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Sample records for waste remediation system

  1. Tank Waste Remediation System Guide

    International Nuclear Information System (INIS)

    Robershotte, M.A.; Dirks, L.L.; Seaver, D.A.; Bothers, A.J.; Madden, M.S.

    1995-06-01

    The scope, number and complexity of Tank Waste Remediation System (TWRS) decisions require an integrated, consistent, and logical approach to decision making. TWRS has adopted a seven-step decision process applicable to all decisions. Not all decisions, however, require the same degree of rigor/detail. The decision impact will dictate the appropriate required detail. In the entire process, values, both from the public as well as from the decision makers, play a key role. This document concludes with a general discussion of the implementation process that includes the roles of concerned parties

  2. Hanford Site Tank Waste Remediation System

    International Nuclear Information System (INIS)

    1993-05-01

    The US Department of Energy's (DOE) Hanford Site in southeastern Washington State has the most diverse and largest amount of highly radioactive waste of any site in the US. High-level radioactive waste has been stored in large underground tanks since 1944. A Tank Waste Remediation System Program has been established within the DOE to safely manage and immobilize these wastes in anticipation of permanent disposal in a geologic repository. The Hanford Site Tank Waste Remediation System Waste Management 1993 Symposium Papers and Viewgraphs covered the following topics: Hanford Site Tank Waste Remediation System Overview; Tank Waste Retrieval Issues and Options for their Resolution; Tank Waste Pretreatment - Issues, Alternatives and Strategies for Resolution; Low-Level Waste Disposal - Grout Issue and Alternative Waste Form Technology; A Strategy for Resolving High-Priority Hanford Site Radioactive Waste Storage Tank Safety Issues; Tank Waste Chemistry - A New Understanding of Waste Aging; Recent Results from Characterization of Ferrocyanide Wastes at the Hanford Site; Resolving the Safety Issue for Radioactive Waste Tanks with High Organic Content; Technology to Support Hanford Site Tank Waste Remediation System Objectives

  3. Tank waste remediation system program plan

    International Nuclear Information System (INIS)

    Powell, R.W.

    1998-01-01

    This program plan establishes the framework for conduct of the Tank Waste Remediation System (TWRS) Project. The plan focuses on the TWRS Retrieval and Disposal Mission and is specifically intended to support the DOE mid-1998 Readiness to Proceed with Privatized Waste Treatment evaluation for establishing firm contracts for waste immobilization

  4. Tank waste remediation system program plan

    Energy Technology Data Exchange (ETDEWEB)

    Powell, R.W.

    1998-01-05

    This program plan establishes the framework for conduct of the Tank Waste Remediation System (TWRS) Project. The plan focuses on the TWRS Retrieval and Disposal Mission and is specifically intended to support the DOE mid-1998 Readiness to Proceed with Privatized Waste Treatment evaluation for establishing firm contracts for waste immobilization.

  5. Tank waste remediation system mission analysis report

    International Nuclear Information System (INIS)

    Acree, C.D.

    1998-01-01

    The Tank Waste Remediation System Mission Analysis Report identifies the initial states of the system and the desired final states of the system. The Mission Analysis Report identifies target measures of success appropriate to program-level accomplishments. It also identifies program-level requirements and major system boundaries and interfaces

  6. Tank Waste Remediation System optimized processing strategy

    International Nuclear Information System (INIS)

    Slaathaug, E.J.; Boldt, A.L.; Boomer, K.D.; Galbraith, J.D.; Leach, C.E.; Waldo, T.L.

    1996-03-01

    This report provides an alternative strategy evolved from the current Hanford Site Tank Waste Remediation System (TWRS) programmatic baseline for accomplishing the treatment and disposal of the Hanford Site tank wastes. This optimized processing strategy performs the major elements of the TWRS Program, but modifies the deployment of selected treatment technologies to reduce the program cost. The present program for development of waste retrieval, pretreatment, and vitrification technologies continues, but the optimized processing strategy reuses a single facility to accomplish the separations/low-activity waste (LAW) vitrification and the high-level waste (HLW) vitrification processes sequentially, thereby eliminating the need for a separate HLW vitrification facility

  7. Tank waste remediation system mission analysis report

    International Nuclear Information System (INIS)

    Acree, C.D.

    1998-01-01

    This document describes and analyzes the technical requirements that the Tank Waste Remediation System (TWRS) must satisfy for the mission. This document further defines the technical requirements that TWRS must satisfy to supply feed to the private contractors' facilities and to store or dispose the immobilized waste following processing in these facilities. This document uses a two phased approach to the analysis to reflect the two-phased nature of the mission

  8. Tank waste remediation system configuration management plan

    International Nuclear Information System (INIS)

    Vann, J.M.

    1998-01-01

    The configuration management program for the Tank Waste Remediation System (TWRS) Project Mission supports management of the project baseline by providing the mechanisms to identify, document, and control the functional and physical characteristics of the products. This document is one of the tools used to develop and control the mission and work. It is an integrated approach for control of technical, cost, schedule, and administrative information necessary to manage the configurations for the TWRS Project Mission. Configuration management focuses on five principal activities: configuration management system management, configuration identification, configuration status accounting, change control, and configuration management assessments. TWRS Project personnel must execute work in a controlled fashion. Work must be performed by verbatim use of authorized and released technical information and documentation. Application of configuration management will be consistently applied across all TWRS Project activities and assessed accordingly. The Project Hanford Management Contract (PHMC) configuration management requirements are prescribed in HNF-MP-013, Configuration Management Plan (FDH 1997a). This TWRS Configuration Management Plan (CMP) implements those requirements and supersedes the Tank Waste Remediation System Configuration Management Program Plan described in Vann, 1996. HNF-SD-WM-CM-014, Tank Waste Remediation System Configuration Management Implementation Plan (Vann, 1997) will be revised to implement the requirements of this plan. This plan provides the responsibilities, actions and tools necessary to implement the requirements as defined in the above referenced documents

  9. Environmental remediation and waste management information systems

    Energy Technology Data Exchange (ETDEWEB)

    Harrington, M.W.; Harlan, C.P.

    1993-12-31

    The purpose of this paper is to document a few of the many environmental information systems that currently exist worldwide. The paper is not meant to be a comprehensive list; merely a discussion of a few of the more technical environmental database systems that are available. Regulatory databases such as US Environmental Protection Agency`s (EPA`s) RODS (Records of Decision System) database [EPA, 1993] and cost databases such as EPA`s CORA (Cost of Remedial Action) database [EPA, 1993] are not included in this paper. Section 2 describes several US Department of Energy (DOE) Environmental Restoration and Waste Management (EM) information systems and databases. Section 3 discusses several US EPA information systems on waste sites and technologies. Section 4 summarizes a few of the European Community environmental information systems, networks, and clearinghouses. And finally, Section 5 provides a brief overview of Geographical Information Systems. Section 6 contains the references, and the Appendices contain supporting information.

  10. Environmental remediation and waste management information systems

    International Nuclear Information System (INIS)

    Harrington, M.W.; Harlan, C.P.

    1993-01-01

    The purpose of this paper is to document a few of the many environmental information systems that currently exist worldwide. The paper is not meant to be a comprehensive list; merely a discussion of a few of the more technical environmental database systems that are available. Regulatory databases such as US Environmental Protection Agency's (EPA's) RODS (Records of Decision System) database [EPA, 1993] and cost databases such as EPA's CORA (Cost of Remedial Action) database [EPA, 1993] are not included in this paper. Section 2 describes several US Department of Energy (DOE) Environmental Restoration and Waste Management (EM) information systems and databases. Section 3 discusses several US EPA information systems on waste sites and technologies. Section 4 summarizes a few of the European Community environmental information systems, networks, and clearinghouses. And finally, Section 5 provides a brief overview of Geographical Information Systems. Section 6 contains the references, and the Appendices contain supporting information

  11. Tank waste remediation system: An update

    International Nuclear Information System (INIS)

    Alumkal, W.T.; Babad, H.; Dunford, G.L.; Honeyman, J.O.; Wodrich, D.D.

    1995-02-01

    The US Department of Energy's Hanford Site, located in southeastern Washington State, contains the largest amount and the most diverse collection of highly radioactive waste in the US. High-level radioactive waste has been stored at the Hanford Site in large, underground tanks since 1944. Approximately 217,000 M 3 (57 Mgal) of caustic liquids, slurries, saltcakes, and sludges have accumulated in 177 tanks. In addition, significant amounts of 90 Sr and 137 Cs were removed from the tank waste, converted to salts, doubly encapsulated in metal containers, and stored in water basins. The Tank Waste Remediation System Program was established by the US Department of Energy in 1991 to safely manage and immobilize these wastes in anticipation of permanent disposal of the high-level waste fraction in a geologic repository. Since 1991, significant progress has been made in resolving waste tank safety issues, upgrading Tank Farm facilities and operations, and developing a new strategy for retrieving, treating, and immobilizing the waste for disposal

  12. Tank waste remediation system dangerous waste training plan

    International Nuclear Information System (INIS)

    POHTO, R.E.

    1999-01-01

    This document outlines the dangerous waste training program developed and implemented for all Treatment, Storage, and Disposal (TSD) Units operated by Lockheed Martin Hanford Corporation (LMHC) Tank Waste Remediation System (TWRS) in the Hanford 200 East, 200 West and 600 Areas and the <90 Day Accumulation Area at 209E. Operating TSD Units operated by TWRS are: the Double-Shell Tank (DST) System (including 204-AR Waste Transfer Building), the 600 Area Purgewater Storage and the Effluent Treatment Facility. TSD Units undergoing closure are: the Single-Shell Tank (SST) System, 207-A South Retention Basin, and the 216-B-63 Trench

  13. Tank waste remediation system risk management plan

    International Nuclear Information System (INIS)

    Zimmerman, B.D.

    1998-01-01

    The purpose of the Tank Waste Remediation System (TWRS) Risk Management Plan is to describe a consistent approach to risk management such that TWRS Project risks are identified and managed to achieve TWRS Project success. The Risk Management Plan implements the requirements of the Tank Waste Remediation System Systems Engineering Management Plan in the area of risk management. Figure ES-1 shows the relationship of the TWRS Risk Management Plan to other major TWRS Project documents. As the figure indicates, the Risk Management Plan is a tool used to develop and control TWRS Project work. It provides guidance on how TWRS Project risks will be assessed, analyzed, and handled, and it specifies format and content for the risk management lists, which are a primary product of the risk management process. In many instances, the Risk Management Plan references the TWRS Risk Management Procedure, which provides more detailed discussion of many risk management activities. The TWRS Risk Management Plan describes an ongoing program within the TWRS Project. The Risk Management Plan also provides guidance in support of the TWRS Readiness To-Proceed (RTP) assessment package

  14. Tank waste remediation system engineering plan

    International Nuclear Information System (INIS)

    Rifaey, S.H.

    1998-01-01

    This Engineering Plan describes the engineering process and controls that will be in place to support the Technical Baseline definition and manage its evolution and implementation to the field operations. This plan provides the vision for the engineering required to support the retrieval and disposal mission through Phase 1 and 2, which includes integrated data management of the Technical Baseline. Further, this plan describes the approach for moving from the ''as is'' condition of engineering practice, systems, and facilities to the desired ''to be'' configuration. To make this transition, Tank Waste Remediation System (TWRS) Engineering will become a center of excellence for TWRS which,will perform engineering in the most effective manner to meet the mission. TWRS engineering will process deviations from sitewide systems if necessary to meet the mission most effectively

  15. Cooperative expert system reasoning for waste remediations

    International Nuclear Information System (INIS)

    Bohn, S.J.; Pennock, K.A.; Franklin, A.L.

    1991-12-01

    The United States Department of Energy (DOE) is facing a large task in completing Remedial Investigations and Feasibility Studies (RI/FS) for hazardous waste sites across the nation. One of the primary objectives of an RI/FS is the specification of viable sequences of technology treatment trains which can provide implementable site solutions. We present a methodology which integrates expert system technology within an object-oriented framework to create a cooperative reasoning system designed to provide a comprehensive list of these implementable solutions. The system accomplishes its goal of specifying technology trains by utilizing a ''team'' of expert system objects. The system distributes the problem solving among the individual expert objects, and then coordinates the combination of individual decisions into a joint solution. Each expert object possesses the knowledge of an expert in a particular technology. An expert object can examine the parameters and characteristics of the waste site, seek information and support from other expert objects, and then make decisions concerning its own applicability. This methodology has at least two primary benefits. First, the creation of multiple expert objects provides a more direct mapping from the actual process to a software system, making the system easier to build. Second, the distribution of the inferencing among a number of loosely connected expert objects allows for a more robust and maintainable final product

  16. Tank Waste Remediation System Projects Document Control Plan

    International Nuclear Information System (INIS)

    Slater, G.D.; Halverson, T.G.

    1994-01-01

    The purpose of this Tank Waste Remediation System Projects Document Control Plan is to provide requirements and responsibilities for document control for the Hanford Waste Vitrification Plant (HWVP) Project and the Initial Pretreatment Module (IPM) Project

  17. Tank waste remediation system retrieval and disposal mission infrastructure plan

    International Nuclear Information System (INIS)

    Root, R.W.

    1998-01-01

    This system plan presents the objectives, organization, and management and technical approaches for the Infrastructure Program. This Infrastructure Plan focuses on the Tank Waste Remediation System (TWRS) Project's Retrieval and Disposal Mission

  18. Tank waste remediation system characterization project quality policies. Revision 1

    International Nuclear Information System (INIS)

    Trimble, D.J.

    1995-01-01

    These Quality Policies (QPs) describe the Quality Management System of the Tank Waste Characterization Project (hereafter referred to as the Characterization Project), Tank Waste Remediation System (TWRS), Westinghouse Hanford Company (WHC). The Quality Policies and quality requirements described herein are binding on all Characterization Project organizations. To achieve quality, the Characterization Project management team shall implement this Characterization Project Quality Management System

  19. Tank waste remediation system retrieval and disposal mission waste feed delivery plan

    International Nuclear Information System (INIS)

    Potter, R.D.

    1998-01-01

    This document is a plan presenting the objectives, organization, and management and technical approaches for the Waste Feed Delivery (WFD) Program. This WFD Plan focuses on the Tank Waste Remediation System (TWRS) Project's Waste Retrieval and Disposal Mission

  20. TECHNICAL GUIDANCE DOCUMENT: CONSTRUCTION QUALITY MANAGEMENT FOR REMEDIAL ACTION AND REMEDIAL DESIGN WASTE CONTAINMENT SYSTEMS

    Science.gov (United States)

    This Technical Guidance Document is intended to augment the numerous construction quality control and construction quality assurance (CQC and CQA) documents that are available far materials associated with waste containment systems developed for Superfund site remediation. In ge...

  1. Tank Farm Contractor Waste Remediation System and Utilization Plan

    International Nuclear Information System (INIS)

    KIRKBRIDE, R.A.

    1999-01-01

    The Tank Waste Remediation System Operation and Utilization Plan updates the operating scenario and plans for the delivery of feed to BNFL Inc., retrieval of waste from single-shell tanks, and the overall process flowsheets for Phases I and II of the privatization of the Tank Waste Remediation System. The plans and flowsheets are updated with the most recent tank-by-tank inventory and sludge washing data. Sensitivity cases were run to evaluate the impact or benefits of proposed changes to the BNFL Inc. contract and to evaluate a risk-based SST retrieval strategy

  2. Decision and systems analysis for underground storage tank waste retrieval systems and tank waste remediation system

    International Nuclear Information System (INIS)

    Bitz, D.A.; Berry, D.L.; Jardine, L.J.

    1994-03-01

    Hanford's underground tanks (USTs) pose one of the most challenging hazardous and radioactive waste problems for the Department of Energy (DOE). Numerous schemes have been proposed for removing the waste from the USTs, but the technology options for doing this are largely unproven. To help assess the options, an Independent Review Group (IRG) was established to conduct a broad review of retrieval systems and the tank waste remediation system. The IRG consisted of the authors of this report

  3. Tank waste remediation system program plan

    International Nuclear Information System (INIS)

    Powell, R.W.

    1998-01-01

    This TWRS Program plan presents the planning requirements and schedules and management strategies and policies for accomplishing the TWRS Project mission. It defines the systems and practices used to establish consistency for business practices, engineering, physical configuration and facility documentation, and to maintain this consistency throughout the program life cycle, particularly as changes are made. Specifically, this plan defines the following: Mission needs and requirements (what must be done and when must it be done); Technical objectives/approach (how well must it be done); Organizational structure and philosophy (roles, responsibilities, and interfaces); and Operational methods (objectives and how work is to be conducted in both management and technical areas). The plan focuses on the TWRS Retrieval and Disposal Mission and supports the DOE mid-1998 Readiness to Proceed with Privatized Waste Treatment evaluation for establishing contracts with private contractors for the treatment (immobilization) of Hanford tank high-level radioactive waste

  4. Tank waste remediation system program plan

    Energy Technology Data Exchange (ETDEWEB)

    Powell, R.W.

    1998-01-09

    This TWRS Program plan presents the planning requirements and schedules and management strategies and policies for accomplishing the TWRS Project mission. It defines the systems and practices used to establish consistency for business practices, engineering, physical configuration and facility documentation, and to maintain this consistency throughout the program life cycle, particularly as changes are made. Specifically, this plan defines the following: Mission needs and requirements (what must be done and when must it be done); Technical objectives/approach (how well must it be done); Organizational structure and philosophy (roles, responsibilities, and interfaces); and Operational methods (objectives and how work is to be conducted in both management and technical areas). The plan focuses on the TWRS Retrieval and Disposal Mission and supports the DOE mid-1998 Readiness to Proceed with Privatized Waste Treatment evaluation for establishing contracts with private contractors for the treatment (immobilization) of Hanford tank high-level radioactive waste.

  5. Testing and development strategy for the tank waste remediation system

    International Nuclear Information System (INIS)

    Reddick, G.W.

    1994-12-01

    This document provides a strategy for performing radioactive (hot) and nonradioactive testing to support processing tank waste. It evaluates the need for hot pilot plant(s) to support pretreatment and other processing functions and presents a strategy for performing hot test work. A strategy also is provided for nonradioactive process and equipment testing. The testing strategy supports design, construction, startup, and operation of Tank Waste Remediation System (TWRS) facilities

  6. Testing and development strategy for the tank waste remediation system

    International Nuclear Information System (INIS)

    Reddick, G.W.

    1995-01-01

    This document provides a strategy for performing radioactive (hot) and nonradioactive testing to support processing tank waste. It evaluates the need for hot pilot plant(s) to support pretreatment and other processing functions and presents a strategy for performing hot test work. A strategy also is provided for nonradioactive process and equipment testing. The testing strategy supports design, construction, startup, and operation of Tank Waste Remediation System (TWRS) facilities

  7. Tank waste remediation system systems engineering management plan

    International Nuclear Information System (INIS)

    Peck, L.G.

    1998-01-01

    This Systems Engineering Management Plan (SEMP) describes the Tank Waste Remediation System (TWRS) implementation of the US Department of Energy (DOE) systems engineering policy provided in 97-IMSD-193. The SEMP defines the products, process, organization, and procedures used by the TWRS Project to implement the policy. The SEMP will be used as the basis for tailoring the systems engineering applications to the development of the physical systems and processes necessary to achieve the desired end states of the program. It is a living document that will be revised as necessary to reflect changes in systems engineering guidance as the program evolves. The US Department of Energy-Headquarters has issued program management guidance, DOE Order 430. 1, Life Cycle Asset Management, and associated Good Practice Guides that include substantial systems engineering guidance

  8. Tank waste remediation system risk management list

    International Nuclear Information System (INIS)

    Collard, L.B.

    1995-01-01

    The Tank Waste Remedation System (TWRS) Risk Management List and it's subset of critical risks, the Critical Risk Management List, provide a tool to senior RL and WHC management (Level-1 and -2) to manage programmatic risks that may significantly impact the TWRS program. The programmatic risks include cost, schedule, and performance risks. Performance risk includes technical risk, supportability risk (such as maintainability and availability), and external risk (i.e., beyond program control, for example, changes in regulations). The risk information includes a description, its impacts, as evaluation of the likelihood, consequences and risk value, possible mitigating actions, and responsible RL and WHC managers. The issues that typically form the basis for the risks are presented in a separate table and the affected functions are provided on the management lists

  9. Hanford site tank waste remediation system programmatic environmental review report

    International Nuclear Information System (INIS)

    Haass, C.C.

    1998-01-01

    The US Department of Energy (DOE) committed in the Tank Waste Remediation System (TWRS) Environmental Impact Statement (EIS) Record of Decision (ROD) to perform future National Environmental Policy Act (NEPA) analysis at key points in the Program. Each review will address the potential impacts that new information may have on the environmental impacts presented in the TWRS EIS and support an assessment of whether DOE's plans for remediating the tank waste are still pursuing the appropriate plan for remediation or whether adjustments to the program are needed. In response to this commitment, DOE prepared a Supplement Analysis (SA) to support the first of these reevaluations. Subsequent to the completion of the SA, the Phase IB negotiations process with private contractors resulted in several changes to the planned approach. These changes along with other new information regarding the TWRS Program have potential implications for Phase 1 and Phase 2 of tank waste retrieval and waste storage and/or disposal that may influence the environmental impacts of the Phased Implementation alternative. This report focuses on identifying those potential environmental impacts that may require NEPA analysis prior to authorization to begin facility construction and operations

  10. Tank waste remediation system nuclear criticality safety program management review

    International Nuclear Information System (INIS)

    BRADY RAAP, M.C.

    1999-01-01

    This document provides the results of an internal management review of the Tank Waste Remediation System (TWRS) criticality safety program, performed in advance of the DOE/RL assessment for closure of the TWRS Nuclear Criticality Safety Issue, March 1994. Resolution of the safety issue was identified as Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Milestone M-40-12, due September 1999

  11. Tank Waste Remediation System decisions and risk assessment

    International Nuclear Information System (INIS)

    Johnson, M.E.

    1994-09-01

    The Tank Waste Remediation System (TWRS) mission is to store, treat, and immobilize the highly radioactive Hanford Site tank wastes and encapsulated cesium and strontium materials in an environmentally sound, safe, and cost effective manner. Additionally, the TWRS conducts, as part of this mission, resolution of safety issues associated with the wastes within the 177 underground radioactive waste tanks. Systems engineering principles are being applied to determine the functions and establish requirements necessary for accomplishing the TWRS mission (DOE 1994 draft). This systematic evaluation of the TWRS program has identified key decisions that must be executed to establish mission scope, determine requirements, or select a technical solution for accomplishing identified functions and requirements. Key decisions identified through the systematic evaluation of the TWRS mission are presented in this document. Potential alternative solutions to each decision are discussed. After-discussion and evaluation of each decision with effected stakeholder groups, the US Department of Energy (DOE) will select a solution from the identified alternatives for implementation. In order to proceed with the development and execution of the tank waste remediation program, the DOE has adopted a planning basis for several of these decisions, until a formal basis is established. The planning bases adopted by the DOE is continuing to be discussed with stakeholder groups to establish consensus for proceeding with proposed actions. Technical and programmatic risks associated with the planning basis adopted by the DOE are discussed

  12. A systematic look at Tank Waste Remediation System privatization

    International Nuclear Information System (INIS)

    Holbrook, J.H.; Duffy, M.A.; Vieth, D.L.; Sohn, C.L.

    1996-01-01

    The mission of the Tank Waste Remediation System (TWRS) Program is to store, treat, immobilize, and dispose, or prepare for disposal, the Hanford radioactive tank waste in an environmentally sound, safe, and cost effective manner. Highly radioactive Hanford waste includes current and future tank waste plus the cesium and strontium capsules. In the TWRS program, as in other Department of Energy (DOE) clean-up activities, there is an increasing gap between the estimated funding required to enable DOE to meet all of its clean-up commitments and level of funding that is perceived to be available. Privatization is one contracting/management approach being explored by DOE as a means to achieve cost reductions and as a means to achieve a more outcome-oriented program. Privatization introduces the element of competition, a proven means of establishing true cost as well as achieving significant cost reduction

  13. Tank waste remediation system architecture tree

    International Nuclear Information System (INIS)

    PECK, L.G.

    1999-01-01

    The TWRS Architecture Tree presented in this document is a hierarchical breakdown to support the TWRS systems engineering analysis of the TWRS physical system, including facilities, hardware and software. The purpose for this systems engineering architecture tree is to describe and communicate the system's selected and existing architecture, to provide a common structure to improve the integration of work and resulting products, and to provide a framework as a basis for TWRS Specification Tree development

  14. Tank waste remediation system architecture tree; TOPICAL

    International Nuclear Information System (INIS)

    PECK, L.G.

    1999-01-01

    The TWRS Architecture Tree presented in this document is a hierarchical breakdown to support the TWRS systems engineering analysis of the TWRS physical system, including facilities, hardware and software. The purpose for this systems engineering architecture tree is to describe and communicate the system's selected and existing architecture, to provide a common structure to improve the integration of work and resulting products, and to provide a framework as a basis for TWRS Specification Tree development

  15. Tank waste remediation system environmental program plan

    Energy Technology Data Exchange (ETDEWEB)

    Borneman, L.E.

    1998-01-09

    This Environmental Program Plan has been developed in support of the Integrated Environmental, Safety and Health Management System and consistent with the goals of DOE/RL-96-50, Hanford Strategic Plan (RL 1996a), and the specifications and guidance for ANSI/ISO 14001-1996, Environmental Management Systems Specification with guidance for use (ANSI/ISO 1996).

  16. Tank waste remediation system environmental program plan

    International Nuclear Information System (INIS)

    Borneman, L.E.

    1998-01-01

    This Environmental Program Plan has been developed in support of the Integrated Environmental, Safety and Health Management System and consistent with the goals of DOE/RL-96-50, Hanford Strategic Plan (RL 1996a), and the specifications and guidance for ANSI/ISO 14001-1996, Environmental Management Systems Specification with guidance for use (ANSI/ISO 1996)

  17. The Hanford Site Tank Waste Remediation System: An update

    International Nuclear Information System (INIS)

    Alumkal, W.T.; Babad, H.; Harmon, H.D.; Wodrich, D.D.

    1994-01-01

    The U.S. Department of Energy's Hanford Site, located in southeastern Washington State, has the most diverse and largest amount of highly radioactive waste in the United States. High-level radioactive waste has been stored in large underground tanks since 1944. Approximately 230,000 m 3 (61 Mgal) of caustic liquids, slurries, saltcakes, and sludges have 137 Cs accumulated in 177 tanks. In addition, significant amounts of 90 Sr and were removed from the tank waste, converted to salts, doubly encapsulated in metal containers., and stored in water basins. A Tank Waste Remediation System Program was established by the U.S. Department of Energy in 1991 to safely manage and immobilize these wastes in anticipation of permanent disposal of the high-level waste fraction in a geologic repository. Since 1991, progress has been made resolving waste tank safety issues, upgrading Tank Farm facilities and operations, and developing a new strategy for retrieving, treating, and immobilizing the waste for disposal

  18. Waste remediation

    Science.gov (United States)

    Halas, Nancy J.; Nordlander, Peter; Neumann, Oara

    2015-12-29

    A system including a steam generation system and a chamber. The steam generation system includes a complex and the steam generation system is configured to receive water, concentrate electromagnetic (EM) radiation received from an EM radiation source, apply the EM radiation to the complex, where the complex absorbs the EM radiation to generate heat, and transform, using the heat generated by the complex, the water to steam. The chamber is configured to receive the steam and an object, wherein the object is of medical waste, medical equipment, fabric, and fecal matter.

  19. Tank waste remediation system integrated technology plan. Revision 2

    Energy Technology Data Exchange (ETDEWEB)

    Eaton, B.; Ignatov, A.; Johnson, S.; Mann, M.; Morasch, L.; Ortiz, S.; Novak, P. [eds.] [Pacific Northwest Lab., Richland, WA (United States)

    1995-02-28

    The Hanford Site, located in southeastern Washington State, is operated by the US Department of Energy (DOE) and its contractors. Starting in 1943, Hanford supported fabrication of reactor fuel elements, operation of production reactors, processing of irradiated fuel to separate and extract plutonium and uranium, and preparation of plutonium metal. Processes used to recover plutonium and uranium from irradiated fuel and to recover radionuclides from tank waste, plus miscellaneous sources resulted in the legacy of approximately 227,000 m{sup 3} (60 million gallons) of high-level radioactive waste, currently in storage. This waste is currently stored in 177 large underground storage tanks, 28 of which have two steel walls and are called double-shell tanks (DSTs) an 149 of which are called single-shell tanks (SSTs). Much of the high-heat-emitting nuclides (strontium-90 and cesium-137) has been extracted from the tank waste, converted to solid, and placed in capsules, most of which are stored onsite in water-filled basins. DOE established the Tank Waste Remediation System (TWRS) program in 1991. The TWRS program mission is to store, treat, immobilize and dispose, or prepare for disposal, the Hanford tank waste in an environmentally sound, safe, and cost-effective manner. Technology will need to be developed or improved to meet the TWRS program mission. The Integrated Technology Plan (ITP) is the high-level consensus plan that documents all TWRS technology activities for the life of the program.

  20. Tank waste remediation system integrated technology plan. Revision 2

    International Nuclear Information System (INIS)

    Eaton, B.; Ignatov, A.; Johnson, S.; Mann, M.; Morasch, L.; Ortiz, S.; Novak, P.

    1995-01-01

    The Hanford Site, located in southeastern Washington State, is operated by the US Department of Energy (DOE) and its contractors. Starting in 1943, Hanford supported fabrication of reactor fuel elements, operation of production reactors, processing of irradiated fuel to separate and extract plutonium and uranium, and preparation of plutonium metal. Processes used to recover plutonium and uranium from irradiated fuel and to recover radionuclides from tank waste, plus miscellaneous sources resulted in the legacy of approximately 227,000 m 3 (60 million gallons) of high-level radioactive waste, currently in storage. This waste is currently stored in 177 large underground storage tanks, 28 of which have two steel walls and are called double-shell tanks (DSTs) an 149 of which are called single-shell tanks (SSTs). Much of the high-heat-emitting nuclides (strontium-90 and cesium-137) has been extracted from the tank waste, converted to solid, and placed in capsules, most of which are stored onsite in water-filled basins. DOE established the Tank Waste Remediation System (TWRS) program in 1991. The TWRS program mission is to store, treat, immobilize and dispose, or prepare for disposal, the Hanford tank waste in an environmentally sound, safe, and cost-effective manner. Technology will need to be developed or improved to meet the TWRS program mission. The Integrated Technology Plan (ITP) is the high-level consensus plan that documents all TWRS technology activities for the life of the program

  1. Light Duty Utility Arm System applications for tank waste remediation

    International Nuclear Information System (INIS)

    Carteret, B.A.

    1994-10-01

    The Light Duty Utility Arm (LDUA) System is being developed by the US Department of Energy's (DOE's) Office of Technology Development (OTD, EM-50) to obtain information about the conditions and contents of the DOE's underground storage tanks. Many of these tanks are deteriorating and contain hazardous, radioactive waste generated over the past 50 years as a result of defense materials production at a member of DOE sites. Stabilization and remediation of these waste tanks is a high priority for the DOE's environmental restoration program. The LDUA System will provide the capability to obtain vital data needed to develop safe and cost-effective tank remediation plans, to respond to ongoing questions about tank integrity and leakage, and to quickly investigate tank events that raise safety concerns. In-tank demonstrations of the LDUA System are planned for three DOE sites in 1996 and 1997: Hanford, Idaho National Engineering Laboratory (INEL), and Oak Ridge National Laboratory (ORNL). This paper provides a general description of the system design and discusses a number of planned applications of this technology to support the DOE's environmental restoration program, as well as potential applications in other areas. Supporting papers by other authors provide additional in-depth technical information on specific areas of the system design

  2. Tank waste remediation system baseline tank waste inventory estimates for fiscal year 1995

    International Nuclear Information System (INIS)

    Shelton, L.W.

    1996-01-01

    A set of tank-by-tank waste inventories is derived from historical waste models, flowsheet records, and analytical data to support the Tank Waste Remediation System flowsheet and retrieval sequence studies. Enabling assumptions and methodologies used to develop the inventories are discussed. These provisional inventories conform to previously established baseline inventories and are meant to serve as an interim basis until standardized inventory estimates are made available

  3. Tank Waste Remediation System Tank Waste Analysis Plan. FY 1995

    International Nuclear Information System (INIS)

    Haller, C.S.; Dove, T.H.

    1994-01-01

    This documents lays the groundwork for preparing the implementing the TWRS tank waste analysis planning and reporting for Fiscal Year 1995. This Tank Waste Characterization Plan meets the requirements specified in the Hanford Federal Facility Agreement and Consent Order, better known as the Tri-Party Agreement

  4. Draft Environmental Impact Statement for the tank waste remediation system. Volume 4

    International Nuclear Information System (INIS)

    1996-04-01

    This appendix describes the current safety concerns associated with the tank waste and analyzes the potential accidents and associated potential health effects that could occur under the alternatives included in this Tank Waste Remediation System (TWRS) Environmental Impact Statement (EIS)

  5. Tank waste remediation system functions and requirements document

    International Nuclear Information System (INIS)

    Carpenter, K.E

    1996-01-01

    This is the Tank Waste Remediation System (TWRS) Functions and Requirements Document derived from the TWRS Technical Baseline. The document consists of several text sections that provide the purpose, scope, background information, and an explanation of how this document assists the application of Systems Engineering to the TWRS. The primary functions identified in the TWRS Functions and Requirements Document are identified in Figure 4.1 (Section 4.0) Currently, this document is part of the overall effort to develop the TWRS Functional Requirements Baseline, and contains the functions and requirements needed to properly define the top three TWRS function levels. TWRS Technical Baseline information (RDD-100 database) included in the appendices of the attached document contain the TWRS functions, requirements, and architecture necessary to define the TWRS Functional Requirements Baseline. Document organization and user directions are provided in the introductory text. This document will continue to be modified during the TWRS life-cycle

  6. Tank waste remediation system functions and requirements document

    Energy Technology Data Exchange (ETDEWEB)

    Carpenter, K.E

    1996-10-03

    This is the Tank Waste Remediation System (TWRS) Functions and Requirements Document derived from the TWRS Technical Baseline. The document consists of several text sections that provide the purpose, scope, background information, and an explanation of how this document assists the application of Systems Engineering to the TWRS. The primary functions identified in the TWRS Functions and Requirements Document are identified in Figure 4.1 (Section 4.0) Currently, this document is part of the overall effort to develop the TWRS Functional Requirements Baseline, and contains the functions and requirements needed to properly define the top three TWRS function levels. TWRS Technical Baseline information (RDD-100 database) included in the appendices of the attached document contain the TWRS functions, requirements, and architecture necessary to define the TWRS Functional Requirements Baseline. Document organization and user directions are provided in the introductory text. This document will continue to be modified during the TWRS life-cycle.

  7. Tank waste remediation system retrieval and disposal mission initial updated baseline summary

    International Nuclear Information System (INIS)

    Swita, W.R.

    1998-01-01

    This document provides a summary of the proposed Tank Waste Remediation System Retrieval and Disposal Mission Initial Updated Baseline (scope, schedule, and cost) developed to demonstrate the Tank Waste Remediation System contractor's Readiness-to-Proceed in support of the Phase 1B mission

  8. Tank waste remediation system tank waste retrieval risk management plan

    International Nuclear Information System (INIS)

    Klimper, S.C.

    1997-01-01

    This Risk Management Plan defines the approach to be taken to manage programmatic risks in the TWRS Tank Waste Retrieval program. It provides specific instructions applicable to TWR, and is used to supplement the guidance given by the TWRS Risk Management procedure

  9. Tank waste remediation system configuration management implementation plan

    International Nuclear Information System (INIS)

    Vann, J.M.

    1998-01-01

    The Tank Waste Remediation System (TWRS) Configuration Management Implementation Plan describes the actions that will be taken by Project Hanford Management Contract Team to implement the TWRS Configuration Management program defined in HNF 1900, TWRS Configuration Management Plan. Over the next 25 years, the TWRS Project will transition from a safe storage mission to an aggressive retrieval, storage, and disposal mission in which substantial Engineering, Construction, and Operations activities must be performed. This mission, as defined, will require a consolidated configuration management approach to engineering, design, construction, as-building, and operating in accordance with the technical baselines that emerge from the life cycles. This Configuration Management Implementation Plan addresses the actions that will be taken to strengthen the TWRS Configuration Management program

  10. Tank waste remediation system programmatic risk management plan

    International Nuclear Information System (INIS)

    Seaver, D.A.

    1995-01-01

    This risk management plan defines the approach to be taken to managing risks in the Tank Waste Remediation System (TWRS) program. It defines the actions to be taken at the overall program level, and the risk management requirements for lower-level projects and other activities. The primary focus of this plan is on ''programmatic'' risks, i.e., risks with respect to the cost, schedule, and technical performance of the program. The plan defines an approach providing managers with the flexibility to manage risks according to their specific needs, yet creates. The consistency needed for effectiveness across the program. The basic risk management approach uses a risk management list for the program, each project, and additional lower-level activities. The risk management list will be regularly reviewed and updated by appropriate level of management. Each list defines key risks, their likelihood and consequences, risk management actions to be taken, responsible individuals, and other management information

  11. Tank waste remediation system multi-year work plan

    International Nuclear Information System (INIS)

    1994-09-01

    The Tank Waste Remediation System (TWRS) Multi-Year Work Plan (MYWP) documents the detailed total Program baseline and was constructed to guide Program execution. The TWRS MYWP is one of two elements that comprise the TWRS Program Management Plan. The TWRS MYWP fulfills the Hanford Site Management System requirement for a Multi-Year Program Plan and a Fiscal-Year Work Plan. The MYWP addresses program vision, mission, objectives, strategy, functions and requirements, risks, decisions, assumptions, constraints, structure, logic, schedule, resource requirements, and waste generation and disposition. Sections 1 through 6, Section 8, and the appendixes provide program-wide information. Section 7 includes a subsection for each of the nine program elements that comprise the TWRS Program. The foundation of any program baseline is base planning data (e.g., defendable product definition, logic, schedules, cost estimates, and bases of estimates). The TWRS Program continues to improve base data. As data improve, so will program element planning, integration between program elements, integration outside of the TWRS Program, and the overall quality of the TWRS MYWP. The MYWP establishes the TWRS baseline objectives to store, treat, and immobilize highly radioactive Hanford waste in an environmentally sound, safe, and cost-effective manner. The TWRS Program will complete the baseline mission in 2040 and will incur costs totalling approximately 40 billion dollars. The summary strategy is to meet the above objectives by using a robust systems engineering effort, placing the highest possible priority on safety and environmental protection; encouraging open-quotes out sourcingclose quotes of the work to the extent practical; and managing significant but limited resources to move toward final disposition of tank wastes, while openly communicating with all interested stakeholders

  12. Tank waste remediation system multi-year work plan

    Energy Technology Data Exchange (ETDEWEB)

    1994-09-01

    The Tank Waste Remediation System (TWRS) Multi-Year Work Plan (MYWP) documents the detailed total Program baseline and was constructed to guide Program execution. The TWRS MYWP is one of two elements that comprise the TWRS Program Management Plan. The TWRS MYWP fulfills the Hanford Site Management System requirement for a Multi-Year Program Plan and a Fiscal-Year Work Plan. The MYWP addresses program vision, mission, objectives, strategy, functions and requirements, risks, decisions, assumptions, constraints, structure, logic, schedule, resource requirements, and waste generation and disposition. Sections 1 through 6, Section 8, and the appendixes provide program-wide information. Section 7 includes a subsection for each of the nine program elements that comprise the TWRS Program. The foundation of any program baseline is base planning data (e.g., defendable product definition, logic, schedules, cost estimates, and bases of estimates). The TWRS Program continues to improve base data. As data improve, so will program element planning, integration between program elements, integration outside of the TWRS Program, and the overall quality of the TWRS MYWP. The MYWP establishes the TWRS baseline objectives to store, treat, and immobilize highly radioactive Hanford waste in an environmentally sound, safe, and cost-effective manner. The TWRS Program will complete the baseline mission in 2040 and will incur costs totalling approximately 40 billion dollars. The summary strategy is to meet the above objectives by using a robust systems engineering effort, placing the highest possible priority on safety and environmental protection; encouraging {open_quotes}out sourcing{close_quotes} of the work to the extent practical; and managing significant but limited resources to move toward final disposition of tank wastes, while openly communicating with all interested stakeholders.

  13. Tank waste remediation system process engineering instruction manual

    International Nuclear Information System (INIS)

    ADAMS, M.R.

    1998-01-01

    The purpose of the Tank Waste Remediation System (TWRS) Process Engineering Instruction Manual is to provide guidance and direction to TWRS Process Engineering staff regarding conduct of business. The objective is to establish a disciplined and consistent approach to business such that the work processes within TWRS Process Engineering are safe, high quality, disciplined, efficient, and consistent with Lockheed Martin Hanford Corporation Policies and Procedures. The sections within this manual are of two types: for compliance and for guidance. For compliance sections are intended to be followed per-the-letter until such time as they are formally changed per Section 2.0 of this manual. For guidance sections are intended to be used by the staff for guidance in the conduct of work where technical judgment and discernment are required. The guidance sections shall also be changed per Section 2.0 of this manual. The required header for each manual section is illustrated in Section 2.0, Manual Change Control procedure. It is intended that this manual be used as a training and indoctrination resource for employees of the TWRS Process Engineering organization. The manual shall be required reading for all TWRS Process Engineering staff, matrixed, and subcontracted employees

  14. Tank waste remediation system privatization infrastructure program requirements and document management process guide

    International Nuclear Information System (INIS)

    ROOT, R.W.

    1999-01-01

    This guide provides the Tank Waste Remediation System Privatization Infrastructure Program management with processes and requirements to appropriately control information and documents in accordance with the Tank Waste Remediation System Configuration Management Plan (Vann 1998b). This includes documents and information created by the program, as well as non-program generated materials submitted to the project. It provides appropriate approval/control, distribution and filing systems

  15. Flammable gas deflagration consequence calculations for the tank waste remediation system basis for interim operation

    Energy Technology Data Exchange (ETDEWEB)

    Van Vleet, R.J., Westinghouse Hanford

    1996-08-13

    This paper calculates the radiological dose consequences and the toxic exposures for deflagration accidents at various Tank Waste Remediation System facilities. These will be used in support of the Tank Waste Remediation System Basis for Interim Operation.The attached SD documents the originator`s analysis only. It shall not be used as the final or sole document for effecting changes to an authorization basis or safety basis for a facility or activity.

  16. Facility design philosophy: Tank Waste Remediation System Process support and infrastructure definition

    International Nuclear Information System (INIS)

    Leach, C.E.; Galbraith, J.D.; Grant, P.R.; Francuz, D.J.; Schroeder, P.J.

    1995-11-01

    This report documents the current facility design philosophy for the Tank Waste Remediation System (TWRS) process support and infrastructure definition. The Tank Waste Remediation System Facility Configuration Study (FCS) initially documented the identification and definition of support functions and infrastructure essential to the TWRS processing mission. Since the issuance of the FCS, the Westinghouse Hanford Company (WHC) has proceeded to develop information and requirements essential for the technical definition of the TWRS treatment processing programs

  17. Tank Waste Remediation System, Hanford Site, Richland, Washington. Final Environmental Impact Statement. Volume IV

    International Nuclear Information System (INIS)

    1996-08-01

    This document, Volume 4, describes the current safety concerns associated with the tank waste and analyzes the potential accidents and associated potential health effects that could occur under the alternatives included in this Tank Waste Remediation System (TWRS) Final Environmental Impact Statement (EIS) for the Hanford Site, Richland, Washington

  18. Tank waste remediation system (TWRS) privatization contractor samples waste envelope D material 241-C-106

    Energy Technology Data Exchange (ETDEWEB)

    Esch, R.A.

    1997-04-14

    This report represents the Final Analytical Report on Tank Waste Remediation System (TWRS) Privatization Contractor Samples for Waste Envelope D. All work was conducted in accordance with ''Addendum 1 of the Letter of Instruction (LOI) for TWRS Privatization Contractor Samples Addressing Waste Envelope D Materials - Revision 0, Revision 1, and Revision 2.'' (Jones 1996, Wiemers 1996a, Wiemers 1996b) Tank 241-C-1 06 (C-106) was selected by TWRS Privatization for the Part 1A Envelope D high-level waste demonstration. Twenty bottles of Tank C-106 material were collected by Westinghouse Hanford Company using a grab sampling technique and transferred to the 325 building for processing by the Pacific Northwest National Laboratory (PNNL). At the 325 building, the contents of the twenty bottles were combined into a single Initial Composite Material. This composite was subsampled for the laboratory-scale screening test and characterization testing, and the remainder was transferred to the 324 building for bench-scale preparation of the Privatization Contractor samples.

  19. Tank waste remediation system optimized processing strategy with an altered treatment scheme

    International Nuclear Information System (INIS)

    Slaathaug, E.J.

    1996-03-01

    This report provides an alternative strategy evolved from the current Hanford Site Tank Waste Remediation System (TWRS) programmatic baseline for accomplishing the treatment and disposal of the Hanford Site tank wastes. This optimized processing strategy with an altered treatment scheme performs the major elements of the TWRS Program, but modifies the deployment of selected treatment technologies to reduce the program cost. The present program for development of waste retrieval, pretreatment, and vitrification technologies continues, but the optimized processing strategy reuses a single facility to accomplish the separations/low-activity waste (LAW) vitrification and the high-level waste (HLW) vitrification processes sequentially, thereby eliminating the need for a separate HLW vitrification facility

  20. Tank Waste Remediation System Characterization Project Programmatic Risk Management Plan

    International Nuclear Information System (INIS)

    Baide, D.G.; Webster, T.L.

    1995-12-01

    The TWRS Characterization Project has developed a process and plan in order to identify, manage and control the risks associated with tank waste characterization activities. The result of implementing this process is a defined list of programmatic risks (i.e. a risk management list) that are used by the Project as management tool. This concept of risk management process is a commonly used systems engineering approach which is being applied to all TWRS program and project elements. The Characterization Project risk management plan and list are subset of the overall TWRS risk management plan and list

  1. Tank waste remediation system nuclear criticality safety inspection and assessment plan

    International Nuclear Information System (INIS)

    VAIL, T.S.

    1999-01-01

    This plan provides a management approved procedure for inspections and assessments of sufficient depth to validate that the Tank Waste Remediation System (TWRS) facility complies with the requirements of the Project Hanford criticality safety program, NHF-PRO-334, ''Criticality Safety General, Requirements''

  2. Object reasoning for waste remediation

    International Nuclear Information System (INIS)

    Pennock, K.A.; Bohn, S.J.; Franklin, A.L.

    1991-08-01

    A large number of contaminated waste sites across the United States await size remediation efforts. These sites can be physically complex, composed of multiple, possibly interacting, contaminants distributed throughout one or more media. The Remedial Action Assessment System (RAAS) is being designed and developed to support decisions concerning the selection of remediation alternatives. The goal of this system is to broaden the consideration of remediation alternatives, while reducing the time and cost of making these considerations. The Remedial Action Assessment System is a hybrid system, designed and constructed using object-oriented, knowledge- based systems, and structured programming techniques. RAAS uses a combination of quantitative and qualitative reasoning to consider and suggest remediation alternatives. The reasoning process that drives this application is centered around an object-oriented organization of remediation technology information. This paper describes the information structure and organization used to support this reasoning process. In addition, the paper describes the level of detail of the technology related information used in RAAS, discusses required assumptions and procedural implications of these assumptions, and provides rationale for structuring RAAS in this manner. 3 refs., 3 figs

  3. Tank waste remediation system retrieval authorization basis amendment task plan

    International Nuclear Information System (INIS)

    Goetz, T.G.

    1998-01-01

    This task plan is a documented agreement between Nuclear Safety and Licensing and the Process Development group within the Waste Feed Delivery organization. The purpose of this task plan is to identify the scope of work, tasks and deliverables, responsibilities, manpower, and schedules associated with an authorization basis amendment as a result of the Waste Feed Waste Delivery Program, Project W-211, and Project W-TBD

  4. Tank Waste Remediation System, Hanford Site, Richland, Washington. Final Environmental Impact Statement. Volume II

    International Nuclear Information System (INIS)

    1996-08-01

    This document, Volume 2, provides the inventory of waste addressed in this Final Environmental Impact Statement (EIS) for the Tank Waste Remediation System, Hanford Site, Richland, Washington. The inventories consist of waste from the following four groups: (1) Tank waste; (2) Cesium (Cs) and Strontium (Sr) capsules; (3) Inactive miscellaneous underground storage tanks (MUSTs); and (4) Anticipated future tank waste additions. The major component by volume of the overall waste is the tank waste inventory (including future tank waste additions). This component accounts for more than 99 percent of the total waste volume and approximately 70 percent of the radiological activity of the four waste groups identified previously. Tank waste data are available on a tank-by-tank basis, but the accuracy of these data is suspect because they primarily are based on historical records of transfers between tanks rather than statistically based sampling and analyses programs. However, while the inventory of any specific tank may be suspect, the overall inventory for all of the tanks combined is considered more accurate. The tank waste inventory data are provided as the estimated overall chemical masses and radioactivity levels for the single-shell tanks (SSTs) and double-shell tanks (DSTs). The tank waste inventory data are broken down into tank groupings or source areas that were developed for analyzing groundwater impacts

  5. Tank Waste Remediation System, Hanford Site, Richland, Washington. Final Environmental Impact Statement. Volume I

    International Nuclear Information System (INIS)

    1996-08-01

    This document, Volume 1 of the Final Environmental Impact Statement, analyzes the potential environmental consequences related to the Hanford Site Tank Waste Remediation System (TWRS) alternatives for management and disposal of radioactive, hazardous, and mixed waste, and the management and disposal of approximately 1,930 cesium and strontium capsules located at the Hanford Site. This waste is currently or projected to be stored in 177 underground storage tanks and approximately 60 miscellaneous underground storage tanks. This document analyzes the following alternatives for remediating the tank waste: No Action, Long-Term Management, In Situ Fill and Cap, In Situ Vitrification, Ex Situ Intermediate Separations, Ex Situ No Separations, Ex Situ Extensive Separations, Ex Situ/In Situ Combination 1, and Ex Situ/In Situ Combination 2. This document also addresses a Phased Implementation alternative (the DOE and Ecology preferred alternative for remediation of tank waste). Alternatives analyzed for the cesium and strontium capsules include: No Action, Onsite Disposal, Overpack and Ship, and Vitrify with Tank Waste. The DOE and Ecology preferred alternative for the cesium and strontium capsules is the No Action alternative

  6. Tank Waste Remediation System, Hanford Site, Richland, Washington. Final environmental impact statement. Summary

    International Nuclear Information System (INIS)

    1996-08-01

    This document analyzes the potential environmental consequences related to the Hanford Site Tank Waste Remediation System (TWRS) alternatives for management and disposal of radioactive, hazardous, and mixed waste, and the management and disposal of approximately 1,930 cesium and strontium capsules located at the Hanford Site. This waste is currently or projected to be stored in 177 underground storage tanks and approximately 60 miscellaneous underground storage tanks. This document analyzes the following alternatives for remediating the tank waste: No Action, Long-Term Management, In Situ Fill and Cap, In Situ Vitrification, Ex Situ Intermediate Separations, Ex Situ No Separations, Ex Situ Extensive Separations, Ex Situ/In Situ Combination 1, and Ex Situ/In Situ Combination 2. This document also addresses a Phased Implementation alternative (the DOE and Ecology preferred alternative for remediation of tank waste). Alternatives analyzed for the cesium and strontium capsules include: No Action, Onsite Disposal, Overpack and Ship, and Vitrify with Tank Waste. The DOE and Ecology preferred alternative for the cesium and strontium capsules is the No Action alternative

  7. Draft Environmental Impact Statement for the tank waste remediation system. Volume 1

    International Nuclear Information System (INIS)

    1996-04-01

    This document analyzes the potential environmental consequences related to the Hanford Site Tank Waste Remediation System (TWRS) alternatives for management and disposal of radioactive, hazardous, and mixed waste. This waste is currently or projected to be stored in 177 underground storage tanks and approximately 60 miscellaneous underground storage tanks, and the management and disposal of approximately 1,930 cesium and strontium capsules located at the Hanford Site. This document analyzes the following alternatives for remediating the tank waste: No Action, Long-Term Management, In Situ Fill and Cap, In Situ Vitrification, Ex Situ Intermediate Separations, Ex Situ No Separations, Ex Situ Extensive Separations, and Ex Situ/In Situ Combination. This document also addresses a Phased Implementation alternative (the DOE and Ecology preferred alternative for remediation of tank waste). Alternatives analyzed for the cesium and strontium capsules include: No Action, Onsite Disposal, Overpack and Ship, and Vitrify with Tank Waste. At this time, DOE and Ecology do not have a preferred alternative for the cesium and strontium capsules

  8. Tank Waste Remediation System retrieval and disposal mission technical baseline summary description

    International Nuclear Information System (INIS)

    McLaughlin, T.J.

    1998-01-01

    This document is prepared in order to support the US Department of Energy's evaluation of readiness-to-proceed for the Waste Retrieval and Disposal Mission at the Hanford Site. The Waste Retrieval and Disposal Mission is one of three primary missions under the Tank Waste Remediation System (TWRS) Project. The other two include programs to characterize tank waste and to provide for safe storage of the waste while it awaits treatment and disposal. The Waste Retrieval and Disposal Mission includes the programs necessary to support tank waste retrieval, wastefeed, delivery, storage and disposal of immobilized waste, and closure of tank farms. This mission will enable the tank farms to be closed and turned over for final remediation. The Technical Baseline is defined as the set of science and engineering, equipment, facilities, materials, qualified staff, and enabling documentation needed to start up and complete the mission objectives. The primary purposes of this document are (1) to identify the important technical information and factors that should be used by contributors to the mission and (2) to serve as a basis for configuration management of the technical information and factors

  9. Tank waste remediation system technical baseline summary description

    International Nuclear Information System (INIS)

    Raymond, R.E.

    1998-01-01

    This document is one of the tools used to develop and control the mission work as depicted in the included figure. This Technical Baseline Summary Description document is the top-level tool for management of the Technical Baseline for waste storage operations

  10. Technologies to remediate hazardous waste sites

    International Nuclear Information System (INIS)

    Falco, J.W.

    1990-03-01

    Technologies to remediate hazardous wastes must be matched with the properties of the hazardous materials to be treated, the environment in which the wastes are imbedded, and the desired extent of remediation. Many promising technologies are being developed, including biological treatment, immobilization techniques, and in situ methods. Many of these new technologies are being applied to remediate sites. The management and disposal of hazardous wastes is changing because of federal and state legislation as well as public concern. Future waste management systems will emphasize the substitution of alternatives for the use of hazardous materials and process waste recycling. Onsite treatment will also become more frequently adopted. 5 refs., 7 figs

  11. Tank waste remediation system vadose zone program plan

    International Nuclear Information System (INIS)

    Fredenburg, E.A.

    1998-01-01

    The objective of the vadose zone characterization under this program is to develop a better conceptual geohydrologic model of identified tank farms which will be characterized so that threats to human health and the environment from past leaks and spills, intentional liquid discharges, potential future leaks during retrieval, and from residual contaminants that may remain in tank farms at closure can be explicitly addressed in decision processes. This model will include geologic, hydrologic, and hydrochemical parameters as defined by the requirements of each of the TWRS programs identified here. The intent of this TWRS Vadose Zone Program Plan is to provide justification and an implementation plan for the following activities: Develop a sufficient understanding of subsurface conditions and transport processes to support decisions on management, cleanup, and containment of past leaks, spills, and intentional liquid discharges; Develop a sufficient understanding of transport processes to support decisions on controlling potential retrieval leaks; Develop a sufficient understanding of transport processes to support decisions on tank farm closure, including allowable residual waste that may remain at closure; and Provide new information on geotechnical properties in the 200 Area to supplement data used for design and performance assessment for immobilized low-activity waste disposal facilities

  12. Tank waste remediation system vadose zone program plan

    Energy Technology Data Exchange (ETDEWEB)

    Fredenburg, E.A.

    1998-07-27

    The objective of the vadose zone characterization under this program is to develop a better conceptual geohydrologic model of identified tank farms which will be characterized so that threats to human health and the environment from past leaks and spills, intentional liquid discharges, potential future leaks during retrieval, and from residual contaminants that may remain in tank farms at closure can be explicitly addressed in decision processes. This model will include geologic, hydrologic, and hydrochemical parameters as defined by the requirements of each of the TWRS programs identified here. The intent of this TWRS Vadose Zone Program Plan is to provide justification and an implementation plan for the following activities: Develop a sufficient understanding of subsurface conditions and transport processes to support decisions on management, cleanup, and containment of past leaks, spills, and intentional liquid discharges; Develop a sufficient understanding of transport processes to support decisions on controlling potential retrieval leaks; Develop a sufficient understanding of transport processes to support decisions on tank farm closure, including allowable residual waste that may remain at closure; and Provide new information on geotechnical properties in the 200 Area to supplement data used for design and performance assessment for immobilized low-activity waste disposal facilities.

  13. Tank waste remediation system high-level waste vitrification system development and testing requirements

    International Nuclear Information System (INIS)

    Calmus, R.B.

    1995-01-01

    This document provides the fiscal year (FY) 1995 recommended high-level waste melter system development and testing (D and T) requirements. The first phase of melter system testing (FY 1995) will focus on the feasibility of high-temperature operation of recommended high-level waste melter systems. These test requirements will be used to establish the basis for defining detailed testing work scope, cost, and schedules. This document includes a brief summary of the recommended technologies and technical issues associated with each technology. In addition, this document presents the key D and T activities and engineering evaluations to be performed for a particular technology or general melter system support feature. The strategy for testing in Phase 1 (FY 1995) is to pursue testing of the recommended high-temperature technologies, namely the high-temperature, ceramic-lined, joule-heated melter, referred to as the HTCM, and the high-frequency, cold-wall, induction-heated melter, referred to as the cold-crucible melter (CCM). This document provides a detailed description of the FY 1995 D and T needs and requirements relative to each of the high-temperature technologies

  14. Tank waste remediation system characterization project quality policies

    International Nuclear Information System (INIS)

    Board, D.C.

    1997-01-01

    This quality plan describes the system used by Characterization Project management to achieve quality. This plan is comprised of eleven quality policies which, when taken together, form a management system deployed to achieve quality. This quality management system is based on the customer's quality requirements known as the 'RULE', 10 CFR 830.120, Quality Assurance

  15. Tank Waste Remediation System fiscal year 1996 multi-year program plan WBS 1.1. Revision 1, Appendix A

    International Nuclear Information System (INIS)

    1995-09-01

    This document is a compilation of data relating to the Tank Waste Remediation System Multi-Year Program. Topics discussed include: management systems; waste volume, transfer and evaporation management; transition of 200 East and West areas; ferricyanide, volatile organic vapor, and flammable gas management; waste characterization; retrieval from SSTs and DSTs; heat management; interim storage; low-level and high-level radioactive waste management; and tank farm closure

  16. Electrodialytic remediation of solid waste

    DEFF Research Database (Denmark)

    Hansen, Henrik K.; Ottosen, Lisbeth M.; Karlsmose, Bodil

    1996-01-01

    Electrodialytic remediation of heavy metal polluted solid waste is a method that combines the technique of electrodialysis with the electromigration of ions in the solid waste. Results of laboratory scale remediation experiments of soil are presented and considerations are given on how to secure...

  17. Final report of the systems engineering technical advisory board for the Tank Waste Remediation Program

    Energy Technology Data Exchange (ETDEWEB)

    Baranowski, F.P.; Goodlett, C.B.; Beard, S.J.; Duckworth, J.P.; Schneider, A.; Zahn, L.L.

    1993-03-01

    The Tank Waste Remediation System (TWRS) is one segment of the environmental restoration program at the Hanford site. The scope is to retrieve the contents of both the single shell and double shell tanks and process the wastes into forms acceptable for long term storage and/or permanent disposal. The quantity of radioactive waste in tanks is significantly larger and substantially more complex in composition than the radioactive waste stored in tanks at other DOE sites. The waste is stored in 149 single shell tanks and 28 double shell tanks. The waste was produced over a period from the mid 1940s to the present. The single shell tanks have exceeded their design life and are experiencing failures. The oldest of the double shell tanks are approaching their design life. Spar double shell tank waste volume is limited. The priorities in the Board`s view are to manage safely the waste tank farms, accelerate emptying of waste tanks, provide spare tank capacity and assure a high degree of confidence in performance of the TWRS integrated program. At its present design capacity, the glass vitrification plant (HWVP) will require a period of about 15 years to empty the double shell tanks; the addition of the waste in single shell tanks adds another 100 years. There is an urgent need to initiate now a well focused and centralized development and engineering program on both larger glass melters and advanced separations processes that reduce radioactive constituents in the low-level waste (LLW). The Board presents its conclusions and has other suggestions for the management plan. The Board reviews planning schedules for accelerating the TWRS program.

  18. Final report of the systems engineering technical advisory board for the Tank Waste Remediation Program

    International Nuclear Information System (INIS)

    Baranowski, F.P.; Goodlett, C.B.; Beard, S.J.; Duckworth, J.P.; Schneider, A.; Zahn, L.L.

    1993-03-01

    The Tank Waste Remediation System (TWRS) is one segment of the environmental restoration program at the Hanford site. The scope is to retrieve the contents of both the single shell and double shell tanks and process the wastes into forms acceptable for long term storage and/or permanent disposal. The quantity of radioactive waste in tanks is significantly larger and substantially more complex in composition than the radioactive waste stored in tanks at other DOE sites. The waste is stored in 149 single shell tanks and 28 double shell tanks. The waste was produced over a period from the mid 1940s to the present. The single shell tanks have exceeded their design life and are experiencing failures. The oldest of the double shell tanks are approaching their design life. Spar double shell tank waste volume is limited. The priorities in the Board's view are to manage safely the waste tank farms, accelerate emptying of waste tanks, provide spare tank capacity and assure a high degree of confidence in performance of the TWRS integrated program. At its present design capacity, the glass vitrification plant (HWVP) will require a period of about 15 years to empty the double shell tanks; the addition of the waste in single shell tanks adds another 100 years. There is an urgent need to initiate now a well focused and centralized development and engineering program on both larger glass melters and advanced separations processes that reduce radioactive constituents in the low-level waste (LLW). The Board presents its conclusions and has other suggestions for the management plan. The Board reviews planning schedules for accelerating the TWRS program

  19. Tank Waste Remediation System Inactive Miscellaneous Underground Storage Tanks Program Plan

    International Nuclear Information System (INIS)

    Gustavson, R.D.

    1995-12-01

    The Program Management Plan (PMP) describes the approach that will be used to manage the Tank Waste Remediation System (TWRS) Inactive Miscellaneous Underground Storage Tank (IMUST) Program. The plan describes management, technical, and administrative control systems that will be used to plan and control the IMUSTs Program performance. The technical data to determine the IMUSTs status for inclusion in the Single Shell Tank Farm Controlled Clean and Stable (CCS) Program. The second is to identify and implement surveillance, characterization, stabilization, and modifications to support CCS prior to final closure

  20. Management assessment of tank waste remediation system contractor readiness to proceed with phase 1B privatization

    International Nuclear Information System (INIS)

    Honeyman, J.O.

    1998-01-01

    This Management Assessment of Tank Waste Remediation System (TWRS) Contractor Readiness to Proceed With Phase 1B Privatization documents the processes used to determine readiness to proceed with tank waste treatment technologies from private industry, now known as TWRS privatization. An overall systems approach was applied to develop action plans to support the retrieval and disposal mission of the TWRS Project. The systems and infrastructure required to support the mission are known. Required systems are either in place or plans have been developed to ensure they exist when needed. Since October 1996 a robust system engineering approach to establishing integrated Technical Baselines, work breakdown structures, tank farms organizational structure and configurations, work scope, and costs has become part of the culture within the TWRS Project. An analysis of the programmatic, management, and technical activities necessary to declare readiness to proceed with execution of the mission demonstrates that the system, personnel, and hardware will be on-line and ready to support the private contractors. The systems approach included defining the retrieval and disposal mission requirements and evaluating the readiness of the Project Hanford Management Contract (PHMC) team to support initiation of waste processing by the private contractors in June 2002 and to receive immobilized waste shortly thereafter. The Phase 1 feed delivery requirements from the private contractor Requests for Proposal were reviewed. Transfer piping routes were mapped, existing systems were evaluated, and upgrade requirements were defined

  1. Tank waste remediation system retrieval and disposal mission phase 1 financial analysis

    International Nuclear Information System (INIS)

    Wells, M.W.

    1998-01-01

    The purpose of the Tank Waste Remediation System (TWRS) Retrieval and Disposal Mission Phase 1 Financial Analysis is to provide a quantitative and qualitative cost and schedule risk analysis of HNF-1946, Tank Waste Remediation System Retrieval and Disposal Mission Initial Updated Baseline (Swita et al. 1998). The Updated Baseline (Section 3.0) is compared to the current TWRS Project Multi-Year Work Plan (MYWP) for fiscal year (FY) 1998 and target budgets for FY 1999 through FY 2011 (Section 4.1). The analysis then evaluates the executability of HNF-1946 (Sections 4.2 through 4.5) and recommends a path forward for risk mitigation (Sections 4.6, 4.7, and 5.0). A sound systems engineering approach was applied to understand and analyze the Phase 1B Retrieval and Disposal mission. Program and Level 1 Logics were decomposed to Level 8 of the Work Breakdown Structure (WBS) where logic was detailed, scope was defined, detail durations and estimates prepared, and resource loaded schedules developed. Technical Basis Review (TBR) packages were prepared which include this information and, in addition, defined the enabling assumptions for each task, and the risks associated with performance. This process is discussed in Section 2.1. Detailed reviews at the subactivity within the Level 1 Logic TBR levels were conducted to provide the recommended solution to the Phase 1B Retrieval and Disposal Mission. Independent cost analysis and risk assessments were performed by members of the Lockheed Martin Hanford Corporation (LMHC) Business Management and Chief Financial Officer organization along with specialists in risk analysis from TRW, Inc. and Lockheed Martin Energy Systems. The process evaluated technical, schedule, and cost risk by category (program specific fixed and variable, integrated program, and programmatic) based on risk certainly from high probability well defined to very low probability that is not bounded or priceable as discussed in Section 2.2. The results have been

  2. An analysis of alternative New Technical Strategy flowsheets for tank waste remediation system

    International Nuclear Information System (INIS)

    Booker, C.P.

    1994-01-01

    The Hanford Tank remediation plans have gone through a few revisions for the best waste processing system. Some designs have been complex while others have been fairly simple. One of the key means in understanding and selecting among the various proposed systems is a discrete events modeling of the system. This modeling provides insight into (1) The total required size of the system; (2) The amount of material, such as reagents and other added materials that must be supplied; (3) The final mass of waste that must be stored; and (4) Areas within the system where a small change can greatly effect the total system. Discrete events modeling also provides the means by which various proposed systems may be compared. It is the framework in which variations within a particular system may be explored and compared to other instantiations. This study examines the current New Technical Strategy flowsheet system with discrete event modeling. Some of the possible variations within that system are examined and compared. Further, an previously proposed, more complex system is examined

  3. Tank waste remediation system retrieval and disposal mission initial updated baseline summary

    International Nuclear Information System (INIS)

    Swita, W.R.

    1998-01-01

    This document provides a summary of the Tank Waste Remediation System (TWRS) Retrieval and Disposal Mission Initial Updated Baseline (scope, schedule, and cost), developed to demonstrate Readiness-to-Proceed (RTP) in support of the TWRS Phase 1B mission. This Updated Baseline is the proposed TWRS plan to execute and measure the mission work scope. This document and other supporting data demonstrate that the TWRS Project Hanford Management Contract (PHMC) team is prepared to fully support Phase 1B by executing the following scope, schedule, and cost baseline activities: Deliver the specified initial low-activity waste (LAW) and high-level waste (HLW) feed batches in a consistent, safe, and reliable manner to support private contractors' operations starting in June 2002; Deliver specified subsequent LAW and HLW feed batches during Phase 1B in a consistent, safe, and reliable manner; Provide for the interim storage of immobilized HLW (IHLW) products and the disposal of immobilized LAW (ILAW) products generated by the private contractors; Provide for disposal of byproduct wastes generated by the private contractors; and Provide the infrastructure to support construction and operations of the private contractors' facilities

  4. Risk-based systems analysis of emerging high-level waste tank remediation technologies. Volume 2: Final report

    International Nuclear Information System (INIS)

    Peters, B.B.; Cameron, R.J.; McCormack, W.D.

    1994-08-01

    The objective of DOE's Radioactive Waste Tank Remediation Technology Focus Area is to identify and develop new technologies that will reduce the risk and/or cost of remediating DOE underground waste storage tanks and tank contents. There are, however, many more technology investment opportunities than the current budget can support. Current technology development selection methods evaluate new technologies in isolation from other components of an overall tank waste remediation system. This report describes a System Analysis Model developed under the US Department of Energy (DOE) Office of Technology Development (OTD) Underground Storage Tank-Integrated Demonstration (UST-ID) program. The report identifies the project objectives and provides a description of the model. Development of the first ''demonstration'' version of this model and a trial application have been completed and the results are presented. This model will continue to evolve as it undergoes additional user review and testing

  5. Risk-based systems analysis of emerging high-level waste tank remediation technologies. Volume 2: Final report

    Energy Technology Data Exchange (ETDEWEB)

    Peters, B.B.; Cameron, R.J.; McCormack, W.D. [Enserch Environmental Corp., Richland, WA (United States)

    1994-08-01

    The objective of DOE`s Radioactive Waste Tank Remediation Technology Focus Area is to identify and develop new technologies that will reduce the risk and/or cost of remediating DOE underground waste storage tanks and tank contents. There are, however, many more technology investment opportunities than the current budget can support. Current technology development selection methods evaluate new technologies in isolation from other components of an overall tank waste remediation system. This report describes a System Analysis Model developed under the US Department of Energy (DOE) Office of Technology Development (OTD) Underground Storage Tank-Integrated Demonstration (UST-ID) program. The report identifies the project objectives and provides a description of the model. Development of the first ``demonstration`` version of this model and a trial application have been completed and the results are presented. This model will continue to evolve as it undergoes additional user review and testing.

  6. Tank Waste Remediation System tank waste pretreatment and vitrification process development testing requirements assessment

    International Nuclear Information System (INIS)

    Howden, G.F.

    1994-01-01

    A multi-faceted study was initiated in November 1993 to provide assurance that needed testing capabilities, facilities, and support infrastructure (sampling systems, casks, transportation systems, permits, etc.) would be available when needed for process and equipment development to support pretreatment and vitrification facility design and construction schedules. This first major report provides a snapshot of the known testing needs for pretreatment, low-level waste (LLW) and high-level waste (HLW) vitrification, and documents the results of a series of preliminary studies and workshops to define the issues needing resolution by cold or hot testing. Identified in this report are more than 140 Hanford Site tank waste pretreatment and LLW/HLW vitrification technology issues that can only be resolved by testing. The report also broadly characterizes the level of testing needed to resolve each issue. A second report will provide a strategy(ies) for ensuring timely test capability. Later reports will assess the capabilities of existing facilities to support needed testing and will recommend siting of the tests together with needed facility and infrastructure upgrades or additions

  7. Tank Waste Remediation System tank waste pretreatment and vitrification process development testing requirements assessment

    Energy Technology Data Exchange (ETDEWEB)

    Howden, G.F.

    1994-10-24

    A multi-faceted study was initiated in November 1993 to provide assurance that needed testing capabilities, facilities, and support infrastructure (sampling systems, casks, transportation systems, permits, etc.) would be available when needed for process and equipment development to support pretreatment and vitrification facility design and construction schedules. This first major report provides a snapshot of the known testing needs for pretreatment, low-level waste (LLW) and high-level waste (HLW) vitrification, and documents the results of a series of preliminary studies and workshops to define the issues needing resolution by cold or hot testing. Identified in this report are more than 140 Hanford Site tank waste pretreatment and LLW/HLW vitrification technology issues that can only be resolved by testing. The report also broadly characterizes the level of testing needed to resolve each issue. A second report will provide a strategy(ies) for ensuring timely test capability. Later reports will assess the capabilities of existing facilities to support needed testing and will recommend siting of the tests together with needed facility and infrastructure upgrades or additions.

  8. Interface control document for tank waste remediation system privatization phase 1 infrastructure support Project W-519

    International Nuclear Information System (INIS)

    Parazin, R.J.

    1998-01-01

    This document describes the functional and physical interfaces between the Tank Waste Remediation System (TWRS) Privatization Phase 1 Infrastructure Project W-519 and the various other projects (i.e., Projects W-314, W-464, W-465, and W-520) supporting Phase 1 that will require the allocation of land in and about the Privatization Phase 1 Site and/or interface with the utilities extended by Project W-519. Project W-519 will identify land use allocations and upgrade/extend several utilities in the 200-East Area into the Privatization Phase 1 Site (formerly the Grout Disposal Compound) in preparation for the Privatization Contractors (PC) to construct treatment facilities. The project will upgrade/extend: Roads, Electrical Power, Raw Water (for process and fire suppression), Potable Water, and Liquid Effluent collection. The replacement of an existing Sanitary Sewage treatment system that may be displaced by Phase 1 site preparation activities may also be included

  9. Tank Waste Remediation System, Hanford Site, Richland, Washington. Final Environmental Impact Statement. Volume VI

    International Nuclear Information System (INIS)

    1996-08-01

    The U.S. Department Of Energy and the Washington State Department of Ecology added Appendix L (Volume 6), Response to Public Comments, to the Tank Waste Remediation System (TWRS) Final Environmental Impact Statement (EIS) for the Hanford Site, Richland, Washington, to fully address and respond to public comments on the Draft EIS. In addition, DOE considered public comments, along with other factors such as programmatic need, short- and long-term impacts, technical feasibility, and cost, in arriving at DOE's preferred alternative. During the public comment period for the Draft EIS, more than 350 individuals, agencies, Tribal Nations, and organizations provided comments. This volume represents a broad spectrum of private citizens; businesses; local, State, and Federal officials; Tribal Nations; and public interest groups

  10. Tank waste remediation system retrieval and disposal mission readiness-to-proceed guidance and requirements to deliverables crosswalk

    International Nuclear Information System (INIS)

    Hall, C.E.

    1998-01-01

    Before RL can authorize proceeding with Phase 1B, the PHMC team must demonstrate its readiness to retrieve and deliver the waste to the private contractors and to receive and dispose of the products and byproducts returned from the treatment. The PHMC team has organized their plans for providing these vitrification-support services into the Retrieval and Disposal Mission within the Tank Waste Remediation System (TWRS) Program

  11. Public values related to decisions in the Tank Waste Remediation System Program

    International Nuclear Information System (INIS)

    Armacost, L.L.; Robershotte, M.; von Winterfeldt, D.; Creighton, J.

    1994-10-01

    Managers of the Tank Waste Remediation System (TWRS) Program have to make numerous decisions, ranging from the strategic decisions on the fundamental tank cleanup goals to technical decisions on which types of equipment to use in mechanical retrieval of wastes. Furthermore, many of these decisions have to be made repeatedly (e.g., the annual allocation of research and development funds to TWRS activities). These decisions have many potential consequences in terms of risks to workers, risks to the public, environmental impacts, and economic development and cost. Because these consequences affect the values of many parties, the consequences need to be evaluated in terms that are accepted and understood by the interested parties. Therefore, an effort needs to be made to incorporate public concerns and values into the TWRS decision-making process. The purpose of this report is to review and integrate this past work on values and to create a maser list of values in order to create a consistent value framework for the numerous TWRS decisions; efficiently and effectively use public values in the decision-making process by updating this report on a regular basis to ensure that the information represents the public's current views; provide guidance about using values in technical TWRS decisions

  12. Experimental logistics plan in support of Extensive Separations for Hanford tank waste remediation systems

    International Nuclear Information System (INIS)

    Enderlin, W.I.; Swanson, J.L.; Carlson, C.D.; Hirschi, E.J.

    1993-12-01

    All proposed methods for remediating the radioactive and chemical waste stored in single- and double-shell tanks (SSTs and DSTs) at the Hanford Site require the separation of the waste mixtures in the tank into high-level and low-level fractions, the safe transport of this separated waste to appropriate immobilization facilities, and the long-term disposal of the immobilized waste forms. Extensive experimentation, especially in waste separations, will be required to develop the technologies and to produce the data that support the most effective and safe cleanup processes. As part of this effort, Pacific Northwest Laboratory (PNL) is developing this detailed experimental logistics plan to determine the logistical/resource requirements, and ultimately the critical paths, necessary to effectively and safely conduct the multitude of experiments within the Extensive Separations Development Program, which addresses the experimental needs of a concept that provides a high degree of separation for the high-level and low-level waste fractions. The logistics issues developed for this program are expected to be similar to those for other programs aimed at remediating and disposing of the wastes

  13. Technology development activities supporting tank waste remediation

    International Nuclear Information System (INIS)

    Bonner, W.F.; Beeman, G.H.

    1994-06-01

    This document summarizes work being conducted under the U.S. Department of Energy's Office of Technology Development (EM-50) in support of the Tank Waste Remediation System (TWRS) Program. The specific work activities are organized by the following categories: safety, characterization, retrieval, barriers, pretreatment, low-level waste, and high-level waste. In most cases, the activities presented here were identified as supporting tank remediation by EM-50 integrated program or integrated demonstration lead staff and the selections were further refined by contractor staff. Data sheets were prepared from DOE-HQ guidance to the field issued in September 1993. Activities were included if a significant portion of the work described provides technology potentially needed by TWRS; consequently, not all parts of each description necessarily support tank remediation

  14. Configuration management plan for waste tank farms and the 242-A evaporator of tank waste remediation system

    International Nuclear Information System (INIS)

    Laney, T.

    1994-01-01

    The configuration management architecture presented in this Configuration Management Plan is based on the functional model established by DOE-STD-1073-93, ''Guide for Operational Configuration Management Program.'' The DOE Standard defines the configuration management program by the five basic program elements of ''program management,'' ''design requirements,'' ''document control,'' ''change control,'' and ''assessments,'' and the two adjunct recovery programs of ''design reconstitution,'' and ''material condition and aging management.'' The CM model of five elements and two adjunct programs strengthen the necessary technical and administrative control to establish and maintain a consistent technical relationship among the requirements, physical configuration, and documentation. Although the DOE Standard was originally developed for the operational phase of nuclear facilities, this plan has the flexibility to be adapted and applied to all life-cycle phases of both nuclear and non-nuclear facilities. The configuration management criteria presented in this plan endorses the DOE Standard and has been tailored specifically to address the technical relationship of requirements, physical configuration, and documentation during the full life cycle of the Waste Tank Farms and 242-A Evaporator of Tank Waste Remediation System

  15. Performance objectives of the tank waste remediation system low-level waste disposal program

    International Nuclear Information System (INIS)

    1994-01-01

    Before low-level waste may be disposed of, a performance assessment must be written and then approved by the U.S. Department of Energy. The performance assessment is to determine whether open-quotes reasonable assuranceclose quotes exists that the performance objectives of the disposal facility will be met. The DOE requirements for waste disposal require: the protection of public health and safety; and the protection of the environment. Although quantitative limits are sometimes stated (for example, the all exposure pathways exposure limit is 25 mrem/year), usually the requirements are stated in a general nature. Quantitative limits were established by: investigating all potentially applicable regulations as well as interpretations of the Peer Review Panel which DOE has established to review performance assessments, interacting with program management to establish their needs, and interacting with the public (i.e., the Hanford Advisory Board members; as well as affected Indian tribes) to understand the values of residents in the Pacific Northwest

  16. Radioactive tank waste remediation focus area

    International Nuclear Information System (INIS)

    1996-08-01

    EM's Office of Science and Technology has established the Tank Focus Area (TFA) to manage and carry out an integrated national program of technology development for tank waste remediation. The TFA is responsible for the development, testing, evaluation, and deployment of remediation technologies within a system architecture to characterize, retrieve, treat, concentrate, and dispose of radioactive waste stored in the underground stabilize and close the tanks. The goal is to provide safe and cost-effective solutions that are acceptable to both the public and regulators. Within the DOE complex, 335 underground storage tanks have been used to process and store radioactive and chemical mixed waste generated from weapon materials production and manufacturing. Collectively, thes tanks hold over 90 million gallons of high-level and low-level radioactive liquid waste in sludge, saltcake, and as supernate and vapor. Very little has been treated and/or disposed or in final form

  17. Radioactive tank waste remediation focus area

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-08-01

    EM`s Office of Science and Technology has established the Tank Focus Area (TFA) to manage and carry out an integrated national program of technology development for tank waste remediation. The TFA is responsible for the development, testing, evaluation, and deployment of remediation technologies within a system architecture to characterize, retrieve, treat, concentrate, and dispose of radioactive waste stored in the underground stabilize and close the tanks. The goal is to provide safe and cost-effective solutions that are acceptable to both the public and regulators. Within the DOE complex, 335 underground storage tanks have been used to process and store radioactive and chemical mixed waste generated from weapon materials production and manufacturing. Collectively, thes tanks hold over 90 million gallons of high-level and low-level radioactive liquid waste in sludge, saltcake, and as supernate and vapor. Very little has been treated and/or disposed or in final form.

  18. Risk-based systems analysis of emerging high-level waste tank remediation technologies. Volume 1: Executive summary

    International Nuclear Information System (INIS)

    Peters, B.B.; Cameron, R.J.; McCormack, W.D.

    1994-08-01

    This report describes a System Analysis Model developed under the US Department of Energy (DOE) Office of Technology Development (OTD) Underground Storage Tank-Integrated Demonstration (UST-ID) program to aid technology development funding decisions for radioactive tank waste remediation. Current technology development selection methods evaluate new technologies in isolation from other components of an overall tank waste remediation system. These methods do not show the relative effect of new technologies on tank remediation systems as a whole. Consequently, DOE may spend its resources on technologies that promise to improve a single function but have a small or possibly negative, impact on the overall system, or DOE may overlook a technology that does not address a high priority problem in the system but that does, if implemented, offer sufficient overall improvements. Systems engineering and detailed analyses often conducted under the National Environmental Policy Act (NEPA 1969) use a ''whole system'' approach but are costly, too time-consuming, and often not sufficiently focused to support the needs of the technology program decision-makers. An alternative approach is required to evaluate these systems impacts but still meet the budget and schedule needs of the technology program

  19. Tank waste remediation system retrieval and disposal mission readiness-to-proceed guidance and requirements to deliverables crosswalk

    International Nuclear Information System (INIS)

    Hall, C.E.

    1998-01-01

    In September 1996, the US Department of Energy, Richland Operations Office (RL) initiated the first of a two-phase program to remediate waste storage in tanks at the Hanford Site in Washington State. Initiating the first phase, RL signed contracts with two private companies who agreed to receive and vitrify a portion of the tank waste in a demonstration and to return the vitrified product and by-products to the Project Management Hanford Contract (PHMC) team for disposition. The first phase of the overall remediation effort is a demonstration of treatment concepts, and the second phase includes treatment of the remaining tank wastes. The demonstration phase, Phase 1 of the project, is further subdivided into two parts, A and B. During Phase 1A, the vitrification contractors are to establish the technical, operational, regulatory, business, and financial elements required to provide treatment services on a fixed unit price basis. Phase 1A deliverables will be evaluated by RL to determine whether it is in the best interest of the government to have one or more vitrification contractors proceed with Phase 1B, in which 6% to 13% of the tank waste would be treated in the demonstration. In addition, before RL can authorize proceeding with Phase 1B, the PHMC team must demonstrate its readiness to retrieve and deliver the waste to the private contractor(s) and to receive and dispose of the products and by-products returned from the treatment. The PHMC team has organized their plans for providing these vitrification-support services into the Retrieval and Disposal Mission within the Tank Waste Remediation System (TWRS) Project. Three RL core teams were established to assist in evaluating the PHMC team's readiness specifically in regard to three task areas: Waste feed delivery; Infrastructure and by-products delivery; and Immobilized products. The core teams each developed a set of criteria and plans to be used in evaluating the PHMC team's readiness to proceed (RTP)

  20. Tank waste remediation system immobilized high-level waste storage project configuration management implementation plan

    International Nuclear Information System (INIS)

    Burgard, K.G.; Schaus, P.S.; Rossi, H.

    1998-01-01

    This Configuration Management Implementation Plan was developed to assist in the management of systems, structures, and components, to facilitate the effective control and statusing of changes to systems, structures, and components; and to ensure technical consistency between design, performance, and operational requirements. Its purpose is to describe the approach Project W-464 will take in implementing a configuration management control, to determine the rigor of control, and to identify the mechanisms for imposing that control.This Configuration Management Implementation Plan was developed to assist in the management of systems, structures, and components, to facilitate the effective control and statusing of changes to systems, structures, and components; and to ensure technical consistency between design, performance, and operational requirements. Its purpose is to describe the approach Project W-464 will take in implementing a configuration management control, to determine the rigor of control, and to identify the mechanisms for imposing that control

  1. Potential enhancements to addressing programmatic risk in the tank waste remediation system (TWRS) program

    International Nuclear Information System (INIS)

    Brothers, A.; Fassbender, L.; Bilyard, G.; Levine, L.

    1996-04-01

    Pacific Northwest National Laboratory (PNNL) conducted a Tank Waste Remediation System (TWRS) Risk Management methodology development task. The objective of this task was to develop risk management methodology focused on (1) the use of programmatic risk information in making TWRS architecture selection decisions and (2) the identification/evaluation/selection of TWRS risk-handling actions. Methods for incorporating programmatic risk/uncertainty estimates into trade studies are provided for engineers/analysts. Methods for identifying, evaluating, and selecting risk-handling actions are provided for managers. The guidance provided in this report is designed to help decision-makers make difficult judgments. Current approaches to architecture selection decisions and identification/evaluation/selection of risk-handling actions are summarized. Three categories of sources of programmatic risk (parametric, external, and organizational) are examined. Multiple analytical approaches are presented to enhance the current alternative generation and analysis (AGA) and risk-handling procedures. Appendix A describes some commercially available risk management software tools and Appendix B provides a brief introduction to quantification of risk attitudes. The report provides three levels of analysis for enhancing the AGA Procedure: (1) qualitative discussion coupled with estimated uncertainty ranges for scores in the alternatives-by-criteria matrix; (2) formal elicitation of probability distributions for the alternative scores; and (3) a formal, more structured, comprehensive risk analysis. A framework is also presented for using the AGA programmatic risk analysis results in making better decisions. The report also presents two levels of analysis for evaluation and selection of risk-handling actions: (1) qualitative analysis and judgmental rankings of alternative actions, and (2) Simple Multi-Attribute Rating Technique (SMART)

  2. Value tradeoffs for the Hanford Tank Waste Remediation System (TWRS) program

    Energy Technology Data Exchange (ETDEWEB)

    Keeney, R.L.; Winterfeldt, D. von [Decision Insights, Inc., Irvine, CA (United States)

    1997-09-01

    The Tank Waste Remediation System (TWRS) program at the Hanford Site of the Department of Energy has adopted a logical approach to making decisions that uses decision analysis to structure and analyze decision alternatives and public values to evaluate them. This report is the third in a series to support this effort. The first identified a set of objectives (called {open_quotes}ends objectives{close_quotes}) that characterize the ultimate goals and desires of Hanford decision makers and stakeholders. The second report developed operational measures for these ends objectives (called {open_quotes}ends measures{close_quotes}) and it also developed a set of performance objectives and associated performance measures that are more directly related to how well decision alternatives in the TWRS program perform to achieve the ends objectives. The present report describes the development of quantitative value tradeoffs for both the ends measures and the performance measures. First, five national value experts were interviewed to obtain value tradeoffs for units of the ends measures identified in Keeney and von Winterfeldt (1996). The results of this assessment are shown in Table S1. Second, the implied value tradeoffs for the units of the performance measures were calculated from the value tradeoffs for units of the ends measures provided by the national experts. When calculating the value tradeoffs for the units of the performance measures, very simple quantitative relationships between ends and performance measures were assumed. The results of this calculation are shown in Table S2. The results of this report shown in Tables S1 and S2 should be considered preliminary and largely illustrative of the principles for developing value tradeoffs. The report lists several important caveats and recommendations for how future work can improve on the assessment of value tradeoffs.

  3. Methodology to remediate a mixed waste site

    Energy Technology Data Exchange (ETDEWEB)

    Berry, J.B.

    1994-08-01

    In response to the need for a comprehensive and consistent approach to the complex issue of mixed waste management, a generalized methodology for remediation of a mixed waste site has been developed. The methodology is based on requirements set forth in the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) and the Resource Conservation and Recovery Act (RCRA) and incorporates ``lessons learned`` from process design, remediation methodologies, and remediation projects. The methodology is applied to the treatment of 32,000 drums of mixed waste sludge at the Oak Ridge K-25 Site. Process technology options are developed and evaluated, first with regard to meeting system requirements and then with regard to CERCLA performance criteria. The following process technology options are investigated: (1) no action, (2) separation of hazardous and radioactive species, (3) dewatering, (4) drying, and (5) solidification/stabilization. The first two options were eliminated from detailed consideration because they did not meet the system requirements. A quantitative evaluation clearly showed that, based on system constraints and project objectives, either dewatering or drying the mixed waste sludge was superior to the solidification/stabilization process option. The ultimate choice between the drying and the dewatering options will be made on the basis of a technical evaluation of the relative merits of proposals submitted by potential subcontractors.

  4. Methodology to remediate a mixed waste site

    International Nuclear Information System (INIS)

    Berry, J.B.

    1994-08-01

    In response to the need for a comprehensive and consistent approach to the complex issue of mixed waste management, a generalized methodology for remediation of a mixed waste site has been developed. The methodology is based on requirements set forth in the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) and the Resource Conservation and Recovery Act (RCRA) and incorporates ''lessons learned'' from process design, remediation methodologies, and remediation projects. The methodology is applied to the treatment of 32,000 drums of mixed waste sludge at the Oak Ridge K-25 Site. Process technology options are developed and evaluated, first with regard to meeting system requirements and then with regard to CERCLA performance criteria. The following process technology options are investigated: (1) no action, (2) separation of hazardous and radioactive species, (3) dewatering, (4) drying, and (5) solidification/stabilization. The first two options were eliminated from detailed consideration because they did not meet the system requirements. A quantitative evaluation clearly showed that, based on system constraints and project objectives, either dewatering or drying the mixed waste sludge was superior to the solidification/stabilization process option. The ultimate choice between the drying and the dewatering options will be made on the basis of a technical evaluation of the relative merits of proposals submitted by potential subcontractors

  5. Performance Assessment of the Waste Dislodging Conveyance System During the Gunite And Associated Tanks Remediation Project

    International Nuclear Information System (INIS)

    Lloyd, P.D.

    2001-01-01

    The Waste Dislodging and Conveyance System (WD and CS) and other components of the Tank Waste Retrieval System (TWRS) were developed to address the need for removal of hazardous wastes from underground storage tanks (USTs) in which radiation levels and access limitations make traditional waste retrieval methods impractical. Specifically, these systems were developed for cleanup of the Gunite and Associated Tanks (GAAT) Operable Unit (OU) at the Oak Ridge National Laboratory (ORNL). The WD and CS is comprised of a number of different components. The three primary hardware subsystems are the Hose Management System (HMS), the Confined Sluicing End-Effector (CSEE), and the Flow Control Equipment and Containment Box (FCE/CB). In addition, a Decontamination Spray Ring (DSR) and a control system were developed for the system. The WD and CS is not a stand-alone system; rather, it is designed for deployment with either a long-reach manipulator like the Modified Light Duty Utility Arm (MLDUA) or a remotely operated vehicle system such as the Houdinitrademark. The HMS was designed to act as a pipeline for the transfer of dislodged waste; as a hose-positioning and tether-management system; and as a housing for process equipment such as the water-powered jet pump that provides the necessary suction to vacuum slurried waste from the UST. The HMS was designed to facilitate positioning of an end-effector at any point within the 25-ft- or 50-ft-diameter USTs in the GAAT OU

  6. Remediation and upgrading of old, inadequate waste management facilities. Integrated waste management system for rare earth and rare metal industry at Sillamaee, Estonia, former uranium facility

    International Nuclear Information System (INIS)

    Kaasik, Tonis; Siinmaa, Anti

    2001-01-01

    Full text: The Sillamaee Metallurgical Plant was built in 1946-1948 at Sillamaee, in North-East Estonia, ca 190 km from Tallinn. Target product was uranium, mostly in form of yellow cake (U 3 O 8 ) for Soviet nuclear program. Uranium ore processing continued from 1948 to 1977, totally 4,013,000 tons of uranium ore were processed at Sillamaee plant. In early 1970s the plant introduced a new production line - rare earth elements. Rare earths were until 1991 produced from loparite (later from semi-processed loparite) - rare earths, niobium, tantalum and NORM-containing ore for Kola peninsula, Russia; later. All wastes were, as typical to hydrometallurgical processing all over the world, discharged to a large, 40 ha liquid waste depository - tailings pond, what in Sillamaee case was designed to discharge all liquid constituents slowly to the Baltic Sea. All uranium related activities were stopped in 1990, when only rare earth and rare metal production lines remained operational. The plant was 100 % privatized in 1997 and is today operated by Silmet Ltd., processing annually up to 8 000 tons of rare earth and 2000 tons of niobium and tantalum ores. Like all industries, inherited from Soviet times, Silmet plant is today facing a serious challenge to upgrading technologies towards waste minimizations process efficiency. The historical tailings pond, containing ca 1800 tons of natural uranium and ca 800 tons of thorium, was found geotechnically unstable and leaking to the Baltic Sea, in mid 90s. Being a problem of common Baltic concern, an international remediation project was initiated by Estonian Government and plant operator in 1998. In cooperation with Estonian, Finnish, Swedish, Danish and Norwegian Governments and with assistance by the European Union, the tailings pond will be environmentally remediated - dams stabilized and surface covered, by end of 2006. Close-down and environmental remediation of the tailings pond provides plant an ultimate challenge of

  7. Waste minimization applications at a remediation site

    International Nuclear Information System (INIS)

    Allmon, L.A.

    1995-01-01

    The Fernald Environmental Management Project (FEMP) owned by the Department of Energy was used for the processing of uranium. In 1989 Fernald suspended production of uranium metals and was placed on the National Priorities List (NPL). The site's mission has changed from one of production to environmental restoration. Many groups necessary for producing a product were deemed irrelevant for remediation work, including Waste Minimization. Waste Minimization does not readily appear to be applicable to remediation work. Environmental remediation is designed to correct adverse impacts to the environment from past operations and generates significant amounts of waste requiring management. The premise of pollution prevention is to avoid waste generation, thus remediation is in direct conflict with this premise. Although greater amounts of waste will be generated during environmental remediation, treatment capacities are not always available and disposal is becoming more difficult and costly. This creates the need for pollution prevention and waste minimization. Applying waste minimization principles at a remediation site is an enormous challenge. If the remediation site is also radiologically contaminated it is even a bigger challenge. Innovative techniques and ideas must be utilized to achieve reductions in the amount of waste that must be managed or dispositioned. At Fernald the waste minimization paradigm was shifted from focusing efforts on source reduction to focusing efforts on recycle/reuse by inverting the EPA waste management hierarchy. A fundamental difference at remediation sites is that source reduction has limited applicability to legacy wastes but can be applied successfully on secondary waste generation. The bulk of measurable waste reduction will be achieved by the recycle/reuse of primary wastes and by segregation and decontamination of secondary wastestreams. Each effort must be measured in terms of being economically and ecologically beneficial

  8. Hazardous Waste Remedial Actions Program: integrating waste management

    International Nuclear Information System (INIS)

    Petty, J.L.; Sharples, F.E.

    1986-01-01

    The Hazardous Waste Remedial Actions Program was established to integrate Defense Programs' activities in hazardous and mixed waste management. The Program currently provides centralized planning and technical support to the Office of the Assistant Secretary for Defense Programs. More direct project management responsibilities may be assumed in the future. The Program, under the direction of the ASDP's Office of Defense Waste and Transportation Management, interacts with numerous organizational entities of the Department. The Oak Ridge Operations Office has been designated as the Lead Field Office. The Program's four current components cover remedial action project identification and prioritization; technology adaptation; an informative system; and a strategy study for long-term, ''corporate'' project and facility planning

  9. Management assessment of tank waste remediation system contractor readiness to proceed with phase 1B privatization

    International Nuclear Information System (INIS)

    Certa, P.J.

    1998-01-01

    Readiness to Proceed With Phase 1B Privatization documents the processes used to determine readiness to proceed with tank waste treatment technologies from private industry, now known as TWRS privatization. An overall systems approach was applied to develop action plans to support the retrieval and disposal mission of the TWRS Project. The systems and infrastructure required to support the mission are known. Required systems are either in place or plans have been developed to ensure they exist when needed. Since October 1996 a robust system engineering approach to establishing integrated Technical Baselines, work breakdown structures, tank farms organizational structure and configurations, work scope, and costs has become part of the culture within the TWRS Project. An analysis of the programmatic, management, and technical activities necessary to declare readiness to proceed with execution of the mission demonstrates that the system, personnel, and hardware will be on line and ready to support the private contractors. The systems approach included defining the retrieval and disposal mission requirements and evaluating the readiness of the Project Hanford Management Contract (PHMC) team to support initiation of waste processing by the private contractors in June 2002 and to receive immobilized waste shortly thereafter. The Phase 1 feed delivery requirements from the private contractor Requests for Proposal were reviewed. Transfer piping routes were mapped, existing systems were evaluated, and upgrade requirements were defined

  10. Tank waste remediation system retrieval and disposal mission key enabling assumptions

    International Nuclear Information System (INIS)

    Baldwin, J.H.

    1998-01-01

    An overall systems approach has been applied to develop action plans to support the retrieval and immobilization waste disposal mission. The review concluded that the systems and infrastructure required to support the mission are known. Required systems are either in place or plans have been developed. An analysis of the programmatic, management and technical activities necessary to declare Readiness to Proceed with execution of the mission demonstrates that the system, people, and hardware will be on line and ready to support the private contractors. The systems approach included defining the retrieval and immobilized waste disposal mission requirements and evaluating the readiness of the TWRS contractor to supply waste feed to the private contractors in June 2002. The Phase 1 feed delivery requirements from the Private Contractor Request for Proposals were reviewed, transfer piping routes were mapped on it, existing systems were evaluated, and upgrade requirements were defined. Technical Basis Reviews were completed to define work scope in greater detail, cost estimates and associated year by year financial analyses were completed. Personnel training, qualifications, management systems and procedures were reviewed and shown to be in place and ready to support the Phase 1B mission. Key assumptions and risks that could negatively impact mission success were evaluated and appropriate mitigative actions plans were planned and scheduled

  11. Hazardous waste treatment and environmental remediation research

    International Nuclear Information System (INIS)

    1989-01-01

    Los Alamos National Laboratory (LANL) is currently evaluating hazardous waste treatment and environmental remediation technologies in existence and under development to determine applicability to remediation needs of the DOE facilities under the Albuquerque Operations Office and to determine areas of research need. To assist LANL is this effort, Science Applications International Corporation (SAIC) conducted an assessment of technologies and monitoring methods that have been demonstrated or are under development. The focus of this assessment is to: (1) identify existing technologies for hazardous waste treatment and environmental remediation of old waste sites; (2) identify technologies under development and the status of the technology; (3) assess new technologies that need development to provide adequate hazardous waste treatment and remedial action technologies for DOD and DOE sites; and (4) identify hazardous waste and remediation problems for environmental research and development. There are currently numerous research and development activities underway nationwide relating to environmental contaminants and the remediation of waste sites. To perform this effort, SAIC evaluated current technologies and monitoring methods development programs in EPA, DOD, and DOE, as these are the primary agencies through which developmental methods are being demonstrated. This report presents this evaluation and provides recommendations as to pertinent research needs or activities to address waste site contamination problems. The review and assessment have been conducted at a programmatic level; site-specific and contaminant-specific evaluations are being performed by LANL staff as a separate, related activity

  12. Tank waste remediation system retrieval and disposal mission key enabling assumptions

    International Nuclear Information System (INIS)

    Baldwin, J.H.

    1998-01-01

    An overall systems approach has been applied to develop action plans to support the retrieval and immobilization waste disposal mission. The review concluded that the systems and infrastructure required to support the mission are known. Required systems are either in place or plans have been developed to ensure they exist when needed. The review showed that since October 1996 a robust system engineering approach to establishing integrated Technical Baselines, work breakdown structures, tank farm structure and configurations and work scope and costs has been established itself as part of the culture within TWRS. An analysis of the programmatic, management and technical activities necessary to declare readiness to proceed with execution of the mission demonstrates that the system, people and hardware will be on line and ready to support the private contractors. The systems approach included defining the retrieval and immobilized waste disposal mission requirements and evaluating the readiness of the TWRS contractor to supply waste feed to the private contractors in June 2OO2. The Phase 1 feed delivery requirements from the Private Contractor Request for Proposals were reviewed. Transfer piping routes were mapped out, existing systems were evaluated, and upgrade requirements were defined. Technical Basis Reviews were completed to define work scope in greater detail, cost estimates and associated year by year financial analyses were completed. TWRS personnel training, qualifications, management systems and procedures were reviewed and shown to be in place and ready to support the Phase 1B mission. Key assumptions and risks that could negatively impact mission success were evaluated and appropriate mitigative actions plans were planned and scheduled

  13. Integrated approach to hazardous and radioactive waste remediation

    International Nuclear Information System (INIS)

    Hyde, R.A.; Reece, W.J.

    1994-01-01

    The US Department of Energy Office of Technology Development is supporting the demonstration, and evaluation of a suite of waste retrieval technologies. An integration of leading-edge technologies with commercially available baseline technologies will form a comprehensive system for effective and efficient remediation of buried waste throughout the complex of DOE nuclear facilities. This paper discusses the complexity of systems integration, addressing organizational and engineering aspects of integration as well as the impact of human operators, and the importance of using integrated systems in remediating buried hazardous and radioactive waste

  14. Tank waste remediation system fiscal year 1998 multi-year work plan WBS 1.1

    Energy Technology Data Exchange (ETDEWEB)

    Lenseigne, D. L.

    1997-09-15

    The TWRS Project Mission is to manage and immobilize for disposal the Hanford Site radioactive tank waste and cesium (Cs)/strontium (Sr) capsules in a safe, environmentally sound, and cost-effective manner. The scope includes all activities needed to (1) resolve safety issues; (2) operate, maintain, and upgrade the tank farms and supporting infrastructure; (3) characterize, retrieve, pretreat, and immobilize the waste for disposal and tank farm closure; and (4) use waste minimization and evaporation to manage tank waste volumes to ensure that the tank capacities of existing DSTs are not exceeded. The TWRS Project is responsible for closure of assigned operable units and D&D of TWRS facilities.

  15. Data Management Plan and Functional System Design for the Information Management System of the Clinch River Remedial Investigation and Waste Area Grouping 6

    Energy Technology Data Exchange (ETDEWEB)

    Ball, T.; Brandt, C.; Calfee, J.; Garland, M.; Holladay, S.; Nickle, B.; Schmoyer, D.; Serbin, C.; Ward, M. [Oak Ridge National Lab., TN (United States)

    1994-03-01

    The Data Management Plan and Functional System Design supports the Clinch River Remedial Investigation (CRRI) and Waste Area Grouping (WAG) 6 Environmental Monitoring Program. The objective of the Data Management Plan and Functional System Design is to provide organization, integrity, security, traceability, and consistency of the data generated during the CRRI and WAG 6 projects. Proper organization will ensure that the data are consistent with the procedures and requirements of the projects. The Information Management Groups (IMGs) for these two programs face similar challenges and share many common objectives. By teaming together, the IMGs have expedited the development and implementation of a common information management strategy that benefits each program.

  16. Development of the remedial action priority system: An improved risk assessment tool for prioritizing hazardous and radioactive-mixed waste disposal sites

    International Nuclear Information System (INIS)

    Whelan, G.; Strenge, D.L.; Steelman, B.L.; Hawley, K.A.

    1985-01-01

    The Remedial Action Priority System (RAPS) represents a methodology that prioritizes inactive hazardous and radioactive mixed-waste disposal sites in a scientific and objective manner based on limited site information. This methodology is intended to bridge the technology gap that exists between the initial site evaluation using the Hazard Ranking System (HRS) and the time-consuming process of actual field site characterization, assessment and remediation efforts. The HRS was designed as an initial screening tool to discriminate between hazardous waste sites that do not and those that are likely to power significant problems to human health, safety and/or the environment. The HRS is used by the U.S. EPA to identify sites for nomination to the National Priorities List (NPL). Because the HRS is not designed to evaluate sites containing radionuclides, a modified Hazard Ranking System (mHRS) addressing both hazardous and radioactive mixed wastes was developed by Pacific Northwest Laboratory (PNL) for the U.S. Department of Energy (DOE). Neither the HRS nor the mHRS was designed to prioritize sites that are nominated to the NPL according to their potential risks. To provide DOE with a better management tool for prioritizing funding and human resource allocations for further investigations and possible remediations at its inactive waste sites, PNL is developing the risk assessment methodology called RAPS. Use of RAPS will help DOE ensure that those sites posing the highest potential risk are addressed first

  17. Tank Waste Remediation System (TWRS) Retrieval Authorization Basis Amendment Task Plan

    International Nuclear Information System (INIS)

    HARRIS, J.P.

    1999-01-01

    This task plan is a documented agreement between Nuclear Safety and Licensing and Retrieval Engineering. The purpose of this task plan is to identify the scope of work, tasks and deliverables, responsibilities, manpower, and schedules associated with an authorization basis amendment as a result of the Waste Feed Delivery Program, Project W-211, Project W-521, and Project W-522

  18. Department of Energy Hazardous Waste Remedial Actions Program: An overview

    International Nuclear Information System (INIS)

    Eyman, L.D.; Swiger, R.F.

    1988-01-01

    This paper describes the national Department of Energy (DOE) program for managing hazardous waste. An overview of the DOE Hazardous Waste Remedial Actions Program (HAZWRAP), including its mission, organizational structure, and major program elements, is given. The paper focuses on the contractor support role assigned to Martin Marietta Energy Systems, Inc., through the establishment of the HAZWRAP Support Contractor Office (SCO). The major SCO programs are described, and the organization for managing the programs is discussed. The HAZWRAP SCO approaches to waste management planning and to technology research, development, and demonstration are presented. The role of the SCO in the DOE Environmental Restoration Program and the development of the DOE Waste Information network are reviewed. Also discussed is the DOE Work for Others Program, where waste management decentralized support, via interagency agreements between DOE and the Department of Defense and DOE and the Environmental Protection Agency, is provided for those sponsors planning remedial response actions. 2 refs

  19. 40 CFR 761.269 - Sampling liquid PCB remediation waste.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 30 2010-07-01 2010-07-01 false Sampling liquid PCB remediation waste..., AND USE PROHIBITIONS Cleanup Site Characterization Sampling for PCB Remediation Waste in Accordance with § 761.61(a)(2) § 761.269 Sampling liquid PCB remediation waste. (a) If the liquid is single phase...

  20. 77 FR 12293 - PCBs Bulk Product v. Remediation Waste

    Science.gov (United States)

    2012-02-29

    .... Remediation Waste AGENCY: Environmental Protection Agency (EPA). ACTION: Request for Public Comment. SUMMARY... biphenyl (PCB) disposal regulations regarding PCB bulk product and PCB remediation waste. The proposed... regarding PCB bulk product and PCB remediation waste under regulations promulgated at 40 CFR part 761. The...

  1. 40 CFR 761.61 - PCB remediation waste.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 30 2010-07-01 2010-07-01 false PCB remediation waste. 761.61 Section... PROHIBITIONS Storage and Disposal § 761.61 PCB remediation waste. This section provides cleanup and disposal options for PCB remediation waste. Any person cleaning up and disposing of PCBs managed under this section...

  2. Hazardous Waste Remedial Actions Program annual progress report, FY 1990

    Energy Technology Data Exchange (ETDEWEB)

    1990-12-01

    The Hazardous Waste Remedial Actions Programs (HAZWRAP), a unit of Martin Marietta Energy Systems, Inc., supports the Department of Energy (DOE) Oak Ridge Operations Office in broadly environmental areas, especially those relating to waste management and environmental restoration. HAZWRAP comprises six program areas, which are supported by central administrative and technical organizations. Existing programs deal with airborne hazardous substances, pollution prevention, remedial actions planning, environmental restoration, technology development, and information and data systems. HAZWRAP's mission to develop, promote, and apply-cost-effective hazardous waste management and environmental technologies to help solve national problems and concerns. HAZWRAP seeks to serve as integrator for hazardous waste and materials management across the federal government. It applies the unique combination of research and development (R D) capabilities, technologies, management expertise, and facilities in the Energy Systems complex to address problems of national importance. 24 figs., 10 tabs.

  3. FY-95 technology catalog. Technology development for buried waste remediation

    International Nuclear Information System (INIS)

    1995-01-01

    The US Department of Energy's (DOE) Buried Waste Integrated Demonstration (BWID) program, which is now part of the Landfill Stabilization Focus Area (LSFA), supports applied research, development, demonstration, and evaluation of a multitude of advanced technologies dealing with underground radioactive and hazardous waste remediation. These innovative technologies are being developed as part of integrated comprehensive remediation systems for the effective and efficient remediation of buried waste sites throughout the DOE complex. These efforts are identified and coordinated in support of Environmental Restoration (EM-40) and Waste Management (EM-30) needs and objectives. Sponsored by the DOE Office of Technology Development (EM-50), BWID and LSFA work with universities and private industry to develop technologies that are being transferred to the private sector for use nationally and internationally. This report contains the details of the purpose, logic, and methodology used to develop and demonstrate DOE buried waste remediation technologies. It also provides a catalog of technologies and capabilities with development status for potential users. Past FY-92 through FY-94 technology testing, field trials, and demonstrations are summarized. Continuing and new FY-95 technology demonstrations also are described

  4. FY-95 technology catalog. Technology development for buried waste remediation

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-10-01

    The US Department of Energy`s (DOE) Buried Waste Integrated Demonstration (BWID) program, which is now part of the Landfill Stabilization Focus Area (LSFA), supports applied research, development, demonstration, and evaluation of a multitude of advanced technologies dealing with underground radioactive and hazardous waste remediation. These innovative technologies are being developed as part of integrated comprehensive remediation systems for the effective and efficient remediation of buried waste sites throughout the DOE complex. These efforts are identified and coordinated in support of Environmental Restoration (EM-40) and Waste Management (EM-30) needs and objectives. Sponsored by the DOE Office of Technology Development (EM-50), BWID and LSFA work with universities and private industry to develop technologies that are being transferred to the private sector for use nationally and internationally. This report contains the details of the purpose, logic, and methodology used to develop and demonstrate DOE buried waste remediation technologies. It also provides a catalog of technologies and capabilities with development status for potential users. Past FY-92 through FY-94 technology testing, field trials, and demonstrations are summarized. Continuing and new FY-95 technology demonstrations also are described.

  5. Tank waste remediation system year 2000 dedicated file server project HNF-3418 project plan

    Energy Technology Data Exchange (ETDEWEB)

    SPENCER, S.G.

    1999-04-26

    The Server Project is to ensure that all TWRS supporting hardware (fileservers and workstations) will not cause a system failure because of the BIOS or Operating Systems cannot process Year 2000 dates.

  6. Tank waste remediation system year 2000 dedicated file server project HNF-3418 project plan

    International Nuclear Information System (INIS)

    SPENCER, S.G.

    1999-01-01

    The Server Project is to ensure that all TWRS supporting hardware (fileservers and workstations) will not cause a system failure because of the BIOS or Operating Systems cannot process Year 2000 dates

  7. Radioactive Tank Waste Remediation Focus Area. Technology summary

    International Nuclear Information System (INIS)

    1995-06-01

    In February 1991, DOE's Office of Technology Development created the Underground Storage Tank Integrated Demonstration (UST-ID), to develop technologies for tank remediation. Tank remediation across the DOE Complex has been driven by Federal Facility Compliance Agreements with individual sites. In 1994, the DOE Office of Environmental Management created the High Level Waste Tank Remediation Focus Area (TFA; of which UST-ID is now a part) to better integrate and coordinate tank waste remediation technology development efforts. The mission of both organizations is the same: to focus the development, testing, and evaluation of remediation technologies within a system architecture to characterize, retrieve, treat, concentrate, and dispose of radioactive waste stored in USTs at DOE facilities. The ultimate goal is to provide safe and cost-effective solutions that are acceptable to both the public and regulators. The TFA has focused on four DOE locations: the Hanford Site in Richland, Washington, the Idaho National Engineering Laboratory (INEL) near Idaho Falls, Idaho, the Oak Ridge Reservation in Oak Ridge, Tennessee, and the Savannah River Site (SRS) in Aiken, South Carolina

  8. Notice of Construction for Tank Waste Remediation System Vadose Zone Characterization

    Energy Technology Data Exchange (ETDEWEB)

    HILL, J.S.

    2000-04-20

    The following description and any attachments and references are provided to the Washington State Department of Health (WDOH), Division of Radiation Protection, Air Emissions and Defense Waste Section as a notice of construction (NOC) in accordance with Washington Administrative Code (WAC) 246-247, Radiation Protection-Air Emissions. The WAC 246-247-060, ''Applications, registration, and licensing'', states ''This section describes the information requirements for approval to construct, modify, and operate an emission unit. Any NOC requires the submittal of information listed in Appendix A.'' Appendix A (WAC 246-247-1 10) lists the requirements that must be addressed. The original NOC was submitted in May of 1999 as DOm-99-34. Additionally, the following description, attachments and references are provided to the U.S. Environmental Protection Agency (EPA) as an NOC, in accordance with Title 40 Code of Federal Regulations (CFR), Part 61, ''National Emission Standards for Hazardous Air Pollutants.'' The information required for submittal to the EPA is specified in 40 CFR 61.07. The potential emissions from this activity are estimated to provide less than 0.1 milliredyear total effective dose equivalent (TEDE) to the hypothetical offsite maximally exposed individual (MEI), and commencement is needed within a short time frame. Therefore, this application is also intended to provide notification of the anticipated date of initial start-up in accordance with the requirement listed in 40 CFR 61.09(a)(1), and it is requested that approval of this application will also constitute EPA acceptance of this initial start-up notification. Written notification of the actual date of initial startup, in accordance with the requirement listed in 40 CFR 61.09(a)(2) will be provided at a later date. This NOC covers the activities associated with vadose zone characterization within the Single-Shell Tank Farms located in the 200

  9. Notice of Construction for Tank Waste Remediation System Vadose Zone Characterization

    Energy Technology Data Exchange (ETDEWEB)

    HILL, J.S.

    2000-03-08

    The following description and any attachments and references are provided to the Washington State Department of Health (WDOH), Division of Radiation Protection, Air Emissions & Defense Waste Section as a notice of construction (NOC) in accordance with Washington Administrative Code (WAC) 246-247, Radiation Protection--Air Emissions. The WAC 246-247-060, ''Applications, registration, and licensing'', states ''This section describes the information requirements for approval to construct, modify, and operate an emission unit. Any NOC requires the submittal of information listed in Appendix A,'' Appendix A (WAC 246-247-1 10) lists the requirements that must be addressed. The original NOC was submitted in May of 1999 as DOE/TU-99-34. Additionally, the following description, attachments and references are provided to the U.S. Environmental Protection Agency (EPA) as an NOC, in accordance with Title 40 Code of Federal Regulations (CFR), Part 61, ''National Emission Standards for Hazardous Air Pollutants.'' The information required for submittal to the EPA is specified in 40 CFR 61.07. The potential emissions from this activity are estimated to provide less than 0.1 millirem/year total effective dose equivalent (TEDE) to the hypothetical offsite maximally exposed individual (MEI), and commencement is needed within a short time frame. Therefore, this application is also intended to provide notification of the anticipated date of initial startup in accordance with the requirement listed in 40 CFR 61.09(axl), and it is requested that approval of this application will also constitute EPA acceptance of this initial start-up notification. Written notification of the actual date of initial startup, in accordance with the requirement listed in 40 CFR 61.09(a)(2) will be provided at a later date. This NOC covers the activities associated with vadose zone characterization within the Single-Shell Tank Farms located in the

  10. Notice of Construction for Tank Waste Remediation System Vadose Zone Characterization

    International Nuclear Information System (INIS)

    HILL, J.S.

    2000-01-01

    The following description and any attachments and references are provided to the Washington State Department of Health (WDOH), Division of Radiation Protection, Air Emissions and Defense Waste Section as a notice of construction (NOC) in accordance with Washington Administrative Code (WAC) 246-247, Radiation Protection--Air Emissions. The WAC 246-247-060, ''Applications, registration, and licensing'', states ''This section describes the information requirements for approval to construct, modify, and operate an emission unit. Any NOC requires the submittal of information listed in Appendix A,'' Appendix A (WAC 246-247-1 10) lists the requirements that must be addressed. The original NOC was submitted in May of 1999 as DOE/TU-99-34. Additionally, the following description, attachments and references are provided to the U.S. Environmental Protection Agency (EPA) as an NOC, in accordance with Title 40 Code of Federal Regulations (CFR), Part 61, ''National Emission Standards for Hazardous Air Pollutants.'' The information required for submittal to the EPA is specified in 40 CFR 61.07. The potential emissions from this activity are estimated to provide less than 0.1 millirem/year total effective dose equivalent (TEDE) to the hypothetical offsite maximally exposed individual (MEI), and commencement is needed within a short time frame. Therefore, this application is also intended to provide notification of the anticipated date of initial startup in accordance with the requirement listed in 40 CFR 61.09(axl), and it is requested that approval of this application will also constitute EPA acceptance of this initial start-up notification. Written notification of the actual date of initial startup, in accordance with the requirement listed in 40 CFR 61.09(a)(2) will be provided at a later date. This NOC covers the activities associated with vadose zone characterization within the Single-Shell Tank Farms located in the 200-East and 200-West Areas of the Hanford Site. Vadose zone

  11. Tank waste remediation system privatization infrastructure program configuration management implementation plan

    International Nuclear Information System (INIS)

    Schaus, P.S.

    1998-01-01

    This Configuration Management Implementation Plan (CMIP) was developed to assist in managing systems, structures, and components (SSCS), to facilitate the effective control and statusing of changes to SSCS, and to ensure technical consistency between design, performance, and operational requirements. Its purpose is to describe the approach Privatization Infrastructure will take in implementing a configuration management program, to identify the Program's products that need configuration management control, to determine the rigor of control, and to identify the mechanisms for that control

  12. An overview on emerging bioelectrochemical systems (BESs): Technology for sustainable electricity, waste remediation, resource recovery, chemical production and beyond

    NARCIS (Netherlands)

    Bajracharya, S.; Sharma, M.; Mohanakrishna, Gunda; Benneton, Xochitl Dominguez; Strik, D.P.B.T.B.; Sarma, Priyangshu M.; Pant, Deepak

    2016-01-01

    Bioelectrochemical systems (BESs) are unique systems capable of converting chemical energy into electrical energy (and vice-versa) while employing microbes as catalysts. Such organic wastes including low-strength wastewaters and lignocellulosic biomass were converted into electricity with microbial

  13. Development of the Remedial Action Priority System: an improved risk assessment tool for prioritizing hazardous and radioactive-mixed waste disposal sites

    International Nuclear Information System (INIS)

    Whelan, G.; Strenge, D.L.; Steelman, B.L.; Hawley, K.A.

    1985-08-01

    The Remedial Action Priority System (RAPS) represents a methodology that prioritizes inactive hazardous and radioactive mixed-waste disposal sites in a scientific and objective manner based on limited site information. This methodology is intended to bridge the technology gap that exists between the initial site evaluation using the Hazard Ranking System (HRS) and the time-consuming process of actual field site characterization, assessment, and remediation efforts. The HRS was designed as an initial screening tool to discriminate between hazardous waste sites that do not and those that are likely to pose significant problems to human health, safety, and/or the environment. The HRS is used by the US Environmental Protection Agency to identify sites for nomination to the National Priorites List (NPL). Because the HRS is not designed to evaluate sites containing radionuclides, a modified Hazard Ranking System (mHRS) addressing both hazardous and radioactive mixed wastes was developed by Pacific Northwest Laboratory (PNL) for the US Department of Energy (DOE). Neither the HRS nor the mHRS was designed to prioritize sites that are nominated to the NPL according to their potential risks. 15 refs., 6 figs., 3 tabs

  14. Rail transportation of Fernald remediation waste

    International Nuclear Information System (INIS)

    Fellman, R.T.; Lojek, D.A.; Motl, G.P.; Weddendorf, W.K.

    1995-01-01

    Remediation of the Department of Energy (DOE) Fernald site located north of Cincinnati will generate large quantities of low-level radwaste. This volume includes approximately 1,050,000 tons of material to be removed from eight waste pits comprising Operable Unit 1 (OU-1). The remedial alternative selected includes waste material excavation, drying and transportation by rail to a burial site in the arid west for disposal. Rail transportation was selected not only because rail transportation is safer than truck transportation, but also because of the sheer magnitude of the project and the availability of bulk rail car unloading facilities at a representative disposal site. Based upon current waste quantity estimates as presented in the Feasibility Study for OUI, a fully-loaded 47-car unit train would depart the Fernald site weekly for five years. This paper illustrates the steps taken to obtain agency and public acceptance of the Record of Decision for the remedy which hinged on rail transportation. A preliminary, but detailed, rail transportation plan was prepared for the project to support a series of CERCLA public meetings conducted in late 1994. Some of the major issues addressed in the plan included the following: (1) Scope of project leading to selection of rail transportation; (2) Waste classification; (3) Rail Company overview; (4) Train configuration and rail car selection; (5) Routing; (6) Safety; (7) Prior Notification Requirements (8) Emergency Response. A series of three public meetings identified a number of issues of prime concern to Fernald stakeholders. Following resolution of these issues during the public comment period, a Record of Decision (ROD) approving implementation of the rail transportation strategy was approved pending incorporation of EPA and State of Ohio comments on December 22, 1994

  15. Privatization considerations of environmental remediation of DOE wastes

    International Nuclear Information System (INIS)

    Zocher, M.A.; Paananen, O.H.; Kost, K.

    1997-01-01

    The US Department of Energy (DOE) is in the process of privatizing the application of environmental cleanup technologies to remediate nuclear waste within the DOE complex. These wastes are the legacy of the production of nuclear materials during the cold war era. It is anticipated that the privatization strategy will result in more efficient and less expensive approaches to the cleanup of DOE wastes. Similar privatization initiatives have the potential to achieve increased efficiency and cost savings at sites under the Department of Defense (DOD) and other Federal agencies. The DOE is privatizing a major, complex portion of the Tank Waste Remediation System (TWRS) Program at the Hanford nuclear reservation located in eastern Washington State. This effort will involve private companies that will design, permit, construct, operate, and finally deactivate waste treatment facilities that will be owned entirely by the private sector. The DOE will purchase treated waste products on a unit cost basis from the facilities after supplying the vendors with waste from the tank farm at Hanford. The privatization of selected United States and international Government functions involve decisions that are based on accurate and valid cost information. Private firms are beginning to privatize certain corporate activities so that they may concentrate business activities along main product or mission lines. In either the public or private sector, many aspects of cost engineering are utilized to make prioritization a success

  16. Remediating the INEL's buried mixed waste tanks

    International Nuclear Information System (INIS)

    Kuhns, D.J.; Matthern, G.E.; Reese, C.L.

    1996-01-01

    The Idaho National Engineering Laboratory (INEL), formerly the National Reactor Testing Station (NRTS), encompasses 890 square miles and is located in southeast Idaho. In 1949, the United States Atomic Energy Commission, now the Department of Energy (DOE), established the NRTS as a site for the building and testing of nuclear facilities. Wastes generated during the building and testing of these nuclear facilities were disposed within the boundaries of the site. These mixed wastes, containing radionuclides and hazardous materials, were often stored in underground tanks for future disposal. The INEL has 11 buried mixed waste storage tanks regulated under the Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) ranging in size from 400 to 50,000 gallons. These tanks are constructed of either stainless or carbon steel and are located at 3 distinct geographic locations across the INEL. These tanks have been grouped based on their similarities in an effort to save money and decrease the time required to complete the necessary remediation. Environmental Restoration and Technology Development personnel are teaming in an effort to address the remediation problem systematically

  17. Remedial action and waste disposal project -- 300-FF-1 remedial action readiness assessment report

    International Nuclear Information System (INIS)

    Carson, J.W.; Carlson, R.A.; Greif, A.A.; Johnson, C.R.; Orewiler, R.I.; Perry, D.M.; Remsen, W.E.; Tuttle, B.G.; Wilson, R.C.

    1997-09-01

    This report documents the readiness assessment for initial startup of the 300-FF-1 Remedial Action Task. A readiness assessment verifies and documents that field activities are ready to start (or restart) safely. The 300-FF-1 assessment was initiated in April 1997. Readiness assessment activities included confirming the completion of project-specific procedures and permits, training staff, obtaining support equipment, receipt and approval of subcontractor submittals, and mobilization and construction of site support systems. The scope of the 300-FF-1 Remedial Action Task includes excavation and disposal of contaminated soils at liquid waste disposal facilities and of waste in the 618-4 Burial Ground and the 300-FF-1 landfills. The scope also includes excavation of test pits and test trenches

  18. Surface water management at a mixed waste remediation site

    International Nuclear Information System (INIS)

    Schlotzhauer, D.S.; Warbritton, K.R.

    1991-01-01

    The Weldon Spring Remedial Action Project (WSSRAP) deals with chemical and radiological contaminants. MK-Ferguson Company is managing the project under contract with the US Department of Energy. Remedial activities include demolishing buildings, constructing material storage and staging areas, excavating and consolidating waste materials, and treating and disposing of the materials in a land disposal facility. Due to the excavation and construction required during remediation, a well-planned surface water management system is essential. Planning involves characterization of source areas and surface water transport mechanisms and identification of applicable regulations. System components include: erosion control sediment control, flow attenuation, and management of contaminated water. Combinations of these components may be utilized during actual construction and remediation to obtain optimum control. Monitoring is performed during implementation in order to assess the effectiveness of control measures. This management scheme provides for comprehensive management of surface water at this site by providing control and/or treatment to appropriate standards. Although some treatment methodologies for contaminated water are specific to site contaminants, this comprehensive program provides a management approach which is applicable to many remedial projects in order to minimize contaminant release and meet Clean Water Act requirements

  19. Inorganic ion exchangers for nuclear waste remediation

    Energy Technology Data Exchange (ETDEWEB)

    Clearfield, A.; Bortun, A.; Bortun, L.; Behrens, E. [Texas A& M Univ., College Station, TX (United States)

    1997-10-01

    The objective of this work is to provide a broad spectrum of inorganic ion exchangers that can be used for a range of applications and separations involving remediation of groundwater and tank wastes. The authors intend to scale-up the most promising exchangers, through partnership with AlliedSignal Inc., to provide samples for testing at various DOE sites. While much of the focus is on exchangers for removal of Cs{sup +} and Sr{sup 2+} from highly alkaline tank wastes, especially at Hanford, the authors have also synthesized exchangers for acid wastes, alkaline wastes, groundwater, and mercury, cobalt, and chromium removal. These exchangers are now available for use at DOE sites. Many of the ion exchangers described here are new, and others are improved versions of previously known exchangers. They are generally one of three types: (1) layered compounds, (2) framework or tunnel compounds, and (3) amorphous exchangers in which a gel exchanger is used to bind a fine powder into a bead for column use. Most of these exchangers can be regenerated and used again.

  20. Department of Energy Hazardous Waste Remedial Actions Program

    International Nuclear Information System (INIS)

    Franco, P.J.

    1989-01-01

    This paper discusses the hazardous waste remedial actions program (HAZWRAP) which manages approximately 200 hazardous waste projects. These projects include preliminary assessments, site inspections, and remedial investigation/feasibility studies. The author describes the procedures HAZWRAP follows to ensure quality. The discussion covers the quality assurance aspects of project management, project planning, site characterization, document control and technical teamwork

  1. Environmental remediation of high-level nuclear waste in geological repository. Modified computer code creates ultimate benchmark in natural systems

    International Nuclear Information System (INIS)

    Peter, Geoffrey J.

    2011-01-01

    Isolation of high-level nuclear waste in permanent geological repositories has been a major concern for over 30 years due to the migration of dissolved radio nuclides reaching the water table (10,000-year compliance period) as water moves through the repository and the surrounding area. Repositories based on mathematical models allow for long-term geological phenomena and involve many approximations; however, experimental verification of long-term processes is impossible. Countries must determine if geological disposal is adequate for permanent storage. Many countries have extensively studied different aspects of safely confining the highly radioactive waste in an underground repository based on the unique geological composition at their selected repository location. This paper discusses two computer codes developed by various countries to study the coupled thermal, mechanical, and chemical process in these environments, and the migration of radionuclide. Further, this paper presents the results of a case study of the Magma-hydrothermal (MH) computer code, modified by the author, applied to nuclear waste repository analysis. The MH code verified by simulating natural systems thus, creating the ultimate benchmark. This approach based on processes similar to those expected near waste repositories currently occurring in natural systems. (author)

  2. Remedial action and waste disposal project: 100-B/C remedial action readiness evaluation plan

    International Nuclear Information System (INIS)

    April, J.G.; Bryant, D.L.; Cislo, G.B.

    1996-06-01

    The Readiness Evaluation Plan presents the methodology used to assess the readiness of the 100-B/C Remedial Action Project. The 100 Areas Remedial Action Project will remediate the 100 Areas liquid waste site identified in the Interim Action Record of Decision for the 100- BC-1, 100-DR-1, and 100-HR-1 Operable Units. These sites are located in the 100 Area of the Hanford Site in Richland, Washington

  3. Remedial action and waste disposal project -- 300-FF-1 remedial action readiness assessment plan

    International Nuclear Information System (INIS)

    April, J.G.; Carlson, R.A.; Greif, A.A.; Johnson, C.R.; Orewiler, R.I.; Perry, D.M.; Plastino, J.C.; Roeck, F.V.; Tuttle, B.G.

    1997-04-01

    This Readiness Assessment Plan presents the methodology used to assess the readiness of the 300-FF-1 Remedial Action Project. Remediation involves the excavation, treatment if applicable, and final disposal of contaminated soil and debris associated with the waste sites in the 300-FF-1 Operable Unit. The scope of the 300-FF-1 remediation is to excavate, transport, and dispose of contaminated solid from sites identified in the 300-FF-1 Operable Unit

  4. Remediation of hazardous waste sites by heap leaching

    International Nuclear Information System (INIS)

    Samani, Z.; Hanson, A.; Dwyer, B.

    1994-01-01

    Efforts are being made to devise technologies and treatment systems to remediate contaminated soil-on site without generating significant wastes for off-site disposal. Heap leaching, a technique used extensively in the mining industry, has been investigated as a method for remediation of hazardous chemical contamination of the vadose zone. In the mining industry, metal-bearing ore is excavated and mounded on a pad. The metals are removed by passing a special leaching solution through the ore. In this study, the removal of chromium(VI) from the New Mexico soils (sand, sandy loam, and clay) using heap leaching was evaluated at a column scale. The heap leaching study demonstrated greater than 99% removal of Cr(VI) from all three soils using tap water as the leaching agent. (author) 13 figs., 5 tabs., 21 refs

  5. Remedial action and waste disposal project: 100-DR-1 remedial action readiness evaluation plan

    International Nuclear Information System (INIS)

    April, J.G.; Bryant, D.L.; Calverley, C.

    1996-08-01

    This plan presents the method used to assess the readiness of the 100- DR-1 Remedial Action Project. Remediation of the 100-D sites (located on the Hanford Site) involves the excavation (treatment if applicable) and final disposal of contaminated soil and debris associated with the high-priority waste sites in the 100 Areas

  6. The Sonophysics and Sonochemistry of Liquid Waste Quantification and Remediation

    Energy Technology Data Exchange (ETDEWEB)

    Matula, Thomas J.

    1998-06-01

    This research is being conducted to (a) perform an in-depth and comprehensive study of the fundamentals of acoustic cavitation and nonlinear bubble dynamics, (b) elucidate the fundamental physics of sonochemical reactions, (c) examine the potential of sonoluminescence to quantify and monitor the presence of alkali metals and other elements in waste liquids, (d) design and evaluate more effective sonochemical reactors for waste remediation, and (e) determine the optimal acoustical parameters in the use of sonochemistry for liquid-waste-contaminant remediation. So far cells have been designed for multibubble sonoluminescence (MBSL) and single-bubble sonoluminescence (SBSL) spectroscopy experiments. Positive results have been obtained in both systems using a Raman system which covers the wavelength range from 790 to 1,070 nm. Further progress from year-1 involved the use of the newly discovered technique of changing the pressure head above the cavitation field to increase the light emission from MBSL. A second method for changing the pressure head involves pressure-jumping, whereby the pressure in the head space above the solution is quickly increased to a new steady value.

  7. Technology needs and trends for hazardous waste site remediation

    International Nuclear Information System (INIS)

    Kovalick, W.W. Jr.

    1995-01-01

    Over the next few decades, federal, state, and local governments and private industry will commit billions of dollars annually to clean up sites contaminated with hazardous waste and petroleum products. While these needs represent an obligation for society, they also represent an important business opportunity for vendors of remediation services. This presentation assesses the remediation market by characterizing sites that comprise the demand for cleanup services, observing remedy selection trends in the Superfund program, and discussing gaps in the supply of technologies

  8. Effectiveness of interim remedial actions at a radioactive waste facility

    International Nuclear Information System (INIS)

    Devgun, J.S.; Beskid, N.J.; Peterson, J.M.; Seay, W.M.; McNamee, E.

    1989-01-01

    Over the past eight years, several interim remedial actions have been taken at the Niagara Falls Storage Site (NFSS), primarily to reduce radon and gamma radiation exposures and to consolidate radioactive waste into a waste containment facility. Interim remedial actions have included capping of vents, sealing of pipes, relocation of the perimeter fence (to limit radon risk), transfer and consolidation of waste, upgrading of storage buildings, construction of a clay cutoff wall (to limit the potential groundwater transport of contaminants), treatment and release of contaminated water, interim use of a synthetic liner, and emplacement of an interim clay cap. An interim waste containment facility was completed in 1986. 6 refs., 3 figs

  9. Tank Waste Remediation System fiscal year 1996 multi-year program plan WBS 1.1. Revision 1, Volume 1

    International Nuclear Information System (INIS)

    1995-09-01

    The 1995 Hanford Mission Plan specifically addresses the tank waste issue and clarifies the link with other initiatives, such as improving management practices and the Hanford Site Waste Minimization and Pollution Prevention Awareness Program Plan (DOE/RL-91-31). This document captures the results of decision making regarding the application of systems engineering at the Hanford Site, external involvement policy, and site end-state goals. Section 3.5 of the Hanford Mission Plan on Decisions and Directives provides an integrating discussion of the actions of the National Environmental Policy Act (NEPA), and DOE policy, guidance, and decisions associated with binding agreements such as the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement). Two significant components of the Hanford Mission Plan 1994 planning basis are (1) the decisions regarding the disposition of onsite material inventory, and the key programs and interfaces to accomplish this; and (2) the Program Interface Issues section, which identified issues that stretch across program boundaries

  10. Remediation of the Provisional Storage of Radioactive Waste near Zavratec

    International Nuclear Information System (INIS)

    Zeleznik, N.; Mele, I.

    1998-01-01

    In 1996 the remediation of the provisional storage situated near village Zavratec in western part of Slovenia started. In this storage radioactive waste contaminated with radium has been stored for many decades The RAO Agency organized remedial works, in which these activities inventorying and repacking of radioactive waste were carried out. Simultaneously with these activities a detailed programme for covering public relations was prepared and implemented. On the basis of the experimental results and general storage conditions relocation of radioactive waste to the Slovenian central storage was recommended and it is planned to be concluded by the end of 1998. In this paper main remedial activities in the provisional storage of radioactive waste near Zavratec are presented. An important and most challenging part of these activities represent PR activities. (author)

  11. Automated remedial assessment methodology software system

    International Nuclear Information System (INIS)

    Whiting, M.; Wilkins, M.; Stiles, D.

    1994-11-01

    The Automated Remedial Analysis Methodology (ARAM) software system has been developed by the Pacific Northwest Laboratory to assist the U.S. Department of Energy (DOE) in evaluating cleanup options for over 10,000 contaminated sites across the DOE complex. The automated methodology comprises modules for decision logic diagrams, technology applicability and effectiveness rules, mass balance equations, cost and labor estimating factors and equations, and contaminant stream routing. ARAM is used to select technologies for meeting cleanup targets; determine the effectiveness of the technologies in destroying, removing, or immobilizing contaminants; decide the nature and amount of secondary waste requiring further treatment; and estimate the cost and labor involved when applying technologies

  12. Electrodialytic remediation of CCA treated waste wood in pilot scale

    DEFF Research Database (Denmark)

    Pedersen, Anne Juul; Christensen, Iben Vernegren; Ottosen, Lisbeth M.

    2005-01-01

    study the utility of the method Electrodialytic Remediation was demonstrated for handling of CCA treated waste wood in pilot scale. The electrodialytic remediation method, which uses a low level DC current as the cleaning agent, combines elektrokinetic movement of ions in the wood matrix with the princi......-ples of electrodialysis. It has previously been shown that it is possible to remove Cu, Cr and As from CCA treated wood using electrodialytic remediation in laboratory scale (Ribeiro et al., 2000; Kristensen et al., 2003), but until now, the method had not been studied in larger scale. The pilot scale plant used...... in this study was designed to contain up to 2 m3 wood chips. Six remediation experiments were carried out. In these experiments, the process was up-scaled stepwise by increasing the distance between the electrodes from initially 60 cm to fi-nally 150 cm. The remediation time was varied between 11 and 21 days...

  13. Plasma filtering techniques for nuclear waste remediation.

    Science.gov (United States)

    Gueroult, Renaud; Hobbs, David T; Fisch, Nathaniel J

    2015-10-30

    Nuclear waste cleanup is challenged by the handling of feed stocks that are both unknown and complex. Plasma filtering, operating on dissociated elements, offers advantages over chemical methods in processing such wastes. The costs incurred by plasma mass filtering for nuclear waste pretreatment, before ultimate disposal, are similar to those for chemical pretreatment. However, significant savings might be achieved in minimizing the waste mass. This advantage may be realized over a large range of chemical waste compositions, thereby addressing the heterogeneity of legacy nuclear waste. Copyright © 2015 Elsevier B.V. All rights reserved.

  14. Development of a waste minimization plan for a Department of Energy remedial action program: Ideas for minimizing waste in remediation scenarios

    International Nuclear Information System (INIS)

    Hubbard, Linda M.; Galen, Glen R.

    1992-01-01

    Waste minimization has become an important consideration in the management of hazardous waste because of regulatory as well as cost considerations. Waste minimization techniques are often process specific or industry specific and generally are not applicable to site remediation activities. This paper will examine ways in which waste can be minimized in a remediation setting such as the U.S. Department of Energy's Formerly Utilized Sites Remedial Action Program, where the bulk of the waste produced results from remediating existing contamination, not from generating new waste. (author)

  15. Process for remediation of plastic waste

    Science.gov (United States)

    Pol, Vilas G [Westmont, IL; Thiyagarajan, Pappannan [Germantown, MD

    2012-04-10

    A single step process for degrading plastic waste by converting the plastic waste into carbonaceous products via thermal decomposition of the plastic waste by placing the plastic waste into a reactor, heating the plastic waste under an inert or air atmosphere until the temperature of 700.degree. C. is achieved, allowing the reactor to cool down, and recovering the resulting decomposition products therefrom. The decomposition products that this process yields are carbonaceous materials, and more specifically egg-shaped and spherical-shaped solid carbons. Additionally, in the presence of a transition metal compound, this thermal decomposition process produces multi-walled carbon nanotubes.

  16. Remediating while preserving wetland habitat at an LLR waste site in Canada

    International Nuclear Information System (INIS)

    Kleb, H.R.; Zelmer, R.L.

    2007-01-01

    The Low-Level Radioactive Waste Management Office was established in 1982 to carry out the federal government's responsibilities for low-level radioactive (LLR) waste management in Canada. The Office operates programs to characterize, delineate, decontaminate and consolidate historic LLR waste for interim and long-term storage. In this capacity, the Office is currently considering the remediation of 9,000 cubic metres of contaminated sediment in a coastal marsh in the context of a major remediation project involving multiple urban sites. The marsh is situated between the Lake Ontario shoreline and the urban fringe of the Town of Port Hope. The marsh is designated a Cattail Mineral Shallow Marsh under the Ecological Land Classification system for Southern Ontario and was recently named the A.K. Sculthorpe Marsh in memory of a local community member. The marsh remediation will therefore require trade off between the disruption of a sensitive wetland and the removal of contaminated sediment. This paper discusses the issues and trade-off relating to the waste characterization, environmental assessment and regulatory findings and thus the remediation objectives for the marsh. Considerations include the spatial distribution of contaminated sediment, the bioavailability of contaminants, the current condition of the wetland and the predicted effects of remediation. Also considered is the significance of the wetland from provincial and municipal regulatory perspectives and the resulting directives for marsh remediation. (authors)

  17. Tank waste remediation system retrieval and disposal mission readiness-to-proceed responses to internal independent assessment

    International Nuclear Information System (INIS)

    Schaus, P.S.

    1998-01-01

    The US Department of Energy (DOE) is planning to make critical decisions during fiscal year (FY) 1998 regarding privatization contracts for the treatment of Hanford tank waste. Specifically, DOE, Richland Operations Office (RL), will make decisions related to proceeding with Phase 1 Privatization. In support of these decisions, the management and integration (M+I) contractor must be able to meet the requirements to support the Phase 1 privatization contractors. As part of the assessment of the Tank Waste Retrieval (TWR) Readiness-To-Proceed (RTP), an independent review of their process and products was required by the RL letter of August 8, 1997. The Independent Review Team reviewed the adequacy of the planning that has been done by the M+I contractor to validate that, if the plans are carried out, there is reasonable assurance of success. Overall, the RTP Independent Review Team concluded that, if the planning by the M+I contractor team is carried out with adequate funding, there is reasonable assurance that the M+I contractor will be able to deliver waste to the privatization contractor for the duration of Phase 1. This conclusion was based on addressing the recommendations contained in the Independent Review Team's Final Report and in the individual Criteria and Review Approach (CRA) forms completed during the assessment. The purpose of this report is to formally document the independent assessment and the RTP team responses to the Independent Review Team recommendations. It also provides closure logics for selected recommendations from a Lockheed Martin Hanford Corporation (LMHC) internal assessment of the Technical Basis Review (TBR) packages. This report contains the RTP recommendation closure process (Section 2.0); the closure tables (Section 3.0) which provide traceability between each review team recommendation and its corresponding Project Hanford Management Contract closure logic; and two attachments that formally document the Independent Review Team

  18. Remedial Action and Waste Disposal Project Manager's Implementing Instructions

    International Nuclear Information System (INIS)

    Dronen, V.R.

    1998-01-01

    These Project Manager's Implementing Instructions provide the performance standards required of all Environmental Restoration Contractor personnel in their work during operation and administration of the Remedial Action and Waste Disposal Project. The instructions emphasize technical competency, workplace discipline, and personal accountability to ensure a high level of safety and performance during operations activities

  19. Buried waste remediation: A new application for in situ vitrification

    International Nuclear Information System (INIS)

    Kindle, C.H.; Thompson, L.E.

    1991-04-01

    Buried wastes represent a significant environmental concern and a major financial and technological challenge facing many private firms, local and state governments, and federal agencies. Numerous radioactive and hazardous mixed buried waste sites managed by the US Department of Energy (DOE) require timely clean up to comply with state or federal environmental regulations. Hazardous wastes, biomedical wastes, and common household wastes disposed at many municipal landfills represent a significant environmental health concern. New programs and regulations that result in a greater reduction of waste via recycling and stricter controls regarding generation and disposal of many wastes will help to stem the environmental consequences of wastes currently being generated. Groundwater contamination, methane generation, and potential exposures to biohazards and chemically hazardous materials from inadvertent intrusion will continue to be potential environmental health consequences until effective and permanent closure is achieved. In situ vitrification (ISV) is being considered by the DOE as a permanent closure option for radioactive buried waste sites. The results of several ISV tests on simulated and actual buried wastes conducted during 1990 are presented here. The test results illustrate the feasibility of the ISV process for permanent remediation and closure of buried waste sites in commercial landfills. The tests were successful in immobilizing or destroying hazardous and radioactive contaminants while providing up to 75 vol % waste reduction. 6 refs., 7 figs., 5 tabs

  20. The Remedial Action Priority System (RAPS): Mathematical formulations

    International Nuclear Information System (INIS)

    Whelan, G.; Strenge, D.L.; Droppo, J.G. Jr.; Steelman, B.L.; Buck, J.W.

    1987-08-01

    The Remedial Action Priority System (RAPS) represents a methodology that prioritizes inactive hazardous and radioactive mixed-waste disposal sites in a scientific and objective manner based on limited site information. This methodology is intended to bridge the technology gap between the initial site evaluation using the Hazard Ranking System (HRS) and the time-consuming process of actual field site characterization, assessment, and remediation efforts. The RAPS methodology provides the US Department of Energy with a management tool for assistance in prioritizing funding and human resource allocations for further investigations and possible remediations at its inactive waste sites. Use of RAPS will help DOE ensure that those sites posing the highest potential risk are addressed first. Chapters 1 through 10 were processed separately for the Energy Data Base

  1. Final Hazard Categorization for the Remediation of the 116-C-3 Chemical Waste Tanks

    Energy Technology Data Exchange (ETDEWEB)

    T. M. Blakley; W. D. Schofield

    2007-09-10

    This final hazard categorization (FHC) document examines the hazards, identifies appropriate controls to manage the hazards, and documents the commitments for the 116-C-3 Chemical Waste Tanks Remediation Project. The remediation activities analyzed in this FHC are based on recommended treatment and disposal alternatives described in the Engineering Evaluation for the Remediation to the 116-C-3 Chemical Waste Tanks (BHI 2005e).

  2. Multivariate methods in nuclear waste remediation: Needs and applications

    International Nuclear Information System (INIS)

    Pulsipher, B.A.

    1992-05-01

    The United States Department of Energy (DOE) has developed a strategy for nuclear waste remediation and environmental restoration at several major sites across the country. Nuclear and hazardous wastes are found in underground storage tanks, containment drums, soils, and facilities. Due to the many possible contaminants and complexities of sampling and analysis, multivariate methods are directly applicable. However, effective application of multivariate methods will require greater ability to communicate methods and results to a non-statistician community. Moreover, more flexible multivariate methods may be required to accommodate inherent sampling and analysis limitations. This paper outlines multivariate applications in the context of select DOE environmental restoration activities and identifies several perceived needs

  3. The Use of Waste Materials in the Passive Remediation of Mine Water Polution

    Science.gov (United States)

    Batty, Lesley C.; Younger, Paul L.

    2004-01-01

    The contamination and resulting degradation of water courses by effluents from abandoned and active mines is a world-wide problem. Traditional methods of remediating the discharges from mines involve the addition of chemicals and the utilisation of artificial energy sources. Over the last 15-20 years passive treatment systems have been developed that harness natural chemical and biological processes to ameliorate the potentially toxic effects of such discharges. There are many different types of passive system, including compost wetlands, reducing and alkalinity producing systems (RAPS), permeable reactive barriers and inorganic media passive systems. Different waste materials can be utilised as reactive media within each of these systems, dependent upon the type of mine water and treatment technology. In many cases the reactivity of these recycled waste materials is key to the remedial performance of these systems. The materials used may be organic (e.g., composts) or inorganic (e.g., blast furnace slag) and where possible are sourced locally in order to minimise transport costs. The remediation of mine waters in itself can produce large quantities of waste products in the form of iron oxide sludge. Potential uses of this material in the production of pigments and in the treatment of phosphate contaminated waters is also currently under investigation. The exploitation of what are traditionally thought of as waste materials within treatment systems for polluted waters is an expanding technology which provides great scope for recycling.

  4. World-first PRB remediation system

    International Nuclear Information System (INIS)

    Mundle, Keely

    2013-01-01

    Full text: The permeable reactive barrier (PRB) project in question was a former waste control site at Bellevue in Western Australia, which burned down in 2001. The fire and the site's historic use as a liquid waste treatment plant created a plume of contaminated groundwater as well as a secondary offsite plume of chlorinated solvents. Damage from the fire and historical use caused the contamination to extend 200m downgradient of the site, under several nearby parcels of land and migrating in the direction of the nearby Helena River. Two areas of chlorinated solvents were identified as residual dense non-aqueous phase liquid (DNAPL) in the unsaturated zone, including concentrations of trichloroethene (TCE) at 1000 micrograms per litre (μg/L) in groundwater, which needed to be reduced to concentrations of around 330μg/L before the groundwater discharged into the river. Complete source removal of DNAPL contamination - such as TCE - in the environment can be difficult and costly. Partial source removal of the contamination may not have a significant impact on the extent of the plume but may reduce its longevity. Treatment of the contaminant plume is more achievable and allows for more time to develop an effective source remediation solution if it is required. Zero-valent iron (ZVI), a non-toxic granular material placed in PRBs, has been proven to be successful in removing a broad range of contaminants, including many chlorinated solvents such as TCE. In a ZVI-based PRB, the system uses the natural groundwater flow to channel contaminants to an engineered treatment area. As groundwater passes through the PRB, contaminants are treated in the barrier and remediated water flows out the other side. There are two primary pathways for the dechlorination of chlorinated ethenes in ZVI PRBs: beta-elimination and hydrogenolysis. Experiments have shown the dominant degradation pathway is p-elimination. This pathway is preferred as it results in the chlorinated ethene

  5. The Rush to Remediate: Long Term Performance Favors Passive Systems at SRS

    International Nuclear Information System (INIS)

    Hoffman, D.; Cauthen, K.; Beul, R. R.

    2003-01-01

    The purpose of this paper is to describe the long-term performance of groundwater remediation systems at SRS and compare active versus passive systems. The presentation will focus on the limited effectiveness of active pump and treat systems and share the experience with more passive and natural systems such as soil vapor extraction, barometric pumping, bioremediation, and phytoremediation. Three remediation projects are presented. In each case the waste source is capped with clay or synthetic barriers; however, extensive groundwater contamination remains. The first project features the cleanup of the largest plume in the United States. The second project entails solvent and vinyl chloride remediation of groundwater beneath a hazardous waste landfill. The third project discusses tritium containment from a 160-acre radioactive waste disposal area. Special emphasis is placed on performance data from alternate technology cleanup. The goals are to share remediation data, successes and lessons learned, while making a case for passive systems use in groundwater remediation

  6. Chemical Remediation of Nickel(II) Waste: A Laboratory Experiment for General Chemistry Students

    Science.gov (United States)

    Corcoran, K. Blake; Rood, Brian E.; Trogden, Bridget G.

    2011-01-01

    This project involved developing a method to remediate large quantities of aqueous waste from a general chemistry laboratory experiment. Aqueous Ni(II) waste from a general chemistry laboratory experiment was converted into solid nickel hydroxide hydrate with a substantial decrease in waste volume. The remediation method was developed for a…

  7. Water treatment technologies for a mixed waste remedial action

    Energy Technology Data Exchange (ETDEWEB)

    Reith, C; Freeman, G [Weldon Spring Site Remedial Action Project, Jacobs Engineering Group, Inc., St. Charles, MO (United States); Ballew, B [Weldon Spring Site Remedial Action Project, Dames and Moore, St. Charles, MO (United States)

    1992-07-01

    Water treatment is an important element of the Weldon Spring Site Remedial Action Project (WSSRAP), which is cleaning up a former uranium processing plant near St. Louis, Missouri. This project, under the management of the U.S. Department of Energy (DOE), includes treatment and release of contaminated surface water and possibly groundwater at the plant site and a nearby quarry, which was once used for waste disposal. The contaminants include uranium, thorium, radium, nitroaromatics, nitrates, and metals. Three water treatment plants will be used to treat contaminated water prior to its release to the Missouri River. The first, construction of which is nearly complete, will treat contaminated surface water and interstitial water in and around the quarry. A stepwise process of sedimentation, clarification, filtration, adsorption, and ion exchange will be used to remove the contaminants. A similar sequence will be used for the first train of the water treatment plant at the plant site, although process details have been adjusted to address the different contaminant concentrations. The site water treatment plant will also have a second train consisting of a vapor compression/ distillation (VCD) system. Train 2 is necessary to treat waters primarily from four raffinate pits containing high concentrations of inorganics (e.g., nitrates, sulfates, and chlorides) in addition to radionuclides, nitroaromatics, and metals contamination that are common in most of the waters at the site. Construction is under way on the First train of this facility. After it is treated, all water will be impounded and batch tested for compliance with the project's National Pollution Discharge Elimination System (NPDES) permits prior to release to the Missouri River. The third water treatment plant is a mobile system that will be used to treat waters in some of the building sumps. (author)

  8. Water treatment technologies for a mixed waste remedial action

    International Nuclear Information System (INIS)

    Reith, C.; Freeman, G.; Ballew, B.

    1992-01-01

    Water treatment is an important element of the Weldon Spring Site Remedial Action Project (WSSRAP), which is cleaning up a former uranium processing plant near St. Louis, Missouri. This project, under the management of the U.S. Department of Energy (DOE), includes treatment and release of contaminated surface water and possibly groundwater at the plant site and a nearby quarry, which was once used for waste disposal. The contaminants include uranium, thorium, radium, nitroaromatics, nitrates, and metals. Three water treatment plants will be used to treat contaminated water prior to its release to the Missouri River. The first, construction of which is nearly complete, will treat contaminated surface water and interstitial water in and around the quarry. A stepwise process of sedimentation, clarification, filtration, adsorption, and ion exchange will be used to remove the contaminants. A similar sequence will be used for the first train of the water treatment plant at the plant site, although process details have been adjusted to address the different contaminant concentrations. The site water treatment plant will also have a second train consisting of a vapor compression/ distillation (VCD) system. Train 2 is necessary to treat waters primarily from four raffinate pits containing high concentrations of inorganics (e.g., nitrates, sulfates, and chlorides) in addition to radionuclides, nitroaromatics, and metals contamination that are common in most of the waters at the site. Construction is under way on the First train of this facility. After it is treated, all water will be impounded and batch tested for compliance with the project's National Pollution Discharge Elimination System (NPDES) permits prior to release to the Missouri River. The third water treatment plant is a mobile system that will be used to treat waters in some of the building sumps. (author)

  9. Program summary for the Office of Remedial Action and Waste Technology

    International Nuclear Information System (INIS)

    1989-10-01

    The US Department of Energy is the lead Federal agency responsible for planning and implementing the programs that ensure safe and efficient management of nuclear wastes from both civilian and defense activities. Within the Department, three offices share this responsibility: the Office of Remedial Action and Waste Technology, the Office of Civilian Radioactive Waste Management, and the Office of Defense Waste and Transportation Management. This document summarizes the programs managed by the Office of Remedial Action and Waste Technology

  10. Waste Information Data System user guide

    International Nuclear Information System (INIS)

    Dietz, L.A.

    1996-09-01

    The Waste Information Data System (also known as the Environmental Sites Database) is a computerized system that provides a traceable source of information about environmental waste sites at the U.S. Department of Energy's Hanford Site in Richland, Washington. The system includes discovery, rejected, and accepted waste sites. The purpose of the system is to assist long-range waste management and environmental restoration planning by providing validated and reliable information about waste sites. The system is used to track site investigation, remediation, and closure-action activities

  11. Briefing paper -- Remedial Action Assessment System

    International Nuclear Information System (INIS)

    Buelt, J.L.

    1990-04-01

    Congress has mandated a more comprehensive management of hazardous wastes with the Resource Conservation and Recovery Act (RCRA), the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA or ''Superfund'') and the Superfund Amendment and Reauthorization Act (SARA). This mandate includes restoration of disposal sites contaminated through past disposal practices. This mandate applies to facilities operated for and by the Department of Energy (DOE), just as it does to industrial and other institutions. To help implement the CERCLA/SARA remedial investigation and feasibility study (RI/FS) process in a consistent, timely, and cost-effective manner, a methodology needs to be developed that will allow definition, sorting, and screening of remediation technologies for each operable unit (waste site). This need is stated specifically in Section 2.2.2.1 of the October 1989 Applied Research, Development, Demonstration, Testing, and Evaluation (RDDT ampersand E) Plan of the DOE. This Briefing Paper is prepared to respond to this need. 1 fig

  12. Long-reach manipulation for waste storage tank remediation

    International Nuclear Information System (INIS)

    Jansen, J.F.; Burks, B.L.; Babcock, S.M.; Kress, R.L.; Hamel, W.R.

    1991-01-01

    Remediation of large underground storage tanks containing hazardous waste provides an application for state-of-the-art technology in flexible link manipulator design and control and a need for additional research and development. Application requirements are described, and preliminary analyses associated with this problem are summarized. Inherent physical limitations of flexible manipulators are discussed. Potential kinematic configurations, drive-train elements, and control issues for both free-space motion and damping of forced vibration are addressed. Also included are future directions for research and development in mechanical components and control strategies. 21 refs., 4 figs., 4 tabs

  13. Remediation of the low-level radioactive waste tailing pond at Kowary, Poland

    International Nuclear Information System (INIS)

    Goerner, R.; Hartsch, J.; Koszela, J.; Krzyskow, A.; Machniewicz, B.; Sennewald, R.; Sowa, J.

    2002-03-01

    The last remaining uranium mining tailing pond in Poland, situated at Kowary, was the subject of the Kowary Tailing Pond Remediation Programme financed by Polish public bodies (70%) and by the European Commission (30%) within the framework of its programme of co-operation on radioactive waste issues with candidate countries. The EC-part of the project comprised investigations of the site, project management duties and large-scale civil works following the initial remediation planning performed by the Wroclaw University of Technology (WUT) in 1998-2000. The EC-part was contracted to G.E.O.S. Freiberg Ingenieurgesellschaft mbH following an Open Call for Tender launched by the European Commission in 1999. The following general tasks were performed in close co-operation with WUT, with the construction works subcontracted to local companies, as proposed in the Terms of Reference (TOR) of the EC-part: review of General Remediation Plan (GRP), technical design of the pond cover, construction work: internal drainage system, pond cover and site reclamation. From the information in the TOR, the following aims of remediation were defined: minimise the detrimental impact of the tailing pond on the environment, provide long-term stability of the slopes surrounding the pond, ensure the remediated site is in harmony with the surrounding natural scenery. Based on the experience gathered in similar projects, which had been running under PHARE-MCE or which belonged to the WISMUT-remediation programme in Germany, cost efficient remediation solutions were designed in close co-operation with all involved parties. They were delineated in the detailed planning documents approved in the overall remediation programme managed by WUT. The planned remediation works were prepared and performed successfully according to Polish law and in agreement with the competent local authorities. The aims of remediation were met. However, some additional tasks have been recommended in zones adjacent to the

  14. Glassy slags as novel waste forms for remediating mixed wastes with high metal contents

    International Nuclear Information System (INIS)

    Feng, X.; Wronkiewicz, D.J.; Bates, J.K.; Brown, N.R.; Buck, E.C.; Gong, M.; Ebert, W.L.

    1994-01-01

    Argonne National Laboratory (ANL) is developing a glassy slag final waste form for the remediation of low-level radioactive and mixed wastes with high metal contents. This waste form is composed of various crystalline and metal oxide phases embedded in a silicate glass phase. This work indicates that glassy slag shows promise as final waste form because (1) it has similar or better chemical durability than high-level nuclear waste (HLW) glasses, (2) it can incorporate large amounts of metal wastes, (3) it can incorporate waste streams having low contents of flux components (boron and alkalis), (4) it has less stringent processing requirements (e.g., viscosity and electric conductivity) than glass waste forms, (5) its production can require little or no purchased additives, which can result in greater reduction in waste volume and overall treatment costs. By using glassy slag waste forms, minimum additive waste stabilization approach can be applied to a much wider range of waste streams than those amenable only to glass waste forms

  15. Strategy to develop and test a multi-function scarifier end effector with an integral conveyance system for waste tank remediation

    International Nuclear Information System (INIS)

    Bamberger, J.A.; Bates, J.M.; Keska, J.K.; Elmore, M.R.; Lombardo, N.J.

    1993-08-01

    This strategy plan describes a coupled analytical/experimental approach to develop a multi-functional scarifier end effector coupled with a pneumatic conveyance system to retrieve wastes from underground storage tanks. The scarifier uses ultra-high-pressure water jets to rubblize and entrain waste forms such as salt cake, sludge, and viscous liquid that can be transported pneumatically. The three waste types (hard, brittle, salt cake, viscous liquid, and deformable sludge) present increasingly complex challenges for scarification and pneumatic conveyance. Salt cake is anticipated to be the easiest to retrieve because (1) a theoretical model of hydraulic rock fracture can be applied to estimate jet performance to fracture salt cake, and (2) gas-solids transport correlations can be used to predict pneumatic transport. Deformable sludge is anticipated to be the most difficult to retrieve: no theories, correlations, or data exist to predict this performance. However order-of-magnitude gas-solid correlations indicate particulate wastes of prototypic density can be transported to a height of 20 m within allowable pressure limits provided that the volume fraction of the gaseous phase is kept above 95%. Viscous liquid is anticipated to be of intermediate complexity to retrieve. Phenomena that are expected to affect system performance are ranked. Experiments and analyses necessary to evaluate the effects of these phenomena are proposed. Subsequent strategies for experiment test plans, system deployment, and operation and control will need to be developed

  16. Remediation of phosphorus from electric furnace waste streams

    International Nuclear Information System (INIS)

    Hanna, J.; Jung, J.O.

    1992-01-01

    Electrothermal production of elemental phosphorus (P4) generates substantial amounts of highly toxic phossy water sludge, slag and other gaseous wastes. Because of their high phosphorus content the sludges pose potential fire hazards. In the absence of a reliable processing technology, large amounts of these hazardous wastes are accumulated at an annual rate of 1.5-2.5 million tons from current and past operations. The accumulated sludges are stored in ponds or in special containment vessels in 30 locations in 18 states including Alabama, California, Tennessee, Idaho and Montana. Serious water pollution problems will result unless these wastes are given extensive treatment to remove the elemental phosphorus. Federal regulations prohibit permanent storage of flammable wastes. This paper reports that recently, researchers at the University of Alabama have developed a two-step method for the treatment of phosphorus sludge that includes bulk removal of phosphorus by physical separation techniques followed by remediation of the residual P4 in the sludge using a novel wet air oxidation technique known as HSAD

  17. Soil remediation process and system

    International Nuclear Information System (INIS)

    Monlux, K.J.

    1992-01-01

    This patent describes a process for remediation of soil containing up to about 30,000 ppm hydrocarbon contaminants. It comprises: providing hydrocarbon-contaminated soil in a divided condition of minus 1 1/2 double-prime to a first confined zone where it is exposed to an open flame; heating while agitating the contaminated soil in an oxidizing atmosphere in the first zone to a temperature below soil ignition within a range of from about 375 degrees F. to about 750 degrees F. for a time sufficient to drive off as vapors a substantial percentage of the hydrocarbon contaminates from the soil; passing hot gases containing the hydrocarbon contaminates from the soil; passing hot gases containing the hydrocarbon vapors from the first zone to a second zone; recovering heat from the hot gases in the second zone to condense a substantial percentage of the hydrocarbon vapors as liquid hydrocarbons; recovering the liquid hydrocarbons; and removing the soil from the first zone as remediated soil having below about 1000 ppm hydrocarbon contaminants

  18. Remedial action and waste disposal project -- 100-DR-1 remedial action readiness assessment report

    International Nuclear Information System (INIS)

    April, J.G.; Ard, J.A.; Corpuz, F.M.; DeMers, S.K.; Donahoe, R.L.; Frank, J.M.; Hobbs, B.J.; Roeck, F.V.

    1997-02-01

    This readiness assessment report presents the results of the project readiness assessment for the 100-DR-1 source sites remediation. The assessment was conducted at the conclusion of a series of project activities that began in August 1996. These activities included confirming the completion of project-specific procedures, training of staff, obtaining support equipment, receipt of subcontractor submittals, and mobilization and construction of site support systems

  19. Thermal processing systems for TRU mixed waste

    International Nuclear Information System (INIS)

    Eddy, T.L.; Raivo, B.D.; Anderson, G.L.

    1992-01-01

    This paper presents preliminary ex situ thermal processing system concepts and related processing considerations for remediation of transuranic (TRU)-contaminated wastes (TRUW) buried at the Radioactive Waste Management Complex (RWMC) of the Idaho National Engineering Laboratory (INEL). Anticipated waste stream components and problems are considered. Thermal processing conditions required to obtain a high-integrity, low-leachability glass/ceramic final waste form are considered. Five practical thermal process system designs are compared. Thermal processing of mixed waste and soils with essentially no presorting and using incineration followed by high temperature melting is recommended. Applied research and development necessary for demonstration is also recommended

  20. Fifth international conference on radioactive waste management and environmental remediation -- ICEM '95: Proceedings. Volume 2: Management of low-level waste and remediation of contaminated sites and facilities

    International Nuclear Information System (INIS)

    Slate, S.; Baker, R.; Benda, G.

    1995-01-01

    The objective of this conference is the broad international exchange of information on technologies, operations, management approaches, economics, and public policies in the critical areas of radioactive waste management and environmental remediation. The ICEM '95 technical program includes four parallel program tracks: Low/intermediate-level waste management; High-level waste, spent fuel, nuclear material management; Environmental remediation and facility D and D; and Major institutional issues in environmental management. Volume 2 contains approximately 200 papers divided into the following topical sections: Characterization of low and intermediate level waste; Treatment of low and intermediate level waste; LLW disposal and near-surface contaminant migration; Characterization and remediation of contaminated sites; and Decontamination and decommissioning technologies and experience. Papers have been processed separately for inclusion on the data base

  1. The Department of Energy's Remedial Action Assessment System (RAAS): Decision support tools for performing streamlined feasibility studies

    International Nuclear Information System (INIS)

    White, M.K.

    1994-06-01

    The United States Department of Energy (DOE) faces the major task of cleaning up hundreds of waste sites across the nation, which will require completion of a large number of remedial investigation/feasibility studies (RI/FSs). The intent of each RI/FS is to characterize the waste problems and environmental conditions at the operable unit level, segment the remediation problem into manageable medium-specific and contaminant-specific pieces, define corresponding remediation objectives, and identify remedial response actions to satisfy those objectives. The RI/FS team can then identify combinations of remediation technologies that will meet the remediation objectives. Finally, the team must evaluate these remedial alternatives in terms of effectiveness, implementability, cost, and acceptability. The Remedial Action Assessment System (RAAS) is being developed by Pacific Northwest Laboratory (PNL) to support DOE in this effort

  2. Waste site characterization and remediation: Problems in developing countries

    Energy Technology Data Exchange (ETDEWEB)

    Kalavapudi, M. [ENVIROSYS, Gaithersburg, MD (United States); Iyengar, V. [Biomineral Sciences International Inc., Bethesda, MD (United States)

    1996-12-31

    Increased industrial activities in developing countries have degraded the environment, and the impact on the environment is further magnified because of an ever-increasing population, the prime receptors. Independent of the geographical location, it is possible to adopt effective strategies to solve environmental problems. In the United States, waste characterization and remediation practices are commonly used for quantifying toxic contaminants in air, water, and soil. Previously, such procedures were extraneous, ineffective, and cost-intensive. Reconciliation between the government and stakeholders, reinforced by valid data analysis and environmental exposure assessments, has allowed the {open_quotes}Brownfields{close_quotes} to be a successful approach. Certified reference materials and standard reference materials from the National Institute of Standards (NIST) are indispensable tools for solving environmental problems and help to validate data quality and the demands of legal metrology. Certified reference materials are commonly available, essential tools for developing good quality secondary and in-house reference materials that also enhance analytical quality. This paper cites examples of environmental conditions in developing countries, i.e., industrial pollution problems in India, polluted beaches in Brazil, and deteriorating air quality in countries, such as Korea, China, and Japan. The paper also highlights practical and effective approaches for remediating these problems. 23 refs., 7 figs., 1 tab.

  3. Review: Waste-Pretreatment Technologies for Remediation of Legacy Defense Nuclear Wastes

    Energy Technology Data Exchange (ETDEWEB)

    Wilmarth, William R.; Lumetta, Gregg J.; Johnson, Michael E.; Poirier, Micheal R.; Thompson, Major C.; Suggs, Patricia C.; Machara, N.

    2011-01-13

    The U.S. Department of Energy (DOE) is responsible for retrieving, immobilizing, and disposing of radioactive waste that has been generated during the production of nuclear weapons in the United States. The vast bulk of this waste material is stored in underground tanks at the Savannah River Site in South Carolina and the Hanford Site in Washington State. The general strategy for treating the radioactive tank waste consists of first separating the waste into high-level and low-activity fractions. This initial partitioning of the waste is referred to as pretreatment. Following pretreatment, the high-level fraction will be immobilized in a glass form suitable for disposal in a geologic repository. The low-activity waste will be immobilized in a waste form suitable for disposal at the respective site. This paper provides a review of recent developments in the application of pretreatment technologies to the processing of the Hanford and Savannah River radioactive tank wastes. Included in the review are discussions of 1) solid/liquid separations methods, 2) cesium separation technologies, and 3) other separations critical to the success of the DOE tank waste remediation effort. Also included is a brief discussion of the different requirements and circumstances at the two DOE sites that have in some cases led to different choices in pretreatment technologies.

  4. Gas cylinder disposal pit remediation waste minimization and management

    International Nuclear Information System (INIS)

    Alas, C.A.; Solow, A.; Criswell, C.W.; Spengler, D.; Brannon, R.; Schwender, J.M.; Eckman, C.K.; Rusthoven, T.

    1995-01-01

    A remediation of a gas cylinder disposal pit at Sandia National Laboratories, New Mexico has recently been completed. The cleanup prevented possible spontaneous releases of hazardous gases from corroded cylinders that may have affected nearby active test areas at Sandia's Technical Area III. Special waste management, safety, and quality plans were developed and strictly implemented for this project. The project was conceived from a waste management perspective, and waste minimization and management were built into the planning and implementation phases. The site layout was planned to accommodate light and heavy equipment, storage of large quantities of suspect soil, and special areas to stage and treat gases and reactive chemicals removed from the pit, as well as radiation protection areas. Excavation was a tightly controlled activity using experienced gas cylinder and reactive chemical specialists. Hazardous operations were conducted at night under lights, to allow nearby daytime operations to function unhindered. The quality assurance plan provided specific control of, and documentation for, critical decisions, as well as the record of daily operations. Both hand and heavy equipment excavation techniques were utilized. Hand excavation techniques were utilized. Hand excavation techniques allows sealed glass containers to be exhumed unharmed. In the end, several dozen thermal batteries; 5 pounds (2.3 kg) of lithium metal; 6.6 pounds (3.0 kg) of rubidium metal; several kilograms of unknown chemicals; 140 cubic yards (107 cubic meters) of thorium-contaminated soil; 270 cubic yards (205 cubic meters) of chromium-contaminated soil; and 450 gas cylinders, including 97 intact cylinders containing inert, flammable, toxic, corrosive, or oxidizing gases were removed and effectively managed to minimize waste

  5. Gradient remediability in linear distributed parabolic systems ...

    African Journals Online (AJOL)

    The aim of this paper is the introduction of a new concept that concerned the analysis of a large class of distributed parabolic systems. It is the general concept of gradient remediability. More precisely, we study with respect to the gradient observation, the existence of an input operator (gradient efficient actuators) ensuring ...

  6. Management challenges in remediating a mixed waste site at the Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    Riddle, S.P.; Wilson, R.C.; Branscom, K.S.

    1992-07-01

    Martin Marietta Energy Systems, Inc., manages the Oak Ridge National Laboratory (ORNL) for the US Department of Energy (DOE). Since ORNL's beginning in the 1940's, a variety of solid and liquid low-level radioactive waste (LLW), hazardous waste, and mixed waste has been generated. The solid wastes have been disposed of on site, primarily in shallow trenches called solid waste storage areas (SWSAs). SWSA 6, opened in 1969, is the only operational disposal site at ORNL for solid LLW. In 1984, SWSA 6 was closed for three months when it was discovered that wastes regulated by the Resource Conservation and Recovery Act (RCRA) were being inadvertently disposed of there. SWSA 6 was then added to ORNL's Part A RCRA permit, administrative controls were modified to exclude RCRA regulated wastes from being disposed of at SWSA 6, and a RCRA closure plan was prepared. This paper describes the regulatory challenges of integrating RCRA,- the Comprehensive Environmental Response, Compensation, and Liability Act; and the National Environmental Policy Act into a cohesive remediation strategy while managing the project with multiple DOE contractors and integrating the regulatory approval cycle with the DOE budget cycle. The paper does not dwell on the recommended alternative but presents instead a case study of how some difficult challenges, unique to DOE and other federal facilities, were handled

  7. Overview of the remedial action priority system (RAPS)

    International Nuclear Information System (INIS)

    Whelan, G.; Steelman, B.L.; Strenge, D.L.; Droppo, J.G.

    1986-01-01

    To provide DOE with a better management tool for prioritizing funding allocations for further site investigations and possible remediations, Pacific Northwest Laboratory developed a more objective, physics-based risk assessment methodology called the Remedial Action Priority System (RAPS). This methodology uses empirically, analytically, and semianalytically based mathematical algorithms and a pathways analysis to predict the potential for contaminant transport from a hazardous waste disposal site to local populations. Four major pathways for contaminant migration are considered in the RAPS methodology: groundwater, overland, surface water, and atmospheric. Using the predications of contaminant transport, simplified exposure assessments are performed for important receptors. The risks associated with the sites can then be calculated relative to other sites for each pathway and for all pathways together. The RAPS methodology addresses many of the typical limitations associated with other ranking systems; it considers: (1) more site information and constituent characteristics associated with the transport pathways; (2) chemical and radioactive wastes; (3) the potential direction of contaminant movement; (4) contaminant retention (e.g., dispersion and decay/degradation), where applicable; (5) population distributions; (6) various routes of exposure (e.g., inhalations, ingestion, and external exposure); (7) contaminant toxicities; (8) duration of exposure of the surrounding population; and (9) contaminant arrival time to sensitive receptors. Because RAPS is based on more site information and constituent characteristics, the scoring system of the RAPS methodology also reduces the subjectivity associated with prioritizing hazardous waste sites. The RAPS methodology requires minimum user knowledge of risk assessment and a minimum amount of input data

  8. Chemical tailoring of steam to remediate underground mixed waste contaminents

    Science.gov (United States)

    Aines, Roger D.; Udell, Kent S.; Bruton, Carol J.; Carrigan, Charles R.

    1999-01-01

    A method to simultaneously remediate mixed-waste underground contamination, such as organic liquids, metals, and radionuclides involves chemical tailoring of steam for underground injection. Gases or chemicals are injected into a high pressure steam flow being injected via one or more injection wells to contaminated soil located beyond a depth where excavation is possible. The injection of the steam with gases or chemicals mobilizes contaminants, such as metals and organics, as the steam pushes the waste through the ground toward an extraction well having subatmospheric pressure (vacuum). The steam and mobilized contaminants are drawn in a substantially horizontal direction to the extraction well and withdrawn to a treatment point above ground. The heat and boiling action of the front of the steam flow enhance the mobilizing effects of the chemical or gas additives. The method may also be utilized for immobilization of metals by using an additive in the steam which causes precipitation of the metals into clusters large enough to limit their future migration, while removing any organic contaminants.

  9. Remediation and decommissioning of radioactive waste facilities in Estonia

    International Nuclear Information System (INIS)

    Putnik, H.; Realo, E.

    2001-01-01

    Full text: The nuclear training facility at Paldiski was constructed in the early 1960's by the former USSR Navy. The hull sections of Delta and Echo class submarines each housing a full-sized ship reactor were installed in the main building of the site for training of navy personnel in safe operation of the submarine nuclear reactor systems. The first reactor was commissioned in 1968 and the second in 1982, while both was shut down in 1989. After Estonia's reproclamation of independence in 1991 the responsibility for the clean up and decommissioning of the Paldiski site became a subject of negotiations between Russia and Estonia. As the result Estonia took the ownership and control of the site in September 1995. Before the take over the Russian authorities defuelled the reactors and transported the spent fuel to Russia, dismantled the hull sections not related with reactor systems, seal-welded the hull sections housing the reactor vessels with their primary circuitry and enclosed those in reinforced concrete sarcophagi. The auxiliary facilities and radioactive waste were left intact. Main goals of the Conceptual Decommissioning Plan for the Paldiski facilities, developed under the auspices of the Paldiski International Expert Reference Group (Pier, a group established at the request of the Estonian government to advise local authorities to maintain the decommissioning and waste management at Paldiski) were defined as following: Establishing the waste management system and a long term monitored interim storage, corresponding to internationally accepted safety standards and capable to condition, receive and store all the waste generated during decommissioning of the facility; Reductions of the extent of radiologically controlled areas as much as possible, in order to minimise maintenance requirements. To achieve these goals the following main tasks were addressed in the short and medium term site management action plans: Rearrangement of site for the needs of

  10. Remedial action and waste disposal project: 100-B/C remedial action readiness report

    International Nuclear Information System (INIS)

    April, J.G.; Bryant, D.L.; Cislo, G.B.

    1996-07-01

    This Readiness Evaluation Report presents the results of the project readiness evaluation to assess the readiness of the 100-B/C source sites remediation. The 100-B/C Area is located at the Hanford Site in Richland, Washington. The evaluation was conducted at the conclusion of a series of readiness activities that began in May 1996. These activities included confirming the completion of project specific procedures, training of staff, obtaining support equipment, receipt of subcontractor submittals, approval of subcontractor submittals, and mobilization and construction of site support systems

  11. Department of Energy hazardous waste remedial actions program: Quality assurance program

    International Nuclear Information System (INIS)

    Horne, T.E.

    1988-01-01

    This paper describes the Quality Assurance Program developed for the Hazardous Waste Remedial Actions Program Support Contractor Office (HAZWRAP SCO). Key topics discussed include an overview of the HAZWRAP SCO mission and organization, the basic quality assurance program requirements and the requirements for the control of quality for the Department of Energy and Work for Others hazardous waste management programs, and the role of ensuring quality through the project team concept for the management of remedial response actions. The paper focuses on planning for quality assurance for this remedial waste management process from preliminary assessments of remedial sites to feasibility studies. Some observations concerning the control of quality during the implementation of remedial actions are presented. (2 refs.)

  12. An innovative in-situ mixing technology and its applications in the waste remediation industry

    International Nuclear Information System (INIS)

    Toor, I.A.; Lanter, R.

    1994-01-01

    An innovative in-situ remediation technology has been developed for solidification and stabilization of hazardous wastes. The system incorporates a specially designed rotary mixing head attached to the boom of a long-reach backhoe or other dirt-moving equipment. A variety of mixing-head configurations are available to treat various types of wastes, ranging from oil sludge to very dry contaminated soils containing significant amounts of large aggregates and gravel. The system has been successfully applied in the field to remediate hazardous petroleum sludge, mine tailings, and steel mill process sediments containing heavy metals (e.g., chromium, arsenic, cadmium, and lead). A very elaborate quality assurance/quality control program was implemented to ensure minimum variation in additive concentration and thorough mixing. The mixing effectiveness and reagent injection capabilities of this unit have resulted in the in-situ treatment of listed hazardous wastes to below delisting thresholds at depths in excess of 15 ft. Applications of this unit are currently being reviewed for incorporating and mixing nutrients in a bioremediation process. The new technology provides a very economical means for treatment, with excellent product quality

  13. Infectious waste feed system

    Science.gov (United States)

    Coulthard, E. James

    1994-01-01

    An infectious waste feed system for comminuting infectious waste and feeding the comminuted waste to a combustor automatically without the need for human intervention. The system includes a receptacle for accepting waste materials. Preferably, the receptacle includes a first and second compartment and a means for sealing the first and second compartments from the atmosphere. A shredder is disposed to comminute waste materials accepted in the receptacle to a predetermined size. A trough is disposed to receive the comminuted waste materials from the shredder. A feeding means is disposed within the trough and is movable in a first and second direction for feeding the comminuted waste materials to a combustor.

  14. Hazardous Waste Manifest System

    Science.gov (United States)

    EPA’s hazardous waste manifest system is designed to track hazardous waste from the time it leaves the generator facility where it was produced, until it reaches the off-site waste management facility that will store, treat, or dispose of the waste.

  15. SADA: Ecological Risk Based Decision Support System for Selective Remediation

    Science.gov (United States)

    Spatial Analysis and Decision Assistance (SADA) is freeware that implements terrestrial ecological risk assessment and yields a selective remediation design using its integral geographical information system, based on ecological and risk assessment inputs. Selective remediation ...

  16. Best Practices for Fuel System Contamination Detection and Remediation

    Science.gov (United States)

    2016-01-15

    The University of Dayton Research Institute Best Practices for Fuel System Contamination Detection and Remediation Final Report Marlin D... Remediation Executive Summary: Fuel contamination is a broad term commonly applied to anything that causes a fuel test to fail quality assurance...Statement A: Approved for public release: distribution unlimited. 1 Best Practices for Fuel System Contamination Detection and Remediation Contents

  17. FY 1995 remedial investigation work plan for Waste Area Grouping 2 at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    Watkins, D.R.; Herbes, S.E.

    1994-09-01

    Field activities to support the remedial investigation (RI) of Waste Area Grouping (WAG) 2 at Oak Ridge National Laboratory (ORNL) include characterization of the nature and extent of contamination in WAG 2, specifically to support risk-based remediation decisions. WAG 2 is the major drainage system downgradient of other WAGs containing significant sources of contamination at ORNL. The RI of WAG 2 is developed in three phases: Phase 1, initial scoping characterization to determine the need for early action; Phase 2, interim activities during remediation of upgradient WAGs to evaluate potential changes in the contamination status of WAG 2 that would necessitate reevaluation of the need for early action; and Phase 3, completion of the RI process following remediation of upslope WAGs. Specifically, Phase 2 activities are required to track key areas to determine if changes have occurred in WAG 2 that would require (1) interim remedial action to protect human health and the environment or (2) changes in remedial action plans and schedules for WAG2 because of changing contaminant release patterns in upslope WAGs or because of the effects of interim remedial or removal actions in other WAGs. This report defines activities to be conducted in FY 1995 for completion of the Phase 1 RI and initiation of limited Phase 2 field work

  18. Remediation and production of low-sludge high-level waste glasses

    International Nuclear Information System (INIS)

    Ramsey, W.G.; Brown, K.G.; Beam, D.C.

    1994-01-01

    High-level radioactive sludge will constitute 24-28 oxide weight percent of the high-level waste glass produced at the Savannah River Site. A recent melter campaign using non-radioactive, simulated feed was performed with a sludge content considerably lower than 24 percent. The resulting glass was processed and shown to have acceptable durability. However, the durability was lower than predicted by the durability algorithm. Additional melter runs were performed to demonstrate that low sludge feed could be remediated by simply adding sludge oxides. The Product Composition Control System, a computer code developed to predict the proper feed composition for production of high-level waste glass, was utilized to determine the necessary chemical additions. The methodology used to calculate the needed feed additives, the effects of sludge oxides on glass production, and the resulting glass durability are discussed

  19. Waste Management Plan for the Oak Ridge National Remedial Investigation/Feasibility Study

    International Nuclear Information System (INIS)

    1988-04-01

    In accordance with the requirements of the Remedial Investigation/Feasibility Study (RI/FS) Project Quality Assurance Plan, this Waste Management Plan establishes clear lines of responsibility and authority, documentation requirements, and operational guidance for the collection, identification, segregation, classification, packaging, certification, and storage/disposal of wastes. These subjects are discussed in the subsequent sections of this document

  20. Waste Management Plan for the Oak Ridge National Remedial Investigation/Feasibility Study

    Energy Technology Data Exchange (ETDEWEB)

    1988-04-01

    In accordance with the requirements of the Remedial Investigation/Feasibility Study (RI/FS) Project Quality Assurance Plan, this Waste Management Plan establishes clear lines of responsibility and authority, documentation requirements, and operational guidance for the collection, identification, segregation, classification, packaging, certification, and storage/disposal of wastes. These subjects are discussed in the subsequent sections of this document.

  1. System description for DART (Decision Analysis for Remediation Technologies)

    International Nuclear Information System (INIS)

    Nonte, J.; Bolander, T.; Nickelson, D.; Nielson, R.; Richardson, J.; Sebo, D.

    1997-09-01

    DART is a computer aided system populated with influence models to determine quantitative benefits derived by matching requirements and technologies. The DART database is populated with data from over 900 DOE sites from 10 Field Offices. These sites are either source terms, such as buried waste pits, or soil or groundwater contaminated plumes. The data, traceable to published documents, consists of site-specific data (contaminants, area, volume, depth, size, remedial action dates, site preferred remedial option), problems (e.g., offsite contaminant plume), and Site Technology Coordinating Group (STCG) need statements (also contained in the Ten-Year Plan). DART uses this data to calculate and derive site priorities, risk rankings, and site specific technology requirements. DART is also populated with over 900 industry and DOE SCFA technologies. Technology capabilities can be used to match technologies to waste sites based on the technology''s capability to meet site requirements and constraints. Queries may be used to access, sort, roll-up, and rank site data. Data roll-ups may be graphically displayed

  2. Oak Ridge National Laboratory Old Hydrofracture Facility Waste Remediation Using the Borehole-Miner Extendible-Nozzle Sluicer

    Energy Technology Data Exchange (ETDEWEB)

    Bamberger, J.A.; Boris, G.F.

    1999-10-07

    A borehole-miner extendible-nozzle sluicing system was designed, constructed, and deployed at Oak Ridge National Laboratory to remediate five horizontal underground storage tanks containing sludge and supernate at the ORNL Old Hydrofracture Facility site. The tanks were remediated in fiscal year 1998 to remove {approx}98% of the waste, {approx}3% greater than the target removal of >95% of the waste. The tanks contained up to 18 in. of sludge covered by supernate. The 42,000 gal of low level liquid waste were estimated to contain 30,000 Ci, with 97% of this total located in the sludge. The retrieval was successful. At the completion of the remediation, the State of Tennessee Department of Environment and Conservation agreed that the tanks were cleaned to the maximum extent practicable using pumping technology. This deployment was the first radioactive demonstration of the borehole-miner extendible-nozzle water-jetting system. The extendible nozzle is based on existing bore hole-miner technology used to fracture and dislodge ore deposits in mines. Typically borehole-miner technology includes both dislodging and retrieval capabilities. Both dislodging, using the extendible-nozzle water-jetting system, and retrieval, using a jet pump located at the base of the mast, are deployed as an integrated system through one borehole or riser. Note that the extendible-nozzle system for Oak Ridge remediation only incorporated the dislodging capability; the retrieval pump was deployed through a separate riser. The borehole-miner development and deployment is part of the Retrieval Process Development and Enhancements project under the direction of the US Department of Energy's EM-50 Tanks Focus Area. This development and deployment was conducted as a partnership between RPD and E and the Oak Ridge National Laboratory's US DOE EM040 Old Hydrofracture Facility remediation project team.

  3. Oak Ridge National Laboratory Old Hydrofracture Facility Waste Remediation Using the Borehole-Miner Extendible-Nozzle Sluicer

    International Nuclear Information System (INIS)

    Boris, G.F.; Bamberger, J.A.

    1999-01-01

    A borehole-miner extendible-nozzle sluicing system was designed, constructed, and deployed at Oak Ridge National Laboratory to remediate five horizontal underground storage tanks containing sludge and supernate at the ORNL Old Hydrofracture Facility site. The tanks were remediated in fiscal year 1998 to remove approximately98% of the waste, approximately3% greater than the target removal of >95% of the waste. The tanks contained up to 18 in. of sludge covered by supernate. The 42,000 gal of low level liquid waste were estimated to contain 30,000 Ci, with 97% of this total located in the sludge. The retrieval was successful. At the completion of the remediation, the State of Tennessee Department of Environment and Conservation agreed that the tanks were cleaned to the maximum extent practicable using pumping technology. This deployment was the first radioactive demonstration of the borehole-miner extendible-nozzle water-jetting system. The extendible nozzle is based on existing borehole-miner technology used to fracture and dislodge ore deposits in mines. Typically borehole-miner technology includes both dislodging and retrieval capabilities. Both dislodging, using the extendible-nozzle water-jetting system, and retrieval, using a jet pump located at the base of the mast, are deployed as an integrated system through one borehole or riser. Note that the extendible-nozzle system for Oak Ridge remediation only incorporated the dislodging capability; the retrieval pump was deployed through a separate riser. The borehole-miner development and deployment is part of the Retrieval Process Development and Enhancements project under the direction of the US Department of Energy's EM-50 Tanks Focus Area. This development and deployment was conducted as a partnership between RPD and E and the Oak Ridge National Laboratory's US DOE EM040 Old Hydrofracture Facility remediation project team

  4. FY 1995 Remedial Investigation Work Plan for Waste Area Grouping 2 at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    Watkins, D.R.; Herbes, S.E.

    1994-12-01

    The purpose of this project is to provide key information needed by decision makers to expedite the process of environmental restoration and to provide the data base required by the Remedial Investigation/Feasibility Study (RI/FS) for Waste Area Grouping (WAG) 2 at Oak Ridge National Laboratory (ORNL). WAG 2 is the major drainage system downgradient of other WAGs that contain significant sources of contamination at ORNL. Field activities to support the remedial investigation for the RI portion include characterization of the nature and extent of contamination in WAG 2 [consisting of White Oak Creek (WOC) and associated tributaries and floodplain, White Oak Lake (WOL), and White Oak Creek Embayment (WOCE)], specifically to support risk-based remediation decisions. The project consists of three phases: Phase 1, initial scoping characterization to determine the need for early action; Phase 2, interim activities during remediation of upslope WAGs to evaluate potential changes in the contamination status of WAG 2 that would necessitate revaluation of the need for early action; and Phase 3, completion of the RI process following remediation of upslope WAGs. Overall RI objectives, consistent with ORNL Environmental Restoration (ER) Program strategic objectives to reduce risks and comply with environmental regulations, are discussed in the WAG 2 Remedial Investigation Plan

  5. Environmental remediation and waste management in the United States

    International Nuclear Information System (INIS)

    Muntzing, L.M.; Person, J.C.

    1994-01-01

    Environmental remediation of radioactively and chemically contaminated sites represents one of the most complex challenges of our age. It is currently a problem at nuclear weapons sites in the United States, but as the civilian nuclear industry everywhere deals with decommissioning and decontamination, the lessons learned from these early activities will be influential. The task is challenging for several reasons. First, standards governing remedial action are complex and constantly evolving. Second, unless contaminated material is to be stabilized in place, it must be removed and sent to another facility for storage and ultimate disposal. Third the task is technically demanding. Those who undertake the challenge must be technically sophisticated, creative, and innovative. Fourth, the challenge is a risky one. Those who seek to remediate past contamination may find themselves exposed to expanding and unfair allegations of liability for that very contamination. Finally, there is often a basic crisis of public confidence regarding remediation efforts

  6. Operable Unit 3-13, Group 3, Other Surface Soils Remediation Sets 4-6 (Phase II) Waste Management Plan

    International Nuclear Information System (INIS)

    G. L. Schwendiman

    2006-01-01

    This Waste Management Plan describes waste management and waste minimization activities for Group 3, Other Surface Soils Remediation Sets 4-6 (Phase II) at the Idaho Nuclear Technology and Engineering Center located within the Idaho National Laboratory. The waste management activities described in this plan support the selected response action presented in the Final Record of Decision for Idaho Nuclear Technology and Engineering Center, Operable Unit 3-13. This plan identifies the waste streams that will be generated during implementation of the remedial action and presents plans for waste minimization, waste management strategies, and waste disposition

  7. Tank 241-SY-101 surface level rise remediation test and evaluation plan for transfer system

    International Nuclear Information System (INIS)

    BAUER, R.E.

    1999-01-01

    The purpose of this testing and evaluation plan (TEP) is to provide the high level guidance on testing requirements for ensuring that the equipment and systems to be implemented for remediation of the SY-101 waste level rise USQ are effective

  8. Determining the number of samples required for decisions concerning remedial actions at hazardous waste sites

    International Nuclear Information System (INIS)

    Skiles, J.L.; Redfearn, A.; White, R.K.

    1991-01-01

    An important consideration for every risk analyst is how many field samples should be taken so that scientifically defensible decisions concerning the need for remediation of a hazardous waste site can be made. Since any plausible remedial action alternative must, at a minimum, satisfy the condition of protectiveness of human and environmental health, we propose a risk-based approach for determining the number of samples to take during remedial investigations rather than using more traditional approaches such as considering background levels of contamination or federal or state cleanup standards

  9. The sonophysics and sonochemistry of liquid waste quantification and remediation. 1998 annual progress report

    International Nuclear Information System (INIS)

    Matula, T.J.

    1998-01-01

    'To perform an in-depth and comprehensive study of the fundamentals of acoustic cavitation and nonlinear bubble dynamics, to elucidate the fundamental physics of sonochemical reactions, to examine the potential of sonoluminescence to quantify and to monitor the presence of alkali metals and other elements in waste liquids, to design and to evaluate more effective sonochemical reactors for waste remediation, and to determine the optimal acoustical parameters in the use of sonochemistry for liquid-waste-contaminant remediation. This report summarizes work performed during year 2 of a 3-year project. The goals included performing near-IR spectroscopy of sonoluminescence. Cells have been designed for multi-bubble sonoluminescence (MBSL) and single-bubble sonoluminescence (SBSL) spectroscopy experiments. The MBSL cells are designed around a 20 kHz acoustic horn with replaceable titanium tips from Sonics and Materials. The horn is pressure-fitted into a stainless steel cell via O-rings and a compression ring, to seal the cell up to 100 psi for pressure experiments. The cell is thermostated by circulating coolant in a jacket, as well as flowing the cell fluid (at 4L/min.) through a temperature control bath. Several ports are located on the cell for gas ports (one for headspace, another for bubbling), a pressure transducer, a thermocouple, a needle hydrophone, and a septum port for addition or withdrawal of samples. The total volume is approximately 80 mL with a 10 mL head space. Directly opposite the horn tip is a 2 cm quartz window against which a fiber optic bundle is placed. Light collected through the fiber optic is imaged onto one of several detection systems.'

  10. Waste Management Plan for the Lower East Fork Poplar Creek Remedial Action Project Oak Ridge, Tennessee

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-08-01

    The Lower East Fork Poplar Creek (LEFPC) Remedial Action project will remove mercury-contaminated soils from the floodplain of LEFPC, dispose of these soils at the Y-12 Landfill V, and restore the affected floodplain upon completion of remediation activities. This effort will be conducted in accordance with the Record of Decision (ROD) for LEFPC as a Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) action. The Waste Management Plan addresses management and disposition of all wastes generated during the remedial action for the LEFPC Project Most of the solid wastes will be considered to be sanitary or construction/demolition wastes and will be disposed of at existing Y-12 facilities for those types of waste. Some small amounts of hazardous waste are anticipated, and the possibility of low- level or mixed waste exists (greater than 35 pCi/g), although these are not expected. Liquid wastes will be generated which will be sanitary in nature and which will be capable of being disposed 0214 of at the Oak Ridge Sewage Treatment Plant.

  11. Waste Management Plan for the Lower East Fork Poplar Creek Remedial Action Project Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1996-08-01

    The Lower East Fork Poplar Creek (LEFPC) Remedial Action project will remove mercury-contaminated soils from the floodplain of LEFPC, dispose of these soils at the Y-12 Landfill V, and restore the affected floodplain upon completion of remediation activities. This effort will be conducted in accordance with the Record of Decision (ROD) for LEFPC as a Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) action. The Waste Management Plan addresses management and disposition of all wastes generated during the remedial action for the LEFPC Project Most of the solid wastes will be considered to be sanitary or construction/demolition wastes and will be disposed of at existing Y-12 facilities for those types of waste. Some small amounts of hazardous waste are anticipated, and the possibility of low- level or mixed waste exists (greater than 35 pCi/g), although these are not expected. Liquid wastes will be generated which will be sanitary in nature and which will be capable of being disposed 0214 of at the Oak Ridge Sewage Treatment Plant

  12. Remediation of toxic and hazardous wastes: issues and concerns

    International Nuclear Information System (INIS)

    2005-01-01

    This workshop presented the status of hazardous waste generation in the Philippines, as well the steps being done by the government to address the problem on hazardous materials in the environment and the disposal of the toxic wastes

  13. Waste management and environmental compliance aspects of a major remedial action program

    International Nuclear Information System (INIS)

    Devgun, J.S.; Beskid, N.J.

    1991-01-01

    The Formerly Utilized Sites Remedial Action Program (FUSRAP) is one of four major programs undertaken by the US Department of Energy (DOE) to remediate various sites where radiological contamination remained from programs conducted during the nation's early years of research and development in atomic energy. The remedial actions at the 33 sites that are currently in FUSRAP could generate an estimated total volume of about 1.6 million cubic meters of radioactive waste. Waste disposal is currently estimated to represent about one-third of the total estimated $2.1 billion cost for the entire program over its total duration. Waste management aspects within the program are diverse. The sites range in size from small areas used only for storage operations to large-scale decommissioned industrial facilities where uranium processing and other operations were carried out in the past. Currently, four sites are on the National Priorities List for remediation. Remedial actions at FUSRAP sites have to satisfy the requirements of both the National Environmental Policy Act and the Comprehensive Environmental Response, Compensation and Liability Act, as amended. In addition, a number of federal, state, and local laws as well as Executive Orders and DOE Orders may be applicable or relevant to each site. Several key issues currently face the program, including the mixed waste issue, both from the environmental compliance (with Resource Conservation and Recovery Act) and the disposal technology perspectives. 7 refs., 1 tab

  14. Utilization of waste materials, non-refined materials, and renewable energy in in situ remediation and their sustainability benefits.

    Science.gov (United States)

    Favara, Paul; Gamlin, Jeff

    2017-12-15

    In the ramp-up to integrating sustainability into remediation, a key industry focus area has been to reduce the environmental footprint of treatment processes. The typical approach to integrating sustainability into remediation projects has been a top-down approach, which involves developing technology options and then applying sustainability thinking to the technology, after it has been conceptualized. A bottom-up approach allows for systems thinking to be included in remedy selection and could potentially result in new or different technologies being considered. When using a bottom-up approach, there is room to consider the utilization of waste materials, non-refined materials, and renewable energy in remediation technology-all of which generally have a smaller footprint than processed materials and traditional forms of energy. By integrating more systems thinking into remediation projects, practitioners can think beyond the traditional technologies typically used and how technologies are deployed. To compare top-down and bottom-up thinking, a traditional technology that is considered very sustainable-enhanced in situ bioremediation-is compared to a successful, but infrequently deployed technology-subgrade biogeochemical reactors. Life Cycle Assessment is used for the evaluation and shows the footprint of the subgrade biogeochemical reactor to be lower in all seven impact categories evaluated, sometimes to a significant degree. Copyright © 2017 Elsevier Ltd. All rights reserved.

  15. Green PCB Remediation from Sediment Systems

    Data.gov (United States)

    National Aeronautics and Space Administration — An ongoing problem facing the global environmental community including NASA centers is the removal and remediation of polychlorinated biphenyls (PCBs). PCBs were...

  16. Integration of Environmental Restoration and Waste Management Activities for a More Cost-Effective Tank Remediation Program Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    Brill, A.; Clark, R.; Stewart, R.

    1998-01-01

    This paper presents plans and strategies for remediation of the liquid low-level radioactive waste (LLLW) tanks that have been removed from service (also known as inactive tanks) at Oak Ridge National Laboratory (ORNL), Oak Ridge, Tennessee. Much of the LLLW system at ORNL was installed more than 50 years ago. The overall objective of the Inactive Tank Program is to remediate all LLLW tanks that have been removed from service to the extent practicable in accordance with the regulatory requirements

  17. Remedial Action Assessment System: A computer-based methodology for conducting feasibility studies

    International Nuclear Information System (INIS)

    White, M.K.; Buelt, J.L.; Stottlemyre, J.A.

    1991-02-01

    Because of the complexity and number of potential waste sites facing the US Department of Energy (DOE) for potential cleanup, DOE is supporting the development of a computer-based methodology to streamline the remedial investigation/feasibility study process. The Remedial Action Assessment System (RAAS), can be used for screening, linking, and evaluating established technology processes in support of conducting feasibility studies. It is also intended to do the same in support of corrective measures studies. The user interface employs menus, windows, help features, and graphical information while RAAS is in operation. Object-oriented programming is used to link unit processes into sets of compatible processes that form appropriate remedial alternatives. Once the remedial alternatives are formed, the RAAS methodology can evaluate them in terms of effectiveness, implementability, and cost. RAAS will access a user-selected risk assessment code to determine the reduction of risk after remedial action by each recommended alternative. The methodology will also help determine the implementability of the remedial alternatives at a site and access cost estimating tools to provide estimates of capital, operating, and maintenance costs. This paper presents the characteristics of two RAAS prototypes currently being developed. These include the RAAS Technology Information System, which accesses graphical, tabular and textual information about technologies, and the main RAAS methodology, which screens, links, and evaluates remedial technologies. 4 refs., 3 figs., 1 tab

  18. Waste area Grouping 2 Phase I remedial investigation: Sediment and Cesium-137 transport modeling report

    International Nuclear Information System (INIS)

    Clapp, R.B.; Bao, Y.S.; Moore, T.D.; Brenkert, A.L.; Purucker, S.T.; Reece, D.K.; Burgoa, B.B.

    1996-06-01

    This report is one of five reports issued in 1996 that provide follow-up information to the Phase I Remedial Investigation (RI) Report for Waste Area Grouping (WAG) 2 at Oak Ridge National Laboratory (ORNL). The five reports address areas of concern that may present immediate risk to public health at the Clinch River and ecological risk within WAG 2 at ORNL. A sixth report, on groundwater, in the series documenting WAG 2 RI Phase I results were part of project activities conducted in FY 1996. The five reports that complete activities conducted as part of Phase I of the Remedial Investigation (RI) for WAG 2 are as follows: (1) Waste Area Grouping 2, Phase I Task Data Report: Seep Data Assessment, (2) Waste Area Grouping 2, Phase I Task Data Report: Tributaries Data Assessment, (3) Waste Area Grouping 2, Phase I Task Data Report: Ecological Risk Assessment, (4) Waste Area Grouping 2, Phase I Task Data Report: Human Health Risk Assessment, (5) Waste Area Grouping 2, Phase I Task Data Report: Sediment and 137 Cs Transport Modeling In December 1990, the Remedial Investigation Plan for Waste Area Grouping 2 at Oak Ridge National Laboratory was issued (ORNL 1990). The WAG 2 RI Plan was structured with a short-term component to be conducted while upgradient WAGs are investigated and remediated, and a long-term component that will complete the RI process for WAG 2 following remediation of upgradient WAGs. RI activities for the short-term component were initiated with the approval of the Environmental Protection Agency, Region IV (EPA), and the Tennessee Department of Environment and Conservation (TDEC). This report presents the results of an investigation of the risk associated with possible future releases of 137 Cs due to an extreme flood. The results are based on field measurements made during storms and computer model simulations

  19. Overview of technology modeling in the Remedial Action Assessment System (RAAS)

    International Nuclear Information System (INIS)

    Johnson, C.D.; Bagaasen, L.M.; Chan, T.C.; Lamar, D.A.; Buelt, J.L.; Freeman, C.J.; Skeen, R.S.

    1994-08-01

    There are numerous hazardous waste sites under the jurisdiction of the US Department of Energy (DOE). To assist the cleanup of these sites in a more consistent, timely, and cost-effective manner, the Remedial Action Assessment System (RAAS) is being developed by the Pacific Northwest Laboratory (PNL). RAAS is a software tool designed to automate the initial technology selection within the remedial investigation/feasibility study (RI/FS) process. The software does several things for the user: (1) provides information about available remedial technologies, (2) sorts possible technologies to recommend a list of technologies applicable to a given site, (3) points out technical issues that may prevent the implementation of a technology, and (4) provides an estimate of the effectiveness of a given technology at a particular site. Information from RAAS can be used to compare remediation options and guide selection of technologies for further study

  20. Environmental remediation and waste management in the United States

    International Nuclear Information System (INIS)

    Muntzing, L.M.; Person, J.C.

    1994-01-01

    Environmental remediation of radioactively and chemically contaminated sites represents one of the most complex challenges of our age. It is currently a problem at nuclear weapons sites in the Unites States, but as the civilian nuclear industry everywhere deals with decommissioning and decontamination, the lessons learned from these early activities will be influential. The task is challenging for several reasons. First, standards governing remedial action are complex and constantly evolving. Second, unless contaminated material is to be stabilized in place, it must be removed and sent to another facility for storage and ultimate disposal. Third, the task is technically demanding. Those who undertake the challenge must be technically sophisticated, creative, and innovative. Fourth, the challenge is a risky one. Those who seek to remediate past contamination may find themselves exposed to expanding and unfair allegations of liability for that very contamination. Finally, there is often a basic crisis of public confidence regarding remediation efforts. This paper briefly outlines some of the liabilities surrounding environmental contracting and ways to minimize risks

  1. REMEDIAL ACTION, TREATMENT AND DISPOSAL OF HAZARDOUS WASTE: PROCEEDINGS OF THE SIXTEENTH ANNUAL HAZARDOUS WASTE RESEARCH SYMPOSIUM

    Science.gov (United States)

    The Sixteenth Annual Research Symposium on Remedial Action, Treatment and Disposal of Hazardous Waste was held in Cincinnati, Ohio, April 3-5, 1990. he purpose of this Symposium was to present the latest significant research findings from ongoing and recently completed projects f...

  2. In Situ Modular Waste Retrieval and Treatment System

    International Nuclear Information System (INIS)

    Walker, M.S.

    1996-10-01

    As part of the Comprehensive Environmental Response, Compensation, and Liability Act process from remediation of Waste Area Grouping (WAG 6) at ORNL, a public meeting was held for the Proposed Plan. It was recognized that contaminant releases from WAG 6 posed minimal potential risk to the public and the environment. The US DOE in conjunction with the US EPA and the TDEC agreed to defer remedial action at WAG 6 until higher risk release sites were first remediated. This report presents the results of a conceptual design for an In Situ Modular Retrieval and Treatment System able to excavate, shred, and process buried waste on site, with minimum disturbance and distribution of dust and debris. the system would bring appropriate levels of treatment to the waste then encapsulate and leave it in place. The system would be applicable to areas in which waste was disposed in long trenches

  3. Environmental health: an analysis of available and proposed remedies for victims of toxic waste contamination

    International Nuclear Information System (INIS)

    Hurwitz, W.J.

    1981-01-01

    Past and present residents of the Love Canal area near Niagara Falls, New York, fear that they and their homes have been contaminated by toxic wastes seeping out from nearby chemical disposal sites. Hundreds of landfills nationwide are as potentially dangerous as Love Canal. In the absence of a statutory remedy, victims of contamination must rely upon common law theories of lability in order to recover damages for injuries suffered as a result of toxic waste contamination. This Note examines the merits and deficiencies of four common law theories: negligence, strict liability, nuisance and trespass. The Note concludes that none of these remedies is adequate to assure recovery to a person injured by toxic waste disposal, and recommends that legislation be adopted to ensure that victims of toxic waste contamination can be compensated for their injuries

  4. Uranium Mill Tailings remedial action project waste minimization and pollution prevention awareness program plan

    International Nuclear Information System (INIS)

    1994-07-01

    The purpose of this plan is to establish a waste minimization and pollution prevention awareness (WM/PPA) program for the U.S. Department of Energy's (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project. The program satisfies DOE requirements mandated by DOE Order 5400.1. This plan establishes planning objectives and strategies for conserving resources and reducing the quantity and toxicity of wastes and other environmental releases

  5. Role of biochar on composting of organic wastes and remediation of contaminated soils-a review.

    Science.gov (United States)

    Wu, Shaohua; He, Huijun; Inthapanya, Xayanto; Yang, Chunping; Lu, Li; Zeng, Guangming; Han, Zhenfeng

    2017-07-01

    Biochar is produced by pyrolysis of biomass residues under limited oxygen conditions. In recent years, biochar as an amendment has received increasing attention on composting and soil remediation, due to its unique properties such as chemical recalcitrance, high porosity and sorption capacity, and large surface area. This paper provides an overview on the impact of biochar on the chemical characteristics (greenhouse gas emissions, nitrogen loss, decomposition and humification of organic matter) and microbial community structure during composting of organic wastes. This review also discusses the use of biochar for remediation of soils contaminated with organic pollutants and heavy metals as well as related mechanisms. Besides its aging, the effects of biochar on the environment fate and efficacy of pesticides deserve special attention. Moreover, the combined application of biochar and compost affects synergistically on soil remediation and plant growth. Future research needs are identified to ensure a wide application of biochar in composting and soil remediation. Graphical abstract ᅟ.

  6. Remediation of Hanford tank waste using magnetic separation

    International Nuclear Information System (INIS)

    Worl, L.A.; Avens, L.R.; de Aguero, K.J.; Coyne Prenger, F.; Stewart, W.F.; Hill, D.D.

    1992-01-01

    Large volumes of high-level radioactive waste are stored at the Department of Energy's Hanford site. Magnetic separation, a physical separation, process, can be used to segregate actinides and certain fission products from the waste. High gradient magnetic separation (HGMS) tests have been performed successfully using a simulated, nonradioactive underground storage tank (UST) waste. Variations in HGMS test parameters included separator matrix material, magnetic field strength, slurry surfactant, and slurry solids loading. Cerium was added to the simulated tank waste to act as a uranium surrogate. Results show that over 77% of the uranium surrogate can be captured and concentrated from the original bulk with a simple procedure. The results of these tests and the feasibility of magnetic separation for pretreatment of UST waste are discussed

  7. Treatment of Bottled Liquid Waste During Remediation of the Hanford 618-10 Burial Ground - 13001

    International Nuclear Information System (INIS)

    Faulk, Darrin E.; Pearson, Chris M.; Vedder, Barry L.; Martin, David W.

    2013-01-01

    A problematic waste form encountered during remediation of the Hanford Site 618-10 burial ground consists of bottled aqueous waste potentially contaminated with regulated metals. The liquid waste requires stabilization prior to landfill disposal. Prior remediation activities at other Hanford burial grounds resulted in a standard process for sampling and analyzing liquid waste using manual methods. Due to the highly dispersible characteristics of alpha contamination, and the potential for shock sensitive chemicals, a different method for bottle processing was needed for the 618-10 burial ground. Discussions with the United States Department of Energy (DOE) and United States Environmental Protection Agency (EPA) led to development of a modified approach. The modified approach involves treatment of liquid waste in bottles, up to one gallon per bottle, in a tray or box within the excavation of the remediation site. Bottles are placed in the box, covered with soil and fixative, crushed, and mixed with a Portland cement grout. The potential hazards of the liquid waste preclude sampling prior to treatment. Post treatment verification sampling is performed to demonstrate compliance with land disposal restrictions and disposal facility acceptance criteria. (authors)

  8. Treatment of Bottled Liquid Waste During Remediation of the Hanford 618-10 Burial Ground - 13001

    Energy Technology Data Exchange (ETDEWEB)

    Faulk, Darrin E.; Pearson, Chris M.; Vedder, Barry L.; Martin, David W. [Washington Closure Hanford, LLC, Richland, WA 99354 (United States)

    2013-07-01

    A problematic waste form encountered during remediation of the Hanford Site 618-10 burial ground consists of bottled aqueous waste potentially contaminated with regulated metals. The liquid waste requires stabilization prior to landfill disposal. Prior remediation activities at other Hanford burial grounds resulted in a standard process for sampling and analyzing liquid waste using manual methods. Due to the highly dispersible characteristics of alpha contamination, and the potential for shock sensitive chemicals, a different method for bottle processing was needed for the 618-10 burial ground. Discussions with the United States Department of Energy (DOE) and United States Environmental Protection Agency (EPA) led to development of a modified approach. The modified approach involves treatment of liquid waste in bottles, up to one gallon per bottle, in a tray or box within the excavation of the remediation site. Bottles are placed in the box, covered with soil and fixative, crushed, and mixed with a Portland cement grout. The potential hazards of the liquid waste preclude sampling prior to treatment. Post treatment verification sampling is performed to demonstrate compliance with land disposal restrictions and disposal facility acceptance criteria. (authors)

  9. Electrodialytic remediation of CCA-treated waste wood in a 2 m3 pilot plant

    DEFF Research Database (Denmark)

    Christensen, Iben Vernegren; Pedersen, Anne Juul; Ottosen, Lisbeth M.

    2006-01-01

    Waste wood that has been treated with chromated-copper-arsenate (CCA) poses a potential environmental problem due to the content of copper, chromium and arsenic. A pilot plant for electrodialytic remediation of up to 2 m3 wood has been designed and tested and the results are presented here. Sever...

  10. Factors for assessment of human health risk associated with remedial action at hazardous waste sites

    International Nuclear Information System (INIS)

    Stephenson, D.E.; King, C.M.; Looney, B.B.; Holmes, W.G.; Gordon, D.E.

    1985-01-01

    A risk assessment strategy that is cost effective and minimized human health risks was developed for closure of hazardous waste sites at the Savannah River Plant. The strategy consists of (1) site characterization, (2) contaminant transport modeling, and (3) determination of relative merits of alternative remedial actions according to the degree of health protection they provide

  11. 77 FR 72691 - Small Business Size Standards: Administrative and Support, Waste Management and Remediation Services

    Science.gov (United States)

    2012-12-06

    ... importantly, the Small Business Act requires SBA to establish one definition of what is a small business... SMALL BUSINESS ADMINISTRATION 13 CFR Part 121 RIN 3245-AG27 Small Business Size Standards: Administrative and Support, Waste Management and Remediation Services AGENCY: U.S. Small Business Administration...

  12. UNITED STATES AND GERMAN BILATERAL AGREEMENT ON REMEDIATION OF HAZARDOUS WASTE SITES

    Science.gov (United States)

    The U.S. Environmental Protection Agency (EPA) and Germany's Bundesministerium fur Forschung und Technologie (BMFT) are involved in a collaborative effort called the U.S. and German Bilateral Agreement on Remediation of Hazardous Waste Sites. he purpose of this interim status rep...

  13. Control of a long reach manipulator with suspension cables for waste storage tank remediation. Final report

    International Nuclear Information System (INIS)

    Wang, S.L.

    1994-01-01

    A long reach manipulator will be used for waste remediation in large underground storage tanks. The manipulator's slenderness makes it flexible and difficult to control. A low-cost and effective method to enhance the manipulator's stiffness is proposed in this research by using suspension cables. These cables can also be used to accurately measure the position of the manipulator's wrist

  14. Safety Assessment Approach for Decision Making Related to Remedial Measures and Radioactive Waste Management

    International Nuclear Information System (INIS)

    Rybalka, Nataliia; Kondratyev, Sergiy; Alekseeva, Zoya

    2016-01-01

    Conclusions: At each particular case of “legacy” radioactive waste management facilities the optimized remedial measures should be justified taken into account: • results of facility investigations; • site status and characteristics; • safety assessment; • economical reasons; • societal factors; • timeframes; • available technologies and techniques

  15. Radiological criteria for the remediation of sites for spent fuel and radioactive waste storage in the Russian Northwest.

    Science.gov (United States)

    Shandala, N K; Sneve, M K; Titov, A V; Smith, G M; Novikova, N Ya; Romanov, V V; Seregin, V A

    2008-12-01

    In the 1960s, two technical bases of the Northern Fleet were created in Northwest Russia, at Andreeva Bay in the Kola Peninsula and Gremikha village on the coast of the Barents Sea. They maintained nuclear submarines, performing receipt and storage of radioactive waste and spent nuclear fuel, and are now designated sites of temporary storage (STSs). An analysis of the radiation situation at these sites demonstrates that substantial long-term remediation work will be required after the removal of the waste and spent nuclear fuel. Regulatory guidance is under development to support this work. Having in mind modern approaches to guaranteeing radiation safety, the primary regulatory focus is on a justification of dose constraints for determining acceptable residual contamination which might lead to exposure to workers and the public. For these sites, four principal options for remediation have been considered-renovation, conversion, conservation and liquidation. This paper describes a system of recommended dose constraints and derived control levels formulated for each option. The unconditional guarantee of long-term radioecological protection provides the basis for criteria development. Non-exceedance of these dose constraints and control levels implies compliance with radiological protection objectives related to the residual contamination. Dose reduction below proposed dose constraint values must also be carried out according to the optimisation principle. The developed criteria relate to the condition of the facilities and the STS areas after the termination of remediation activities. The proposed criteria for renovation, conversion, conservation and liquidation are entirely within the dose limits adopted in Russia for the management of man-made radiation sources, and are consistent with ICRP recommendations and national practice in other countries. The proposed criteria for STS remediation and new industrial (non-radiation-hazardous) facilities and buildings on

  16. Composite waste analysis system

    International Nuclear Information System (INIS)

    Wachter, J.R.; Hagan, R.C.; Bonner, C.A.; Malcom, J.E.; Camp, K.L.

    1993-01-01

    Nondestructive analysis (NDA) of radioactive waste forms an integral component of nuclear materials accountability programs and waste characterization acceptance criterion. However, waste measurements are often complicated by unknown isotopic compositions and the potential for concealment of special nuclear materials in a manner that is transparent to gamma-ray measurement instruments. To overcome these complications, a new NDA measurement system has been developed to assay special nuclear material in both transuranic and low level waste from the same measurement platform. The system incorporates a NaI detector and customized commercial software routines to measure small quantities of radioactive material in low level waste. Transuranic waste analysis is performed with a coaxial HPGE detector and uses upgraded PC-based segmented gamma scanner software to assay containers up to 55 gal. in volume. Gamma-Ray isotopics analysis of both waste forms is also performed with this detector. Finally, a small neutron counter using specialized software is attached to the measurement platform to satisfy safeguards concerns related to nuclear materials that are not sensed by the gamma-ray instruments. This report describes important features and capabilities of the system and presents a series of test measurements that are to be performed to define system parameters

  17. Clean option: An alternative strategy for Hanford Tank Waste Remediation. Volume 2, Detailed description of first example flowsheet

    Energy Technology Data Exchange (ETDEWEB)

    Swanson, J.L.

    1993-09-01

    Disposal of high-level tank wastes at the Hanford Site is currently envisioned to divide the waste between two principal waste forms: glass for the high-level waste (HLW) and grout for the low-level waste (LLW). The draft flow diagram shown in Figure 1.1 was developed as part of the current planning process for the Tank Waste Remediation System (TWRS), which is evaluating options for tank cleanup. The TWRS has been established by the US Department of Energy (DOE) to safely manage the Hanford tank wastes. It includes tank safety and waste disposal issues, as well as the waste pretreatment and waste minimization issues that are involved in the ``clean option`` discussed in this report. This report describes the results of a study led by Pacific Northwest Laboratory to determine if a more aggressive separations scheme could be devised which could mitigate concerns over the quantity of the HLW and the toxicity of the LLW produced by the reference system. This aggressive scheme, which would meet NRC Class A restrictions (10 CFR 61), would fit within the overall concept depicted in Figure 1.1; it would perform additional and/or modified operations in the areas identified as interim storage, pretreatment, and LLW concentration. Additional benefits of this scheme might result from using HLW and LLW disposal forms other than glass and grout, but such departures from the reference case are not included at this time. The evaluation of this aggressive separations scheme addressed institutional issues such as: radioactivity remaining in the Hanford Site LLW grout, volume of HLW glass that must be shipped offsite, and disposition of appropriate waste constituents to nonwaste forms.

  18. Field Sampling and Analysis Plan for the Remedial Investigation of Waste Area Grouping 2 at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1992-10-01

    This report provides responses to US Environmental Protection Agency Region IV EPA-M and Tennessee Department of Environment and Conservation Oversite Division (TDEC-O) comments on report ORNL/ER-58, Field Sampling and Analysis Plan for the Remedial Investigation of Waste Area Grouping 2 at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Waste Area Grouping (WAG) 2 consists of the White Oak Creek (WOC) drainage system downgradient of the major ORNL WAGs in the WOC watershed. A strategy for the remedial investigation (RI) of WAG2 was developed in report ES/ER-14 ampersand Dl, Remedial Investigation Plan for Waste Area Grouping 2 at Oak Ridge National Laboratory, Oak Ridge, Tennessee. This strategy takes full advantage of WAG2's role as an integrator of contaminant releases from the ORNL WAGs in the WOC watershed, and takes full advantage of WAG2's role as a conduit for contaminants from the ORNL site to the Clinch River. The strategy calls for a multimedia environmental monitoring and characterization program to be conducted in WAG2 while upgradient contaminant sources are being remediated. This monitoring and characterization program will (1) identify and quantify contaminant fluxes, (2) identify pathways of greatest concern for human health and environmental risk, (3) improve conceptual models of contaminant movement, (4) support the evaluation of remedial alternatives, (5) support efforts to prioritize sites for remediation, (6) document the reduction in contaminant fluxes following remediation, and (7) support the eventual remediation of WAG2. Following this strategy, WAG2 has been termed an ''integrator WAG,'' and efforts in WAG2 over the short term are directed toward supporting efforts to remediate the contaminant ''source WAGS'' at ORNL

  19. Reduction of radioactive waste from remediation of uranium-contaminated soil

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Il Gook; Kim, Seung Soo; Kim, Gye Nam; Han, Gyu Seong; Choi, Jong Won [Decontamination and Decommissioning Research Division, Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2016-06-15

    Great amounts of solid radioactive waste (second waste) and waste solution are generated from the remediation of uranium-contaminated soil. To reduce these, we investigated washing with a less acidic solution and recycling the waste solution after removal of the dominant elements and uranium. Increasing the pH of the washing solution from 0.5 to 1.5 would be beneficial in terms of economics. A high content of calcium in the waste solution was precipitated by adding sulfuric acid. The second waste can be significantly reduced by using sorption and desorption techniques on ampholyte resin S-950 prior to the precipitation of uranium at pH 3.0.

  20. Reduction of radioactive waste from remediation of uranium-contaminated soil

    International Nuclear Information System (INIS)

    Kim, Il Gook; Kim, Seung Soo; Kim, Gye Nam; Han, Gyu Seong; Choi, Jong Won

    2016-01-01

    Great amounts of solid radioactive waste (second waste) and waste solution are generated from the remediation of uranium-contaminated soil. To reduce these, we investigated washing with a less acidic solution and recycling the waste solution after removal of the dominant elements and uranium. Increasing the pH of the washing solution from 0.5 to 1.5 would be beneficial in terms of economics. A high content of calcium in the waste solution was precipitated by adding sulfuric acid. The second waste can be significantly reduced by using sorption and desorption techniques on ampholyte resin S-950 prior to the precipitation of uranium at pH 3.0

  1. RFID technology for environmental remediation and radioactive waste management

    International Nuclear Information System (INIS)

    Tsai, Hanchung; Liu, Yung Y.; Shuler, James

    2011-01-01

    An advanced Radio Frequency Identification (RFID) system capable of tracking and monitoring a wide range of materials and components - from fissionable stocks to radioactive wastes - has been developed. The system offers a number of advantages, including enhanced safety, security and safeguards, reduced personnel exposure to radiation, and improved inventory control and cost-effectiveness. Using sensors, RFID tags can monitor the state of health of the tracked items and trigger alarms instantly when the normal ranges are violated. Nonvolatile memories in the tags can store sensor data, event records, as well as a contents manifest. Gamma irradiation tests showed that the tag components possess significant radiation resistance. Long-life batteries and smart management circuitries permit the tags to operate for up to 10 years without battery replacement. The tags have a near universal form factor, i.e., they can fit different package types. The read range is up to >100 m with no line-of-sight required. With careful implementation, even a large-size processing or storage facility with a complex configuration can be monitored with a handful of readers in a network. In transportation, by incorporating Global Positioning System (GPS), satellite/cellular communication technology, and secure Internet, situation awareness is assured continuously. The RFID system, when integrated with Geographic Information System (GIS) technology, can promptly provide content- and event-specific information to first responders and emergency management teams in case of incidents. In stand-alone applications, the monitoring and tracking data are contained within the local computer. With a secure Internet, information can be shared within the complex or even globally in real time. As with the deployment of any new technology, overcoming the cultural resistance is part of the developmental process. With a strong institutional support and multiple successful live demonstrations, the cultural

  2. Final remediation of the provisional storage near Zavratec. Separation of waste, decontamination and radiological measurements

    International Nuclear Information System (INIS)

    Stepisnik, M.; Zeleznik, N.; Mele, I.

    2000-01-01

    This paper presents remedial activities in Zavratec during winter 1999 - 2000. The difficult and slow process of separation radioactive from non-radioactive waste is explained, and the measuring techniques and equipment for separation are presented. The measurements of storage contamination and its decontamination, involving different practical problems, are described in detail. As a result, the initial volume of the waste was reduced to 50%, in spite of the extended decontamination works. The waste has been relocated to the Brinje storage facility. Measurements inside and outside the Zavratec facility after decontamination showed that no radioactivity higher than the natural background was present. The facility was released for unrestricted use. (author)

  3. Environmental Impact and Remediation of Uranium Tailings and Waste Rock Dumps at Mailuu-Suu in Kyrgyzstan

    International Nuclear Information System (INIS)

    Kunze, C.; Walter, U.; Wagner, F.; Schmidt, P.; Barnekow, U.; Gruber, A.

    2011-01-01

    This paper describes the environmental situation in the former uranium mining and milling region of Mailuu-Suu (Kyrgyzstan), the approach to environmental remediation of the waste facilities (tailings ponds and waste dumps) and the results achieved so far. It starts with an outline of the history of the environmental remediation project which has received international attention and is seen as a pilot project for further remediation activities of former uranium mining and milling sites in the region. Apart from technical aspects, the paper draws conclusions with respect to the administrative environment, institutional capacity building and the local availability of resources needed to successfully implement a complex remediation project. (author)

  4. Flare pits wastes remediation by low temperature oxidation

    International Nuclear Information System (INIS)

    Catalan, L. J. L.; Jamaluddin, A. K. M.; Mehta, R.; Moore, R. G.; Okazawa, N.; Ursenbach, M.

    1997-01-01

    The remediation of contaminated soil in oilfield sites, flare pits in particular, is subject to strict environmental regulations. Most current remediation techniques such as biological or thermal treatment are not particularly effective in highly contaminated sites, or effective only at costs that are considered prohibitive. This contribution describes a cost-effective method for the treatment of contaminated soil in-situ. The proposed treatment involves low temperature oxidation which converts the hydrocarbons in the contaminated soil to inert coke. In laboratory studies contaminated soil was oxidized with air at temperatures between 150 degrees C and 170 degrees C for three weeks. After the three week treatment extractable hydrocarbon levels were reduced to less than 0.1 per cent. Bioassays also demonstrated that toxicity associated with hydrocarbons was eliminated. Salts and metals remaining in the soil after treatment were removed by leaching with water. Low temperature oxidation requires no special equipment; it can occur under conditions and with equipment that are readily available in an oilfield setting. 5 refs., 8 tabs., 7 figs

  5. Solid phase bio-electrofermentation of food waste to harvest value-added products associated with waste remediation.

    Science.gov (United States)

    Chandrasekhar, K; Amulya, K; Mohan, S Venkata

    2015-11-01

    A novel solid state bio-electrofermentation system (SBES), which can function on the self-driven bioelectrogenic activity was designed and fabricated in the laboratory. SBES was operated with food waste as substrate and evaluated for simultaneous production of electrofuels viz., bioelectricity, biohydrogen (H2) and bioethanol. The system illustrated maximum open circuit voltage and power density of 443 mV and 162.4 mW/m(2), respectively on 9 th day of operation while higher H2 production rate (21.9 ml/h) was observed on 19th day of operation. SBES system also documented 4.85% w/v bioethanol production on 20th day of operation. The analysis of end products confirmed that H2 production could be generally attributed to a mixed acetate/butyrate-type of fermentation. Nevertheless, the presence of additional metabolites in SBES, including formate, lactate, propionate and ethanol, also suggested that other metabolic pathways were active during the process, lowering the conversion of substrate into H2. SBES also documented 72% substrate (COD) removal efficiency along with value added product generation. Continuous evolution of volatile fatty acids as intermediary metabolites resulted in pH drop and depicted its negative influence on SBES performance. Bio-electrocatalytic analysis was carried out to evaluate the redox catalytic capabilities of the biocatalyst. Experimental data illustrated that solid-state fermentation can be effectively integrated in SBES for the production of value added products with the possibility of simultaneous solid waste remediation. Copyright © 2015 Elsevier Ltd. All rights reserved.

  6. Remedial Action Plan for Expanded Bioventing System Facility 6454

    National Research Council Canada - National Science Library

    1996-01-01

    This draft remedial action plan (RAP) presents the scope for an expanded bioventing system for in situ treatment of fuel-contaminated soils at Site 6454 at Vandenberg Air Force Base (AFB), California...

  7. Process Knowledge Characterization of Radioactive Waste at the Classified Waste Landfill Remediation Project Sandia National Laboratories, Albuquerque, New Mexico

    International Nuclear Information System (INIS)

    DOTSON, PATRICK WELLS; GALLOWAY, ROBERT B.; JOHNSON JR, CARL EDWARD

    1999-01-01

    This paper discusses the development and application of process knowledge (PK) to the characterization of radioactive wastes generated during the excavation of buried materials at the Sandia National Laboratories/New Mexico (SNL/NM) Classified Waste Landfill (CWLF). The CWLF, located in SNL/NM Technical Area II, is a 1.5-acre site that received nuclear weapon components and related materials from about 1950 through 1987. These materials were used in the development and testing of nuclear weapon designs. The CWLF is being remediated by the SNL/NM Environmental Restoration (ER) Project pursuant to regulations of the New Mexico Environment Department. A goal of the CWLF project is to maximize the amount of excavated materials that can be demilitarized and recycled. However, some of these materials are radioactively contaminated and, if they cannot be decontaminated, are destined to require disposal as radioactive waste. Five major radioactive waste streams have been designated on the CWLF project, including: unclassified soft radioactive waste--consists of soft, compatible trash such as paper, plastic, and plywood; unclassified solid radioactive waste--includes scrap metal, other unclassified hardware items, and soil; unclassified mixed waste--contains the same materials as unclassified soft or solid radioactive waste, but also contains one or more Resource Conservation and Recovery Act (RCRA) constituents; classified radioactive waste--consists of classified artifacts, usually weapons components, that contain only radioactive contaminants; and classified mixed waste--comprises radioactive classified material that also contains RCRA constituents. These waste streams contain a variety of radionuclides that exist both as surface contamination and as sealed sources. To characterize these wastes, the CWLF project's waste management team is relying on data obtained from direct measurement of radionuclide activity content to the maximum extent possible and, in cases where

  8. Remediation of petroleum hydrocarbon polluted systems: Exploiting ...

    African Journals Online (AJOL)

    African Journal of Biotechnology ... others often result in pollution of the environment, thus creating serious imbalance in the biotic and abiotic regimes of the ecosystem. Several remediation alternatives have been in use for the restoration of ... In this paper, we present an overview of bioremediation alternative vis-à-vis other ...

  9. Reduction of waste solution volume generated on electrokinetic remediation

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Gye-Nam; Koo, Dae-Seo; Kim, Seung-Soo; Jeong, Jung-Whan; Han, Gyu-Seong; Moon, Jei-Kwon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-05-15

    In this study, for the reduction of volume of metal oxides generated in cathode chamber, the optimum pH of waste electrolyte in cathode chamber were drawn out through several experiments with the manufactured electrokinetic decontamination equipment. Also, the required time to reach to below the clearance concentration level for self- disposal was estimated through experiments using the manufactured electrokinetic decontamination equipment. A diagram of soil decontamination process for the removal of uranium from contaminated soil was drawn out. The optimum pH of waste electrolyte in cathode chamber for the reduction of volume of metal oxides was below 2.35. Also, when the initial uranium concentration of the soils were 7-20 Bq/g, the required times to reach to below the clearance concentration level for self- disposal were 25-40 days. A diagram of soil decontamination process for the removal of uranium from contaminated soil was drawn out.

  10. Isotope Specific Remediation Media and Systems - 13614

    Energy Technology Data Exchange (ETDEWEB)

    Denton, Mark S.; Mertz, Joshua L. [Kurion, Inc. Oak Ridge, Tennessee 37831 (United States); Morita, Keisuke [Japan Atomic Energy Agency, Tokai Research and Development Center, Fukushima Project Team, Tokai-mura, Ibaraki-ken, 319-1195 (Japan)

    2013-07-01

    On March 11, 2011, now two years ago, the magnitude 9.0 Great East Japan earthquake, Tohoku, hit off the Fukushima coast of Japan. While, of course, most of the outcome of this unprecedented natural and manmade disaster was a negative, both in Japan and worldwide, there have been some extremely invaluable lessons learned and new emergency recovery technologies and systems developed. As always, the mother of invention is necessity. Among these developments has been the development and full-scale implementation of proven isotope specific media (ISMs) with the intent of surgically removing specific hazardous isotopes for the purpose of minimizing dose to workers and the environment. The first such ISMs to be deployed at the Fukushima site were those removing cesium (Cs-137) and iodine (I-129). Since deployment on June 17, 2011, along with treated cooling water recycle, some 70% of the curies in the building liquid wastes have been removed by the Kurion system alone. The current levels of cesium are now only 2% of the original levels. Such an unprecedented, 'external cooling system' not only allowed the eventual cold shut down of the reactors in mid-December, 2011, but has allowed workers to concentrate on the cleanup of other areas of the site. Water treatment will continue for quite some time due to continued leakage into the buildings and the eventual goal of cleaning up the reactors and fuel pools themselves. With the cesium removal now in routine operation, other isotopes of concern are likely to become priorities. One such isotope is that of strontium, and yttrium (Sr-90 and Y-90), which is still at original levels causing further dose issues as well as impediments to discharge of the treated waste waters. For over a year now, a new synthetic strontium specific media has been under development and testing both in our licensed facility in Oak Ridge, Tennessee, but also in confirmatory tests by the Japan Atomic Energy Agency (JAEA) in Japan for Tokyo

  11. Case history update: RCRA waste site remediation by telerobotic methods

    International Nuclear Information System (INIS)

    Yemington, C.R.; Stone, J.

    1992-01-01

    This paper presents a summary of the first 18 months of closure work at the Kerr Hollow Quarry site on the DOE reservation at Oak Ridge, Tennessee. Closure work includes recovery and processing of explosive, toxic and radioactive waste. As of January 1992, more than 10,000 items had been processed and removed from the quarry, exclusively by remotely operated equipment. Drums, buckets, tubing assemblies and other containers are being shredded to react any explosive contents. Concussion and projectiles are controlled by operating the shredder under 30 feet of water. The performance of the shredder, the effectiveness of the approach, production rates and maintenance requirements are addressed in the paper. To avoid exposing personnel to hazards, all work in the restricted area is done remotely. Two remotely operated vehicles were used to clear a pad, set a stand and install the 200-hp shredder. Some materials exposed by shredding are stable in water but react when exposed to air. In addition, radioactive items are mixed in with the other wastes. Safety considerations have therefore led to use of remote techniques for handling and examining materials after recovery. Deteriorated gas cylinders, which may contain pressurized toxic materials, are recovered and handled exclusively by remotely operated equipment. Waste retrieval work at the Kerr Hollow Quarry has proven the capability and cost-effectiveness of remotely operated equipment to deal with a wide variety of hazardous materials in an unstructured waste site environment. A mixture of radioactive materials, toxic chemicals, explosives and asbestos has been found and processed. Remotely operated vehicles have retrieved, sorted and processed more than 10,000 items including drums, buckets, pipe manifolds, gas cylinders and other containers

  12. Radioecological condition assessment and remediation criteria for sites of spent fuel and radioactive waste storage in the russian northwest

    International Nuclear Information System (INIS)

    Shandala, Nataliya; Titov, Alex; Novikova, Natalia; Kiselev, Mikhail; Romanov, Vladimir; Sneve, Malgorzata; Smith, Graham

    2008-01-01

    The Norwegian Radiation Protection Authority and the Federal Medical-Biological Agency of the Russian Federation have a regulatory cooperation programme which is concerned with management of the nuclear legacy in northwest Russia, and, in particular, the remediation of facilities for spent fuel and radioactive waste management at the former Shore Technical Bases at Andreeva Bay and Gremikha Village. New regulatory guidance documents have been developed, necessary because of the special abnormal situation at these sites, now designated as Sites of Temporary Storage, but also because of the transition from military to civilian regulatory supervision and the evolving regulatory system in the Russian Federation. This paper presents the progress made and on-going projects in 2008 which involve development of the radio-ecological basis for identifying radiation supervision area boundaries and a system of recommended dose constraints and derived control levels for protection of workers and the public. Unconditional guarantee of long-term radioecological protection serves as the basis for criteria development. Non-exceedance of these dose constraints and control levels implies compliance with radiological protection objectives related to the residual contamination. Dose reduction below proposed dose constraint values must also be carried out according to the optimization principle. A number of remediation strategies are considered, corresponding to different future land use assumptions, including interim continued use in a nuclear context. The developed criteria relate to conditions of facilities and surrounding areas at the sites of temporary storage after completion of their remediation, and during the interim stages of remediation, depending upon the remediation strategy adopted. (author)

  13. Protecting Lake Ontario - Treating Wastewater from the Remediated Low-Level Radioactive Waste Management Facility - 13227

    Energy Technology Data Exchange (ETDEWEB)

    Freihammer, Till; Chaput, Barb [AECOM, 99 Commerce Drive, Winnipeg, Manitoba, R3P 0Y7 (Canada); Vandergaast, Gary [Atomic Energy of Canada Limited, Port Hope, Ontario (Canada); Arey, Jimi [Public Works and Government Services Canada, Ontario (Canada)

    2013-07-01

    The Port Granby Project is part of the larger Port Hope Area Initiative, a community-based program for the development and implementation of a safe, local, long-term management solution for historic low level radioactive waste (LLRW) and marginally contaminated soils (MCS). The Port Granby Project involves the relocation and remediation of up to 0.45 million cubic metres of such waste from the current Port Granby Waste Management Facility located in the Municipality of Clarington, Ontario, adjacent to the shoreline of Lake Ontario. The waste material will be transferred to a new suitably engineered Long-Term Waste Management Facility (LTWMF) to be located inland approximately 700 m from the existing site. The development of the LTWMF will include construction and commissioning of a new Wastewater Treatment Plant (WWTP) designed to treat wastewater consisting of contaminated surface run off and leachate generated during the site remediation process at the Port Granby Waste Management Facility as well as long-term leachate generated at the new LTWMF. Numerous factors will influence the variable wastewater flow rates and influent loads to the new WWTP during remediation. The treatment processes will be comprised of equalization to minimize impacts from hydraulic peaks, fine screening, membrane bioreactor technology, and reverse osmosis. The residuals treatment will comprise of lime precipitation, thickening, dewatering, evaporation and drying. The distribution of the concentration of uranium and radium - 226 over the various process streams in the WWTP was estimated. This information was used to assess potential worker exposure to radioactivity in the various process areas. A mass balance approach was used to assess the distribution of uranium and radium - 226, by applying individual contaminant removal rates for each process element of the WTP, based on pilot scale results and experience-based assumptions. The mass balance calculations were repeated for various flow

  14. Protecting Lake Ontario - Treating Wastewater from the Remediated Low-Level Radioactive Waste Management Facility - 13227

    International Nuclear Information System (INIS)

    Freihammer, Till; Chaput, Barb; Vandergaast, Gary; Arey, Jimi

    2013-01-01

    The Port Granby Project is part of the larger Port Hope Area Initiative, a community-based program for the development and implementation of a safe, local, long-term management solution for historic low level radioactive waste (LLRW) and marginally contaminated soils (MCS). The Port Granby Project involves the relocation and remediation of up to 0.45 million cubic metres of such waste from the current Port Granby Waste Management Facility located in the Municipality of Clarington, Ontario, adjacent to the shoreline of Lake Ontario. The waste material will be transferred to a new suitably engineered Long-Term Waste Management Facility (LTWMF) to be located inland approximately 700 m from the existing site. The development of the LTWMF will include construction and commissioning of a new Wastewater Treatment Plant (WWTP) designed to treat wastewater consisting of contaminated surface run off and leachate generated during the site remediation process at the Port Granby Waste Management Facility as well as long-term leachate generated at the new LTWMF. Numerous factors will influence the variable wastewater flow rates and influent loads to the new WWTP during remediation. The treatment processes will be comprised of equalization to minimize impacts from hydraulic peaks, fine screening, membrane bioreactor technology, and reverse osmosis. The residuals treatment will comprise of lime precipitation, thickening, dewatering, evaporation and drying. The distribution of the concentration of uranium and radium - 226 over the various process streams in the WWTP was estimated. This information was used to assess potential worker exposure to radioactivity in the various process areas. A mass balance approach was used to assess the distribution of uranium and radium - 226, by applying individual contaminant removal rates for each process element of the WTP, based on pilot scale results and experience-based assumptions. The mass balance calculations were repeated for various flow

  15. Sandia National Laboratories Chemical Waste Landfill: Innovative strategies towards characterization and remediation

    International Nuclear Information System (INIS)

    Ardito, Cynthia P.; Parsons, Alva M.; Lindgren, Eric R.; Phelan, James M.; Mattson, Earl D.

    1992-01-01

    The Chemical Waste Landfill (CWL) was used by Sandia National Laboratories (SNL), Albuquerque for disposal of hazardous chemicals from the years 1962 to 1985. During routine sampling in the spring of 1990, low levels of trichloroethylene (TCE) were detected in groundwater samples from a water table aquifer approximately 146 meters below ground surface. Therefore, a RCRA Site Investigation (RSI) has been initiated and remediation of organic contaminants will be performed at the CWL prior to closure of this landfill. The RSI is focused on optimal characterization of the volatile organic contamination (VOC) and dense non-aqueous phase liquid (DNAPL) contamination at this site. This will be possible through application of innovative strategies for characterization and promising new technologies which are discussed in this paper. The first part of this paper provides a discussion of conceptual models of VOC and DNAPL transport at the CWL and an overview of our investigative strategy. Each stage of the RSI has been developed to gather information which will reduce the uncertainty in the design of each subsequent phase of the investigation. Three stages are described; a source characterization stage, unsaturated zone characterization stage, and a saturated zone characterization stage. An important focus of the unsaturated zone characterization phase is to provide all data necessary to make decisions concerning the necessity of additional saturated zone characterization. The second part of this paper presents a brief discussion of some innovative approaches to characterization and remediation that are being applied at the CWL. Through the. SNL Environmental Restoration Program's desire to find new and improved methods for site characterization and remediation, several innovative technologies have been identified. These technologies include: the surface towed arrays developed by the Naval Research Laboratory for use in locating buried ordinance, core drilling using sonic

  16. New sorbents and ion exchangers for nuclear waste solution remediation

    International Nuclear Information System (INIS)

    Clearfield, A.; Peng, G.Z.; Cahill, R.A.; Bellinghausen, P.; Aly, H.I.; Scott, K.; Wang, J.D.

    1993-01-01

    There is now a concerted effort underway to clean up the accumulated nuclear wastes as the major sites around the country. Because of the complexity of the mixtures in the holding tanks highly specific exchangers are required to fulfill a multitude of desired tasks. These include removal of Cs + , Sr 2+ , Tc, Actinides and possible recovery of rare and precious metals. No one exchanger or sequestrant can accomplish these tasks and a variety of exchangers in a multistep process will be required. The behavior of a number of inorganic ion exchangers in a multistep process will be required. The behavior of a number of inorganic ion exchangers and new organo-inorganic exchangers towards Cs + , Sr 2+ and rare-earth ions in acid and basic media will be described. Preliminary data on the effect of high levels of sodium nitrate on the uptake of these ions will also be presented, as well as the changes observed in selectivity in simulated waste solutions. A possible separation scheme based on these data will be described

  17. Management of legacy spent nuclear fuel wastes at the Chalk River Laboratories: operating experience and progress towards waste remediation

    International Nuclear Information System (INIS)

    Cox, D.S.; Bainbridge, I.B.; Greenfield, K.R.

    2006-01-01

    AECL has been managing and storing a diversity of spent nuclear fuel, arising from operations at its Chalk River Laboratories (CRL) site over more than 50 years. A subset of about 22 tonnes of research reactor fuels, primarily metallic uranium, have been identified as a high priority for remediation, based on monitoring and inspection that has determined that these fuels and their storage containers are corroding. This paper describes the Fuel Packaging and Storage (FPS) project, which AECL has launched to retrieve these fuels from current storage, and to emplace them in a new above-ground dry storage system, as a prerequisite step to decommissioning some of the early-design waste storage structures at CRL. The retrieved fuels will be packaged in a new storage container, and subjected to a cold vacuum drying process that will remove moisture, and thereby reduce the extent of future corrosion and degradation. The FPS project will enable improved interim storage to be implemented for legacy fuels at CRL, until a decision is made on the ultimate disposition of legacy fuels in Canada. (author)

  18. An overview of the hazardous waste remedial actions program: hazardous and mixed waste activities for the U.S. Departments of energy and defense

    International Nuclear Information System (INIS)

    Craig, Robert B.; Rothermich, Nancy E.

    1991-01-01

    In May 1987 all mixed waste generated at the U.S. Department of Energy (DOE) facilities became jointly regulated by the U.S. Environmental Protection Agency (EPA) and DOE. The Department of Defense (DOD) generates hazardous wastes and is also regulated by the EPA. To maintain or attain compliance, both DOE and DOD have initiated compliance activities on all hazardous and mixed waste streams. This compliance includes the development of innovative technologies and processes to avoid the generation of hazardous and mixed wastes, development of technologies to treat the process wastes that are unavoidably generated, development of technologies to restore the environment where wastes have been released to the environment, the cleanup of asbestos and the monitoring of radon in federal facilities, the completion of remedial investigation/feasibility studies, and development of the data systems that are necessary to compile this information. This paper will describe each of these activities as they relate to compliance with the Resource Conservation and Recovery Act and/or CERCLA and their implementing regulations

  19. Oxalic acid as an assisting agent for the electrodialytic remediation of chromated copper arsenate treated timber waste

    DEFF Research Database (Denmark)

    Ribeiro, Alexandra B.; Mateus, Eduardo P.; Ottosen, Lisbeth M.

    1999-01-01

    The electrodialytic process is proposed as a technique for the remediation of chromated copper arsenate treated timber waste, using oxalic acid as assisting agent. The method prowed succesfull 93% Cu, 95% Cr and 99% As was removed from the timber.......The electrodialytic process is proposed as a technique for the remediation of chromated copper arsenate treated timber waste, using oxalic acid as assisting agent. The method prowed succesfull 93% Cu, 95% Cr and 99% As was removed from the timber....

  20. Project Strategy For The Remediation And Disposition Of Legacy Transuranic Waste At The Savannah River Site, South Carolina, USA

    International Nuclear Information System (INIS)

    Rodriguez, M.

    2010-01-01

    This paper discusses the Savannah River Site Accelerated Transuranic (TRU) Waste Project that was initiated in April of 2009 to accelerate the disposition of remaining legacy transuranic waste at the site. An overview of the project execution strategy that was implemented is discussed along with the lessons learned, challenges and improvements to date associated with waste characterization, facility modifications, startup planning, and remediation activities. The legacy waste was generated from approximately 1970 through 1990 and originated both on site as well as at multiple US Department of Energy sites. Approximately two thirds of the waste was previously dispositioned from 2006 to 2008, with the remaining one third being the more hazardous waste due to its activity (curie content) and the plutonium isotope Pu-238 quantities in the waste. The project strategy is a phased approach beginning with the lower activity waste in existing facilities while upgrades are made to support remediation of the higher activity waste. Five waste remediation process lines will be used to support the full remediation efforts which involve receipt of the legacy waste container, removal of prohibited items, venting of containers, and resizing of contents to fit into current approved waste shipping containers. Modifications have been minimized to the extent possible to meet the accelerated goals and involve limited upgrades to address life safety requirements, radiological containment needs, and handling equipment for the larger waste containers. Upgrades are also in progress for implementation of the TRUPACT III for the shipment of Standard Large Boxes to the Waste Isolation Pilot Plant, the US TRU waste repository. The use of this larger shipping container is necessary for approximately 20% of the waste by volume due to limited size reduction capability. To date, approximately 25% of the waste has been dispositioned, and several improvements have been made to the overall processing

  1. Treatment Study Plan for Nitrate Salt Waste Remediation Revision 1.0

    Energy Technology Data Exchange (ETDEWEB)

    Juarez, Catherine L. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Funk, David John [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Vigil-Holterman, Luciana R. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Naranjo, Felicia Danielle [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2016-03-07

    The two stabilization treatment methods that are to be examined for their effectiveness in the treatment of both the unremediated and remediated nitrate salt wastes include (1) the addition of zeolite and (2) cementation. Zeolite addition is proposed based on the results of several studies and analyses that specifically examined the effectiveness of this process for deactivating nitrate salts. Cementation is also being assessed because of its prevalence as an immobilization method used for similar wastes at numerous facilities around the DOE complex, including at Los Alamos. The results of this Treatment Study Plan will be used to provide the basis for a Resource Conservation and Recovery Act (RCRA) permit modification request of the LANL Hazardous Waste Facility Permit for approval by the New Mexico Environment Department-Hazardous Waste Bureau (NMED-HWB) of the proposed treatment process and the associated facilities.

  2. Review of selected 100-N waste sites related to N-Springs remediation projects

    International Nuclear Information System (INIS)

    DeFord, D.H.; Carpenter, R.W.

    1996-01-01

    This document has been prepared in support of the environmental restoration program at the US Department of Energy's Hanford Site near Richland, Washington, by the Bechtel Hanford, Inc. Facility and Waste Site Research Office. It provides historical information that documents and characterizes selected waste sites that are related to the N-Springs remediation projects. The N-Springs are a series of small, inconspicuous groundwater seepage springs located along the Columbia River shoreline near the 100-N Reactor. The spring site is hydrologically down-gradient from several 100-N Area liquid waste sites that are believed to have been the source(s) of the effluents being discharged by the springs. This report documents and characterizes these waste sites, including the 116-N-1 Crib and Trench, 116-N-3 Crib and Trench, unplanned releases, septic tariks, and a backwash pond

  3. DOE underground storage tank waste remediation chemical processing hazards. Part I: Technology dictionary

    International Nuclear Information System (INIS)

    DeMuth, S.F.

    1996-10-01

    This document has been prepared to aid in the development of Regulating guidelines for the Privatization of Hanford underground storage tank waste remediation. The document has been prepared it two parts to facilitate their preparation. Part II is the primary focus of this effort in that it describes the technical basis for established and potential chemical processing hazards associated with Underground Storage Tank (UST) nuclear waste remediation across the DOE complex. The established hazards involve those at Sites for which Safety Analysis Reviews (SARs) have already been prepared. Potential hazards are those involving technologies currently being developed for future applications. Part I of this document outlines the scope of Part II by briefly describing the established and potential technologies. In addition to providing the scope, Part I can be used as a technical introduction and bibliography for Regulatory personnel new to the UST waste remediation, and in particular Privatization effort. Part II of this document is not intended to provide examples of a SAR Hazards Analysis, but rather provide an intelligence gathering source for Regulatory personnel who must eventually evaluate the Privatization SAR Hazards Analysis

  4. Radioisotope waste processing systems

    International Nuclear Information System (INIS)

    Machida, Tadashi

    1978-01-01

    The Atomic Energy Safety Bureau established the policy entitled ''On Common Processing System of Radioactive Wastes'' consulting with the Liaison Committee of Radioactive Waste Processing. Japan Atomic Energy Research Institute (JAERI) and Japan Radioisotope Association (JRIA) had been discussing the problems required for the establishment of the common disposal facilities based on the above policy, and they started the organization in spring, 1978. It is a foundation borrowing equipments from JAERI though installing newly some of them not available from JAERI, and depending the fund on JRIA. The operation expenses will be borne by those who want to dispose the wastes produced. The staffs are sent out from JAERI and JRIA. For animal wastes contaminated with RI, formaldehyde dipping should be abolished, but drying and freezing procedures will be taken before they are burnt up in a newly planned exclusive furnace with disposing capacity of 50 kg/hour. To settle the problems of other wastes, enough understanding and cooperation of users are to be requested. (Kobatake, H.)

  5. Double-shell tank waste system assessment status and schedule

    International Nuclear Information System (INIS)

    Walter, E.J.

    1995-01-01

    The integrated program for completing the integrity assessments of the dangerous waste tank systems managed by the Tank Waste Remediation System (TWRS) Division of Westinghouse Hanford Company is presented in the Tank Waste Remediation System Tank System Integrity Assessments Program Plan, WHC-SD-AP017, Rev. 1. The program plan identified the assessment requirements and the general scope to which these requirements applied. Some of these assessment requirements have been met and others are either in process of completion or scheduled to be worked. To define the boundary of the double-shell tank (DST) system and the boundaries of the DST system components (or system parts) for the purpose of performing integrity assessment activities; To identify the planned activities to meet the assessment requirements for each component; Provide the status of the assessment activities; and Project a five year assessment activity schedule

  6. A conceptual chemical solidification/stabilization system to remediate radioactive raffinate sludge

    International Nuclear Information System (INIS)

    Carpenter, D.J.; Ansted, J.P.; Foldyna, J.T.

    1994-01-01

    Past operations at the U.S. Department of Energy's (DOE) Weldon Spring, Missouri, Superfund Site included the manufacture of nitroaromatic-based munitions and the production of uranium and thorium metal from ore concentrates. These operations generated a large quantity of diverse contaminated waste media including raffinate sludge, soil, sediment, and building debris. These various waste media are contaminated with varying amounts of radionuclides nitroaromatics, metals, metalloids, non-metals, polychlorinated biphenyls (PCBs) and asbestos. The volumes and diversity of contaminants and waste media pose significant challenges in identifying applicable remedial technologies, particularly for the excavation and treatment of the water-rich raffinate sludge. This paper presents the results of comprehensive efforts to develop a conceptual chemical solidification/stabilization (CSS) system to treat a variety of waste media. The emphasis of this paper is the treatment of a water-rich refractory raffinate sludge and site contaminated soils both radioactive and nonradioactive. The conceptual system design includes raffinate sludge excavation, dewatering, and CSS processing (reagent selection and formulation, reagent and waste storage and metering, and product mixing). Many innovations were incorporated into the design, producing a system that can process the various waste types. Additionally, the radioactive and hazardous constituents are sufficiently immobilized to allow the secured disposal in a waste cell of the treated product. The conceptual CSS system can also produce a variety of treated product types, ranging from a monolithic form to a compactible soil-like medium. The advantages of this system flexibility are also presented

  7. Applicability of petroleum horizontal drilling technology to hazardous waste site characterization and remediation

    International Nuclear Information System (INIS)

    Goranson, C.

    1992-09-01

    Horizontal wells have the potential to become an important tool for use in characterization, remediation and monitoring operations at hazardous waste disposal, chemical manufacturing, refining and other sites where subsurface pollution may develop from operations or spills. Subsurface pollution of groundwater aquifers can occur at these sites by leakage of surface disposal ponds, surface storage tanks, underground storage tanks (UST), subsurface pipelines or leakage from surface operations. Characterization and remediation of aquifers at or near these sites requires drilling operations that are typically shallow, less than 500-feet in depth. Due to the shallow nature of polluted aquifers, waste site subsurface geologic formations frequently consist of unconsolidated materials. Fractured, jointed and/or layered high compressive strength formations or compacted caliche type formations can also be encountered. Some formations are unsaturated and have pore spaces that are only partially filled with water. Completely saturated underpressured aquifers may be encountered in areas where the static ground water levels are well below the ground surface. Each of these subsurface conditions can complicate the drilling and completion of wells needed for monitoring, characterization and remediation activities. This report describes some of the equipment that is available from petroleum drilling operations that has direct application to groundwater characterization and remediation activities. A brief discussion of petroleum directional and horizontal well drilling methodologies is given to allow the reader to gain an understanding of the equipment needed to drill and complete horizontal wells. Equipment used in river crossing drilling technology is also discussed. The final portion of this report is a description of the drilling equipment available and how it can be applied to groundwater characterization and remediation activities

  8. Remedial action assessment system (RAAS) - A computer-based methodology for conducting feasibility studies

    International Nuclear Information System (INIS)

    Buelt, J.L.; Stottlemyre, J.A.; White, M.K.

    1991-01-01

    Because of the great complexity and number of potential waste sites facing the US Department of Energy (DOE) for potential cleanup, the DOE is supporting the development of a computer-based methodology to streamline the remedial investigation/feasibility study process required for DOE operable units. DOE operable units are generally more complex in nature because of the existence of multiple waste sites within many of the operable units and the presence of mixed radioactive and hazardous chemical wastes. Consequently, Pacific Northwest Laboratory (PNL) is developing the Remedial Action Assessment System (RAAS), which is aimed at screening, linking, and evaluating established technology process options in support of conducting feasibility studies under the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA). It is also intended to do the same in support of corrective measures studies required by the Resource Conservation and Recovery Act (RCRA). One of the greatest attributes of the RAAS project is that the computer interface with the user is being designed to be friendly, intuitive, and interactive. Consequently, the user interface employs menus, windows, help features, and graphical information while RAAS is in operation. During operation, each technology process option is represented by an open-quotes objectclose quotes module. Object-oriented programming is then used to link these unit processes into remedial alternatives. In this way, various object modules representing technology process options can communicate so that a linked set of compatible processes form an appropriate remedial alternative. Once the remedial alternatives are formed, they can be evaluated in terms of effectiveness, implementability, and cost

  9. Biofilm treatment of soil for waste containment and remediation

    International Nuclear Information System (INIS)

    Turner, J.P.; Dennis, M.L.; Osman, Y.A.; Chase, J.; Bulla, L.A.

    1997-01-01

    This paper examines the potential for creating low-permeability reactive barriers for waste treatment and containment by treating soils with Beijerinckia indica, a bacterium which produces an exopolysaccharide film. The biofilm adheres to soil particles and causes a decrease in soil hydraulic conductivity. In addition, B. Indica biodegrades a variety of polycyclic aromatic hydrocarbons and chemical carcinogens. The combination of low soil hydraulic conductivity and biodegradation capabilities creates the potential for constructing reactive biofilm barriers from soil and bacteria. A laboratory study was conducted to evaluate the effects of B. Indica on the hydraulic conductivity of a silty sand. Soil specimens were molded with a bacterial and nutrient solution, compacted at optimum moisture content, permeated with a nutrient solution, and tested for k sat using a flexible-wall permeameter. Saturated hydraulic conductivity (k sat ) was reduced from 1 x 10 -5 cm/sec to 2 x 10 -8 cm/sec: by biofilm treatment. Permeation with saline, acidic, and basic solutions following formation of a biofilm was found to have negligible effect on the reduced k sat , for up to three pore volumes of flow. Applications of biofilm treatment for creating low-permeability reactive barriers are discussed, including compacted liners for bottom barriers and caps and creation of vertical barriers by in situ treatment

  10. Maintenance study for W-340 Waste Retrieval System

    International Nuclear Information System (INIS)

    Christensen, C.; Conner, C.C.; Sekot, J.P.

    1994-05-01

    This study was performed to identify attributes and maintainability requirements for the Tank Waste Retrieval System (TWRS). The system will be developed for Westinghouse Hanford Company in Richland, Washington, as an integrated system to perform waste removal in Tank C-106 and, thus, demonstrate technologies for tank remediation that will satisfy requirements of the Tri-Party Agreement. The study examines attributes of the TWRS, scope of maintenance operations required for the TWRS, maintenance requirements, and potential methods of performing maintenance functions. Recommendations are provided for consideration in the development of both the conceptual design and performance specification, which will be used in procuring the W-340 Waste Retrieval System

  11. Alternatives for management of wastes generated by the formerly utilized sites remedial action program and supplement

    International Nuclear Information System (INIS)

    Gilbert, T.L.; Peterson, J.M.; Vocke, R.W.; Alexander, J.K.

    1983-03-01

    Alternatives for disposal or stabilization of the wastes generated by the US Department of Energy's Formerly Utilized Sites Remedial Action Program (FUSRAP) are identified and compared, with emphasis on the long-term aspects. These wastes consist of soil material and rubble containing trace amounts of radionuclides. A detailed pathway analysis for the dose to the maximally exposed individual is carried out using an adaptation of the natural analogue method. Comparisons of the different alternatives, based on the results of the pathway analysis and qualitative cost considerations, indicate that, if the hazard is such that the wastes must be removed and disposed of rather than stabilized in place, disposal by immediate dispersal is preferable to containment, and containment followed by slow planned dispersal is preferable to containment without dispersal. The Supplement presents refinements of work that was reported at the 1982 International Decommissioning Symposium. The new material consists of revisions of the estimates of the predicted potential dose to the maximally exposed individual and a more detailed comparative assessment of the radiological impacts of alternatives for management of wastes generated by the US Department of Energy's Formerly Utilized Sites Remedial Action Program (FUSRAP)

  12. Rover waste assay system

    Energy Technology Data Exchange (ETDEWEB)

    Akers, D.W.; Stoots, C.M.; Kraft, N.C.; Marts, D.J. [Idaho National Engineering Lab., Idaho Falls, ID (United States)

    1997-11-01

    The Rover Waste Assay System (RWAS) is a nondestructive assay system designed for the rapid assay of highly-enriched {sup 235}U contaminated piping, tank sections, and debris from the Rover nuclear rocket fuel processing facility at the Idaho Chemical Processing Plant. A scanning system translates a NaI(Tl) detector/collimator system over the structural components where both relative and calibrated measurements for {sup 137}Cs are made. Uranium-235 concentrations are in operation and is sufficiently automated that most functions are performed by the computer system. These functions include system calibration, problem identification, collimator control, data analysis, and reporting. Calibration of the system was done through a combination of measurements on calibration standards and benchmarked modeling. A description of the system is presented along with the methods and uncertainties associated with the calibration and analysis of the system for components from the Rover facility. 4 refs., 2 figs., 4 tabs.

  13. Rover waste assay system

    International Nuclear Information System (INIS)

    Akers, D.W.; Stoots, C.M.; Kraft, N.C.; Marts, D.J.

    1997-01-01

    The Rover Waste Assay System (RWAS) is a nondestructive assay system designed for the rapid assay of highly-enriched 235 U contaminated piping, tank sections, and debris from the Rover nuclear rocket fuel processing facility at the Idaho Chemical Processing Plant. A scanning system translates a NaI(Tl) detector/collimator system over the structural components where both relative and calibrated measurements for 137 Cs are made. Uranium-235 concentrations are in operation and is sufficiently automated that most functions are performed by the computer system. These functions include system calibration, problem identification, collimator control, data analysis, and reporting. Calibration of the system was done through a combination of measurements on calibration standards and benchmarked modeling. A description of the system is presented along with the methods and uncertainties associated with the calibration and analysis of the system for components from the Rover facility. 4 refs., 2 figs., 4 tabs

  14. Comparative life-cycle cost analysis for low-level mixed waste remediation alternatives

    International Nuclear Information System (INIS)

    Jackson, J.A.; White, T.P.; Kloeber, J.M.; Toland, R.J.; Cain, J.P.; Buitrago, D.Y.

    1995-03-01

    The purpose of this study is two-fold: (1) to develop a generic, life-cycle cost model for evaluating low-level, mixed waste remediation alternatives, and (2) to apply the model specifically, to estimate remediation costs for a site similar to the Fernald Environmental Management Project near Cincinnati, OH. Life-cycle costs for vitrification, cementation, and dry removal process technologies are estimated. Since vitrification is in a conceptual phase, computer simulation is used to help characterize the support infrastructure of a large scale vitrification plant. Cost estimating relationships obtained from the simulation data, previous cost estimates, available process data, engineering judgment, and expert opinion all provide input to an Excel based spreadsheet for generating cash flow streams. Crystal Ball, an Excel add-on, was used for discounting cash flows for net present value analysis. The resulting LCC data was then analyzed using multi-attribute decision analysis techniques with cost and remediation time as criteria. The analytical framework presented allows alternatives to be evaluated in the context of budgetary, social, and political considerations. In general, the longer the remediation takes, the lower the net present value of the process. This is true because of the time value of money and large percentage of the costs attributed to storage or disposal

  15. Waste management facility remediation and decommissioning at a national nuclear research site

    International Nuclear Information System (INIS)

    Cameron, D.J.; Dolinar, G.M.; Killey, R.W.D.

    1994-01-01

    Historic waste management practices at eight locations on AECL's Chalk River site have resulted in the formation of contaminated groundwater plumes, some of which have surfaced and contaminated surface materials. A priority setting process has been used to establish a plan of attack that will lead to the eventual decommissioning of these facilities. In general terms, the preferred approach is to install impermeable covers to prevent further leaching of waste sources and to prevent escape of leachate to the biosphere, followed by cleanup of surface contamination and remediation of aquifers. Final disposal of the waste sources would be delayed for perhaps 20 years. Substantial progress has been made in the treatment of contaminated groundwater, with one field installation in place and another under development. This paper describes how the prioritization task was tackled to produce a long term plan of action and describes initial interventions that have been attempted and their results. 4 refs., 3 tabs., 3 figs

  16. The role of performance assessment in the evaluation of remedial action alternatives for the Radioactive Waste Management Complex (RWMC) at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Rood, A.S.; Case, M.J.

    1988-01-01

    The Idaho National Engineering Laboratory (INEL) is operated by the Department of Energy (DOE) and is involved in nuclear research and development. The Radioactive Waste Management Complex (RWMC) at the INEL serves as a disposal facility for low level radioactive wastes generated onsite. Transuranic (TRU) wastes received from other DOE sites are currently stored at the RWMC, but were buried at the facility from 1952 until 1970. Recent findings of the Subsurface Investigations Program have determined that migration of TRU nuclides and hazardous materials from the RWMC has occurred. The primary source of organics in the buried TRU waste was generated by the Rocky Flats Plant. The INEL has proposed an aggressive four-year action plan for buried TRU waste. As a part of this plan, a task has been identified to evaluate existing remedial technologies for preventing further contaminant migration or removing the source of TRU radionuclides and nonradioactive hazardous material from the RWMC. A systems approach is being applied to evaluate, compare and recommend technologies or combinations of technologies. One criterion used in the evaluation is the net risk reduction afforded by each proposed remedial action. The method used to develop the criterion relies on models to assess the potential pathways and scenarios for the migration of radioactive and nonradioactive materials and the subsequent exposure of individuals to those materials. This paper describes the approach used to assess the performance of various remedial actions and the results obtained to date

  17. Development of inorganic ion exchangers for nuclear waste remediation. 1997 annual progress report

    International Nuclear Information System (INIS)

    Clearfield, A.; Collins, J.L.; Egan, B.Z.

    1997-01-01

    'In this research program, Oak Ridge National Laboratory (ORNL) is collaborating with Texas A and M University in the development of highly selective inorganic ion exchangers for the removal of cesium and strontium from nuclear tank-waste and from groundwater. Inorganic ion exchangers are developed and characterized at Texas A and M University; ORNL is involved in preparing the powders in engineered forms and testing the performance of the sorbents in actual nuclear waste solutions. The Texas A and M studies are divided into two main categories: (1) exchangers for tank wastes and (2) exchangers for groundwater remediation. These are subdivided into exchangers for use in acid and alkaline solutions for tank wastes and those that can be recycled for use in groundwater remediation. The exchangers will also be considered for in situ immobilization of radionuclides. The approach will involve a combination of exchanger synthesis, structural characterization, and ion exchange behavior. ORNL has developed a technique for preparing inorganic ion exchangers in the form of spherules by a gel-sphere internal gelation process. This technology, which was developed and used for making nuclear fuels, has the potential of greatly enhancing the usability of many other special inorganic materials because of the improved flow dynamics of the spherules. Also, pure inorganic spherules can be made without the use of binders. ORNL also has access to actual nuclear waste in the form of waste tank supernatant solutions for testing the capabilities of the sorbents for removing the cesium and strontium radionuclides from actual waste solutions. The ORNL collaboration will involve the preparation of the powdered ion exchangers, developed and synthesized at Texas A and M, in the form of spherules, and evaluating the performance of the exchangers in real nuclear waste solutions. Selected sorbents will be provided by Texas A and M for potential incorporation into microspheres, and the performance

  18. DOE Hazardous Waste Remedial Actions Program: Annual report, FY 1986

    International Nuclear Information System (INIS)

    Eyman, L.D.

    1987-05-01

    The activities of HAZWRAP for the past fiscal year were organized into seven principal areas: technical analysis and technology transfer; regulatory analysis; strategic planning;information systems; program administration; technology adaptation; and technology demonstration. The scope, major FY 1986 accomplishments, and future directions for each of these areas are described in the following sections of this report. Listings of reports produced through the SCO are given in Appendixes A and B for the current year and since the program started, respectively

  19. Simulant composition for the Mixed Waste Management Facility (MWMF) groundwater remediation project

    International Nuclear Information System (INIS)

    Siler, J.L.

    1992-01-01

    A project has been initiated at the request of ER to study and remediate the groundwater contamination at the Mixed Waste Management Facility (MWMF). This water contains a wide variety of both inorganics (e.g., sodium) and organics (e.g., benzene, trichloroethylene). Most compounds are present in the ppB range, and certain components (e.g., trichloroethylene, silver) are present at concentrations that exceed the primary drinking water standards (PDWS). These compounds must be reduced to acceptable levels as per RCRA and CERCLA orders. This report gives a listing of the important constituents which are to be included in a simulant to model the MWMF aquifer. This simulant will be used to evaluate the feasibility of various state of the art separation/destruction processes for remediating the aquifer

  20. The use of historical imagery in the remediation of an urban hazardous waste site

    Science.gov (United States)

    Slonecker, E.T.

    2011-01-01

    The information derived from the interpretation of historical aerial photographs is perhaps the most basic multitemporal application of remote-sensing data. Aerial photographs dating back to the early 20th century can be extremely valuable sources of historical landscape activity. In this application, imagery from 1918 to 1927 provided a wealth of information about chemical weapons testing, storage, handling, and disposal of these hazardous materials. When analyzed by a trained photo-analyst, the 1918 aerial photographs resulted in 42 features of potential interest. When compared with current remedial activities and known areas of contamination, 33 of 42 or 78.5% of the features were spatially correlated with areas of known contamination or other remedial hazardous waste cleanup activity.

  1. Anthropology and decision making about chronic technological disasters: Mixed waste remediation on the Oak Ridge Reservation

    International Nuclear Information System (INIS)

    Wolfe, A.K.; Schweitzer, M.

    1996-01-01

    This paper discusses two related case studies of decision making about the remediation of mixed (hazardous and radioactive) wastes on the Oak Ridge Reservation in Tennessee. The three goals of the paper are to (1) place current decision-making efforts in the varied and evolving social, political, regulatory, economic, and technological contexts in which they occur; (2) present definitions and attributes of open-quotes successfulclose quotes environmental decision making from the perspectives of key constituency groups that participate in decision making; and (3) discuss the role of anthropology in addressing environmental decision making. Environmental decision making about remediation is extraordinarily complex, involving human health and ecological risks; uncertainties about risks, technological ability to clean up, the financial costs of clean up; multiple and sometimes conflicting regulations; social equity and justice considerations; and decreasing budgets. Anthropological theories and methods can contribute to better understanding and, potentially, to better decision making

  2. Evolution of EPA/DOE technical cooperation in remediation of radiation/mixed waste contaminated sites

    International Nuclear Information System (INIS)

    Dyer, Robert S.; Garcia-Frias, Beverly; Wolbarst, Anthony B.; Coe, Larry J.

    1992-01-01

    The EPA Office of Radiation Programs (ORP) and the DOE Office of Environmental Restoration and Waste Management (EM) are cooperating in efforts related to restoration of radioactive and mixed waste sites. The impetus for these efforts derived from DOE's need to perform restoration activities according to CERCLA/RCRA requirements, and from ORP's role as a supplier of radiation expertise to federal agencies. These activities include: assessing remediation technology, developing radioanalytical protocols; matching cleanup technologies to soil characteristics; developing a process for the evaluation, selection, and appropriate use of groundwater models; reviewing incinerator practices; and addressing technical issues associated with the WIPP. Cooperative projects planned for the future include: evaluation of methodologies for streamlining the restoration process; assessment of the applicability of process knowledge for waste characterization; evaluation of recycling of radioactive metals; and expansion of selected environmental protection initiatives at the International Atomic Energy Agency (IAEA). Public acceptance is a crucial component of the remediation process. An underlying objective of these cooperative initiatives is to address issues of concern to the public in an open and honest fashion. (author)

  3. Superfund record of decision (EPA Region 4): Whitehouse Waste Oil Pits Site, Duval County, Jacksonville, FL. (First remedial action), (Amendment), June 1992. Final report

    International Nuclear Information System (INIS)

    1992-01-01

    The 7-acre Whitehouse Waste Oil Pits site was used by Allied Petroleum Products (Allied) to dispose of acidic waste oil sludges from its oil reclamation process in Whitehouse, Duval County, Florida. A cypress swamp system and residential area are immediately adjacent to the site. The acid sludge produced in the first step and clay used to decolorize the oil were dumped into the unlined pits at the site. A 1985 ROD addressed source control as a containment remedy consisting of a slurry wall construction, soil cap, and a ground water recovery and treatment system; however, EPA has re-evaluated the 1985 ROD selection and determined that the containment remedy failed to meet the requirements of SARA. As a result, the ROD Amendment focuses on an alternative for treating Whitehouse wastes by eliminating direct contact risk associated with pit soil/sludge wastes and preventing contaminated ground water in the surficial aquifer from migrating laterally. The primary contaminants of concern that affect the soil, sediment, surface water, and ground water are VOCs, including benzene, toluene, and xylenes; organics, including PCBs and phenols; and metals, including arsenic, chromium, and lead. The amended remedial action for the site are included

  4. In situ vitrification: A new process for waste remediation

    International Nuclear Information System (INIS)

    Fitzpatrick, V.F.; Timmerman, C.L.; Buelt, J.L.

    1987-07-01

    In situ vitrification is a thermal treatment process that converts contaminated soil into a chemically inert, stable glass and crystalline product. A square array of four electrodes are inserted into the ground to the desired treatment depth. Because the soil is not electrically conductive once the moisture has been driven off, a conductive mixture of flaked graphite and glass frit is placed among the electrodes to act as the starter path. An electrical potential is applied to the electrodes, which establishes an electrical current in the starter path. The resultant power heats the starter path and surrounding soil up to 3600 0 F, well above the normal fusion temperature of soil of between 2000 and 2500 0 F. The graphite starter path is eventually consumed by oxidation, and the current is transferred to the molten soil, which is now electrically conductive. As the vitrified zone grows, it incorporates nonvolatile elements and destroys organic components by pyrolysis. The pyrolyzed byproducts migrate to the surface of the vitrified zone, where they combust in the presence of oxygen. A hood placed over the processing area provides confinement for the combustion gases, and the gases are drawn into the off-gas treatment system. 8 refs., 7 figs., 2 tabs

  5. Waste heat recovery system

    International Nuclear Information System (INIS)

    Phi Wah Tooi

    2010-01-01

    Full text: The Konzen in-house designed anaerobic digester system for the POME (Palm Oil Mill Effluent) treatment process is one of the registered Clean Development Mechanism (CDM) projects in Malaysia. It is an organic wastewater treatment process which achieves excellent co-benefits objectives through the prevention of water pollution and reduction of greenhouse gas emissions, which is estimated to be 40,000 to 50,000 t-CO 2 per year. The anaerobic digester was designed in mesophile mode with temperature ranging from 37 degree Celsius to 45 degree Celsius. A microorganisms growth is optimum under moderately warm temperature conditions. The operating temperature of the anaerobic digester needs to be maintained constantly. There are two waste heat recovery systems designed to make the treatment process self-sustaining. The heat recovered will be utilised as a clean energy source to heat up the anaerobic digester indirectly. The first design for the waste heat recovery system utilises heat generated from the flue gas of the biogas flaring system. A stainless steel water tank with an internal water layer is installed at the top level of the flare stack. The circulating water is heated by the methane enriched biogas combustion process. The second design utilizes heat generated during the compression process for the biogas compressor operation. The compressed biogas needs to be cooled before being recycled back into the digester tank for mixing purposes. Both the waste heat recovery systems use a design which applies a common water circulation loop and hot water tank to effectively become a closed loop. The hot water tank will perform both storage and temperature buffer functions. The hot water is then used to heat up recycled sludge from 30 degree Celsius to 45 degree Celsius with the maximum temperature setting at 50 degree Celsius. The recycled sludge line temperature will be measured and monitored by a temperature sensor and transmitter, which will activate the

  6. Process development work plan for waste feed delivery system

    International Nuclear Information System (INIS)

    Papp, I.G.

    1998-01-01

    This work plan defines the process used to develop project definition for Waste Feed Delivery (WFD). Project definition provides the direction for development of definitive design media required for the ultimate implementation of operational processing hardware and software. Outlines for the major deliverables are attached as appendices. The implementation of hardware and software will accommodate requirements for safe retrieval and delivery of waste currently stored in Hanford's underground storage tanks. Operations and maintenance ensure the availability of systems, structures, and components for current and future planned operations within the boundary of the Tank Waste Remediation System (TWRS) authorization basis

  7. Hazardous Waste Remedial Actions Program requirements for quality control of analytical data

    International Nuclear Information System (INIS)

    Miller, M.S.; Zolyniak, J.W.

    1988-08-01

    The Hazardous Waste Remedial Action Program (HAZWRAP) is involved in performing field investigations and sample analysis pursuant to the NCP for the Department of Energy and other federal agencies. The purpose of this document is to specify the requirements for the control of the accuracy, precision and completeness of the samples, and data from the point of collection through analysis. The requirements include data reduction and reporting of the resulting environmentally related data. Because every instance and concern may not be addressed in this document, HAZWRAP subcontractors are encouraged to discuss any questions with the HAZWRAP Project Manager hereafter identified as the Project Manager

  8. Targeted Health Assessment for Wastes Contained at the Niagara Falls Storage Site to Guide Planning for Remedial Action Alternatives - 13428

    Energy Technology Data Exchange (ETDEWEB)

    Busse, John; Keil, Karen; Staten, Jane; Miller, Neil; Barker, Michelle [U.S. Army Corps of Engineers, Buffalo District, 1776 Niagara Street, Buffalo, NY (United States); MacDonell, Margaret; Peterson, John; Chang, Young-Soo; Durham, Lisa [Argonne National Laboratory, Environmental Science Division, 9700 S. Cass Ave., Argonne, IL 60439 (United States)

    2013-07-01

    The U.S. Army Corps of Engineers (USACE) is evaluating potential remedial alternatives at the 191-acre Niagara Falls Storage Site (NFSS) in Lewiston, New York, under the Formerly Utilized Sites Remedial Action Program (FUSRAP). The Manhattan Engineer District (MED) and Atomic Energy Commission (AEC) brought radioactive wastes to the site during the 1940's and 1950's, and the U.S. Department of Energy (US DOE) consolidated these wastes into a 10-acre interim waste containment structure (IWCS) in the southwest portion of the site during the 1980's. The USACE is evaluating remedial alternatives for radioactive waste contained within the IWCS at the NFSS under the Feasibility Study phase of the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) process. A preliminary evaluation of the IWCS has been conducted to assess potential airborne releases associated with uncovered wastes, particularly during waste excavation, as well as direct exposures to uncovered wastes. Key technical issues for this assessment include: (1) limitations in waste characterization data; (2) representative receptors and exposure routes; (3) estimates of contaminant emissions at an early stage of the evaluation process; (4) consideration of candidate meteorological data and air dispersion modeling approaches; and (5) estimates of health effects from potential exposures to both radionuclides and chemicals that account for recent updates of exposure and toxicity factors. Results of this preliminary health risk assessment indicate if the wastes were uncovered and someone stayed at the IWCS for a number of days to weeks, substantial doses and serious health effects could be incurred. Current controls prevent such exposures, and the controls that would be applied to protect onsite workers during remedial action at the IWCS would also effectively protect the public nearby. This evaluation provides framing context for the upcoming development and detailed

  9. Green remediation and recycling of contaminated sediment by waste-incorporated stabilization/solidification.

    Science.gov (United States)

    Wang, Lei; Tsang, Daniel C W; Poon, Chi-Sun

    2015-03-01

    Navigational/environmental dredging of contaminated sediment conventionally requires contained marine disposal and continuous monitoring. This study proposed a green remediation approach to treat and recycle the contaminated sediment by means of stabilization/solidification enhanced by the addition of selected solid wastes. With an increasing amount of contaminated sediment (20-70%), the 28-d compressive strength of sediment blocks decreased from greater than 10MPa to slightly above 1MPa. For augmenting the cement hydration, coal fly ash was more effective than lime and ground seashells, especially at low sediment content. The microscopic and spectroscopic analyses showed varying amounts of hydration products (primarily calcium hydroxide and calcium silicate hydrate) in the presence of coal fly ash, signifying the influence of pozzolanic reaction. To facilitate the waste utilization, cullet from beverage glass bottles and bottom ashes from coal combustion and waste incineration were found suitable to substitute coarse aggregate at 33% replacement ratio, beyond which the compressive strength decreased accordingly. The mercury intrusion porosimetry analysis indicated that the increase in the total pore area and average pore diameter were linearly correlated with the decrease of compressive strength due to waste replacement. All the sediment blocks complied with the acceptance criteria for reuse in terms of metal leachability. These results suggest that, with an appropriate mixture design, contaminated sediment and waste materials are useful resources for producing non-load-bearing masonry units or fill materials for construction uses. Copyright © 2014 Elsevier Ltd. All rights reserved.

  10. Waste Derived Sorbents and Their Potential Roles in Heavy Metal Remediation Applications

    Directory of Open Access Journals (Sweden)

    Chiang Y. W.

    2013-04-01

    Full Text Available Inorganic waste materials that have the suitable inherent characteristics could be used as precursors for the synthesis of micro- and mesoporous materials, which present great potential to be re-utilized as sorbent materials for heavy metal remediation. Three inorganic waste materials were studied in the present work: water treatment residuals (WTRs from an integrated drinking water/wastewater treatment plant, and fly ash and bottom ash samples from a municipal solid waste incinerator (MSWI. These wastes were converted into three sorbent materials: ferrihydrite-like materials derived from drying of WTRs, hydroxyapatite-like material derived from ultrasound assisted synthesis of MSWI fly ash with phosphoric acid solution, and a zeolitic material derived from alkaline hydrothermal conversion of MSWI bottom ash. The performance of these materials, as well as their equivalent commercially available counterparts, was assessed for the adsorption of multiple heavy metals (As, Cd, Co, Ni, Pb, Zn from synthetic solutions, contaminated sediments and surface waters; and satisfactory results were obtained. In addition, it was observed that the combination of sorbents into sorbent mixtures enhanced the performance levels and, where applicable, stabilized inherently mobile contaminants from the waste derived sorbents.

  11. A Simple and Effective Remedial Learning System with a Fuzzy Expert System

    Science.gov (United States)

    Lin, C.-C.; Guo, K.-H.; Lin, Y.-C.

    2016-01-01

    This study aims at implementing a simple and effective remedial learning system. Based on fuzzy inference, a remedial learning material selection system is proposed for a digital logic course. Two learning concepts of the course have been used in the proposed system: number systems and combinational logic. We conducted an experiment to validate…

  12. A Potential Bio-Sorbent for Heavy Metals in the Remediation of Waste Water

    Directory of Open Access Journals (Sweden)

    Mohammad Laskar

    2016-12-01

    Full Text Available Bay leaves are used for flavoring in cold drinks production, in bakery goods, sauces, confectionary products and liquors. The waste generated from these sources has been valorized by attempting the remediation of waste water. Hence, adsorption of toxic metals onto Bay leaves has been investigated after optimizing the experimental parameters, namely the pH, contact time, adsorbent and Zn (II concentrations as well as the temperature of the equilibrium mixture (consisting of the metal solution in contact with the adsorbent. The participation of the constituent functional groups, of the adsorbent, was ascertained with Fourier Transform spectroscopic studies. The mode of adsorption was examined by employing important isotherm models, namely Langmuir, Freundlich and Dubinin-Radushkevich models. The adsorption process was found to follow pseudo-first order kinetic model and also followed the intraparticle diffusion up to 60 minutes of contact time. The thermodynamic parameters suggest the spontaneous nature of adsorption

  13. High-level waste tank remediation technology integration summary. Revision 1

    International Nuclear Information System (INIS)

    DeLannoy, C.R.; Susiene, C.; Fowler, K.M.; Robson, W.M.; Cruse, J.M.

    1994-07-01

    The U.S. Department of Energy's Environmental Restoration and Waste Management and Technology Development Programs are engaged in a number of projects to develop, demonstrate, test, and evaluate new technologies to support the cleanup and site remediation of more than 300 underground storage tanks containing over 381,000 m 3 (100 million gal) of liquid radioactive mixed waste at the Hanford Reservation. Significant development is needed within primary functions and in determining an overall bounding strategy. This document is an update of continuing work to summarize the overall strategy and to provide data regarding technology development activities within the strategy. It is intended to serve as an information resource to support understanding, decision making, and integration of multiple program technology development activities. Recipients are encouraged to provide comments and input to the authors for incorporation in future revisions

  14. Remediation of a historically Pb contaminated soil using a model natural Mn oxide waste.

    Science.gov (United States)

    McCann, Clare M; Gray, Neil D; Tourney, Janette; Davenport, Russell J; Wade, Matthew; Finlay, Nina; Hudson-Edwards, Karen A; Johnson, Karen L

    2015-11-01

    A natural Mn oxide (NMO) waste was assessed as an in situ remediation amendment for Pb contaminated sites. The viability of this was investigated using a 10 month lysimeter trial, wherein a historically Pb contaminated soil was amended with a 10% by weight model NMO. The model NMO was found to have a large Pb adsorption capacity (qmax 346±14 mg g(-1)). However, due to the heterogeneous nature of the Pb contamination in the soils (3650.54-9299.79 mg kg(-1)), no treatment related difference in Pb via geochemistry could be detected. To overcome difficulties in traditional geochemical techniques due to pollutant heterogeneity we present a new method for unequivocally proving metal sorption to in situ remediation amendments. The method combines two spectroscopic techniques; namely electron probe microanalysis (EPMA) and X-ray photoelectron spectroscopy (XPS). Using this we showed Pb immobilisation on NMO, which were Pb free prior to their addition to the soils. Amendment of the soil with exogenous Mn oxide had no effect on microbial functioning, nor did it perturb the composition of the dominant phyla. We conclude that NMOs show excellent potential as remediation amendments. Copyright © 2015 The Authors. Published by Elsevier Ltd.. All rights reserved.

  15. Regulatory systems for the control of land remediation processes

    Energy Technology Data Exchange (ETDEWEB)

    Lowe, J.; Vijgen, J.; Summersgill, M.

    2003-07-01

    One of the recurring themes in looking at land remediation over the last decade has been identifying and overcoming barriers to the use of innovative, sustainable technologies, whilst still ensuring that there are no adverse environmental impacts from their use. In parallel with this, the regeneration of brownfield sites has increasingly needed effective and economic solutions that leave the site without the stigma of being associated with contamination and waste disposal. Regulatory controls are often identified as one of the main barriers to both of these objectives. Previously, the focus of attention in the study of regulatory controls relating to land contamination has largely been on regimes that trigger the need for clean-up. These may be pollution control legislation or land-use planning controls. However, the focus of this paper will be on the controls on the selection and implementation of the remediation technologies and processes themselves. It will look in particular at the European-wide controls on waste management, pollution prevention and environmental impact assessment. The UK work is being carried out by a working group involving: landowners; developers; public sector regeneration agencies; house-builders; industry; insurers; technology providers; professional advisers; local government authorities; and national government regulators and policy-makers. This multi-stakeholder approach has facilitated the identification of practical, legal, financial and administrative issues to assist in developing new solutions. (orig.)

  16. An assessment of dioxin contamination from the intermittent operation of a municipal waste incinerator in Japan and associated remediation.

    Science.gov (United States)

    Takeda, Nobuo; Takaoka, Masaki

    2013-04-01

    Significant dioxin (polychlorinated dibenzo-para-dioxins (PCDDs)/polychlorinated dibenzo-furans (PCDFs)) pollution from a municipal solid waste incinerator was discovered in 1997 in Osaka prefecture/Japan. The cause and mechanism of pollution was identified by a detailed assessment of the environment and incinerator plant. The primary sources of PCDD/PCDF pollution were high dioxin releases from an intermittently operated waste incinerator with PCDD/PCDF emissions of 150 ng-TEQ/Nm(3). PCDD/PCDF also accumulated in the wet scrubber system (3,000 μg TEQ/L) by adsorption and water recirculation in the incinerator. Scrubber water was air-cooled with a cooling tower located on the roof of the incinerator. High concentrations of dioxins in the cooling water were released as aerosols into the surrounding and caused heavy soil pollution in the area near the plant. These emissions were considered as the major contamination pathway from the plant. Decontamination and soil remediation in and around the incinerator plant were conducted using a variety of destruction technologies (including incineration, photochemical degradation and GeoMelt technology). Although the soil remediation process was successfully finished in December 2006 about 3% of the waste still remains. The case demonstrates that releases from incinerators which do not use best available technology or which are not operated according to best environmental practices can contaminate their operators and surrounding land. This significant pollution had a large impact on the Japanese government's approach toward controlling dioxin pollution. Since this incident, a ministerial conference on dioxins has successfully strengthened control measures.

  17. Sampling and analysis plan for remediation of Operable Unit 100-IU-3 waste site 600-104

    International Nuclear Information System (INIS)

    1997-08-01

    This sampling and analysis plan (SAP) presents the rationale and strategy for the sampling and analysis activities to support remediation of 100-IU-3 Operable Unit waste site 600-104. The purpose of the proposed sampling and analysis activities is to demonstrate that time-critical remediation of the waste site for soil containing 2,4-Dichlorophonoxyacetic acid salts and esters (2,4-D) and dioxin/furan isomers at concentrations that exceed cleanup levels has been effective. This shall be accomplished by sampling various locations of the waste site before and after remediation, analyzing the samples, and comparing the results to action levels set by the Washington State Department of Ecology

  18. Sampling and analysis plan for remediation of Operable Unit 100-IU-3 waste site 600-104. Revision 1

    International Nuclear Information System (INIS)

    1997-08-01

    This sampling and analysis plan presents the rationale and strategy for the sampling and analysis activities to support remediation of 100-IU-3 Operable Unit waste site 600-104. The purpose of the proposed sampling and analysis activities is to demonstrate that time-critical remediation of the waste site for soil containing 2,4-Dichlorophenoxyacetic acid salts and esters (2,4-D) and dioxin/furan isomers at concentrations that exceed cleanup levels has been effective. This shall be accomplished by sampling various locations of the waste site before and after remediation, analyzing the samples, and comparing the results to action levels set by the Washington State Department of Ecology

  19. Recent developments in health risks modeling techniques applied to hazardous waste site assessment and remediation

    International Nuclear Information System (INIS)

    Mendez, W.M. Jr.

    1990-01-01

    Remediation of hazardous an mixed waste sites is often driven by assessments of human health risks posed by the exposures to hazardous substances released from these sites. The methods used to assess potential health risk involve, either implicitly or explicitly, models for pollutant releases, transport, human exposure and intake, and for characterizing health effects. Because knowledge about pollutant fate transport processes at most waste sites is quite limited, and data cost are quite high, most of the models currently used to assess risk, and endorsed by regulatory agencies, are quite simple. The models employ many simplifying assumptions about pollutant fate and distribution in the environment about human pollutant intake, and toxicologic responses to pollutant exposures. An important consequence of data scarcity and model simplification is that risk estimates are quite uncertain and estimates of the magnitude uncertainty associated with risk assessment has been very difficult. A number of methods have been developed to address the issue of uncertainty in risk assessments in a manner that realistically reflects uncertainty in model specification and data limitations. These methods include definition of multiple exposure scenarios, sensitivity analyses, and explicit probabilistic modeling of uncertainty. Recent developments in this area will be discussed, along with their possible impacts on remediation programs, and remaining obstacles to their wider use and acceptance by the scientific and regulatory communities

  20. Cost benefit of caustic recycle for tank waste remediation at the Hanford and Savannah River Sites

    International Nuclear Information System (INIS)

    DeMuth, S.

    1998-01-01

    The potential cost savings due to the use of caustic recycle used in conjunction with remediation of radioactive underground storage tank waste, is shown in a figure for the Hanford and Savannah River sites. Two cost savings estimates for each case have been made for Hanford, and one cost savings estimate for each case have been made for Hanford, and one cost savings estimate for each case has been made for the Savannah River site. This is due to the Hanford site remediation effort being less mature than that of Savannah River; and consequently, a range of cost savings being more appropriate for Hanford. This range of cost savings (rather than a ingle value) for each case at Hanford is due to cost uncertainties related to the LAW immobilization operation. Caustic recycle Case-1 has been defined as the sodium required to meet al identified caustic needs for the entire Site. Case-2 has been defined as the maximum sodium which can be separated from the low activity waste without precipitation of Al(OH) 3 . It has been determined that the potential cost savings at Hanford ranges from $194 M to $215 M for Case-1, and $293 M to $324 M for Case-2. The potential cost savings at Savannah River are $186 M for Case-1 and $281 M for Case-2. A discussion of the uncertainty associated with these cost savings estimates can be found in the Discussion and Conclusions section

  1. The Gunite and Associated Tanks Remediation Project Tank Waste Retrieval Performance and Lessons Learned, vol. 1 [of 2

    Energy Technology Data Exchange (ETDEWEB)

    Lewis, BE

    2003-10-07

    The Gunite and Associated Tanks (GAAT) Remediation Project was the first of its kind performed in the United States. Robotics and remotely operated equipment were used to successfully transfer almost 94,000 gal of remote-handled transuranic sludge containing over 81,000 Ci of radioactive contamination from nine large underground storage tanks at the Oak Ridge National Laboratory (ORNL). The sludge was transferred with over 439,000 gal of radioactive waste supernatant and {approx}420,500 gal of fresh water that was used in sluicing operations. The GAATs are located in a high-traffic area of ORNL near a main thoroughfare. A phased and integrated approach to waste retrieval operations was used for the GAAT Remediation Project. The project promoted safety by obtaining experience from low-risk operations in the North Tank Farm before moving to higher-risk operations in the South Tank Farm. This approach allowed project personnel to become familiar with the tanks and waste, as well as the equipment, processes, procedures, and operations required to perform successful waste retrieval. By using an integrated approach to tank waste retrieval and tank waste management, the project was completed years ahead of the original baseline schedule, which resulted in avoiding millions of dollars in associated costs. This report is organized in two volumes. Volume 1 provides information on the various phases of the GAAT Remediation Project. It also describes the different types of equipment and how they were used. The emphasis of Volume 1 is on the description of the tank waste retrieval performance and the lessons learned during the GAAT Remediation Project. Volume 2 provides the appendixes for the report, which include the following information: (A) Background Information for the Gunite and Associated Tanks Operable Unit; (B) Annotated Bibliography; (C) Comprehensive Listing of the Sample Analysis Data from the GAAT Remediation Project; (D) GAAT Equipment Matrix; and (E) Vendor List

  2. Situating Remediation: Accommodating Success and Failure in Medical Education Systems.

    Science.gov (United States)

    Ellaway, Rachel H; Chou, Calvin L; Kalet, Adina L

    2018-03-01

    There has been a widespread shift to competency-based medical education (CBME) in the United States and Canada. Much of the CBME discourse has focused on the successful learner, with relatively little attention paid to what happens in CBME systems when learners stumble or fail. Emerging issues, such as the well-documented problem of "failure to fail" and concerns about litigious learners, have highlighted a need for well-defined and integrated frameworks to support and guide strategic approaches to the remediation of struggling medical learners.This Perspective sets out a conceptual review of current practices and an argument for a holistic approach to remediation in the context of their parent medical education systems. The authors propose parameters for integrating remediation into CBME and describe a model based on five zones of practice along with the rules of engagement associated with each zone. The zones are "normal" curriculum, corrective action, remediation, probation, and exclusion.The authors argue that, by linking and integrating theory and practice in remediation with CBME, a more integrated systems-level response to differing degrees of learner difficulty and failure can be developed. The proposed model demonstrates how educational practice in different zones is based on different rules, roles, responsibilities, and thresholds for moving between zones. A model such as this can help medical educators and medical education leaders take a more integrated approach to learners' failures as well as their successes by being more explicit about the rules of engagement that apply in different circumstances across the competency continuum.

  3. GIS-based tools to identify tradeoffs between waste management and remediation strategies from radiological dispersal device incidents

    Energy Technology Data Exchange (ETDEWEB)

    Lemieux, P.; Wood, J.; Snyder, E. [U.S. Environmental Protection Agency, Research Triangle Park, NC (United States); Boe, T. [Oak Ridge Inst. for Science and Education, Research Triangle Park, NC (United States); Schulthiesz, D.; Peake, T.; Ierardi, M. [U.S. Environmental Protection Agency, Washington, DC (United States); Hayes, C.; Rodgers, M. [Eastern Research Group, Inc., Morrisville, NC (United States)

    2011-07-01

    Management of waste and debris from the detonation of a Radiological Dispersal Device (RDD) will likely comprise a significant portion of the overall remediation effort and possibly contribute to a significant portion of the overall remediation costs. As part of the recent National Level Exercise, Liberty RadEx, that occurred in Philadelphia in April 2010, a methodology was developed by EPA to generate a first-order estimate of a waste inventory for the hypothetical RDD from the exercise scenario. Determination of waste characteristics and whether the generated waste is construction and demolition (C&D) debris, municipal solid waste (MSW), hazardous waste, mixed waste, or low level radioactive waste (LLRW), and characterization of the wastewater that is generated from the incident or subsequent cleanup activities will all influence the cleanup costs and timelines. Decontamination techniques, whether they involve chemical treatment, abrasive removal, or aqueous washing, will also influence the waste generated and associated cleanup costs and timelines. This paper describes the ongoing effort to develop a tool to support RDD planning and response activities by assessing waste quantities and characteristics as a function of potential mitigation strategies and targeted cleanup levels. (author)

  4. GIS-based tools to identify tradeoffs between waste management and remediation strategies from radiological dispersal device incidents

    International Nuclear Information System (INIS)

    Lemieux, P.; Wood, J.; Snyder, E.; Boe, T.; Schulthiesz, D.; Peake, T.; Ierardi, M.; Hayes, C.; Rodgers, M.

    2011-01-01

    Management of waste and debris from the detonation of a Radiological Dispersal Device (RDD) will likely comprise a significant portion of the overall remediation effort and possibly contribute to a significant portion of the overall remediation costs. As part of the recent National Level Exercise, Liberty RadEx, that occurred in Philadelphia in April 2010, a methodology was developed by EPA to generate a first-order estimate of a waste inventory for the hypothetical RDD from the exercise scenario. Determination of waste characteristics and whether the generated waste is construction and demolition (C&D) debris, municipal solid waste (MSW), hazardous waste, mixed waste, or low level radioactive waste (LLRW), and characterization of the wastewater that is generated from the incident or subsequent cleanup activities will all influence the cleanup costs and timelines. Decontamination techniques, whether they involve chemical treatment, abrasive removal, or aqueous washing, will also influence the waste generated and associated cleanup costs and timelines. This paper describes the ongoing effort to develop a tool to support RDD planning and response activities by assessing waste quantities and characteristics as a function of potential mitigation strategies and targeted cleanup levels. (author)

  5. Waste heat recovery system

    Energy Technology Data Exchange (ETDEWEB)

    Ernst, Timothy C.; Zigan, James A.

    2017-12-19

    A waste heat recovery system includes a Rankine cycle (RC) circuit having a pump, a boiler, an energy converter, and a condenser fluidly coupled via conduits in that order, to provide additional work. The additional work is fed to an input of a gearbox assembly including a capacity for oil by mechanically coupling to the energy converter to a gear assembly. An interface is positioned between the RC circuit and the gearbox assembly to partially restrict movement of oil present in the gear assembly into the RC circuit and partially restrict movement of working fluid present in the RC circuit into the gear assembly. An oil return line is fluidly connected to at least one of the conduits fluidly coupling the RC components to one another and is operable to return to the gear assembly oil that has moved across the interface from the gear assembly to the RC circuit.

  6. Measurement systems in the area of land remediation and soil segregation activities

    International Nuclear Information System (INIS)

    Simon, Gerold G.; Sokcic-Kostic, Marina; Auler, Ingolf; Eickelpasch, Ludger; Betts, Jonathan

    2007-01-01

    Available in abstract form only. Full text of publication follows: The remediation of radioactively contaminated land is a small but growing sector in the area of decommissioning of nuclear facilities. This also includes the material from buildings after demolition. Contamination comprises in general alpha and beta activities and emission of alpha, beta and gamma radiation. The measurement is in practice restricted to the measurement of gamma emission, because of the high penetration of material by gamma rays. All isotopes, which do not emit gammas are estimated on the basis of given relation between alpha and beta emitters without gamma radiation and emitters with gamma radiation. This method is called 'key nuclide method'. Whilst many studies have been completed, others still continue in the processing of large volumes of concrete, steel and soil. An important conclusion from these and similar research programs is that a significant proportion of the waste contains only low concentrations of radioactive nuclides. Therefore, much of the material from the remediation can be considered for 'free release'. It was often not possible to attain adequate specific information on these materials, so a measurement system is needed for their classification and characterization. NUKEM Technologies has practical experience in characterising and remediating of nuclear sites. Recently, it has pioneered the use of innovative in-situ and ex-situ characterisation and waste segregation technologies, which enhance the efficiency of remedial actions and provide assurance to customers, regulators and the public that all significant contamination has been removed and sites can be used for new purposes. (authors)

  7. Assessment of technologies for hazardous waste site remediation: Non-treatment technologies and pilot scale facility implementation -- monitoring technology

    International Nuclear Information System (INIS)

    Johnson, H.R.; Overbey, W.K. Jr.; Molnar, D.L.

    1994-02-01

    The objective of this study was to investigate and evaluate existing proven technologies for the monitoring of hazardous waste sites during remediation activities and to protect the health and safety of all related entities while complying with government regulations. The study began with a literature search to determine manufacturers and related instrumentation which would be applicable to the most complex (in terms of toxicity and mediums affected) sites. Criteria for monitoring and analyses were established and a functional analysis was performed to select the most appropriate instrumentation available. Gas Chromatography/Mass Spectrometry is the most widely accepted method for generating quantitative data given the characterization of the Winfield site. Fourier Transform Infrared Spectroscopy, while not a new technology, has the distinct advantage of measuring simultaneously hundreds of gaseous pollutants which can also be sparged from water and this technology received the highest score as per the functional analysis. To protect workers and the public surrounding remediation sites which are known to contain VOCs, on site monitoring prior to, and during the excavation operations, is recommended until enough data are obtained to assess the health risks to workers. The conclusion of this study is to recommend evaluation of both the mobile GC/MS and FTIR systems simultaneously in identical operating conditions

  8. Waste monitoring system for effluents

    International Nuclear Information System (INIS)

    Macdonald, J.M.; Gomez, B.; Trujillo, L.; Malcom, J.E.; Nekimken, H.; Pope, N.; Bibeau, R.

    1995-07-01

    The waste monitoring system in use at Los Alamos National Laboratory's Plutonium Facility, TA-55, is a computer-based system that proves real-time information on industrial effluents. Remote computers monitor discharge events and data moves from one system to another via a local area network. This report describes the history, system design, summary, instrumentation list, displays, trending screens, and layout of the waste monitoring system

  9. The Development and Evaluation of Listening and Speaking Diagnosis and Remedial Teaching System

    Science.gov (United States)

    Hsiao, Hsien-Sheng; Chang, Cheng-Sian; Lin, Chiou-Yan; Chen, Berlin; Wu, Chia-Hou; Lin, Chien-Yu

    2016-01-01

    In this study, a system was developed to offer adaptive remedial instruction materials to learners of Chinese as a foreign language (CFL). The Chinese Listening and Speaking Diagnosis and Remedial Instruction (CLSDRI) system integrated computerized diagnostic tests and remedial instruction materials to diagnose errors made in listening…

  10. ISS Internal Active Thermal Control System (IATCS) Coolant Remediation Project

    Science.gov (United States)

    Morrison, Russell H.; Holt, Mike

    2005-01-01

    The IATCS coolant has experienced a number of anomalies in the time since the US Lab was first activated on Flight 5A in February 2001. These have included: 1) a decrease in coolant pH, 2) increases in inorganic carbon, 3) a reduction in phosphate buffer concentration, 4) an increase in dissolved nickel and precipitation of nickel salts, and 5) increases in microbial concentration. These anomalies represent some risk to the system, have been implicated in some hardware failures and are suspect in others. The ISS program has conducted extensive investigations of the causes and effects of these anomalies and has developed a comprehensive program to remediate the coolant chemistry of the on-orbit system as well as provide a robust and compatible coolant solution for the hardware yet to be delivered. The remediation steps include changes in the coolant chemistry specification, development of a suite of new antimicrobial additives, and development of devices for the removal of nickel and phosphate ions from the coolant. This paper presents an overview of the anomalies, their known and suspected system effects, their causes, and the actions being taken to remediate the coolant.

  11. Disposal Notifications and Quarterly Membership Updates for the Utility Solid Waste Group Members’ Risk-Based Approvals to Dispose of PCB Remediation Waste Under Title 40 of the Code of Federal Regulations Section 761.61(c)

    Science.gov (United States)

    Disposal Notifications and Quarterly Membership Updates for the Utility Solid Waste Group Members’ Risk-Based Approvals to Dispose of Polychlorinated Biphenyl (PCB) Remediation Waste Under Title 40 of the Code of Federal Regulations Section 761.61(c)

  12. Decision support tools for evaluation and selection of technologies for soil remediation and disposal of halogenated waste

    Energy Technology Data Exchange (ETDEWEB)

    Khelifi, O.; Zinovyev, S.; Lodolo, A.; Vranes, S.; Miertus, S. [ICS-UNIDO, Trieste (Italy)

    2004-09-15

    One of the most justified demands in abating the pollution created by polychlorinated substances is the remediation of contaminated sites, mainly soil remediation, which is also the most complex technical task in removing pollution because of the necessity to process huge quantities of matrix and to account for numerous side factors. The commercial technologies are usually based on rather direct and simplified but also secure processes, which often approach remediation in a general way, where different types of pollutants can be decontaminated at the same time by each technology. A number of different soil remediation technologies are nowadays available and the continuous competition among environmental service companies and technology developers generates a further increase in the clean-up options. The demand for decision support tools that could help decision makers in selecting the most appropriate technology for the specific contaminated site has consequently increased. These decision support tools (DST) are designed to help decision makers (site owners, local community representatives, environmentalists, regulators, etc.) to assess available technologies and preliminarily select the preferred remedial options. The analysis for the identification of the most suitable options in the DST is based on technical, economic, environmental, and social criteria. These criteria are ranked by all parties involved in the decision process to determine their relative importance for a particular remediation project. The aim of the present paper is to present the new approach for building decision support tool to evaluate different technologies for remediation and disposal of halogenated waste.

  13. Evaluation of select trade-offs between ground-water remediation and waste minimization for petroleum refining industry

    International Nuclear Information System (INIS)

    Andrews, C.D.; McTernan, W.F.; Willett, K.K.

    1996-01-01

    An investigation comparing environmental remediation alternatives and attendant costs for a hypothetical refinery site located in the Arkansas River alluvium was completed. Transport from the land's surface to and through the ground water of three spill sizes was simulated, representing a base case and two possible levels of waste minimization. Remediation costs were calculated for five alternative remediation options, for three possible regulatory levels and alternative site locations, for four levels of technology improvement, and for eight different years. It is appropriate from environmental and economic perspectives to initiate significant efforts and expenditures that are necessary to minimize the amount and type of waste produced and disposed during refinery operations; or conversely, given expected improvements in technology, is it better to wait until remediation technologies improve, allowing greater environmental compliance at lower costs? The present work used deterministic models to track a light nonaqueous phase liquid (LNAPL) spill through the unsaturated zone to the top of the water table. Benzene leaching from LNAPL to the ground water was further routed through the alluvial aquifer. Contaminant plumes were simulated over 50 yr of transport and remediation costs assigned for each of the five treatment options for each of these years. The results of these efforts show that active remediation is most cost effective after a set point or geochemical quasi-equilibrium is reached, where long-term improvements in technology greatly tilt the recommended option toward remediation. Finally, the impacts associated with increasingly rigorous regulatory levels present potentially significant penalties for the remediation option, but their likelihood of occurrence is difficult to define

  14. Remediation measures at the former hazardous waste dump at Malsch near Heidelberg; Sanierung der ehemaligen Sonderabfalldeponie Malsch. Hydrogeologische Bewertung

    Energy Technology Data Exchange (ETDEWEB)

    Hanstein, P.; Hoetzl, H. [Karlsruhe Univ. (T.H.) (Germany). Lehrstuhl fuer Angewandte Geologie

    1998-12-31

    The former hazardous waste deposit of Malsch is located south of Heidelberg at the eastern margin of the Upper Rhine Graben. Using a former clay pit about 700.000 m{sup 3} of partly high toxic organic and inorganic wastes were deposited from 1971 to 1984. A leakage from the deposit was first recognised in 1984. Detailed investigation showed that thin channel-like conglomerate layers intercalated in the clays and marls as well as faults are cropping out into the base of the deposit and cause a direct seepage of leachate. Contaminants pollute the downstream area over a distance of 500 m. Remediation measures adding up to 100 Mio. DM were carried out including the construction of a slurry wall encircling laterally the whole site, a surface cover with a multi-liner system as well as a pump and treat system for the leachate was installed and are now in operation. Model studies of the ground water flow including a 3-dimensional site model and a 2-dimensional regional model started during the remediation work. According to the complex geological situation specific procedures was applied to transform the heterogeneous tectonical structure into the numerical models. The balance of water flowing through the deposit was calculated by the piezometric heads to assess different remediation stages. In spite of the missing impervious base the calculation could prove that in connection of a certain pumping rate of the leachate the environment and especially the groundwater can be protected from further leakage. (orig.) [Deutsch] Die fruehere Sonderabfalldeponie Malsch wurde 1971 in einer stillgelegten Tongrube suedlich von Heidelberg am oestlichen Rand des Oberrheingrabens angelegt und bis 1984 betrieben. Insgesamt wurden ueber 700.000 m{sup 3} zum Teil hochtoxische organische und anorganische Sonderabfaelle abgelagert. Mit Abschluss der Deponierungsphase wurden Sickerwasseraustritte im westlichen Deponievorfeld festgelstellt. Ursache fuer die Undichtigkeiten waren geringmaechtige

  15. Characterization and Potential Use of Biochar for the Remediation of Coal Mine Waste Containing Efflorescent Salts

    Directory of Open Access Journals (Sweden)

    Luis Carlos Díaz Muegue

    2017-11-01

    Full Text Available In open pit coal mining, soil and vegetation are removed prior to the start of mining activities, causing physical, chemical, and microbiological changes to the soil and landscape. The present work shows the results of an integrated study of the remediation of mine waste with a high level of salt contamination in areas of the Cesar Department (Colombia, employing biochar as an amendment. Physical-chemical properties including Munsell color, texture, pH, electrical conductivity, water-holding capacity, cation exchange capacity, metal content, organic carbon, sulfates, extractable P, and total nitrogen were characterized both in the soils contaminated with mine residues and the biochar sample. A high concentration of sulfates, calcium, iron, and aluminum and a significant presence of Na, followed by minor amounts of Mg, K, Cu, and Mn, were observed in efflorescent salts. X-ray diffraction indicated a high presence of quartz and gypsum and the absence of pyrite and Schwertmannite in the efflorescent salt, while showing broad peaks belonging to graphene sheets in the biochar sample. Soil remediation was evaluated in Petri dish seed germination bioassays using Brachiaria decumbens. Biochar was shown to be effective in the improvement of pH, and positively influenced the germination percentage and root length of Brachiaria grass seeds.

  16. Remediation of electronic waste polluted soil using a combination of persulfate oxidation and chemical washing.

    Science.gov (United States)

    Chen, Fu; Luo, Zhanbin; Liu, Gangjun; Yang, Yongjun; Zhang, Shaoliang; Ma, Jing

    2017-12-15

    Laboratory experiments were conducted to investigate the efficiency of a simultaneous chemical extraction and oxidation for removing persistent organic pollutants (POPs) and toxic metals from an actual soil polluted by the recycling activity of electronic waste. Various chemicals, including hydroxypropyl-β-cyclodextrin (HPCD), citric acid (CA) and sodium persulfate (SP) were applied synchronously with Fe 2+ activated oxidation to enhance the co-removal of both types of pollutants. It is found that the addition of HPCD can enhance POPs removal through solubilization of POPs and iron chelation; while the CA-chelated Fe 2+ activation process is effective for extracting metals and degrading residual POPs. Under the optimized reagent conditions, 69.4% Cu, 78.1% Pb, 74.6% Ni, 97.1% polychlorinated biphenyls, 93.8% polycyclic aromatic hydrocarbons, and 96.4% polybrominated diphenylethers were removed after the sequential application of SP-HPCD-Fe 2+ and SP-CA-Fe 2+ processes with a duration of 180 and 240 min, respectively. A high dehalogenation efficiency (84.8% bromine and 86.2% chlorine) is observed, suggesting the low accumulation of halogen-containing organic intermediates. The remediated soil can satisfy the national soil quality standard of China. Collectively, co-contaminated soil can be remediated with reasonable time and capital costs through simultaneous application of persulfate oxidation and chemical extraction. Copyright © 2017 Elsevier Ltd. All rights reserved.

  17. Determining the number of samples required for decisions concerning remedial actions at hazardous waste sites

    International Nuclear Information System (INIS)

    Skiles, J.L.; Redfearn, A.; White, R.K.

    1991-01-01

    The processing of collecting, analyzing, and assessing the data needed to make to make decisions concerning the cleanup of hazardous waste sites is quite complex and often very expensive. This is due to the many elements that must be considered during remedial investigations. The decision maker must have sufficient data to determine the potential risks to human health and the environment and to verify compliance with regulatory requirements, given the availability of resources allocated for a site, and time constraints specified for the completion of the decision making process. It is desirable to simplify the remedial investigation procedure as much as possible to conserve both time and resources while, simultaneously, minimizing the probability of error associated with each decision to be made. With this in mind, it is necessary to have a practical and statistically valid technique for estimating the number of on-site samples required to ''guarantee'' that the correct decisions are made with a specified precision and confidence level. Here, we will examine existing methodologies and then develop our own approach for determining a statistically defensible sample size based on specific guidelines that have been established for the risk assessment process

  18. New tailor-made bio-organoclays for the remediation of olive mill waste water

    International Nuclear Information System (INIS)

    Calabrese, Ilaria; Liveri, Maria Liria Turco; Gelardi, Giulia; Merli, Marcello; Sciascia, Luciana; Rytwo, Giora

    2013-01-01

    A systematic study aimed at obtaining new organoclays for the treatment of Olive Mill Waste water (OMW) has been performed. Several organoclays have been prepared by loading different amounts of the biocompatible surfactant Tween20 onto the K10 montmorillonite (MMT). Complementary kinetic and equilibrium studies on the adsorption of the Tween20 onto the MMT have been carried out and the characterization of the new tailor-made bio-materials has been performed by means of the XRD and FT-IR measurements. Finally the prepared bio-organoclays have been successfully applied for the OMW remediation and they proved to be highly effective in decreasing the organic content (OC) to an extent that depends on both the amount of loaded surfactant and the experimental protocols applied

  19. New tailor-made bio-organoclays for the remediation of olive mill waste water

    Science.gov (United States)

    Calabrese, Ilaria; Gelardi, Giulia; Merli, Marcello; Rytwo, Giora; Sciascia, Luciana; Liria Turco Liveri, Maria

    2013-12-01

    A systematic study aimed at obtaining new organoclays for the treatment of Olive Mill Waste water (OMW) has been performed. Several organoclays have been prepared by loading different amounts of the biocompatible surfactant Tween20 onto the K10 montmorillonite (MMT). Complementary kinetic and equilibrium studies on the adsorption of the Tween20 onto the MMT have been carried out and the characterization of the new tailor-made bio-materials has been performed by means of the XRD and FT-IR measurements. Finally the prepared bio-organoclays have been successfully applied for the OMW remediation and they proved to be highly effective in decreasing the organic content (OC) to an extent that depends on both the amount of loaded surfactant and the experimental protocols applied.

  20. Production and remediation of low sludge simulated Purex waste glasses, 2: Effects of sludge oxide additions on glass durability

    International Nuclear Information System (INIS)

    Ramsey, W.G.

    1993-01-01

    Glass produced during the Purex 4 campaigns of the Integrated DWPF Melter System (IDMS) and the 774 Research Melter contained a lower fraction of sludge components than targeted by the Product Composition Control System (PCCS). Purex 4 glass was more durable than the benchmark (EA) glass, but was less durable than most other simulated SRS high-level waste glasses. Further, the measured durability of Purex 4 glass was not as well correlated with the durability predicted from the DWPF process control algorithm, probably because the algorithm was developed to predict the durability of SRS high-level waste glasses with higher sludge content than Purex 4. A melter run, designated Purex 4 Remediation, was performed using the 774 Research Melter to determine if the initial PCCS target composition determined for Purex 4 would produce acceptable glass whose durability could be accurately modeled by the DWPF glass durability algorithm. Reagent grade oxides and carbonates were added to Purex 4 melter feed stock to simulate a higher sludge loading. Each canister of glass produced was sampled and the glass durability was determined by the Product Consistency Test method. This document details the durability data and subsequent analysis

  1. Selection of innovative technologies for the remediation of soils contaminated with radioactive and mixed wastes

    International Nuclear Information System (INIS)

    Steude, J.; Tucker, B.

    1991-01-01

    The remediation of sites containing radioactive and mixed wastes is in a period of rapid growth. The state of the art of remediation is progressing to handle the shortcomings of conventional pump and treat or disposal technologies. The objective of this paper is to review the status of selected innovative technologies which treat soils contaminated with radioactive and mixed waste. Technologies are generally classified as innovative if they are fully developed, but lack sufficient cost or performance data for comparison with conventional technologies. The Environmental Protection Agency recommends inclusion of innovative technologies in the RI/FS screening process if there is reason to believe that they would offer advantages in performance, implementability, cost, etc. This paper serves as a compilation of the pertinent information necessary to gain an overview of the selected innovative technologies to aid in the RI/F'S screening process. The innovative technologies selected for evaluation are listed below. Bioremediation, although innovative, was not included due to the combination of the vast amount of literature on this subject and the limited scope of this project. 1. Soil washing and flushing; 2. Low temperature thermal treatment; 3. Electrokinetics; 4. Infrared incineration; 5. Ultrasound; 6. In situ vitrification; 7. Soil vapor extraction; 8. Plasma torch slagging; 9. In situ hot air/steam extraction; 10. Cyclone reactor treatment; 11. In situ radio frequency; 12. Vegetative radionuclide uptake; and 13. In situ soil heating. The information provided on each technology includes a technical description, status, summary of results including types of contaminants and soils treated, technical effectiveness, feasibility and estimated cost

  2. Systems analysis support to the waste management technology center

    International Nuclear Information System (INIS)

    Rivera, A.L.; Osborne-Lee, I.W.; DePaoli, S.M.

    1988-01-01

    This paper describes a systems analysis concept being developed in support of waste management planning and analysis activities for Martin Marietta Energy Systems, Inc. (Energy Systems), sites. This integrated systems model serves as a focus for the accumulation and documentation of technical and economic information from current waste management practices, improved operations projects, remedial actions, and new system development activities. The approach is generic and could be applied to a larger group of sites. This integrated model is a source of technical support to waste management groups in the Energy Systems complex for integrated waste management planning and related technology assessment activities. This problem-solving methodology for low-level waste (LLW) management is being developed through the Waste Management Technology Center (WMTC) for the Low-Level Waste Disposal, Development, and Demonstration (LLWDDD) Program. In support of long-range planning activities, this capability will include the development of management support tools such as specialized systems models, data bases, and information systems. These management support tools will provide continuing support in the identification and definition of technical and economic uncertainties to be addressed by technology demonstration programs. Technical planning activities and current efforts in the development of this system analysis capability for the LLWDDD Program are presented in this paper

  3. Optimization of remediation strategies using vadose zone monitoring systems

    Science.gov (United States)

    Dahan, Ofer

    2016-04-01

    In-situ bio-remediation of the vadose zone depends mainly on the ability to change the subsurface hydrological, physical and chemical conditions in order to enable development of specific, indigenous, pollutants degrading bacteria. As such the remediation efficiency is much dependent on the ability to implement optimal hydraulic and chemical conditions in deep sections of the vadose zone. These conditions are usually determined in laboratory experiments where parameters such as the chemical composition of the soil water solution, redox potential and water content of the sediment are fully controlled. Usually, implementation of desired optimal degradation conditions in deep vadose zone at full scale field setups is achieved through infiltration of water enriched with chemical additives on the land surface. It is assumed that deep percolation into the vadose zone would create chemical conditions that promote biodegradation of specific compounds. However, application of water with specific chemical conditions near land surface dose not necessarily results in promoting of desired chemical and hydraulic conditions in deep sections of the vadose zone. A vadose-zone monitoring system (VMS) that was recently developed allows continuous monitoring of the hydrological and chemical properties of deep sections of the unsaturated zone. The VMS includes flexible time-domain reflectometry (FTDR) probes which allow continuous monitoring of the temporal variation of the vadose zone water content, and vadose-zone sampling ports (VSPs) which are designed to allow frequent sampling of the sediment pore-water and gas at multiple depths. Implementation of the vadose zone monitoring system in sites that undergoes active remediation provides real time information on the actual chemical and hydrological conditions in the vadose zone as the remediation process progresses. Up-to-date the system has been successfully implemented in several studies on water flow and contaminant transport in

  4. Minutes from Department of Energy/Hazardous Waste Remedial Actions Program research and development technology needs assessment review meeting

    International Nuclear Information System (INIS)

    1989-01-01

    On November 1--2, 1988, representatives of the Department of Energy (DOE) Headquarters, DOE Operations Offices, DOE contractors, and the Hazardous Waste Remedial Actions Program met in Salt Lake City, Utah, to select and prioritize candidate waste problems in need of research and development. The information gained will be used in planning for future research and development tasks and in restructuring current research activities to address the priority needs. All Operations Offices were represented by DOE staff and by contractor delegates from the area. This document summarizes the results of the meeting and lists the priority waste problems established

  5. The 300 area waste acid treatment system closure plan

    International Nuclear Information System (INIS)

    Luke, S.N.

    1996-01-01

    The 300 Area Waste Acid Treatment System (WATS) is located within operable units 300-FF-2 (source) and 300-FF-5 (groundwater), as designated in the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) . Operable units 300-FF-2 and 300-FF-5 are scheduled to be remediated using the Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) Remedial Investigation/Feasibility Study (RI/FS) process. Thus, any remediation of the 300 Area WATS with respect to contaminants not produced by those facilities and soils and groundwater will be deferred to the CERCLA RI/FS process. Final closure activities will be completed in 3 phases and certified in accordance with the 300 Area WATS closure plan by the Washington State Department of Ecology (Ecology) and the U.S. Environmental Protection Agency (EPA). It is anticipated that the 300 Area WATS closure would take 2 years to complete

  6. The Gunite and Associated Tanks Remediation Project Tank Waste Retrieval Performance and Lessons Learned, vol. 2 [of 2

    Energy Technology Data Exchange (ETDEWEB)

    Lewis, BE

    2003-10-07

    The Gunite and Associated Tanks (GAAT) Remediation Project was the first of its kind performed in the United States. Robotics and remotely operated equipment were used to successfully transfer almost 94,000 gal of remote-handled transuranic sludge containing over 81,000 Ci of radioactive contamination from nine large underground storage tanks at the Oak Ridge National Laboratory (ORNL). The sludge was transferred with over 439,000 gal of radioactive waste supernatant and {approx}420,500 gal of fresh water that was used in sluicing operations. The GAATs are located in a high-traffic area of ORNL near a main thoroughfare. Volume 1 provides information on the various phases of the project and describes the types of equipment used. Volume 1 also discusses the tank waste retrieval performance and the lessons learned during the remediation effort. Volume 2 consists of the following appendixes, which are referenced in Vol. 1: A--Background Information for the Gunite and Associated Tanks Operable Unit; B--Annotated Bibliography; C--GAAT Equipment Matrix; D--Comprehensive Listing of the Sample Analysis Data from the GAAT Remediation Project; and E--Vendor List for the GAAT Remediation Project. The remediation of the GAATs was completed {approx}5.5 years ahead of schedule and {approx}$120,435K below the cost estimated in the Remedial Investigation/Feasibility Study for the project. These schedule and cost savings were a direct result of the selection and use of state-of-the-art technologies and the dedication and drive of the engineers, technicians, managers, craft workers, and support personnel that made up the GAAT Remediation Project Team.

  7. The Gunite and Associated Tanks Remediation Project Tank Waste Retrieval Performance and Lessons Learned, vol. 2 [of 2

    International Nuclear Information System (INIS)

    Lewis, BE

    2003-01-01

    The Gunite and Associated Tanks (GAAT) Remediation Project was the first of its kind performed in the United States. Robotics and remotely operated equipment were used to successfully transfer almost 94,000 gal of remote-handled transuranic sludge containing over 81,000 Ci of radioactive contamination from nine large underground storage tanks at the Oak Ridge National Laboratory (ORNL). The sludge was transferred with over 439,000 gal of radioactive waste supernatant and ∼420,500 gal of fresh water that was used in sluicing operations. The GAATs are located in a high-traffic area of ORNL near a main thoroughfare. Volume 1 provides information on the various phases of the project and describes the types of equipment used. Volume 1 also discusses the tank waste retrieval performance and the lessons learned during the remediation effort. Volume 2 consists of the following appendixes, which are referenced in Vol. 1: A--Background Information for the Gunite and Associated Tanks Operable Unit; B--Annotated Bibliography; C--GAAT Equipment Matrix; D--Comprehensive Listing of the Sample Analysis Data from the GAAT Remediation Project; and E--Vendor List for the GAAT Remediation Project. The remediation of the GAATs was completed ∼5.5 years ahead of schedule and ∼$120,435K below the cost estimated in the Remedial Investigation/Feasibility Study for the project. These schedule and cost savings were a direct result of the selection and use of state-of-the-art technologies and the dedication and drive of the engineers, technicians, managers, craft workers, and support personnel that made up the GAAT Remediation Project Team

  8. Remediation of uranium mill tailings wastes in Australia: a critical review

    International Nuclear Information System (INIS)

    Mudd, G.M.

    2000-01-01

    Australia has been an active participant in the global uranium mining industry since its inception in the 1940s. By the late 1950s five major mining and milling projects were operating, several small mines supplied custom ores. All of these projects were closed by the early 1960s, except for Rum Jungle which continued under government subsidy. Most sites have had lasting Environmental impacts. The advances in nuclear power in the 1960s saw increasing demand for uranium and Australia again explored with remarkable success in the Northern Territory, South Australia and Western Australia. After several government inquiries in the 1970s, Ranger, Nabarlek and Olympic Dam were operating by the mid 1980s. The principal risks from uranium mill tailings wastes arise from their radioactive nature and often their chemical toxicities. A critical review of the rehabilitation of abandoned uranium mines and mill tailings as a comparison for current projects is presented. It is concluded that the management of uranium mill tailings wastes is a complex task, requiring a sound multi-disciplinary approach. The problems include groundwater contamination, erosion, radon emanation and gamma radiation. evidence to data from the remediation of old and modern sites does not demonstrate effective long-term closure and safety

  9. Thermal processing system concepts and considerations for RWMC buried waste

    Energy Technology Data Exchange (ETDEWEB)

    Eddy, T.L.; Kong, P.C.; Raivo, B.D.; Anderson, G.L.

    1992-02-01

    This report presents a preliminary determination of ex situ thermal processing system concepts and related processing considerations for application to remediation of transuranic (TRU)-contaminated buried wastes (TRUW) at the Radioactive Waste Management Complex (RWMC) of the Idaho National Engineering Laboratory (INEL). Beginning with top-level thermal treatment concepts and requirements identified in a previous Preliminary Systems Design Study (SDS), a more detailed consideration of the waste materials thermal processing problem is provided. Anticipated waste stream elements and problem characteristics are identified and considered. Final waste form performance criteria, requirements, and options are examined within the context of providing a high-integrity, low-leachability glass/ceramic, final waste form material. Thermal processing conditions required and capability of key systems components (equipment) to provide these material process conditions are considered. Information from closely related companion study reports on melter technology development needs assessment and INEL Iron-Enriched Basalt (IEB) research are considered. Five potentially practicable thermal process system design configuration concepts are defined and compared. A scenario for thermal processing of a mixed waste and soils stream with essentially no complex presorting and using a series process of incineration and high temperature melting is recommended. Recommendations for applied research and development necessary to further detail and demonstrate the final waste form, required thermal processes, and melter process equipment are provided.

  10. Thermal processing system concepts and considerations for RWMC buried waste

    International Nuclear Information System (INIS)

    Eddy, T.L.; Kong, P.C.; Raivo, B.D.; Anderson, G.L.

    1992-02-01

    This report presents a preliminary determination of ex situ thermal processing system concepts and related processing considerations for application to remediation of transuranic (TRU)-contaminated buried wastes (TRUW) at the Radioactive Waste Management Complex (RWMC) of the Idaho National Engineering Laboratory (INEL). Beginning with top-level thermal treatment concepts and requirements identified in a previous Preliminary Systems Design Study (SDS), a more detailed consideration of the waste materials thermal processing problem is provided. Anticipated waste stream elements and problem characteristics are identified and considered. Final waste form performance criteria, requirements, and options are examined within the context of providing a high-integrity, low-leachability glass/ceramic, final waste form material. Thermal processing conditions required and capability of key systems components (equipment) to provide these material process conditions are considered. Information from closely related companion study reports on melter technology development needs assessment and INEL Iron-Enriched Basalt (IEB) research are considered. Five potentially practicable thermal process system design configuration concepts are defined and compared. A scenario for thermal processing of a mixed waste and soils stream with essentially no complex presorting and using a series process of incineration and high temperature melting is recommended. Recommendations for applied research and development necessary to further detail and demonstrate the final waste form, required thermal processes, and melter process equipment are provided

  11. 1995 Baseline solid waste management system description

    International Nuclear Information System (INIS)

    Anderson, G.S.; Konynenbelt, H.S.

    1995-09-01

    This provides a detailed solid waste system description that documents the treatment, storage, and disposal (TSD) strategy for managing Hanford's solid low-level waste, low-level mixed waste, transuranic and transuranic mixed waste, and greater-than-Class III waste. This system description is intended for use by managers of the solid waste program, facility and system planners, as well as system modelers. The system description identifies the TSD facilities that constitute the solid waste system and defines these facilities' interfaces, schedules, and capacities. It also provides the strategy for treating each of the waste streams generated or received by the Hanford Site from generation or receipt through final destination

  12. The proceduralisation of data protection remedies under EU data protection law : Towards a more effective and data subject-oriented remedial system?

    NARCIS (Netherlands)

    Galetta, Antonella; de Hert, Paul

    2015-01-01

    The proceduralisation of data protection remedies under EU data protection law: towards a more effective and data subject-oriented remedial system?
The right to remedy breaches of data protection is laid down in both Directive 95/46/EC (Art. 22) and the Council of Europe Data Protection Convention

  13. Data and information management system for the ORNL (Oak Ridge National Laboratory) Remedial Action Program

    International Nuclear Information System (INIS)

    Voorhees, L.D.; Hook, L.A.; Gentry, M.J.; Owen, P.T.; Newman, K.A.; McCord, R.A.; Faulkner, M.A.; Bledsoe, J.L.

    1988-01-01

    A Remedial Action Program (RAP) was established in FY 1985 at Oak Ridge National Laboratory (ORNL) to provide corrective measures at areas contaminated with radioactive and/or hazardous chemical wastes. To achieve this goal, numerous and varied studies are being conducted to characterize the waste disposal sites. Environmental data collected in support of other programs at ORNL are also of use to RAP. Collectively, these studies are generating a voluminous amount of data on a scale unprecedented for ORNL. A computerized Data and Information Management System (DIMS) was developed to (1) provide a centralized repository for data pertinent to RAP and (2) provide support for the investigations and assessments leading to the long-term remediation of contaminated sites and facilities. The current DIMS and its role in supporting RAP are described. The DIMS consists of three components: (1) the Bibliographic Data Base, (2) the Records Control Data Base, and (3) the Numeric Data Base. This paper/poster emphasizes the Numeric Data Base, including its development and organization, and also summarizes the status of other activities associated with management and use of such data (i.e., bibliographic information, records control, geographic information, and quality assurance). The types of data currently available have been summarized, and a synopsis of the contents of the RAP numeric data base has been compiled in a menu-driven program available on PC diskettes. The synopsis will be demonstrated at the conference

  14. Gaseous radioactive waste processing system

    International Nuclear Information System (INIS)

    Onizawa, Hideo.

    1976-01-01

    Object: To prevent explosion of hydrogen gas within gaseous radioactive waste by removing the hydrogen gas by means of a hydrogen absorber. Structure: A coolant extracted from a reactor cooling system is sprayed by nozzle into a gaseous phase (hydrogen) portion within a tank, thus causing slipping of radioactive rare gas. The gaseous radioactive waste rich in hydrogen, which is purged in the tank, is forced by a waste gas compressor into a hydrogen occlusion device. The hydrogen occlusion device is filled with hydrogen occluding agents such as Mg, Mg-Ni alloy, V-Nb alloy, La-Ni alloy and so forth, and hydrogen in the waste gas is removed through reaction to produce hydrogen metal. The gaseous radioactive waste, which is deprived of hydrogen and reduced in volume, is stored in an attenuation tank. The hydrogen stored in the hydrogen absorber is released and used again as purge gas. (Horiuchi, T.)

  15. WASTE TREATMENT BUILDING SYSTEM DESCRIPTION DOCUMENT

    Energy Technology Data Exchange (ETDEWEB)

    F. Habashi

    2000-06-22

    The Waste Treatment Building System provides the space, layout, structures, and embedded subsystems that support the processing of low-level liquid and solid radioactive waste generated within the Monitored Geologic Repository (MGR). The activities conducted in the Waste Treatment Building include sorting, volume reduction, and packaging of dry waste, and collecting, processing, solidification, and packaging of liquid waste. The Waste Treatment Building System is located on the surface within the protected area of the MGR. The Waste Treatment Building System helps maintain a suitable environment for the waste processing and protects the systems within the Waste Treatment Building (WTB) from most of the natural and induced environments. The WTB also confines contaminants and provides radiological protection to personnel. In addition to the waste processing operations, the Waste Treatment Building System provides space and layout for staging of packaged waste for shipment, industrial and radiological safety systems, control and monitoring of operations, safeguards and security systems, and fire protection, ventilation and utilities systems. The Waste Treatment Building System also provides the required space and layout for maintenance activities, tool storage, and administrative facilities. The Waste Treatment Building System integrates waste processing systems within its protective structure to support the throughput rates established for the MGR. The Waste Treatment Building System also provides shielding, layout, and other design features to help limit personnel radiation exposures to levels which are as low as is reasonably achievable (ALARA). The Waste Treatment Building System interfaces with the Site Generated Radiological Waste Handling System, and with other MGR systems that support the waste processing operations. The Waste Treatment Building System interfaces with the General Site Transportation System, Site Communications System, Site Water System, MGR

  16. WASTE TREATMENT BUILDING SYSTEM DESCRIPTION DOCUMENT

    International Nuclear Information System (INIS)

    Habashi, F.

    2000-01-01

    The Waste Treatment Building System provides the space, layout, structures, and embedded subsystems that support the processing of low-level liquid and solid radioactive waste generated within the Monitored Geologic Repository (MGR). The activities conducted in the Waste Treatment Building include sorting, volume reduction, and packaging of dry waste, and collecting, processing, solidification, and packaging of liquid waste. The Waste Treatment Building System is located on the surface within the protected area of the MGR. The Waste Treatment Building System helps maintain a suitable environment for the waste processing and protects the systems within the Waste Treatment Building (WTB) from most of the natural and induced environments. The WTB also confines contaminants and provides radiological protection to personnel. In addition to the waste processing operations, the Waste Treatment Building System provides space and layout for staging of packaged waste for shipment, industrial and radiological safety systems, control and monitoring of operations, safeguards and security systems, and fire protection, ventilation and utilities systems. The Waste Treatment Building System also provides the required space and layout for maintenance activities, tool storage, and administrative facilities. The Waste Treatment Building System integrates waste processing systems within its protective structure to support the throughput rates established for the MGR. The Waste Treatment Building System also provides shielding, layout, and other design features to help limit personnel radiation exposures to levels which are as low as is reasonably achievable (ALARA). The Waste Treatment Building System interfaces with the Site Generated Radiological Waste Handling System, and with other MGR systems that support the waste processing operations. The Waste Treatment Building System interfaces with the General Site Transportation System, Site Communications System, Site Water System, MGR

  17. Development and Implementation of the Waste Management Information System to Support Hanford's River Corridor Cleanup

    Energy Technology Data Exchange (ETDEWEB)

    Nolan, L M [Washington Closure Hanford, LLC, 3070 George Washington Way, Richland, WA 99354 (United States)

    2006-07-01

    This paper describes the development of a Waste Information Management System (WMIS) to support the waste designation, transportation, and disposal processes used by Washington Closure Hanford, LLC to support cleanup of the Columbia River Corridor. This waste, primarily consisting of remediated burial sites and building demolition debris, is disposed at the Environmental Restoration Disposal Facility (ERDF), which is located in the center of the Hanford Site (an approximately 1460 square kilometers site). WMIS uses a combination of bar-code scanning, hand-held computers, and strategic employment of a radio frequency identification (RFID) tag system to track each waste shipment from waste generation to disposal. (authors)

  18. Specialized sorting and measuring system for site remediation

    International Nuclear Information System (INIS)

    Runge, H.; Christ, G.

    2001-01-01

    The machine design and measurement philosophy of the SSGE, developed for excavation and treatment of some 21,000 metric tons of ground material and concrete from NUKEM decommissioned fuel element factory, have already been passed the official licensing procedure. The start up of site clean-up is scheduled for summer 2001. With the SSGE there has been made available a method to safe and economically remediate contaminated ground of nuclear sites. The SSEG, being a mobile system, can be applied at various sites

  19. Physical System Requirements: Transport Waste

    International Nuclear Information System (INIS)

    1992-04-01

    The Nuclear Waste Policy Act (NWPA) of 1982 assigned to the Department of Energy (DOE) the responsibility for managing the disposal of spent nuclear fuel and high-level radioactive waste and established the Office of Civilian Radioactive Waste Management (OCRWM) for that purpose. The Secretary of Energy, in his November 1989 report to Congress (DOE/RW-0247), announced three new initiatives for the conduct of the Civilian Radioactive Waste Management (CRWM) program. One of these initiatives was to establish improved management structure and procedures. In response, OCRWM performed a management study and the Director subsequently issued the Management Systems Improvement Strategy (MSIS) on August 10, 1990, calling for a rigorous implementation of systems engineering principles with a special emphasis on functional analysis. The functional analysis approach establishes a framework for integrating the program management efforts with the technical requirements analysis into a single, unified, and consistent program. This approach recognizes that just as the facilities and equipment comprising the physical waste management system must perform certain functions, so must certain programmatic and management functions be performed within the program in order to successfully bring the physical system into being. The objective of this document is to establish the essential functions, requirements, interfaces, and system architecture for the Transport Waste mission. Based upon the Nuclear Waste Policy Act, the mission of the Waste Transportation System is to transport SNF and/or HLW from the purchaser's/producer's facilities to, and between, NWMS facilities in a manner that protects the health and safety of the public and of workers and the quality of the environment makes effective use of financial and other resources, and to the fullest extent possible uses the private sector

  20. Structural analysis of Hanford's single-shell 241-C-106 tank: A first step toward waste-tank remediation

    International Nuclear Information System (INIS)

    Harris, J.P.; Julyk, L.J.; Marlow, R.S.; Moore, C.J.; Day, J.P.; Dyrness, A.D.; Jagadish, P.; Shulman, J.S.

    1993-10-01

    The buried single-shell waste tank 241-C-106, located at the US Department of Energy's Hanford Site, has been a repository for various liquid radioactive waste materials since its construction in 1943. A first step toward waste tank remediation is demonstrating that remediation activities can be performed safely. Determination of the current structural capacity of this high-heat tank is an important element in this assessment. A structural finite-element model of tank 241-C-106 has been developed to assess the tank's structural integrity with respect to in situ conditions and additional remediation surface loads. To predict structural integrity realistically, the model appropriately addresses two complex issues: (1) surrounding soil-tank interaction associated with thermal expansion cycling and surcharge load distribution and (2) concrete-property degradation and creep resulting from exposure to high temperatures generated by the waste. This paper describes the development of the 241-C-106 structural model, analysis methodology, and tank-specific structural acceptance criteria

  1. BioKonversion technology recovers, remediates and reuses waste and hydrocarbons from oil drilling

    Energy Technology Data Exchange (ETDEWEB)

    Topf, A.

    2008-01-15

    Houston-based Nopal Group has developed a solution to dispose of oilfield waste in a safe and cost-effective manner. The company is actively engaged in a large-scale project to remediate a 400-hectare site on the Aspheron Peninsula in Azerbaijan. The site is currently regarded as the most polluted place in the world after a century of oil extraction with little regard for the surrounding environment. The Nopal Group will use its patented BioKonversion technology, which cleanses the soil of hydrocarbons in a two-part process using a large machine known as the Green Machine. Several pipelines will need to be relocated, and ancient drilling rigs that have been there as long as 100 years will have to be dealt with. The cleanup cost has been estimated at between $20 million to $40 million, and will take between 18 and 36 months, depending on how deep into the ground the machines have to dig for hydrocarbons. The 90-foot by 40-foot machine processes drill cuttings, contaminated soil and drill fluids by first separating the dirt from the liquid hydrocarbons, which can be recycled or refined for resale. The remaining dirt, which still contains 3 to 7 percent oil, is then placed into a centrifuge and mixed with a heating agent and other elements, including naturally oleophilic kenaf powder. The process micronizes and absorbs hydrocarbons. Once the process is finished, the hydrocarbons are immediately non-detectable and non-leachable. The leftover benign dirt can be used as landfill cover, or mixed with road aggregate. BioKonversion can also be adapted for use on oil rigs. This article demonstrated that the process has clear advantages over traditional oilfield remediation methods such as land farming. Opportunities exist to utilize the process in Venezuela and Kuwait. 1 fig.

  2. Waste Area Grouping 2 Remedial Investigation Phase 1 Seep Task data report: Contaminant source area assessment

    International Nuclear Information System (INIS)

    Hicks, D.S.

    1996-03-01

    This report presents the findings of the Waste Area Grouping (WAG) 2, Phase 1 Remedial Investigation (RI) Seep Task efforts during 1993 and 1994 at Oak Ridge National Laboratory (ORNL). The results presented here follow results form the first year of sampling, 1992, which are contained in the Phase 1 RI report for WAG 2 (DOE 1995a). The WAG 2 Seep Task efforts focused on contaminants in seeps, tributaries, and main streams within the White Oak Creek (WOC) watershed. This report is designed primarily as a reference for contaminants and a resource for guiding remedial decisions. Additional in-depth assessments of the Seep Task data may provide clearer understandings of contaminant transport from the different source areas in the WOC watershed. WAG 2 consists of WOC and its tributaries downstream of the ORNL main plant area, White Oak Lake, the White Oak Creek Embayment of the Clinch River, and the associated flood plains and subsurface environment. The WOC watershed encompasses ORNL and associated WAGs. WAG 2 acts as an integrator for contaminant releases from the contaminated sites at ORNL and as the conduit transporting contaminants to the Clinch River. The main objectives of the Seep Task were to identify and characterize seeps, tributaries and source areas that are responsible for the contaminant releases to the main streams in WAG 2 and to quantify their input to the total contaminant release from the watershed at White Oak Dam (WOD). Efforts focused on 90 Sr, 3 H, and 137 Cs because these contaminants pose the greatest potential human health risk from water ingestion at WOD. Bimonthly sampling was conducted throughout the WOC watershed beginning in March 1993 and ending in August 1994. Samples were also collected for metals, anions, alkalinity, organics, and other radionuclides

  3. Internal monitoring system for radioactive waste disposal

    International Nuclear Information System (INIS)

    Blanke, J.A.; McConnell, B.C.

    1988-01-01

    The U.S. Department of Energy (DOE), with Bechtel National, Inc. as the project management contractor, is responsible for the Niagara Falls Storage Site (NFSS) interim waste containment facility in Lewiston, New York. The NFSS contains approximately 190,000 m 3 of low-level radioactive waste resulting from the remediation of approximately 600 hectares of the U.S. Army's former Lake Ontario Ordnance Works. The remedial action for the site and vicinity properties was performed as part of DOE's Formerly Utilized Site Remedial Action Program and Surplus Facilities Management Program. The NFSS adapted off-the-shelf instrumentation to show that the design features are functioning, and develops confidence that long-term stability, without constant surveillance, is feasible

  4. Remedial investigation report on Waste Area Group 5 at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Volume 1: Technical summary

    International Nuclear Information System (INIS)

    1995-03-01

    A remedial investigation (RI) was performed to support environmental restoration activities for Waste Area Grouping (WAG) 5 at the Oak Ridge National Laboratory (ORNL) in Oak Ridge, Tennessee. The WAG 5 RI made use of the observational approach, which concentrates on collecting only information needed to assess site risks and support future cleanup work. This information was interpreted and is presented using the framework of the site conceptual model, which relates contaminant sources and release mechanisms to migration pathways and exposure points that are keyed to current and future environmental risks for both human and ecological receptors. The site conceptual model forms the basis of the WAG 5 remedial action strategy and remedial action objectives. The RI provided the data necessary to verify this model and allows recommendations to be made to accomplish those objectives

  5. Remedial investigation report on Waste Area Grouping 5 at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Volume 1: Technical summary

    International Nuclear Information System (INIS)

    1995-09-01

    A remedial investigation (RI) was performed to support environmental restoration activities for Waste Area Grouping (WAG) 5 at the Oak Ridge National Laboratory (ORNL) in Oak Ridge, Tennessee. The WAG 5 RI made use of the observational approach, which concentrates on collecting only information needed to assess site risks and support future cleanup work. This information was interpreted and is presented using the framework of the site conceptual model, which relates contaminant sources and release mechanisms to migration pathways and exposure points that are keyed to current and future environmental risks for both human and ecological receptors. The site conceptual model forms the basis of the WAG 5 remedial action strategy and remedial action objectives. The RI provided the data necessary to verify this model and allows recommendations to be made to accomplish those objectives.

  6. In situ vitrification - A potential remedial action technique for hazardous wastes

    International Nuclear Information System (INIS)

    Fitzpatrick, V.F.; Buelt, J.L.; Oma, K.H.; Timmerman, C.L.

    1984-01-01

    In situ vitrification (ISV) is an innovative technology being developed as a potential method for stabilizing transuranic (TRU) contaminated wastes in place. Although the process is being developed for TRU contaminated wastes, it is envisioned that the process could also be applied to hazardous chemical wastes. In situ vitrification (ISV) is the conversion of contaminated soil into a durable glass and crystalline wastes form through melting by joule heating. The technology for in situ vitrification is based upon electric melter technology developed at the Pacific Northwest Laboratory (PNL) for the immobilization of high-level nuclear waste. In situ vitrification was initially tested by researchers at PNL in August, 1980 (U.S. Patent 4,376,598). Since then, ISV has grown from a concept to an emerging technology through a series of 21 engineering-scale (laboratory) tests and 7 pilot-scale (field) tests. A large-scale system is currently being fabricated for testing. The program has been sponsored by the U.S. Department of Energy's (DOE) Richland Operations Office for potential application to Hanford TRU contaminated soil sites. A more detailed description outlining the power system design and the off-gas treatment system follows

  7. Remediation of the low-level radioactive waste tailing pond in Kowary

    International Nuclear Information System (INIS)

    Waclawek, Z.

    1999-01-01

    The town of Kowary was the centre of uranium mining activities in Poland. The headquarters of the uranium mining company ZPR-1 (Zaklady Przemyslowe R-1) were located there, as it was the only uranium processing plant in Poland. Mining in Uranium in Poland ceased in 1963, but processing of low-grade dumps was continued in Kowary until 1972. As a result of these processing activities, a significant volume of wastes was produced and the tailings pond in Kowary was constructed to accommodate these wastes. The tailings pond covers an area of 1,3 ha. It is a hydrotechnical construction closed on three sides by a dam, which has been modified a number of times over the years. It is now 300 m long (the sum of the three sides)m with a maximum height of 12 m, and is at the limits of the geotechnical stability. As a result of the uranium processing activities, the tailings pond was filled with about 2,5 x 10 5 t of disposed fine-grained gneisses and schists containing about 4,5 t of uranium and about 440 GBq of radium (from processing of uranium ores). A prompt remedial action in this case is particularly necessary because the tailings pond is located in a steep mountainous valley where the local climate involves rapid summer rains with heavy erosion. The nearest buildings in the town of Kowary are located literally at the foot of the 12 m high dam and private gardens extend onto the dam slope. The urgency has recently been demonstrated during the flood of summer 1997 when the base of the dam eroded. In the early seventies, Wroclaw University of Technology (WUT) received, by a governmental decision, ownership of both the area and the facilities of the former uranium mining company ZPR-1. Subsequently, the company Hydromet, Ltd., owned by WUT, has continued to use the existing chemical plant for the various experimental processes of rare (radioactive) metals, chemical production and galvanic processes. As a result, 30 t of mixed heavy metals and 300 t of the remnants from the

  8. Design compliance matrix waste sample container filling system for nested, fixed-depth sampling system

    International Nuclear Information System (INIS)

    BOGER, R.M.

    1999-01-01

    This design compliance matrix document provides specific design related functional characteristics, constraints, and requirements for the container filling system that is part of the nested, fixed-depth sampling system. This document addresses performance, external interfaces, ALARA, Authorization Basis, environmental and design code requirements for the container filling system. The container filling system will interface with the waste stream from the fluidic pumping channels of the nested, fixed-depth sampling system and will fill containers with waste that meet the Resource Conservation and Recovery Act (RCRA) criteria for waste that contains volatile and semi-volatile organic materials. The specifications for the nested, fixed-depth sampling system are described in a Level 2 Specification document (HNF-3483, Rev. 1). The basis for this design compliance matrix document is the Tank Waste Remediation System (TWRS) desk instructions for design Compliance matrix documents (PI-CP-008-00, Rev. 0)

  9. Electrokinetic remediation of plutonium-contaminated nuclear site wastes: Results from a pilot-scale on-site trial

    International Nuclear Information System (INIS)

    Agnew, Kieran; Cundy, Andrew B.; Hopkinson, Laurence; Croudace, Ian W.; Warwick, Phillip E.; Purdie, Philip

    2011-01-01

    This paper examines the field-scale application of a novel low-energy electrokinetic technique for the remediation of plutonium-contaminated nuclear site soils, using soil wastes from the Atomic Weapons Establishment (AWE) Aldermaston site, Berkshire, UK as a test medium. Soils and sediments with varying composition, contaminated with Pu through historical site operations, were electrokinetically treated at laboratory-scale with and without various soil pre-conditioning agents. Results from these bench-scale trials were used to inform a larger on-site remediation trial, using an adapted containment pack with battery power supply. 2.4 m 3 (ca. 4 tonnes) of Pu-contaminated soil was treated for 60 days at a power consumption of 33 kW h/m 3 , and then destructively sampled. Radiochemical data indicate mobilisation of Pu in the treated soil, and migration (probably as a negatively charged Pu-citrate complex) towards the anodic compartment of the treatment cell. Soil in the cathodic zone of the treatment unit was remediated to a level below free-release disposal thresholds (1.7 Bq/g, or <0.4 Bq/g above background activities). The data show the potential of this method as a low-cost, on-site tool for remediation of radioactively contaminated soils and wastes which can be operated remotely on working sites, with minimal disruption to site infrastructure or operations.

  10. Nationwide Risk-Based PCB Remediation Waste Disposal Approvals under Title 40 of the Code of Federal Regulations (CFR) Section 761.61(c)

    Science.gov (United States)

    This page contains information about Nationwide Risk-Based Polychlorinated Biphenyls (PCBs) Remediation Waste Disposal Approvals under Title 40 of the Code of Federal Regulations (CFR) Section 761.61(c)

  11. Implementation of SAP Waste Management System

    International Nuclear Information System (INIS)

    Frost, M.L.; LaBorde, C.M.; Nichols, C.D.

    2008-01-01

    The Y-12 National Security Complex (Y-12) assumed responsibility for newly generated waste on October 1, 2005. To ensure effective management and accountability of newly generated waste, Y-12 has opted to utilize SAP, Y-12's Enterprise Resource Planning (ERP) tool, to track low-level radioactive waste (LLW), mixed waste (MW), hazardous waste, and non-regulated waste from generation through acceptance and disposal. SAP Waste will include the functionality of the current waste tracking system and integrate with the applicable modules of SAP already in use. The functionality of two legacy systems, the Generator Entry System (GES) and the Waste Information Tracking System (WITS), and peripheral spreadsheets, databases, and e-mail/fax communications will be replaced by SAP Waste. Fundamentally, SAP Waste will promote waste acceptance for certification and disposal, not storage. SAP Waste will provide a one-time data entry location where waste generators can enter waste container information, track the status of their waste, and maintain documentation. A benefit of the new system is that it will provide a single data repository where Y-12's Waste Management organization can establish waste profiles, verify and validate data, maintain inventory control utilizing hand-held data transfer devices, schedule and ship waste, manage project accounting, and report on waste handling activities. This single data repository will facilitate the production of detailed waste generation reports for use in forecasting and budgeting, provide the data for required regulatory reports, and generate metrics to evaluate the performance of the Waste Management organization and its subcontractors. SAP Waste will replace the outdated and expensive legacy system, establish tools the site needs to manage newly generated waste, and optimize the use of the site's ERP tool for integration with related business processes while promoting disposition of waste. (authors)

  12. Hazardous waste minimization tracking system

    International Nuclear Information System (INIS)

    Railan, R.

    1994-01-01

    Under RCRA section 3002 9(b) and 3005f(h), hazardous waste generators and owners/operators of treatment, storage, and disposal facilities (TSDFs) are required to certify that they have a program in place to reduce the volume or quantity and toxicity of hazardous waste to the degree determined to be economically practicable. In many cases, there are environmental, as well as, economic benefits, for agencies that pursue pollution prevention options. Several state governments have already enacted waste minimization legislation (e.g., Massachusetts Toxic Use Reduction Act of 1989, and Oregon Toxic Use Reduction Act and Hazardous Waste Reduction Act, July 2, 1989). About twenty six other states have established legislation that will mandate some type of waste minimization program and/or facility planning. The need to address the HAZMIN (Hazardous Waste Minimization) Program at government agencies and private industries has prompted us to identify the importance of managing The HAZMIN Program, and tracking various aspects of the program, as well as the progress made in this area. The open-quotes WASTEclose quotes is a tracking system, which can be used and modified in maintaining the information related to Hazardous Waste Minimization Program, in a manageable fashion. This program maintains, modifies, and retrieves information related to hazardous waste minimization and recycling, and provides automated report generating capabilities. It has a built-in menu, which can be printed either in part or in full. There are instructions on preparing The Annual Waste Report, and The Annual Recycling Report. The program is very user friendly. This program is available in 3.5 inch or 5 1/4 inch floppy disks. A computer with 640K memory is required

  13. Radioactive waste integrated management system

    Energy Technology Data Exchange (ETDEWEB)

    Song, D Y; Choi, S S; Han, B S [Atomic Creative Technology, Taejon (Korea, Republic of)

    2003-10-01

    In this paper, we present an integrated management system for radioactive waste, which can keep watch on the whole transporting process of each drum from nuclear power plant temporary storage house to radioactive waste storage house remotely. Our approach use RFID(Radio Frequency Identification) system, which can recognize the data information without touch, GSP system, which can calculate the current position precisely using the accurate time and distance measured from satellites, and the spread spectrum technology CDMA, which is widely used in the area of mobile communication.

  14. Radioactive waste integrated management system

    International Nuclear Information System (INIS)

    Song, D. Y.; Choi, S. S.; Han, B. S.

    2003-01-01

    In this paper, we present an integrated management system for radioactive waste, which can keep watch on the whole transporting process of each drum from nuclear power plant temporary storage house to radioactive waste storage house remotely. Our approach use RFID(Radio Frequency Identification) system, which can recognize the data information without touch, GSP system, which can calculate the current position precisely using the accurate time and distance measured from satellites, and the spread spectrum technology CDMA, which is widely used in the area of mobile communication

  15. In situ vitrification of buried waste: Containment issues and suppression systems

    International Nuclear Information System (INIS)

    Luey, J.; Powell, T.D.

    1992-03-01

    Pacific Northwest Laboratory (PNL) and Idaho National Engineering Laboratory (INEL) are developing a remedial action technology for buried waste through the adaptation of the in situ vitrification (ISV) process. The ISV process is a thermal treatment process originally developed for the US Department of Energy (DOE) to stabilize soils contaminated with transuranic waste. ISV tests with buried waste forms have demonstrated that the processing of buried waste is more dynamic than the processing of soils. This paper will focus on the issue of containment of the gases released during the processing of buried waste and on engineered suppression systems to alleviate transient events associated with dynamic off-gassing from the ISV melt

  16. Physical system requirements - Accept waste

    International Nuclear Information System (INIS)

    1992-08-01

    The Nuclear Waste Policy Act (NWPA) assigned to the Department of Energy (DOE) the responsibility for managing the disposal of spent nuclear fuel and high-level radioactive waste and established the Office of Civilian Radioactive Waste Management (OCRWM) for that purpose. The Secretary of Energy, in his November 1989 report to Congress (DOE/RW-0247), announced new initiatives for the conduct of the Civilian Radioactive Waste Management (CRWM) program. One of these initiatives was to establish improved management structure and procedures. In response, OCRWM performed a management study and the OCRWM Director subsequently issued the Management Systems improvement Strategy (MSIS) on August 10, 1990, calling for a rigorous implementation of systems engineering principles with a special emphasis on functional analysis. The functional analysis approach establishes a framework for integrating the program management efforts with the technical requirements analysis into a single, unified, and consistent program. This approach recognizes that just as the facilities and equipment comprising the physical waste management system must perform certain functions, so must certain programmatic and management functions be performed within the program in order to successfully bring the physical system into being. Thus, a comprehensive functional analysis effort has been undertaken which is intended to: Identify the functions that must be performed to fulfill the waste disposal mission; Identify the corresponding requirements imposed on each of the functions; and Identify the conceptual architecture that will be used to satisfy the requirements. The principal purpose of this requirements document is to present the results that were obtained from the conduct of a functional analysis effort for the Accept Waste mission

  17. The risk implications of approaches to setting soil remediation goals at hazardous waste contaminated sites

    Energy Technology Data Exchange (ETDEWEB)

    Labieniec, Paula Ann [Carnegie Mellon Univ., Pittsburgh, PA (United States)

    1994-08-01

    An integrated exposure and carcinogenic risk assessment model for organic contamination in soil, SoilRisk, was developed and used for evaluating the risk implications of both site-specific and uniform-concentration approaches to setting soil remediation goals at hazardous-waste-contaminated sites. SoilRisk was applied to evaluate the uncertainty in the risk estimate due to uncertainty in site conditions at a representative site. It was also used to evaluate the variability in risk across a region of sites that can occur due to differences in site characteristics that affect contaminant transport and fate when a uniform concentration approach is used. In evaluating regional variability, Ross County, Ohio and the State of Ohio were used as examples. All analyses performed considered four contaminants (benzene, trichloroethylene (TCE), chlordane, and benzo[a]pyrene (BAP)) and four exposure scenarios (commercial, recreational and on- and offsite residential). Regardless of whether uncertainty in risk at a single site or variability in risk across sites was evaluated, the exposure scenario specified and the properties of the target contaminant had more influence than variance in site parameters on the resulting variance and magnitude of the risk estimate. In general, variance in risk was found to be greater for the relatively less degradable and more mobile of the chemicals studied (TCE and chlordane) than for benzene which is highly degradable and BAP which is very immobile in the subsurface.

  18. Plant and fungal biodiversity from metal mine wastes under remediation at Zimapan, Hidalgo, Mexico.

    Science.gov (United States)

    Ortega-Larrocea, María del Pilar; Xoconostle-Cázares, Beatriz; Maldonado-Mendoza, Ignacio E; Carrillo-González, Rogelio; Hernández-Hernández, Jani; Garduño, Margarita Díaz; López-Meyer, Melina; Gómez-Flores, Lydia; González-Chávez, Ma del Carmen A

    2010-05-01

    Plant establishment, presence of arbuscular mycorrhizal fungi (AMF) and other rhizospheric fungi were studied in mine wastes from Zimapan, Hidalgo state, Mexico, using a holistic approach. Two long-term afforested and three non-afforested mine tailings were included in this research. Fifty-six plant species belonging to 29 families were successfully established on the afforested sites, while unmanaged tailings had only a few native plant species colonizing the surrounding soils. Almost all plant roots collected were associated to AMF in these sites. The genus Glomus was the most abundant AMF species found in their rhizosphere; however, the Acaulospora genus was also observed. Other rhizospheric fungi were identified by 18S rDNA sequencing analysis. Their role in these substrates, i.e. biocontrol, pollutant- and organic matter-degradation, and aides that increase plant metal tolerance is discussed. Our results advance the understanding of fungal diversity in sites polluted with metals and present alternative plants for remediation use. Copyright 2009 Elsevier Ltd. All rights reserved.

  19. Cylindrical Electrolyser Enhanced Electrokinetic Remediation of Municipal Solid Waste Incineration Fly Ashes

    Science.gov (United States)

    Huang, Tao; Zhou, Lulu; Tao, Junjun; Liu, Longfei

    2018-01-01

    The paper discusses enhancement and efficiency of removing spiked heavy metal (HM) contaminants from the municipal solid waste incineration (MSWI) fly ashes in the cylindrical electrolyser device. The characterization parameters of the electrolyte solution pH, electric current, electrical conductivity, voltage gradient were discussed after the experiment. The chemical speciation of HMs was analysed between the original samples and remediated ones by BCR sequential extraction. The detoxification efficiencies of Zn, Pb, Cu and Cd in the column-uniform device were compared with that in the traditional rectangular apparatus. The pH value changed smoothly with small amplitude of oscillation in general in cathode and anode compartments except the initial break. The electrical current rapidly increased on the first day of the experiment and steadily declined after that and the electrical conductivity presented a clear rising trend. The residual partition of detoxified samples were obviously lifted which was much higher than the analysis data of the raw materials. The pH and the electrical conductivity in sample region were distributed more uniformly and the blind area was effectively eliminated in the electrolytic cells which was indirectly validated by the contrastive detoxification result of the spiked HMs between the rectangular and cylindrical devices.

  20. The risk implications of approaches to setting soil remediation goals at hazardous waste contaminated sites

    International Nuclear Information System (INIS)

    Labieniec, P.A.

    1994-08-01

    An integrated exposure and carcinogenic risk assessment model for organic contamination in soil, SoilRisk, was developed and used for evaluating the risk implications of both site-specific and uniform-concentration approaches to setting soil remediation goals at hazardous-waste-contaminated sites. SoilRisk was applied to evaluate the uncertainty in the risk estimate due to uncertainty in site conditions at a representative site. It was also used to evaluate the variability in risk across a region of sites that can occur due to differences in site characteristics that affect contaminant transport and fate when a uniform concentration approach is used. In evaluating regional variability, Ross County, Ohio and the State of Ohio were used as examples. All analyses performed considered four contaminants (benzene, trichloroethylene (TCE), chlordane, and benzo[a]pyrene (BAP)) and four exposure scenarios (commercial, recreational and on- and offsite residential). Regardless of whether uncertainty in risk at a single site or variability in risk across sites was evaluated, the exposure scenario specified and the properties of the target contaminant had more influence than variance in site parameters on the resulting variance and magnitude of the risk estimate. In general, variance in risk was found to be greater for the relatively less degradable and more mobile of the chemicals studied (TCE and chlordane) than for benzene which is highly degradable and BAP which is very immobile in the subsurface

  1. Plant and fungal biodiversity from metal mine wastes under remediation at Zimapan, Hidalgo, Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Ortega-Larrocea, Maria del Pilar [Departamento de Edafologia, Instituto de Geologia, Universidad Nacional Autonoma de Mexico (UNAM) (Mexico); Xoconostle-Cazares, Beatriz [Departamento de Biotecnologia y Bioingenieria, Centro de Investigacion y de Estudios Avanzados del Instituto Politecnico Nacional, Av. IPN 2508, Zacatenco 07360, D.F. (Mexico); Maldonado-Mendoza, Ignacio E. [Centro Interdisciplinario de Investigacion para el Desarrollo Integral Regional (CIIDIR)-Instituto Politecnico Nacional - Unidad Sinaloa, Blvd. Juan de Dios Batiz Paredes No. 250, Guasave, Sinaloa 81101 (Mexico); Carrillo-Gonzalez, Rogelio [Programa de Edafologia, Colegio de Postgraduados en Ciencias Agricolas, Campus Montecillo, Carretera Mexico-Texcoco, km 36.5, Texcoco, Estado de Mexico 56230 (Mexico); Hernandez-Hernandez, Jani [Departamento de Edafologia, Instituto de Geologia, Universidad Nacional Autonoma de Mexico (UNAM) (Mexico); Garduno, Margarita Diaz [Universidad Autonoma Chapingo, Carretera Mexico-Texcoco, km 38.5, Chapingo, Estado de Mexico 56230 (Mexico); Lopez-Meyer, Melina [Centro Interdisciplinario de Investigacion para el Desarrollo Integral Regional (CIIDIR)-Instituto Politecnico Nacional - Unidad Sinaloa, Blvd. Juan de Dios Batiz Paredes No. 250, Guasave, Sinaloa 81101 (Mexico); Gomez-Flores, Lydia [Departamento de Biotecnologia y Bioingenieria, Centro de Investigacion y de Estudios Avanzados del Instituto Politecnico Nacional, Av. IPN 2508, Zacatenco 07360, D.F. (Mexico); Gonzalez-Chavez, Ma. del Carmen A., E-mail: carmeng@colpos.m [Programa de Edafologia, Colegio de Postgraduados en Ciencias Agricolas, Campus Montecillo, Carretera Mexico-Texcoco, km 36.5, Texcoco, Estado de Mexico 56230 (Mexico)

    2010-05-15

    Plant establishment, presence of arbuscular mycorrhizal fungi (AMF) and other rhizospheric fungi were studied in mine wastes from Zimapan, Hidalgo state, Mexico, using a holistic approach. Two long-term afforested and three non-afforested mine tailings were included in this research. Fifty-six plant species belonging to 29 families were successfully established on the afforested sites, while unmanaged tailings had only a few native plant species colonizing the surrounding soils. Almost all plant roots collected were associated to AMF in these sites. The genus Glomus was the most abundant AMF species found in their rhizosphere; however, the Acaulospora genus was also observed. Other rhizospheric fungi were identified by 18S rDNA sequencing analysis. Their role in these substrates, i.e. biocontrol, pollutant- and organic matter-degradation, and aides that increase plant metal tolerance is discussed. Our results advance the understanding of fungal diversity in sites polluted with metals and present alternative plants for remediation use. - Rhizospheric fungi and organic matter encourage plant vegetation of tailings by pioneers and colonizing species.

  2. Plant and fungal biodiversity from metal mine wastes under remediation at Zimapan, Hidalgo, Mexico

    International Nuclear Information System (INIS)

    Ortega-Larrocea, Maria del Pilar; Xoconostle-Cazares, Beatriz; Maldonado-Mendoza, Ignacio E.; Carrillo-Gonzalez, Rogelio; Hernandez-Hernandez, Jani; Garduno, Margarita Diaz; Lopez-Meyer, Melina; Gomez-Flores, Lydia; Gonzalez-Chavez, Ma. del Carmen A.

    2010-01-01

    Plant establishment, presence of arbuscular mycorrhizal fungi (AMF) and other rhizospheric fungi were studied in mine wastes from Zimapan, Hidalgo state, Mexico, using a holistic approach. Two long-term afforested and three non-afforested mine tailings were included in this research. Fifty-six plant species belonging to 29 families were successfully established on the afforested sites, while unmanaged tailings had only a few native plant species colonizing the surrounding soils. Almost all plant roots collected were associated to AMF in these sites. The genus Glomus was the most abundant AMF species found in their rhizosphere; however, the Acaulospora genus was also observed. Other rhizospheric fungi were identified by 18S rDNA sequencing analysis. Their role in these substrates, i.e. biocontrol, pollutant- and organic matter-degradation, and aides that increase plant metal tolerance is discussed. Our results advance the understanding of fungal diversity in sites polluted with metals and present alternative plants for remediation use. - Rhizospheric fungi and organic matter encourage plant vegetation of tailings by pioneers and colonizing species.

  3. Characterization and remediation of a mixed waste-contaminated site at Kirtland Air Force Base, New Mexico

    International Nuclear Information System (INIS)

    Johnston, J.W.; Thacker, M.S.; DeWitt, C.B.

    1997-01-01

    In the area of environmental restoration, one of the most challenging problems is the task of remediating mixed waste-contaminated sites. This paper discusses a successful Interim Corrective Measure (ICM) performed at a mixed waste-contaminated site on Kirtland Air Force Base (AFB) in Albuquerque, New Mexico. The site, known as RW-68, Cratering Area and Radium Dump/Slag Piles, was used during the late 1940s and early 1950s for the destruction and incineration of captured World War II aircraft. It contained 19 slag piles totaling approximately 150 tons of slag, ash, refractory brick, and metal debris. The piles were contaminated with radium-226 and RCRA-characteristic levels of heavy metals. Therefore, the piles were considered mixed waste. To eliminate the threat to human health and the environment, an ICM of removal, segregation, stabilization, and disposal was conducted from October through December 1996. Approximately 120 cubic yards (cu yds) of mixed waste, 188 cu yds of low-level radioactive-contaminated soil, 1 cu yd of low-level radioactive-contaminated debris, 5 cu yds of RCRA-characteristic hazardous waste, and 45 tons of nonhazardous debris were stabilized and disposed of during the ICM. To render the RCRA metals and radionuclides insoluble, stabilization was performed on the mixed and RCRA-characteristic waste streams. All stabilized material was subjected to TCLP analysis to verify it no longer exhibited RCRA-characteristic properties. Radiological and geophysical surveys were conducted concurrently with site remediation activities. These surveys provided real-time documentation of site conditions during each phase of the ICM and confirmed successful cleanup of the site. The three radioactive waste streams, stabilized mixed waste, low-level radioactive-contaminated soil, and low-level radioactive-contaminated debris, were disposed of at the Envirocare low-level radioactive disposal facility

  4. Performance-Based Technology Selection Filter description report. INEL Buried Waste Integrated Demonstration System Analysis project

    Energy Technology Data Exchange (ETDEWEB)

    O`Brien, M.C.; Morrison, J.L.; Morneau, R.A.; Rudin, M.J.; Richardson, J.G.

    1992-05-01

    A formal methodology has been developed for identifying technology gaps and assessing innovative or postulated technologies for inclusion in proposed Buried Waste Integrated Demonstration (BWID) remediation systems. Called the Performance-Based Technology Selection Filter, the methodology provides a formalized selection process where technologies and systems are rated and assessments made based on performance measures, and regulatory and technical requirements. The results are auditable, and can be validated with field data. This analysis methodology will be applied to the remedial action of transuranic contaminated waste pits and trenches buried at the Idaho National Engineering Laboratory (INEL).

  5. Decentralized Energy from Waste Systems

    Directory of Open Access Journals (Sweden)

    Blanca Antizar-Ladislao

    2010-01-01

    Full Text Available In the last five years or so, biofuels have been given notable consideration worldwide as an alternative to fossil fuels, due to their potential to reduce greenhouse gas emissions by partial replacement of oil as a transport fuel. The production of biofuels using a sustainable approach, should consider local production of biofuels, obtained from local feedstocks and adapted to the socio-economical and environmental characteristics of the particular region where they are developed. Thus, decentralized energy from waste systems will exploit local biomass to optimize their production and consumption. Waste streams such as agricultural and wood residues, municipal solid waste, vegetable oils, and algae residues can all be integrated in energy from waste systems. An integral optimization of decentralized energy from waste systems should not be based on the optimization of each single process, but the overall optimization of the whole process. This is by obtaining optimal energy and environmental benefits, as well as collateral beneficial co-products such as soil fertilizers which will result in a higher food crop production and carbon dioxide fixation which will abate climate change.

  6. Decentralized energy from waste systems

    International Nuclear Information System (INIS)

    Antizar-Ladislao, B.; Turrion-Gomez, J. L.

    2010-01-01

    In the last five years or so, biofuels have been given notable consideration worldwide as an alternative to fossil fuels, due to their potential to reduce greenhouse gas emissions by partial replacement of oil as a transport fuel. The production of biofuels using a sustainable approach, should consider local production of biofuels, obtained from local feedstocks and adapted to the socio-economical and environmental characteristics of the particular region where they are developed. Thus, decentralized energy from waste systems will exploit local biomass to optimize their production and consumption. Waste streams such as agricultural and wood residues, municipal solid waste, vegetable oils, and algae residues can all be integrated in energy from waste systems. An integral optimization of decentralized energy from waste systems should not be based on the optimization of each single process, but the overall optimization of the whole process. This is by obtaining optimal energy and environmental benefits, as well as collateral beneficial co-products such as soil fertilizers which will result in a higher food crop production and carbon dioxide fixation which will abate climate change. (author)

  7. Waste collection systems for recyclables

    DEFF Research Database (Denmark)

    Larsen, Anna Warberg; Merrild, Hanna Kristina; Møller, Jacob

    2010-01-01

    and technical limitations are respected, and what will the environmental and economic consequences be? This was investigated in a case study of a municipal waste management system. Five scenarios with alternative collection systems for recyclables (paper, glass, metal and plastic packaging) were assessed...... and treatment of waste were reduced with increasing recycling, mainly because the high cost for incineration was avoided. However, solutions for mitigation of air pollution caused by increased collection and transport should be sought. (C) 2009 Elsevier Ltd. All rights reserved....

  8. Remediation and assessment of the national radioactive waste storage and disposal site in Tajikistan - 59110

    International Nuclear Information System (INIS)

    Buriev, Nazirzhon T.; Abdushukurov, Dzhamshed A.; Vandergraaf, Tjalle T.

    2012-01-01

    The National Radioactive Waste Storage and Disposal Site was established in 1959 in the Faizabad region approximately 50 km east of the capital, Dushanbe. The site is located on the southern flank of the Fan Mountains facing the Gissar Valley in a sparsely populated agricultural area, with the nearest villages located a few km from the site. The site was initially designed to accept a wide range of contaminated materials, including obsolete smoke detectors, sealed radioactive sources, waste from medical institutions, and radioactive liquids. Between 1962 and 1976, 363 tonnes and 1146 litres of material, contaminated with a range of radionuclides were shipped to the site. Between 1972 - 1980 and 1985 - 1991, ∼4.8 x 10 14 and 2 x 10 13 Bq, respectively, were shipped to the site. An additional 7 x 10 14 Bq was shipped to the site in 1996. Partly as a result of the dissolution of the former Soviet Union, the disposal site had fallen into disrepair and currently presents both an environmental hazard and a potential for the proliferation of radionuclides that could potentially be used for illicit purposes. Remediation of the disposal site was started in 2005. New security fences were erected and a new superstructure over an in-ground storage site constructed. A central alarm monitoring and observation station has been constructed and is now operational. The geology, flora, and fauna of the region have been documented. Radiation surveys of the buildings and the storage and disposal sites have been carried out. Samples of soil, surface water and vegetation have been taken and analyzed by gamma spectrometry. Results show a slight extent of contamination of soils near the filling ports of the underground liquid storage container where a Cs-137 concentration of 2.3 x 104 Bq/kg was obtained. Similar values were obtained for Ra- 226. Radiation fields of the in-ground storage site were generally 3 . Most of the activity appears to be associated with the sediments in the tank

  9. Waste management plan for the remedial investigation/feasibility study of Waste Area Grouping 5 at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1992-12-01

    This plan defines the criteria and methods to be used for managing waste generated during activities associated with Waste Area Grouping (WAG) 5 at Oak Ridge National Laboratory (ORNL). WAG 5 is located in Melton Valley, south of the main ORNL plant area. It contains 17 solid waste management units (SWMUs) to be evaluated during the remedial investigation. The SWMUs include three burial areas, two hydrofracture facilities, two settling ponds, eight tanks, and two low-level liquid waste leak sites. These locations are all considered to be within the WAG 5 area of contamination (AOC). The plan contains provisions for safely and effectively managing soils, rock cuttings, development and sampling water, decontamination fluids, and disposable personal protective equipment (PPE) consistent with the Environmental Protection Agency (EPA) guidance of May 1991 (EPA 1991). Consistent with EPA guidance, this plan is designed to protect the environment and the health and safety of workers and the public

  10. Nuclear Facility Isotopic Content (NFIC) Waste Management System to provide input for safety envelope definition

    International Nuclear Information System (INIS)

    Genser, J.R.

    1992-01-01

    The Westinghouse Savannah River Company (WSRC) is aggressively applying environmental remediation and radioactive waste management activities at the US Department of Energy's Savannah River Site (SRS) to ensure compliance with today's challenging governmental laws and regulatory requirements. This report discusses a computer-based Nuclear Facility Isotopic Content (NFIC) Waste Management System developed to provide input for the safety envelope definition and assessment of site-wide facilities. Information was formulated describing the SRS ''Nuclear Facilities'' and their respective bounding inventories of nuclear materials and radioactive waste using the NFIC Waste Management System

  11. Phase I remedial investigation report of Waste Area Grouping 2 at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    Miller, D.E.

    1995-07-01

    This report presents the activities and findings of the first phase of a three-phase remedial investigation (RI) of Waste Area Grouping (WAG) 2 at Oak Ridge National Laboratory (ORNL) in Oak Ridge, Tennessee, and updates the scope and strategy for WAG-2-related efforts. WAG 2 contains White Oak Creek (WOC) and its tributaries downstream of the ORNL main plant area, White Oak Lake, White Oak Creek Embayment on the Clinch River, and the associated floodplain and subsurface environment. Water, sediment, soil, and biota in WAG 2 are contaminated and continue to receive contaminants from upgradient WAGs. This report includes field activities completed through October 1992. The remediation of WAG 2 is scheduled to follow the cessation of contaminant input from hydrologically upgradient WAGs. While upgradient areas are being remediated, the strategy for WAG 2 is to conduct a long-term monitoring and investigation program that takes full advantage of WAG 2's role as an integrator of contaminant fluxes from other ORNL WAGs and focuses on four key goals: (1) Implement, in concert with other programs, long-term, multimedia environmental monitoring and tracking of contaminants leaving other WAGs, entering WAG 2, and being transported off-site. (2) Provide a conceptual framework to integrate and develop information at the watershed-level for pathways and processes that are key to contaminant movement, and so support remedial efforts at ORNL. (3) Provide periodic updates of estimates of potential risk (both human health and ecological) associated with contaminants accumulating in and moving through WAG 2 to off-site areas. (4) Support the ORNL Environmental Restoration Program efforts to prioritize, remediate, and verify remedial effectiveness for contaminated sites at ORNL, through long-term monitoring and continually updated risk assessments

  12. Colloid formation as an approach to remediate toxic wastes containing chromium and lead

    Energy Technology Data Exchange (ETDEWEB)

    Barton, Larry L [Laboratory of Microbial Chemistry, Department of Biology, University of New Mexico, Albuquerque, NM (United States); Lindemann, William C [Department of Agronomy and Horticulture, New Mexico State University, Las Cruces, NM (United States); Bearden, Deborah L [Department of Chemical and Nuclear Engineering, University of New Mexico, Albuquerque, NM (United States)

    1992-07-01

    We have explored the use of bacteria to remediate soil and aquatic sites containing toxic levels of Pb II or Cr VI. Bacterial isolates from metal-containing sites are capable of detoxifying water containing up to 10 mM Pb II. This activity is a two step process with an initial binding of Pb II to the cells followed by production of a black Pb-containing colloid. Numerous bacteria will reduce Cr VI to Cr III and some isolates have been found to bind Cr III to the bacterial cell. Colloids consisting of Cr III would result from the formation of chromium hydroxide or from binding to bacteria. The bacterial metabolism of Pb II and Cr III converts the biologically toxic and chemically reactive metal to compounds of reduced toxicity and modified chemical activity. We propose a system which can employ bacteria for the bioremediation of toxic sites containing lead or chromium. (author)

  13. LCA of Solid Waste Management Systems

    DEFF Research Database (Denmark)

    Bakas, Ioannis; Laurent, Alexis; Clavreul, Julie

    2018-01-01

    The chapter explores the application of LCA to solid waste management systems through the review of published studies on the subject. The environmental implications of choices involved in the modelling setup of waste management systems are increasingly in the spotlight, due to public health...... concerns and new legislation addressing the impacts from managing our waste. The application of LCA to solid waste management systems, sometimes called “waste LCA”, is distinctive in that system boundaries are rigorously defined to exclude all life cycle stages except from the end-of-life. Moreover...... LCA on solid waste systems....

  14. Radioactive liquid waste processing system

    International Nuclear Information System (INIS)

    Noda, Tetsuya; Kuramitsu, Kiminori; Ishii, Tomoharu.

    1997-01-01

    The present invention provides a system for processing radioactive liquid wastes containing laundry liquid wastes, shower drains or radioactive liquid wastes containing chemical oxygen demand (COD) ingredients and oil content generated from a nuclear power plant. Namely, a collecting tank collects radioactive liquid wastes. A filtering device is connected to the exit of the collective tank. A sump tank is connected to the exit of the filtering device. A powdery active carbon supplying device is connected to the collecting tank. A chemical fluid tank is connected to the collecting tank and the filtering device by way of chemical fluid injection lines. Backwarding pipelines connect a filtered water flowing exit of the filtering device and the collecting tank. The chemical solution is stored in the chemical solution tank. Then, radioactive materials in radioactive liquid wastes generated from a nuclear power plant are removed by the filtering device. The water quality standard specified in environmental influence reports can be satisfied. In the filtering device, when the filtering flow rate is reduced, the chemical fluid is supplied from the chemical fluid tank to the filtering device to recover the filtering flow rate. (I.S.)

  15. Integrating radiation protection criteria for radioactive waste management into remediation procedures in existing exposure situations after a nuclear accident.

    Science.gov (United States)

    Sugiyama, Daisuke; Kimura, Hideo; Tachikawa, Hirokazu; Iimoto, Takeshi; Kawata, Yosuke; Ogino, Haruyuki; Okoshi, Minoru

    2018-03-01

    Experience after the accident at the Fukushima Daiichi nuclear power station has shown that there is a need to establish radiation protection criteria for radioactive waste management consistent with the criteria adopted for the remediation of existing exposure situations. A stepwise approach to setting such criteria is proposed. Initially, a reference level for the annual effective dose from waste management activities in the range 1-10 mSv should be set, with the reference level being less than the reference level for the ambient dose. Subsequently, the reference level for the annual effective dose from waste management activities should be reduced in one or more steps to achieve a final target value of 1 mSv. The dose criteria at each stage should be determined with relevant stakeholder involvement. Illustrative case studies show how this stepwise approach might be applied in practice.

  16. Implementation of a funnel-and-gate remediation system

    International Nuclear Information System (INIS)

    O'Brien, K.; Keyes, G.; Sherman, N.

    1997-01-01

    A funnel-and-gate trademark system incorporating activated carbon was deemed the most attractive remediation method for an active lumber mill in the western United States. Petroleum hydrocarbons, chlorinated solvents, pentachlorophenol, and tetrachlorophenol were detected in on-site groundwater samples. The shallow aquifer consists of a heterogeneous mixture of marine deposits and artificial fill, underlain by low-permeability siltstones and mudstone. In the funnel-and-gate trademark system, a low-permeability cutoff wall was installed to funnel groundwater flow to a smaller area (a open-quotes gateclose quotes) where a passive below-grade treatment system treats the plume as it flows through the gate. Groundwater flow modeling focused on the inhomogeneities of the aquifer and the spatial relationship between gate(s) and barrier walls. The gate design incorporates several factors, including contaminant concentration, flow rate, and time between carbon changeouts. To minimize back pressure and maximize residence time, each gate was designed using 1.25-meter (4-foot) diameter corrugated metal pipe filled with a 1.25-meter (4-foot) thick bed of activated carbon. The configuration will allow water to flow through the treatment gates without pumps. The installed system is 190 meters (625 feet) long and treats approximately 76 L/min (20 gpm) during the winter months

  17. Packaged low-level waste verification system

    Energy Technology Data Exchange (ETDEWEB)

    Tuite, K.; Winberg, M.R.; McIsaac, C.V. [Idaho National Engineering Lab., Idaho Falls, ID (United States)

    1995-12-31

    The Department of Energy through the National Low-Level Waste Management Program and WMG Inc. have entered into a joint development effort to design, build, and demonstrate the Packaged Low-Level Waste Verification System. Currently, states and low-level radioactive waste disposal site operators have no method to independently verify the radionuclide content of packaged low-level waste that arrives at disposal sites for disposition. At this time, the disposal site relies on the low-level waste generator shipping manifests and accompanying records to ensure that low-level waste received meets the site`s waste acceptance criteria. The subject invention provides the equipment, software, and methods to enable the independent verification of low-level waste shipping records to ensure that the site`s waste acceptance criteria are being met. The objective of the prototype system is to demonstrate a mobile system capable of independently verifying the content of packaged low-level waste.

  18. Bench scale experiments for the remediation of Hanford Waste Treatment Plant low activity waste melter off-gas condensate

    Energy Technology Data Exchange (ETDEWEB)

    Taylor-Pashow, Kathryn M.L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Poirier, Michael [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); McCabe, Daniel J. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2017-08-11

    The Low Activity Waste (LAW) vitrification facility at the Hanford Waste Treatment and Immobilization Plant (WTP) will generate an aqueous condensate recycle stream (LAW Off-Gas Condensate) from the off-gas system. The plan for disposition of this stream during baseline operations is to send it to the WTP Pretreatment Facility, where it will be blended with LAW, concentrated by evaporation and recycled to the LAW vitrification facility again. The primary reason to recycle this stream is so that the semi-volatile 99Tc isotope eventually becomes incorporated into the glass. This stream also contains non-radioactive salt components that are problematic in the melter, so diversion of this stream to another process would eliminate recycling of these salts and would enable simplified operation of the LAW melter and the Pretreatment Facilities. This diversion from recycling this stream within WTP would have the effect of decreasing the LAW vitrification mission duration and quantity of glass waste. The concept being tested here involves removing the 99Tc so that the decontaminated aqueous stream, with the problematic salts, can be disposed elsewhere.

  19. Waste Feed Delivery System Phase 1 Preliminary Reliability and Availability and Maintainability Analysis [SEC 1 and 2

    Energy Technology Data Exchange (ETDEWEB)

    CARLSON, A.B.

    1999-11-11

    The document presents updated results of the preliminary reliability, availability, maintainability analysis performed for delivery of waste feed from tanks 241-AZ-101 and 241-AN-105 to British Nuclear Fuels Limited, inc. under the Tank Waste Remediation System Privatization Contract. The operational schedule delay risk is estimated and contributing factors are discussed.

  20. Waste Feed Delivery System Phase 1 Preliminary Reliability and Availability and Maintainability Analysis [SEC 1 and 2

    International Nuclear Information System (INIS)

    CARLSON, A.B.

    1999-01-01

    The document presents updated results of the preliminary reliability, availability, maintainability analysis performed for delivery of waste feed from tanks 241-AZ-101 and 241-AN-105 to British Nuclear Fuels Limited, inc. under the Tank Waste Remediation System Privatization Contract. The operational schedule delay risk is estimated and contributing factors are discussed

  1. Final Hazard Categorization for the Remediation of Six 300-FF-2 Operable Unit Solid Waste Burial Grounds

    International Nuclear Information System (INIS)

    Ludowise, J.D.

    2006-01-01

    This report provides the final hazard categorization (FHC) for the remediation of six solid waste disposal sites (referred to as burial grounds) located in the 300-FF-2 Operable Unit (OU) on the Hanford Site. These six sites (618-1, 618-2, 618-3, 618-7, 618-8, and 618-13 Burial Grounds) were determined to have a total radionuclide inventory (WCH 2005a, WCH 2005d, WCH 2005e and WCH 2006b) that exceeds the DOE-STD-1027 Category 3 threshold quantity (DOE 1997) and are the subject of this analysis. This FHC document examines the hazards, identifies appropriate controls to manage the hazards, and documents the FHC and commitments for the 300-FF-2 Burial Grounds Remediation Project

  2. Final Hazard Categorization for the Remediation of Six 300-FF-2 Operable Unit Solid Waste Burial Grounds

    Energy Technology Data Exchange (ETDEWEB)

    J. D. Ludowise

    2006-12-12

    This report provides the final hazard categorization (FHC) for the remediation of six solid waste disposal sites (referred to as burial grounds) located in the 300-FF-2 Operable Unit (OU) on the Hanford Site. These six sites (618-1, 618-2, 618-3, 618-7, 618-8, and 618-13 Burial Grounds) were determined to have a total radionuclide inventory (WCH 2005a, WCH 2005d, WCH 2005e and WCH 2006b) that exceeds the DOE-STD-1027 Category 3 threshold quantity (DOE 1997) and are the subject of this analysis. This FHC document examines the hazards, identifies appropriate controls to manage the hazards, and documents the FHC and commitments for the 300-FF-2 Burial Grounds Remediation Project.

  3. Multi agent gathering waste system

    Directory of Open Access Journals (Sweden)

    Álvaro LOZANO MURCIEGO

    2016-07-01

    Full Text Available Along this paper, we present a new multi agent-based system to gather waste on cities and villages. We have developed a low cost wireless sensor prototype to measure the volume level of the containers. Furthermore a route system is developed to optimize the routes of the trucks and a mobile application has been developed to help drivers in their working days. In order to evaluate and validate the proposed system a practical case study in a real city environment is modeled using open data available and with the purpose of identifying limitations of the system.

  4. Issues and remedies for secondary system of PWR/VVER

    International Nuclear Information System (INIS)

    Nordmann, Francis; Odar, Suat; Rochester, Dewey

    2012-09-01

    Secondary side degradation of steam generators (SG) and Flow Accelerated Corrosion (FAC) in the secondary system have been for a long time important issues in PWR and VVER types of Nuclear Power Plants. With the evolution of the design, the most important issues are progressively moving from secondary side corrosion of Alloy 600 SG tubing, which is being replaced, to a larger variety of risks associated with potential inadequate chemistries. As far as FAC of carbon steel is concerned, the evolution of treatment selection for minimizing corrosion products transport toward the SG, as well as progressive replacement of components in the feedwater train, decreases the risk of dramatic failures which have occurred in the past. After having briefly explained the reason for the past problems encountered in the secondary system of PWR and VVER, this paper evaluates the risk associated with various impurities or contaminants that may be present in the secondary system and how to mitigate them in the most appropriate, efficient, economical and environmental friendly way. The covered species are sodium, calcium, magnesium, chloride, sulfate and sulfur compounds, fluorides, organic compounds, silica, oxygen, lead, ion exchange resins. This paper also proposes the best remedies for mitigating the new issues that may be encountered in operating plants or units under construction. These are mainly: - Selecting a steam water treatment able to minimize the quantity of corrosion products transported toward the SG; - Mitigating the risk of Flow Induced Vibration by a proper control of deposits in sensitive areas; - Minimizing the risk of concentration of impurities in local areas where they may induce corrosion; - Avoiding the presence of abnormal quantities of some species in SG, such as the detrimental presence of lead and ion exchange resin debris or the controversial presence of organic compounds; - Optimizing costs of maintenance activities (SG mechanical, chemical cleaning

  5. 76 FR 16534 - Hazardous Waste Management System Identification and Listing of Hazardous Waste; Final Exclusion

    Science.gov (United States)

    2011-03-24

    ... Waste Management System Identification and Listing of Hazardous Waste; Final Exclusion AGENCY...) on a one-time basis from the lists of hazardous waste, a certain solid waste generated at its Mt... waste is [[Page 16535

  6. Radioactive waste gas processing systems

    International Nuclear Information System (INIS)

    Kita, Kaoru; Minemoto, Masaki; Takezawa, Kazuaki.

    1981-01-01

    Purpose: To effectively separate and remove only hydrogen from hydrogen gas-containing radioactive waste gases produced from nuclear power plants without using large scaled facilities. Constitution: From hydrogen gas-enriched waste gases which contain radioactive rare gases (Kr, Xe) sent from the volume control tank of a chemical volume control system, only the hydrogen is separated in a hydrogen separator using palladium alloy membrane and rare gases are concentrated, volume-decreased and then stored. In this case, an activated carbon adsorption device is connected at its inlet to the radioactive gas outlet of the hydrogen separator and opened at its outlet to external atmosphere. In this system, while only the hydrogen gas permeates through the palladium alloy membrane, other gases are introduced, without permeation, into the activated carbon adsorption device. Then, the radioactive rare gases are decayed by the adsorption on the activated carbon and then released to the external atmosphere. (Furukawa, Y.)

  7. Waste Feed Delivery Transfer System Analysis

    Energy Technology Data Exchange (ETDEWEB)

    JULYK, L.J.

    2000-05-05

    This document provides a documented basis for the required design pressure rating and pump pressure capacity of the Hanford Site waste-transfer system in support of the waste feed delivery to the privatization contractor for vitrification. The scope of the analysis includes the 200 East Area double-shell tank waste transfer pipeline system and the associated transfer system pumps for a11 Phase 1B and Phase 2 waste transfers from AN, AP, AW, AY, and A2 Tank Farms.

  8. Waste Feed Delivery Transfer System Analysis

    International Nuclear Information System (INIS)

    JULYK, L.J.

    2000-01-01

    This document provides a documented basis for the required design pressure rating and pump pressure capacity of the Hanford Site waste-transfer system in support of the waste feed delivery to the privatization contractor for vitrification. The scope of the analysis includes the 200 East Area double-shell tank waste transfer pipeline system and the associated transfer system pumps for a11 Phase 1B and Phase 2 waste transfers from AN, AP, AW, AY, and A2 Tank Farms

  9. 75 FR 11002 - Hazardous Waste Management System; Identification and Listing of Hazardous Waste; Final Rule

    Science.gov (United States)

    2010-03-10

    ... Waste Management System; Identification and Listing of Hazardous Waste; Final Rule AGENCY: Environmental... and specific types of management of the petitioned waste, the quantities of waste generated, and waste... wastes. This final rule responds to a petition submitted by Valero to delist F037 waste. The F037 waste...

  10. Defense High Level Waste Disposal Container System Description Document

    International Nuclear Information System (INIS)

    2000-01-01

    will be selected for the disposal container inner and outer cylinders. The two metal cylinders, in combination with the Emplacement Drift System, drip shield, and natural barrier, will support the design philosophy of defense-in-depth. The use of materials with different properties prevents a single mode failure from breaching the waste package. The inner cylinder and inner cylinder lids will be constructed of stainless steel and the outer cylinder and outer cylinder lids will be a barrier made of high-nickel alloy. The defense HLW disposal container interfaces with the emplacement drift environment and the internal waste by transferring heat from the canisters to the external environment and by protecting the canisters and their contents from damage/degradation by the external environment. The disposal container also interfaces with the canisters by limiting access of moderator and oxidizing agents to the waste. A loaded and sealed disposal container (waste package) interfaces with the Emplacement Drift System's emplacement drift waste package supports upon which the waste packages are placed. The disposal container interfaces with the Canister Transfer System, Waste Emplacement /Retrieval System, Disposal Container Handling System, and Waste Package Remediation System during loading, handling, transfer, emplacement, and retrieval for the disposal container/waste package

  11. Transport concept of new waste management system (inner packaging system)

    International Nuclear Information System (INIS)

    Hakozaki, K.; Wada, R.

    2004-01-01

    Kobe Steel, Ltd. (KSL) and Transnuclear Tokyo (TNT) have jointly developed a new waste management system concept (called ''Inner packaging system'') for high dose rate wastes generated from nuclear power plants under cooperation with Tokyo Electric Power Company (TEPCO). The inner packaging system is designed as a total management system dedicated to the wastes from nuclear plants in Japan, covering from the wastes conditioning in power plants up to the disposal in final repository. This paper presents the new waste management system concept

  12. Risk assessment and optimization (ALARA) analysis for the environmental remediation of Brookhaven National Laboratory's hazardous waste management facility

    International Nuclear Information System (INIS)

    Dionne, B.J.; Morris, S. III; Baum, J.W.

    1998-03-01

    The Department of Energy's (DOE) Office of Environment, Safety, and Health (EH) sought examples of risk-based approaches to environmental restoration to include in their guidance for DOE nuclear facilities. Extensive measurements of radiological contamination in soil and ground water have been made at Brookhaven National Laboratory's Hazardous Waste Management Facility (HWMF) as part of a Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) remediation process. This provided an ideal opportunity for a case study. This report provides a risk assessment and an open-quotes As Low as Reasonably Achievableclose quotes (ALARA) analysis for use at other DOE nuclear facilities as an example of a risk-based decision technique

  13. The Excavation and Remediation of the Sandia National Laboratories Chemical Waste Landfill

    International Nuclear Information System (INIS)

    KWIECINSKI, DANIEL ALBERT; METHVIN, RHONDA KAY; SCHOFIELD, DONALD P.; YOUNG, SHARISSA G.

    1999-01-01

    The Chemical Waste Landfill (CWL) at Sandia National Laboratories/New Mexico (SNL/NM) is a 1.9-acre disposal site that was used for the disposal of chemical wastes generated by many of SNL/NM research laboratories from 1962 until 1985. These laboratories were primarily involved in the design, research and development of non-nuclear components of nuclear weapons and the waste generated by these labs included small quantities of a wide assortment of chemical products. A Resource Conservation and Recovery Act (RCRA) Closure Plan for the Chemical Waste Landfill was approved by the New Mexico Environment Department (NMED) in 1992. Subsequent site characterization activities identified the presence of significant amounts of chromium in the soil as far as 80 feet below ground surface (fbgs) and the delineation of a solvent plume in the vadose zone that extends to groundwater approximately 500 fbgs. Trichloroethylene (TCE) was detected in some groundwater samples at concentrations slightly above the drinking water limit of 5 parts per billion. In 1997 an active vapor extraction system reduced the size of the TCE vapor plume and for the last six quarterly sampling events groundwater samples have not detected TCE above the drinking water standard. A source term removal, being conducted as a Voluntary Corrective Measure (VCM), began in September 1998 and is expected to take up to two years. Four distinct disposal areas were identified from historical data and the contents of disposal pits and trenches in these areas, in addition to much of the highly contaminated soil surrounding the disposal cells, are currently being excavated. Buried waste and debris are expected to extend to a depth of 12 to 15 fbgs. Excavation will focus on the removal of buried debris and contaminated soil in a sequential, area by area manner and will proceed to whatever depth is required in order to remove all pit contents. Up to 50,000 cubic yards of soil and debris will be removed and managed during

  14. Completion report for the Inactive Liquid Low-Level Waste Tank Remediation Project at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1996-02-01

    This report documents the results of the Inactive Liquid Low-Level Waste Tank Remediation Project at Oak Ridge National Laboratory (ORNL). The work performed is compared with that proposed in the statement of work and the service contract specification for the maintenance action to remediate tanks 3013, 3004-B, T-30, and 3001-B. The Federal Facility Agreement (FFA) among the U.S. Environmental Protection Agency (EPA), the Tennessee Department of Environment and Conservation (TDEC), and the U.S. Department of Energy (DOE) requires that all tanks, which have been removed from service and are designated in the FFA as Category D, must be remediated in accordance with the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) requirements. The Environmental Restoration Program's inactive tank removal program strategy and plans for remediating the inactive LLLW tanks were documented in a report issued in January 1995 (Inactive Tanks Remediation Program Strategy and Plans for Oak Ridge National Laboratory, Oak Ridge, Tennessee, ORNL/ER-297). The inactive (Category D) tanks were initially screened for remediation according to risk, remediation technology required, level of instrumentation available, interferences with other piping and equipment, location, and available sludge removal techniques and storage requirements. On the basis of this preliminary screening, the tanks were assigned to one of five batches (I through V) for consideration of remedial action alternatives, and these batches were tentatively scheduled for remedial actions. The eight links tentatively assigned to Batch I were divided into two groups (Series I and Series II)

  15. Issues and remedies for secondary system of PWR/VVER

    International Nuclear Information System (INIS)

    Nordmann, F.; Odar, S.; Rochester, D.

    2012-01-01

    Secondary side degradation of steam generators (SG) tubing with Alloy 600 MA and flow accelerated corrosion (FAC) of carbon steel have been for a long time important issues for the secondary system of PWR and VVER. With the beneficial evolution of the design (for instance the replacement of Alloy 600 SG tubing), the most important issues are progressively moving to a larger variety of risks associated to potential inadequate chemistries. The best remedies for mitigating the new concerns are: -) selecting a steam water treatment able to minimize the quantity of corrosion products transported to the steam generator, -) mitigating the risk of flow induced vibration by a proper control of deposits in sensitive areas, -) minimizing the risk of concentration of impurities in local areas where they may induce corrosion. The paper also explains: -) the benefit of eliminating or by pass of condensate polishers, -) the absence of need for expensive lead investigation, if no specific pollution occurred, -) the absence of need for very low oxygen in the condensate water, and -) the necessary and optimum number of on-line monitors

  16. In-situ remediation system for groundwater and soils

    Science.gov (United States)

    Corey, John C.; Kaback, Dawn S.; Looney, Brian B.

    1993-01-01

    A method and system for in-situ remediation of contaminated groundwater and soil where the contaminants, such as toxic metals, are carried in a subsurface plume. The method comprises selection and injection into the soil of a fluid that will cause the contaminants to form stable, non-toxic compounds either directly by combining with the contaminants or indirectly by creating conditions in the soil or changing the conditions of the soil so that the formation of stable, non-toxic compounds between the contaminants and existing substances in the soil are more favorable. In the case of non-toxic metal contaminants, sulfides or sulfates are injected so that metal sulfides or sulfates are formed. Alternatively, an inert gas may be injected to stimulate microorganisms in the soil to produce sulfides which, in turn, react with the metal contaminants. Preferably, two wells are used, one to inject the fluid and one to extract the unused portion of the fluid. The two wells work in combination to create a flow of the fluid across the plume to achieve better, more rapid mixing of the fluid and the contaminants.

  17. Program plan for evaluation and remediation of the generation and release of flammable gases in Hanford Site waste tanks

    International Nuclear Information System (INIS)

    Johnson, G.D.

    1991-08-01

    This program plan describes the activities being conducted for the resolution of the flammable gas problem that is associated with 23 high-level waste tanks at the Hanford Site. The classification of the wastes in all of these tanks is not final and some wastes may not be high-level wastes. However, until the characterization and classification is complete, all the tanks are treated as if they contain high-level waste. Of the 23 tanks, Tank 241-SY-101 (referred to as Tank 101-SY) has exhibited significant episodic releases of flammable gases (hydrogen and nitrous oxide) for the past 10 years. The major near-term focus of this program is for the understanding and stabilization of this tank. An understanding of the mechanism for gas generation and the processes for the episodic release will be obtained through sampling of the tank contents, laboratory studies, and modeling of the tank behavior. Additional information will be obtained through new and upgraded instrumentation for the tank. A number of remediation, or stabilization, concepts will be evaluated for near-term (2 to 3 years) applications to Tank 101-SY. Detailed safety assessments are required for all activities that will occur in the tank (sampling, removal of equipment, and addition of new instruments). This program plan presents a discussion of each task, provides schedules for near-term activities, and gives a summary of the expected work for fiscal years 1991, 1992, and 1993. 16 refs., 7 figs., 8 tabs

  18. Program plan for evaluation and remediation of the generation and release of flammable gases in Hanford Site waste tanks

    Energy Technology Data Exchange (ETDEWEB)

    Johnson, G.D. (comp.)

    1991-08-01

    This program plan describes the activities being conducted for the resolution of the flammable gas problem that is associated with 23 high-level waste tanks at the Hanford Site. The classification of the wastes in all of these tanks is not final and some wastes may not be high-level wastes. However, until the characterization and classification is complete, all the tanks are treated as if they contain high-level waste. Of the 23 tanks, Tank 241-SY-101 (referred to as Tank 101-SY) has exhibited significant episodic releases of flammable gases (hydrogen and nitrous oxide) for the past 10 years. The major near-term focus of this program is for the understanding and stabilization of this tank. An understanding of the mechanism for gas generation and the processes for the episodic release will be obtained through sampling of the tank contents, laboratory studies, and modeling of the tank behavior. Additional information will be obtained through new and upgraded instrumentation for the tank. A number of remediation, or stabilization, concepts will be evaluated for near-term (2 to 3 years) applications to Tank 101-SY. Detailed safety assessments are required for all activities that will occur in the tank (sampling, removal of equipment, and addition of new instruments). This program plan presents a discussion of each task, provides schedules for near-term activities, and gives a summary of the expected work for fiscal years 1991, 1992, and 1993. 16 refs., 7 figs., 8 tabs.

  19. Waste processing system for nuclear power plant

    International Nuclear Information System (INIS)

    Higashinakagawa, Emiko; Tezuka, Fuminobu; Maesawa, Yukishige; Irie, Hiromitsu; Daibu, Etsuji.

    1996-01-01

    The present invention concerns a waste processing system of a nuclear power plant, which can reduce the volume of a large amount of plastics without burying them. Among burnable wastes and plastic wastes to be discarded in the power plant located on the sea side, the plastic wastes are heated and converted into oils, and the burnable wastes are burnt using the oils as a fuel. The system is based on the finding that the presence of Na 2 O, K 2 O contained in the wastes catalytically improves the efficiency of thermal decomposition in a heating atmosphere, in the method of heating plastics and converting them into oils. (T.M.)

  20. Waste Management System Description Document (WMSD)

    International Nuclear Information System (INIS)

    1992-02-01

    This report is an appendix of the ''Waste Management Description Project, Revision 1''. This appendix is about the interim approach for the technical baseline of the waste management system. It describes the documentation and regulations of the waste management system requirements and description. (MB)

  1. Environmental remediation of the Wismut legacy and utilization of the reclaimed areas, waste rock piles and tailings ponds

    International Nuclear Information System (INIS)

    Hagen, M.; Jakubick, A.T.

    2006-01-01

    Between 1945 and reunification (1989) of Germany more than 232 000 t of U 3 O 8 has been produced in Saxony and Thuringia, East Germany. This affected an area of approximately 100 km 2 and left behind an extensive legacy of contaminated operations areas, underground and open pit mines, waste rock piles and tailings ponds. Following reunification, DM 13 billion (Euro 6.6 billion) were committed (and later revised to Euro 6.2 billion) to remediation of the liabilities and the government owned corporation, Wismut GmbH entrusted with the implementation of the Environmental Remediation (ER) of the liabilities. The prime goal of the ER Project follows from the legal requirements to abate health risks, mitigate existing and prevent future environmental damages. During the investigations and assessment of risks, development of remediation concepts, adoption of suitable technologies and work procedures as well as physical implementation of the remedial measures extensive use was made of international (mostly US and Canadian) ER experience. The extent of remedial measures was based on object-specific Environmental Assessments rather than on uniformly applied health/environmental standards. The ER workflow is more an iterative process than a linear succession of tasks, such as common for civil engineering projects. The internal (technical) parts of the problems were partly resolved by using Conceptual Site Models (CSM) for selection and prioritization of remedial measures. Reclamation of the waste rock piles is by covering in situ, relocation to a central pile or backfilling into an open pit. The backfilling of the open pit at Ronneburg with acid generating waste rock has been optimized from a geochemical point of view. For tailings ponds reclamation in form of dry landforms is being followed. To increase release (and reuse) of scrap metal from demolition, a fast and reliable method of discrimination of the non-contaminated metal has been developed. The flooding of

  2. Waste Acceptance System Requirements document (WASRD)

    International Nuclear Information System (INIS)

    1993-01-01

    This Waste Acceptance System Requirements document (WA-SRD) describes the functions to be performed and the technical requirements for a Waste Acceptance System for accepting spent nuclear fuel (SNF) and high-level radioactive waste (HLW) into the Civilian Radioactive Waste Management System (CRWMS). This revision of the WA-SRD addresses the requirements for the acceptance of HLW. This revision has been developed as a top priority document to permit DOE's Office of Environmental Restoration and Waste Management (EM) to commence waste qualification runs at the Savannah River Site's (SRS) Defense Waste Processing Facility (DWPF) in a timely manner. Additionally, this revision of the WA-SRD includes the requirements from the Physical System Requirements -- Accept Waste document for the acceptance of SNF. A subsequent revision will fully address requirements relative to the acceptance of SNF

  3. Process equipment waste and process waste liquid collection systems

    International Nuclear Information System (INIS)

    1990-06-01

    The US DOE has prepared an environmental assessment for construction related to the Process Equipment Waste (PEW) and Process Waste Liquid (PWL) Collection System Tasks at the Idaho Chemical Processing Plant. This report describes and evaluates the environmental impacts of the proposed action (and alternatives). The purpose of the proposed action would be to ensure that the PEW and PWL collection systems, a series of enclosed process hazardous waste, and radioactive waste lines and associated equipment, would be brought into compliance with applicable State and Federal hazardous waste regulations. This would be accomplished primarily by rerouting the lines to stay within the buildings where the lined floors of the cells and corridors would provide secondary containment. Leak detection would be provided via instrumented collection sumps locate din the cells and corridors. Hazardous waste transfer lines that are routed outside buildings will be constructed using pipe-in-pipe techniques with leak detection instrumentation in the interstitial area. The need for the proposed action was identified when a DOE-sponsored Resource Conservation and Recovery Act (RCRA) compliance assessment of the ICPP facilities found that singly-contained waste lines ran buried in the soil under some of the original facilities. These lines carried wastes with a pH of less than 2.0, which were hazardous waste according to the RCRA standards. 20 refs., 7 figs., 1 tab

  4. Modularized system for disposal of low-level radioactive waste

    International Nuclear Information System (INIS)

    Mallory, C.W.; DiSibio, R.

    1985-01-01

    A modularized system for the disposal of low-level radioactive waste is presented that attempts to overcome the past problems with shallow land burial and gain public acceptance. All waste received at the disposal site is packaged into reinforced concrete modules which are filled with grout, covered and sealed. The hexagonal shape modules are placed in a closely packed array in a disposal unit. The structural stability provided by the modules allow a protective cover constructed of natural materials to be installed, and the disposal units are decommissioned as they are filled. The modules are designed to be recoverable in the event remedial action is necessary. The cost of disposal with a facility of this type is comparable to current prices of shallow land burial facilities. The system is intended to address the needs of generators, regulators, communities, elected officials, licensees and future generations

  5. Headquarters Air Force Logistics Command guidance manual for hazardous waste minimization (PACER REDUCE): Hazardous Waste Remedial Actions Program

    International Nuclear Information System (INIS)

    Jones, L.W.; Weeter, D.; Roth, J.A.; Debelak, K.A.; Bowers, A.R.

    1988-09-01

    This manual provides guidance for the Air Force Logistics Command (AFLC) Waste Minimization Program, called PACER REDUCE, and applies to all AFLC installations and personel who are responsible for implementing and monitoring activities relating to PACER REDUCE. This guidance for waste minimization provides management and technical approaches for assessing potential waste reduction techniques and for making informed decisions concerning industrial process and waste stream management. Such actions will assist in achieving regulatory compliance with the Resource Conservation and Recovery Act of 1976 as updated by the Hazardous and Solid Waste Amendments of 1984. 37 refs., 14 figs., 22 tabs

  6. The system for waste management

    International Nuclear Information System (INIS)

    Hennelly, E.J.

    1987-01-01

    The author views the system for the management of high level radioactive waste as having five major components science and technology, domestic politics, international programs, regulation and institutions, and the ever changing rules and public perceptions. A system failure will usually occur because of the failure to communicate and not because of inadequate scientific data or engineering skills. For effective communication to occur the participants need to understand each other. The author will focus on this issue as a major theme of this presentation

  7. Development of dry barriers for containment and remediation at waste sites

    International Nuclear Information System (INIS)

    Thomson, B.M.; Morris, C.E.; Ankeny, M.D.

    1994-01-01

    This paper describes a concept in which dry air is injected into an unsaturated formation to reduce the soil moisture content, referred to here as a dry (or sometimes tensiometric) barrier. The objective is to reduce the hydraulic conductivity of the unsaturated media to the point where liquid phase transport becomes negligible, thereby achieving containment. The concept could be applied in subsurface formations to provide containment from a leaking facility, or it could be incorporated into a cover design to provide redundancy for a capillary barrier. The air injection process could in principle be coupled with a vacuum extraction system to recover soil vapors, which would then provide a remediation process that would be appropriate if volatile organic compounds were present. Work to date has consisted of a combined theoretical, laboratory, and field research investigation. The objective of this research was to demonstrate the technical feasibility of the dry barrier concept by identifying the parameters which determine its effectiveness. Based on the results obtained for the experimental and theoretical studies, feasibility analyses were prepared for as a modification for a landfill cover design to prevent infiltration from atmospheric precipitation and for potential application of dry barriers to achieve subsurface containment and removal of volatile constituents. These analyses considered the technical as well as the economic aspects of the dry barrier concept

  8. Development of vitrified waste storage system

    International Nuclear Information System (INIS)

    Namiki, S.; Tani, Y.

    1993-01-01

    The authors have developed the radioactive waste vitrification technology and the vitrified waste storage technology. Regarding the vitrified waste storage system development, the authors have completed the design of two types of storage systems. One is a forced convection air cooling system, and the other is a natural convection air cooling system. They have carried out experiments and heat transfer analysis, seismic analysis, vitrified waste dropping and radiation shielding, etc. In this paper, the following three subjects, are discussed: the cooling air flow experiment, the wind effect experiment on the cooling air flow pattern, using a wind tunnel apparatus and the structural integrity evaluation on the dropping vitrified waste

  9. 1993 International conference on nuclear waste management and environmental remediation, Prague, Czech Republic, September 5--11, 1993

    International Nuclear Information System (INIS)

    Slate, S.C.; Allen, R.E.

    1993-12-01

    The purpose of the trip was to attend the 1993 International Conference on Nuclear Waste Management and Environmental Remediation. The principal objective of this conference was to facilitate a truly international exchange of information on the management of nuclear wastes as well as contaminated facilities and sites emanating from nuclear operations. The conference was sponsored by the American Society of Mechanical Engineers, the Czech and Slovak Mechanical Engineering Societies, and the Czech and Slovak Nuclear Societies in cooperation with the Commission of the European Communities, the International Atomic Energy Agency, and the OECD Nuclear Agency. The conference was cosponsored by the American Nuclear Society, the Atomic Energy Society of Japan, the Canadian Nuclear Society, the (former USSR) Nuclear Society, and the Japan Society of Mechanical Engineers. This was the fourth in a series of biennial conferences, which started in Hong Kong, in 1987. This report summarizes shared aspects of the trip; however, each traveler's observations and recommendations are reported separately

  10. Waste management plan for the remedial investigation of Waste Area Grouping 2 at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    Baron, L.A.

    1994-10-01

    This Project Waste Management Plan defines the criteria and methods to be used for managing waste generated during activities associated with Waste Area Grouping 2 at Oak Ridge National Laboratory. The waste management strategy is based on the generation and management of waste on a systematic basis using the most appropriate combination of waste reduction, segregation, treatment, storage, and disposal practices while protecting the environment and human health, maintaining as low as reasonably achievable limits. This plan contains provisions for safely and effectively managing soils and sediments, sampling water, decontamination fluids, and disposable personal protective equipment consistent with the US Environmental Protection Agency guidance. This plan will be used in conjunction with the ORNL ER Program Waste Management Plan

  11. The regulatory environment for drilling and oilfield waste disposal and remediation in Alberta

    International Nuclear Information System (INIS)

    MacLachlan, L.J.; Stimpson, S.

    1999-01-01

    The legislative basis of regulation of all aspects of oilfield waste, including all oil and gas, oil sands, and oilfield waste management facility operations in Alberta is discussed. The appropriate waste management practices for the upstream petroleum industry and all waste stream associated with the petroleum industry are outlined. Major topics discussed include: (1) the roles and the jurisdictions of the Alberta Energy and Utilities Board (EUB) and Alberta Environmental Protection (AEP), (2) drilling waste and oilfield waste disposal, EUB guides 50 and 58, (3) wellsite abandonment and reclamation of wellsites, (4) spills and contaminated sites, (5) environmental offences, enforcement, penalties and defences

  12. Impacts of landscape remediation on the heavy metal pollution dynamics of a lake surrounded by non-ferrous smelter waste

    International Nuclear Information System (INIS)

    Blake, William H.; Walsh, Rory P.D.; Reed, Jane M.; Barnsley, Michael J.; Smith, Jamie

    2007-01-01

    Heavy metal concentrations and potential bioavailability are reported for sediment in a shallow flood detention lake surrounded by reclaimed, smelter-contaminated land. A range of sediment column proxy indicators is used to explore changes in pollution dynamics with remediation. Sediment concentrations of Pb and Zn are high at ∼600 and 20 000 mg kg -1 , respectively. Less than 7% of total Pb is potentially bioavailable following sequential extraction as opposed to 47% of Zn. Metal transfer mechanisms to lake sediment include detrital inputs, scavenging by particulates and biogeochemical precipitation. Sedimentary evidence indicates that detrital inputs to the lake declined following land reclamation after which it is proposed that dissolved inputs increased with leaching of reworked waste material. Whilst downcore metal profiles may be subject to post-depositional change, diatom analysis suggests more recent improvements in water quality. The potential for post-remediation pollution episodes relating to metal release from historic sedimentary stores should be considered in future remediation strategies. - The contaminant hydrology of reworked smelter spoil is complex

  13. Impacts of landscape remediation on the heavy metal pollution dynamics of a lake surrounded by non-ferrous smelter waste

    Energy Technology Data Exchange (ETDEWEB)

    Blake, William H. [Department of Geography, University of Wales, Swansea SA2 8PP (United Kingdom)]. E-mail: william.blake@plymouth.ac.uk; Walsh, Rory P.D. [Department of Geography, University of Wales, Swansea SA2 8PP (United Kingdom); Reed, Jane M. [Department of Geography, University of Hull, Cottingham Road, Hull HU6 7RX (United Kingdom); Barnsley, Michael J. [Department of Geography, University of Wales, Swansea SA2 8PP (United Kingdom); Smith, Jamie [Department of Geography, University of Wales, Swansea SA2 8PP (United Kingdom)

    2007-07-15

    Heavy metal concentrations and potential bioavailability are reported for sediment in a shallow flood detention lake surrounded by reclaimed, smelter-contaminated land. A range of sediment column proxy indicators is used to explore changes in pollution dynamics with remediation. Sediment concentrations of Pb and Zn are high at {approx}600 and 20 000 mg kg{sup -1}, respectively. Less than 7% of total Pb is potentially bioavailable following sequential extraction as opposed to 47% of Zn. Metal transfer mechanisms to lake sediment include detrital inputs, scavenging by particulates and biogeochemical precipitation. Sedimentary evidence indicates that detrital inputs to the lake declined following land reclamation after which it is proposed that dissolved inputs increased with leaching of reworked waste material. Whilst downcore metal profiles may be subject to post-depositional change, diatom analysis suggests more recent improvements in water quality. The potential for post-remediation pollution episodes relating to metal release from historic sedimentary stores should be considered in future remediation strategies. - The contaminant hydrology of reworked smelter spoil is complex.

  14. Waste Feed Delivery System Phase 1 Preliminary RAM Analysis

    International Nuclear Information System (INIS)

    DYKES, A.A.

    2000-01-01

    This report presents the updated results of the preliminary reliability, availability, and maintainability (RAM) analysis of selected waste feed delivery (WFD) operations to be performed by the Tank Farm Contractor (TFC) during Phase I activities in support of the Waste Treatment and Immobilization Plant (WTP). For planning purposes, waste feed tanks are being divided into five classes in accordance with the type of waste in each tank and the activities required to retrieve, qualify, and transfer waste feed. This report reflects the baseline design and operating concept, as of the beginning of Fiscal Year 2000, for the delivery of feed from three of these classes, represented by source tanks 241-AN-102, 241-AZ-101 and 241-AN-105. The preliminary RAM analysis quantifies the potential schedule delay associated with operations and maintenance (OBM) field activities needed to accomplish these operations. The RAM analysis is preliminary because the system design, process definition, and activity planning are in a state of evolution. The results are being used to support the continuing development of an O and M Concept tailored to the unique requirements of the WFD Program, which is being documented in various volumes of the Waste Feed Delivery Technical Basis (Carlson. 1999, Rasmussen 1999, and Orme 2000). The waste feed provided to the WTP must: (1) meet limits for chemical and radioactive constituents based on pre-established compositional envelopes (i.e., feed quality); (2) be in acceptable quantities within a prescribed sequence to meet feed quantities; and (3) meet schedule requirements (i.e., feed timing). In the absence of new criteria related to acceptable schedule performance due to the termination of the TWRS Privatization Contract, the original criteria from the Tank Waste Remediation System (77443s) Privatization Contract (DOE 1998) will continue to be used for this analysis

  15. Responsiveness summary for the remedial investigation/feasibility study for management of the bulk wastes at the Weldon Spring quarry, Weldon Spring, Missouri

    International Nuclear Information System (INIS)

    Peterson, J.M.; MacDonell, M.M.

    1990-08-01

    The US Department of Energy (DOE) is responsible for conducting remedial actions at the Weldon Spring site in St. Charles County, Missouri, under its Surplus Facilities Management Program. The site consists of a quarry and a chemical plant area located about 6.4 km (4 mi) northeast of the quarry. The quarry is surrounded by the Weldon Spring Wildfire Area and is near an alluvial well field that constitutes a major source of potable water for St. Charles County; the nearest supply well is located about 0.8 km (0.5 mi) southeast of the quarry. From 1942 to 1969, the quarry was used for the disposal of various radioactively and chemically contaminated materials. Bulk wastes in the quarry consist of contaminated soils and sediments, rubble, metal debris, and equipment. As part of overall site remediation, DOE is proposing to conduct an interim remedial action at the quarry to manage the radioactively and chemically contaminated bulk wastes contained therein. Potential remedial action alternatives for managing the quarry bulk wastes have been evaluated consistent with US Environmental Protection Agency (EPA) guidance for conducting remedial actions under the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), as amended. The contents of these documents were developed in consultation with EPA Region VII and the state of Missouri and reflect the focused scope defined for this interim remedial action. 9 refs

  16. Liquid waste treatment system. Final report

    International Nuclear Information System (INIS)

    Baker, M.N.; Houston, H.M.

    1999-01-01

    Pretreatment of high-level liquid radioactive waste (HLW) at the West Valley Demonstration Project (WVDP) involved three distinct processing operations: decontamination of liquid HLW in the Supernatant Treatment System (STS); volume reduction of decontaminated liquid in the Liquid Waste Treatment System (LWTS); and encapsulation of resulting concentrates into an approved cement waste form in the Cement Solidification System (CSS). Together, these systems and operations made up the Integrated Radwaste Treatment System (IRTS)

  17. Innovative technology summary report: System for Tracking Remediation, Exposure, Activities and Materials

    International Nuclear Information System (INIS)

    1998-09-01

    The System for Tracking Remediation, Exposure, Activities, and Materials (STREAM) technology is a multi-media database that consolidates project information into a single, easily-accessible place for day-to-day work performance and management tracking. Information inputs can range from procedures, reports, and references to waste generation logs and manifests to photographs and contaminant survey maps. Key features of the system are quick and easy information organization and retrieval, versatile information display options, and a variety of visual imaging methods. These elements enhance productivity and compliance and facilitate communications with project staff, clients, and regulators. Use of STREAM also gives visual access to contaminated areas, reducing the number of physical entries and promoting safety and as low as reasonably achievable (ALARA) principles. The STREAM system can be customized to focus on the information needs of a specific project, and provides a capability and work process improvement well beyond the usual collection of paperwork and independent databases. Especially when incorporated early in project planning and implemented to the fullest extent, it is a systematic and cost-effective tool for controlling and using project information. The STREAM system can support up to 50 different work stations. This report covers the period February through October 1997, when the STREAM software program, owned by Delphinus Engineering, was demonstrated at the Hanford Site's Reactor Interim Safe Storage (ISS) Project

  18. Waste Management System Requirement document

    International Nuclear Information System (INIS)

    1990-04-01

    This volume defines the top level technical requirements for the Monitored Retrievable Storage (MRS) facility. It is designed to be used in conjunction with Volume 1, General System Requirements. Volume 3 provides a functional description expanding the requirements allocated to the MRS facility in Volume 1 and, when appropriate, elaborates on requirements by providing associated performance criteria. Volumes 1 and 3 together convey a minimum set of requirements that must be satisfied by the final MRS facility design without unduly constraining individual design efforts. The requirements are derived from the Nuclear Waste Policy Act of 1982 (NWPA), the Nuclear Waste Policy Amendments Act of 1987 (NWPAA), the Environmental Protection Agency's (EPA) Environmental Standards for the Management and Disposal of Spent Nuclear Fuel (40 CFR 191), NRC Licensing Requirements for the Independent Storage of Spent Nuclear and High-Level Radioactive Waste (10 CFR 72), and other federal statutory and regulatory requirements, and major program policy decisions. This document sets forth specific requirements that will be fulfilled. Each subsequent level of the technical document hierarchy will be significantly more detailed and provide further guidance and definition as to how each of these requirements will be implemented in the design. Requirements appearing in Volume 3 are traceable into the MRS Design Requirements Document. Section 2 of this volume provides a functional breakdown for the MRS facility. 1 tab

  19. Remedial investigation plan for Waste Area Grouping 1 at Oak Ridge National Laboratory, Oak Ridge, Tennessee: Responses to regulator comments

    International Nuclear Information System (INIS)

    1991-05-01

    This document, ES/ER-6 ampersand D2, is a companion document to ORNL/RAP/Sub-87/99053/4 ampersand R1, Remedial Investigation Plan for ORNL Waste Area Grouping 1, dated August 1989. This document lists comments received from the Environmental Protection Agency, Region 4 (EPA) and the Tennessee Department of Health and Environment (TDHE) and responses to each of these comments. As requested by EPA, a revised Remedial Investigation (RI) Plan for Waste Area Grouping (WAG) 1 will not be submitted. The document is divided into two Sections and Appendix. Section I contains responses to comments issued on May 22, 1990, by EPA's Region 4 program office responsible for implementing the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA). Section 2 contains responses to comments issued on April 7, 1989, by EPA's program office responsible for implementing the Resource Conservation and Recovery Act (RCRA); these comments include issues raised by the TDHE. The Appendix contains the attachments referenced in a number of the responses. 35 refs

  20. Chemical and microbial remediation of hexavalent chromium from contaminated soil and mining/metallurgical solid waste: a review.

    Science.gov (United States)

    Dhal, B; Thatoi, H N; Das, N N; Pandey, B D

    2013-04-15

    Chromium is a highly toxic non-essential metal for microorganisms and plants, and its occurrence is rare in nature. Lower to higher chromium containing effluents and solid wastes released by activities such as mining, metal plating, wood preservation, ink manufacture, dyes, pigments, glass and ceramics, tanning and textile industries, and corrosion inhibitors in cooling water, induce pollution and may cause major health hazards. Besides, natural processes (weathering and biochemical) also contribute to the mobility of chromium which enters in to the soil affecting the plant growth and metabolic functions of the living species. Generally, chemical processes are used for Cr- remediation. However, with the inference derived from the diverse Cr-resistance mechanism displayed by microorganisms and the plants including biosorption, diminished accumulation, precipitation, reduction of Cr(VI) to Cr(III), and chromate efflux, bioremediation is emerging as a potential tool to address the problem of Cr(VI) pollution. This review focuses on the chemistry of chromium, its use, and toxicity and mobility in soil, while assessing its concentration in effluents/wastes which becomes the source of pollution. In order to conserve the environment and resources, the chemical/biological remediation processes for Cr(VI) and their efficiency have been summarised in some detail. The interaction of chromium with various microbial/bacterial strains isolated and their reduction capacity towards Cr(VI) are also discussed. Copyright © 2013 Elsevier B.V. All rights reserved.

  1. Initial Remedial Action Plan for Expanded Bioventing System BX Service Station, Patrick Air Force Base, Florida

    National Research Council Canada - National Science Library

    1995-01-01

    This initial remedial action plan presents the scope for an expanded bioventing system for in situ treatment of fuel-contaminated soils at the BX Service Station at Patrick Air Force Base (AFB), Florida...

  2. Remedial Action Plan for Expanded Bioventing System Buildings 2034/2035, Fairchild Air Force Base, Washington

    National Research Council Canada - National Science Library

    1996-01-01

    This remedial action plan (RAP) presents the scope for an expanded bioventing system for in situ treatment of fuel-contaminated soils in the vicinity of Buildings 2034 and 2035 at Fairchild Air Force Base (AFB), Washington...

  3. Proceedings of the Department of Energy Defense Programs hazardous and mixed waste minimization workshop: Hazardous Waste Remedial Actions Program

    International Nuclear Information System (INIS)

    1988-09-01

    The first workshop on hazardous and mixed waste minimization was held in Las Vegas, Nevada, on July 26--28, 1988. The objective of this workshop was to establish an interchange between DOE headquarters (DOE-HQ) DP, Operations Offices, and contractors of waste minimization strategies and successes. The first day of the workshop began with presentations stressing the importance of establishing a waste minimization program at each site as required by RCRA, the land ban restrictions, and the decrease in potential liabilities associated with waste disposal. Discussions were also centered on pending legislation which would create an Office of Waste Reduction in the Environmental Protection Agency (EPA). The Waste Minimization and Avoidance Study was initiated by DOE as an addition to the long-term productivity study to address the issues of evolving requirements facing RCRA waste management activities at the DP sites, to determine how major operations will be affected by these requirements, and to determine the available strategies and options for waste minimization and avoidance. Waste minimization was defined in this study as source reduction and recycling

  4. Tank waste remediation system heat stress control program report, 1995

    International Nuclear Information System (INIS)

    Carls, D.R.

    1995-01-01

    Protecting employees from heat stress within tank farms during the summer months is challenging. Work constraints typically experienced in tank farms complicate the measures taken to protect employees from heat stress. TWRS-Industrial Hygiene (IH) has endeavored to control heat stress injuries by anticipating, recognizing, evaluating and controlling the factors which lead or contribute to heat stress in Tank Farms. The TWRS Heat Stress Control Program covers such areas as: employee and PIC training, communication of daily heat stress alerts to tank farm personnel, setting work/rest regimens, and the use of engineering and personal protective controls when applicable. The program has increased worker awareness of heat stress and prevention, established provisions for worker rest periods, increased drinking water availability to help ensure worker hydration, and allowed for the increased use of other protective controls to combat heat stress. The TWRS Heat Stress Control Program is the cornerstone for controlling heat stress among tank farm employees. The program has made great strides since it's inception during the summer of 1994. Some improvements can still be made to enhance the program for the summer of 1996, such as: (1) procurement and use of personal heat stress monitoring equipment to ensure appropriate application of administrative controls, (2) decrease the need for use of containment tents and anti-contamination clothing, and (3) providing a wider variety of engineering and personal protective controls for heat stress prevention

  5. Waste Management Information System (WMIS) User Guide

    International Nuclear Information System (INIS)

    Broz, R.E.

    2008-01-01

    This document provides the user of the Waste Management Information System (WMIS) instructions on how to use the WMIS software. WMIS allows users to initiate, track, and close waste packages. The modular design supports integration and utilization of data through the various stages of waste management. The phases of the waste management work process include generation, designation, packaging, container management, procurement, storage, treatment, transportation, and disposal

  6. Waste Management Information System (WMIS) User Guide

    Energy Technology Data Exchange (ETDEWEB)

    R. E. Broz

    2008-12-22

    This document provides the user of the Waste Management Information System (WMIS) instructions on how to use the WMIS software. WMIS allows users to initiate, track, and close waste packages. The modular design supports integration and utilization of data throuh the various stages of waste management. The phases of the waste management work process include generation, designation, packaging, container management, procurement, storage, treatment, transportation, and disposal.

  7. Development of tensiometric barriers for containment and remediation at waste sites

    International Nuclear Information System (INIS)

    Thomson, B.M.; Stormont, J.C.; Morris, C.E.

    1996-01-01

    This report describes a concept in which dry air is injected into an unsaturated formation to reduce the soil moisture content, referred to here as a tensiometric (or sometimes dry) barrier. The objective is to reduce the hydraulic conductivity of the unsaturated media to the point where liquid phase transport becomes negligible, thereby achieving containment. The concept could be applied in subsurface formations to provide containment from a leaking facility, or it could be incorporated into a cover design to provide redundancy for a capillary barrier. The air injection process could in principle be coupled with a vacuum extraction system to recover soil vapors, which would then provide a remediation process that would be appropriate if volatile organic compounds were present. Work to date has consisted of a combined theoretical, laboratory, and field research investigation. The objective of this research was to demonstrate the technical feasibility of the tensiometric barrier concept by identifying the parameters which determine its effectiveness. Based on the results obtained for the experimental and theoretical studies, feasibility analyses were prepared as a modification for a landfill cover design to prevent infiltration from atmospheric precipitation and for potential application of tensiometric barriers to achieve subsurface containment of mobile pollutants and removal of volatile constituents. These analyses considered the technical as well as the economic aspects of the tensiometric barrier concept, and found that a properly designed and operated tensiometric barrier is competitive with conventional containment methods. In addition, they benefit from being able to recover from failure by circulating additional dry air through the formation to re-establish the barrier phenomena. (author) 10 figs., 4 tabs., 17 refs

  8. Synchrotron-based X-Ray Spectroscopy Studies for Redox-based Remediation of Lead, Zinc, and Cadmium in Mine Waste Materials.

    Science.gov (United States)

    Karna, Ranju R; Hettiarachchi, Ganga M; Newville, Matthew; Sun, ChengJun; Ma, Qing

    2016-11-01

    Several studies have examined the effect of submergence on the mobility of metals present in mine waste materials. This study examines the effect of organic carbon (OC) and sulfur (S) additions and submergence time on redox-induced biogeochemical transformations of lead (Pb), zinc (Zn), and cadmium (Cd) present in mine waste materials collected from the Tri-State mining district located in southeastern Kansas, southwestern Missouri, and northeastern Oklahoma. A completely randomized design, with a two-way treatment structure, was used for conducting a series of column experiments. Two replicates were used for each treatment combination. Effluent samples were collected at several time points, and soil samples were collected at the end of each column experiment. Because these samples are highly heterogeneous, we used a variety of synchrotron-based techniques to identify Pb, Zn, and Cd speciation at both micro- and bulk-scale. Spectroscopic analysis results from the study revealed that the addition of OC, with and without S, promoted metal-sulfide formation, whereas metal carbonates dominated in the nonamended flooded materials and in mine waste materials only amended with S. Therefore, the synergistic effect of OC and S may be more promising for managing mine waste materials disposed of in flooded subsidence mine pits instead of individual S or OC treatments. The mechanistic understanding gained in this study is also relevant for remediation of waste materials using natural or constructed wetland systems. Copyright © by the American Society of Agronomy, Crop Science Society of America, and Soil Science Society of America, Inc.

  9. Mobile waste inspection real time radiography system

    International Nuclear Information System (INIS)

    Vigil, J.; Taggart, D.; Betts, S.; Rael, C.; Martinez, F.; Mendez, J.

    1995-01-01

    The 450-KeV Mobile Real Time Radiography System was designed and purchased to inspect containers of radioactive waste produced at Los Alamos National Laboratory (LANL). The Mobile Real Time Radiography System has the capability of inspecting waste containers of various sizes from 5-gal. buckets to standard waste boxes (SWB, dimensions 54.5 in. x 71 in. x 37 in.). The fact that this unit is mobile makes it an attractive alternative to the costly road closures associated with moving waste from the waste generator to storage or disposal facilities

  10. Fall Protection Procedures for Sealing Bulk Waste Shipments by Rail Cars at Formerly Utilized Sites Remedial Action Program (FUSRAP) Sites - 13509

    Energy Technology Data Exchange (ETDEWEB)

    Boyle, J.D. [U.S. Army Corps of Engineers - Buffalo District, Buffalo, New York 14207 (United States); Fort, E. Joseph; Lorenz, William [Cabrera Services (Cabrera) East Harford, CT 06108 (United States); Mills, Andy [Shaw Environmental and Infrastructure, Inc. (Shaw) Baton Rouge, LA 70809 (United States)

    2013-07-01

    Rail-cars loaded with radioactive materials must be closed and fastened to comply with United States Department of Transportation (DOT) requirements before they shipped. Securing waste shipments in a manner that meets these regulations typically results in the use of a sealable rail-car liner. Workers accessing the tops of the 2.74 m high rail-cars to seal and inspect liners for compliance prior to shipment may be exposed to a fall hazard. Relatively recent revisions to the Fall Protection requirements in the Safety and Health Requirements Manual (EM385-1-1, U.S. Army Corps of Engineers) have necessitated modifications to the fall protection systems previously employed for rail-car loading at Formerly Utilized Sites Remedial Action Program (FUSRAP) sites. In response these projects have developed site-specific procedures to protect workers and maintain compliance with the improved fall protection regulations. (authors)

  11. Remediation of a radioactively contaminated soil using a mobile soil-washing system

    International Nuclear Information System (INIS)

    Grant, D.C.; Lahoda, E.J.; Dietrich, A.J.; Weigle, D.H.; Keegan, C.P.; Sachse, J.D.

    1993-01-01

    In order to obtain free-release of a former uranium mining site in Texas, it was required that the surface soil meet specific radiological guidelines. The soil has been contaminated with uranium and radium as a result of the spillage of well-drilling material, process solutions, and ion exchange resins during mining. To meet the required guidelines, the contaminated soil had to be either removed and disposed of off-site or remediated. For economic and long-term liability reasons, remediation of the soil by soil washing was performed. The remediation of this site utilizing the Scientific Ecology Group's soil washing system is discussed in this paper

  12. Field sampling and analysis plan for the remedial investigation of Waste Area Grouping 2 at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    Boston, H.L.; Ashwood, T.L.; Borders, D.M.; Chidambariah, V.; Downing, D.J.; Fontaine, T.A.; Ketelle, R.H.; Lee, S.Y.; Miller, D.E.; Moore, G.K.; Suter, G.W.; Tardiff, M.F.; Watts, J.A.; Wickliff, D.S.

    1992-02-01

    This field sampling and analysis (S ampersand A) plan has been developed as part of the Department of Energy's (DOE's) remedial investigation (RI) of Waste Area Grouping (WAG) 2 at Oak Ridge National Laboratory (ORNL) located in Oak Ridge, Tennessee. The S ampersand A plan has been written in support of the remedial investigation (RI) plan for WAG 2 (ORNL 1990). WAG 2 consists of White Oak Creek (WOC) and its tributaries downstream of the ORNL main plant area, White Oak Lake (WOL), White Oak Creek embayment (WOCE) on the Clinch River, and the associated floodplain and subsurface environment (Fig. 1.1). The WOC system is the surface drainage for the major ORNL WAGs and has been exposed to a diversity of contaminants from operations and waste disposal activities in the WOC watershed. WAG 2 acts as a conduit through which hydrologic fluxes carry contaminants from upgradient areas to the Clinch River. Water, sediment, soil, and biota in WAG 2 are contaminated and continue to receive contaminants from upgradient WAGs. This document describes the following: an overview of the RI plan, background information for the WAG 2 system, and objectives of the S ampersand A plan; the scope and implementation of the first 2 years of effort of the S ampersand A plan and includes recent information about contaminants of concern, organization of S ampersand A activities, interactions with other programs, and quality assurance specific to the S ampersand A activities; provides details of the field sampling plans for sediment, surface water, groundwater, and biota, respectively; and describes the sample tracking and records management plan

  13. Field sampling and analysis plan for the remedial investigation of Waste Area Grouping 2 at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Environmental Restoration Program

    Energy Technology Data Exchange (ETDEWEB)

    Boston, H.L.; Ashwood, T.L.; Borders, D.M.; Chidambariah, V.; Downing, D.J.; Fontaine, T.A.; Ketelle, R.H.; Lee, S.Y.; Miller, D.E.; Moore, G.K.; Suter, G.W.; Tardiff, M.F.; Watts, J.A.; Wickliff, D.S.

    1992-02-01

    This field sampling and analysis (S & A) plan has been developed as part of the Department of Energy`s (DOE`s) remedial investigation (RI) of Waste Area Grouping (WAG) 2 at Oak Ridge National Laboratory (ORNL) located in Oak Ridge, Tennessee. The S & A plan has been written in support of the remedial investigation (RI) plan for WAG 2 (ORNL 1990). WAG 2 consists of White Oak Creek (WOC) and its tributaries downstream of the ORNL main plant area, White Oak Lake (WOL), White Oak Creek embayment (WOCE) on the Clinch River, and the associated floodplain and subsurface environment (Fig. 1.1). The WOC system is the surface drainage for the major ORNL WAGs and has been exposed to a diversity of contaminants from operations and waste disposal activities in the WOC watershed. WAG 2 acts as a conduit through which hydrologic fluxes carry contaminants from upgradient areas to the Clinch River. Water, sediment, soil, and biota in WAG 2 are contaminated and continue to receive contaminants from upgradient WAGs. This document describes the following: an overview of the RI plan, background information for the WAG 2 system, and objectives of the S & A plan; the scope and implementation of the first 2 years of effort of the S & A plan and includes recent information about contaminants of concern, organization of S & A activities, interactions with other programs, and quality assurance specific to the S & A activities; provides details of the field sampling plans for sediment, surface water, groundwater, and biota, respectively; and describes the sample tracking and records management plan.

  14. WASTES: Waste System Transportation and Economic Simulation--Version 2:

    International Nuclear Information System (INIS)

    Sovers, R.A.; Shay, M.R.; Ouderkirk, S.J.; McNair, G.W.; Eagle, B.G.

    1988-02-01

    The Waste System Transportation and Economic Simulation (WASTES) Technical Reference Manual was written to describe and document the algorithms used within the WASTES model as implemented in Version 2.23. The manual will serve as a reference for users of the WASTES system. The intended audience for this manual are knowledgeable users of WASTES who have an interest in the underlying principles and algorithms used within the WASTES model. Each algorithm is described in nonprogrammers terminology, and the source and uncertainties of the constants in use by these algorithms are described. The manual also describes the general philosophy and rules used to: 1) determine the allocation and priority of spent fuel generation sources to facility destinations, 2) calculate transportation costs, and 3) estimate the cost of at-reactor ex-pool storage. A detailed description of the implementation of many of the algorithms is also included in the WASTES Programmers Reference Manual (Shay and Buxbaum 1986a). This manual is separated into sections based on the general usage of the algorithms being discussed. 8 refs., 14 figs., 2 tabs

  15. Prioritization Risk Integration Simulation Model (PRISM) For Environmental Remediation and Waste Management - 12097

    Energy Technology Data Exchange (ETDEWEB)

    Pentz, David L.; Stoll, Ralph H.; Greeves, John T. [Predicus LLC, Issaquah, WA 98027 (United States); Miller, R. Ian [GoldSim Technology Group, LLC, Issaquah, WA 98027 (United States); Nutt, W. Mark [Argonne National Laboratory, Argonne, IL 60439 (United States)

    2012-07-01

    that is widely used for risk and performance assessment calculations. PRISM can be run in a deterministic mode, which quickly provides an estimate of the most likely results of a given plan. Alternatively, the model can be run probabilistically in a Monte Carlo mode, exploring the risks and uncertainties in the system and producing probability distributions for the different performance measures. The PRISM model demonstrates how EM can evaluate a portfolio of ELOs, and transform the ELOs from their current conditions to acceptable conditions, utilizing different strategic approaches. There are many types of ELOs - contaminated soils and groundwater plumes, disused facilities awaiting D and D, and various types of wastes waiting for processing or disposal. This scope of work for the PRISM process and the development of a dynamic simulation model are a logical extension of the GoldSim simulation software used by the OCRWM to assess the long-term performance for the Yucca Mountain Project and by NNSA to assess project risk at its sites. Systems integration modeling will promote better understanding of all project risks, technical and nontechnical, and more defensible decision-making for complex projects with significant uncertainties. It can provide effective visual communication and rapid adaptation during interactions with stakeholders (Administration, Congress, State, Local, and NGO). It will also allow rapid assessment of alternative management approaches. (authors)

  16. Assessing waste management systems using reginalt software

    International Nuclear Information System (INIS)

    Meshkov, N.K.; Camasta, S.F.; Gilbert, T.L.

    1988-03-01

    A method for assessing management systems for low-level radioactive waste is being developed for US Department of Energy. The method is based on benefit-cost-risk analysis. Waste management is broken down into its component steps, which are generation, treatment, packaging, storage, transportation, and disposal. Several different alternatives available for each waste management step are described. A particular waste management system consists of a feasible combination of alternatives for each step. Selecting an optimal waste management system would generally proceed as follows: (1) qualitative considerations are used to narrow down the choice of waste management system alternatives to a manageable number; (2) the costs and risks for each of these system alternatives are evaluated; (3) the number of alternatives is further reduced by eliminating alternatives with similar risks but higher costs, or those with similar costs but higher risks; (4) a trade-off factor between cost and risk is chosen and used to compute the objective function (sum of the cost and risk); and (5) the selection of the optimal waste management system among the remaining alternatives is made by choosing the alternative with the smallest value for the objective function. The authors propose that the REGINALT software system, developed by EG and G Idaho, Inc., as an acid for managers of low-level commerical waste, be augmented for application to the managment of DOE-generated waste. Specific recommendations for modification of the REGINALT system are made. 51 refs., 3 figs., 2 tabs

  17. Buried Waste Integrated Demonstration

    International Nuclear Information System (INIS)

    1994-03-01

    The Buried Waste Integrated Demonstration (BWID) supports the applied research, development, demonstration, and evaluation of a suite of advanced technologies that offer promising solutions to the problems associated with the remediation of buried waste. BWID addresses the difficult remediation problems associated with DOE complex-wide buried waste, particularly transuranic (TRU) contaminated buried waste. BWID has implemented a systems approach to the development and demonstration of technologies that will characterize, retrieve, treat, and dispose of DOE buried wastes. This approach encompasses the entire remediation process from characterization to post-monitoring. The development and demonstration of the technology is predicated on how a technology fits into the total remediation process. To address all of these technological issues, BWID has enlisted scientific expertise of individuals and groups from within the DOE Complex, as well as experts from universities and private industry. The BWID mission is to support development and demonstration of a suite of technologies that, when integrated with commercially-available technologies, forms a comprehensive, remediation system for the effective and efficient remediation of buried waste throughout the DOE Complex. BWID will evaluate and validate demonstrated technologies and transfer this information and equipment to private industry to support the Office of Environmental Restoration (ER), Office of Waste Management (WM), and Office of Facility Transition (FT) remediation planning and implementation activities

  18. Application of Fe-Cu/Biochar System for Chlorobenzene Remediation of Groundwater in Inhomogeneous Aquifers

    OpenAIRE

    Xu Zhang; Yanqing Wu; Pingping Zhao; Xin Shu; Qiong Zhou; Zichen Dong

    2017-01-01

    Chlorobenzene (CB), as a typical Volatile Organic Contaminants (VOC), is toxic, highly persistent and easily migrates in water, posing a significant risk to human health and subsurface ecosystems. Therefore, exploring effective approaches to remediate groundwater contaminated by CB is essential. As an enhanced micro-electrolysis system for CB-contaminated groundwater remediation, this study attempted to couple the iron-copper bimetal with biochar. Two series of columns using sands with differ...

  19. Green PCB Remediation from Sediment Systems (GPRSS) Project

    Science.gov (United States)

    Falker, John; Thompson, Karen; Zeitlin, Nancy; Quinn, Jacqueline; Parrish, Lewis M.

    2014-01-01

    An ongoing problem facing the global environment community including NASA centers is the removal and remediation of polychlorinated biphenyls (PCBs). PCBs were commonly used in a variety of materials including paints, caulking, and adhesives due to the advantageous physical and chemical properties that PCBs imparted to these various materials. Unfortunately, these properties have made the treatment of sites contaminated with these chemicals extremely difficult to deal with, due to their inherent chemical stability. The remediation of sediments contaminated with PCBs is especially difficult, primarily due to the risk of releasing the contaminant into the environment during the treatment process. Traditional treatment options involve the use of dredging and incineration of the contaminated soils/sediments, in which the chance of releasing the contaminants is greatly increased. The purpose of this project is to develop cleanup technology capable of remediating contaminated sediments in-situ, with minimum intrusion. This allows for the minimization of any potential contaminant release during the treatment process, providing a safer method for cleanup operations (as opposed to dredging/incineration) and still treating the basic problem of PCB contamination (as opposed to capping).

  20. Electrodialytic remediation of municipal solid waste incineration residues using different membranes

    DEFF Research Database (Denmark)

    Parés Viader, Raimon; Jensen, Pernille Erland; Ottosen, Lisbeth M.

    2017-01-01

    In the present work, three different commercial membrane brands were used in an identical electrodialytic cell setup and operating conditions, in order to reduce the leaching of metals and salt anions of two types of municipal solid waste incineration residues: air pollution control residues...... as a technology to upgrade municipal solid waste incineration residues....

  1. Assessment of residual DDE at four remediated Hanford waste sites, Richland, Washington

    International Nuclear Information System (INIS)

    Linville, J.K.

    1999-01-01

    The objectives of this study were to determine the extent and distribution of residual DDE, a metabolite of dichlorodiphenyltrichloroethane (DDT), across the four waste sites by sampling ground-dwelling insects and bird eggs, evaluating the use of insects for monitoring contamination pathways, and determining the species of passerine birds present and the number of nesting pairs utilizing the waste sites

  2. International waste management conference

    International Nuclear Information System (INIS)

    Anon.

    1989-01-01

    This book contains the proceedings of the international waste management conference. Topics covered include: Quality assurance in the OCR WM program; Leading the spirit of quality; Dept. of Energy hazardous waste remedial actions program; management of hazardous waste projects; and System management and quality assurance

  3. Remediation of radiocesium-contaminated liquid waste, soil, and ash: a mini review since the Fukushima Daiichi Nuclear Power Plant accident.

    Science.gov (United States)

    Ding, Dahu; Zhang, Zhenya; Lei, Zhongfang; Yang, Yingnan; Cai, Tianming

    2016-02-01

    The radiation contamination after the Fukushima Daiichi Nuclear Power Plant accident attracts considerable concern all over the world. Many countries, areas, and oceans are greatly affected by the emergency situation other than Japan. An effective remediation strategy is in a highly urgent demand. Though plenty of works have been carried out, progressive achievements have not yet been well summarized. Here, we review the recent advances on the remediation of radiocesium-contaminated liquid waste, soil, and ash. The overview of the radiation contamination is firstly given. Afterwards, the current remediation strategies are critically reviewed in terms of the environmental medium. Special attentions are paid on the adsorption/ion exchange and electrically switched ion exchange methods. Finally, the present review outlines the possible works to do for the large-scale application of the novel remediation strategies.

  4. Transportable Vitrification System Demonstration on Mixed Waste

    International Nuclear Information System (INIS)

    Zamecnik, J.R.; Whitehouse, J.C.; Wilson, C.N.; Van Ryn, F.R.

    1998-01-01

    This paper describes preliminary results from the first demonstration of the Transportable Vitrification System (TVS) on actual mixed waste. The TVS is a fully integrated, transportable system for the treatment of mixed and low-level radioactive wastes. The demonstration was conducted at Oak Ridge's East Tennessee Technology Park (ETTP), formerly known as the K-25 site. The purpose of the demonstration was to show that mixed wastes could be vitrified safely on a 'field' scale using joule-heated melter technology and obtain information on system performance, waste form durability, air emissions, and costs

  5. 1993 baseline solid waste management system description

    International Nuclear Information System (INIS)

    Armacost, L.L.; Fowler, R.A.; Konynenbelt, H.S.

    1994-02-01

    Pacific Northwest Laboratory has prepared this report under the direction of Westinghouse Hanford Company. The report provides an integrated description of the system planned for managing Hanford's solid low-level waste, low-level mixed waste, transuranic waste, and transuranic mixed waste. The primary purpose of this document is to illustrate a collective view of the key functions planned at the Hanford Site to handle existing waste inventories, as well as solid wastes that will be generated in the future. By viewing this system as a whole rather than as individual projects, key facility interactions and requirements are identified and a better understanding of the overall system may be gained. The system is described so as to form a basis for modeling the system at various levels of detail. Model results provide insight into issues such as facility capacity requirements, alternative system operating strategies, and impacts of system changes (ie., startup dates). This description of the planned Hanford solid waste processing system: defines a baseline system configuration; identifies the entering waste streams to be managed within the system; identifies basic system functions and waste flows; and highlights system constraints. This system description will evolve and be revised as issues are resolved, planning decisions are made, additional data are collected, and assumptions are tested and changed. Out of necessity, this document will also be revised and updated so that a documented system description, which reflects current system planning, is always available for use by engineers and managers. It does not provide any results generated from the many alternatives that will be modeled in the course of analyzing solid waste disposal options; such results will be provided in separate documents

  6. Potential future waste-to-energy systems

    OpenAIRE

    Thorin, Eva; Guziana, Bozena; Song, Han; Jääskeläinen, Ari; Szpadt, Ryszard; Vasilic, Dejan; Ahrens, Thorsten; Anne, Olga; Lõõnik, Jaan

    2012-01-01

    This report discusses potential future systems for waste-to-energy production in the Baltic Sea Region, and especially for the project REMOWE partner regions, the County of Västmanland in Sweden, Northern Savo in Finland, Lower Silesia in Poland, western part of Lithuania and Estonia. The waste-to-energy systems planned for in the partner regions are combustion of municipal solid waste (MSW) and solid recovered fuels from household and industry as well as anaerobic digestion of sewage sludge ...

  7. State of the Science Review: Potential for Beneficial Use of Waste By-Products for In-situ Remediation of Metal-Contaminated Soil and Sediment

    Science.gov (United States)

    Metal and metalloid contamination of soil and sediment is a widespread problem both in urban and rural areas throughout the United States (U.S. EPA, 2014). Beneficial use of waste by-products as amendments to remediate metal-contaminated soils and sediments can provide major eco...

  8. Summary Report of Comprehensive Laboratory Testing to Establish the Effectiveness of Proposed Treatment Methods for Unremediated and Remediated Nitrate Salt Waste Streams

    Energy Technology Data Exchange (ETDEWEB)

    Anast, Kurt Roy [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Funk, David John [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Hargis, Kenneth Marshall [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2017-10-04

    The inadvertent creation of transuranic waste carrying hazardous waste codes D001 and D002 requires the treatment of the material to eliminate the hazardous characteristics and allow its eventual shipment and disposal at the Waste Isolation Pilot Plant (WIPP). This report documents the effectiveness of two treatment methods proposed to stabilize both the unremediated and remediated nitrate salt waste streams (UNS and RNS, respectively) at Los Alamos National Laboratory (LANL). The two technologies include the addition of zeolite (with and without the addition of water as a processing aid) and cementation. Surrogates were developed to evaluate both the solid and liquid fractions expected from parent waste containers, and both the solid and liquid fractions were tested. Both technologies are shown to be effective at eliminating the characteristic of ignitability (D001), and the addition of zeolite was determined to be effective at eliminating corrosivity (D002), with the preferred option1 of adding zeolite currently planned for implementation at LANL’s Waste Characterization, Reduction, and Repackaging Facility (WCRRF). The course of this work verified the need to evaluate and demonstrate the effectiveness of the proposed remedy for debris material, if required. The evaluation determined that WypAlls, cheesecloth, and Celotex absorbed with saturated nitrate salt solutions exhibit the ignitability characteristic (all other expected debris is not classified as ignitable). Finally, liquid surrogates containing saturated nitrate salts did not exhibit the characteristic of ignitability in their pure form (those neutralized with Kolorsafe and mixed with sWheat did exhibit D001). Sensitivity testing and an analysis were conducted to evaluate the waste form for reactivity. Tests included subjecting surrogate material to mechanical impact, friction, electrostatic discharge and thermal insults. The testing confirmed that the waste does not exhibit the characteristic of

  9. Risk assessment and optimization (ALARA) analysis for the environmental remediation of Brookhaven National Laboratory's hazardous waste management facility

    International Nuclear Information System (INIS)

    Dionne, B.J.; Morris, S.C. III; Baum, J.W.

    1998-01-01

    The Department of Energy's (DOE) Office of Environment, Safety, and Health (EH) sought examples of risk-based approaches to environmental restoration to include in their guidance for DOE nuclear facilities. Extensive measurements of radiological contamination in soil and ground water have been made at Brookhaven National Laboratory's Hazardous Waste Management Facility (HWMF) as part of a Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) remediation process. This provided an ideal opportunity for a case study. This report provides a risk assessment and an open-quotes As Low as Reasonably Achievableclose quotes (ALARA) analysis for use at other DOE nuclear facilities as an example of a risk-based decision technique. This document contains the Appendices for the report

  10. Development of monitoring and diagnostic methods for robots used in remediation of waste sites. 1997 annual progress report

    International Nuclear Information System (INIS)

    Tecza, J.

    1998-01-01

    'Safe and efficient clean up of hazardous and radioactive waste sites throughout the DOE complex will require extensive use of robots. This research effort focuses on developing Monitoring and Diagnostic (M and D) methods for robots that will provide early detection, isolation, and tracking of impending faults before they result in serious failure. The utility and effectiveness of applying M and D methods to hydraulic robots has never been proven. The present research program is utilizing seeded faults in a laboratory test rig that is representative of an existing hydraulically-powered remediation robot. This report summarizes activity conducted in the first 9 months of the project. The research team has analyzed the Rosie Mobile Worksystem as a representative hydraulic robot, developed a test rig for implanted fault testing, developed a test plan and agenda, and established methods for acquiring and analyzing the test data.'

  11. Risk assessment and optimization (ALARA) analysis for the environmental remediation of Brookhaven National Laboratory`s hazardous waste management facility

    Energy Technology Data Exchange (ETDEWEB)

    Dionne, B.J.; Morris, S.C. III; Baum, J.W. [and others

    1998-01-01

    The Department of Energy`s (DOE) Office of Environment, Safety, and Health (EH) sought examples of risk-based approaches to environmental restoration to include in their guidance for DOE nuclear facilities. Extensive measurements of radiological contamination in soil and ground water have been made at Brookhaven National Laboratory`s Hazardous Waste Management Facility (HWMF) as part of a Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) remediation process. This provided an ideal opportunity for a case study. This report provides a risk assessment and an {open_quotes}As Low as Reasonably Achievable{close_quotes} (ALARA) analysis for use at other DOE nuclear facilities as an example of a risk-based decision technique. This document contains the Appendices for the report.

  12. Risk assessment and optimization (ALARA) analysis for the environmental remediation of Brookhaven National Laboratory`s hazardous waste management facility

    Energy Technology Data Exchange (ETDEWEB)

    Dionne, B.J.; Morris, S. III; Baum, J.W. [and others

    1998-03-01

    The Department of Energy`s (DOE) Office of Environment, Safety, and Health (EH) sought examples of risk-based approaches to environmental restoration to include in their guidance for DOE nuclear facilities. Extensive measurements of radiological contamination in soil and ground water have been made at Brookhaven National Laboratory`s Hazardous Waste Management Facility (HWMF) as part of a Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) remediation process. This provided an ideal opportunity for a case study. This report provides a risk assessment and an {open_quotes}As Low as Reasonably Achievable{close_quotes} (ALARA) analysis for use at other DOE nuclear facilities as an example of a risk-based decision technique.

  13. Remediation of lead from lead electroplating industrial effluent using sago waste.

    Science.gov (United States)

    Jeyanthi, G P; Shanthi, G

    2007-01-01

    Heavy metals are known toxicants, which inflict acute disorders to the living beings. Electroplating industries pose great threat to the environment through heavy load of metals in the wastewater discharged on land and water sources. In the present study, sago processing waste, which is both a waste and a pollutant, was used to adsorb lead ions from lead electroplating industrial effluent. Two types of sago wastes, namely, coarse sago waste and fine sago waste were used to study their adsorption capacity with the batch adsorption and Freundlich adsorption isotherm. The parameters that were considered for batch adsorption were pH (4, 5 and 6), time of contact (1, 2 and 3 hrs), temperature (30, 37 and 45 degrees C) and dosage of the adsorbent (2,4 and 6 g/L). The optimal condition for the effective removal of lead was found to be pH 5, time of contact 3 hrs, temperature 30 degrees C and dosage 4 g/L with coarse sago waste than fine sago waste.

  14. Biogeochemical dynamics of pollutants in Insitu groundwater remediation systems

    Science.gov (United States)

    Kumar, N.; Millot, R.; Rose, J.; Négrel, P.; Battaglia-Brunnet, F.; Diels, L.

    2010-12-01

    Insitu (bio) remediation of groundwater contaminants has been area of potential research interest in last few decades as the nature of contaminant encountered has also changed drastically. This gives tough challenge to researchers in finding a common solution for all contaminants together in one plume. Redox processes play significant role in pollutant dynamics and mobility in such systems. Arsenic particularly in reduced environments can get transformed into its reduced form (As3+), which is apparently more mobile and highly toxic. Also parallel sulfate reduction can lead to sulfide production and formation of thioarsenic species. On the other hand heavy metals (Zn, Fe, and Cd) in similar conditions will favour more stable metal sulfide precipitation. In the present work, we tested Zero Valent Iron (ZVI) in handling such issues and found promising results. Although it has been well known for contaminants like arsenic and chlorinated compounds but not much explored for heavy metals. Its high available surface area supports precipitation and co -precipitation of contaminants and its highly oxidizing nature and water born hydrogen production helps in stimulation of microbial activities in sediment and groundwater. These sulfate and Iron reducing bacteria can further fix heavy metals as stable metal sulfides by using hydrogen as potential electron donor. In the present study flow through columns (biotic and control) were set up in laboratory to understand the behaviour of contaminants in subsurface environments, also the impact of microbiology on performance of ZVI was studied. These glass columns (30 x 4cm) with intermediate sampling points were monitored over constant temperature (20°C) and continuous groundwater (up)flow at ~1ml/hr throughout the experiment. Simulated groundwater was prepared in laboratory containing sulfate, metals (Zn,Cd) and arsenic (AsV). While chemical and microbial parameters were followed regularly over time, solid phase has been

  15. Liquid low level waste management expert system

    International Nuclear Information System (INIS)

    Ferrada, J.J.; Abraham, T.J.; Jackson, J.R.

    1991-01-01

    An expert system has been developed as part of a new initiative for the Oak Ridge National Laboratory (ORNL) systems analysis program. This expert system will aid in prioritizing radioactive waste streams for treatment and disposal by evaluating the severity and treatability of the problem, as well as the final waste form. The objectives of the expert system development included: (1) collecting information on process treatment technologies for liquid low-level waste (LLLW) that can be incorporated in the knowledge base of the expert system, and (2) producing a prototype that suggests processes and disposal technologies for the ORNL LLLW system. 4 refs., 9 figs

  16. Sources and remediation for mercury contamination in aquatic systems--a literature review

    International Nuclear Information System (INIS)

    Wang, Qianrui; Kim, Daekeun; Dionysiou, Dionysios D.; Sorial, George A.; Timberlake, Dennis

    2004-01-01

    Sources of mercury contamination in aquatic systems were studied in a comprehensive literature review. The results show that the most important anthropogenic sources of mercury pollution in aquatic systems are: (1) atmospheric deposition, (2) erosion, (3) urban discharges, (4) agricultural materials, (5) mining, and (6) combustion and industrial discharges. Capping and dredging are two possible remedial approaches to mercury contamination in aquatic systems, and natural attenuation is a passive decontamination alternative. Capping seems to be an economical and effective remedial approach to mercury-contaminated aquatic systems. Dredging is an expensive remedial approach. However, for heavily polluted systems, dredging may be more effective. Natural attenuation, involving little or no cost, is a possible and very economical choice for less contaminated sites. Proper risk assessment is necessary to evaluate the effectiveness of remedial and passive decontamination methods as well as their potential adverse environmental effects. Modeling tools have a bright future in the remediation and passive decontamination of mercury contamination in aquatic systems. Existing mercury transport and transformation models were reviewed and compared

  17. Waste bituminization system in CDTN

    International Nuclear Information System (INIS)

    Guzella, M.F.R.; Miaw, S.T.W.

    1990-01-01

    Experimental works on low level waste bituminization have been developed at the Radioactive Waste Treatment Division of CDTN. A small scale bitumen extruder (1 kg/h) similar to the Angra II one is in operation. Some types of Brazilian bitumen have been selected and incorporation experiments with different types of waste were carried out; the operating conditions have been defined and the final product properties investigated. (author) [pt

  18. Biogas-centred domestic waste recycling system

    Energy Technology Data Exchange (ETDEWEB)

    Gupta, C L

    1983-04-01

    In fast developing suburban towns, there is an urgent need for an integrated system for waste recycling and energy and fertiliser supply on a single house basis. This is because even though toilet waste is handled by a septic tank-soak pit arrangement, kitchen and bathroom water and solid organic wastes have to be discharged outside the house. A biogas based domestic waste recycling system has been designed and constructed and has been successfully working. Some salient features of this plant are discussed here.

  19. Method of determining remedial control actions for a power system in an insecure state

    DEFF Research Database (Denmark)

    2013-01-01

    A method of determining remedial control actions for a power system in an insecure and unstable operating condition is provided. The power system has a plurality of generators injecting power into a network and each generator has a generator injection impedance and a stability boundary in the inj......A method of determining remedial control actions for a power system in an insecure and unstable operating condition is provided. The power system has a plurality of generators injecting power into a network and each generator has a generator injection impedance and a stability boundary...

  20. 76 FR 4823 - Hazardous Waste Management System; Identifying and Listing Hazardous Waste Exclusion

    Science.gov (United States)

    2011-01-27

    ... Waste Management System; Identifying and Listing Hazardous Waste Exclusion AGENCY: Environmental... hazardous wastes. The Agency has decided to grant the petition based on an evaluation of waste-specific... excludes the petitioned waste from the requirements of hazardous waste regulations under the Resource...

  1. 75 FR 60632 - Hazardous Waste Management System; Identification and Listing of Hazardous Waste; Direct Final Rule

    Science.gov (United States)

    2010-10-01

    ... Waste Management System; Identification and Listing of Hazardous Waste; Direct Final Rule AGENCY... management and treatment of several F- and K-waste codes. These waste codes are F037, F038, K048, K049, K051... released from the waste, plausible and specific types of management of the petitioned waste, the quantities...

  2. Tank waste treatment science

    International Nuclear Information System (INIS)

    LaFemina, J.P.; Blanchard, D.L.; Bunker, B.C.; Colton, N.G.; Felmy, A.R.; Franz, J.A.; Liu, J.; Virden, J.W.

    1994-01-01

    Remediation efforts at the U.S. Department of Energy's Hanford Site require that many technical and scientific principles be combined for effectively managing and disposing the variety of wastes currently stored in underground tanks. Based on these principles, pretreatment technologies are being studied and developed to separate waste components and enable the most suitable treatment methods to be selected for final disposal of these wastes. The Tank Waste Treatment Science Task at Pacific Northwest Laboratory is addressing pretreatment technology development by investigating several aspects related to understanding and processing the tank contents. The experimental work includes evaluating the chemical and physical properties of the alkaline wastes, modeling sludge dissolution, and evaluating and designing ion exchange materials. This paper gives some examples of results of this work and shows how these results fit into the overall Hanford waste remediation activities. This work is part of series of projects being conducted for the Tank Waste Remediation System

  3. Radiation effects issues related to US DOE site remediation and nuclear waste storage

    International Nuclear Information System (INIS)

    Weber, W.J.; Ewing, R.C.

    1994-10-01

    Site restoration activities at DOE facilities and the permanent disposal of nuclear waste generated at the same DOE facilities involve working with and within various types and levels of radiation fields. Radionuclide decay and the associated radiation fields lead to physical and chemical changes that can degrade or enhance material properties. This paper reviews the impact of radiation fields on site restoration activities and on the release rate of radionuclides to the biosphere from nuclear waste forms

  4. Development of waste water reuse water system for power plants

    Energy Technology Data Exchange (ETDEWEB)

    Park, K K; Kim, D H; Weon, D Y; Yoon, S W; Song, H R [Korea Electric Power Research Institute, Taejeon (Korea, Republic of)

    1998-12-31

    1. Status of waste water discharge at power plants 2. Present status of waste water reuse at power plants 3. Scheme of waste water reuse at power plants 4. Standardization of optimum system for waste water reuse at power plants 5. Establishment of low cost zero discharge system for waste water 6. Waste water treatment technology of chemical cleaning. (author). 132 figs., 72 tabs.

  5. Development of waste water reuse water system for power plants

    Energy Technology Data Exchange (ETDEWEB)

    Park, K.K.; Kim, D.H.; Weon, D.Y.; Yoon, S.W.; Song, H.R. [Korea Electric Power Research Institute, Taejeon (Korea, Republic of)

    1997-12-31

    1. Status of waste water discharge at power plants 2. Present status of waste water reuse at power plants 3. Scheme of waste water reuse at power plants 4. Standardization of optimum system for waste water reuse at power plants 5. Establishment of low cost zero discharge system for waste water 6. Waste water treatment technology of chemical cleaning. (author). 132 figs., 72 tabs.

  6. Proceedings of emerging technologies for hazardous waste management

    International Nuclear Information System (INIS)

    Tedder, D.W.

    1992-01-01

    This paper contains the proceedings of emergin technologies for hazardous waste management. Topics covered include: advanced transuranic waste managements; remediation of soil/water systems contaminated with nonaqueous pollutants; advances in molten salt oxidation; air treatment and protection; advanced waste minimization strategies; removal of hazardous materials from soils or groundwater; bioremediation of soils and sediment; innovation, monitoring, and asbestos; high-level liquid waste chemistry in the Hanford tanks; biological contributions to soil and groundwater remediation; soil treatment technologies; pollution prevention; incineration and vitrification; current technology; systematic design approaches to hazardous waste management; waste management and environmental restoration at Savannah River; soil washing and flushing for remediation of hazardous wastes

  7. The legal system of nuclear waste disposal

    International Nuclear Information System (INIS)

    Dauk, W.

    1983-01-01

    This doctoral thesis presents solutions to some of the legal problems encountered in the interpretation of the various laws and regulations governing nuclear waste disposal, and reveals the legal system supporting the variety of individual regulations. Proposals are made relating to modifications of problematic or not well defined provisions, in order to contribute to improved juridical security, or inambiguity in terms of law. The author also discusses the question of the constitutionality of the laws for nuclear waste disposal. Apart from the responsibility of private enterprise to contribute to safe treatment or recycling, within the framework of the integrated waste management concept, and apart from the Government's responsibility for interim or final storage of radioactive waste, there is a third possibility included in the legal system for waste management, namely voluntary measures taken by private enterprise for radioactive waste disposal. The licence to be applied for in accordance with section 3, sub-section (1) of the Radiation Protection Ordinance is interpreted to pertain to all measures of radioactive waste disposal, thus including final storage of radioactive waste by private companies. Although the terminology and systematic concept of nuclear waste disposal are difficult to understand, there is a functionable system of legal provisions contained therein. This system fits into the overall concept of laws governing technical safety and safety engineering. (orig./HSCH) [de

  8. Automated sample analysis and remediation

    International Nuclear Information System (INIS)

    Hollen, R.; Settle, F.

    1995-01-01

    The Contaminant Analysis Automation Project is developing an automated chemical analysis system to address the current needs of the US Department of Energy (DOE). These needs focus on the remediation of large amounts of radioactive and chemically hazardous wastes stored, buried and still being processed at numerous DOE sites. This paper outlines the advantages of the system under development, and details the hardware and software design. A prototype system for characterizing polychlorinated biphenyls in soils is also described

  9. Waste Management System Requirements Document

    International Nuclear Information System (INIS)

    1992-02-01

    This DCP establishes an interim plan for the Office of Civilian Radioactive Waste Management (OCRWM) technical baseline until the results of the OCRWM Document Hierarchy Task Force can be implemented. This plan is needed to maintain continuity in the Program for ongoing work in the areas of Waste Acceptance, Transportation, Monitored Retrievable Storage (MRS) and Yucca Mountain Site Characterization

  10. Innovative systems for mixed waste retrieval and/or treatment in confined spaces

    International Nuclear Information System (INIS)

    Fekete, L.J.; Ghusn, A.E.

    1993-03-01

    Fernald established operations in 1951 and produced uranium and other metals for use at other DOE facilities. A part of the sitewide remediation effort is the removal, treatment, and disposal of the K-65 wastes from Silos 1 and 2. These silos contain radium-bearing residues from the processing of pitchblende ore. An Engineering Evaluation/Cost Analysis was prepared to evaluate the removal action alternatives using the preliminary characterization data and select a preferred alternative. The selected alternative consisted of covering the K-65 residues and the silo dome. The remediation of the K-65 wastes consists of the retrieval and treatment of the wastes prior to final disposal, which has not yet been determined. Treatment will be performed in a new facility to be built adjacent to the silos. The wastes must be retrieved from silos in an efficient and reliable way and delivered to the treatment facility. The first challenge of covering the wastes with bentonite has been successfully met. The second phase of retrieving the wastes from the silos is not due for a few years. However, conceptual design and configuration of the retrieval system have been developed as part of the Conceptual Design Report. The system is based on the utilization of hydraulic mining techniques, and is based on similar successful applications. This report describes the emplacement of the bentonite grant and the design for the slurry retrieval system

  11. Los Alamos Plutonium Facility Waste Management System

    International Nuclear Information System (INIS)

    Smith, K.; Montoya, A.; Wieneke, R.; Wulff, D.; Smith, C.; Gruetzmacher, K.

    1997-01-01

    This paper describes the new computer-based transuranic (TRU) Waste Management System (WMS) being implemented at the Plutonium Facility at Los Alamos National Laboratory (LANL). The Waste Management System is a distributed computer processing system stored in a Sybase database and accessed by a graphical user interface (GUI) written in Omnis7. It resides on the local area network at the Plutonium Facility and is accessible by authorized TRU waste originators, count room personnel, radiation protection technicians (RPTs), quality assurance personnel, and waste management personnel for data input and verification. Future goals include bringing outside groups like the LANL Waste Management Facility on-line to participate in this streamlined system. The WMS is changing the TRU paper trail into a computer trail, saving time and eliminating errors and inconsistencies in the process

  12. Site-specific waste management instruction - 200-ZP-1 pump-and-treat system

    International Nuclear Information System (INIS)

    Hopkins, G.G.

    1997-01-01

    This Site-Specific Waste Management Instruction (SSWMI) provides guidance for managing waste generated from operation of the 200-ZP-1 Pump-and-Treat (P and T) System, located just north of the Plutonium Finishing Plant in the 200 West Area. The construction and implementation of the 200-ZP-1 P and T System are an integral part of the 200-ZP-1 interim remedial measure activities. The goal of the interim remedial measure activities is to reduce further migration of carbon tetrachloride (CCl 4 ), chloroform, and trichloroethylene (TCE) in the groundwater of the 200 West Area. The P and T system is designed to initiate hydraulic containment of the contaminant mass in the high-concentration portion of the CCl 4 plume. The P and T contaminant removal mechanism consists of a combination of air stripping and vapor-phase granular activated carbon (GAC) adsorption technologies

  13. First generation long-reach manipulator for retrieval of waste from Hanford single-shell tanks

    International Nuclear Information System (INIS)

    Gibbons, P.W.; McDaniel, L.B.

    1994-10-01

    The US Department of Energy, Richland Operations Office, has established the Tank Waste Remediation System to resolve environmental and safety issues related to underground waste-storage tanks at the Hanford Site. The Tank Waste Remediation System has identified the use of an advanced-technology, long-reach manipulator system as a low-water-addition retrieval alternative to past-practice sluicing

  14. Feasibility study of a self-remediation system for mine drainage using its thermal energy

    Science.gov (United States)

    Oh, Chamteut; Cheong, Youngwook; Yim, Giljae; Ji, Sangwoo

    2016-04-01

    Mine drainage is defined as the water which is discharged to the ground surface through shafts and/or cracks formed by mining activities. Typically, mine drainage features high concentration of acidity and metals since it passes through the underground. Therefore, for the purpose of protecting the surrounding natural environment, mine drainage should be remediated before being discharged to nature. Mine drainage, due to its nature of being retained underground, shows constant temperature which is independent from the temperature of the atmosphere above ground. This condition allows mine drainage to become a promising renewable energy source since energy can be recovered from water with constant temperature. In this research, a self-remediation system is proposed which remediates the mine drainage through electrochemical reactions powered by the thermal energy of mine drainage. High energy efficiency is able to be achieved by shortening the distance between the energy source and consumption, and therefore, this system has a strong advantage to be actualized. A feasibility study for the system was conducted in this research where the thermal energy of mine drainage over time and depth was calculated as energy supply and the required electrical energy for remediating the mine drainage was measured as energy consumption. While the technology of converting thermal energy directly into electrical energy is yet to be developed, energy balance analysis results showed that the proposed self-remediation system is theoretically possible.

  15. Waste minimization opportunities at the U.S. Uranium Mill Tailings Remedial Action (UMTRA) Project, Rifle, Colorado, site

    International Nuclear Information System (INIS)

    Hartmann, G.L.; Arp, S.; Hempill, H.

    1993-01-01

    At two uranium mill sites in Rifle, Colorado, the US Department of Energy (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project is removing uranium mill tailings and contaminated subgrade soils. This remediation activity will result in the production of groundwater contaminated with uranium, heavy metals, ammonia, sulfates, and total dissolved solids (TDS). The initial remediation plan called for a wastewater treatment plant for removal of the uranium, heavy metals, and ammonia, with disposal of the treated water, which still includes the sulfates and TDSS, to the Colorado River. The National Pollutant Discharge Elimination (NPDES) permit issued by the Colorado Department of Health for the two Rifle sites contained more restrictive discharge limits than originally anticipated. During the detailed review of alternate treatment systems to meet these more restrictive limits, the proposed construction procedures were reviewed emphasizing the methods to minimize groundwater production to reduce the size of the water treatment facility, or to eliminate it entirely. It was determined that with changes to the excavation procedures and use of the contaminated groundwater for use in dust suppression at the disposal site, discharge to the river could be eliminated completely

  16. Biosurfactant production by Mucor circinelloides on waste frying oil and possible uses in crude oil remediation.

    Science.gov (United States)

    Hasanizadeh, Parvin; Moghimi, Hamid; Hamedi, Javad

    2017-10-01

    Biosurfactants are biocompatible surface active agents which many microorganisms produce. This study investigated the production of biosurfactants by Mucor circinelloides. The effects of different factors on biosurfactant production, including carbon sources and concentrations, nitrogen sources, and iron (II) concentration, were studied and the optimum condition determined. Finally, the strain's ability to remove the crude oil and its relationship with biosurfactant production was evaluated. The results showed that M. circinelloides could reduce the surface tension of the culture medium to 26.6 mN/m and create a clear zone of 12.9 cm diameter in an oil-spreading test. The maximum surface tension reduction was recorded 3 days after incubation. The optimum condition for biosurfactant production was achieved in the presence of 8% waste frying oil as a carbon source, 2 g/L yeast extract as a nitrogen source, and 0.01 mM FeSO 4 . M. circinelloides could consume 8% waste frying oil in 5 days of incubation, and 87.6% crude oil in 12 days of incubation. A direct correlation was observed between oil degradation and surface tension reduction in the first 3 days of fungal growth. The results showed that the waste frying oil could be recommended as an inexpensive oily waste substance for biosurfactant production, and M. circinelloides could have the potential to treat waste frying oil. According to the results, the produced crude biosurfactant or fungal strain could be directly used for the mycoremediation of crude oil contamination in oil fields.

  17. Environmental Assessment and Finding of No Significant Impact: Waste Remediation Activities at Elk Hills (Former Naval petroleum Reserve No. 1), Kern County, California

    Energy Technology Data Exchange (ETDEWEB)

    N/A

    1999-12-17

    DOE proposes to conduct a variety of post-sale site remediation activities, such as characterization, assessment, clean-up, and formal closure, at a number of inactive waste sites located at Elk Hills. The proposed post-sale site remediation activities, which would be conducted primarily in developed portions of the oil field, currently are expected to include clean-up of three basic categories of waste sites: (1) nonhazardous solid waste surface trash scatters, (2) produced wastewater sumps, and (3) small solid waste landfills. Additionally, a limited number of other inactive waste sites, which cannot be typified under any of these three categories, have been identified as requiring remediation. Table 2.1-1 presents a summary, organized by waste site category, of the inactive waste sites that require remediation per the PSA, the ASA, and/or the UPCTA. The majority of these sites are known to contain no hazardous waste. However, one of the surface scatter sites (2G) contains an area of burn ash with hazardous levels of lead and zinc, another surface scatter site (25S) contains an area with hazardous levels of lead, a produced wastewater sump site (23S) and a landfill (42-36S) are known to contain hazardous levels of arsenic, and some sites have not yet been characterized. Furthermore, additional types of sites could be discovered. For example, given the nature of oil field operations, sites resulting from either spills or leaks of hazardous materials could be discovered. Given the nature of the agreements entered into by DOE regarding the required post-sale clean-up of the inactive waste sites at Elk Hills, the Proposed Action is the primary course of action considered in this EA. The obligatory remediation activities included in the Proposed Action are standard procedures such that possible variations of the Proposed Action would not vary substantially enough to require designation as a separate, reasonable alternative. Thus, the No Action Alternative is the only

  18. Remediation of uranium-contaminated soil using the Segmented Gate System and containerized vat leaching techniques: a cost effectiveness study

    International Nuclear Information System (INIS)

    Cummings, M.; Booth, S.R.

    1996-01-01

    Because it is difficult to characterize heterogeneously contaminated soils in detail and to excavate such soils precisely using heavy equipment, it is common for large quantities of uncontaminated soil to be removed during excavation of contaminated sites. Until now, volume reduction of radioactively contaminated soil depended upon manual screening and analysis of samples, a costly and impractical approach, particularly with large volumes of heterogeneously contaminated soil. The baseline approach for the remediation of soils containing radioactive waste is excavation, pretreatment, containerization, and disposal at a federally permitted landfill. However, disposal of low-level radioactive waste is expensive and storage capacity is limited. ThermoNuclean's Segmented Gate System (SGS) removes only the radioactively contaminated soil, in turn greatly reducing the volume of soils that requires disposal. After processing using the SGS, the fraction of contaminated soil is processed using the containerized vat leaching (CVL) system developed at LANL. Uranium is leached out of the soil in solution. The uranium is recovered with an ion exchange resin, leaving only a small volume of liquid low-level waste requiring disposal. The reclaimed soil can be returned to its original location after treatment with CVL

  19. New IAEA guidelines on environmental remediation

    Energy Technology Data Exchange (ETDEWEB)

    Fesenko, Sergey [International Atomic Energy Agency, A2444, Seibersdorf (Austria); Howard, Brenda [Centre for Ecology and Hydrology, Lancaster Environment Centre, LA1 4AP, Lancaster (United Kingdom); Kashparov, Valery [Ukrainian Institute of Agricultural Radiology, 08162, 7, Mashinobudivnykiv str., Chabany, Kyivo-Svyatoshin region, Kyiv (Ukraine); Sanzharova, Natalie [Russian Institute of Agricultural Radiology and Agroecology, Russian Federation, 249032, Obninsk (Russian Federation); Vidal, Miquel [Analytical Chemistry Department-Universitat de Barcelona, Barcelona, 08028 Barcelona (Spain)

    2014-07-01

    dimensions including radiological, economic, social and environmental aspects. The system of criteria used for evaluating management options, including effectiveness and technical feasibility economic cost, waste generation, social and ethical issues, side effects and factors constraining application are discussed. Rather than a comprehensive analysis of remedial options, the new document gives selected information, describe key issues that are relevant to their implementation based on practical experience, and provide some guidance of their usefulness as part of a remediation strategy. Basic mechanisms behind the effectiveness of most of management options are also described. The document provides recommendations on remediation planning, optimising remediation strategies and available tools for decision making on remediation of different environments. The document specifically collates, and summarises, recent activities relevant to remediation conducted under the auspices of the IAEA, but also refers to relevant studies conducted elsewhere. The text thus capitalises on the knowledge and expertise gained by the many experts involved. In common with previous IAEA documents on remediation, much of the document is relevant for many other situations which may need to be remediated. (authors)

  20. Completion report for the isolation and remediation of inactive liquid low-level radioactive waste tanks WC-5, WC-6, WC-8, WC-19, 3002-A, 7560, and 7562 at Oak Ridge National Laboratory Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1997-12-01

    The Federal Facility Agreement (FFA) between the U.S. Environmental Protection Agency (EPA), Tennessee Department of Environment and Conservation (TDEC), and U.S. Department of Energy (DOE) requires that all liquid low-level waste tanks at Oak Ridge National Laboratory removed from service, designated in the FFA as Category D, be remediated in accordance with Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) requirements. A human health risk screening assessment was conducted for inactive Tanks WC-5, WC-6, WC-8, WC-19, 3002-A, 7560, and 7562 as part of an evaluation to determine the method of remediation necessary to safely and permanently isolate and remediate the tanks. Risk screening assessment results indicated that the health risks associated with these tanks were within or below the EPA range of concern of 1 x 10 -4 to 1 x 10 -6 . On the basis of these results and with regulators concurrence, it was determined that either no action or in-place stabilization of the tanks would satisfy risk-based remediation goals. Therefore, decisions were made and approved by DOE to remediate these tanks in-place as maintenance actions rather than actions under the CERCLA process. Letters documenting these decisions were approved by DOE and subsequently submitted to TDEC and EPA, who concurred with the maintenance actions. Tanks WC-5, WC-6, WC-8, WC-19, 3002-A, 7560, and 7562 were isolated from associated piping, electrical systems, and instrumentation and were grouted in-place. Tank 7562 was originally isolated from associated piping and instrumentation and left in-place empty for future remedial consideration. Upon further consideration, the decision was made by DOE, with concurrence by the regulators, to complete the maintenance action of Tank 7562 by grouting it in-place in March 1997

  1. Waste system optimization - can diameter selection

    International Nuclear Information System (INIS)

    Ashline, R.C.

    1983-08-01

    The purpose of the waste system optimization study is to define in terms of cost incentives the preferred waste package for HLW which has been converted to glass at a commercial reprocessing plant. The Waste Management Economic Model (WMEM) was employed to analyze the effect of varying important design parameters on the overall net present cost of waste handling. The parameters found to have the greatest effect on the calculated overall net present cost were can diameter, repository type (salt, basalt/bentonite, or welded tuff), allowable areal heat loading, and the repository availability date. The overall net present of a waste handling option is calculated over a 20-year operating period. It includes the total capital and operating costs associated with high-level and intermediate-level liquid waste storage, liquid waste solidification, hulls storage and compaction, and general process trash handling. It also includes the cask leasing and transportation costs associated with each waste type and the waste repository disposal costs. The waste repository disposal costs used in WMEM for this analysis were obtained from Battelle Pacific Northwest Laboratories and thir RECON model. 2 figures, 2 tables

  2. In situ vitrification of buried waste: Containment issues and suppression systems

    International Nuclear Information System (INIS)

    Luey, J.; Powell, T.D.

    1992-01-01

    Pacific Northwest Laboratory (PNL) and Idaho National Engineering Laboratory (INEL) are developing a remedial action technology for buried waste through the adaptation of the in situ vitrification (ISV) process. The ISV process is a thermal treatment process originally developed for the U.S. Department of Energy (DOE) to stabilize soils contaminated with transuranic waste. ISV tests with buried waste forms have demonstrated that the processing of buried waste is more dynamic than the processing of soils. This paper will focus on the issue of containment of the gases released during the processing of buried waste and on engineered suppression systems to alleviate transient events associated with dynamic off-gassing from the ISV melt. (author)

  3. Roles of Historical Photography in Waste Site Characterization, Closure, and Remediation

    International Nuclear Information System (INIS)

    Mackey, H.

    1998-07-01

    Over 40,000 frames of vertical historical photography from 1938 to 1996 and over 10,000 frames of oblique photography from 1981 to 1991 of the 777-square kilometer Savannah River Site in south central South Carolina were reviewed, cataloged, and referenced utilizing ARCView and associated ArcInfo tools. This allows environmental reviews of over 400 potential waste units on the SRS to be conducted in a rapid fashion to support preparation of work plans, characterization, risk assessments, and closure of the waste units in a more cost effective manner

  4. Management of toxic waste resulting from decommissioning and environmental remediation of nuclear facilities in Northwest Russia

    International Nuclear Information System (INIS)

    Vysotskij, V.L.; Nikitin, V.S.; Kulikov, K.N.; Ivanov, S.A.; Bogdanova, G.S.; Zakharov, A.A.

    2008-01-01

    Integrated information on toxic wastes formed during utilization and rehabilitation of shutdown naval nuclear object at Northwest Russia is performed. Dynamics of their accumulation to 2025 is estimated. Necessity of present waste management review and search of new methods with the view of decrease of environmental risks by means of systematic reprocessing or economic favorable destruction. Several strategies are treated. Advantages and imperfections of each of them are estimated by safety factors and economic costs, and the most acceptable strategy is selected. Functional model is found. Lists of projects, technical means are given, periods, costs for its realization are evaluated. Guidelines are provided [ru

  5. Capping as an alternative for remediating radioactive and mixed waste landfills

    International Nuclear Information System (INIS)

    Hakonson, T.E.

    1994-01-01

    This report describes some of the regulatory and technical issues concerning the use of capping as a containment strategy for radioactive and hazardous waste. Capping alternatives for closure of landfills is not just an engineering problem, but rather involves complex physical, biological, and chemical processes requiring a multidisciplinary approach to develop designs that will work over the long haul and are cost-effective. Much of the information has been distilled from regulatory and guidance documents and a compilation of research activities on waste disposal, contaminant transport processes, and technology development for landfills that has been conducted over the last 21 years

  6. Packaged low-level waste verification system

    International Nuclear Information System (INIS)

    Tuite, K.T.; Winberg, M.; Flores, A.Y.; Killian, E.W.; McIsaac, C.V.

    1996-01-01

    Currently, states and low-level radioactive waste (LLW) disposal site operators have no method of independently verifying the radionuclide content of packaged LLW that arrive at disposal sites for disposal. At this time, disposal sites rely on LLW generator shipping manifests and accompanying records to insure that LLW received meets the waste acceptance criteria. An independent verification system would provide a method of checking generator LLW characterization methods and help ensure that LLW disposed of at disposal facilities meets requirements. The Mobile Low-Level Waste Verification System (MLLWVS) provides the equipment, software, and methods to enable the independent verification of LLW shipping records to insure that disposal site waste acceptance criteria are being met. The MLLWVS system was developed under a cost share subcontract between WMG, Inc., and Lockheed Martin Idaho Technologies through the Department of Energy's National Low-Level Waste Management Program at the Idaho National Engineering Laboratory (INEL)

  7. A Diagnostic-Remediation Teaching System for Enhancing Elementary Students' Science Listening Comprehension

    Science.gov (United States)

    Lin, Sheau-Wen; Liu, Yu

    2017-01-01

    The purpose of this study was to explore elementary students' listening comprehension changes using a Web-based teaching system that can diagnose and remediate students' science listening comprehension problems during scientific inquiry. The 3-component system consisted of a 9-item science listening comprehension test, a 37-item diagnostic test,…

  8. 29 CFR 1602.43 - Commission's remedy for school systems' or districts' failure to file report.

    Science.gov (United States)

    2010-07-01

    ...' failure to file report. Any school system or district failing or refusing to file report EEO-5 when... 29 Labor 4 2010-07-01 2010-07-01 false Commission's remedy for school systems' or districts' failure to file report. 1602.43 Section 1602.43 Labor Regulations Relating to Labor (Continued) EQUAL...

  9. Integrated waste and water management system

    Science.gov (United States)

    Murray, R. W.; Sauer, R. L.

    1986-01-01

    The performance requirements of the NASA Space Station have prompted a reexamination of a previously developed integrated waste and water management system that used distillation and catalytic oxydation to purify waste water, and microbial digestion and incineration for waste solids disposal. This system successfully operated continuously for 206 days, for a 4-man equivalent load of urine, feces, wash water, condensate, and trash. Attention is given to synergisms that could be established with other life support systems, in the cases of thermal integration, design commonality, and novel technologies.

  10. Waste package performance allocation system study report

    International Nuclear Information System (INIS)

    Memory, R.D.

    1994-01-01

    The Waste Package Performance Allocation system study was performed in order to provide a technical basis for the selection of the waste package period of substantially complete containment and its resultant contribution to the overall total system performance. This study began with a reference case based on the current Mined Geologic Disposal System (MGDS) baseline design and added a number of alternative designs. The waste package designs were selected from the designs being considered in detail during Advanced Conceptual Design (ACD). The waste packages considered were multi-barrier packages with a 0.95 cm Alloy 825 inner barrier and a 10, 20, or 45 cm thick carbon steel outer barrier. The waste package capacities varied from 6 to 12 to 21 Pressurized Water Reactor (PWR) fuel assemblies. The vertical borehole and in-drift emplacement modes were also considered, as were thermal loadings of 25, 57, and 114 kW/acre. The repository cost analysis indicated that the 21 PWR in-drift emplacement mode option with the 10 cm and 20 cm outer barrier thicknesses are the least expensive and that the 12 PWR in-drift case has approximately the same cost as the 6 PWR vertical borehole. It was also found that the cost increase from the 10 cm outer barrier waste package to the 20 cm waste package was less per centimeter than the increase from the 20 cm outer barrier waste package to the 45 cm outer barrier waste package. However, the repository cost was nearly linear with the outer barrier thickness for the 21 PWR in-drift case. Finally, corrosion rate estimates are provided and the relationship of repository cost versus waste package lifetime is discussed as is cumulative radionuclide release from the waste package and to the accessible environment for time periods of 10,000 years and 100,000 years

  11. Determination of a radioactive waste classification system

    Energy Technology Data Exchange (ETDEWEB)

    Cohen, J.J.; King, W.C.

    1978-03-01

    Several classification systems for radioactive wastes are reviewed and a system is developed that provides guidance on disposition of the waste. The system has three classes: high-level waste (HLW), which requires complete isolation from the biosphere for extended time periods; low-level waste (LLW), which requires containment for shorter periods; and innocuous waste (essentially nonradioactive), which may be disposed of by conventional means. The LLW/innocuous waste interface was not defined in this study. Reasonably conservative analytical scenarios were used to calculate that HLW/LLW interface level which would ensure compliance with the radiological exposure guidelines of 0.5 rem/y maximum exposure for a few isolated individuals and 0.005 rem/y for large population groups. The recommended HLW/LLW interface level for /sup 239/Pu or mixed transuranic waste is 1.0 ..mu..Ci/cm/sup 3/ of waste. Levels for other radionuclides are based upon a risk equivalent to this level. A cost-benefit analysis in accordance with as low as reasonably achievable (ALARA) and National Environmental Protection Act (NEPA) guidance indicates that further reduction of this HLW/LLL interface level would entail marginal costs greater than $10/sup 8/ per man-rem of dose avoided. The environmental effects considered were limited to those involving human exposure to radioactivity.

  12. Determination of a radioactive waste classification system

    International Nuclear Information System (INIS)

    Cohen, J.J.; King, W.C.

    1978-03-01

    Several classification systems for radioactive wastes are reviewed and a system is developed that provides guidance on disposition of the waste. The system has three classes: high-level waste (HLW), which requires complete isolation from the biosphere for extended time periods; low-level waste (LLW), which requires containment for shorter periods; and innocuous waste (essentially nonradioactive), which may be disposed of by conventional means. The LLW/innocuous waste interface was not defined in this study. Reasonably conservative analytical scenarios were used to calculate that HLW/LLW interface level which would ensure compliance with the radiological exposure guidelines of 0.5 rem/y maximum exposure for a few isolated individuals and 0.005 rem/y for large population groups. The recommended HLW/LLW interface level for 239 Pu or mixed transuranic waste is 1.0 μCi/cm 3 of waste. Levels for other radionuclides are based upon a risk equivalent to this level. A cost-benefit analysis in accordance with as low as reasonably achievable (ALARA) and National Environmental Protection Act (NEPA) guidance indicates that further reduction of this HLW/LLL interface level would entail marginal costs greater than $10 8 per man-rem of dose avoided. The environmental effects considered were limited to those involving human exposure to radioactivity

  13. [Continuous remediation of heavy metal contaminated soil by co-cropping system enhanced with chelator].

    Science.gov (United States)

    Wei, Ze-Bin; Guo, Xiao-Fang; Wu, Qi-Tang; Long, Xin-Xian

    2014-11-01

    In order to elucidate the continuous effectiveness of co-cropping system coupling with chelator enhancement in remediating heavy metal contaminated soils and its environmental risk towards underground water, soil lysimeter (0.9 m x 0.9 m x 0.9 m) experiments were conducted using a paddy soil affected by Pb and Zn mining in Lechang district of Guangdong Province, 7 successive crops were conducted for about 2.5 years. The treatments included mono-crop of Sedum alfredii Hance (Zn and Cd hyperaccumulator), mono-crop of corn (Zea mays, cv. Yunshi-5, a low-accumulating cultivar), co-crop of S. alfredii and corn, and co-crop + MC (Mixture of Chelators, comprised of citric acid, monosodium glutamate waste liquid, EDTA and KCI with molar ratio of 10: 1:2:3 at the concentration of 5 mmol x kg(-1) soil). The changes of heavy metal concentrations in plants, soil and underground water were monitored. Results showed that the co-cropping system was suitable only in spring-summer seasons and significantly increased Zn and Cd phytoextraction. In autumn-winter seasons, the growth of S. alfredii and its phytoextraction of Zn and Cd were reduced by co-cropping and MC application. In total, the mono-crops of S. alfredii recorded a highest phytoextraction of Zn and Cd. However, the greatest reduction of soil Zn, Cd and Pb was observed with the co-crop + MC treatment, the reduction rates were 28%, 50%, and 22%, respectively, relative to the initial soil metal content. The reduction of this treatment was mainly attributed to the downwards leaching of metals to the subsoil caused by MC application. The continuous monitoring of leachates during 2. 5 year's experiment also revealed that the addition of MC increased heavy metal concentrations in the leaching water, but they did not significantly exceed the III grade limits of the underground water standard of China.

  14. Electromagnetic mixed-waste processing system for asbestos decontamination

    International Nuclear Information System (INIS)

    1995-04-01

    The first phase of a program to develop and demonstrate a cost-effective, integrated process for remediation of asbestos-containing material that is contaminated with organics, heavy metals, and radioactive compounds was successfully completed. Laboratory scale tests were performed to demonstrate initial process viability for asbestos conversion, organics removal, and radionuclide and heavy metal removal. All success criteria for the laboratory tests were met. (1) Ohio DSI demonstrated greater than 99% asbestos conversion to amorphous solids using their commercial process. (2) KAI demonstrated 90% removal of organics from the asbestos suspension. (3) Westinghouse STC achieved the required metals removal criteria on a laboratory scale (e.g., 92% removal of uranium from solution, resin loadings of 0.6 equivalents per liter, and greater than 50% regeneration of resin in a batch test.) Using the information gained in the laboratory tests, the process was reconfigured to provide the basis for the mixed waste remediation system. An integrated process is conceptually developed, and a Phase 2 program plan is proposed to provide the bench-scale development needed in order to refine the design basis for a pilot processing system

  15. Development of a Radioactive Waste Assay System

    Energy Technology Data Exchange (ETDEWEB)

    Kang, Duck Won; Song, Myung Jae; Shin, Sang Woon; Sung, Kee Bang; Ko, Dae Hach [Korea Electric Power Research Institute, Taejon (Korea, Republic of); Kim, Kil Jeong; Park, Jong Mook; Jee, Kwang Yoong [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1996-12-31

    Nuclear Act of Korea requires the manifest of low and intermediate level radioactive waste generated at nuclear power plants prior to disposal sites.Individual history records of the radioactive waste should be contained the information about the activity of nuclides in the drum, total activity, weight, the type of waste. A fully automated nuclide analysis assay system, non-destructive analysis and evaluation system of the radioactive waste, was developed through this research project. For the nuclides that could not be analysis directly by MCA, the activities of the representative {gamma}-emitters(Cs-137, Co-60) contained in the drum were measured by using that system. Then scaling factors were used to calculate the activities of {alpha}, {beta}-emitters. Furthermore, this system can automatically mark the analysis results onto the drum surface. An automated drum handling system developed through this research project can reduce the radiation exposure to workers. (author). 41 refs., figs.

  16. SUGERE - a unified system for waste management

    International Nuclear Information System (INIS)

    Silva, Eliane Magalhaes Pereira da; Vasconcelos, Vanderley de; Senne Junior, Murillo; Jordao, Elizabete

    2005-01-01

    Generation and disposal of wastes has been responsible for many economical, ecological and public health problems. In order to manage hazardous wastes in an environment friendly manner, many technical and administrative procedures should be implemented, including prevention, control of generation, and final disposal. A software named SUGERE - a unified system for waste management - is being developed. It is an easy to use tool that integrates all the steps involved in hazardous and radioactive waste management. This system is intended to help generators, transporters and owners of treatment, storage and disposal facilities to manage hazardous and radioactive wastes, by assuring compliance with environmental laws and consumer requirements. This paper presents the current status of the SUGERE software, developed using Borland Delphi package. The nuclear industry is used as a reference for developing this work. (author)

  17. Remedial investigation report on waste area grouping 5 at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Volume 4, Appendix C, Risk assessment

    International Nuclear Information System (INIS)

    1995-09-01

    Waste Area Grouping (WAG) 5 is part of Oak Ridge National Laboratory (ORNL) and is located on the United States Department of Energy's Oak Ridge Reservation (DOE-ORR). The site lies southeast of Haw Ridge in Melton Valley and comprises approximately 32 ha (80 ac) [12 ha (30 ac) of forested area and the balance in grassed fields]. Waste Area Grouping 5 consists of several contaminant source areas for the disposal of low-level radioactive, transuranic (TRU), and fissile wastes (1959 to 1973) as well as inorganic and organic chemical wastes. Wastes were buried in trenches and auger holes. Radionuclides from buried wastes are being transported by shallow groundwater to Melton Branch and White Oak Creek. Different chemicals of potential concern (COPCs) were identified (e.g., cesium-137, strontium-90, radium-226, thorium-228, etc.); other constituents and chemicals, such as vinyl chloride, bis(2-ethylhexyl)phthalate, trichloroethene, were also identified as COPCs. Based on the results of this assessment contaminants of concern (COCs) were subsequently identified. The objectives of the WAG 5 Baseline Human Health Risk Assessment (BHHRA) are to document the potential health hazards (i.e., risks) that may result from contaminants on or released from the site and provide information necessary for reaching informed remedial decisions. As part of the DOE-Oak Ridge Operations (ORO), ORNL and its associated waste/contamination sites fall under the auspices of the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), also known as Superfund under the Superfund Amendments and Reauthorization Act (SARA). The results of the BHHRA will (1) document and evaluate risks to human health, (2) help determine the need for remedial action, (3) determine chemical concentrations protective of current and future human receptors, and (4) help select and compare various remedial alternatives.

  18. Remediating MGP brownfields

    International Nuclear Information System (INIS)

    Larsen, B.R.

    1997-01-01

    Before natural gas pipelines became widespread in this country, gas fuel was produced locally in more than 5,000 manufactured gas plants (MGPs). The toxic wastes from these processes often were disposed onsite and have since seeped into the surrounding soil and groundwater. Although the MGPs--commonly called gas plants, gas-works or town gas plants--have closed and most have been demolished, they have left a legacy of environmental contamination. At many MGP sites, underground storage tanks were constructed of wood or brick, with process piping and equipment which frequently leaked. Waste materials often were disposed onsite. Releases of coal tars, oils and condensates produced within the plants contributed to a wide range of contamination from polycyclic aromatic hydrocarbons, phenols, benzene and cyanide. Remediation of selected MGP sites has been sporadic. Unless the site has been identified as a Comprehensive Environmental Response, Compensation and Liability Information System (CERCLIS) Superfund site, the regulatory initiative to remediate often remains with the state in which the MGP is located. A number of factors are working to change that picture and to create a renewed interest in MGP site remediation. The recent Brownfield Initiative by the US Environmental Protection Agency (EPA) is such an example

  19. West Valley waste removal system study

    International Nuclear Information System (INIS)

    Janicek, G.P.

    1981-04-01

    This study addresses the specific task of removing high-level wastes from underground tanks at Western New York Nuclear Center and delivering them to an onsite waste solidification plant. It begins with a review of the design and construction features of the waste storage tanks pertinent to the waste removal task with particular emphasis on the unique and complex tank internals which severely complicate the task of removal. It follows with a review of tank cleaning techniques used and under study at both Hanford and Savannah River and previous studies proposing the use of these techniques at West Valley. It concludes from these reviews that existing techniques are not directly transferable to West Valley and that a new approach is required utilizing selected feature and attributes from existing methodology. The study also concludes, from an investigation of the constraints imposed by the processing facility, that waste removal will be intermittent, requiring batch transfer over the anticipated 3 years of processing operations. Based on these reviews and conclusions, the study proposes that the acid waste be processed first and that one of the 15,000-gallon acid tanks then be used for batch feeding the neutralized waste. The proposed system would employ commercially available pumping equipment to transfer the wastes from the batch tank to processing via existing process piping. A commercially available mixed-flow pump and eight turbine pumps would homogenize the neutralized waste in conjunction with eight custom-fabricated sluicers for periodic transfer to the batch tank

  20. Method of controlling radioactive waste processing systems

    International Nuclear Information System (INIS)

    Mikawa, Hiroji; Sato, Takao.

    1981-01-01

    Purpose: To minimize the pellet production amount, maximize the working life of a solidifying device and maintaining the mechanical strength of pellets to a predetermined value irrespective of the type and the cycle of occurrence of the secondary waste in the secondary waste solidifying device for radioactive waste processing systems in nuclear power plants. Method: Forecasting periods for the type, production amount and radioactivity level of the secondary wastes are determined in input/output devices connected to a control system and resulted signals are sent to computing elements. The computing elements forecast the production amount of regenerated liquid wastes after predetermined days based on the running conditions of a condensate desalter and the production amounts of filter sludges and liquid resin wastes after predetermined days based on the liquid waste processing amount or the like in a processing device respectively. Then, the mass balance between the type and the amount of the secondary wastes presently stored in a tank are calculated and the composition and concentration for the processing liquid are set so as to obtain predetermined values for the strength of pellets that can be dried to solidify, the working life of the solidifying device itself and the radioactivity level of the pellets. Thereafter, the running conditions for the solidifying device are determined so as to maximize the working life of the solidifying device. (Horiuchi, T.)