional, technological and economic aspects of the accident. (author)

  9. GHRSST Level 2P European Medspiration TMI SST:1

    Data.gov (United States)

    National Aeronautics and Space Administration — GHRSST-PP L2P data derived using Remote Sensing Systems BMAPS format TMI SSTsub-skin data. Data are downloaded form Remote Sensing Systems every hour to capture the...

  10. Spontaneous abortions after the Three Mile Island nuclear accident: a life table analysis.

    Science.gov (United States)

    Goldhaber, M K; Staub, S L; Tokuhata, G K

    1983-07-01

    A study was conducted to determine whether the incidence of spontaneous abortion was greater than expected near the Three Mile Island (TMI) nuclear power plant during the months following the March 28, 1979 accident. All persons living within five miles of TMI were registered shortly after the accident, and information on pregnancy at the time of the accident was collected. After one year, all pregnancy cases were followed up and outcomes ascertained. Using the life table method, it was found that, given pregnancies after four completed weeks of gestation counting from the first day of the last menstrual period, the estimated incidence of spontaneous abortion (miscarriage before completion of 16 weeks of gestation) was 15.1 per cent for women pregnant at the time of the TMI accident. Combining spontaneous abortions and stillbirths (delivery of a dead fetus after 16 weeks of gestation), the estimated incidence was 16.1 per cent for pregnancies after four completed weeks of gestation. Both incidences are comparable to baseline studies of fetal loss.

  11. Spontaneous abortions after the Three Mile Island nuclear accident: a life table analysis

    International Nuclear Information System (INIS)

    Goldhaber, M.K.; Staub, S.L.; Tokuhata, G.K.

    1983-01-01

    A study was conducted to determine whether the incidence of spontaneous abortion was greater than expected near the Three Mile Island (TMI) nuclear power plant during the months following the March 28, 1979 accident. All persons living within five miles of TMI were registered shortly after the accident, and information on pregnancy at the time of the accident was collected. After one year, all pregnancy cases were followed up and outcomes ascertained. Using the life table method, it was found that, given pregnancies after four completed weeks of gestation counting from the first day of the last menstrual period, the estimated incidence of spontaneous abortion (miscarriage before completion of 16 weeks of gestation) was 15.1 per cent for women pregnant at the time of the TMI accident. Combining spontaneous abortions and stillbirths (delivery of a dead fetus after 16 weeks of gestation), the estimated incidence was 16.1 per cent for pregnancies after four completed weeks of gestation. Both incidences are comparable to baseline studies of fetal loss

  12. Final environmental impact statement for the construction and operation of an independent spent fuel storage installation to store the Three Mile Island Unit 2 spent fuel at the Idaho National Engineering and Environmental Laboratory. Docket Number 72-20

    International Nuclear Information System (INIS)

    1998-03-01

    This Final Environmental Impact Statement (FEIS) contains an assessment of the potential environmental impacts of the construction and operation of an Independent Spent Fuel Storage Installation (ISFSI) for the Three Mile Island Unit 2 (TMI-2) fuel debris at the Idaho National Engineering and Environmental laboratory (INEEL). US Department of Energy-Idaho Operations Office (DOE-ID) is proposing to design, construct, and operate at the Idaho Chemical Processing Plant (ICPP). The TMI-2 fuel debris would be removed from wet storage, transported to the ISFSI, and placed in storage modules on a concrete basemat. As part of its overall spent nuclear fuel (SNF) management program, the US DOE has prepared a final programmatic environmental impact statement (EIS) that provides an overview of the spent fuel management proposed for INEEL, including the construction and operation of the TMI-2 ISFSI. In addition, DOE-ID has prepared an environmental assessment (EA) to describe the environmental impacts associated with the stabilization of the storage pool and the construction/operation of the ISFSI at the ICPP. As provided in NRC's NEPA procedures, a FEIS of another Federal agency may be adopted in whole or in part in accordance with the procedures outlined in 40 CFR 1506.3 of the regulations of the Council on Environmental Quality (CEQ). Under 40 CFR 1506.3(b), if the actions covered by the original EIS and the proposed action are substantially the same, the agency adopting another agency's statement is not required to recirculate it except as a final statement. The NRC has determined that its proposed action is substantially the same as actions considered in DOE's environmental documents referenced above and, therefore, has elected to adopt the DOE documents as the NRC FEIS

  13. Cleanup of TMI-2 demineralizer resins

    International Nuclear Information System (INIS)

    Bond, W.D.; King, L.J.; Knauer, J.B.; Hofstetter, K.J.; Thompson, J.D.

    1985-01-01

    Radiocesium is being removed from Demineralizers A and B (DA and DB by a process that was developed from laboratory tests on small samples of resin from the demineralizers. The process was designed to elute the radiocesium from the demineralizer resins and then to resorb it onto the zeolite ion exchangers contained in the Submerged Demineralizer System (SDS). The process was also required to limit the maximum cesium activities in the resin eluates (SDS feeds) so that the radiation field surrounding the pipelines would not be excessive. The process consists of 17 stages of batch elution. In the initial stage, the resin is contacted with 0.18 M boric acid. Subsequent stages subject the resin to increasing concentrations of sodium in NaH 2 BO 3 -H 3 BO 3 solution (total B = 0.35 M) and then 1 M sodium hydroxide in the final stages. Results on the performance of the process in the cleanup of the demineralizers at TMI-2 are compared to those obtained from laboratory tests with small samples of the DA and DB resins. To date, 15 stages of batch elution have been completed on the demineralizers at TMI-2 which resulted in the removal of about 750 Ci of radiocesium from DA and about 3300 Ci from DB

  14. Use of photographic film to estimate exposure near the Three Mile Island Nuclear Power Station

    International Nuclear Information System (INIS)

    Shuping, R.E.

    1981-02-01

    This report documents the methodology and results of a Bureau of Radiological Health study of the use of photographic film samples for estimating exposure levels near the Three Mile Island nuclear power station. The study was conducted to provide an independent assessment of the radiation levels near TMI following the accident on March 28, 1979

  15. Limits on the Secular Drift of the TMI Calibration

    Science.gov (United States)

    Wilheit, T. T.; Farrar, S.; Jones, L.; Santos-Garcia, A.

    2012-12-01

    Data from the TRMM Microwave Imager (TMI) can be applied to the problem of determining the trend in oceanic precipitation over more than a decade. It is thus critical to know if the calibration of the instrument has any drift over this time scale. Recently a set of Windsat data with a self-consistent calibration covering July 2005 through June of 2006 and all of 2011 has become available. The mission of Windsat, determining the feasibility of measuring oceanic wind speed and direction, requires extraordinary attention to instrument calibration. With TRMM being in a low inclination orbit and Windsat in a near polar sun synchronous orbit, there are many observations coincident in space and nearly coincident in time. A data set has been assembled where the observations are averaged over 1 degree boxes of latitude and longitude and restricted to a maximum of 1 hour time difference. University of Central Florida (UCF) compares the two radiometers by computing radiances based on Global Data Assimilation System (GDAS) analyses for all channels of each radiometer for each box and computing double differences for corresponding channels. The algorithm is described in detail by Biswas et al., (2012). Texas A&M (TAMU) uses an independent implementation of GDAS-based algorithm and another where the radiances of Windsat are used to compute Sea Surface Temperature, Sea Surface Wind Speed, Precipitable Water and Cloud Liquid Water for each box. These are, in turn, used to compute the TMI radiances. These two algorithms have been described in detail by Wilheit (2012). Both teams apply stringent filters to the boxes to assure that the conditions are consistent with the model assumptions. Examination of both teams' results indicates that the drift is less than 0.04K over the 5 ½ year span for the 10 and 37 GHz channels of TMI. The 19 and 21 GHz channels have somewhat larger differences, but they are more influenced by atmospheric changes. Given the design of the instruments, it is

  16. Life stage differences in resident coping with restart of the Three Mile Island nuclear generating facility

    International Nuclear Information System (INIS)

    Prince-Embury, S.; Rooney, J.F.

    1990-01-01

    A study of residents who remained in the vicinity of Three Mile Island (TMI) immediately following the restart of the nuclear generating plant revealed that older residents employed a more emotion-focused coping style in the face of this event than did younger residents. Coping style was, however, unrelated to the level of psychological symptoms for these older residents, whereas demographic variables were related. Among younger residents, on the other hand, coping style was related to the level of psychological symptoms, whereas demographic variables were not. Among younger residents, emotion-focused coping was associated with more symptoms and problem-focused coping was associated with fewer symptoms, contradicting previous findings among TMI area residents

  17. The effect of increased CRA trip insertion times for TMI

    International Nuclear Information System (INIS)

    Irani, A.; Link, J.; Trikouos, N.

    1996-01-01

    In recent years, testing of control rod assembly (CRA) drop times at TMI has resulted in a few rods that have failed to meet the Technical Specification (TS) acceptance criteria of 1.66 seconds to 3/4 inserted. Crud deposition was determined to be the cause of the slow rod insertion times. Corrective actions included increasing lithium concentration and increasing the frequency and extent of exercising the control rod drive mechanisms. However, after one cycle of operation, it was determined that these measures were not fully successful in retarding the crud buildup. Consequently, the safety significance of rods potentially having a longer drop time than the TS limit was evaluated. The analyses in Chapter 14 of the TMI FSAR demonstrate the ability of the plant to mitigate the consequences of postulated accidents without undue hazard to the health and safety of the public. To determine the safety consequences of the longer rod drop times, a reanalysis of some limiting accidents had to be done using the RETRAN, RELAP5 and TRAC computer codes. The safety evaluation concluded that a 3.0 second rod drop time would be acceptable because all of the event acceptance criteria were met. A permanent resolution of the problem is the replacement of the existing thermal barriers with new open flow path thermal barriers. Thermal barriers on half the CRAs at TMI have been replaced to date

  18. Applicability of health physics lessons learned from the Three Mile Island Unit 2 accident to the Fukushima Daiichi accident.

    Science.gov (United States)

    Bevelacqua, J J

    2012-02-01

    The TMI-2 and Fukushima Daiichi accidents appear to be dissimilar because they involve different reactor types. However, the health physics related lessons learned from TMI-2 are applicable, and can enhance the Fukushima Daiichi recovery effort. Copyright © 2011 Elsevier Ltd. All rights reserved.

  19. Indonesia sea surface temperature from TRMM Microwave Imaging (TMI) sensor

    Science.gov (United States)

    Marini, Y.; Setiawan, K. T.

    2018-05-01

    We analysis the Tropical Rainfall Measuring Mission's (TRMM) Microwave Imager (TMI) data to monitor the sea surface temperature (SST) of Indonesia waters for a decade of 2005-2014. The TMI SST data shows the seasonal and interannual SST in Indonesian waters. In general, the SST average was highest in March-May period with SST average was 29.4°C, and the lowest was in June – August period with the SST average was 28.5°C. The monthly SST average fluctuation of Indonesian waters for 10 years tends to increase. The lowest SST average of Indonesia occurred in August 2006 with the SST average was 27.6° C, while the maximum occurred in May 2014 with the monthly SST average temperature was 29.9 ° C.

  20. Clarification of TMI action plan requirements. Requirements for emergency response capability

    International Nuclear Information System (INIS)

    1983-01-01

    This document, Supplement 1 to NUREG-0737, is a letter from D. G. Eisenhut, Director of the Division of Licensing, NRR, to licensees of operating power reactors, applicants for operating licenses, and holders of construction permits forwarding post-TMI requirements for emergency response capability which have been approved for implementation. On October 30, 1980, the NRC staff issued NUREG-0737, which incorporated into one document all TMI-related items approved for implementation by the Commission at that time. In this NRC report, additional clarification is provided regarding Safety Parameter Display Systems, Detailed Control Room Design Reviews, Regulatory Guide 1.97 (Revision 2) - Application to Emergency Response Facilities, Upgrade of Emergency Operating Procedures, Emergency Response Facilities, and Meteorological Data

  1. Hospital organizational response to the nuclear accident at Three Mile Island: implications for future-oriented disaster planning

    International Nuclear Information System (INIS)

    Maxwell, C.

    1982-01-01

    The 1979 nuclear accident at Three Mile Island (TMI) near Harrisburg, Pennsylvania, caused severe organizational problems for neighboring health care institutions. Dauphin County, just north of TMI, contained four hospitals ranging in distance from 9.5 to 13.5 miles from the stricken plant. Crash plans put into effect within 48 hours of the initial incident successfully reduced hospital census to below 50 per cent of capacity, but retained bedridden and critically ill patients within the risk-zone. No plans existed for area-wide evacuation of hospitalized patients. Future-oriented disaster planning should include resource files of host institution bed capacity and transportation capabilities for the crash evacuation of hospitalized patients during non-traditional disasters

  2. Fuel models and results from the TRAC-PF1/MIMAS TMI-2 accident calculation

    International Nuclear Information System (INIS)

    Schwegler, E.C.; Maudlin, P.J.

    1983-01-01

    A brief description of several fuel models used in the TRAC-PF1/MIMAS analysis of the TMI-2 accident is presented, and some of the significant fuel-rod behavior results from this analysis are given. Peak fuel-rod temperatures, oxidation heat production, and embrittlement and failure behavior calculated for the TMI-2 accident are discussed. Other aspects of fuel behavior, such as cladding ballooning and fuel-cladding eutectic formation, were found not to significantly affect the accident progression

  3. TMI-2: Unique waste management technology

    International Nuclear Information System (INIS)

    Bixby, W.W.; Young, W.R.; Grant, P.J.

    1987-01-01

    The 1979 accident at TMI-2 severely damaged the reactor core and contaminated more than a million gallons of water. Subsequent activities created another million gallons of water. The damaged reactor core represented a new waste form and cleanup of the contaminated water and system components created other new waste forms requiring creative approaches to waste management. This paper focuses on technologies that were developed specific to fuel waste management, core debris shipping, processing accident generated water, and disposal of the resultant waste forms

  4. Investigation: revelations about Three Mile Island disaster raise doubts over nuclear plant safety: a special facing south investigation by Sue Sturgis.

    Science.gov (United States)

    Sturgis, Sue

    2009-01-01

    A series of mishaps in a reactor at the Three Mile Island (TMI) nuclear plant led to the 1979 meltdown of almost half the uranium fuel and uncontrolled releases of radiation into the air and surrounding Susquehanna River. It was the single worst disaster ever to befall the U.S. nuclear power industry. Health physics technician Randall Thompson's story about what he witnessed while monitoring radiation there after the incident is being publicly disclosed for the first time. It is supported by a growing body of evidence and it contradicts the U.S. government's contention that the TMI accident posed no threat to the public. Thompson and his wife, a nuclear health physicist who also worked at TMI in the disaster's wake, warn that the government's failure to acknowledge the full scope of the disaster is leading officials to underestimate the risks posed by a new generation of nuclear power plants.

  5. Incidence of thyroid cancer surrounding Three Mile Island nuclear facility: the 30-year follow-up.

    Science.gov (United States)

    Levin, Roger J; De Simone, Nicole F; Slotkin, Jaime F; Henson, Baker L

    2013-08-01

    Original data reported a potential increased incidence of thyroid cancer surrounding the Three Mile Island (TMI) nuclear facility. A causal link to the accident, however, was indeterminate. Our objective was to determine if data 30 years later will change original conclusions, explore thyroid cancer incidence rates near nuclear power plants, and better understand effects of chronic low level radiation. Retrospective cross-sectional study. Retrospective data for specific Pennsylvania counties were provided by the Pennsylvania Cancer Registry Dataset for thyroid cancer using the Epidemiological Query and Mapping System search engine. Our study examines thyroid cancer incidence from 1985 through 2009 analyzed by year, county, and age. Thirty years after the TMI accident, an increased incidence of thyroid cancer is seen in counties south of TMI and in high-risk age groups. The average incidence rates from 1990 through 2009 were greater than expected in York, Lancaster, Adams, and Chester Counties. Thyroid cancer incidence since the TMI accident was greater than expected in the counties analyzed when compared to local and national population growth. This supports a link to chronic low level radiation exposure and thyroid cancer development. Despite these findings, a direct correlation to the accident remains uncertain as incidence rates may coincide with other factors, and original data were limited. © 2013 The American Laryngological, Rhinological and Otological Society, Inc.

  6. Safety of Ikata Nuclear Power Station from the accident of Three Mile Island

    International Nuclear Information System (INIS)

    Nonaka, Hiroshi

    1979-01-01

    The leak of radioactive substances occurred on March 28, 1979, in the No. 2 plant of Three Mile Island Nuclear Power Station, and this accident must be put to use to prevent similar accidents and to secure safety hereafter in the nuclear power stations being operated in Japan. In the TMI accident, too many problems concerning the operation management seemed to exist in a series of events. In this paper, a few matters related to the TMI accident among the aspects of the operation management in Ikata Nuclear Power Station are reported. As the problems of operation management, it is considered that the operation of the TMI plant was continued as the exit valve of auxiliary feed line was closed, that it took long time to close the root valve for a pressurizer relief valve manually, and that the ECCS was stopped manually. In TMI, the abnormal phenomenon of losing main feed water has occurred 6 times since the attainment of criticality in March, 1978, and the opening and sticking of pressurizer relief valves occurred at least twice in about 150 times of their actuation in the nuclear reactors designed by Babcock and Wilcox Co. In Ikata Nuclear Power Station, these problems are detected early and the suitable measures are taken immediately, therefore it never happens to continue the operation as the problems are left as they are. It is not conceivable that similar troubles occur many times. (Kako, I.)

  7. In-vessel inspection before head removal: TMI II: Phase I. (Conceptual development)

    International Nuclear Information System (INIS)

    Calloway, N.E.; Greenlee, D.W.; Lawrence, G.R.; Paglia, A.L.; Piatt, T.D.; Tucker, B.A.

    1981-08-01

    The objective of the task is to provide for an internal inspection of the reactor vessel and the fuel assemblies prior to reactor vessel head removal. Because the degree of damage to equipment and fuel in the TMI-II reactor is not precisely known, it is important that as much information as possible be obtained on present conditions inside the reactor. This information will serve to benchmark the various analyses already completed or underway and will also guide the development of programs to obtain more information on the TMI-II core damage. In addition, the early look will provide data for planning the reactor disassembly program

  8. United States position on severe accidents

    International Nuclear Information System (INIS)

    Ross, D.F.

    1988-01-01

    The United States policy on severe accidents was published in 1985 for both new plant applications and for existing plants. Implementation of this policy is in progress. This policy, aided by a related safety goal policy and by analysis capabilities emerging from improved understanding of accident phenomenology, is viewed as a logical development from the pioneering work in the WASH-1400 Reactor Safety Study published by the United States Nuclear Regulatory Commission (NRC) in 1975. This work provided an estimate of the probability and consequences of severe accidents which, prior to that time, had been mostly evaluated by somewhat arbitrary assumptions dating back 30 years. The early history of severe accident evaluation is briefly summarized for the period 1957-1979. Then, the galvanizing action of Three Mile Island Unit 2 (TMI-2) on severe accident analysis, experimentation and regulation is reviewed. Expressions of US policy in the form of rulemaking, severe accident policy, safety research, safety goal policy and court decisions (on adequacy of safety) are discussed. Finally, the NRC policy as of March 1988 is stated, along with a prospective look at the next few years. (author). 19 refs

  9. Status of safety issues at licensed power plants: TMI Action Plan requirements; unresolved safety issues; generic safety issues; other multiplant action issues

    International Nuclear Information System (INIS)

    1993-12-01

    As part of ongoing US Nuclear Regulatory Commission (NRC) efforts to ensure the quality and accountability of safety issue information, the NRC established a program for publishing an annual report on the status of licensee implementation and NRC verification of safety issues in major NRC requirements areas. This information was initially compiled and reported in three NUREG-series volumes. Volume 1, published in March 1991, addressed the status of Three Mile Island (TMI) Action Plan Requirements. Volume 2, published in May 1991, addressed the status of unresolved safety issues (USIs). Volume 3, published in June 1991, addressed the implementation and verification status of generic safety issues (GSIs). The first annual supplement, which combined these volumes into a single report and presented updated information as of September 30, 1991, was published in December 1991. The second annual supplement, which provided updated information as of September 30, 1992, was published in December 1992. Supplement 2 also provided the status of licensee implementation and NRC verification of other multiplant action (MPA) issues not related to TMI Action Plan requirements, USIs, or GSIs. This third annual NUREG report, Supplement 3, presents updated information as of September 30, 1993. This report gives a comprehensive description of the implementation and verification status of TMI Action Plan requirements, safety issues designated as USIs, GSIs, and other MPAs that have been resolved and involve implementation of an action or actions by licensees. This report makes the information available to other interested parties, including the public. Additionally, this report serves as a follow-on to NUREG-0933, ''A Prioritization of Generic Safety Issues,'' which tracks safety issues until requirements are approved for imposition at licensed plants or until the NRC issues a request for action by licensees

  10. Health-related economic costs of the Three-Mile Island accident.

    Science.gov (United States)

    Hu, T W; Slaysman, K S

    1984-01-01

    On March 1979, a nuclear power station at Three-Mile Island (TMI) near Harrisburg, Pennsylvania, had a major breakdown. During the two-week period of the accident, about 150,000 residents were evacuated for reasons associated with safety and health. Many residents during and after the accident, regardless of whether they left or stayed, made mental and physical adjustments due to this accident. This paper is to estimate the economic costs incurred by individuals or communities as a result of a change in physical or mental health status and/or a change in health care services due to the TMI accident. The findings indicate that stress symptoms caused by the accident did affect the health-related behaviors of area residents. Of the costs examined, the economic costs of work days lost and physician visits are the largest cost items. There were some increases in consumption of alcohol, cigarettes, and tranquilizers immediately following the accident.

  11. Combined TRMM Microwave Imager (TMI) and Precipitation Radar (PR) Gridded Orbital Data Set (G2A12) V6

    Data.gov (United States)

    National Aeronautics and Space Administration — The TRMM Microwave Imager (TMI) Gridded Orbital rainfall data, a special product derived from the TRMM standard product, TMI rain profile (2A-12), and mapped to a...

  12. Aerial radiological survey of the Three Mile Island Nuclear Station and surrounding area, Middletown, Pennsylvania

    International Nuclear Information System (INIS)

    Colton, D.P.

    1983-08-01

    An aerial radiological survey was performed over the area surrounding the Three Mile Island Nuclear Station during October 26 to 30, 1982. The survey covered an 82-square-kilometer area centered on the nuclear plant and encompassed the communities of Middletown, York Haven, Goldsboro and Royalton, Pennsylvania. The highest radiation exposure rates, up to a maximum of 200 microroentgens per hour (μR/h), were inferred from data measured directly over the TMI facilities. This detected radiation was due to the presence of cobalt-58, cobalt-60 and cesium-137, which was consistent with normal plant operations. Similar activity is routinely observed in aerial surveys over nuclear power plants which have been or are presently in an operational mode. For the remainder of the survey area, the inferred radiation exposure rates varied from 6 to 14 μR/h. The reported exposure rate values include an estimated cosmic ray contribution of 3.7 μR/h. Ground-based measurements, conducted during the time of the aerial survey, were compared to the aerial results. Pressurized ionization chamber readings and a group of soil samples were acquired at several locations within the survey area, along the river banks upstream and downstream of the survey area, and at the ground-based locations used for a previous aerial survey which was conducted in 1976. The exposure rate values obtained from these measurements were in agreement with the corresponding aerial data. With the exception of the activity observed within the TMI facilities, no evidence of any contamination which might have occurred as a result of past reactor operations or the 1979 TMI Unit 2 accident was detected from the aerial survey data. This was further supported by the results of the soil sample analyses and the comparison with the 1976 aerial survey data. 7 references, 12 figures, 4 tables

  13. A reevaluation of cancer incidence near the Three Mile Island nuclear plant: the collision of evidence and assumptions.

    Science.gov (United States)

    Wing, S; Richardson, D; Armstrong, D; Crawford-Brown, D

    1997-01-01

    Previous studies concluded that there was no evidence that the 1979 nuclear accident at Three Mile Island (TMI) affected cancer incidence in the surrounding area; however, there were logical and methodological problems in earlier reports that led us to reconsider data previously collected. A 10-mile area around TMI was divided into 69 study tracts, which were assigned radiation dose estimates based on radiation reading and models of atmospheric dispersion. Incident cancers from 1975 to 1985 were ascertained from hospital records and assigned to study tracts. Associations between accident doses and incidence rates of leukemia, lung cancer, and all cancer were assessed using relative dose estimates calculated by the earlier investigators. Adjustments were made for age, sex, socioeconomic characteristics, and preaccident variation in incidence. Considering a 2-year latency, the estimated percent increase per dose unit +/- standard error was 0.020 +/- 0.012 for all cancer, 0.082 +/- 0.032 for lung cancer, and 0.116 +/- 0.067 for leukemia. Adjustment for socioeconomic variables increased the estimates to 0.034 +/- 0.013, 0.103 +/- 0.035, and 0.139 +/- 0.073 for all cancer, lung cancer, and leukemia, respectively. Associations were generally larger considering a 5-year latency, but were based on smaller numbers of cases. Results support the hypothesis that radiation doses are related to increased cancer incidence around TMI. The analysis avoids medical detection bias, but suffers from inaccurate dose classification; therefore, results may underestimate the magnitude of the association between radiation and cancer incidence. These associations would not be expected, based on previous estimates of near-background levels of radiation exposure following the accident.

  14. A reevaluation of cancer incidence near the Three Mile Island nuclear plant: The collision of evidence and assumptions

    International Nuclear Information System (INIS)

    Wing, S.; Richardson, D.; Armstrong, D.; Crawford-Brown, D.

    1997-01-01

    Previous studies concluded that there was no evidence that the 1979 nuclear accident at Three Mile Island (TMI) affected cancer incidence in the surrounding area; however, there were logical and methodological problems in earlier reports that led us to reconsider data previously collected. A 10-mile area around TMI was divided into 69 study tracts, which were assigned radiation dose estimates based on radiation readings and models of atmospheric dispersion. Incident cancers from 1975 to 1985 were ascertained from hospital records and assigned to study tracts. Associations between accident doses and incidence rates of leukemia, lung cancer, and all cancer were assessed using relative dose estimates calculated by the earlier investigators. Adjustments were made for age, sex, socioeconomic characteristics, and preaccident variation in incidence. Considering a 2-year latency, the estimated percent increase per dose unit ± standard error was 0.020 ± 0.012 for all cancer, 0.082 ± 0.032 for lung cancer, and 0.116 ± 0.067 for leukemia. Adjustment for socioeconomic variables increased the estimates to 0.034 ± 0.013, 0.103 ± 0.035, and 0.139 ± 0.073 for all cancer, lung cancer, and leukemia, respectively. Associations were generally larger considering a 5-year latency, but were based on smaller numbers of cases. Results support the hypothesis that radiation doses are related to increased cancer incidence around TMI. The analysis avoids medical detection bias, but suffers from inaccurate dose classification; therefore, results may underestimate the magnitude of the association between radiation and cancer incidence. These associations would not be expected, based on previous estimates of near-background levels of radiation exposure following the accident. 35 refs., 3 tabs

  15. Status of safety issues at licensed power plants: TMI Action Plan requirements, unresolved safety issues, generic safety issues, other multiplant action issues

    International Nuclear Information System (INIS)

    1992-12-01

    This report is to provide a comprehensive description of the implementation and verification status of Three Mile Island (TMI) Action Plan requirements, safety issues designated as Unresolved Safety Issues (USIs), Generic Safety Issues(GSIs), and other Multiplant Actions (MPAs) that have been resolved and involve implementation of an action or actions by licensees. This report makes the information available to other interested parties, including the public. An additional purpose of this NUREG report is to serve as a follow-on to NUREG-0933, ''A Prioritization of Generic Safety Issues,'' which tracks safety issues up until requirements are approved for imposition at licensed plants or until the NRC issues a request for action by licensees

  16. Drill core investigations from the TMI-2 pressure vessel. Final report

    International Nuclear Information System (INIS)

    Sturm, D.; Katerbau, K.H.; Maile, K.; Ruoff, H.

    1994-01-01

    For the evaluation of the results obtained in TMI-2 VIP and for the preparation of the continuing discussion in the OECD and of research measures in the national sphere but also for the appraisal of the effect of the results to date on safety philosophy and safety research in Germany, the present research project, inter alia, was commenced. In content was: a) Furtherance of the OECD-NEA-TMI-2 Vessel Investigation Project in dealing with the testing programme by active collaboration in the Programme Review Group, by participation in ad-hoc meetings on the question of specimen extraction, by advice on the conduct of metallographic, metallurgical and mechanical investigations on the specimens from the RPV bottom head and by assessment of the findings. b) Investigation of specimens from the bottom head of the TMI-2 reactor pressure vessel. c) Investigation of specimens from archive material. The investigations reach the widely agreed conclusion that during the accident a hot spot developed in the bottom head of the reactor in which for a time of about 30 minutes a maximum temperature of some 1100 C or greater than 900 C prevailed. Around this zone there is a region with temperatures higher than ca. 730 C (A 1 ) whilst the predominant portion of the head had not been heated beyond the 1 temperature. (orig.) [de

  17. Environmental measurements during the TMI-2 accident

    International Nuclear Information System (INIS)

    Hull, A.P.

    1988-01-01

    Although the environmental consequences of the TMI accident were relatively insignificant, it was a major test of the ability of the involved state and federal radiological agencies to make a coordinated environmental monitoring response. This was accomplished largely on an ad hoc basis under the leadership of DOE. With some fine tuning, it is the basis for today's integrated FRMAP monitoring plan, which would be put into operation should another major accident occur at a US nuclear facility

  18. Three Mile Island nuclear reactor accident of March 1979. Environmental radiation data: Volume V. A report to the President's Commission on the Accident at Three Mile Island

    International Nuclear Information System (INIS)

    Bretthauer, E.W.; Grossman, R.F.; Thome, D.J.; Smith, A.E.

    1981-03-01

    This report contains a listing of environmental radiation monitoring data collected in the vicinity of Three Mile Island (TMI) following the March 28, 1979 accident. These data were collected by the EPA, NRC, DOE, HHS, the Commonwealth of Pennsylvania, or the Bethlehem Steel Corporation. This volume consists of the following 2 volumes: Table 16 Summary of Metropolitan Edison Company (Met-Ed) sampling and analytical procedures; and Table 17 Computer printout of data collected by Met-Ed

  19. Review of the TMI-2 accident evaluation and vessel investigation projects

    Energy Technology Data Exchange (ETDEWEB)

    Ladekarl Thomsen, Knud

    1998-03-01

    The results of the TMI-2 Accident Evaluation Programme and the Vessel Investigation Project have been reviewed as part of a literature study on core meltdown and in-vessel coolability. The emphasis is placed on the late phase melt progression, which is of special relevance to the NKS-sponsored RAK-2.1 project on Severe Accident Phenomenology. The body of the report comprises three main sections, The TMI-2 Accident Scenario, Core Region and Relocation Path Investigations, and Lower Head Investigations. In the final discussion, the lower head gap formation mechanism is explained in terms of thermal contraction and fracturing of the debris crust. This model seems more plausible than the MAAP model based on creep expansion of the lower head. (au) 1 tab., 33 ills., 31 refs.

  20. TMI-2 Core Shipping Preparations

    International Nuclear Information System (INIS)

    Ball, L.J.; Barkanic, R.J.; Conaway, W.T. II; Schmoker, D. S.; Post, Roy G.

    1988-01-01

    Shipping the damaged core from the Unit 2 reactor of Three Mile Island Nuclear Power Station near Harrisburg, PA, to the Idaho National Engineering Laboratory near Idaho Falls, ID, required development and implementation of a completely new spent fuel transportation system. This paper describes of the equipment developed, the planning and activities used to implement the hard-ware-systems into the facilities, and the planning involved in making the rail shipments. It also includes a summary of recommendations resulting from this experience. (author)

  1. Investigation into information flow during the accident at Three Mile Island

    International Nuclear Information System (INIS)

    1981-01-01

    This report was prepared in response to a request from NRC Chairman Ahearne that directed the Office of Inspection and Enforcement to resume its investigation of information flow during the accident at Three Mile Island (TMI) that occurred on March 28, 1979. This investigation was resumed on March 21, 1980. The transfer of information among individuals, agencies, and personnel from Metropolitan Edison was analyzed to ascertain what knowledge was held by various individuals of the specific events, parameters, and systems during the accident at TMI. Maximum use was made of existing records, and additional interviews were conducted to clarify areas that had not been pursued during earlier investigations. Although the passage of time between the accident and post-accident interviews hampered precise recollections of events and circumstances, the investigation revealed that information was not intentionally withheld during the accident and that the system for effective transfer of information was inadequate during the accident

  2. Dispositional and situational variables related to evacuation at Three Mile Island

    International Nuclear Information System (INIS)

    Miller, I.S.

    1981-01-01

    The purpose of this study was to explore some of the factors influential in local residents' evacuating or remaining in the Three Mile Island area during the nuclear power plant accident of March, 1979. Investigated variables included individuals' behavioral dispositions to attend or to avoid threatening stimuli as well as situational concerns related to demographic characteristics and subjective experience. Investigation of situational variables also probed respondents' concerns about accident-related fears. Two main relationships were investigated. The first hypothesized that positive relationships existed both between dispositional attention to threat and evacuation and between dispositional avoidance of threat and remaining. The second investigation task of the research explored evacuation-related situational variables in regard to individuals' awareness of potential danger at TMI. No support was found for the hypothesized relationships between evacuation and dispositions relative to threat. Situational variables significantly related to evacuation included: specific directives to evacuate the area; disruption of telephone service during the week of the accident; and household proximity to TMI

  3. Differential paths to activism: a study of social movement organizations in Three Mile Island communities

    International Nuclear Information System (INIS)

    Cable, S.M.

    1985-01-01

    This project compares political activists from four community protest organizations in Three Mile Island (TMI) communities that were formed as a response of the March 1979 accident at the TMI nuclear power plant. These organizations constituted four separate groups of activists concerned with the same set of grievances. The purpose of the study was to compare the activists across groups to assess differential paths to activism. The data were gathered over a three-year period from March 1979 to March 1982 and included monthly newsletters published by the organizations, newspaper accounts of relevant events; and a systematic survey of 149 of the most active participants. The thesis of differential paths to activism was supported by the data; two relatively distinct paths were found to dominate the TMI communities. In the path that dominated in communities within five miles of the plant, activists tended to be older, more conservative, and less ideologically inclined to protest prior to the accident. In the path to activism that dominated in communities further from the plant site, activists tended to be younger, more liberal, and more experienced in protests

  4. Markkinointiviestinnän kanavien kartoittaminen Tmi Kalikoolle

    OpenAIRE

    Kaikkonen, Päivi

    2011-01-01

    Opinnäytetyön toimeksiantajana oli tamperelainen lastenvaatteita valmistava yritys Tmi Kalikoo. Työn tarkoituksena oli selvittää, mitkä markkinointiviestinnän kanavat olisivat yritykselle sopivia. Päämääränä oli uusien asiakkaiden tavoittaminen. Työssä tuli ottaa huomioon yrityksen vähäiset resurssit. Työn teoreettisena viitekehyksenä käytettiin yleistä markkinoinnin ja markkinointiviestinnän kirjallisuutta sekä internetmarkkinointiin keskittyvää kirjallisuutta. Toimeksiantajalta saatiin ...

  5. Summary of TMI-2 data bases

    International Nuclear Information System (INIS)

    Brower, R.W.

    1987-09-01

    This report summarizes seven major data base products produced by the Data Reduction and qualification Section of the TMI-2 Accident Evaluation Program. The purpose and a brief description of data base structure are presented in the introductory section, together with rational involved in selection of data base media. Major emphasis in the report is placed in more detailed examinations of four personal computer data bases which utilize an INEL developed data base management system, SAGE. Content of each data base is described, the current development status is defined and future activity associated with each dynamic structures is outlined

  6. TMI-2 core debris analytical methods and results

    International Nuclear Information System (INIS)

    Akers, D.W.; Cook, B.A.

    1984-01-01

    A series of six grab samples was taken from the debris bed of the TMI-2 core in early September 1983. Five of these samples were sent to the Idaho National Engineering Laboratory for analysis. Presented is the analysis strategy for the samples and some of the data obtained from the early stages of examination of the samples (i.e., particle size-analysis, gamma spectrometry results, and fissile/fertile material analysis)

  7. Status of safety issues at licensed power plants: TMI Action Plan requirements, unresolved safety issues, generic safety issues, other multiplant action issues. Supplement 4

    International Nuclear Information System (INIS)

    1994-12-01

    As part of ongoing US Nuclear Regulatory Commission (NRC) efforts to ensure the quality and accountability of safety issue information, the NRC established a program for publishing an annual report on the status of licensee implementation and NRC verification of safety issues in major NRC requirements areas. This information was initially compiled and reported in three NUREG-series volumes. Volume 1, published in March 1991, addressed the status of Three Mile Island (TMI) Action Plan Requirements. Volume 2, published in May 1991, addressed the status of unresolved safety issues (USIs). Volume 3, published in June 1991, addressed the implementation and verification status of generic safety issues (GSIs). The first annual supplement, which combined these volumes into a single report and presented updated information as of September 30, 1991, was published in December 1991. The second annual supplement, which provided updated information as of September 30, 1992, was published in December 1992. Supplement 2 also provided the status of licensee implementation and NRC verification of other multiplant action (MPA) issues not related to TMI Action Plan requirements, USIs, or GSIs. Supplement 3 gives status as of September 30, 1993. This annual report, Supplement 4, presents updated information as of September 30, 1994. This report gives a comprehensive description of the implementation and verification status of TMI Action Plan requirements, safety issues designated as USIs, GSIs, and other MPAs that have been resolved and involve implementation of an action or actions by licensees. This report makes the information available to other interested parties, including the public. Additionally, this report serves as a follow-on to NUREG-0933, ''A Prioritization of Generic Safety Issues,'' which tracks safety issues until requirements are approved for imposition at licensed plants or until the NRC issues a request for action by licensees

  8. Cancer incidence among residents of the Three Mile Island accident area: 1982-1995.

    Science.gov (United States)

    Han, Yueh-Ying; Youk, Ada O; Sasser, Howell; Talbott, Evelyn O

    2011-11-01

    The Pennsylvania Department of Health established a registry of the Three Mile Island (TMI) nuclear power plant accident in 1979. Over 93% of the population present on the day of the accident within a 5-mile radius was enrolled and interviewed. We used the registry to investigate the potential cancer risk from low-dose radiation exposure among the TMI population. Cancer incidence data among the TMI cohort were available from 1982 to 1995. Because more than 97% of the population were white and few cancer cases were reported for those younger than 18 years of age, we included whites of age 18 years and older (10,446 men and 11,048 women) for further analyses. Cox regression models were used to estimate the relative risk (RR) per 0.1 mSv and 95% confident interval (CI) of cancer by radiation-related exposures. The cancers of interest were all malignant neoplasms, cancer of bronchus, trachea, and lung, cancer of lymphatic and hematopoietic tissues, leukemia, and female breast. Among men and women, there was no evidence of an increased risk for all malignant neoplasms among the TMI cohort exposed to higher maximum and likely γ radiation (RR=1.00, 95% CI=0.97, 1.01 and RR=0.99, 95% CI=0.94, 1.03, respectively) after adjusting for age, gender, education, smoking, and background radiation. Elevation in risk was noted for cancer of the bronchus, trachea, and lung in relation to higher background radiation exposure (RR=1.45, 95% CI=1.02-2.05 at 8.0-8.8 μR/h compared to 5.2-7.2 μR/h). An increased risk of leukemia was found among men exposed to higher maximum and likely γ radiation related to TMI exposure during the ten days following the accident (RR=1.15, 95% CI=1.04, 1.29 and RR=1.36, 95% CI=1.08, 1.71, respectively). This relationship was not found in women. Increased cancer risks from low-level radiation exposure within the TMI cohort were small and mostly statistically non-significant. However, additional follow-up on this population is warranted, especially to

  9. Summary of the consequences for safety which result from the Three-Mile-Island accident

    International Nuclear Information System (INIS)

    Smidt, D.

    1982-01-01

    The paper focusses on the Three-Mile-Island (TMI) accident in terms of reactor safety, and describes the first stage of the event's course (the first 2 hours and 18 minutes), the second stage (up to 16 hours after accident onset) and the stage till ultimate transition to stationary cooling. Conclusions are drawn for plant design and control room concepts. In conclusion, problems of staff training for critical situations are discussed. (HAG) [de

  10. Status of safety issues at licensed power plants: TMI action plan requirements, unresolved safety issues, generic safety issues

    International Nuclear Information System (INIS)

    1991-12-01

    As part of ongoing US Nuclear Regulatory Commission (NRC) efforts to ensure the quality and accountability of safety issue information, a program was established whereby an annual NUREG report would be published on the status of licensee implementation and NRC verification of safety issues in major NRC requirements areas. This information was compiled and reported in three NUREG volumes. Volume 1, published in March 1991, addressed the status of of Three Mile Island (TMI) Action Plan Requirements. Volume 2, published in May 1991, addressed the status of unresolved safety issues (USIs). Volume 3, published in June 1991, addressed the implementation and verification status of generic safety issues (GSIs). This annual NUREG report combines these volumes into a single report and provides updated information as of September 30, 1991. The data contained in these NUREG reports are a product of the NRC's Safety Issues Management System (SIMS) database, which is maintained by the Project Management Staff in the Office of Nuclear Reactor Regulation and by NRC regional personnel. This report is to provide a comprehensive description of the implementation and verification status of TMI Action Plan Requirements, safety issues designated as USIs, and GSIs that have been resolved and involve implementation of an action or actions by licensees. This report makes the information available to other interested parties, including the public. An additional purpose of this NUREG report is to serve as a follow-on to NUREG-0933, ''A Prioritization of Generic Safety Issues,'' which tracks safety issues up until requirements are approved for imposition at licensed plants or until the NRC issues a request for action by licensees

  11. Psychological impact of the Three Mile Island incident

    International Nuclear Information System (INIS)

    Cleary, P.D.; Houts, P.S.

    1984-01-01

    This study examines the psychological impact of the Three Mile Island incident. The results are based on data from a panel study of 403 persons living within five miles of Three Mile Island (TMI), and a telephone survey of 1,506 people living within 55 miles of that area. Active coping strategies were associated with continued high levels of distress. Having more friends was related to reduced distress, but introspection, taking protective actions, being active in organizations, and seeking out others were all related to higher levels of distress. High self-esteem was related to a decrease in symptoms and psychotropic drug use, and avoidance behaviors were related to higher than expected numbers of symptoms. Efforts to profile those who used different coping strategies were relatively unsuccessful. The results emphasize the need to consider the nature of the stressor when developing models of coping and response to stressful situations

  12. Analysis of the Three Mile Island (TMI-2) hydrogen burn

    International Nuclear Information System (INIS)

    Henrie, J.; Postma, A.

    1983-01-01

    As a basis for the analysis of the hydrogen burn which occurred in the Three Mile Island Containment on March 28, 1979, a study of recorded temperatures and pressures was made. Long-term temperature information was obtained from the multipoint temperature recorder which shows 12 containment atmosphere temperatures plotted every 6 min. The containment atmosphere pressure recorder provided excellent long and short-term pressure information. Short-term information was obtained from the multiplex record of 24 channels of data, recorded every 3 sec, and the alarm printer record which shows status change events and prints out temperatures, pressures, and the time of the events. The timing of these four data recording systems was correlated and pertinent data were tabulated, analyzed and plotted to show average containment temperature and pressure versus time. The data used have not been qualified and accuracy is not fully assured. Photographs and videotapes of the containment entries provided qualitative burn information

  13. Technical evaluation report - TMI action: NUREG-0737 (II.D.1) relief and safety valve testing for Grand Gulf Nuclear Station Unit No. 1 (Docket No. 50-416)

    International Nuclear Information System (INIS)

    Burr, T.K.; Nalezny, C.L.

    1985-09-01

    Light water reactors operators have experienced a number of occurrences of improper performance by safety and relief valves installed in their primary coolant systems. Because of this, the authors of NUREG-0578 (TMI-2 Lessons Learned Task Force Status Report and Short-Term Recommendations) recommended that programs be developed and completed which would reevaluate the performance capabilities of BWR safety and relief valves. This report provides the results of the review of these programs and their results by the NRC and their consultant, EG and G Idaho, Inc. Specifically, this report has examined the response of the Licensee for the Grand Gulf Nuclear Station, Unit 1 to the requirements of NUREG-0578 and subsequently NUREG-0737 and finds that the Licensee has provided an acceptable response, reconfirming that the General Design Criteria 14, 15 and 30 of Appendix A to 10 CFR-50 have been met

  14. Three Mile Island Unit-2 events of 28 March 1979

    Energy Technology Data Exchange (ETDEWEB)

    Syed Hussin Shabuddin, Syed Nahar [PUSPATI, Selangor (Malaysia)

    1984-12-01

    Three Mile Island was the most severe accident at a commercial nuclear power plant in the United States. This paper attempts to give in detail and chronological order the technical events that happened on the day of the accident. Operator response to plant conditions and its consequences are explained.

  15. Effective communications bring greater public acceptance

    International Nuclear Information System (INIS)

    Clawson, C.

    1992-01-01

    In 1986, GPU Nuclear Corporation announced a plan to evaporate into the atmosphere 2.3 million gal of water remaining from the Three Mile Island Unit 2 (TMI-2) accident. The water would be processed to remove most of the radioactivity, but still remaining were >1,000 Ci of tritium to be released to the atmosphere during the evaporation process. It was expected that, following regulatory approvals, it would take >2 yr to complete the process. Fed by well-established antinuclear groups, public concern about evaporating the TMI-2-accident-generated water ran high among residents living near the plant. In the years since the TMI-2 accident, GPU Nuclear had developed a highly effective communications program in the communities surrounding TMI. This ongoing program provided a solid foundation on which to create and implement a risk communications approach to community understanding and acceptance of the evaporation process

  16. The psychological impact of the Three Mile Island incident.

    Science.gov (United States)

    Cleary, P D; Houts, P S

    1984-01-01

    This study examines the psychological impact of the Three Mile Island incident. The results are based on data from a panel study of 403 persons living within five miles of Three Mile Island (TMI), and a telephone survey of 1,506 people living within 55 miles of that area. Active coping strategies were associated with continued high levels of distress. Having more friends was related to reduced distress, but introspection, taking protective actions, being active in organizations, and seeking out others were all related to higher levels of distress. High self-esteem was related to a decrease in symptoms and psychotropic drug use, and avoidance behaviors were related to higher than expected numbers of symptoms. Efforts to profile those who used different coping strategies were relatively unsuccessful. The results emphasize the need to consider the nature of the stressor when developing models of coping and response to stressful situations.

  17. TMI abnormal wastes disposal options

    International Nuclear Information System (INIS)

    Ayers, A.L. Jr.

    1984-03-01

    A substantial quantity of high beta-gamma/high-TRU contaminated wastes are expected from cleanup activities of Unit 2 of the Three Mile Island Nuclear Power Station. Those wastes are not disposable because of present regulatory constraints. Therefore, they must be stored temporarily. This paper discusses three options for storage of those wastes at the Idaho National Engineering Laboratory: (1) storage in temporary storage casks; (2) underground storage in vaults; and (3) storage in silos at a hot shop. Each option is analyzed and evaluated. Also included is a discussion of future disposal strategies, which might be pursued when a suitable federal or commercial repository is built

  18. Answers to frequently asked questions about cleanup activities at Three Mile Island, Unit 2. Public information report

    International Nuclear Information System (INIS)

    1980-09-01

    The document presents answers to frequently asked questions about plans for cleanup and decontamination activities at Three Mile Island, Unit 2. Answers to the questions asked are based on information in the NRC 'Draft Programmatic Environmental Impact Statement related to decontamination and disposal of radioactive wastes resulting from March 28, 1979, accident, Three Mile Island Nuclear Station, Unit 2' NUREG-0683

  19. Impact of the TMI accident on the French nuclear program and the safety analysis

    International Nuclear Information System (INIS)

    Fourest, B.; Boaretto, Y.; Cayol, A.; Droulers, Y.; Goudal, M.; Oury, J.M.

    1980-04-01

    Almost immediately after the TMI accident, Electricite de France (EdF), Framatome and the French safety authorities started a large scale program of actions designed to analyse and understand the causes of the accident, and draw lessons applicable in France. This paper discusses these actions and the main conclusions of TMI accident analysis in France, notably: the fundamental role of plant operators, and the importance of operator training, written instructions and procedures, and diagnostic aids; the importance of feeding back operating experience to design teams, and incorporating the results of accident and post-accident studies in operating procedures; the necessity to improve knowledge of core cooling modes, including during two-phase flow and natural circulation; measures to improve particular systems and components [fr

  20. Annotated bibliography of GEND-sponsored TMI-2 reports

    International Nuclear Information System (INIS)

    1983-04-01

    In the continuing effort to distribute information about the TMI-2 cleanup and recovery effort, the GEND group has sponsored publication of 70 reports to date on various aspects of the Technical Information and Examination Program. Each report is indicated below by number, title, and date of publication, and followed by a brief description. For the formal reports, the National Technical Information Service price codes are indicated within parentheses following the date of publication (where available). The first code is for printed copy; the second is for microfiche

  1. TMI-2 core debris grab samples: Examination and analysis: Part 1

    International Nuclear Information System (INIS)

    Akers, D.W.; Carlson, E.R.; Cook, B.A.; Ploger, S.A.; Carlson, J.O.

    1986-09-01

    Six samples of particulate debris were removed from the TMI-2 core rubble bed during September and October 1983, and five more samples were obtained in March 1984. The samples (up to 174 g each) were obtained at two locations in the core: H8 (center) and E9 (mid-radius). Ten of the eleven samples were examined at the Idaho National Engineering Laboratory to obtain data on the physical and chemical nature of the debris and the postaccident condition of the core. Portions of the samples also were subjected to differential thermal analysis at Rockwell Hanford Operations and metallurgical and chemical examinations at Argonne National Laboratories. This report presents results of the examination of the core debris grab samples, including physical, metallurgical, chemical, and radiochemical analyses. The results indicate that temperatures in the core reached at least 3100 K during the TMI-2 accident, fuel melting and significant mixing of core structural material occurred, and large fractions of some radionuclides (e.g., 90 Sr and 144 Ce) were retained in the core

  2. PK Tradesman Tmi Developing marketing in a multicultural environment

    OpenAIRE

    Juutilainen, Tomi; Kangasperko, Pyry

    2010-01-01

    Purpose of the thesis was to find ways to improve PK Tradesman Tmi's customer and partner relations and marketing processes as well as research the viability of its product offering. This was accomplished by researching the concepts of guerrilla marketing and customer relationship management, and comparing different aspects of the Finnish and Chinese culture. The thesis consists in part of exploring the theory of aforementioned concepts, and in part of a ques-tionnaire which was implement...

  3. Nuclear power: renaissance or relapse? Global climate change and long-term Three Mile Island activists' narratives.

    Science.gov (United States)

    Culley, Marci R; Angelique, Holly

    2010-06-01

    Community narratives are increasingly important as people move towards an ecologically sustainable society. Global climate change is a multi-faceted problem with multiple stakeholders. The voices of affected communities must be heard as we make decisions of global significance. We document the narratives of long-term anti-nuclear activists near the Three Mile Island (TMI) nuclear power plant who speak out in the dawn of a nuclear renaissance/relapse. While nuclear power is marketed as a "green" solution to global warming, their narratives reveal three areas for consideration; (1) significant problems with nuclear technology, (2) lessons "not" learned from the TMI disaster, and (3) hopes for a sustainable future. Nuclear waste, untrustworthy officials and economic issues were among the problems cited. Deceptive shaping of public opinion, nuclear illiteracy, and an aging anti-nuclear movement were reasons cited for the lessons not learned. However, many remain optimistic and envision increased participation to create an ecologically-balanced world.

  4. Three Mile Island nuclear reactor accident of March 1979. Environmental radiation data: Volume II. A report to the President's Commission on the Accident at Three Mile Island

    International Nuclear Information System (INIS)

    Bretthauer, E.W.; Grossman, R.F.; Thome, D.J.; Smith, A.E.

    1981-03-01

    This report contains a listing of environmental radiation monitoring data collected in the vicinity of Three Mile Island (TMI) following the March 28, 1979 accident. These data were collected by the EPA, NRC, DOE, HHS, the Commonwealth of Pennsylvania, or the Bethlehem Steel Corporation. The original report was printed in September 1979 and the update was released in December 1979. Table 6-Summary of Department of Health, Education, and Welfare (HEW) sampling and analytical procedures; Table 7-Computer printout of environmental data collected by HEW; Table 8-Summary of US Nuclear Regulatory Commission (NRC) sampling and analytical procedures

  5. The TMI-2 clean-up project collection and databases

    International Nuclear Information System (INIS)

    Osif, B.A.; Conkling, T.W.

    1996-01-01

    A publicly accessible collection containing several thousand of the videotapes, photographs, slides and technical reports generated during the clean-up of the TMI-2 reactor has been established by the Pennsylvania State University Libraries. The collection is intended to serve as a technical resource for the nuclear industry as well as the interested public. Two Internet-searchable databases describing the videotapes and technical reports have been created. The development and use of these materials and databases are described in this paper. (orig.)

  6. Incidence of thyroid cancer in residents surrounding the Three Mile Island nuclear facility.

    Science.gov (United States)

    Levin, Roger J

    2008-04-01

    On March 28, 1979, the worst nuclear exposure incident in U.S. history occurred near Harrisburg, PA. Small quantities of xenon and iodine radioisotopes were released into the environment from the Three Mile Island (TMI) nuclear power plant. The Pennsylvania Department of Health (PDoH) implemented a TMI Population Registry, including 32,135 individuals within a 5-mile radius of TMI, to track possible health effects to the local population. Although no increase in cancer mortality has been noted in this cohort, cancer incidence has not been tracked. Given the long latency period for the development of thyroid cancer after exposure to low-level radiation exposure, it is plausible that an increase in thyroid cancer incidence might just now be occurring. Retrospective analysis of the Pennsylvania Cancer Registry Dataset for Thyroid Cancer using the Epidemiological Query and Mapping System (EpiQMS) search engine. EpiQMS is an interactive health statistics Website that can produce numbers, rates, graphs, charts, maps, and county profiles using various demographic variables (age, sex, race, etc.) from birth, death, cancer, and population datasets for the state and counties or regions of Pennsylvania. Eighteen years of data (1985-2002) on thyroid cancer incidence were obtained from the PDoH. The three at-risk counties of Dauphin, York, and Lancaster were analyzed with regard to observed numbers of thyroid cancer cases versus expected incidence. Although the nuclear accident at TMI occurred in 1979, 1985 was chosen as the starting point for data analysis because that is when the PDoH began maintaining cancer incidence records. In the first year available for evaluation (1985), there were 11 new thyroid cancer cases in each of the at-risk counties (Dauphin, York, Lancaster). By 2002, the incidence had increased to 29 in Dauphin County, 81 in Lancaster County, and 69 in York County. The increase in thyroid cancer in Dauphin County is not above what would be expected for both

  7. Three Mile Island nuclear reactor accident of March 1979. Environmental radiation data: Update 2, Volume III

    International Nuclear Information System (INIS)

    Hilton, B.A.; Grossman, R.F.

    1981-03-01

    The original report contains a listing of environmental radiation monitoring data collected in the vicinity of Three Mile Island (TMI) following the March 28, 1979 accident. These data were collected by the EPA, NRC, DOE, HHS, the Commonwealth of Pennsylvania, or the Bethlehem Steel Corporation. The original report was printed in September 1979 and the update was released in December 1979. This final update consists of additional data for 1979 by the same participating organizations, which has not been previously reported

  8. Release and transport of fission product cesium in the TMI-2 accident

    International Nuclear Information System (INIS)

    Lorenz, R.A.; Collins, J.L.

    1986-01-01

    Approximately 50% of the fission product cesium was released from the overheated UO 2 fuel in the TMI-2 accident. Steam that boiled away from a water pool in the bottom of the reactor vessel transported the released fission products throughout the reactor coolant system (RCS). Some fission products passed directly through a leaking valve with steam and water into the containment structure, but most deposited on dry surfaces inside of the RCS before being dissolved or resuspended when the RCS was refilled with water. A cesium transport model was developed that extended measured cesium in the RCS back to the first day of the accident. The model revealed that ∼62% of the released 137 Cs deposited on dry surfaces inside of the RCS before being slowly leached and transported out of the RCS in leaked or letdown water. The leach rates from the model agreed reasonably well with those measured in the laboratory. The chemical behavior of cesium in the TMI-2 accident agreed with that observed in fission product release tests at Oak Ridge National Laboratory (ORNL)

  9. The significance of radiological control documentation in litigation

    International Nuclear Information System (INIS)

    Lodde, G.M.; Murphy, T.D.

    1988-01-01

    Commercial nuclear facilities accumulate radiological control program data and documents generated and retained pursuant to regulatory, license, and technical specification requirements. During and following the Three Mile Island Unit 2 (TMI-2) accident, many documents were produced that would not normally have been produced. Shortly after the accident, the US Nuclear Regulatory Commission (NRC) issued an order requiring the retention of all data, including documentary material and physical samples relating to the TMI-2 accident (44 Fed. Reg. 30788, May 29, 1979). Three years later, the NRC vacated the requirement to retain catalogued physical samples, provided the radioactivity data had been properly recorded, allowing disposal of many samples. After the TMI-2 accident, GPU Nuclear Corporation (GPU) designed and implemented an effective and efficient record management program for TMI. This Computer-Assisted Records and Information Retrieval System (CARIRS) was developed to assess the official record for TMI, which is maintained as a microform. GPU also retains hard copies of selected radiological control documents for potential litigation. This paper describes the use of radiological control documentation in the postaccident litigation and the magnitude of document production required to support that litigation

  10. Operator/instrumentation interactions during the Three Mile Island incident

    International Nuclear Information System (INIS)

    Cummings, G.E.

    1979-10-01

    A discussion is presented of the operator/instrumentation interactions which had an effect on the course of the incident at the Three Mile Island-2 Nuclear Power Plant. A brief review of the sequence of occurrences at TMI-2 over the first 16 hours of the incident is given with particular emphasis on operator/instrumentation interactions. A breakdown of the six major items that seemed to have contributed to the characteristics of the incident is then given and also an outline of some of the currently proposed operator/instrumentation improvements. The six major items involve water level indication in the reactor, electromatic relief valve operation, auxiliary feed-water flow indication, containment isolation, extended range instrumentation, and computer readout

  11. Altered molecular profile in thyroid cancers from patients affected by the Three Mile Island nuclear accident.

    Science.gov (United States)

    Goldenberg, David; Russo, Mariano; Houser, Kenneth; Crist, Henry; Derr, Jonathan B; Walter, Vonn; Warrick, Joshua I; Sheldon, Kathryn E; Broach, James; Bann, Darrin V

    2017-07-01

    In 1979, Three Mile Island (TMI) nuclear power plant experienced a partial meltdown with release of radioactive material. The effects of the accident on thyroid cancer (TC) in the surrounding population remain unclear. Radiation-induced TCs have a lower incidence of single nucleotide oncogenic driver mutations and higher incidence of gene fusions. We used next generation sequencing (NGS) to identify molecular signatures of radiation-induced TC in a cohort of TC patients residing near TMI during the time of the accident. Case series. We identified 44 patients who developed papillary thyroid carcinoma between 1974 and 2014. Patients who developed TC between 1984 and 1996 were at risk for radiation-induced TC, patients who developed TC before 1984 or after 1996 were the control group. We used targeted NGS of paired tumor and normal tissue from each patient to identify single nucleotide oncogenic driver mutations. Oncogenic gene fusions were identified using quantitative reverse transcription polymerase chain reaction. We identified 15 patients in the at-risk group and 29 patients in the control group. BRAF V600E mutations were identified in 53% patients in the at-risk group and 83% patients in the control group. The proportion of patients with BRAF mutations in the at-risk group was significantly lower than predicted by the The Cancer Genome Atlas cohort. Gene fusion or somatic copy number alteration drivers were identified in 33% tumors in the at-risk group and 14% of tumors in the control group. Findings were consistent with observations from other radiation-exposed populations. These data raise the possibility that radiation released from TMI may have altered the molecular profile of TC in the population surrounding TMI. 4 Laryngoscope, 127:S1-S9, 2017. © 2017 The American Laryngological, Rhinological and Otological Society, Inc.

  12. Comments on the NRC Safety Research Program budget

    International Nuclear Information System (INIS)

    1979-07-01

    This report includes comments on the budget levels and program plans for the supplemental request for FY 1980 to support research related to the accident at Three Mile Island, Unit 2 (TMI) as well as for the FY 1981 Budget. For both budgets, the funding levels considered by the ACRS are the original requests by RES and the Budget Review Group (BRG) markup as of July 10, 1979. In its current review of the NRC research program, the ACRS has given special attention to both the short- and long-term implications of the TMI accident and their significance to research for both the short- and long-term research programs

  13. Critique of source term and environmental measurement at Three Mile Island

    International Nuclear Information System (INIS)

    Hull, A.P.

    1979-01-01

    The most serious malfunction to date at an operating power reactor in the US occurred at Unit 2 of the Three Mile Island Nuclear Power Station (TMI) at 0400 est on March 28, 1979. Subsequently, between 3X and 10 x 10 6 Ci of radiogases (principally 133 Xe) were released to the atmosphere from the plant vent in decreasing concentrations over the next few weeks, accompanied by abut 10 Ci of 131 I. During this period, the plant's typical effluent monitors and field radiation monitoring program were unable to supply prompt and reliable radiological information. In order to provide a sufficient radioanalytical capability for the large number of in-plant and environmental samples (air, water, soil, vegetation and milk) which were obtained, the existing on-site facilities were augmented by mobile laboratories. The laboratory facilities of the Bureau of Radiological Health (BRH-PA) of the Pennsylvania Department of Environmental Conservation were supplemented by a nearby temporary facility for gamma analysis set up by the Department of Energy (DOE). Many environmental samples, principally of milk, were also transported to more remotely established radioanalytical laboratories of state and federal agencies

  14. TMI-2 reactor vessel plenum final lift

    International Nuclear Information System (INIS)

    Wilson, D.C.

    1986-01-01

    Removal of the plenum assembly from the TMI-2 reactor vessel was necessary to gain access to the core region for defueling. The plenum was lifted from the reactor vessel by the polar crane using three specially designed pendant assemblies. It was then transferred in air to the flooded deep end of the refueling canal and lowered onto a storage stand where it will remain throughout the defueling effort. The lift and transfer were successfully accomplished on May 15, 1985 in just under three hours by a lift team located in a shielded area within the reactor building. The success of the program is attributed to extensive mockup and training activities plus thorough preparations to address potential problems. 54 refs

  15. TMI-2 data qualification and data bases

    International Nuclear Information System (INIS)

    Golden, D.W.; Anderson, J.L.; Brower, R.W.; Fackrell, L.J.; McCormick, R.D.

    1988-01-01

    TMI-2 data are of great interest to the scientific community, since the March, 1979 accident represents the only occurrence of a transient resulting in severe fuel damage in a full-scale commercial production reactor. This paper discusses the data sources available for accident analyses. Techniques to qualify and quantify time series measurement and sample data which have been collected and evaluated to this time are discussed. Data base products are described which have been developed for use by analysts investigating the many aspects of the accident. Applications processing features have been incorporated into the software designs to provide the end user with many useful capabilities in sorting, viewing and analyzing the data; data base discussions emphasize these features. 14 refs., 5 figs

  16. Cancer rates after the Three Mile Island nuclear accident and proximity of residence to the plant.

    Science.gov (United States)

    Hatch, M C; Wallenstein, S; Beyea, J; Nieves, J W; Susser, M

    1991-06-01

    In the light of a possible link between stress and cancer promotion or progression, and of previously reported distress in residents near the Three Mile Island (TMI) nuclear power plant, we attempted to evaluate the impact of the March 1979 accident on community cancer rates. Proximity of residence to the plant, which related to distress in previous studies, was taken as a possible indicator of accident stress; the postaccident pattern in cancer rates was examined in 69 "study tracts" within a 10-mile radius of TMI, in relation to residential proximity. A modest association was found between postaccident cancer rates and proximity (OR = 1.4; 95% CI = 1.3, 1.6). After adjusting for a gradient in cancer risk prior to the accident, the odds ratio contrasting those closest to the plant with those living farther out was 1.2 (95% CI = 1.0, 1.4). A postaccident increase in cancer rates near the Three Mile Island plant was notable in 1982, persisted for another year, and then declined. Radiation emissions, as modeled mathematically, did not account for the observed increase. Interpretation in terms of accident stress is limited by the lack of an individual measure of stress and by uncertainty about whether stress has a biological effect on cancer in humans. An alternative mechanism for the cancer increase near the plant is through changes in care-seeking and diagnostic practice arising from postaccident concern.

  17. Power plant economy of scale and cost trends: further analyses and review of empirical studies

    International Nuclear Information System (INIS)

    Fisher, C.F. Jr.; Paik, S.; Schriver, W.R.

    1986-07-01

    Multiple regression analyses were performed on capital cost data for nuclear and coal-fired power plants in an extension of an earlier study which indicated that nuclear units completed prior to the accident at Three-Mile Island (TMI) have no economy of scale, and that units completed after that event have a weak economy of scale (scaling exponent of about 0.81). The earlier study also indicated that the scaling exponent for coal-fired units is about 0.92, compared with conceptual models which project scaling exponents in a range from about 0.5 to 0.9. Other empirical studies have indicated poor economy of scale, but a large range of cost-size scaling exponents has been reported. In the present study, the results for nuclear units indicate a scaling exponent of about 0.94 but with no economy of scale for large units, that a first unit costs 17% more than a second unit, that a unit in the South costs 20% less than others, that a unit completed after TMI costs 33% more than one completed before TMI, and that costs are increasing at 9.3% per year. In the present study, the results for coal-fired units indicate a scaling exponent of 0.93 but with better scaling economy in the larger units, that a first unit costs 38.5% more, a unit in the South costs 10% less, flue-gas desulfurization units cost 23% more, and that costs are increasing at 4% per year

  18. Effects of the accident at Three Mile Island on the mental health and behavior responses of the general population and the nuclear workers

    International Nuclear Information System (INIS)

    Fabrikant, J.I.

    1982-02-01

    A main conclusion drawn from the investigation by the President's Commission was that the most serious health effect of the Three Mile Island nuclear accident was severe mental stress, which was short-lived. The highest levels of psychological distress were found among those living within 5 miles of Three Mile Island, in families with preschool children, and among the Three Mile Island nuclear workers. This report provides some understanding of how these conclusions were drawn, the methods used to obtain information of the experiences of mental stress and the behavioral effects and responses of the general population and the nuclear workers to the accident at Three Mile Island. In order to limit the scope of the discussion, information is taken from the Behavioral Effects Task Group Report [TMI79c] to the President's Commission, and thus from the labors of the many behavioral scientists

  19. A human reliability analysis of the Three Mile power plant accident considering the THERP and ATHEANA methodologies; Uma analise da confiabilidade humana do acidente na Usina de Three Mile Island II considerando as metodologias Therp e Atheana

    Energy Technology Data Exchange (ETDEWEB)

    Fonseca, Renato Alves da

    2004-03-15

    The main purpose of this work is the study of human reliability using the THERP (Technique for Human Error Prediction) and ATHEANA methods (A Technique for Human Error Analysis), and some tables and also, from case studies presented on the THERP Handbook to develop a qualitative and quantitative study of nuclear power plant accident. This accident occurred in the TMI (Three Mile Island Unit 2) power plant, PWR type plant, on March 28th, 1979. The accident analysis has revealed a series of incorrect actions, which resulted in the Unit 2 shut down and permanent loss of the reactor. This study also aims at enhancing the understanding of the THERP method and ATHEANA, and of its practical applications. In addition, it is possible to understand the influence of plant operational status on human failures and of these on equipment of a system, in this case, a nuclear power plant. (author)

  20. Report of the emergency preparedness and response task force

    International Nuclear Information System (INIS)

    Dynes, R.R.; Purcell, A.H.; Wenger, D.E.; Stern, P.S.; Stallings, R.A.; Johnson, Q.T.

    1979-10-01

    The accident at Three Mile Island (TMI) marked the first time in the US when traditional planning for emergencies was applied to a possible radiological emergency. This report examines the planning that existed in the counties surrounding the plant and at the state and federal levels. It also examines the responses of the various governmental units following the initial accident

  1. Report of the Emergency Preparedness and Response Task Force

    International Nuclear Information System (INIS)

    Dynes, R.R.; Purcell, A.H.; Wenger, D.E.; Stern, P.S.; Stallings, R.A.; Johnson, Q.T.

    1979-10-01

    The accident at Three Mile Island (TMI) marked the first time in the US when traditional planning for emergencies was applied to a possible radiological emergency. This report examines the planning that existed in the counties surrounding the plant and at the state and federal levels. It also examines the responses of the various governmental units following the initial accident

  2. TMI-2 [Three-Mile Island-Unit 2] rail cask and railcar maintenance

    International Nuclear Information System (INIS)

    Tyacke, M.J.; Ayers, A.L. Jr.; Ball, L.J.; Anselmo, A.A.

    1988-02-01

    This paper describes the NuPac 125-B cask system (i.e., cask and railcar), and the maintenance and inspection requirements for that system. The paper discusses the operations being done to satisfy those requirements and how, in some cases, it has been efficient for the operations to be more rigorous than the requirements. Finally, this paper discusses the experiences gained from those operations and how specific hardware and procedural enhancements have resulted in a reliable and continuous shipping campaign. 2 refs., 2 figs

  3. Evaluation results of TMI-2 solenoids AH-V6 and AH-V74

    International Nuclear Information System (INIS)

    Soberano, F.T.

    1984-01-01

    Two Class 1E solenoid operators were removed from the Three Mile Island unit 2 Reactor Building and examined to determine whether they had degraded as a result of accident and post-accident conditions. Both units were functional during post-accident operation. This report discusses the examination, findings, causes of the anomalies, and recommendations for system improvement

  4. The Three Mile Island accident. Diagnosis and prognosis

    International Nuclear Information System (INIS)

    Toth, L.M.; Malinauskas, A.P.; Eidam, G.R.; Burton, H.M.

    1986-01-01

    The Three Mile Island accident occurred on March 29, 1979. The decision to hold a symposium on the TMI accident aftermath was reached when it was realized that enough information had been gathered during the past 6 years to provide a fairly complete picture of the damage and of the activities required for eventual recovery. The symposium was organized into three sessions: the first dealt with a description of the accident, the second focused on the chemical aspects involved, and the third addressed the strategy and progress made toward recovery. The symposium was intended to focus on these three subjects and leave the environmental considerations to future meetings and reports. Although it might appear shortsighted to exclude the environmental impact, the exclusion was considered necessary in order to maintain the focus we sought

  5. Fuel removal, transport, and storage

    International Nuclear Information System (INIS)

    Reno, H.W.

    1986-01-01

    The March 1979 accident at Unit 2 of the Three Mile Island Nuclear Power Station (TMI-2) which damaged the core of the reactor resulted in numerous scientific and technical challenges. Some of those challenges involve removing the core debris from the reactor, packaging it into canisters, loading canisters into a rail cask, and transporting the debris to the Idaho National Engineering Laboratory (INEL) for storage, examination, and preparation for final disposal. This paper highlights how some challenges were resolved, including lessons learned and benefits derived therefrom. Key to some success at TMI was designing, testing, fabricating, and licensing two rail casks, which each provide double containment of the damaged fuel. 10 refs., 12 figs

  6. Report of a Special Committee on the Review of U.S. Nuclear Power Plant Accident, second report

    International Nuclear Information System (INIS)

    1979-01-01

    Following on the issuance of the first report, for the accident in Three Mile Island Nuclear Power Plant in the United States there has appeared detailed information of such as reactor operation and radiation control. This has enabled technical evaluation of those items involved in nuclear power safety. The review results up to the beginning of September 1979 are presented, to meet popular desires to know the accident situation and to reflect the results in the nation's nuclear power generation. Contents are features and background of the TMI Nuclear Power Plant accident consequences, safety measures to be taken in Japan, and (in the appendix) the data on the TMI accident, countermeasures taken in Japan, etc. (Mori, K.)

  7. An analysis of the human reliability on Three Mile Island II accident considering THERP and ATHEANA methodologies

    International Nuclear Information System (INIS)

    Fonseca, Renato Alves da; Alvim, Antonio Carlos Marques

    2005-01-01

    The research on the Analysis of the Human Reliability becomes more important every day, as well as the study of the human factors and the contributions of the same ones to the incidents and accidents, mainly in complex plants or of high technology. The analysis here developed it uses the methodologies THERP (Technique for Human Error Prediction) and ATHEANA (A Technique for Human Error Analysis), as well as, the tables and the cases presented in THERP Handbook and to develop a qualitative and quantitative study of an occurred nuclear accident. The chosen accident was it of Three Mile Island (TMI). The accident analysis has revealed a series of incorrect actions that resulted in the permanent loss of the reactor and shutdown of Unit 2. This study also aims at enhancing the understanding of the THERP and ATHEANA methods and at practical applications. In addition, it is possible to understand the influence of plant operational status on human failures and the influence of human failures on equipment of a system, in this case, a nuclear power plant. (author)

  8. Progress in nuclear energy. Volume 10

    International Nuclear Information System (INIS)

    Williams, M.M.R.; McCormick, N.J.

    1983-01-01

    This book consists of 15 articles written by specialists in the field of atomic energy. A significant portion of this volume is devoted to a special section reporting on the impact of the accident at Three Mile Island on the nuclear power industry. Changes in reactor instrumentation, operator training, and emergency preparedness are discussed in detail. A paper reporting on the effects of the accident on the public's attitude toward nuclear power is included in this section. Contents, abridged: The safety of CO 2 cooled reactor technology. Denaturing fissile materials. Impact of the Three Mile Island accident on the nuclear power industry; changes in the nuclear power industry after TMI; impact of TMI on combustion engineering technical activities. Impact of the accident at Three Mile Island on a NSSS vendor--a Westinghouse perspective; emergency planning and preparedness since Three Mile Island. The impact of TMI upon the public acceptance of nuclear power

  9. TMI-2 reactor vessel head removal

    International Nuclear Information System (INIS)

    Bengel, P.R.; Smith, M.D.; Estabrook, G.A.

    1984-12-01

    This report describes the safe removal and storage of the Three Mile Island Unit 2 reactor vessel head. The head was removed in July 1984 to permit the removal of the plenum and the reactor core, which were damaged during the 1979 accident. From July 1982, plans and preparations were made using a standard head removal procedure modified by the necessary precautions and changes to account for conditions caused by the accident. After data acquisition, equipment and structure modifications, and training the head was safely removed and stored and the internals indexing fixture and a work platform were installed on top of the vessel. Dose rates during and after the operation were lower than expected; lessons were learned from the operation which will be applied to the continuing fuel removal operations activities

  10. Training and qualification of licensed reactor operators at General Public Utilities Nuclear Corporation

    International Nuclear Information System (INIS)

    Long, R.L.; Coe, R.P.

    1992-01-01

    Following the Three Mile Island-2 (TMI-2) accident in 1979, the utility responsible for managing the facility has looked closely at the training and qualification of its reactor operators. Performance-based operator training programmes are now in place, as required by the United States National Academy for Nuclear Training. Operators also participate directly in the development of a professional code of behaviour. (UK)

  11. Status of the TMI-2 core: a review of damage assessments

    International Nuclear Information System (INIS)

    Croucher, D.W.

    1981-01-01

    Assessments of the damage within the core of the Three Mile Island Unit 2 reactor, performed by reconstructing the transient thermal-hydraulic sequence of events, estimating the amount of hydrogen generation, and evaluating the amount of fission products released, are reviewed and summarized. Minimum and maximum bounds of damage to the core are identified

  12. 27 CFR 26.201a - Production in the Virgin Islands for tax-free shipment to the United States.

    Science.gov (United States)

    2010-04-01

    ...) Industrial spirits produced or manufactured in the Virgin Islands and shipped to the United States free of... containing denatured spirits are to be shipped to the United States free of tax. [T.D. 6402, 24 FR 6090, July...

  13. Potassium iodide as a thyroid blocker--Three Mile Island to today

    International Nuclear Information System (INIS)

    Halperin, J.A.

    1989-01-01

    The Three Mile Island (TMI) nuclear emergency in the U.S. in March 1979 marked the first occasion when use of potassium iodide (KI) was considered for thyroid blocking of the population in the vicinity of a potentially serious release of fission products from a nuclear power reactor. In face of a demand that could not be satisfied by commercial supplies of low-dose KI drug products from the U.S. pharmaceutical industry, the Food and Drug Administration directed the manufacture and stockpiling of sufficient quantities of saturated solution of potassium iodide (SSKI) to provide protection for one million people in the event of a large-scale release of radioiodines. Although the drug was not used, the experience of producing, stockpiling, and making ready for use a large quantity of the drug resulted in significant public policy, regulatory, and logistical issues. A number of these issues have been resolved through scientific debate and consensus, development of official guidance regarding the proper role of KI in nuclear emergencies, and the approval of New Drug Applications for KI products specifically intended for thyroid blocking in nuclear emergencies. Other issues regarding broad-scale implementation of the guidelines remain today. This paper traces the history of the development and implementation of the use of KI from pre-TMI to the present

  14. Potassium iodide as a thyroid blocker--Three Mile Island to today.

    Science.gov (United States)

    Halperin, J A

    1989-05-01

    The Three Mile Island (TMI) nuclear emergency in the U.S. in March 1979 marked the first occasion when use of potassium iodide (KI) was considered for thyroid blocking of the population in the vicinity of a potentially serious release of fission products from a nuclear power reactor. In face of a demand that could not be satisfied by commercial supplies of low-dose KI drug products from the U.S. pharmaceutical industry, the Food and Drug Administration directed the manufacture and stockpiling of sufficient quantities of saturated solution of potassium iodide (SSKI) to provide protection for one million people in the event of a large-scale release of radioiodines. Although the drug was not used, the experience of producing, stockpiling, and making ready for use a large quantity of the drug resulted in significant public policy, regulatory, and logistical issues. A number of these issues have been resolved through scientific debate and consensus, development of official guidance regarding the proper role of KI in nuclear emergencies, and the approval of New Drug Applications for KI products specifically intended for thyroid blocking in nuclear emergencies. Other issues regarding broad-scale implementation of the guidelines remain today. This paper traces the history of the development and implementation of the use of KI from pre-TMI to the present.

  15. Epidemiology of HIV/AIDS among Asians and Pacific Islanders in the United States

    Science.gov (United States)

    Zaidi, Irum F.; Crepaz, Nicole; Song, Ruiguang; Wan, Choi K.; Lin, Lillian S.; Hu, Dale J.; Sy, Francisco S.

    2005-01-01

    Although the percentage of overall AIDS diagnoses remains low among Asian and Pacific Islanders (APIs) in the United States compared with other racial/ethnic groups, research on API risk behaviors and health status suggest that the low number of AIDS cases may not provide a full picture of the epidemic and issues faced by this understudied and…

  16. TMI-2 instrumentation and electrical program final evaluation report

    International Nuclear Information System (INIS)

    Mayo, C.W.; Huzdovich, J.W.; Roby, A.R.; Test, L.D.

    1986-11-01

    This report presents the authors collective opinions on the value to the nuclear industry of the various investigations performed at TMI-2 by the Instrumentation and Electrical Program. The authors demonstrate that more attention must be given to the prevention of moisture intrusion during design, construction, operation, and maintenance of a nuclear power plant. They also point out that, while basic engineering designs of instruments are more than adequate, the applications engineering and specifications could be improved. Finally, they show that advanced testing technology, exemplified by the Electrical Circuit Characterization and Diagnostics (ECCAD) System, may be very useful as a diagnostic tool when used as part of the testing or maintenance program in a nuclear power plant

  17. TMI-2 core-examination program: INEL facilities-readiness study

    International Nuclear Information System (INIS)

    McLaughlin, T.B.

    1982-09-01

    This document is a review of the Idaho National Engineering Laboratory's (INEL) remote handling facilities. Their availability and readiness to conduct examination and analyses of TMI-2 core samples was determined. Examination of these samples require that the facilities be capable of receiving commercial casks, unloading canisters from the casks, opening the canisters, handling the fuel debris and assemblies, and performing various examinations. The documentation that was necessary for the INEL to have before the receipt of the core material was identified. The core information was also required for input to these documents. The costs, schedules, and a preliminary-project plan are presented for the tasks which are identified as prerequisites to the receipt of the first core sample

  18. NRC as referee (reactor licensing following the Three Mile Island accident)

    International Nuclear Information System (INIS)

    Eisenhut, D.G.

    1984-01-01

    In this article, the NRC's licensing director reports on the progress made by US utilities in complying with the key regulations stemming from the Three Mile Island accident. Over 130 items must be improved at more than 65 reactors. The actions taken by France in response to its own analysis of the accident are discussed. New NRC requirements with regard to operational safety, design, and emergency-response capability are outlined. Nearly all the training, or software, items in Nureg-0737 (''Clarification of TMI Action Plan Requirements'') and more than half of the mechanical, or hardware, items have been completed at plants with operating reactors. The Committee to Review Generic Requirements was created to develop means for controlling the number and nature of NRC requirements placed on licensees. Probabilistic risk-assessment techniques were not widely used by the NRC until after the Three Mile Island accident. The NRC has directed licensees and applicants for operating licenses to conduct control-room design reviews to identify and correct human-engineering discrepancies. Includes 2 tables

  19. Recent chemical engineering requirements as the result of TMI on-site experience

    International Nuclear Information System (INIS)

    Brooksbank, R.E. Sr.

    1980-01-01

    From the experiences gained from the on-site experience at TMI, it is apparent that the role of chemical engineers should increase in order for the nuclear option to proceed in a safe and efficient fashion. It is also obvious that as the results of the reports investigating the causes and effects of the accident come to light and attempts to backfit system designs to prevent a recurrence are studied, more technical demands will be placed on the profession

  20. Revision to ANSI/ANS 3.1 1978: resulting from TMI-2

    International Nuclear Information System (INIS)

    Palmer, F.A.

    1981-01-01

    The personnel errors which occurred at TMI-2 brought forth several areas of weaknesses in personnel selection, qualification and training that impacted ANS-3. As a result, the ANS-3 Committee started working on a revision to ANSI/ANS 3.1-1978 Standard in May 1979. In July 1979 the first set of official recommendations was issued in NUREG 0578. Due to the interim nature of these regulations some interpretation of the intent of these recommendations had to be made and a basis developed to justify changes to the standard

  1. Comparison of licensing activities for operating plants designed by Babcock and Wilcox

    International Nuclear Information System (INIS)

    Thoma, J.O.

    1985-01-01

    This report provides a comparison of a number of licensing activities for the operating Babcock and Wilcox (B and W) plants with emphasis on Rancho Seco. The factors selected were a comparison of staff resources expended in FY84, active licensing action reviews, implementation of NUREG-0737 modifications, exemptions to regulations, SALP reports, enforcement actions, and Licensee Event Reports (LERs). The eight licensed operating plants examined are as follows: Arkansas Nuclear One Unit 1 (ANO-1), Crystal River Unit 3, Davis Besse, Oconee Units 1, 2, and 3, Rancho Seco, and Three Mile Island Unit 1 (TMI-1)

  2. Passive surveillance: a technique to characterize the condition of power and control circuits in a nuclear plant

    International Nuclear Information System (INIS)

    Meininger, R.D.; Dinsel, M.R.

    1985-01-01

    This paper reports on progress by EG and G Idaho in examination of electrical circuits exposed to the accident environment at Three Mile Island Unit 2 (TMI-2) during and after the loss-of-coolant accident of March 28, 1979. Interpretations of the data collected suggest that the major functional impact on the electrical circuits (a) occurs very late in time, (b) is caused by moisture intrusion, and (c) can be detected by remote surveillance prior to functional failure. The electrical testing was performed from outside the TMI-2 Reactor Building at the penetrations using a special circuit characterization and diagnostic system developed by EG and G Idaho. This paper concentrates on representative data from those circuits which were recently retested. 12 refs., 9 figs

  3. GEND planning report

    International Nuclear Information System (INIS)

    1980-10-01

    The Three Mile Island (TMI) Unit 2 accident on March 28, 1979 was and is of great concern to the nuclear industry; electric power generating companies and their customers, regulatory and other government agencies, the entire nuclear community, and to the country as a whole. While the accident resulted in only limited external plant radiation exposure, the plant itself suffered extensive damage with high radiation contamination within the reactor and auxiliary system facilities. The GEND Planning Report for cleanup activities at TMI-2 covers the areas of: instrumentation and electrical equipment survivability; fission product transport; decontamination/radiation dose reduction technology; data bank organization and sample archive facility; characterization of primary system pressure boundary and mechanical components; core damage assessment; and fuel handling, removal, examination and disposal

  4. Social survey of Three Mile Island area residents. Final report

    International Nuclear Information System (INIS)

    Brunn, S.D.; Johnson, J.H. Jr; Zeigler, D.J.

    1979-08-01

    Recognizing that there is concern among government officials, utility company officials, engineers, physical, social, and behavioral scientists, and the general public about the consequences of the Three Mile Island accident, the overall objective of this report is to examine how the accident affected TMI area residents. This final report is a detailed analysis and description of the summary results published previously. A questionnaire was mailed to a sample of residents in the Three Mile Island area within one month of the accident. The survey instrument and sampling design are discussed in a subsequent chapter. Because of the nature of the accident and individual memories about dates, places, and events, it was necessary to conduct a survey as soon as possible after the accident. Area residents were asked a variety of questions including: (1) when and how they learned about the accident; (2) where they evacuated and why; (3) what confidence they placed in reports by the government and utility companies; (4) how their attitudes toward nuclear power have changed as a result of the accident; and (5) what impact the accident is likely to have on themselves and the Three Mile Island area. These questions and others are examined in this report. The results are analyzed in light of a number of social, economic, and political characteristics. Both statistical tests and a graphical presentation of the results are included

  5. Interim report on the TMI-2 purification filter examination

    International Nuclear Information System (INIS)

    Mason, R.E.; Hobbins, R.R.; Cook, B.A.; MacDonald, P.E.

    1983-02-01

    Filters from the purification/makeup system of the Three Mile Island Unit 2 Reactor were examined after the March 28, 1979, accident to determine the character of the debris transported to the filters. The general condition of the filters is presented. Material was removed from the filters and examined. The elemental and radionuclide makeup of the debris is discussed. Distribution of particle size and shape is presentd for some of the material examined. This is an interim report. When the investigation is completed, another report summarizing all of the data will be issued

  6. Combined TRMM Microwave Imager (TMI) and Precipitation Radar (PR) Gridded Orbital Data Set (G2B31) V6

    Data.gov (United States)

    National Aeronautics and Space Administration — Combined TRMM Microwave Imager (TMI) and Precipitation Radar (PR) gridded orbital rainfall data, is a special product derived from the TRMM standard product (2B-31)...

  7. Inhibiting mild steel corrosion from sulfate-reducing bacteria using antimicrobial-producing biofilms in Three-Mile-Island process water.

    Science.gov (United States)

    Zuo, R; Ornek, D; Syrett, B C; Green, R M; Hsu, C-H; Mansfeld, F B; Wood, T K

    2004-04-01

    Biofilms were used to produce gramicidin S (a cyclic decapeptide) to inhibit corrosion-causing, sulfate-reducing bacteria (SRB). In laboratory studies these biofilms protected mild steel 1010 continuously from corrosion in the aggressive, cooling service water of the AmerGen Three-Mile-Island (TMI) nuclear plant, which was augmented with reference SRB. The growth of both reference SRB (Gram-positive Desulfosporosinus orientis and Gram-negative Desulfovibrio vulgaris) was shown to be inhibited by supernatants of the gramicidin-S-producing bacteria as well as by purified gramicidin S. Electrochemical impedance spectroscopy and mass loss measurements showed that the protective biofilms decreased the corrosion rate of mild steel by 2- to 10-fold when challenged with the natural SRB of the TMI process water supplemented with D. orientis or D. vulgaris. The relative corrosion inhibition efficiency was 50-90% in continuous reactors, compared to a biofilm control which did not produce the antimicrobial gramicidin S. Scanning electron microscope and reactor images also revealed that SRB attack was thwarted by protective biofilms that secrete gramicidin S. A consortium of beneficial bacteria (GGPST consortium, producing gramicidin S and other antimicrobials) also protected the mild steel.

  8. Rhode Island unemployment

    OpenAIRE

    Leonard Lardaro

    2010-01-01

    How can a state like Rhode Island have such a high unemployment rate? This question has been asked often over the past year, especially since at one point, Rhode Island found itself with the dubious distinction of having the highest unemployment rate in the United States. Following that extreme, Rhode Island seemed to settle into a niche where its rank was third nationally.

  9. Estimation of global solar radiation by means of sunshine duration

    Energy Technology Data Exchange (ETDEWEB)

    Luis, Mazorra Aguiar; Felipe, Diaz Reyes [Electrical Engineering Dept., Las Palmas de Gran Canaria Univ. (U.L.P.G.C.), Campus Univ. Tafira (Spain); Pilar, Navarro Rivero [Canary Islands Technological Inst. (I.T.C.), Gran Canaria (Spain)

    2008-07-01

    This paper analyses the relationship between global solar irradiation and sunshine duration with different estimation models for the island of Gran Canaria (Spain). These parameters were taken from six measurement stations around the Island, and selected for their reliability and the long period of time they covered. All data used in this paper were handed over by the Canary Islands Technological Institute (I.T.C.). As a first approach, it was decided to study the Angstrom lineal model. In order to improve the knowledge on solar resources, a Typical Meteorological Year (TMY) was created from all daily data. TMY shows differences between southern and northern locations, where Trade Winds generate clouds during the summer months. TMY resumes a data bank much longer than a year in duration, generating the characteristics for a year series of each location, for both irradiation and sunshine duration. To create the TMY, weighted means have been used to smooth high or low values. At first, Angstrom lineal model has been used to estimate solar global irradiation from sunshine duration values, using TMY. But the lineal model didn't reproduce satisfactory results when used to obtain global solar radiation from all daily sunshine duration data. For this reason, different models based in both parameters were used. The parameters estimation of this model was achieved both from TMY daily and monthly series and from all daily data for every location. Because of the weather stability all over the year in the Island, most of the daily data are concentrated in a close range, occasioning a deviation in the lineal equations. To avoid this deviation it was proposed to consider a limit condition data, taking into account values out of the main cloud of data. Additionally, different models were proposed (quadratic, cubic, logarithmic and exponential) to make a regression from all daily data. The best results were obtained with the exponential model proposed in this paper. The

  10. Thermal interaction of core melt debris with the TMI-2 baffle, core-former, and lower head structures

    International Nuclear Information System (INIS)

    Cronenberg, A.W.; Tolman, E.L.

    1987-09-01

    Recent inspection of the TMI-2 core-former baffle walls (vertical), former plates (horizontal), and lower plenum has been conducted to assess potential damage to these structures. Video observations show evidence of localized melt failure of the baffle walls, whereas fiberoptics data indicate the presence of resolidified debris on the former plates. Lower plenum inspection also confirms the presence of 20 tons or more of core debris in the lower plenum. These data indicate massive core melt relocation and the potential for melt attack on vessel structural components. This report presents analyses aimed at developing an understanding of melt relocation behavior and damage progression to TMI-2 vessel components. Thermal analysis indicates melt-through of the baffle plates, but maintenance of structural integrity of the former plates and lower head. Differences in the damage of these structures is attributed largely to differences in contact time with melt debris and pressure of water. 29 refs., 17 figs., 9 tabs

  11. Transport package maintenance requirements and operations

    International Nuclear Information System (INIS)

    Tyacke, M.J.; Ball, L.J.; Ayers, A.L. Jr.; Hayes, G.R.; Anselmo, A.A.

    1988-01-01

    The NuPac 125-B rail cask, which transports the damaged core debris from Three Mile Island Unit 2 (TMI-2) to the Idaho National Engineering Laboratory (INEL), is the only new spent-fuel rail shipping cask to be licensed in the United States within the last decade. EG ampersand G Idaho, Inc. (EG ampersand G), acting on behalf of the US Department of Energy, is responsible for ensuring that those new casks and rail cars are properly maintained per regulatory requirements. Both the casks and rail cars have comprehensive in-service inspection and preventive maintenance programs, which are more involved than implied by the requirements. The TMI-2 shipping campaign is the most ambitious spent-fuel transport activity being conducted in the nuclear industry. The experience gained in this campaign, as it relates to maintenance of a transport system, should be of interest and have direct applicability to similar shipping activities planned in the years ahead

  12. Heatup of the TMI-2 lower head during core relocation

    International Nuclear Information System (INIS)

    Wang, S.K.; Sienicki, J.J.; Spencer, B.W.

    1989-01-01

    An analysis has been carried out to assess the potential of a melting attack upon the reactor vessel lower head and incore instrument nozzle penetration weldments during the TMI core relocation event at 224 minutes. Calculations were performed to determine the potential for molten corium to undergo breakup into droplets which freeze and form a debris bed versus impinging upon the lower head as one or more coherent streams. The effects of thermal-hydraulic interactions between corium streams and water inside the lower plenum, the effects of the core support assembly structure upon the corium, and the consequences of corium relocation by way of the core former region were examined. 19 refs., 24 figs

  13. Ergonomic (human factors) problems in design of NPPs. A review of TMI and Chernobyl accidents

    International Nuclear Information System (INIS)

    Huang Xiangrui; Zheng Fuyu; Gao Jia

    1994-01-01

    The general principle of ergonomic in design of NPPs is given and some causes of TMI and Chernobyl accidents from the view point of human factor engineering are reviewed. The paper also introduces some Ergonomic problems in design, operation and management of earlier NPPs. Some ergonomic principles of man-machine systems design have been described. Some proposals have been suggested for improving human reliability in NPPs

  14. TMI-2 reactor-vessel head removal and damaged-core-removal planning

    International Nuclear Information System (INIS)

    Logan, J.A.; Hultman, C.W.; Lewis, T.J.

    1982-01-01

    A major milestone in the cleanup and recovery effort at TMI-2 will be the removal of the reactor vessel closure head, planum, and damaged core fuel material. The data collected during these operations will provide the nuclear power industry with valuable information on the effects of high-temperature-dissociated coolant on fuel cladding, fuel materials, fuel support structural materials, neutron absorber material, and other materials used in reactor structural support components and drive mechanisms. In addition, examination of these materials will also be used to determine accident time-temperature histories in various regions of the core. Procedures for removing the reactor vessel head and reactor core are presented

  15. Black bear population and connectivity in the Sky Islands of Mexico and the United States

    Science.gov (United States)

    N. E. Lara-Diaz; C. A. Lopez-Gonzalez; H. Coronel-Arellano; A. Gonzalez-Bernal

    2013-01-01

    The Sky Island region is a mountainous region surrounded by grasslands, deserts and intermountain valleys, located between Mexico and the United States. However, different land management and human impact can have an effect on its wildlife populations. Currently, the border wall poses an immediate threat to the survival of black bears (Ursus americanus), considered an...

  16. Three Mile Island nuclear accident and its effect on the surrounding population

    International Nuclear Information System (INIS)

    Tokuhata, G.K.

    1985-01-01

    Although the effect of psychological stress is difficult to predict, these public health concerns should be addressed. The author discusses taking a precautionary route by carefully documenting both the exposed population and its health experiences after the nuclear accident. The already established TMI Population Registry and the TMI Mother-Child Registry provides reliable data bases for longterm followup studies of the health effects (physical, psychological and behavioral), if any, from the TMI nuclear accident for both the general population and for the special cohort of pregnant women and their in-utero exposed children. Causes of death and cancer diagnoses will be routinely ascertained by linkage to the State mortality and cancer incidence files. Data for other physical, psychological and behavioral health indices will be collected every five years, on the basis of a random sample through prospective followup surveys for both cohorts. Regardless of the results of a variety of short-term and long-term studies undertaken, the primary mission of the TMI Health Research Program is to fulfill the need to respond to the much publicised, potentially important public health concerns. Because of the uniqueness of the TMI nuclear accident, thus its historical significance, as well as the scientific need to document health effects of very low dose radiation in humans, the rare opportunity presented by the TMI nuclear accident should not be lost in the pursuit of these important epidemiologic studies

  17. Ductile nappe stacking and refolding in the Cycladic Blueschist Unit: insights from Sifnos Island (south Aegean Sea)

    NARCIS (Netherlands)

    Aravadinou, E.; Xypolias, P.; Chatzaras, V.; Iliopoulos, I.; Gerogiannis, N.

    2016-01-01

    New geological and structural mapping combined with kinematic and amphibole chemistry analyses is used to investigate the deformation history of the Cycladic Blueschist Unit (CBU) on Sifnos Island (Cyclades, Aegean Sea). We concentrate on north Sifnos, an area characterized by exceptionally

  18. 78 FR 22347 - GPU Nuclear Inc., Three Mile Island Nuclear Power Station, Unit 2, Exemption From Certain...

    Science.gov (United States)

    2013-04-15

    ... NUCLEAR REGULATORY COMMISSION [Docket No. 50-320; NRC-2013-0065] GPU Nuclear Inc., Three Mile Island Nuclear Power Station, Unit 2, Exemption From Certain Security Requirements AGENCY: Nuclear... and State Materials and Environmental Management Programs, U.S. Nuclear Regulatory Commission...

  19. Instrumentation and electrical program at the Three Mile Island Unit 2, Technical Integration Office

    International Nuclear Information System (INIS)

    Hecker, L.A.

    1982-01-01

    The Three Mile Island Unit 2 accident of March 28, 1979 presents unique research opportunities that can provide valuable information on nuclear power plant safety philosophy and safety systems performance. The Technical Integration Office at Three Mile Island was established by the Department of Energy to manage a broad-based research and development program. One significant part of this effort is the Instrumentation and Electrical Program, which operates: (1) to identify instruments and electrical components that failed during or since the accident; (2) to test and analyze them in order to identify the causes of failure; and (3) to assess the survivability of those that did not fail. The basis for selection of equipment is discussed, and the testing methodology is described. Also, some results of Instrumentation and Electrical Program work to date are presented

  20. Workshop on data-acquisition and -display systems: directions after TMI

    International Nuclear Information System (INIS)

    1980-11-01

    The accident at Three Mile Island Unit-2 raised questions as to the adequacy of data acquisition and display systems in commercial nuclear power plants. A series of recommendations have developed from the various groups that have analyzed the accident in order to improve the oprator's overview of the plant safety conditions and to facilitate information transfer to technical support centers in emergency situations. This report is the result of an NSAC-sponsored workshop, where the various recommendations and emerging regulatory requirements were reviewed in an attempt to provide an integrated basis for their implementation

  1. Three Mile Island: Impact on electric rate structures

    International Nuclear Information System (INIS)

    Carter, E.F.

    1983-01-01

    The historical significance of the March 28, 1979 accident at TMI-2 has not, can not and will not likely be fully appreciated by our generation. The nuclear industry, the financial community, regulator of electric utilities and the investor-owned electric utilities are beginning to understand this newly added complex dimension that has entered our daily work process. The degree of understanding that each possesses is a function of his involvement in the restoration process in evaluating whether the nuclear option is to survive. The body of material presented herein represents an effort to capsulize the significant associated with providing electricity at reasonable prices to all service classifications that followed in the wake of the March 29, 1979 TMI accident. Highlights of some of the oft-conflicting activities and cost implications are defined. An attempt is also made to quantify the rate changes, subsequent to the accident, as to TMI related and non-TMI related cost. Some of the cost allocation difficulties encountered are also enumerated. There are no classic textbooks, treatise, or manuals on the market that abridge the traditional approaches to ratemaking. Finally, a perspective comparison is made to demonstrate that GPU's rates are still reasonable considering other factors - namely overall inflation and regional electricity prices

  2. Assessment of PASS Effectiveness under Severe Accidents in Nuclear Power Plants

    International Nuclear Information System (INIS)

    Choi, Yu Jung; Lee, Sung Bok; Kim, Hyeong Taek; Lee, Jin Yong

    2008-01-01

    Following the accident at Three Mile Island Unit 2 (TMI-2) on March 28, 1979, the USNRC formed a lessons-learned Task Force to identify and evaluate safety concerns originating with the TMI-2 accident. NUREG-0578 documented the results of the task force effort. One of the recommendations of the task force was for licensees to upgrade the capability to obtain samples from the reactor coolant system and containment atmosphere under high radioactivity conditions and to provide the capability for chemical and spectral analyses of high-level samples on site. NUREG-0737 contained the details of the TMI recommendations that were to be implemented by the licensees. Additional criteria for post accident sampling system(PASS) were issued by Regulatory Guide 1.97. As the results, PASS has been installed on nuclear power plants(NPPs) in Korea as well as United States. However, significant improvements have been achieved since the TMI-2 accident in the areas of understanding risks associated with nuclear plant operations and developing better strategies for managing the response to potential severe accidents at NPPs. Thus, the requirements for PASS have been re-evaluated in some reports. According to the reports, the samples and measurements from PASS do not contribute significantly to emergency management response to severe accidents due to the long analyzing time, 3 hours. Hence, this paper focused on the development of the quantitative analysis methodology to analyze the sequence of the severe accident in Yonggwang nuclear power plants (YGN) and presented the results of the analysis according to the developed methodology

  3. Reactor-building-basement radionuclide and source distribution studies. Volume 3

    International Nuclear Information System (INIS)

    Cox, T.E.; Horan, J.T.; Worku, G.

    1983-06-01

    The Three Mile Island Unit 2 (TMI-2) Reactor Building basement has been sampled several times since August 1979. This report compiles the analytical results and sample history for the liquid and solid samples obtained to date. In addition, basement radiation levels were also obtained using thermoluminescent dosimeters (TLDs). The data obtained will provide information to support ongoing mass balance and source term studies and will aid in characterizing the 282-ft elevation for decontamination planning and dose reduction

  4. The gender gap in reactions to nuclear accidents

    International Nuclear Information System (INIS)

    Wernette, D.R.

    1992-01-01

    Studies have shown that women are less in favor of nuclear power than are men. These differences have been explained by observed gender differences in values, levels of knowledge about nuclear energy, and perceptions of risks and benefits of advanced technology. This study employs data from three national surveys taken in the United States after the Three Mile Island (TMI) and Chernobyl events to identify the extent and nature of gender differences in views toward nuclear energy

  5. Three Mile Island nuclear reactor accident of March 1979. Environmental radiation data: Volume IV. A report to the President's Commission on the Accident at Three Mile Island

    International Nuclear Information System (INIS)

    Bretthauer, E.W.; Grossman, R.F.; Thome, D.J.; Smith, A.E.

    1981-03-01

    This report contains a listing of environmental radiation monitoring data collected in the vicinity of Three Mile Island (TMI) following the March 28, 1979 accident. These data were collected by the EPA, NRC, DOE, HHS, the Commonwealth of Pennsylvania, or the Bethlehem Steel Corporation. The original report was printed in September 1979 and the update was released in December 1979. This volume consists of the following: Table 10 Summary of US Department of Energy (DOE) sampling and analytical procedures; Table 11 Computer printout of environmental data collected by DOE; Table 12 Summary of Commonwealth of Pennsylvania sampling and analytical procedures; Table 13 Computer printout of environmental data collected by the Commonwealth of Pennsylvania; Table 14 Summary of State of New Jersey sampling and analytical procedures; Table 15 Computer printout of data collected by the State of New Jersey

  6. Control and Operation of Islanded Distribution System

    DEFF Research Database (Denmark)

    Mahat, Pukar

    deviation and real power shift. When a distribution system, with all its generators operating at maximum power, is islanded, the frequency will go down if the total load is more than the total generation. An under-frequency load shedding procedure for islanded distribution systems with DG unit(s) based...... states. Short circuit power also changes when some of the generators in the distribution system are disconnected. This may result in elongation of fault clearing time and hence disconnection of equipments (including generators) in the distribution system or unnecessary operation of protective devices...... operational challenges. But, on the other hand, it has also opened up some opportunities. One opportunity/challenge is an islanded operation of a distribution system with DG unit(s). Islanding is a situation in which a distribution system becomes electrically isolated from the remainder of the power system...

  7. Biodiversity and management of the Madrean Archipelago: The Sky Islands of southwestern United States and northwestern Mexico

    Science.gov (United States)

    Leonard H. DeBano; Peter H. Ffolliott; Alfredo Ortega-Rubio; Gerald J. Gottfried; Robert H. Hamre; Carleton B. Edminster

    1995-01-01

    This conference brought together scientists and managers from government, universities, and private organizations to examine the biological diversity and management challenges of the unique "sky island" ecosystems of the mountains of the southwestern United States and northwestern Mexico. Session topics included: floristic resources, plant ecology,...

  8. Surface deposition measurements of the TMI-2 gross decontamination experiment

    International Nuclear Information System (INIS)

    McIssac, C.V.; Hetzer, D.C.

    1982-01-01

    In order to measure the effectiveness of the gross decontamination experiment (principally a water spray technique) performed in the TMI-2 reactor building, the Technical Information and Examination Program's Radiation and Environment personnel made surface activity measurements before and after the experiment. In conjunction with surface sampling, thermoluminescent dosimeter (TLD) and gamma spectrometry measurements were also performed to distinguish between radiation fields and contamination. The surface sampler used to collect samples from external surfaces within the reactor building is a milling tool having four major components: a 1.27-cm constant-speed drill; a drill support assembly that allows setting sample penetration depth; filter cartridges for intake air purification and sample collection; and an air pump that forces air across the surface being sampled and through the sample filter cartridge

  9. Review of human factors R and D in the nuclear power industry

    International Nuclear Information System (INIS)

    Parris, H.L.

    1986-01-01

    The history of human factors (HF) R and D in the nuclear power industry can clearly be divided into two phases: pre- and post-Three Mile Island (TMI). Pre-TMI, most people in the industry were unfamiliar with the discipline and its contributions to military and space system designs, and the number of HF professionals involved with nuclear power could essentially be counted on the fingers of two hands. Consequently, there was little research into the improvement of plant man/machine interfaces. The picture changed dramatically in the aftermath of TMI as investigation after investigation pointed to deficiencies in the operator/control room interface, training, procedures, communications, and organizational effectiveness. This paper first outlines pre-TMI events, then examines the post-TMI scenario, and concludes with summary observations and suggestions for future efforts

  10. Severe fuel-damage scoping test performance

    International Nuclear Information System (INIS)

    Gruen, G.E.; Buescher, B.J.

    1983-01-01

    As a result of the Three Mile Island Unit-2 (TMI-2) accident, the Nuclear Regulatory Commission has initiated a severe fuel damage test program to evaluate fuel rod and core response during severe accidents similar to TMI-2. The first test of Phase I of this series has been successfully completed in the Power Burst Facility at the Idaho National Engineering Laboratory. Following the first test, calculations were performed using the TRAC-BD1 computer code with actual experimental boundary conditions. This paper discusses the test conduct and performance and presents the calculated and measured test bundle results. The test resulted in a slow heatup to 2000 K over about 4 h, with an accelerated reaction of the zirconium cladding at temperatures above 1600 K in the lower part or the bundle and 2000 K in the upper portion of the bundle

  11. Controlling hydrogen behavior in light water reactors

    International Nuclear Information System (INIS)

    Cullingford, H.S.; Edeskuty, F.J.

    1981-01-01

    In the aftermath of the incident at Three Mile Island Unit 2 (TMI-2), a new and different treatment of the Light Water Reactor (LWR) risks is needed for public safety because of the specific events involving hydrogen generation, transport, and behavior following the core damage. Hydrogen behavior in closed environments such as the TMI-2 containment building is a complex phenomenon that is not fully understood. Hence, an engineering approach is presented for prevention of loss of life, equipment, and environment in case of a large hydrogen generation in an LWR. A six-level defense strategy is described that minimizes the possibility of ignition of released hydrogen gas and otherwise mitigates the consequences of hydrogen release. Guidance is given to reactor manufacturers, utility companies, regulatory agencies, and research organizations committed to reducing risk factors and insuring safety of life, equipment, and environment

  12. Potential impact of licensee default on cleanup of TMI-2. Technical report

    International Nuclear Information System (INIS)

    Roberts, J.O.; Saltzman, J.

    1980-11-01

    Financial repercussions of the accident at Three Mile Island Unit 2 on the ability of the Licensee, Metropolitan Edison Co., to complete cleanup of the facility are examined. Potential impacts of licensee default on cleanup and alternatives to minimize the potential of bankruptcy are discussed. Specific recommendations are made regarding steps the Nuclear Regulatory Commission might take in keeping with its regulatory functions and its mission to protect the public health and safety

  13. Answers to questions about removing krypton from the Three Mile Island, Unit 2 reactor building. Public information report

    International Nuclear Information System (INIS)

    1980-05-01

    This document presents answers to frequently asked questions about the probable effects of controlled releases of the krypton presently contained within the reactor building of Three Mile Island, Unit 2. Also answered are questions about alternative means for removing the krypton

  14. NRC action plan developed as a result of the TMI-2 accident. Volume 2

    International Nuclear Information System (INIS)

    1980-05-01

    The Action Plan provides a comprehensive and integrated plan for all actions judged necessary by the Nuclear Regulatory Commission to correct or improve the regulation and operation of nuclear facilities based on the experience from the accident at the Three Mile Island, Unit 2, nuclear facility and the official studies and investigations of the accident. The tables included in this volume list the recommendations from the various organizations and task forces investigating the accident at Three Mile Island. The tables are annotated to provide easy references to the associated parts of the Action Plan in Volume 1. The tables are also annotated to provide a shorthand indication of how the various recommendations are treated in the Action Plan

  15. Quick look report, Entry 3: Three Mile Island Unit 2, October 16, 1980

    International Nuclear Information System (INIS)

    1981-07-01

    This report summarizes tasks performed during the third entry at Three Mile Island Unit 2. During the entry into containment, which was made on October 16, 1980, additional beta, gamma, and neutron surveys were performed to supplement data obtained on previous entries. In addition, several maintenance tasks were completed including testing the operation of both equipment hatch doors, replacing a loose parts monitor system pre-amplifier, and removing a source range monitor. The five-man entry team accomplished these tasks in about 1-1/2 hours

  16. Evaluation of long-term post-accident core cooling of Three Mile Island Unit 2

    Energy Technology Data Exchange (ETDEWEB)

    None

    1979-04-15

    On the basis of current understanding of the accident scenario and available data, the staff reports here on its evaluation of the condition of the core and the core flow resistance as it might affect ability to cool the core by natural circulation. The natural circulation cooling capability of TMI-2 for the estimated core flow resistance and a variety of other conditions is evaluated and a comparison of the Base Case and off-nominal plant configurations is presented. The potential for and effects of natural convection core cooling are addressed, and the staff recommendations for reactor performance acceptance criteria upon initiation of natural convection are presented.

  17. Analysis of the effects of the TMI accident on the public health after nearly a quarter of Century; Analisis de los efectos del accidente de TMI sobre la salud del publico a casi un cuarto de siglo

    Energy Technology Data Exchange (ETDEWEB)

    Arredondo S, C [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

    2003-07-01

    After almost a quarter of century of the accident happened in the nuclear plant of the Three Miles Island (TMI), they continue being published studies that analyze the effects in the population's health that lived in the surroundings of the plant. In this work a review of the studies but outstanding carried out to the date is made, considering with certain detail the made suppositions, the methods used and the obtained results. Since some studies contradict those suppositions, methods and results of the other ones, we seek to make one impartial and objective evaluation of all the analyses to obtain coherent conclusions and without bias. The underlying concepts to the epidemiological studies were revised, making emphasis in those that can introduce some bias. The models that exist on the effect in the health of the population of low dose were also revised. It was also revised the published correspondence in the scientific literature among the different authors, analyzing the different arguments, to decide which are those of more validity. A very important factor at this time is that a lapse has elapsed sufficiently appropriate as to think that the probability of changes in the tendencies of observed cancer diseases it changes. In our analyses it was tried to take into account that the suppositions and methodologies used in the studies were supported by those facts that can be checked by the existent registrations to the date and not by anecdotes or preconceived ideas. Lastly the conclusions of this work of review and analysis are presented. (Author)

  18. Analysis of the effects of the TMI accident on the public health after nearly a quarter of Century; Analisis de los efectos del accidente de TMI sobre la salud del publico a casi un cuarto de siglo

    Energy Technology Data Exchange (ETDEWEB)

    Arredondo S, C. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)]. e-mail: cas@nuclear.inin.mx

    2003-07-01

    After almost a quarter of century of the accident happened in the nuclear plant of the Three Miles Island (TMI), they continue being published studies that analyze the effects in the population's health that lived in the surroundings of the plant. In this work a review of the studies but outstanding carried out to the date is made, considering with certain detail the made suppositions, the methods used and the obtained results. Since some studies contradict those suppositions, methods and results of the other ones, we seek to make one impartial and objective evaluation of all the analyses to obtain coherent conclusions and without bias. The underlying concepts to the epidemiological studies were revised, making emphasis in those that can introduce some bias. The models that exist on the effect in the health of the population of low dose were also revised. It was also revised the published correspondence in the scientific literature among the different authors, analyzing the different arguments, to decide which are those of more validity. A very important factor at this time is that a lapse has elapsed sufficiently appropriate as to think that the probability of changes in the tendencies of observed cancer diseases it changes. In our analyses it was tried to take into account that the suppositions and methodologies used in the studies were supported by those facts that can be checked by the existent registrations to the date and not by anecdotes or preconceived ideas. Lastly the conclusions of this work of review and analysis are presented. (Author)

  19. Accident at Three Mile Island nuclear power plant and lessons learned

    International Nuclear Information System (INIS)

    Ashrafi, A.; Farnoudi, F.; Tochai, M.T.M.; Mirhabibi, N.

    1986-01-01

    On March 28, 1979, the TMI, unit 2 nuclear power plant experienced a loss of coolant accident (LOCA) which has had a major impact among the others, upon the safety of nuclear power plants. Although a small part of the reactor core melted in this accident, but due to well performance of the vital safety equipment, there was no serious radioactivity release to the environment, and the accident has had no impact on the basic safety goals. A brief scenario of the accident, its consequences and the lessons learned are discussed

  20. Mechanical decontamination techniques for floor drain systems

    International Nuclear Information System (INIS)

    Palau, G.L.

    1987-01-01

    The unprecedented nature of cleanup activities at Three Mile Island Unit 2 (TMI-2) following the 1979 accident has necessitated the development of new techniques to deal with radiation and contamination in the plant. One of these problems was decontamination of floor drain systems, which had become highly contaminated with various forms of dirt and sludge containing high levels of fission products and fuel from the damaged reactor core. The bulk of this contamination is loosely adherent to the drain pipe walls; however, significant amounts of contamination have become incorporated into pipe wall oxide and corrosion layers and embedded in microscopic pits and fissures in the pipe wall material. The need to remove this contamination was recognized early in the TMI-2 cleanup effort. A program consisting of development and laboratory testing of floor drain decontamination techniques was undertaken early in the cleanup with support from the Electric Power Research Institute (EPRI). Based on this initial research, two techniques were judged to show promise for use at TMI-2: a rotating brush hone system and a high-pressure water mole nozzle system. Actual use of these devices to clean floor drains at TMI-2 has yielded mixed decontamination results. The decontamination effectiveness that has been obtained is highly dependent on the nature of the contamination in the drain pipe and the combination of decontamination techniques used

  1. Fission-product transfer in the TMI-2 purification system

    International Nuclear Information System (INIS)

    Cox, T.E.

    1982-01-01

    The makeup purification system at TMI-2 operated during the course of the accident, processing water from the reactor coolant system cold leg at an average flow rate not exceeding 4.4 x 10 - 3 m 3 /s. The system operated through most of 28 March 1979, finally being shutdown when the system filters or demineralizers, or both, plugged and overpressured. The system was restored to service on 29 March 1979 at a flow rate of about 1.6 x 10 - 3 m 3 /s. Subsequent radiation readings of the system filters and demineralizer cubicles revealed that these components contained appreciable levels of radionuclides. One project being implemented within the Radiation and Environment Program of the Technical Integration Office is to analyze the demineralizer resins and filters, as they are removed from the makeup purification system. The object is to determine the quantity and composition of the material retained by the resins and filters

  2. TMI-2 instrument nozzle examinations at Argonne National Laboratory

    International Nuclear Information System (INIS)

    Neimark, L.A.; Shearer, T.L.; Purohit, A.; Hins, A.G.

    1993-09-01

    Six of the 14 instrument-penetration-tube nozzles removed from the lower head of TMI-2 were examined to identify damage mechanisms, provide insight to the fuel relocation scenario, and provide input data to the margin-to-failure analysis. Visual inspection, gamma scanning, metallography, microhardness measurements, and scanning electron microscopy were used to obtain the desired information. The results showed varying degrees of damage to the lower head nozzles, from ∼50% melt-off to no damage at all to near-neighbor nozzles. The elevations of nozzle damage suggested that the lower elevations (near the lower head) were protected from molten fuel, apparently by an insulating layer of fuel debris. The pattern of nozzle damage was consistent with fuel movement toward the hot-spot location identified in the vessel wall. Evidence was found for the existence of a significant quantity of control assembly debris on the lower head before the massive relocation of fuel occurred

  3. Three Mile Island, Unit 2, radiation protection program: report of the special panel

    International Nuclear Information System (INIS)

    Meinhold, C.B.; Murphy, T.D.; Neely, D.R.; Kathren, R.L.; Rich, B.L.; Stone, G.F.; Casey, W.R.

    1979-12-01

    A special panel was appointed by the Director of Nuclear Reactor Regulation, NRC, to review the radiation protection program at Three Mile Island Unit 2. The Panel confirmed several management and technical deficiencies in the program. Recent major GPU/Met Ed commitments and actions demonstrated a major change in management attitude. The Panel concluded that exposures to personnel can be maintained to as low as is reasonably achievable while limited preparatory recovery work continues and when further needed improvements are implemented as needed, the radiation safety program will be able to support major recovery activities

  4. Three Mile Island, Unit 2, radiation protection program: report of the special panel

    Energy Technology Data Exchange (ETDEWEB)

    Meinhold, C. B. [Brookhaven National Lab., Upton, NY (United States); Murphy, T. D. [Nuclear Regulatory Commission, Washington, DC (United States); Neely, D. R. [Nuclear Regulatory Commission, Washington, DC (United States); Kathren, R. L. [Batelle Pacific Northwest Lab. (United States); Rich, B. L. [Exxon Nuclear Idaho Co., Inc. ID (United States); Stone, G. F. [Tennessee Valley Authority, Chattanooga, TN (United States); Casey, W. R. [Brookhaven National Lab., Upton, NY (United States)

    1979-12-01

    A special panel was appointed by the Director of Nuclear Reactor Regulation, NRC, to review the radiation protection program at Three Mile Island Unit 2. The Panel confirmed several management and technical deficiencies in the program. Recent major GPU/Met Ed commitments and actions demonstrated a major change in management attitude. The Panel concluded that exposures to personnel can be maintained to as low as is reasonably achievable while limited preparatory recovery work continues and when further needed improvements are implemented as needed, the radiation safety program will be able to support major recovery activities.

  5. Neutronic analysis of the Three Mile Island Unit 2 ex-core detector response

    International Nuclear Information System (INIS)

    Malloy, D.J.; Chang, Y.I.

    1981-10-01

    A neutronic analysis has been made with respect to the ex-core neutron detector response during the TMI-2 incident. A series of transport theory calculations quantified the impact upon the detector count rate of various core and downcomer conditions. In particular, various combinations of coolant void content and spatial distributions were investigated to yield the resulting transmission of the photoneutron source to the detector. The impact of a hypothetical distributed source within the downcomer region was also examined in order to simulate the potential effect of the release of neutron producing fission products into the coolant. These results are then offered as potential explanations for the anomalous behavior of the detector during the period of approx. 20 minutes through approx. 3 hours following the reactor scram

  6. Direction on characterization of fuel debris for defueling process in Fukushima Daiichi Nuclear Power Station

    International Nuclear Information System (INIS)

    Yano, Kimihiko; Kitagaki, Toru; Ikeuchi, Hirotomo; Wakui, Ryohei; Higuchi, Hidetoshi; Kaji, Naoya; Koizumi, Kenji; Washiya, Tadahiro

    2013-01-01

    For the decommissioning of Fukushima Daiichi Nuclear Power Station (1F), defueling of the fuel debris in the reactor core of Units 1-3 is planned to start within 10 years. Preferential items in the characterization of the fuel debris were identified for this work, in which the procedure and handling tools were assumed on the basis of information on 1F and experience after the Three Mile Island Unit 2 (TMI-2) accident. The candidates for defueling tools for 1F were selected from among the TMI- 2 defueling tools. It was found that they could be categorized into six groups according to their operating principles. The important properties of the fuel debris for defueling were selected considering the effect of the target materials on the tool performance. The selected properties are shape, size, density, thermal conductivity, heat capacity, melting point, hardness, elastic modulus, and fracture toughness. Of these properties, the mechanical properties (hardness, elastic modulus, fracture toughness) were identified as preferential items, because too few data on these characteristics of fuel debris are available in past severe accident studies. (authors)

  7. Progress in the U.S. nuclear utility industry 1979-1989

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1989-07-01

    March 28, 1979 changed the course of the commercial U.S. nuclear utility industry. An accident at Three Mile Island Nuclear Station Unit 2 in Middletown, Pennsylvania damaged the reactor's fuel core, as well as the industry's reputation and confidence. In the months after the event, the president of the United States, the nuclear industry, the public, government regulators and the media sought answers to many questions. Among the most important were, how and why did the accident happen? The President's Commission on the Accident at TMI, the Kemeny Commission, was formed to address these questions. Four major causes were identified by the commission: - inadequate or inappropriate operator training; - mechanical problems and faulty instrumentation; - poor control room design; - communication failures at the facility and in information exchange within the industry. Of even greater importance was another question: How could another such accident be prevented? A look at the industry's progress in the 10 years since the TMI accident shows this question has been vigorously addressed and that corrective actions have been taken.

  8. Progress in the U.S. nuclear utility industry 1979-1989

    International Nuclear Information System (INIS)

    1989-01-01

    March 28, 1979 changed the course of the commercial U.S. nuclear utility industry. An accident at Three Mile Island Nuclear Station Unit 2 in Middletown, Pennsylvania damaged the reactor's fuel core, as well as the industry's reputation and confidence. In the months after the event, the president of the United States, the nuclear industry, the public, government regulators and the media sought answers to many questions. Among the most important were, how and why did the accident happen? The President's Commission on the Accident at TMI, the Kemeny Commission, was formed to address these questions. Four major causes were identified by the commission: - inadequate or inappropriate operator training; - mechanical problems and faulty instrumentation; - poor control room design; - communication failures at the facility and in information exchange within the industry. Of even greater importance was another question: How could another such accident be prevented? A look at the industry's progress in the 10 years since the TMI accident shows this question has been vigorously addressed and that corrective actions have been taken

  9. TRAC analysis of steam-generator overfill transients for TMI-1

    International Nuclear Information System (INIS)

    Bassett, B.

    1983-01-01

    A reactor safety issue concerning the overfilling of once-through steam generators leading to combined primary/secondary blowdown has been raised recently. A series of six calculations, performed with the LWR best-estimate code, TRAC-PD2, on a Babcock and Wilcox Plant (TMI-1), was performed to investigate this safety issue. The base calculation assumed runaway main feedwater to one steam generator causing it to overfill and to break the main steam line. Four additional calculations build onto the base case with combinations of a pump-seal failure, a steam-generator tube rupture, and the pilot-operated relief valve not reseating. A sixth calculation involved only the rupture of a single steam-generator tube. The results of these analyses indicate that for the transients investigated, the emergency cooling system provided an adequate make-up coolant flow to mitigate the accidents

  10. 75 FR 44292 - Northern States Power Company; Prairie Island Nuclear Generating Plant, Units 1 and 2; Notice of...

    Science.gov (United States)

    2010-07-28

    ... and DPR-60] Northern States Power Company; Prairie Island Nuclear Generating Plant, Units 1 and 2... assessment, and behavioral observation) of the unescorted access authorization program when making the... under consideration to determine whether it met the criteria established in NRC Management Directive (MD...

  11. Interview with Pennsylvania PUC chairman Susan M. Shanaman

    International Nuclear Information System (INIS)

    Utroska, D.

    1981-01-01

    Chairman Shanaman notes that Pennsylvania law justifies the Public Utility Commission (PUC) refusal to charge ratepayers for the cost of Three Mile Island units 1 and 2, neither of which are providing service, because ratepayers are already paying the costs of replacement power. The PUC chairman points to other service territories around the country where rates are kept below national averages because the average income level is low. The Metropolitan Edison Company is seeking Federal relief as well as legislative permission to put TMI-1 back into the rate base in fairness to ratepayers, but the PUC does not see bankruptcy for the utility as an appropriate way to force Federal assistance. The Administration needs to understand the local impact of Federal policies, especially those which are incompatible with state situations. Appropriate involvement includes nuclear waste research and underwriting some of the cleanup costs of onsite accidents that are too large for a single utility to handle. Chairman Shanaman feels that ratepayers should contribute to the insurance premium for future accidents, but not retroactively to support TMI-2. Nuclear power plant construction in the US will not progress until the issues of TMI-2 are resolved

  12. Report of Special Review Group, Office of Inspection and Enforcement, on lessons learned from Three Mile Island

    International Nuclear Information System (INIS)

    1979-12-01

    The IE Special Review Group (SRG) was constituted by V. Stello, Jr., Director, Office of Inspection and Enforcement (IE), in a memorandum to IE Management dated July 12, 1979, to review the lessons learned from the Three Mile Island (TMI) Accident. This memorandum is enclosed as Appendix A to this report. The members of SRG were selected on the basis of their qualifications and experience in IE. SRG members were selected mainly from Regional Offices. Several of the members had been assigned to Three Mile Island following the accident. Several members had been assigned to the Incident Response Center in NRC Headquarters following the accident. Several other members had no direct involvement in responding to the accident. SRG was divided into two groups, one to review the preventive aspects and one to review the responsive aspects. This action was taken so that the qualifications of individual SRG members could be utilized most efficiently across the spectrum of matters considered. Although for the most part the two groups worked separately, each member of SRG has reviewed the entire report and concurs in its contents

  13. GHRSST L2P Gridded Global Subskin Sea Surface Temperature from the Tropical Rainfall Mapping Mission (TRMM) Microwave Imager (TMI) (GDS version 1)

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — The Tropical Rainfall Measuring Mission (TRMM) Microwave Imager (TMI) is a well calibrated passive microwave radiometer, similar to SSM/I, that contains lower...

  14. Autonomous control of inverter-interfaced Distributed Generation units for harmonic current filtering and resonance damping in an islanded microgrid

    DEFF Research Database (Denmark)

    Wang, Xiongfei; Blaabjerg, Frede; Chen, Zhe

    2012-01-01

    Harmonic current filtering and resonance damping have become important concerns on the control of an islanded microgrids. To address these challenges, this paper proposes a control method of inverter-interfaced Distributed Generation (DG) units, which can autonomously share harmonic currents and ...

  15. NRC plan for cleanup operations at Three Mile Island Unit 2

    International Nuclear Information System (INIS)

    Lo, R.; Snyder, B.

    1982-02-01

    This NRC Plan, which defines NRC's functional role in cleanup operations at Three Mile Island Unit 2 and outlines NRC's regulatory responsibilities in fulfilling this role, is the first revision to the initial plan issued in July 1980 (NUREG-0698). Since 1980, a number of policy developments have occurred which will have an impact on the course of cleanup operations. This revision reflects these developments in the area of NRC's review and approval process with regard to cleanup operations as well as NRC's interface with the Department of Energy's involvement in the cleanup and waste disposal. This revision is also intended to update the cleanup schedule by presenting the cleanup progress that has taken place and NRC's role in ongoing and future cleanup activities

  16. Tourism impacts of Three Mile Island and other adverse events: implications for Lincoln County and other rural counties bisected by radioactive wastes intended for Yucca Mountain

    International Nuclear Information System (INIS)

    Himmelberger, J.J.; Baughman, M.; Ogneva-Himmelberger, Y.A.

    1995-01-01

    Whether the proposed Yucca Mountain nuclear waste repository system will adversely impact tourism in southern Nevada is an open question of particular importance to visitor-oriented rural counties bisected by planned waste transportation corridors (highway or rail). As part of one such county's repository impact assessment program, tourism implications of Three Mile Island (TMI) and other major hazard events have been revisited to inform ongoing county-wide socioeconomic assessments and contingency planning efforts. This paper summarizes key research implications of such research as applied to Lincoln County, Nevada. Implications for other rural counties are discussed in light of the research findings

  17. Nuclear accident at Three Mile Island: its effect on a local community

    International Nuclear Information System (INIS)

    Behler, G.T. Jr.

    1987-01-01

    This dissertation consists of a longitudinal case study of the extent to which the structure of community power in Riverside, (a pseudonym) Pennsylvania (the largest community located within five miles of the Three Mile Island nuclear facility) changed as a result of the March, 1979 accident. The investigation centers around testing a basic working hypothesis. Simply stated, this working hypothesis argues that Riverside's power structure has become more pluralistic in response to the Three Mile Island nuclear accident. An additional corollary to this working hypothesis is also tested. This corollary asserts that many of Riverside's community power actors have become much more cosmopolitan in their political-action tactics and problem-solving orientations as a results of the TMI crisis. The aforementioned working hypothesis and associated corollary are tested via the combined utilization of three different techniques for measuring the distribution of social power. The findings of the study clearly demonstrate the existence of increased pluralism, politicization, and cosmopolitanism within Riverside since March of 1979. Furthermore, these research results, and the entire dissertation itself, contribute to a number of subfields within the discipline of sociology. In particular,contributions are noted for the subfields of community power, social movements, and disaster research

  18. Diomede Islands, Bering Straight

    Science.gov (United States)

    2008-01-01

    The Diomede Islands consisting of the western island Big Diomede (also known as Imaqliq, Nunarbuk or Ratmanov Island), and the eastern island Little Diomede (also known as Krusenstern Island or Inaliq), are two rocky islands located in the middle of the Bering Strait between Russia and Alaska. The islands are separated by an international border and the International Date Line which is approximately 1.5 km from each island; you can look from Alaska into tomorrow in Russia. At the closest land approach between the United States, which controls Little Diomede, and Russia, which controls Big Diomede, they are 3 km apart. Little Diomede Island constitutes the Alaskan City of Diomede, while Big Diomede Island is Russia's easternmost point. The first European to reach the islands was the Russian explorer Semyon Dezhnev in 1648. The text of the 1867 treaty finalizing the sale of Alaska uses the islands to designate the border between the two nations. The image was acquired July 8, 2000, covers an area of 13.5 x 10.8 km, and is located at 65.8 degrees north latitude, 169 degrees west longitude. The U.S. science team is located at NASA's Jet Propulsion Laboratory, Pasadena, Calif. The Terra mission is part of NASA's Science Mission Directorate.

  19. Decentralized Method for Load Sharing and Power Management in a Hybrid Single/Three-Phase-Islanded Microgrid Consisting of Hybrid Source PV/Battery Units

    DEFF Research Database (Denmark)

    Karimi, Yaser; Oraee, Hashem; Guerrero, Josep M.

    2017-01-01

    This paper proposes a new decentralized power management and load sharing method for a photovoltaic based, hybrid single/three-phase islanded microgrid consisting of various PV units, battery units and hybrid PV/battery units. The proposed method is not limited to the systems with separate PV...... in different load, PV generation and battery conditions is validated experimentally in a microgrid lab prototype consisted of one three-phase unit and two single-phase units....

  20. One million served: Rhode Island`s recycling facility

    Energy Technology Data Exchange (ETDEWEB)

    Malloy, M.G.

    1997-11-01

    Rhode Island`s landfill and adjacent materials recovery facility (MRF) in Johnston, both owned by the quasi-public Rhode Island Resource Recovery Corp. (RIRRC, Johnston), serve the entire state. The $12-million recycling facility was built in 1989 next to the state`s sole landfill, the Central Landfill, which accepts only in-state trash. The MRF is operated for RIRRC by New England CRInc. (Hampton, N.H.), a unit of Waste Management, Inc. (WMI, Oak Brook, Ill.). It handles a wide variety of materials, from the usual newspaper, cardboard, and mixed containers to new streams such as wood waste, scrap metal, aseptic packaging (milk and juice boxes), and even textiles. State municipalities are in the process of adding many of these new recyclable streams into their curbside collection programs, all of which feed the facility.

  1. Working with the states to transport TMI-2 core debris

    International Nuclear Information System (INIS)

    Smith, T.A.; Anselmo, A.A.

    1989-01-01

    This reports that close communications with state officials has been a key factor in success of the Three Mile Island Unit 2 core debris shipments. The U.S. Department of Energy made extensive efforts to provide state officials with schedule information, answer technical questions, and satisfy concerns. Communications started before the campaign and continued during shipments and at intervals between shipments. Those efforts led to good working relationships with the states, kept governors and other state officials informed so they could respond to public concerns, facilitated state inspections, and provided avenues to avoid conflict and potential litigation. Good communications and working relationships with state officials also greatly benefited the community relations effort for the campaign

  2. Community Relations for the Transport of TMI-2 Core Debris

    International Nuclear Information System (INIS)

    Smith, T.A.

    1988-01-01

    This paper describes community relations for the transport of Three Mile Island Unit 2 core debris, before and during the first two years of the campaign. The author defines community relations as interactions with groups or individuals to influence public perception. Members of Congress, state and local officials, news media, special interest groups, and private citizens are included in the definition of community. The paper discusses issues of concern to the community, level of interest generated by the transport campaign, events that kept community interest focused on the campaign, and communication techniques employed to provide the community with factual information and to generate public confidence. Finally, the paper describes lessons learned from the community relations effort. (author)

  3. Geology of Tok Island, Korea: eruptive and depositional processes of a shoaling to emergent island volcano

    Science.gov (United States)

    Sohn, Y. K.

    1995-02-01

    Detailed mapping of Tok Island, located in the middle of the East Sea (Sea of Japan), along with lithofacies analysis and K-Ar age determinations reveal that the island is of early to late Pliocene age and comprises eight rock units: Trachyte I, Unit P-I, Unit P-II, Trachyandesite (2.7±0.1 Ma), Unit P-III, Trachyte II (2.7±0.1 Ma), Trachyte III (2.5±0.1 Ma) and dikes in ascending stratigraphic order. Trachyte I is a mixture of coherent trachytic lavas and breccias that are interpreted to be subaqueous lavas and related hyaloclastites. Unit P-I comprises massive and inversely graded basaltic breccias which resulted from subaerial gain flows and subaqueous debris flows. A basalt clast from the unit, derived from below Trachyte I, has an age of 4.6±0.4 Ma. Unit P-II is composed of graded and stratified lapilli tuffs with the characteristics of proximal pyroclastic surge deposits. The Trachyandesite is a massive subaerial lava ponded in a volcano-tectonic depression, probably a summit crater. A pyroclastic sequence containing flattened scoria clasts (Unit P-III) and a small volume subaerial lava (Trachyte II) occur above the Trachyandesite, suggesting resumption of pyroclastic activity and lava effusion. Afterwards, shallow intrusion of magma occurred, producing Trachyte III and trachyte dikes. The eight rock units provide an example of the changing eruptive and depositional processes and resultant succession of lithofacies as a seamount builds up above sea level to form an island volcano: Trachyte I represents a wholly subaqueous and effusive stage; Units P-I and P-II represent Surtseyan and Taalian eruptive phases during an explosive transitional (subaqueous to emergent) stage; and the other rock units represent later subaerial effusive and explosive stages. Reconstruction of volcano morphology suggests that the island is a remnant of the south-western crater rim of a volcano the vent of which lies several hundred meters to the north-east.

  4. Answers to questions about updated estimates of occupational radiation doses at Three Mile Island, Unit 2

    International Nuclear Information System (INIS)

    1983-12-01

    The purpose of this question and answer report is to provide a clear, easy-to-understand explanation of revised radiation dose estimates which workers are likely to receive over the course of the cleanup at Three Mile Island, Unit 2, and of the possible health consequences to workers of these new estimates. We will focus primarily on occupational dose, although pertinent questions about public health and safety will also be answered

  5. Workshop on data-acquisition and -display systems: directions after TMI. [PWR; BWR

    Energy Technology Data Exchange (ETDEWEB)

    1980-11-01

    The accident at Three Mile Island Unit-2 raised questions as to the adequacy of data acquisition and display systems in commercial nuclear power plants. A series of recommendations have developed from the various groups that have analyzed the accident in order to improve the oprator's overview of the plant safety conditions and to facilitate information transfer to technical support centers in emergency situations. This report is the result of an NSAC-sponsored workshop, where the various recommendations and emerging regulatory requirements were reviewed in an attempt to provide an integrated basis for their implementation.

  6. Neocolonialism and Health Care Access among Marshall Islanders in the United States.

    Science.gov (United States)

    Duke, Michael R

    2017-09-01

    In the Marshall Islands, a history of extensive nuclear weapons testing and covert biomedical research, coupled with the U.S.'s ongoing military presence in the country, has severely compromised the health of the local population. Despite the U.S.'s culpability in producing ill health along with high rates of emigration from the islands to the mainland United States, the large portion of Marshallese who reside in the United States face substantial barriers to accessing health care. Drawing from ongoing field research with a Marshallese community in Arkansas, this article explores the multifaceted impediments that U.S.-based Marshall Islanders face in receiving medical treatment. Calling on an expansive and inclusive notion of neocolonialism, I argue that Marshallese structural vulnerability with regard to health and health care treatment derives from their status as neocolonial subjects and from their limited claims to health-related deservingness associated with this status. [Marshall Islanders, health care access, neocolonialism, radiation exposure, immigrant health] L̗ōmn̗ak ko rōttin̗o: Ilo M̗ajel̗, juon bwebwenato kōn kōmmālmel im nuclear baam̗ ko im ekkatak ko rōttin̗o̗ kōn wāwein an baijin ko jelōt armej, barāinwōt an to an ri tarinae ro an Amedka pād ilo aelōn̄ kein, em̗ōj an jelōt ājmour an armej ro ilo aelōn̄ kein. Men̄e alikkar bwe Amedka in ear jino nan̄inmej kein im ej un eo armej rein rej em̗m̗akūt jān āne kein āne er n̄an ioon Amedka, elōn̄ iaan ri M̗ajel̗ rein rej jelm̗ae elōn̄ apan̄ ko n̄an aer del̗o̗n̄e jikin ājmour ko. Jān ekkatak eo ej bōk jikin kiō, jerbal in ej etali kabōjrak rak kein rōlōn̄ im armej in M̗ajel̗ ro ioon Amedka in rej jelm̗ae ilo aer jibadōk lo̗k jikin taktō. Ilo an kar Amedka jibadōk juon jea eo eutiej imejān lal̗ in, ij kwal̗ok juon aō akweelel bwe apan̄ ko an armej in M̗ajel̗ ikijjeen ājmour im jikin taktō ej itok jān aer kar ri kōm̗akoko ilo an kar

  7. Analysis of the effects of the TMI accident on the public health after nearly a quarter of Century

    International Nuclear Information System (INIS)

    Arredondo S, C.

    2003-01-01

    After almost a quarter of century of the accident happened in the nuclear plant of the Three Miles Island (TMI), they continue being published studies that analyze the effects in the population's health that lived in the surroundings of the plant. In this work a review of the studies but outstanding carried out to the date is made, considering with certain detail the made suppositions, the methods used and the obtained results. Since some studies contradict those suppositions, methods and results of the other ones, we seek to make one impartial and objective evaluation of all the analyses to obtain coherent conclusions and without bias. The underlying concepts to the epidemiological studies were revised, making emphasis in those that can introduce some bias. The models that exist on the effect in the health of the population of low dose were also revised. It was also revised the published correspondence in the scientific literature among the different authors, analyzing the different arguments, to decide which are those of more validity. A very important factor at this time is that a lapse has elapsed sufficiently appropriate as to think that the probability of changes in the tendencies of observed cancer diseases it changes. In our analyses it was tried to take into account that the suppositions and methodologies used in the studies were supported by those facts that can be checked by the existent registrations to the date and not by anecdotes or preconceived ideas. Lastly the conclusions of this work of review and analysis are presented. (Author)

  8. Controlled air incinerator conceptual design study

    International Nuclear Information System (INIS)

    1982-01-01

    This report presents a conceptual design study for a controlled air incinerator facility for incineration of low level combustible waste at Three Mile Island Unit 2 (TMI-2). The facility design is based on the use of a Helix Process Systems controlled air incinerator. Cost estimates and associated engineering, procurement, and construction schedules are also provided. The cost estimates and schedules are presented for two incinerator facility designs, one with provisions for waste ash solidification, the other with provisions for packaging the waste ash for transport to an undefined location

  9. Safety requirement of the nuclear power plants, after TMI-2 accident and their possible implementation on Bushehr NPP

    International Nuclear Information System (INIS)

    Mirhabibi, N.; Tochai, M.T.M.; Ashrafi, A.; Farnoudi, E.

    1985-01-01

    Based on the lessons learned from the TMI-2 accident and other research and developments, many improvements have been required for the design, manufacturing and operation of nuclear power plants in recent years. These requirements have already been implemented to the plants in operation and considered as new safety requirements for new plants. In the present paper these requirements and their possible implementation on Bushehr NPP are discussed. (Author)

  10. Quick look report, entry 4: Three Mile Island Unit 2, November 13, 1980

    International Nuclear Information System (INIS)

    Eidam, G.E.

    1981-06-01

    This report summarizes tasks performed during entry 4 at Three Mile Island Unit 2. During the entry into containment, which was made on November 13, 1980, additional beta and gamma surveys were conducted to supplement data acquired on previous entries. A decontamination test was completed on Elevation 305. Power receptables tested on Elevation 305 were deenergized, but receptacles on Elevation 347 were energized. Still photography was acquired of Elevations 305 and 347. During the entry, 86 still photographs were taken. Videotaping (color and black and white) was done on Elevations 305 and 347, but lighting on both elevations was insufficient for high-quality video

  11. Working with the States to Transport TMI-2 Core Debris

    International Nuclear Information System (INIS)

    Smith, T.A.; Anselmo, A.A.

    1989-01-01

    Close communications with state officials has been a key factor in success of the Three Mile Island Unit 2 core debris shipments. The U.S. Department of Energy made extensive efforts to provide state officials with schedule information, answer technical questions, and satisfy concerns. Communications started before the campaign and continued during shipments and at intervals between shipments. Those efforts led to good working relationships with the states, kept governors and other state officials informed so they could respond to public concerns, provided the opportunity to recognize and respond to specific state concerns, facilitated state inspections, and provided avenues to avoid conflict and potential litigation. Good communications and working relationships with state officials also greatly benefited the community relations effort for the campaign. (author)

  12. Title list, publicly available documents: Three Mile Island Unit 1, Docket 50-289 - cumulated to November 16, 1979

    International Nuclear Information System (INIS)

    1979-01-01

    This title list of publicly available documents pertaining to Three Mile Island Unit 1, Docket 50-289, includes all documents pertaining to this Docket that had been filed in the NRC Public Document Room as of November 16, 1979. The categories used for filing and searching in the NRC Public Document Room are used to catalog the entries

  13. Longitudinal analysis of categorical epidemiological data: a study of Three Mile Island.

    Science.gov (United States)

    Fienberg, S E; Bromet, E J; Follmann, D; Lambert, D; May, S M

    1985-11-01

    The accident at the Three Mile Island nuclear power plant in 1979 led to an unprecedented set of events with potentially life threatening implications. This paper focusses on the analysis of a longitudinal study of the psychological well-being of the mothers of young children living within 10 miles of the plant. The initial analyses of the data utilize loglinear/logit model techniques from the contingency table literature, and involve the fitting of a sequence of logit models. The inadequancies of these analyses are noted, and a new class of mixture models for logistic response structures is introduced to overcome the noted shortcomings. The paper includes a brief outline of the methodology relevant for the fitting of these models using the method of maximum likelihood, and then the model is applied to the TMI data. The paper concludes with a discussion of some of the substantive implications of the mixture model analysis.

  14. Raman and luminescence spectroscopy of zirconium oxide with the use of the MOLE microprobe

    International Nuclear Information System (INIS)

    Doyle, T.E.; Alvarez, J.L.

    1984-01-01

    Raman and luminescence spectroscopy with the use of the MOLE microprobe has been used to characterize ZrO 2 originating from oxidized fuel-rod cladding in nuclear accidents. Micro-Raman analysis of samples from Three Mile Island Unit 2 and the Power Burst Facility identified tetragonal and cubic ZrO 2 . The tetragonal and cubic phases are high-temperature polymorphs of ZrO 2 and provide information about temperatures and hydrogen formation in the TMI-2 core. The data suggest that the tetragonal ZrO 2 in TMI-2 samples was stabilized by a crystallite size effect, whereas cubic ZrO 2 in PBF debris samples was stabilized by impurities. Luminescence was used to differentiate yttria-stabilized ZrO 2 ceramics and oxidized fuel-rod cladding in PBF debris samples. The ZrO 2 ceramics produced strong, sharp luminescence peaks which indicated the presence of titanium and yttria in the ZrO 2 . Oxidized fuel-rod cladding displayed no luminescence

  15. Tourism impacts of Three Mile Island and other adverse events: Implications for Lincoln County and other rural counties bisected by radioactive wastes intended for Yucca Mountain

    Energy Technology Data Exchange (ETDEWEB)

    Himmelberger, J.J.; Ogneva-Himmelberger, Y.A. [Clark Univ., Worcester, MA (United States); Baughman, M. [Interech Services Corporation, Carson City, NV (United States)

    1995-11-01

    Whether the proposed Yucca Mountain nuclear waste repository system will adversely impact tourism in southern Nevada is an open question of particular importance to visitor-oriented rural counties bisected by planned waste transportation corridors (highway or rail). As part of one such county`s repository impact assessment program, tourism implications of Three Mile Island (TMI) and other major hazard events have been revisited to inform ongoing county-wide socioeconomic assessments and contingency planning efforts. This paper summarizes key research implications of such research as applied to Lincoln County, Nevada. Implications for other rural counties are discussed in light of the research findings. 29 refs., 3 figs., 1 tab.

  16. The urban heat island dynamics during heat waves: a study of cities in the United States

    Science.gov (United States)

    Hu, Leiqiu

    2016-04-01

    The urban heat island (UHI) is a common phenomenon describing that metropolitan areas are usually warmer than their rural surroundings. This effect is compounded by extreme heat events, which are a leading cause of weather-related human mortality in many countries worldwide. However, the spatial and diurnal variability of temperature and humidity in urban and adjacent rural areas during extreme heat events is not well measured and therefore not well understood. The recently developed dataset of near-surface air and dew temperature from MODIS atmospheric profiles and the new method for the UHI quantification--urban heat island curve are used to quantify the urban climatic changes during heat waves in cities of the United States. The enhanced and weakened UHIs are observed in various cities. The causes of UHI changes during heat waves are discussed, including climate region, vegetation type and amount, city geolocation, etc.

  17. Title list publicly available documents: Three Mile Island Unit 2, Docket 50-320. Cumulated to May 21, 1979

    International Nuclear Information System (INIS)

    1979-01-01

    This title list of publicly available documents pertaining to Three Mile Island Unit 2, Docket 50-320, includes those preincident and postincident documents filed in the NRC Public Document Room as of May 21, 1979. It is divided into preincident and postincident listings, with both listings subdivided into the categories used for filing and searching in the NRC Public Document Room

  18. GHRSST Level 2P Regional Subskin Sea Surface Temperature from the Tropical Rainfall Mapping Mission (TRMM) Microwave Imager (TMI) for the Atlantic Ocean (GDS version 1)

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — The Tropical Rainfall Measuring Mission (TRMM) Microwave Imager (TMI) is a well calibrated passive microwave radiometer, similar to SSM/I, that contains lower...

  19. Recommended HPI [High Pressure Injection] rates for the TMI-2 analysis exercise (0 to 300 minutes)

    International Nuclear Information System (INIS)

    Anderson, J.L.

    1987-09-01

    An international analysis exercise has been organized to evaluate the ability of nuclear reactor severe accident computer codes to predict the TMI-2 accident sequence and core damage progression during the first 300 minutes of the accident. A required boundary condition for the analysis exercise is the High Pressure Injection or make-up rates into the primary system during the accident. Recommended injection rates for the first 300 minutes of the accident are presented. Recommendations for several sensitivity studies are also presented. 6 refs., 5 figs., 1 tab

  20. THE EFFORT TO IMPROVE TEACHERS’PERFORMANCE OF SMA TMI ROUDLATUL QUR’AN IN COMPOSING LESSON PLAN AND EVALUATION INSTRUMENT OF CHARACTER EDUCATION THROUGH WORKSHOP ACADEMIC YEAR 2015/2016

    Directory of Open Access Journals (Sweden)

    Budi Raharjo

    2015-10-01

    Full Text Available Abstract: Difficulties found in Senior High School (SMA TMI Roudlatul Qur’an, teachers were not able to integrate character value into their lesson plan and to identify which behaviour must be success indicators of character education. Out of 18 Character value existed, the measurement of students’success as the better change of their behaviour, some only covering observation and lack of triangulation consideration to more accountable result. Worskhop potentially becomes one of the ways to up grade teachers’performance in determining the instrument of character value education, at the same time, train them the way composing lesson plan which integrates character education. This school action research was aimed to carry out workshop at SMA TMI Roudlatul Qur’an of Metro Municipal City, to improve teachers’performance in composing evaluation instrumen of value character education, to improve teachers’performance in composing integrated character value education.The research took place at SMA TMI Roudlatul Qur’an, located at Mulyojati, Metro Barat, Metro Municipal City. It was done in odd semester, continually to one month. Started in early Academic Year 2015/2016, July to August.The researcher concluded that teachers of SMA TMI Roudlatul Qur’an improved their performance well in composing evaluation instrument of value character education and integrated value character lesson plan through workshop. Facts: Workshop process was considered fair 11 teachers, good by 16 teachers, and very good by 12 teachers. At cycle II, the performance of composing evaluation instrument of character education showed 11 teachers were less sufficient performance, 16 teachers were good performance, and 12 teachers were very good. And the performance of composing integrated character value at cycle II showed 8 moderate teachers, 19 good teachers, and 12 excellent teachers. Key words: Workshop, Lesson Plan, Character Education Evaluation

  1. GHRSST Level 2P Global Subskin Sea Surface Temperature from TRMM Microwave Imager (TMI) onboard Tropical Rainfall Measurement Mission (TRMM) satellite (GDS versions 1 and 2)

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — GDS2 Version -The Tropical Rainfall Measuring Mission (TRMM) Microwave Imager (TMI) is a well calibrated passive microwave radiometer, similar to the Special Sensor...

  2. Virtually Impossible: Deleuze and Derrida on the Political Problem of Islands (and Island Studies

    Directory of Open Access Journals (Sweden)

    Stewart Williams

    2012-11-01

    Full Text Available It is commonplace to think of an island as a discreetly bounded unit. Selected writings on islands by the poststructuralist philosophers Gilles Deleuze and Jacques Derrida reveal the island variously to be both real and imaginary, mythological and scientific, but as most problematic when constituted in political terms as an indivisible, sovereign entity. These two thinkers’ more broadly developed concepts of the virtual and the impossible, respectively, are seen to disrupt any assumptions about the fixity and closure of the island polity. Instead they emphasize its actualization through processual relations that can be difficult yet dynamic and decisive in effecting the move from being to becoming-other. As the possibilities for instituting more ethical as well as different political relations open up, the question of island studies remaining in its currently coherent, familiar form is raised for consideration.

  3. Meeting the challenges in managing TMI-2 liquid waste and resolving disposal issues

    International Nuclear Information System (INIS)

    Schmitt, R.C.; Brown, G.R.; Ayers, A.L. Jr.

    1986-01-01

    This paper describes challenges of decontaminating water resulting from the accident at the Unit 2 of the Three Mile Island nuclear power station, disposing of highly contaminated prefilter liners as commercial low-level wastes, and controlling gas generation in highly loaded, disposable zeolite vessels. Disposal of EPICOR-II prefilter liners necessitated development of the first-of-a-kind, concrete high-integrity containers. Shipment of zeolite vessels for use in a research and development program required developing and testing a catalytic recombiner that controlled gases produced by radiolytic decomposition of interstitial water in the vessels

  4. Reactor safety after TMI (Three-Mile Island)

    International Nuclear Information System (INIS)

    Smidt, D.

    1980-01-01

    The present status of safety design in Germany and the governing principles behind it, are presented. The problem of human failure and what could be done about it, are discussed. This is followed by the description of some research projects for further increasing the accident prevention capability of German plants. (E.G.) [pt

  5. TMI-2 decay power: LASL fission-product and actinide decay power calculations for the President's Commission at Three Mile Island

    International Nuclear Information System (INIS)

    England, T.R.; Wilson, W.B.

    1979-10-01

    Fission-product and actinide decay heating, gas content, curies, and detailed contributions of the most important nuclide contributors were supplied in a series of letters following requests from the Presidential Commission on the Accident at Three Mile Island. In addition, similar data assuming different irradiation (power) histories were requested for purposes of comparison. This report consolidates the tabular and graphical data supplied and explains its basis

  6. TMI/TRMM precipitation and uncertainty (TMPA) L3 3 hour 0.25 degree x 0.25 degree V001 (WC_MULTISEN_PREC_025) at GES DISC

    Data.gov (United States)

    National Aeronautics and Space Administration — TMI/TRMM precipitation and uncertainty (TMPA) L3 3 hour 0.25 degree x 0.25 degree V001 provides estimates of accumulated precipitation from the Tropical Rainfall...

  7. A review of source term and dose estimation for the TMI-2 reactor accident

    International Nuclear Information System (INIS)

    Gudiksen, P.H.; Dickerson, M.H.

    1990-09-01

    The TMI-2 nuclear reactor accident, which occurred on March 28, 1979 in Harrisburg, Pennsylvania, produced environmental releases of noble gases and small quantities of radioiodine. The releases occurred over a roughly two week period with almost 90% of the noble gases being released during the first three days after the initiation of the accident. Meteorological conditions during the prolonged release period varied from strong synoptic driven flows that rapidly transported the radioactive gases out of the Harrisburg area to calm situations that allowed the radioactivity to accumulate within the low lying river area and to subsequently slowly disperse within the immediate vicinity of the reactor. The results reported by various analysts, revealed that approximately 2.4--10 million curies of noble gases (mainly Xe-133), and about 14 curies of I-131 were released. During the first two days, when most of the noble gas release occurred, the plume was transported in a northerly direction causing the most exposed area to lie within a northwesterly to northeasterly direction from TMI. Changing surface winds caused the plume to be subsequently transported in a southerly direction, followed by an easterly direction. The calculated maximum whole body dose due to plume passage exceeded 100 mrem over an area extending several kilometers north of the plant, although the highest measured dose was 75 mrem. The collective dose equivalent (within a radius of 80 km) due to the noble gas exposure ranged over several orders of magnitude with a central estimate of 3300 person-rem. The small I-131 release produced barely detectable levels of activity in air and milk samples. This may have produced thyroid doses of a few milirem to a small segment of the population. 7 refs., 4 figs., 2 tabs

  8. Power Burst Facility severe-fuel-damage test program

    International Nuclear Information System (INIS)

    McCardell, R.K.; MacDonald, P.E.

    1982-01-01

    As a result of the Three Mile Island Unit 2 (TMI-2) accident, the United States Nuclear Regulatory Commission (USNRC) has initiated a severe fuel damage research program to investigate fuel rod and core response, and fission product and hydrogen release and transport during degraded core cooling accidents. This paper presents a discussion of the expected benefits of the PBF severe fuel damage tests to the nuclear industry, a description of the first five planned experiments, the results of pretest analysis performed to predict the fuel bundle heatup for the first two experiments, and a discussion of Phase II severe fuel damage experiments. Modifications to the fission product detection system envisioned for the later experiments are also described

  9. Publicly available documents Three Mile Island Unit 2, Docket 50-320. Title list, July 1-October 31, 1979

    Energy Technology Data Exchange (ETDEWEB)

    1979-01-01

    This supplemental title list of publicly available documents pertaining to Three Mile Island Unit 2, Docket 50-320, includes those preincident and postincident documents filed in the NRC Public Document Room between July 1, 1979 and October 31, 1979. It is divided into preincident and postincident listings, with both listings sub-divided into the categories used for filing and searching in the NRC Public Document Room.

  10. Publicly available documents Three Mile Island Unit 2, Docket 50-320. Title list, July 1-October 31, 1979

    International Nuclear Information System (INIS)

    1979-01-01

    This supplemental title list of publicly available documents pertaining to Three Mile Island Unit 2, Docket 50-320, includes those preincident and postincident documents filed in the NRC Public Document Room between July 1, 1979 and October 31, 1979. It is divided into preincident and postincident listings, with both listings sub-divided into the categories used for filing and searching in the NRC Public Document Room

  11. Radiological conditions and experiences in the TMI-2 Auxiliary Building

    International Nuclear Information System (INIS)

    Ruhter, P.E.; Zurliene, W.G.

    1988-01-01

    Although the radiological conditions following the TMI-2 accident were extraordinary, those that had a potential impact on personnel were largely confined to the Auxiliary and Fuel Handling Building. The most significant pathway was the Letdown and Make-Up and Purification System. Dose rates in some locations in the Aux/Fuel Handling Buildings were in excess of 3 mSv/s (1000 R/h) during the first few days following the accident. They decreased after three to four days and stabilized after about one week. Airborne radioactivity levels were initially due to the release of noble gases, and subsequently due to resuspension of surface contamination. During the first month, the mixture of fission products in the reactor coolant change from one of largely cesium to where the strontium and cesium were about equal in radiological importance. This created some very high beta radiation levels. The significant strontium levels caused the contamination control limit to be reduced to one-half of the pre-accident limit. 5 refs., 6 figs

  12. Thermal behavior of molten corium during TMI-2 core relocation event

    International Nuclear Information System (INIS)

    Anderson, J.L.; Sienicki, J.J.

    1988-01-01

    During the TMI-2 accident, a pool of molten corium formed in the central region of the core and was contained by solidified crusts. Failure of the crust surrounding the molten material, at approximately 224 min, resulted in a relocation of an estimated 20-25 tons of molten corium through peripheral fuel assemblies in the east side of the vessel, as well as through the core barrel assembly (CBA) at the periphery of the core. This paper presents the results of an analyses carried out to investigate the thermal interactions of molten corium with the CBA structures during the relocation event. The principal objectives of the analyses are: (a) to assess the potential for relocation to take place through the CBA versus the flow of molten core material directly downward through the core via the fuel assemblies; and (b) to understand the distribution of prior molten corium observed during vessel defueling examinations. 5 refs., 1 fig

  13. Radionuclide distribution in TMI-2 reactor building basement liquids and solids

    International Nuclear Information System (INIS)

    Horan, J.T.; McIsaac, C.V.; Keefer, D.G.

    1984-01-01

    As a result of the TMI-2 accident, approximately 2.46 x 10 6 L of contaminated water were released to the Reactor Building basement. The principal fission product release pathway from the damaged core was through the reactor coolant system (RCS) to the pressurizer, through the pressure-operated relief valve (PORV) on the pressurizer to the Reactor Coolant Drain Tank (RCDT), and then through the RCDT rupture disk to the Reactor Building basement. Since August 1979, a number of efforts have been made to determine the location, quantity, and composition of fission products released to the Reactor Building basement. These efforts have included sampling of the basement water and solids, the basement sump pump recirculation line, the RCDT, and visual surveys using a closed circuit television (CCTV) system. The analysis of basement samples has provided data on the physical and radioisotopic characteristics of the liquids and solids. This paper describes the sample collection techniques and discusses radiochemical analyses results

  14. Estimation of Rainfall Associated with Typhoons over the Ocean Using TRMM/TMI and Numerical Models

    Directory of Open Access Journals (Sweden)

    Nan-Ching Yeh

    2015-11-01

    Full Text Available This study quantitatively estimated the precipitation associated with a typhoon in the northwestern Pacific Ocean by using a physical algorithm which included the Weather Research and Forecasting model, Radiative Transfer for TIROS Operational Vertical Sounder model, and data from the Tropical Rainfall Measuring Mission (TRMM/TRMM Microwave Imager (TMI and TRMM/Precipitation Radar (PR. First, a prior probability distribution function (PDF was constructed using over three million rain rate retrievals from the TRMM/PR data for the period 2002–2010 over the northwestern Pacific Ocean. Subsequently, brightness temperatures for 15 typhoons that occurred over the northwestern Pacific Ocean were simulated using a microwave radiative transfer model and a conditional PDF was obtained for these typhoons. The aforementioned physical algorithm involved using a posterior PDF. A posterior PDF was obtained by combining the prior and conditional PDFs. Finally, the rain rate associated with a typhoon was estimated by inputting the observations of the TMI (attenuation indices at 10, 19, 37 GHz into the posterior PDF (lookup table. Results based on rain rate retrievals indicated that rainband locations with the heaviest rainfall showed qualitatively similar horizontal distributions. The correlation coefficient and root-mean-square error of the rain rate estimation were 0.63 and 4.45 mm·h−1, respectively. Furthermore, the correlation coefficient and root-mean-square error for convective rainfall were 0.78 and 7.25 mm·h−1, respectively, and those for stratiform rainfall were 0.58 and 9.60 mm·h−1, respectively. The main contribution of this study is introducing an approach to quickly and accurately estimate the typhoon precipitation, and remove the need for complex calculations.

  15. TRMM Microwave Imager (TMI) Level 3 Monthly 0.5 degree x 0.5 degree Profiling V7 (3A12) at GES DISC V7

    Data.gov (United States)

    National Aeronautics and Space Administration — This document provides basic information on 3A12, TMI Monthly 0.5 deg. x 0.5 deg. Profiling. Algorithm 3A12 produces global 0.5 deg. x 0.5 deg. monthly gridded means...

  16. Control principles for blackstart and island operation of microgrid

    Energy Technology Data Exchange (ETDEWEB)

    Laaksonen, H.; Kauhaniemi, K. (University of Vaasa (Finland))

    2008-07-01

    In some unexpected situations a microgrid may become unstable after transition to islanded mode and all DG units must be disconnected from microgrid. In case of these events a restoration strategy for microgrid blackstart is needed. Also if the islanded microgrid is divided into different protection zones in case of a fault, fault management strategy with capability of very fast operation is needed to maintain stability in the healthy section of the islanded microgrid. The control of microgrid voltage and frequency during the microgrid blackstart is not possible without energy storage unit. In this paper sequence of actions for the microgrid blackstart operation as well as control principles of some DG units during blackstart are defined and simulated with two different microgrid configurations. Also one simulation case considering fault management strategy and control principles during fault in islanded microgrid is presented. Based on the simulations dimensioning principles for the needed energy storage and size of simultaneously controlled loads can be drawn. (orig.)

  17. Nanosecond Tm:Y2O3 ceramic laser passively Q-switched by a Ho:LuAG ceramic

    Science.gov (United States)

    Wang, Hui; Huang, Haitao; Wang, Shiqiang; Shen, Deyuan

    2018-02-01

    A passively Q-switched 2.05-μm Tm:Y2O3 ceramic laser, employing Ho:LuAG ceramic as a saturable absorber, was demonstrated for the first time. Under the absorbed pump power of 20.5 W, a maximum output power of 497 mW was obtained. Pulses with a minimum pulse width of 642 ns under the repetition rate of 33 kHz were achieved. Our works validate that Ho-doped materials have good potential for passive Q-switching of Tm-doped lasers at 2-μm wavelength region.

  18. Frequency Control for Island Operation of Bornholm Power System

    DEFF Research Database (Denmark)

    Cha, Seung-Tae; Wu, Qiuwei; Zhao, Haoran

    2014-01-01

    the primary frequency control and the DG units are used to provide the secondary frequency control. As such, the proposed control scheme can strike a balance of the frequency control speed and the energy used from the BESS for the frequency control support. The real-time model of the Bornholm power system......This paper presents a coordinated control strategy of a battery energy storage system (BESS) and distributed generation (DG) units for the island operation of the Danish island of Bornholm. The Bornholm power system is able to transit from the grid connected operation with the Nordic power system...... to the isolated island operation. In order to ensure the secure island operation, the coordinated control of the BESS and the DG has been proposed to stabilize the frequency of the system after the transition to the island operation. In the proposed coordinate control scheme, the BESS is used to provide...

  19. Development of a high integrity container for storage, transportation, and disposal of radioactive wastes from Three Mile Island unit II

    International Nuclear Information System (INIS)

    Holzworth, R.E.; Chapman, R.L.; Burton, H.M.; Bixby, W.W.

    1981-01-01

    The EPICOR II ion exchange system used to decontaminate approximately 1900 m 3 of contaminated water in the Auxiliary and Fuel Handling Building (AFHB) generated 50 highly loaded and 22 lesser loaded organic resin liners. The 22 lesser loaded resins were shipped to a commercial disposal site, but the highly loaded liners have been stored on the island since their generation. One highly loaded liner, or prefilter, was shipped to Battelle Columbus Laboratories (BCL) in May, 1981 as part of the United States Department of Energy (DOE) Three Mile Island Information and Examination Program. The prefilter is being characterized to determine the behavior of the waste form with respect to time and the internal environment and to provide an information base for use in management and regulatory decisions relative to the storage, processing, and disposal of these wastes. Due to the unique characteristics of these wastes, the US DOE is sponsoring programs, such as the BCL Sorbent Experiments Program, to evaluate their characteristics and to provide a High Integrity Container (HIC) Development Program which would improve waste suitability for disposal at a land burial facility. This paper addresses regulatory considerations, establishment of design criteria, proposed design concepts, system demonstration, and status of the HIC Development Program for storage, transportation, and disposal of high specific activity, low level radioactive wastes from Three Mile Island Unit II as typified by EPICOR II ion exchange media and liners

  20. Real-Time Analysis of an Active Distribution Network - Coordinated Frequency Control for Islanding Operation

    DEFF Research Database (Denmark)

    Cha, Seung-Tae

    distribution networks makes it possible to operate the distribution networks independently which is called islanding operation. However, it is a challenge to ensure secure and reliable operation of the islanded system due to a num-ber of reasons, e.g. low inertia in the islanded system, intermittency of some...... of the DERs, etc. Particularly during islanding operation, with relatively few DG units, the frequency and voltage control of the islanded system is not straightforward. DG units, specially based on renewable energy sources (RESs), i.e. wind and solar, have an inter-mittent nature and intrinsic...... system (BESS) and two secondary frequency control scenarios with BESS and DG units. During the island-ing transition, the frequency is regulated by the fast-acting primary control of the BESS. The secondary control of the main management system (MMS) detects the status of the BESS and tries to return...

  1. Transporting TMI-2 core debris to INEL: Public safety and public response

    International Nuclear Information System (INIS)

    Schmitt, R.C.; Reno, H.W.; Young, W.R.; Hamric, J.P.

    1987-01-01

    This paper describes the approach taken by the US Department of Energy to ensure that public safety is maintained during transport of core debris from the Unit-2 reactor at the Three Mile Island Nuclear Power Station near Harrisburg, PA, to the Idaho National Engineering Laboratory near Idaho Falls, ID. It provides up-to-date information about public response to the transport action and discusses DOE's position on several institutional issues. The authors advise that planners of future transport operations be prepared for a multitude of comments from all levels of federal, state, and local governments, special interest groups, and private citizens. They also advise planners to keep meticulous records concerning all informational transactions. 3 figs

  2. Answers to frequently asked questions about cleanup activities at Three Mile Island, Unit 2

    International Nuclear Information System (INIS)

    1984-03-01

    This question-and-answer report provides answers in nontechnical language to frequently asked questions about the status of cleanup activities at Three Mile Island, Unit 2. The answers update information first prepared in 1981, shortly after the cleanup got under way. Since then, a variety of important developments in the cleanup has occurred. The information in the report should be read in conjunction with NUREG 1060, a discussion of increased occupational exposure estimates for the cleanup. The questions and answers in this report cover purpose and community involvement, decontamination of water and reactor, fuel removal, radwaste transport, environmental impact, social and economic effects, worker exposures and safety, radiation monitoring, potential for accidents, and schedule and funding

  3. Implementasi Kurikulum Kulliyatul Mu’alimin Al-Islamiyah (KMI Di Pondok Pesantren Tarbiyatul Mu’allimien Al-Islamiyah (TMI Al-Amien Prenduan Dan Ma’hadul Mu’allimien Al-Islamiyah (MMI Mathlabul Ulum Jambu Sumenep

    Directory of Open Access Journals (Sweden)

    Fajriyah Fajriyah

    2017-07-01

    Full Text Available Tujuan penelitian ini mendeskripsikan dan memahami: Kurikulum kulliyatul mu’allimin al-islamiyah; Implementasi kurikulum kulliyatul mu’allimin al-islamiyah; Faktor pendukung dan faktor penghambat kurikulum kulliyatul mu’allimin al-islamiyah; dan Strategi mengatasi faktor penghambat kurikulum kulliyatul mu’allimin al-islamiyah. Penelitian ini menggunakan pendekatan kualitatif dengan rancangan penelitian studi multi situs. Hasil penelitian ini yaitu: kurikulum KMI di TMI dan MMI perumusan kurikulum KMI didasarkan filosofi yang tercermin dari visi dan misi yang diturunkan dalam tujuan dan disusun dalam langkah yang opersional. Faktor pendukung: terdapat kedisiplinan yang ditanamkan kepada guru dan santri; SDM yang berkompeten; kepedulian orang tua dan masyarakat; dan  strategi mengatasi faktor penghambat kurikulum KMI di TMI dan MMI, memaksimalkan penggunaan teknologi informasi (IT dalam proses pembelajaran, peningkatan kualitas SDM dengan mengikutsertakan guru dalam pelatihan dan pendidikan di pesantren maupun di luar pesantren. guru berperan aktif. Kata Kunci: Implementasi, Kurikuilum, KMI.   Abstract:   While the purpose of this research are to describe: The curriculum of  kulliyatul mu’allimin al-islamiyah; Implementation of  curriculum of kulliyatul mu’allimin al-islamiyah; Factor of support and factor pursuer of curriculum of kulliyatul mu’allimin al-islamiyah; and Strategy to overcome factor of pursuer of curriculum of kulliyatul mu’allimin al-islamiyah. Results of this research are: curriculum KMI in TMI and MMI: the first, curriculum formulating of KMI based philosophy that taken by vision and mission applied the aim and arranged  in step operational, the curriculum implementation KMI and MMI boarding house as formal education institution and non formal to do learning process for 24 hour, support factor and pursuer factor of curriculum KMI in TMI and MMI,pursuer factor are: minimize boarding house facility; limited

  4. Study of trypanosome and anaemia indicators during the eradication of tsetse flies from Unguja island, United Republic of Tanzania

    International Nuclear Information System (INIS)

    Dwinger, R.H.; Holland, W.G.; Ndegwa, T.K.; Wint, W.; Kassim, S.S.; Hongjie, P.; Slingenbergh, J.H.W.

    2000-01-01

    A large number of cattle has been monitored regularly during a ten-year period on Unguja island, United Republic of Tanzania, as part of a number of consecutive programmes to initially control and eventually eradicate tsetse and trypanosomosis. Haematological and parasitological results were used among others to monitor and adjust the control and eradication programmes from 1988 to 1997. A Geographic Information System (GIS) was applied to the data set to assess changes of animal health parameters in time and space. Analysis of the data showed significant changes over the years in infection status and degree of anaemia. Moreover, differences in health status of cattle populations between adjacent geographic areas were detected. Regular monitoring using standardized protocols by a multidisciplinary team resulted eventually in the eradication of tsetse flies from the island. (author)

  5. Nuclear power in the United States

    International Nuclear Information System (INIS)

    Johnston, J.B.

    1985-01-01

    All over the world except in the United States, nuclear energy is a low cost, secure, environmentally acceptable form of energy. In the United States, civilian nuclear power is dead. 112 nuclear power plants have been abandoned or cancelled in the last decade, and there has been no new order for nuclear plants since 1978. It will be fortunate to have 125 operating nuclear plants in the United States in the year 2000. There are almost 90 completed nuclear power plants and about 45 under construction in the United States, but several of those under construction will eventually be abandoned. About 20 % of the electricity in the United States will be generated by nuclear plants in 2000 as compared with 13 % supplied in the last year. Under the present regulatory and institutional arrangement, American electric utilities would not consider to order a new nuclear power plant. Post-TMI nuclear plants became very expensive, and there is also ideological opposition to nuclear power. Coal-firing plants are also in the similar situation. The uncertainty about electric power demand, the cost of money, the inflation of construction cost and regulation caused the situation. (Kako, I.)

  6. Strippable coating used for the TMI-2 reactor building decontamination

    International Nuclear Information System (INIS)

    Adams, J.W.; Dougherty, D.R.; Barletta, R.E.

    1984-01-01

    Strippable coating material used in the TMI-2 reactor building decontamination has been tested for Sr, Cs, and Co leachability, for radiation stability, thermal stability, and for resistance to biodegradation. It was also immersion tested in water, a water solution saturated with toluene and xylene, toluene, xylene, and liquid scintillation counting (LSC) cocktail. Leach testing resulted in all of the Cs and Co activity and most of the Sr activity being released from the coating in just a few days. Immersion resulted in swelling of the coating in all of the liquids tested. Gamma irradiation and heating of the coating did not produce any apparent physical changes in the coating to 1 x 10 8 rad and 100 0 C; however, gas generation of H 2 , CO, CO 2 was observed in both cases. Biodegradation of the coating occurred readily in soils as indicated by monitoring CO 2 produced from microbial respiration. These test results indicate that strippable coating radwaste would have to be stabilized to meet the requirements for Class B waste outlined in 10 CFR Part 61 and the NRC Draft Technical Position on Waste Form

  7. Prioritizing islands for the eradication of invasive vertebrates in the United Kingdom overseas territories.

    Science.gov (United States)

    Dawson, Jeffrey; Oppel, Steffen; Cuthbert, Richard J; Holmes, Nick; Bird, Jeremy P; Butchart, Stuart H M; Spatz, Dena R; Tershy, Bernie

    2015-02-01

    Invasive alien species are one of the primary threats to native biodiversity on islands worldwide. Consequently, eradicating invasive species from islands has become a mainstream conservation practice. Deciding which islands have the highest priority for eradication is of strategic importance to allocate limited resources to achieve maximum conservation benefit. Previous island prioritizations focused either on a narrow set of native species or on a small geographic area. We devised a prioritization approach that incorporates all threatened native terrestrial vertebrates and all invasive terrestrial vertebrates occurring on 11 U.K. overseas territories, which comprise over 2000 islands ranging from the sub-Antarctic to the tropics. Our approach includes eradication feasibility and distinguishes between the potential and realistic conservation value of an eradication, which reflects the benefit that would accrue following eradication of either all invasive species or only those species for which eradication techniques currently exist. We identified the top 25 priority islands for invasive species eradication that together would benefit extant populations of 155 native species including 45 globally threatened species. The 5 most valuable islands included the 2 World Heritage islands Gough (South Atlantic) and Henderson (South Pacific) that feature unique seabird colonies, and Anegada, Little Cayman, and Guana Island in the Caribbean that feature a unique reptile fauna. This prioritization can be rapidly repeated if new information or techniques become available, and the approach could be replicated elsewhere in the world. © 2014 Crown copyright. Conservation Biology © 2014 Society for Conservation Biology.

  8. Decentralized method for load sharing and power management in a hybrid single/three-phase islanded microgrid consisting of hybrid source PV/battery units

    DEFF Research Database (Denmark)

    Karimi, Yaser; Guerrero, Josep M.; Oraee, Hashem

    2016-01-01

    This paper proposes a new decentralized power management and load sharing method for a photovoltaic based, hybrid single/three-phase islanded microgrid consisting of various PV units, battery units and hybrid PV/battery units. The proposed method takes into account the available PV power...... and battery conditions of the units to share the load among them and power flow among different phases is performed automatically through three-phase units. Modified active power-frequency droop functions are used according to operating states of each unit and the frequency level is used as trigger...... for switching between the states. Efficacy of the proposed method in different load, PV generation and battery conditions is validated experimentally in a microgrid lab prototype consisted of one three-phase unit and two single-phase units....

  9. Reactor accidents. Chernobyl and Three Miles Island

    International Nuclear Information System (INIS)

    Marx, G.

    1990-01-01

    A description of the facilities at Chernobyl and TMI, as well as of the course of the accidents is given. Supplementary information relates to the quantities and types of radionuclides released and to the size of the group of persons concerned. (DG) [de

  10. Complex patterns of genetic and phenotypic divergence in an island bird and the consequences for delimiting conservation units.

    Science.gov (United States)

    Phillimore, A B; Owens, I P F; Black, R A; Chittock, J; Burke, T; Clegg, S M

    2008-06-01

    Substantial phenotypic and genetic variation is often found below the species level and this may be useful in quantifying biodiversity and predicting future diversification. However, relatively few studies have tested whether different aspects of intraspecific variation show congruent patterns across populations. Here, we quantify several aspects of divergence between 13 insular populations of an island endemic bird, the Vanuatu white-eye (Zosterops flavifrons). The components of divergence studied are mitochondrial DNA (mtDNA), nuclear DNA microsatellites and morphology. These different aspects of divergence present subtly different scenarios. For instance, an mtDNA phylogenetic tree reveals a potential cryptic species on the most southerly island in Vanuatu and considerable divergence between at least two other major phylogroups. Microsatellite loci suggest that population genetic divergence between insular populations, both between and within phylogroups, is substantial, a result that is consistent with a low level of interisland gene flow. Finally, most populations were found to be strongly morphologically divergent, but no single population was morphologically diagnosable from all others. Taken together, our results show that, although many measures of divergence are concordant in this system, the number of divergent units identified varies widely depending on the characters considered and approach used. A continuum of divergence and a degree of discordance between different characters are both to be expected under simple models of evolution, but they present problems in terms of delimiting conservation units.

  11. Optimal Power Flow in three-phase islanded microgrids with inverter interfaced units

    DEFF Research Database (Denmark)

    Sanseverino, Eleonora Riva; Quang, Ninh Nguyen; Di Silvestre, Maria Luisa

    2015-01-01

    In this paper, the solution of the Optimal Power Flow (OPF) problem for three phase islanded microgrids is studied, the OPF being one of the core functions of the tertiary regulation level for an AC islanded microgrid with a hierarchical control architecture. The study also aims at evaluating the...

  12. Planning and implementing nuclear emergency response facilities

    International Nuclear Information System (INIS)

    Williams, D.H.

    1983-01-01

    After Three Mile Island, Arkansas Nuclear One produced a planning document called TMI-2 Response Program. Phase I of the program defined action plans in nine areas: safety assessment, training, organization, public information, communication, security, fiscal-governmental, technical and logistical support. Under safety assessment, the staff was made even better prepared to handle radioactive material. Under training, on site simulators for each unit at ANO were installed. The other seven topics interface closely with each other. An emergency control center is diagrammed. A habitable technical support system was created. A media center, with a large media area, and an auditorium, was built. Electric door strike systems increased security. Phone networks independently run via microwave were installed. Until Three Mile Island, logistical problems were guesswork. That incident afforded an opportunity to better identify and prepare for these problems

  13. Detailed flow analysis for the Three Mile Island unit 2 reactor accident

    International Nuclear Information System (INIS)

    Lillington, J.N.; Lyons, A.J.

    1990-01-01

    Some particular characteristics of the steam flow in the accident at the Three Mile Island unit 2 pressurized water reactor are investigated using the AEA Technology Flow3D code. Natural circulation flows with heat removal from the core and deposition in the upper plenum are predicted during the primary heating phase. The structure of the upper plenum cylinder and core blockage, owing to material relocation, are shown to force the flow into a complex three-dimensional pattern. The flows and temperature distributions from the calculations are shown to be consistent with the observed damage pattern above the core. Despite high core temperatures, damage was limited by the operation of one of the pumps at the end of the initial heating phase. Flow3D calculations are also carried out to demonstrate that the three-dimensional buoyancy driven flows are completely destroyed by the high steam generation rates arising from the pump operation. (author)

  14. TMI-2 core damage: a summary of present knowledge

    International Nuclear Information System (INIS)

    Owen, D.E.; Mason, R.E.; Meininger, R.D.; Franz, W.A.

    1983-01-01

    Extensive fuel damage (oxidation and fragmentation) has occurred and the top approx. 1.5 m of the center portion of the TMI-2 core has relocated. The fuel fragmentation extends outward to slightly beyond one-half the core radius in the direction examined by the CCTV camera. While the radial extent of core fragmentation in other directions was not directly observed, control and spider drop data and in-core instrument data suggest that the core void is roughly symmetrical, although there are a few indications of severe fuel damage extending to the core periphery. The core material fragmented into a broad range of particle sizes, extending down to a few microns. APSR movement data, the observation of damaged fuel assemblies hanging unsupported from the bottom of the reactor upper plenum structure, and the observation of once-molten stainless steel immediately above the active core indicate high temperatures (up to at least 1720 K) extended to the very top of the core. The relative lack of damage to the underside of the plenum structure implies a sharp temperature demarcation at the core/plenum interface. Filter debris and leadscrew deposit analyses indicate extensive high temperature core materials interaction, melting of the Ag-In-Cd control material, and transport of particulate control material to the plenum and out of the vessel

  15. Annual Radiological Environmental Monitoring Program Report for the Three Mile Island, Unit 2, Independent Spent Fuel Storage Installation

    International Nuclear Information System (INIS)

    Hall, Gregory Graham

    2002-01-01

    This report presents the results of the 2001 Radiological Environmental Monitoring Program conducted in accordance with 10 CFR 72.44 for the Three Mile Island, Unit 2, Independent Spent Fuel Storage Installation. A description of the facility and the monitoring program is provided. The results of monitoring the two predominant radiation exposure pathways, potential airborne radioactivity releases and direct radiation exposure, indicate the facility operation has not contributed to any increase in the estimated maximum potential dose commitment to the general public.

  16. Review of literature on the TMI accident and correlation to the LWR Safety Technology Program

    International Nuclear Information System (INIS)

    Miller, W.J.

    1980-05-01

    This report is the result of approximately two man-months of effort devoted to assimilating and comprehending significant publicly available material related to Three Mile Island Unit 2 and events during and subsequent to the accident experienced on March 28, 1979. Those events were then correlated with the Preliminary LWR Safety Technology Program Plan (Preliminary Program Plan) prepared for the US Department of Energy by Sandia National Lab. This report is being submitted simultaneously with the SAI report entitled Preliminary Prioritization of Tasks in the Draft LWR Safety Technology Program Plan

  17. Review of literature on the TMI accident and correlation to the LWR Safety Technology Program

    Energy Technology Data Exchange (ETDEWEB)

    Miller, W.J.

    1980-05-01

    This report is the result of approximately two man-months of effort devoted to assimilating and comprehending significant publicly available material related to Three Mile Island Unit 2 and events during and subsequent to the accident experienced on March 28, 1979. Those events were then correlated with the Preliminary LWR Safety Technology Program Plan (Preliminary Program Plan) prepared for the US Department of Energy by Sandia National Lab. This report is being submitted simultaneously with the SAI report entitled Preliminary Prioritization of Tasks in the Draft LWR Safety Technology Program Plan.

  18. Emergy Evaluation of Dwelling Operation in Five Housing Units of Montreal Island, Canada

    Directory of Open Access Journals (Sweden)

    Ricardo Enrique Vega-Azamar

    2017-04-01

    Full Text Available Sustainability of cities and the environmental implications of high resource utilization by the domestic sector are growing concerns related to urban regions. Well-informed urban planning decision-making is an essential tool to help in the task and, for that, an important point to consider is the influence of parameters like residential density and housing typology on the intensity of resource utilization. Emergy synthesis, a life-cycle energy analysis methodological approach that considers the interaction of natural and human-made flows, was used to evaluate the environmental support for dwelling operational stage in five typical present-day housing units on the island of Montreal. As expected, resource utilization, measured as total emergy used, was positively correlated to housing unit size both with respect to number of occupants and dwelling size. Results suggest that variables affecting notably the intensity of resource utilization are per household income and per dweller habitable space and, while a higher income increased per capita emergy in all cases, increasing space availability per resident did not result in a decrease of empower density after 50 m2/person. Future work should consider lower and higher densities and analyses at the scale of blocks, neighborhoods and urban planning zones.

  19. Application of TRMM PR and TMI Measurements to Assess Cloud Microphysical Schemes in the MM5 Model for a Winter Storm

    Science.gov (United States)

    Han, Mei; Braun, Scott A.; Olson, William S.; Persson, P. Ola G.; Bao, Jian-Wen

    2009-01-01

    Seen by the human eye, precipitation particles are commonly drops of rain, flakes of snow, or lumps of hail that reach the ground. Remote sensors and numerical models usually deal with information about large collections of rain, snow, and hail (or graupel --also called soft hail ) in a volume of air. Therefore, the size and number of the precipitation particles and how particles interact, evolve, and fall within the volume of air need to be represented using physical laws and mathematical tools, which are often implemented as cloud and precipitation microphysical parameterizations in numerical models. To account for the complexity of the precipitation physical processes, scientists have developed various types of such schemes in models. The accuracy of numerical weather forecasting may vary dramatically when different types of these schemes are employed. Therefore, systematic evaluations of cloud and precipitation schemes are of great importance for improvement of weather forecasts. This study is one such endeavor; it pursues quantitative assessment of all the available cloud and precipitation microphysical schemes in a weather model (MM5) through comparison with the observations obtained by National Aeronautics and Space Administration (NASA) s and Japan Aerospace Exploration Agency (JAXA) s Tropical Rainfall Measuring Mission (TRMM) precipitation radar (PR) and microwave imager (TMI). When satellite sensors (like PR or TMI) detect information from precipitation particles, they cannot directly observe the microphysical quantities (e.g., water species phase, density, size, and amount etc.). Instead, they tell how much radiation is absorbed by rain, reflected away from the sensor by snow or graupel, or reflected back to the satellite. On the other hand, the microphysical quantities in the model are usually well represented in microphysical schemes and can be converted to radiative properties that can be directly compared to the corresponding PR and TMI observations

  20. An international comparison of commercial nuclear power plant staffing regulations and practice, 1980--1990

    International Nuclear Information System (INIS)

    Melber, B.; Hauth, J.; Terrill, E.; Berk, B.; Gore, B.

    1994-03-01

    In this report an international review of regulatory and industry practices is provided in the area of nuclear power plant staffing during the 1980s in Canada, France, Germany, Japan, Sweden, and the United Kingdom. The objective of this review is to highlight trends in staffing regulatory approaches, industry practices, and issues of concern in other countries that have potential relevance to nuclear power plant staffing issues in the United States. The decade of the 1980s was marked by a great deal of growth in nuclear power operations internationally; however, growth of nuclear power is not expected to continue in the 1990s except in France and Japan. A continuum of regulatory approaches to staffing was identified, ranging from prescribed regulations that are applied to all licensees (Germany is most similar to the United States in this regard), to indirect staffing regulations where the regulatory authority oversees plant operating practices that are agreed to in the plant operating license (most notably, France and the United Kingdom). Most of the changes observed in staffing regulations and practices in the early 1980s were made in response to the accident at the Three Mile Island Unit 2 nuclear power plant (TMI) in 1979. These changes included the widespread issuance of new operator and licensing requirements and the establishment of national training centers. After the post-TMI changes were implemented, a period of relative stability followed. Changes in the latter half of the 1980s have focused on continuing improvements and additions to training curricula and methods, most notably increased reliance on simulator training

  1. Three Mile Island accident: a case study of life event appraisal

    International Nuclear Information System (INIS)

    Goldsteen, R.L.

    1983-01-01

    This research investigates community reactions to the accident at the Three Mile Island (TMI) nuclear powered electric generating plant in March, 1979. The investigation is placed in the context of life event research and chooses an appraisal orientation. Three innovations are argued: 1) perceived consequences of the event best predict reactions to it, 2) the attitudes of significant others toward the event influence reactions to the accident under certain circumstances, and 3) sense of well-being is a good outcome measure for a general population. The hypotheses posit that the attitudes of others will affect sense of well-being only when individual attitudes concerning the consequences of the accident are moderate; when individual attitudes are extreme, the attitudes of others will have no demonstrable effect on outcomes. The findings did not support all the prediction of the hypotheses. However, they indicate that perceived consequences are the best predictors of sense of well-being and that an individual's attitudinal position, his strength of attitude, and the nature of the stimulus are highly related to whether or not an individual will be influenced by the views of others

  2. Evaluation of nuclear facility decommissioning projects. Three Mile Island Unit 2 reactor coolant system and systems decontamination. Summary status report. Volume 1

    International Nuclear Information System (INIS)

    Doerge, D.H.; Miller, R.L.; Scotti, K.S.

    1986-05-01

    This document summarizes information relating to the decontamination and restoration of the Three Mile Island Unit 2 reactor coolant system and other plant systems. Data have been collected from activity reports, reactor containment entry records, and other sources and entered in a computerized data system which permits extraction/manipulation of specific data which can be used in planning for recovery from a loss of coolant event similar to that experienced by the Three Mile Island Unit 2 on March 28, 1979. This report contains a summary of radiation exposures, manpower, and time spent in radiation areas during the referenced period. Support activities conducted outside of radiation areas are not included. Computer reports included are: A chronological listing of all activities related to decomtamination and restoration of the reactor coolant system and other plant systems for the period of April 5, 1979, through December 19, 1984; a summary of labor and exposures by department for the same time period; and summary reports for each major task undertaken in connection with this specific work scope during the referenced time period

  3. TMI-2 decay power: LASL fission-product and actinide decay power calculations for the President's Commission at Three Mile Island

    Energy Technology Data Exchange (ETDEWEB)

    England, T.R.; Wilson, W.B.

    1979-10-01

    Fission-product and actinide decay heating, gas content, curies, and detailed contributions of the most important nuclide contributors were supplied in a series of letters following requests from the Presidential Commission on the Accident at Three Mile Island. In addition, similar data assuming different irradiation (power) histories were requested for purposes of comparison. This report consolidates the tabular and graphical data supplied and explains its basis.

  4. The Three Mile Island - 2 incident and damage to pheasants

    International Nuclear Information System (INIS)

    Boeck, H.

    1981-01-01

    In popular Austrian TV show deformed pheasants were shown hatched from eggs which were purchased by an Austrian pheasants breeder from a pheasantry about 60 miles from Harrisburg. The case was presented in such a way that the public could have correlated the deformed pheasants to the TMI-2 incident. As detailed investigations showed that the radiation dose after the TMI-2 incident was rather low even very close to the nuclear power plant such an effect seems highly unlikely. Analyses of the hatch percentages of other pheasants breeder using eggs from the very same flock showed no abnormal behaviour whatsoever. Therefore, the negative hatch result of the Austrian breeder must originate in other environmental effects either during transport or breeding. (author)

  5. Structural and geophysical interpretation of Roatan Island, Honduras, Western Caribbean

    Science.gov (United States)

    Sutton, Daniel Scott

    Roatan Island is the largest of the Bay Islands of Honduras. These islands form an emergent crest off the Caribbean coast of Honduras called the Bonacca Ridge. The Bartlett Trough to the north and subsequent Bonacca Ridge were likely formed due to the transform fault system of the Motagua-Swan Islands Fault System. This fault system forms the tectonic plate boundary between the North American and Caribbean plates. Although the timing and kinematics are poorly constrained, the Bay Islands and the Bonacca Ridge were likely uplifted due to transpression along this left-lateral strike-slip system. With limited regional exposures along the adjacent tectonic boundary, this study aimed to present a structural interpretation for Roatan. This new interpretation is further explained through regional considerations for a suggested geologic history of the northwestern Caribbean. In order to better constrain the kinematics of uplift and exhumation of Roatan Island, structural, gravity, and magnetic surveys were conducted. Principal attention was directed to the structural relationship between the geologic units and their relationship to one another through deformation. Resulting geologic cross-sections from this study present the metamorphic basement exposed throughout the island to be in a normal structural order consisting of biotite schist and gneiss, with overlying units of chlorite schist, carbonate, and conglomerate. These units have relatively concordant strike and dip measurements, consistent with resultant magnetic survey readings. Additionally, large and irregular bodies of amphibolite and serpentinite throughout the island are interpreted to have been emplaced as mafic and ultra-mafic intrusions in weakness zones along Early Paleogene transform system fault planes. The interpretation and suggested geologic history from this study demonstrate the importance of transpressive tectonics both local to Roatan and regionally throughout geologic history. Consideration of

  6. Strategic Environmental Assessment practices in European small islands: Insights from Azores and Orkney islands

    Energy Technology Data Exchange (ETDEWEB)

    Polido, Alexandra, E-mail: a.polido@campus.fct.unl.pt [CENSE, Center for Environmental and Sustainability Research, Departamento de Ciências e Engenharia do Ambiente, Faculdade de Ciências e Tecnologia, Universidade NOVA de Lisboa, Campus da Caparica, 2829-516 Caparica (Portugal); João, Elsa, E-mail: elsa.joao@strath.ac.uk [Department of Civil and Environmental Engineering, University of Strathclyde, Level 5, James Weir Building, 75 Montrose Street, Glasgow G1 1XJ, Scotland (United Kingdom); Ramos, Tomás B., E-mail: tabr@fct.unl.pt [CENSE, Center for Environmental and Sustainability Research, Departamento de Ciências e Engenharia do Ambiente, Faculdade de Ciências e Tecnologia, Universidade NOVA de Lisboa, Campus da Caparica, 2829-516 Caparica (Portugal)

    2016-02-15

    The literature concerning Strategic Environmental Assessment (SEA) often refers to the importance of context-specific approaches. However, there is a lack of systematised and consistent studies that enhance tailor-made SEA practices and procedures. Small islands are bounded units of study which may help explore SEA theory and practice in special territories. Small islands present particular features and unique values, such as, small size and population, geographic isolation, limited resources and vulnerable ecosystems. Hence, the main goal of this research was to profile SEA practices and procedures in European small islands and provide a background for future research aiming to improve context-specific SEA applications. To achieve this goal, an exploratory case study was developed using Azores (Portugal) and Orkney (Scotland) archipelagos. An analysis of the corresponding mainland was also carried out to contextualise both case studies. The data collection was achieved through a qualitative content analysis of 43 Environmental Reports. The research found that there is not an SEA context-specific approach used within these European small islands, including guidelines, assessment topics, assessment techniques, follow-up and stakeholders engagement. The debate concerning specific approaches to small islands must be re-focused on the enhancement of SEA capacity-building amongst different stakeholders (including decision-makers), on the development and implementation of collaborative approaches, and on the exchange of knowledge and experiences between small islands networks. - Highlights: • Reviewed the differences between the Portuguese and Scottish SEA system • Showed a low integration of SEA specific features in reports of European small islands • Provides background for future SEA research for small islands approaches.

  7. Strategic Environmental Assessment practices in European small islands: Insights from Azores and Orkney islands

    International Nuclear Information System (INIS)

    Polido, Alexandra; João, Elsa; Ramos, Tomás B.

    2016-01-01

    The literature concerning Strategic Environmental Assessment (SEA) often refers to the importance of context-specific approaches. However, there is a lack of systematised and consistent studies that enhance tailor-made SEA practices and procedures. Small islands are bounded units of study which may help explore SEA theory and practice in special territories. Small islands present particular features and unique values, such as, small size and population, geographic isolation, limited resources and vulnerable ecosystems. Hence, the main goal of this research was to profile SEA practices and procedures in European small islands and provide a background for future research aiming to improve context-specific SEA applications. To achieve this goal, an exploratory case study was developed using Azores (Portugal) and Orkney (Scotland) archipelagos. An analysis of the corresponding mainland was also carried out to contextualise both case studies. The data collection was achieved through a qualitative content analysis of 43 Environmental Reports. The research found that there is not an SEA context-specific approach used within these European small islands, including guidelines, assessment topics, assessment techniques, follow-up and stakeholders engagement. The debate concerning specific approaches to small islands must be re-focused on the enhancement of SEA capacity-building amongst different stakeholders (including decision-makers), on the development and implementation of collaborative approaches, and on the exchange of knowledge and experiences between small islands networks. - Highlights: • Reviewed the differences between the Portuguese and Scottish SEA system • Showed a low integration of SEA specific features in reports of European small islands • Provides background for future SEA research for small islands approaches

  8. Advances in continuous gamma-ray spectrometry and applications

    International Nuclear Information System (INIS)

    Gold, R.; McNeece, J.P.; Kaiser, B.J.

    1984-07-01

    Recent advances and applications in continuous Compton recoil gamma-ray spectrometry are described. Applications of continuous gamma-ray spectrometry are presented for: (1) Characterization of light water reactor (LWR) pressures vessel (PV) environments. (2) Assessment of fuel distributions for Three Mile Island Unit 2 (TMI-2) reactor recovery. (3) Measurement of LWR-PV-neutron exposure. The latest improvements attained with the Janus probe, a special in-situ configuration of Si(Li) detectors, are presented. The status of current efforts to extend the domain of applicability of this method beyond 3 MeV is discussed with emphasis on recent work carried out with Si(Li) detectors of much larger volume

  9. Improving nuclear generating station response for electrical grid islanding

    International Nuclear Information System (INIS)

    Chou, Q.B.; Kundur, P.; Acchione, P.N.; Lautsch, B.

    1989-01-01

    This paper describes problems associated with the performance characteristics of nuclear generating stations which do not have their overall plant control design functions co-ordinated with the other grid controls. The paper presents some design changes to typical nuclear plant controls which result in a significant improvement in both the performance of the grid island and the chances of the nuclear units staying on-line following the disturbance. This paper focuses on four areas of the overall unit controls and turbine governor controls which could be modified to better co-ordinate the control functions of the nuclear units with the electrical grid. Some simulation results are presented to show the performance of a typical electrical grid island containing a nuclear unit with and without the changes

  10. Mechanical properties and examination of cracking in TMI-2 pressure vessel lower head material

    International Nuclear Information System (INIS)

    Diercks, D.R.; Neimark, L.A.

    1993-09-01

    Mechanical tests have been conducted on material from 15 samples removed from the lower head of the Three Mile Island unit 2 nuclear reactor pressure vessel. Measured properties include tensile properties and hardness profiles at room temperature, tensile and creep properties at temperatures of 600 to 1200 degrees C, and Charpy V-notch impact properties at -20 to +300 degrees C. These data, which were used in the subsequent analyses of the margin-to-failure of the lower head during the accident, are presented here. In addition, the results of metallographic and scanning electron microscope examinations of cladding cracking in three of the lower head samples are discussed

  11. Geomorphological control on podzolisation - An example from a tropical barrier island

    Science.gov (United States)

    Martinez, Pedro; Buurman, Peter; Lopes-Mazzetto, Josiane Millani; Giannini, Paulo César Fonseca; Schellekens, Judith; Vidal-Torrado, Pablo

    2018-05-01

    We investigated how the geomorphology of coastal barrier islands impacts soil hydrology and drainage at the landscape scale. Ilha Comprida is a Holocene barrier island with a 2.5 km-long cliff that is perpendicular to the coastal shore which provides an ideal condition to study the relation between age, relief, hydrology, and podzol morphology. Five geomorphic units were identified that differed in surface morphology and alignment of ridges and swales. Optical stimulated luminescence (OSL) dating showed that these geomorphic units had growth phases that decreased in age from west to east (Units I-V, from 5250 ± 820 to 325 ± 31 years ago, respectively). The geomorphic units were studied in two parallel 3 km transects on the southern part of the island. Along transect A-B, about 1 km from the southern shore, deep augerings were used to study sedimentary sequence and soil development, while on transect C-D on the southern shore, the continuous cliff exposure allowed more detailed morphological investigation. On all geomorphic units excluding the youngest, podzolisation has been the main soil-forming process. Groundwater level was monitored monthly for two years in 14 deep wells along transect A-B. Groundwater level during the formation of the B horizon was ascertained by determination of Fe. Podzol morphology (color of B horizon and its boundary with the E horizon) generally showed correlation to groundwater levels for both transects, except for the podzols in southwestern part of the island (Unit II). The podzols of Unit II showed an extremely thick (3 m) Bhm horizon devoid of Fe, indicating that they were formed under poor drainage conditions. However, soil morphology (undulating EB horizon boundary) and measured groundwater levels (below the B horizons) demonstrated that drainage has been improved. The extremely thick B horizon (3 m) in those podzols, which was formed in approximately 3000 years, and its genesis is explained by concentrated lateral flow of DOM

  12. A nuclear power unit with a Babcock type steam generating system-analysis of the break-down in the Three Mile Island power plant

    International Nuclear Information System (INIS)

    Werner, A.

    1980-01-01

    Installations of the primary and the secondary circuits and basic automatic control and protection systems for a nuclear power unit with Babcock type vertical, once-through steam generator are described. On this background the course of the break-down in the Three Mile Island power plant at Harrisburg is presented and analysed. (author)

  13. Ground Water Atlas of the United States: Segment 13, Alaska, Hawaii, Puerto Rico, and the U.S. Virgin Islands

    Science.gov (United States)

    Miller, James A.; Whitehead, R.L.; Oki, Delwyn S.; Gingerich, Stephen B.; Olcott, Perry G.

    1997-01-01

    Alaska is the largest State in the Nation and has an area of about 586,400 square miles, or about one-fifth the area of the conterminous United States. The State is geologically and topographically diverse and is characterized by wild, scenic beauty. Alaska contains abundant natural resources, including ground water and surface water of chemical quality that is generally suitable for most uses.The central part of Alaska is drained by the Yukon River and its tributaries, the largest of which are the Porcupine, the Tanana, and the Koyukuk Rivers. The Yukon River originates in northwestern Canada and, like the Kuskokwim River, which drains a large part of southwestern Alaska , discharges into the Bering Sea. The Noatak River in northwestern Alaska discharges into the Chukchi Sea. Major rivers in southern Alaska include the Susitna and the Matanuska Rivers, which discharge into Cook Inlet, and the Copper River, which discharges into the Gulf of Alaska . North of the Brooks Range, the Colville and the Sagavanirktok Rivers and numerous smaller streams discharge into the Arctic Ocean.In 1990, Alaska had a population of about 552,000 and, thus , is one of the least populated States in the Nation. Most of the population is concentrated in the cities of Anchorage, Fairbanks, and Juneau, all of which are located in lowland areas. The mountains, the frozen Arctic desert, the interior plateaus, and the areas covered with glaciers lack major population centers. Large parts of Alaska are uninhabited and much of the State is public land. Ground-water development has not occurred over most of these remote areas.The Hawaiian islands are the exposed parts of the Hawaiian Ridge, which is a large volcanic mountain range on the sea floor. Most of the Hawaiian Ridge is below sea level (fig. 31) . The State of Hawaii consists of a group of 132 islands, reefs, and shoals that extend for more than 1 ,500 miles from southeast to northwest across the central Pacific Ocean between about 155

  14. Test Area North Pool Stabilization Project: Environmental assessment

    International Nuclear Information System (INIS)

    1996-05-01

    The Test Area North (TAN) Pool is located within the fenced TAN facility boundaries on the Idaho National Engineering Laboratory (INEL). The TAN pool stores 344 canisters of core debris from the March, 1979, Three Mile Island (TMI) Unit 2 reactor accident; fuel assemblies from Loss-of-Fluid Tests (LOFT); and Government-owned commercial fuel rods and assemblies. The LOFT and government owned commercial fuel rods and assemblies are hereafter referred to collectively as open-quotes commercial fuelsclose quotes except where distinction between the two is important to the analysis. DOE proposes to remove the canisters of TMI core debris and commercial fuels from the TAN Pool and transfer them to the Idaho Chemical Processing Plant (ICPP) for interim dry storage until an alternate storage location other than at the INEL, or a permanent federal spent nuclear fuel (SNF) repository is available. The TAN Pool would be drained and placed in an industrially and radiologically safe condition for refurbishment or eventual decommissioning. This environmental assessment (EA) identifies and evaluates environmental impacts associated with (1) constructing an Interim Storage System (ISS) at ICPP; (2) removing the TMI and commercial fuels from the pool and transporting them to ICPP for placement in an ISS, and (3) draining and stabilizing the TAN Pool. Miscellaneous hardware would be removed and decontaminated or disposed of in the INEL Radioactive Waste Management Complex (RWMC). This EA also describes the environmental consequences of the no action alternative

  15. Heat transfer between relocated materials and the RPV lower head

    International Nuclear Information System (INIS)

    Rempe, J.L.; Knudson, D.L.; Kohriyama, T.

    2001-01-01

    Questions about the coolability of a continuous mass of relocated corium were raised during the Three Mile Island Unit 2 (TMI-2) Vessel Investigation Project (VIP) Post-accident examinations indicate that nearly half of the material that relocated to the vessel lower head during the TMI-2 accident formed a cohesive or ''continuous'' layer. TMI-2 VIP results and other evidence suggest that conduction through this continuous layer of solidified corium materials was assisted by other cooling mechanisms. Because increased knowledge about in-vessel coolability of corium materials may assist reactor designers in demonstrating that their concepts are passively safe, there is international interest in this topic. However, data are needed to identify what cooling mechanism(s) occurred and to develop a validated model for predicting this cooling. Corium cooling models significantly impact predictions for subsequent accident progression, such as the estimated time and mode of vessel failure. Hence, improved cooling models will provide a much needed, missing component of severe accident analyses. This paper provides a critical review of research investigating the coolability of corium relocating to a water-filled lower head. Where possible, existing models and data for predicting cooling are quantitatively compared; and governing relationships are identified. Key phenomena that should be incorporated into models for predicting this heat transfer are discussed, and deficiencies in current models and available data for predicting cooling are noted. Recommendations for improving these models and for obtaining data to validate these models are also provided. (author)

  16. The people of Three Mile Island

    International Nuclear Information System (INIS)

    Tredici, R. del.

    1982-01-01

    Compilation of 51 interviews with people of the most various social classes of the surrounding of TMI immediately and some time after the accident. Interviews of the year 1981, e.g. with Dr. Tokuhata, functionary in the Ministry of Health of Pa, on a pretended increase of infant mortality after the accident, are not contained in the original American edition. (HP) [de

  17. Compensation for the victims of the Marshall Islands nuclear testing programme: the Marshall Islands Nuclear Claims Tribunal

    International Nuclear Information System (INIS)

    Briscoe, W.

    1992-01-01

    The Marshall Islands Nuclear Claims Tribunal was established in 1988 pursuant to legislation enacted by the Republic of the Marshall Islands as part of its obligations under the Compact of Free Association between it and the United States (ratified 1986) and an associated Compact implementation agreement. The Tribunal is generally considered to be the last hope for compensation for a large number of Marshallese who claim to have suffered injury or damage as a result of the United States Nuclear Testing Programme in the Marshall Islands, 1946 - 1958. Under the Compact, the United States admitted liability for injuries and damages suffered by Marshallese as a result of the Testing Programme and made provision for the payment of compensation. In return, the Republic agreed to espouse, on behalf of it and its citizens, all current and future claims for compensation against the United States. The Tribunal has been given a most challenging and unique assignment: - to identify and compensate the victims of the Testing Programme, with a potentially limited sum of money, an indefinite number of victims, and with cultural, environmental and political circumstances which are not altogether conducive to Western concepts associated with compensating people for damages and personal injuries suffered as a result of a wrongful act. The paper will describe the Tribunal's role in compensating the victims of the Testing Programme. It will highlight a number of legal, social and cultural difficulties in establishing and operating a scheme to compensate people for damages and injuries suffered or commenced up to forty years previously. (author)

  18. CNSS plant concept, capital cost, and multi-unit station economics

    Energy Technology Data Exchange (ETDEWEB)

    1984-07-01

    United Engineers and Constructors (UE and C) and the Babcock and Wilcox Company (B and W) have performed several studies over the last eight years related to small integral pressurized water reactors. These reactors include the 365 MWt (100 MWe) Consolidated Nuclear Steam Generator (CNSG) and the 1200 MWt Consolidated Nuclear Steam System (CNSS). The studies, mostly performed under contract to the Oak Ridge National Laboratory, have led to a 1250 MWt (400 MWe) Consolidated Nuclear Steam System (CNSS) plant concept, with unique design and cost features. This report contains an update of earlier studies of the CNSS reactor and balance-of-plant concept design, capital costs, and multi-unit plant economics incorporating recent design developments, improvements, and post-TMI-2 upgrades. The economic evaluation compares the total system economic impact of a phased, three stage 400 MWe CNSS implementation program, i.e., a three-unit station, to the installation of a single 1200 MWe Pressurized Water Reactor (PWR) into a typical USA utility system.

  19. CNSS plant concept, capital cost, and multi-unit station economics

    International Nuclear Information System (INIS)

    1984-07-01

    United Engineers and Constructors (UE and C) and the Babcock and Wilcox Company (B and W) have performed several studies over the last eight years related to small integral pressurized water reactors. These reactors include the 365 MWt (100 MWe) Consolidated Nuclear Steam Generator (CNSG) and the 1200 MWt Consolidated Nuclear Steam System (CNSS). The studies, mostly performed under contract to the Oak Ridge National Laboratory, have led to a 1250 MWt (400 MWe) Consolidated Nuclear Steam System (CNSS) plant concept, with unique design and cost features. This report contains an update of earlier studies of the CNSS reactor and balance-of-plant concept design, capital costs, and multi-unit plant economics incorporating recent design developments, improvements, and post-TMI-2 upgrades. The economic evaluation compares the total system economic impact of a phased, three stage 400 MWe CNSS implementation program, i.e., a three-unit station, to the installation of a single 1200 MWe Pressurized Water Reactor (PWR) into a typical USA utility system

  20. Optimized Dispatch Schedule for Autonomous Grids in Isolated Islands

    Directory of Open Access Journals (Sweden)

    Fan Liuyang

    2016-01-01

    Full Text Available The rapid development of wind power provides a new solution for power supply of isolated island. However, due to the intermittent and stochastic nature of renewable energy resources (RES, the energy storage unit (ESU is required for power grid reliability. This paper proposed an automatic programming method for autonomous grid in isolated islands. The sea water pumped storage plant serves as ESU to counter-balance the fluctuations of RESs. The penetration level of RES and the profit of the Island system operator (ISO increase significantly. With the geographical and historical data of an island in China, the effectiveness of the proposed method is testified.

  1. TMI-2 decay power: LASL fission-product and actinide decay power calculations for the President's commission on the accident at Three Mile Island

    International Nuclear Information System (INIS)

    England, T.R.; Wilson, W.B.

    1980-03-01

    Fission-product and actinide decay heating, gas content, curies, and detailed contributions of the most important nuclide contributors were supplied in a series of letters following requests from the Presidential Commission on the Accident at Three Mile Island. In addition, similar data assuming different irradiation (power) histories were requested for purposes of comparison. This report consolidates the tabular and graphical data supplied and explains its basis

  2. Tellurium release and deposition during the TMI-2 accident

    International Nuclear Information System (INIS)

    Vinjamuri, K.; Osetek, D.J.; Hobbins, R.R.; Jessup, J.S.

    1984-09-01

    The estimated behavior of tellurium during and after the accident at the Three Mile Island Unit-2 is presented. The behavior is based on all available measurement data for /sup 129m/Te, 132 Te, stable tellurium ( 126 Te, 128 Te and 130 Te), and best estimate calculations of tellurium release and transport. The predicted release was calculated using current techniques that relate release rate to fuel temperature and holdup of tellurium in zircaloy until significant oxidation occurs. The calculated release fraction was low, approx. 7%, but the total measured release for samples analyzed to date is about 5.8%. Of the measured tellurium about 2.4, 1.8, 0.88, 0.42, 0.17 and 0.086% of core inventory were in the containment sump water, upper plenum assembly surfaces, containment solids in the sump water, makeup and purification demineralizer, containment inside surface, and the reactor primary coolant, respectively. A significant fraction (54%) of the tellurium calculated to be retained on the upper plenum surfaces (4.61% of the core inventory) was deposited during the high pressure injection of coolant at about 200 min after the reactor scram. Comparison of tellurium behavior with in-pile and out-of-pile tests strongly suggests that zircaloy holds tellurium until significant cladding oxidation occurs

  3. Tellurium behavior during and after the TMI-2 accident

    International Nuclear Information System (INIS)

    Vinjamuri, K.; Osetek, D.J.; Hobbins, R.R.

    1984-01-01

    The estimated behavior of tellurium during and after the accident at the Three Mile Island Unit-2 is presented. The behavior is based on all available measurement data for /sup 129m/Te, 132 Te and stable tellurium ( 126 Te, 128 Te and 130 Te), and best estimate calculations of tellurium release and transport. The predicted release was calculated using current techniques that relate release rate to fuel temperature and holdup of tellurium in zircaloy until significant oxidation occurs. The calculated release fraction was low, approximately 7%, but the total measured release for samples analyzed to date is about 4.0%. Of the measured tellurium about 2.4, 0.88, 0.42, 0.17 and 0.086% of core inventory were in the containment sump water, containment solids in water, makeup and purification demineralizer, containment inside surface, and the reactor primary coolant, respectively. A significant fraction (54%) of the calculated tellurium retained on the upper plenum surfaces (4.61% of the core inventory) was deposited during the high pressure injection of coolant at about 200 minutes after the reactor scram. Comparison of tellurium behavior with inpile and out-of-pile tests strongly suggests that zircaloy holds tellurium until significant cladding oxidation occurs

  4. The Frequency Control in the islanded Micro Grid by using STATCOM Controllers

    Directory of Open Access Journals (Sweden)

    Ghulam Mustufa Bhutto

    2015-10-01

    Full Text Available When the distribution system is disconnected from the transmission system, the islanded portion of the network comprising DG (Distributed Generation units forms a MG (Micro Grid. It is essential either to shut down the DG units or ensure the stable and the controlled operation of the islanded MG. The frequency and the voltage of the islanded MG vary when it is isolated from the main transmission grid. The voltage and the frequency of the islanded MG can be controlled to the permissible limits by providing the required amount of the active and reactive power by the local available sources in the MG. The main focus of this paper is about the control of the network frequency in the islanded MG by employing PI controllers based STATCOM (Static Compensator and BESS-STATCOM (Battery Energy Storage System Equipped devices. The study is done by using DIgSILENT power factory software version 15.0

  5. The frequency control in the islanded micro grid by using statcom controllers

    International Nuclear Information System (INIS)

    Bhutto, G.M.

    2015-01-01

    When the distribution system is disconnected from the transmission system, the islanded portion of the network comprising DG (Distributed Generation) units forms a MG (Micro Grid). It is essential either to shut down the DG units or ensure the stable and the controlled operation of the islanded MG. The frequency and the voltage of the islanded MG vary when it is isolated from the main transmission grid. The voltage and the frequency of the islanded MG can be controlled to the permissible limits by providing the required amount of the active and reactive power by the local available sources in the MG. The main focus of this paper is about the control of the network frequency in the islanded MG by employing PI controllers based STATCOM (Static Compensator) and BESS-STATCOM (Battery Energy Storage System Equipped) devices. The study is done by using DIgSILENT power factory software version 15.0. (author)

  6. Percolation cooling of the Three Mile Island Unit 2 lower head by way of thermal cracking and gap formation

    DEFF Research Database (Denmark)

    Thomsen, K.L.

    2002-01-01

    Two partial models have been developed to elucidate the Three Mile Island Unit 2 lower head coolability by water percolation from above into the thermally cracking debris bed and into a gap between the debris and the wall The bulk permeability of the cracked top crust is estimated based on simple...... fracture mechanics and application of Poiseuille's law to the fractures. The gap is considered as an abstraction representing an initially rugged interface, which probably expanded by thermal deformation and cracking in connection with the water ingress. The coupled flow and heat conduction problem...

  7. Evaluation of Nuclear Facility Decommissioning Projects. Summary Report. Three Mile Island Unit 2 Polar Crane Recovery

    International Nuclear Information System (INIS)

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

    1984-08-01

    This document summarizes information concerning restoration of the Three Mile Island-Unit 2 Polar Crane to a fully operational condition following the loss of coolant accident experienced on March 28, 1979. The data collected from activity reports, reactor containment entry records, and other sources were placed in a computerized information retrieval/manipulation system which permits extraction/manipulation of specific data which could be utilized in planning for recovery activities should a similar accident occur in a nuclear generating plant. The information is presented in both computer output form and a manually assembled summarization. This report contains only the manpower requirements and radiation exposures actually incurred during recovery operations within the reactor containment and does not include support activities or costs. (author)

  8. Surficial geology of the sea floor in Long Island Sound offshore of Plum Island, New York

    Science.gov (United States)

    McMullen, K.Y.; Poppe, L.J.; Danforth, W.W.; Blackwood, D.S.; Schaer, J.D.; Ostapenko, A.J.; Glomb, K.A.; Doran, E.F.

    2010-01-01

    The U.S. Geological Survey (USGS), the Connecticut Department of Environmental Protection, and the National Oceanic and Atmospheric Administration (NOAA) have been working cooperatively to interpret surficial sea-floor geology along the coast of the Northeastern United States. NOAA survey H11445 in eastern Long Island Sound, offshore of Plum Island, New York, covers an area of about 12 square kilometers. Multibeam bathymetry and sidescan-sonar imagery from the survey, as well as sediment and photographic data from 13 stations occupied during a USGS verification cruise are used to delineate sea-floor features and characterize the environment. Bathymetry gradually deepens offshore to over 100 meters in a depression in the northwest part of the study area and reaches 60 meters in Plum Gut, a channel between Plum Island and Orient Point. Sand waves are present on a shoal north of Plum Island and in several smaller areas around the basin. Sand-wave asymmetry indicates that counter-clockwise net sediment transport maintains the shoal. Sand is prevalent where there is low backscatter in the sidescan-sonar imagery. Gravel and boulder areas are submerged lag deposits produced from the Harbor Hill-Orient Point-Fishers Island moraine segment and are found adjacent to the shorelines and just north of Plum Island, where high backscatter is present in the sidescan-sonar imagery.

  9. Application of space and aviation technology to improve the safety and reliability of nuclear power plant operations. Final report

    International Nuclear Information System (INIS)

    1980-04-01

    This report investigates various technologies that have been developed and utilized by the aerospace community, particularly the National Aeronautics and Space Administration (NASA) and the aviation industry, that would appear to have some potential for contributing to improved operational safety and reliability at commercial nuclear power plants of the type being built and operated in the United States today. The main initiator for this study, as well as many others, was the accident at the Three Mile Island (TMI) nuclear power plant in March 1979. Transfer and application of technology developed by NASA, as well as other public and private institutions, may well help to decrease the likelihood of similar incidents in the future

  10. Three Mile Island Startup program and its contributions to plant performance

    International Nuclear Information System (INIS)

    Brill, R.A.; Barton, J.J.

    1976-01-01

    The General Public Utilities Service Corporation Startup Organization provided a specialized group for startup testing, coordination, and management of the Three Mile Island Unit No. 1 nuclear power plant. This organization conducted an extensive test program which contributed to Three Mile Island's high first year plant availability

  11. Sähköisen markkinointiviestinnän kehittäminen pienyritykselle : Case: Kodinkonehuolto ja myynti T:mi Jukka Mäkeläinen

    OpenAIRE

    Kerola, Anna

    2016-01-01

    Tämän opinnäytetyön aiheena on markkinointiviestinnän kehittäminen pienyritykselle. Toimeksiantajana toimii Kodinkonehuolto ja myynti T:mi Jukka Mäkeläinen. Toiveena oli markkinointiviestinnän siirtäminen verkkoon. Markkinointiviestintää on yrityksessä hoidettu ainoastaan lehtimainonnan avulla, joka ei ole enää tuottanut toivottua tulosta. Facebook-sivun käyttöönoton tarkoituksena oli näkyvyyden lisääminen omalla toiminta-alueella, olemassa olevien asiakkaiden aktivoiminen ja uusien asiakkaid...

  12. TMI-2: Lessons learned by the US Department of Energy: A programmatic perspective

    International Nuclear Information System (INIS)

    Schmitt, R.C.; Reno, H.W.; Bentley, K.J.; Owens, D.E.

    1990-03-01

    This report is a summary of the lessons learned by the US Department of Energy during its decade-long participation in the research and accident cleanup project at Three Mile Island Nuclear Power Station Unit 2 near Harrisburg, Pennsylvania. It is based on a review of a wide range of project documents and interviews with personnel from the many organizations involved. The lessons are organized into major subjects with a brief background section to orient the reader to that subject. The subjects are divided into sub-topics, each with a brief discussion and a series of lessons learned. The lessons are very brief and each is preceded with a keyword phrase to highlight its specific topic. References are given so that the details of the subject and the lesson can be further investigated. 99 refs., 24 figs

  13. Voltage control of DC islanded microgrids

    DEFF Research Database (Denmark)

    Tucci, Michele; Riverso, Stefano; Quintero, Juan Carlos Vasquez

    2015-01-01

    We propose a new decentralized control scheme for DC Islanded microGrids (ImGs) composed by several Distributed Generation Units (DGUs) with a general interconnection topology. Each local controller regulates to a reference value the voltage of the Point of Common Coupling (PCC...

  14. Characterization of solids in the Three Mile Island Unit 2 reactor defueling water

    International Nuclear Information System (INIS)

    Campbell, D.O.

    1987-12-01

    Because of the impact of poor water clarity on defueling operations at the Three Mile Island Unit 2 Nuclear Power Station, a study was undertaken to characterize suspended particulates in the reactor defueling water. The examination included cascade filtration through Nuclepore filters of progressively smaller pore sizes, using three water samples obtained at different times and after varying degrees of clarification. The solids collected on the filters were examined with a scanning electron microscope and analyzed with energy-dispersive x-ray fluorescence. A wide variety of solids was observed, and 26 elements were detected. These included all the materials expected from the reactor system (uranium, zirconium, silver, cadmium, indium, iron, chromium, and nickel), chemicals and zeolites used to decontaminate the water (aluminum, silicon, sodium), common impurities (potassium, chlorine, sulfur, magnesium, calcium, and others), as well as some unexpected metals (molybdenum, manganese, bromine, and lead). There was also evidence for the presence of organic material. A diverse assortment of particles with widely varying surface properties was found to be present

  15. QA in the design and fabrication of the TMI-2 rail cask

    International Nuclear Information System (INIS)

    Hayes, G.R.

    1988-01-01

    EGandG Idaho, Inc., acting on behalf of the US Department of Energy, is responsible for transporting core debris from Three Mile Island-Unit 2 to the Idaho National Engineering Laboratory. Transportation of the debris is being accomplished using an NRC licensed container, called the NuPac 125-B. This paper describes the NuPac 125-B Rail Cask and the quality assurance (QA) requirements for that system. Also discussed are the QA roles of the various organizations involved in designing, building, inspecting and testing the NuPac 125-B. The paper presents QA/QC systems implemented during the design, procurement, and fabrication of the cask to assure compliance with all applicable technical codes, standards and regulations. It also goes beyond the requirements aspect and describes unique QA/QC measures employed to assure that the cask was built with minimum QA problems. Finally, the lessons learned from the NuPac 125-B project is discussed. 4 refs., 4 figs

  16. PREFACE: Selected contributions from the 3rd Theory Meets Industry International Workshop, TMI2009 (Nagoya, Japan, 11-13 November 2009) Selected contributions from the 3rd Theory Meets Industry International Workshop, TMI2009 (Nagoya, Japan, 11-13 November 2009)

    Science.gov (United States)

    Tanaka, Isao; Hafner, Jürgen; Wimmer, Erich; Asahi, Ryoji

    2010-09-01

    The structures, physicochemical and thermodynamic properties of materials are becoming increasingly amenable to treatment by first-principles (ab initio) quantum mechanical simulations. Calculations containing a few hundred atoms are now routine, thanks to improvements in computer technology and computational techniques. Schemes to determine electronic structures more accurately and to treat more complex systems continue to be developed. A growing number of scientists and engineers are becoming aware of the power of these approaches. By applying these new computational tools, materials science and technology is expected to enter a new era of accelerated progress and efficiency. In 1998 the first workshop entitled 'Theory Meets Industry' (TMI) was held at the Vienna University of Technology. The aim of the workshop was to direct the potential of the ab initio simulation codes developed in academia towards the necessities arising from industrial research. Over the next decade, significant advances in ab initio methodology and its application to academic and industrial research were achieved. It was thus considered timely to hold a second TMI workshop in 2007, again in Vienna. The contributions from academia concentrated on a wide range of new developments in ab initio simulations, as well as on applications at the forefront of materials research. Speakers from the industrial sector also emphasized the progress made in successfully applying ab initiotechniques to key areas of modern technology. The proceedings were published in Journal of Physics: Condensed Matter as a special issue (volume 20, number 6, 2008), which was included in the 'Top papers 2008 showcase' of that journal. Following the notable success of the first two workshops, it was decided that the third TMI workshop would be held outside Europe. Holding the workshop in Japan was intended to increase awareness of theoretical materials science and foster further international collaboration in this field

  17. Transport Signatures of Quasiparticle Poisoning in a Majorana Island.

    Science.gov (United States)

    Albrecht, S M; Hansen, E B; Higginbotham, A P; Kuemmeth, F; Jespersen, T S; Nygård, J; Krogstrup, P; Danon, J; Flensberg, K; Marcus, C M

    2017-03-31

    We investigate effects of quasiparticle poisoning in a Majorana island with strong tunnel coupling to normal-metal leads. In addition to the main Coulomb blockade diamonds, "shadow" diamonds appear, shifted by 1e in gate voltage, consistent with transport through an excited (poisoned) state of the island. Comparison to a simple model yields an estimate of parity lifetime for the strongly coupled island (∼1  μs) and sets a bound for a weakly coupled island (>10  μs). Fluctuations in the gate-voltage spacing of Coulomb peaks at high field, reflecting Majorana hybridization, are enhanced by the reduced lever arm at strong coupling. When converted from gate voltage to energy units, fluctuations are consistent with previous measurements.

  18. Aerial radiological and photographic survey of eleven atolls and two islands within the Northern Marshall Islands. Dates of surveys, July-November 1978

    International Nuclear Information System (INIS)

    1981-06-01

    An aerial radiological survey was conducted over eleven atolls and two islands within the northern Marshall Islands between September and November 1978. This survey was part of a comprehensive radiological survey, which included extensive terrestrial and marine sampling, to determine possible residual contamination which might remain as a result of the United States nuclear testing program conducted at Bikini Enewetak Atolls between 1946 and 1958. A similar survey was conducted at Enewetak Atoll in 1972. The present survey covered those atolls known to have received direct fallout from the Bravo event, conducted in March 1954 at Bikini Atoll. These included Bikini, Rongelap, Rongerik, Ailinginae, Bikar, Taka, and Utirik Atolls. In addition, several atolls and islands which might have been at the fringes of the Bravo fallout were also surveyed, including Likiep and Ailuk Atolls, Jemo and Mejit Islands, and Wotho Atoll. Ujelang Atoll, which lies approximately 200 km southwest of Enewetak, was also surveyed. Island-averaged terrestrial exposure rates in the range of 30 to 50 μR/h were observed over parts of Bikini Atoll, including Bikini Island, and over the northern part of Rongelap Atoll. Levels over southern Rongelap and over Rongerik Atoll ranged from 4 to 7 μR/h. Levels were somewhat lower at Ailinginae Atoll (approximately 2 μR/h) and at Utirik Atoll (approximately 0.7 μR/h). The variations observed were consistent with what might be expected from the fallout pattern of the Bravo event. Levels at Ailuk, Likiep, Wotho and Ujelang Atolls and at Mejit and Jemo Islands were consistent with 137 Cs activity, due to worldwide fallout, observed within the United States and at other locations in the central Pacific. These four atolls and the two islands, therefore, do not appear to have recieved any significant direct contamination from the Bravo event or the other tests conducted at Bikini and Enewetak Atolls

  19. Heat transfer between relocated materials and the RPV lower head

    Energy Technology Data Exchange (ETDEWEB)

    Rempe, J.L.; Knudson, D.L. [Idaho National Engineering and Environmental Lab., Idaho Falls, ID (United States); Kohriyama, T. [INSS, Fukui (Japan)

    2001-07-01

    Questions about the coolability of a continuous mass of relocated corium were raised during the Three Mile Island Unit 2 (TMI-2) Vessel Investigation Project (VIP) Post-accident examinations indicate that nearly half of the material that relocated to the vessel lower head during the TMI-2 accident formed a cohesive or ''continuous'' layer. TMI-2 VIP results and other evidence suggest that conduction through this continuous layer of solidified corium materials was assisted by other cooling mechanisms. Because increased knowledge about in-vessel coolability of corium materials may assist reactor designers in demonstrating that their concepts are passively safe, there is international interest in this topic. However, data are needed to identify what cooling mechanism(s) occurred and to develop a validated model for predicting this cooling. Corium cooling models significantly impact predictions for subsequent accident progression, such as the estimated time and mode of vessel failure. Hence, improved cooling models will provide a much needed, missing component of severe accident analyses. This paper provides a critical review of research investigating the coolability of corium relocating to a water-filled lower head. Where possible, existing models and data for predicting cooling are quantitatively compared; and governing relationships are identified. Key phenomena that should be incorporated into models for predicting this heat transfer are discussed, and deficiencies in current models and available data for predicting cooling are noted. Recommendations for improving these models and for obtaining data to validate these models are also provided. (author)

  20. Studies in training nuclear plant personnel

    International Nuclear Information System (INIS)

    Hamlin, K.W.

    1987-01-01

    One of the lessons learned from the Three Mile Island (TMI) accident was that the nuclear industry was ineffective in learning from previous events at other plants. As training programs and methods have improved since TMI, the nuclear industry has searched for effective methods to teach the lessons learned from industry events. The case study method has great potential as a solution. By reviewing actual plant events in detail, trainees can be challenged with solving actual problems. When used in a seminar or discussion format, these case studies also help trainees compare their decision-making processes with other trainees, the instructor, and the personnel involved in the actual case study event

  1. Research needs for strandplain/barrier island reservoirs in the United States

    Energy Technology Data Exchange (ETDEWEB)

    Cole, E.L.; Fowler, M.L.; Salamy, S.P.; Sarathi, P.S.; Young, M.A.

    1994-12-01

    This report identifies reservoir characterization and reservoir management research needs and IOR process and related research needs for the fourth geologic class, strandplain/barrier island reservoirs. The 330 Class 4 reservoirs in the DOE Tertiary OH Recovery Information System (TORIS) database contain about 30.8 billion barrels of oil or about 9% of the total original oil-in-place (OOIP) in all United States reservoirs. The current projection of Class 4 ultimate recovery with current operations is only 38% of the OOIP, leaving 19 billion barrels as the target for future IOR projects. Using the TORIS database and its predictive and economic models, the recovery potential which could result from future application of IOR technologies to Class 4 reservoirs was estimated to be between 1.0 and 4.3 billion barrels, depending on oil price and the level of technology advancement. The analysis indicated that this potential could be realized through (1) infill drilling alone and in combination with polymer flooding and profile modification, (2) chemical flooding (surfactant), and (3) thermal processes. Most of this future potential is in Texas, Oklahoma, California, and the Rocky Mountain region. Approximately two-thirds of the potentially recoverable resource is at risk of abandonment by the year 2000, which emphasizes the urgent need for the development and demonstration of cost-effective recovery technologies.

  2. 3-D core modelling of RIA transient: the TMI-1 benchmark

    International Nuclear Information System (INIS)

    Ferraresi, P.; Studer, E.; Avvakumov, A.; Malofeev, V.; Diamond, D.; Bromley, B.

    2001-01-01

    The increase of fuel burn up in core management poses actually the problem of the evaluation of the deposited energy during Reactivity Insertion Accidents (RIA). In order to precisely evaluate this energy, 3-D approaches are used more and more frequently in core calculations. This 'best-estimate' approach requires the evaluation of code uncertainties. To contribute to this evaluation, a code benchmark has been launched. A 3-D modelling for the TMI-1 central Ejected Rod Accident with zero and intermediate initial powers was carried out with three different methods of calculation for an inserted reactivity respectively fixed at 1.2 $ and 1.26 $. The studies implemented by the neutronics codes PARCS (BNL) and CRONOS (IPSN/CEA) describe an homogeneous assembly, whereas the BARS (KI) code allows a pin-by-pin representation (CRONOS has both possibilities). All the calculations are consistent, the variation in figures resulting mainly from the method used to build cross sections and reflectors constants. The maximum rise in enthalpy for the intermediate initial power (33 % P N ) calculation is, for this academic calculation, about 30 cal/g. This work will be completed in a next step by an evaluation of the uncertainty induced by the uncertainty on model parameters, and a sensitivity study of the key parameters for a peripheral Rod Ejection Accident. (authors)

  3. 3-D core modelling of RIA transient: the TMI-1 benchmark

    Energy Technology Data Exchange (ETDEWEB)

    Ferraresi, P. [CEA Cadarache, Institut de Protection et de Surete Nucleaire, Dept. de Recherches en Securite, 13 - Saint Paul Lez Durance (France); Studer, E. [CEA Saclay, Dept. Modelisation de Systemes et Structures, 91 - Gif sur Yvette (France); Avvakumov, A.; Malofeev, V. [Nuclear Safety Institute of Russian Research Center, Kurchatov Institute, Moscow (Russian Federation); Diamond, D.; Bromley, B. [Nuclear Energy and Infrastructure Systems Div., Brookhaven National Lab., BNL, Upton, NY (United States)

    2001-07-01

    The increase of fuel burn up in core management poses actually the problem of the evaluation of the deposited energy during Reactivity Insertion Accidents (RIA). In order to precisely evaluate this energy, 3-D approaches are used more and more frequently in core calculations. This 'best-estimate' approach requires the evaluation of code uncertainties. To contribute to this evaluation, a code benchmark has been launched. A 3-D modelling for the TMI-1 central Ejected Rod Accident with zero and intermediate initial powers was carried out with three different methods of calculation for an inserted reactivity respectively fixed at 1.2 $ and 1.26 $. The studies implemented by the neutronics codes PARCS (BNL) and CRONOS (IPSN/CEA) describe an homogeneous assembly, whereas the BARS (KI) code allows a pin-by-pin representation (CRONOS has both possibilities). All the calculations are consistent, the variation in figures resulting mainly from the method used to build cross sections and reflectors constants. The maximum rise in enthalpy for the intermediate initial power (33 % P{sub N}) calculation is, for this academic calculation, about 30 cal/g. This work will be completed in a next step by an evaluation of the uncertainty induced by the uncertainty on model parameters, and a sensitivity study of the key parameters for a peripheral Rod Ejection Accident. (authors)

  4. 64 Percent of Asian and Pacific Islander Treatment Admissions Name Alcohol as Their Problem

    Science.gov (United States)

    Data Spotlight May 28, 2013 64 Percent of Asian and Pacific Islander Treatment Admissions Name Alcohol as ... common problem in the United States. 1 When Asians and Pacific Islanders (APIs) go to treatment, alcohol ...

  5. Prevalence of behavior problems in three-year-old children living near Three Mile Island: a comparative analysis.

    Science.gov (United States)

    Cornely, P; Bromet, E

    1986-07-01

    The Behavior Screening Questionnaire (BSQ) was used to determine whether 2 1/2-3 1/2 yr old children living near the TMI nuclear reactor were more disturbed than children living near another nuclear plant or near a fossil-fuel facility in Pennsylvania when assessed 2 1/2 yr later. The prevalence of behavior problems was 11%. Differences among the sites in overall rates and individual symptoms were small. Perceptions of environmental stress among the TMI sample of mothers were unrelated to BSQ scores, whereas in the comparison sites, where unemployment was rising, economic concerns were meaningfully related to the BSQ.

  6. Future wave and wind projections for United States and United-States-affiliated Pacific Islands

    Science.gov (United States)

    Storlazzi, Curt D.; Shope, James B.; Erikson, Li H.; Hegermiller, Christine A.; Barnard, Patrick L.

    2015-01-01

    Changes in future wave climates in the tropical Pacific Ocean from global climate change are not well understood. Spatially and temporally varying waves dominate coastal morphology and ecosystem structure of the islands throughout the tropical Pacific. Waves also impact coastal infrastructure, natural and cultural resources, and coastal-related economic activities of the islands. Wave heights, periods, and directions were forecast through the year 2100 using wind parameter outputs from four atmosphere-ocean global climate models from the Coupled Model Inter-Comparison Project, Phase 5, for Representative Concentration Pathways (RCP) scenarios 4.5 and 8.5 that correspond to moderately mitigated and unmitigated greenhouse gas emissions, respectively. Wind fields from the global climate models were used to drive a global WAVEWATCH-III wave model and generate hourly time-series of bulk wave parameters for 25 islands in the mid to western tropical Pacific for the years 1976–2005 (historical), 2026–2045 (mid-century projection), and 2085–2100 (end-of-century projection). Although the results show some spatial heterogeneity, overall the December-February extreme significant wave heights, defined as the mean of the top 5 percent of significant wave height time-series data modeled within a specific period, increase from present to mid-century and then decrease toward the end of the century; June-August extreme wave heights increase throughout the century within the Central region of the study area; and September-November wave heights decrease strongly throughout the 21st century, displaying the largest and most widespread decreases of any season. Peak wave periods increase east of the International Date Line during the December-February and June-August seasons under RCP4.5. Under the RCP8.5 scenario, wave periods decrease west of the International Date Line during December-February but increase in the eastern half of the study area. Otherwise, wave periods decrease

  7. Amchitka Island, Alaska, Biological Monitoring Report 2011 Sampling Results

    Energy Technology Data Exchange (ETDEWEB)

    None

    2013-09-01

    The Long-Term Surveillance and Maintenance (LTS&M) Plan for the U.S. Department of Energy (DOE) Office of Legacy Management (LM) Amchitka Island sites describes how LM plans to conduct its mission to protect human health and the environment at the three nuclear test sites located on Amchitka Island, Alaska. Amchitka Island, near the western end of the Aleutian Islands, is approximately 1,340 miles west-southwest of Anchorage, Alaska. Amchitka is part of the Aleutian Island Unit of the Alaska Maritime National Wildlife Refuge, which is administered by the U.S. Fish and Wildlife Service (USFWS). Since World War II, Amchitka has been used by multiple U.S. government agencies for various military and research activities. From 1943 to 1950, it was used as a forward air base for the U.S. Armed Forces. During the middle 1960s and early 1970s, the U.S. Department of Defense (DOD) and the U.S. Atomic Energy Commission (AEC) used a portion of the island as a site for underground nuclear tests. During the late 1980s and early 1990s, the U.S. Navy constructed and operated a radar station on the island. Three underground nuclear tests were conducted on Amchitka Island. DOD, in conjunction with AEC, conducted the first nuclear test (named Long Shot) in 1965 to provide data that would improve the United States' capability of detecting underground nuclear explosions. The second nuclear test (Milrow) was a weapons-related test conducted by AEC in 1969 as a means to study the feasibility of detonating a much larger device. Cannikin, the third nuclear test on Amchitka, was a weapons-related test detonated on November 6, 1971. With the exception of small concentrations of tritium detected in surface water shortly after the Long Shot test, radioactive fission products from the tests remain in the subsurface at each test location As a continuation of the environmental monitoring that has taken place on Amchitka Island since before 1965, LM in the summer of 2011 collected biological

  8. Analysis of Three Mile Island-Unit 2 accident

    International Nuclear Information System (INIS)

    1980-03-01

    The Nuclear Safety Analysis Center (NSAC) of the Electric Power Research Institute has analyzed the Three Mile Island-2 accident. Early results of this analysis were a brief narrative summary, issued in mid-May 1979 and an initial version of this report issued later in 1979 as noted in the Foreword. The present report is a revised version of the 1979 report, containing summaries, a highly detailed sequence of events, a comparison of that sequence of events with those from other sources, 25 appendices, references and a list of abbreviations and acronyms. A matrix of equipment and system actions is included as a folded insert

  9. Telemedicine in Majuro Hospital, Marshall Islands.

    Science.gov (United States)

    Gunawardane, K J

    2000-09-01

    Since March 1998 up to June 2000, telemedicine activities in Marshall Islands have mainly been for Referrals to Tripler Army Medical Center (TAMC) in Hawaii. The activities are based on a computer which has the Internet connection and accessories including a digital camera, flatbed scanner with a transparency adapter, color printer, a video printer, ophthalmoscope, otoscope and a video Lens, all of which were donated by Project Akamai in Hawaii. Two sessions of training were conducted by representatives from Akamai Project and from PBMA at the very beginning of the establishment of the unit, to all levels of Health Care Providers in Ministry of Health in Majuro. The computer and Internet facility is available 24 hours. Since March 1998 to June 2000, there had been 144 telemedicine consultations to TAMC. Out of a total of 326 off-island referrals for the same period, approximately 80 patients have been sent to TAMC using the PIHCP/Telemedicine program. This accounts for approximately 25% of total off-island referrals. This represents a significant reduction in cost. In addition to cost reduction the telemedicine unit most important impact is on the health providers, especially the physicians working at Majuro Hospital. Availability of medical information through internet has helped them to feel less isolated from the constantly changing field of medical science.

  10. Cask development, testing, and licensing

    International Nuclear Information System (INIS)

    Quinn, G.J.; Haelsig, R.T.; Warrant, M.M.

    1986-01-01

    The NuPac 125-B Rail Cask was developed to provide a safe means of transporting the damaged core of Three Mile Island Unit 2 from the TMI site at Middletown, PA, to the Idaho National Engineering laboratory (INEL) at Idaho Falls, ID. The development of the NuPac 125-B Rail Cask posed two engineering and technical management challenges; Licensing Strategy - The NuPac 125-B Rail Cask represented the first irradiated fuel rail cask developed within the United States in the past decade, a decade characterized by changing nuclear regulations, and Accelerated Schedule - The TMI-2 defueling schedule demanded a cask development schedule one-third as long as normally required. These challenges governed the overall development and licensing process for the cask. First, a high degree of conservation was incorporated into the design to allow quick, simplified demonstrations of adequacy to regulatory staff. Second, redundant design techniques were employed in all areas of uncertainty. The testing program eliminated performance uncertainties and validated predictions and predictive models. Drop tests of a quarter-scale model of the cask were conducted, and results were correlated with analytic predictions to verify structural and mechanical performance of the cask. Full-scale tests of the canisters were conducted to verify structural behavior of canister internals which provide criticality control. This paper describes the testing program for the NuPac 125-B Rail Cask, presents results therefrom, and correlates findings with Regulation 10 CFR 71 of the U.S. Nuclear Regulatory Commission

  11. Controlled Operation of the Islanded Portion of the International Council on Large Electric Systems (CIGRE Low Voltage Distribution Network

    Directory of Open Access Journals (Sweden)

    Ghullam Mustafa Bhutto

    2017-07-01

    Full Text Available In islanding, a portion of the power network, comprised of the loads and distributed generation (DG units, is isolated from the rest of the power grid and forms a micro grid (MG. In this condition, it becomes essential for the islanded MG to operate in a stable and controlled manner by providing ancillary services. When the MG is cut off from the main grid, the islanding must be detected by the DG units. In this condition it is essential that one of the controllers should be switched to the voltage-frequency (VF control mode. In islanding, the network loses it slack reference and this reference is established by a VF controller. The voltage and the frequency of the islanded MG deviate when disconnected from the transmission grid and these deviations are caused by the load-generation imbalance. The voltage and the frequency of the islanded MG can be restored to the permissible limits if the desired/exceeded amount of active and reactive power is injected/absorbed by the locally available sources in islanded MG. This paper proposes a control strategy which can compensate the voltage and the frequency deviations in the islanded portion of the International Council on Large Electric Systems (CIGRE low voltage distribution network by using advanced power electronics devices such as STATCOMs for Photovoltaic (PV Units and Battery Energy Storage Systems (BESS STATCOMs (for battery units. The selection of the VF controller for the most suitable DG unit of this test network is also presented in this paper, and the effectiveness of the controllers is verified by presenting simulation results using DIgSILENT (DIgSILENT GmbH, Gomaringen, Germany power factory software version 15.0.

  12. Geomorphology and Depositional Subenvironments of Gulf Islands National Seashore, Mississippi

    Science.gov (United States)

    Morton, Robert A.; Rogers, Bryan E.

    2010-01-01

    The U.S. Geological Survey (USGS) is studying coastal hazards and coastal change to improve our understanding of coastal ecosystems and to develop better capabilities of predicting future coastal change. One approach to understanding the dynamics of coastal systems is to monitor changes in barrier-island subenvironments through time. This involves examining morphological and topographic change at temporal scales ranging from millennia to years and spatial scales ranging from tens of kilometers to meters. Of particular interest are the processes that produce those changes and the determination of whether or not those processes are likely to persist into the future. In these analyses of hazards and change, both natural and anthropogenic influences are considered. Quantifying past magnitudes and rates of coastal change and knowing the principal factors that govern those changes are critical to predicting what changes are likely to occur under different scenarios, such as short-term impacts of extreme storms or long-term impacts of sea-level rise. Gulf Islands National Seashore was selected for detailed mapping of barrier-island morphology and topography because the islands offer a diversity of depositional subenvironments and the islands' areas and positions have changed substantially in historical time. The geomorphologic and subenvironmental maps emphasize the processes that formed the surficial features and also serve as a basis for documenting which subenvironments are relatively stable, such as the beach ridge complex, and those which are highly dynamic, such as the beach and active overwash zones. The primary mapping procedures used supervised functions within a Geographic Information System (GIS) that classified depositional subenvironments and features (map units) and delineated boundaries of the features (shapefiles). The GIS classified units on the basis of tonal patterns of a feature in contrast to adjacent features observed on georeferenced aerial

  13. Mapping process and age of Quaternary deposits on Santa Rosa Island, Channel Islands National Park, California

    Science.gov (United States)

    Schmidt, K. M.; Minor, S. A.; Bedford, D.

    2016-12-01

    Employing a geomorphic process-age classification scheme, we mapped the Quaternary surficial geology of Santa Rosa (SRI) within the Channel Islands National Park. This detailed (1:12,000 scale) map represents upland erosional transport processes and alluvial, fluvial, eolian, beach, marine terrace, mass wasting, and mixed depositional processes. Mapping was motivated through an agreement with the National Park Service and is intended to aid natural resource assessments, including post-grazing disturbance recovery and identification of mass wasting and tectonic hazards. We obtained numerous detailed geologic field observations, fossils for faunal identification as age control, and materials for numeric dating. This GPS-located field information provides ground truth for delineating map units and faults using GIS-based datasets- high-resolution (sub-meter) aerial imagery, LiDAR-based DEMs and derivative raster products. Mapped geologic units denote surface processes and Quaternary faults constrain deformation kinematics and rates, which inform models of landscape change. Significant findings include: 1) Flights of older Pleistocene (>120 ka) and possibly Pliocene marine terraces were identified beneath younger alluvial and eolian deposits at elevations as much as 275 m above modern sea level. Such elevated terraces suggest that SRI was a smaller, more submerged island in the late Neogene and (or) early Pleistocene prior to tectonic uplift. 2) Structural and geomorphic observations made along the potentially seismogenic SRI fault indicate a protracted slip history during the late Neogene and Quaternary involving early normal slip, later strike slip, and recent reverse slip. These changes in slip mode explain a marked contrast in island physiography across the fault. 3) Many of the steeper slopes are dramatically stripped of regolith, with exposed bedrock and deeply incised gullies, presumably due effects related to past grazing practices. 4) Surface water presence is

  14. Destination: Marshall Islands. Video Guide.

    Science.gov (United States)

    Legowski, Margaret

    This video guide was developed by the Peace Corps' Office of World Wise Schools. Activities that the guide describes are for use in a 3- to 5-day unit on one of the nations of Oceania, the Republic of the Marshall Islands. The activities are designed to provide students with opportunities to: (1) compare and contrast Marshallese and U.S. culture;…

  15. Mental health effects of the Three Mile Island nuclear reactor restart.

    Science.gov (United States)

    Dew, M A; Bromet, E J; Schulberg, H C; Dunn, L O; Parkinson, D K

    1987-08-01

    Controversy over potential mental health effects of the Three Mile Island Unit-1 restart led the authors to examine prospectively the pattern of psychiatric symptoms in a sample of Three Mile Island area mothers of young children. Symptom levels after restart were elevated over previous levels; a sizable subcohort of the sample reported relatively serious degrees of postrestart distress. History of diagnosable major depression and generalized anxiety following the Three Mile Island accident, plus symptoms and beliefs about personal risk prior to the restart, best predicted postrestart symptoms.

  16. Mental health effects of the Three Mile Island nuclear reactor restart

    International Nuclear Information System (INIS)

    Dew, M.A.; Bromet, E.J.; Schulberg, H.C.; Dunn, L.O.; Parkinson, D.K.

    1987-01-01

    Controversy over potential mental health effects of the Three Mile Island Unit-1 restart led the authors to examine prospectively the pattern of psychiatric symptoms in a sample of Three Mile Island area mothers of young children. Symptom levels after restart were elevated over previous levels; a sizable subcohort of the sample reported relatively serious degrees of postrestart distress. History of diagnosable major depression and generalized anxiety following the Three Mile Island accident, plus symptoms and beliefs about personal risk prior to the restart, best predicted postrestart symptoms

  17. Vitrification process for the volume reduction and stabilization of organic resins

    International Nuclear Information System (INIS)

    Buelt, J.L.

    1982-10-01

    Pacific Northwest Laboratory has completed a series of experimental tests sponsored by the US Department of Energy (DOE) to determine the feasibility of incinerating and vitrifying organic ion-exchange resins in a single-step process. The resins used in this study were identical to those used for decontaminating auxiliary building water at the Three Mile Island (TMI) Unit 2 reactor. The primarily organic resins were loaded with nonradioactive isotopes of cesium and strontium for processing in a pilot-scale, joule-heated glass melter modified to support resin combustion. The feasibility tests demonstrated an average process rate of 3.0 kg/h. Based on this rate, if 50 organic resin liners were vitrified in a six-month campaign, a melter 2.5 times the size of the pilot scale unit would be adequate. A maximum achievable volume reduction of 91% was demonstrated in these tests

  18. A human reliability analysis of the Three Mile power plant accident considering the THERP and ATHEANA methodologies

    International Nuclear Information System (INIS)

    Fonseca, Renato Alves da

    2004-03-01

    The main purpose of this work is the study of human reliability using the THERP (Technique for Human Error Prediction) and ATHEANA methods (A Technique for Human Error Analysis), and some tables and also, from case studies presented on the THERP Handbook to develop a qualitative and quantitative study of nuclear power plant accident. This accident occurred in the TMI (Three Mile Island Unit 2) power plant, PWR type plant, on March 28th, 1979. The accident analysis has revealed a series of incorrect actions, which resulted in the Unit 2 shut down and permanent loss of the reactor. This study also aims at enhancing the understanding of the THERP method and ATHEANA, and of its practical applications. In addition, it is possible to understand the influence of plant operational status on human failures and of these on equipment of a system, in this case, a nuclear power plant. (author)

  19. Three Mile Island accident. Local reactions; L'accident de Three Mile Island. Reactions locales

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1979-04-15

    Local reactions to the Three Mile Island are presented as well as newspaper articles covering this accident. In addition, this document presents a plan to set forth procedures and guidelines to be utilized by authorized emergency personnel in Middletown, Royalton, Londonderry Township, and Lower Swatara Township located in Pennsylvania, United States. The plan will provide for the orderly and efficient handling of area residents during time of serious incidents emanating from Three Mile Island facility. Emergency personnel in each community should be familiar with portions of the plan that pertain to the other near-by communities. The cooperation of all parties concerned will insure that a maximum effort is being made to help protect the public against injuries and v/ill in some cases keep any damages to communities to a minimum.

  20. Abu Dhabi’s New Urban Islands and Shorefront Development

    Directory of Open Access Journals (Sweden)

    El Amrousi Mohamed

    2017-01-01

    Full Text Available Abu Dhabi is in the process of urbanizing a group of Islands that surround its northern and eastern coastlines. Al-Lulu, Al-Saadiyat, Al- Maryah, Al-Reem and Yas Islands are all new urban enclaves that were desert islands and marshlands yet, have been developed over the past decade to urban islands that include epic and entertainment centres such as the Abu Dhabi Louvre, Guggenheim Museum, Ferrari World, NYU Abu Dhabi, the Paris Sorbonne Abu Dhabi in addition to iconic and exclusive waterfront residential units. These new islands re-brand the image of the main archipelago of Abu Dhabi that for decades retained a grid street pattern and pragmatic concrete blocks created in the late 1970s. The new urban islands transform Abu Dhabi’s image into a multinational modern Arab city seeking to become part of the global city network. Abu Dhabi’s new urban islands also act as breakwaters that protect the main archipelago’s coastline from erosion resulting from tidal change, because they are designed to include concrete and stone breakwater barriers. This paper represents a cross-disciplinary research between Civil Engineering and Architecture Departments in an attempt to explore the emerging infrastructure and urban expansion of Abu Dhabi from a multi-disciplinary perspective. We also highlight through simulating the effect of breakwaters on wave heights two scenarios for Al-Lulu Island the importance of these new barrier Islands on the urban expansion of Abu Dhabi.