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Sample records for waste discharge requirements

  1. California Waste Discharge Requirements Website | Open Energy...

    Open Energy Info (EERE)

    Requirements Website Jump to: navigation, search OpenEI Reference LibraryAdd to library Web Site: California Waste Discharge Requirements Website Abstract This website contains...

  2. Transuranic Waste Requirements

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    1999-07-09

    The guide provides criteria for determining if a waste is to be managed in accordance with DOE M 435.1-1, Chapter III, Transuranic Waste Requirements.

  3. Report of Waste Discharge application (Form 200) | Open Energy...

    Open Energy Info (EERE)

    Waste Discharge application (Form 200) Jump to: navigation, search OpenEI Reference LibraryAdd to library Form: Report of Waste Discharge application (Form 200) Abstract Persons...

  4. WAC - 173 - 226 - Waste Discharge General Permit Program | Open...

    Open Energy Info (EERE)

    6 - Waste Discharge General Permit Program Jump to: navigation, search OpenEI Reference LibraryAdd to library Legal Document- RegulationRegulation: WAC - 173 - 226 - Waste...

  5. Radioactive Liquid Waste Treatment Facility Discharges in 2014

    SciTech Connect (OSTI)

    Del Signore, John C.

    2015-07-14

    This report documents radioactive discharges from the TA50 Radioactive Liquid Waste Treatment Facilities (RLWTF) during calendar 2014.

  6. State waste discharge permit application: Hydrotest, maintenance and construction discharges. Revision 0

    SciTech Connect (OSTI)

    1995-11-01

    On December 23, 1991, the US DOE< Richland Operation Office (RL) and the Washington State Department of Ecology (Ecology) agreed to adhere to the provisions of the Department of Ecology Consent Order No. DE91NM-177 (216 Consent Order) (Ecology and US DOE 1991). The 216 Consent Order list regulatory milestones for liquid effluent streams at the Hanford Site and requires compliance with the permitting requirements of Washington Administrative Code. Hanford Site liquid effluent streams discharging to the soil column have been categorized on the 216 Consent Order as follows: Phase I Streams; Phase II Streams; Miscellaneous Streams. Phase I and Phase II Streams were initially addressed in two report. Miscellaneous Streams are subject to the requirements of several milestones identified in the 216 Consent Order. This document constitutes the Categorical State Waste Discharge Permit application for hydrotest,maintenance and construction discharges throughout the Hanford Site. This categorical permit application form was prepared and approved by Ecology.

  7. State waste discharge permit application for cooling water and condensate discharges

    SciTech Connect (OSTI)

    Haggard, R.D.

    1996-08-12

    The following presents the Categorical State Waste Discharge Permit (SWDP) Application for the Cooling Water and Condensate Discharges on the Hanford Site. This application is intended to cover existing cooling water and condensate discharges as well as similar future discharges meeting the criteria set forth in this document.

  8. State waste discharge permit application: 400 Area secondary cooling water

    SciTech Connect (OSTI)

    Not Available

    1992-12-01

    This document constitutes the Washington Administrative Code 173-216 State Waste Discharge Permit Application that serves as interim compliance as required by the Consent Order DE 91NM-177, for the 400 Area Secondary Cooling Water stream. As part of the Hanford Federal Facility Agreement and Consent Order negotiations, the US Department of Energy, Richland Operations Office, the US Environmental Protection Agency, and the Washington State Department of Ecology agreed that liquid effluent discharges to the ground on the Hanford Site which affect groundwater or have the potential to affect groundwater would be subject to permitting under the structure of Chapter 173-216 (or 173-218 where applicable) of the Washington Administrative Code, the State Waste Discharge Permitting Program. As a result of this decision, the Washington State Department of Ecology and the US Department of Energy, Richland Operations Office entered in to Consent Order DE 91NM-177. The Consent Order DE 91NM-177 requires a series of permitting activities for liquid effluent discharges.

  9. State Waste Discharge Permit application: 400 Area Septic System

    SciTech Connect (OSTI)

    Not Available

    1994-06-01

    As part of the Hanford Federal Facility Agreement and Consent Order negotiations, the US Department of Energy, Richland Operations Office, the US Environmental Protection Agency, and the Washington State Department of Ecology agreed that liquid effluent discharges to the ground on the Hanford Site which affects groundwater or has the potential to affect groundwater would be subject to permitting under the structure of Chapter 173-216 (or 173-218 where applicable) of the Washington Administrative Code, the State Waste Discharge Permit Program. This document constitutes the State Waste Discharge Permit application for the 400 Area Septic System. The influent to the system is domestic waste water. Although the 400 Area Septic System is not a Public Owned Treatment Works, the Public Owned Treatment Works application is more applicable than the application for industrial waste water. Therefore, the State Waste Discharge Permit application for Public Owned Treatment Works Discharges to Land was used.

  10. Civilian Radioactive Waste Management System Requirements Document...

    Office of Environmental Management (EM)

    Civilian Radioactive Waste Management System Requirements Document Civilian Radioactive Waste Management System Requirements Document This document specifies the top-level ...

  11. State Waste Discharge Permit Application: Electric resistance tomography testing

    SciTech Connect (OSTI)

    Not Available

    1994-04-01

    This permit application documentation is for a State Waste Discharge Permit issued in accordance with requirements of Washington Administrative Code 173-216. The activity being permitted is a technology test using electrical resistance tomography. The electrical resistance tomography technology was developed at Lawrence Livermore National Laboratory and has been used at other waste sites to track underground contamination plumes. The electrical resistance tomography technology measures soil electrical resistance between two electrodes. If a fluid contaminated with electrolytes is introduced into the soil, the soil resistance is expected to drop. By using an array of measurement electrodes in several boreholes, the areal extent of contamination can be estimated. At the Hanford Site, the purpose of the testing is to determine if the electrical resistance tomography technology can be used in the vicinity of large underground metal tanks without the metal tank interfering with the test. It is anticipated that the electrical resistance tomography technology will provide a method for accurately detecting leaks from the bottom of underground tanks, such as the Hanford Site single-shell tanks.

  12. Food waste management using an electrostatic separator with corona discharge

    SciTech Connect (OSTI)

    Lai, Koonchun; Teh, Pehchiong; Lim, Sooking

    2015-05-15

    In Malaysia, municipal solid waste contains a high portion of organic matters, typically contributed by food waste. It is estimated that about 45% of the municipal waste are food waste, followed by the non-food waste such as plastics, metals, glass and others. Food waste, while being properly sorted and contamination free from non-food waste, can be reused (e.g. fertiliser) instead of being landfilled. Therefore, recycling of food waste is crucial not only from the view point of waste management, but also with respect to the reduction of resource losses and greenhouse gases emission. A new waste separation process involved food particles, non-food particles and electrostatic discharge was investigated in this study. The empirical results reveal that the corona electrostatic separation is an environmental-friendly way in recovering foods from municipal waste. The efficiency of the separator, under same operating conditions, varies with the particle size of the food and non-food particles. The highest efficiency of 82% is recorded for the particle sizes between 1.5 and 3.0 mm.

  13. Technical requirements specification for tank waste retrieval

    SciTech Connect (OSTI)

    Lamberd, D.L.

    1996-09-26

    This document provides the technical requirements specification for the retrieval of waste from the underground storage tanks at the Hanford Site. All activities covered by this scope are conducted in support of the Tank Waste Remediation System (TWRS) mission.

  14. Low-Level Waste Requirements

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    1999-07-09

    The guide provides criteria for determining which DOE radioactive wastes are to be managed as low-level waste in accordance with DOE M 435.1-1, Chapter IV.

  15. High-Level Waste Requirements

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    1999-07-09

    The guide provides the criteria for determining which DOE radioactive wastes are to be managed as high-level waste in accordance with DOE M 435.1-1.

  16. Radioactive Liquid Waste Treatment Facility Discharges in 2011

    SciTech Connect (OSTI)

    Del Signore, John C.

    2012-05-16

    This report documents radioactive discharges from the TA50 Radioactive Liquid Waste Treatment Facilities (RLWTF) during calendar 2011. During 2011, three pathways were available for the discharge of treated water to the environment: discharge as water through NPDES Outfall 051 into Mortandad Canyon, evaporation via the TA50 cooling towers, and evaporation using the newly-installed natural-gas effluent evaporator at TA50. Only one of these pathways was used; all treated water (3,352,890 liters) was fed to the effluent evaporator. The quality of treated water was established by collecting a weekly grab sample of water being fed to the effluent evaporator. Forty weekly samples were collected; each was analyzed for gross alpha, gross beta, and tritium. Weekly samples were also composited at the end of each month. These flow-weighted composite samples were then analyzed for 37 radioisotopes: nine alpha-emitting isotopes, 27 beta emitters, and tritium. These monthly analyses were used to estimate the radioactive content of treated water fed to the effluent evaporator. Table 1 summarizes this information. The concentrations and quantities of radioactivity in Table 1 are for treated water fed to the evaporator. Amounts of radioactivity discharged to the environment through the evaporator stack were likely smaller since only entrained materials would exit via the evaporator stack.

  17. State waste discharge permit application 400 Area secondary cooling water. Revision 2

    SciTech Connect (OSTI)

    1996-01-01

    This document constitutes the Washington Administrative Code 173-216 State Waste Discharge Permit Application that serves as interim compliance as required by Consent Order DE 91NM-177, for the 400 Area Secondary Cooling Water stream. As part of the Hanford Federal Facility Agreement and Consent Order negotiations, the US Department of Energy, Richland Operations Office, the US Environmental Protection Agency, and the Washington State Department of Ecology agreed that liquid effluent discharges to the ground on the Hanford Site that affect groundwater or have the potential to affect groundwater would be subject to permitting under the structure of Chapter 173-216 of the Washington Administrative Code, the State Waste Discharge Permitting Program. As a result of this decision, the Washington State Department of Ecology and the US Department of Energy, Richland Operations Office entered into Consent Order DE 91NM-177. The Consent Order DE 91NM-177 requires a series of permitting activities for liquid effluent discharges. Based upon compositional and flow rate characteristics, liquid effluent streams on the Hanford Site have been categorized into Phase 1, Phase 2, and Miscellaneous streams. This document only addresses the 400 Area Secondary Cooling Water stream, which has been identified as a Phase 2 stream. The 400 Area Secondary Cooling Water stream includes contribution streams from the Fuels and Materials Examination Facility, the Maintenance and Storage Facility, the 481-A pump house, and the Fast Flux Test Facility.

  18. FY 1998 waste information requirements document

    SciTech Connect (OSTI)

    Poppiti, J.A.

    1997-09-05

    The Waste Information Requirements Document describes the activities of the Tank Waste Remediation System (TWRS) Characterization Project that provide characterization information on Hanford Site waste tanks. The characterization information is required to perform operations and meet the commitments of TWRS end users. These commitments are derived from the Hanford Federal Facility Agreement and Consent Order, also known as the Tri-Party Agreement; the Recommendation 93-5 Implementation Plan to the Defense Nuclear Facilities Safety Board (DNFSB); and other directives as listed in Section 4.0. This Waste Information Requirement Document applies to Fiscal Years 1997 and 1998 activities. Its contents are based on the best information available in August 1997. The format and content are based on the directions of DOE-RL (Sieracki, 1997) and Fluor Daniel Hanford Incorporated (Umek, 1997). Activities, such as the revision of the Tank Characterization Technical Sampling Basis (Brown et al. 1997), the revision of the data quality objectives (DQOs), issue closures, discussions with Ecology, and management decisions may cause subsequent updates to the Waste Information Requirements Document.

  19. Elimination of liquid discharge to the environment from the TA-50 Radioactive Liquid Waste Treatment Facility

    SciTech Connect (OSTI)

    Moss, D.; Williams, N.; Hall, D.; Hargis, K.; Saladen, M.; Sanders, M.; Voit, S.; Worland, P.; Yarbro, S.

    1998-06-01

    Alternatives were evaluated for management of treated radioactive liquid waste from the radioactive liquid waste treatment facility (RLWTF) at Los Alamos National Laboratory. The alternatives included continued discharge into Mortandad Canyon, diversion to the sanitary wastewater treatment facility and discharge of its effluent to Sandia Canyon or Canada del Buey, and zero liquid discharge. Implementation of a zero liquid discharge system is recommended in addition to two phases of upgrades currently under way. Three additional phases of upgrades to the present radioactive liquid waste system are proposed to accomplish zero liquid discharge. The first phase involves minimization of liquid waste generation, along with improved characterization and monitoring of the remaining liquid waste. The second phase removes dissolved salts from the reverse osmosis concentrate stream to yield a higher effluent quality. In the final phase, the high-quality effluent is reused for industrial purposes within the Laboratory or evaporated. Completion of these three phases will result in zero discharge of treated radioactive liquid wastewater from the RLWTF.

  20. Civilian Radioactive Waste Management System Requirements Document

    SciTech Connect (OSTI)

    C.A. Kouts

    2006-05-10

    The CRD addresses the requirements of Department of Energy (DOE) Order 413.3-Change 1, ''Program and Project Management for the Acquisition of Capital Assets'', by providing the Secretarial Acquisition Executive (Level 0) scope baseline and the Program-level (Level 1) technical baseline. The Secretarial Acquisition Executive approves the Office of Civilian Radioactive Waste Management's (OCRWM) critical decisions and changes against the Level 0 baseline; and in turn, the OCRWM Director approves all changes against the Level 1 baseline. This baseline establishes the top-level technical scope of the CRMWS and its three system elements, as described in section 1.3.2. The organizations responsible for design, development, and operation of system elements described in this document must therefore prepare subordinate project-level documents that are consistent with the CRD. Changes to requirements will be managed in accordance with established change and configuration control procedures. The CRD establishes requirements for the design, development, and operation of the CRWMS. It specifically addresses the top-level governing laws and regulations (e.g., ''Nuclear Waste Policy Act'' (NWPA), 10 Code of Federal Regulations (CFR) Part 63, 10 CFR Part 71, etc.) along with specific policy, performance requirements, interface requirements, and system architecture. The CRD shall be used as a vehicle to incorporate specific changes in technical scope or performance requirements that may have significant program implications. Such may include changes to the program mission, changes to operational capability, and high visibility stakeholder issues. The CRD uses a systems approach to: (1) identify key functions that the CRWMS must perform, (2) allocate top-level requirements derived from statutory, regulatory, and programmatic sources, and (3) define the basic elements of the system architecture and operational concept. Project-level documents address CRD requirements by further

  1. Technical Safety Requirements for the Waste Storage Facilities May 2014

    SciTech Connect (OSTI)

    Laycak, D. T.

    2014-04-16

    This document contains the Technical Safety Requirements (TSR) for the Radioactive and Hazardous Waste Management (RHWM) WASTE STORAGE FACILITIES, which include Area 625 (A625) and the Building 693 (B693) Yard Area of the Decontamination and Waste Treatment Facility (DWTF) at LLNL. The TSRs constitute requirements for safe operation of the WASTE STORAGE FACILITIES. These TSRs are derived from the Documented Safety Analyses for the Waste Storage Facilities (DSA) (LLNL 2011). The analysis presented therein concluded that the WASTE STORAGE FACILITIES are low-chemical hazard, Hazard Category 2 non-reactor nuclear facilities. The TSRs consist primarily of inventory limits and controls to preserve the underlying assumptions in the hazard and accident analyses. Further, appropriate commitments to safety programs are presented in the administrative controls sections of the TSRs. The WASTE STORAGE FACILITIES are used by RHWM to handle and store hazardous waste, TRANSURANIC (TRU) WASTE, LOW-LEVEL WASTE (LLW), mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL as well as small amounts of waste from other DOE facilities, as described in the DSA. In addition, several minor treatments (e.g., size reduction and decontamination) are carried out in these facilities.

  2. State Waste Discharge Permit ST-4502 Implementation Plan

    SciTech Connect (OSTI)

    BROWN, M.J.; LECLAIR, M.D.

    2000-09-27

    Plan has been developed to demonstrate compliance with regulatory requirements set forth in Permit ST-3502 and as a line management tool for use in maintaining configuration control of permit as well as documentation used to implement permit requirements.

  3. Fueling Requirements for Steady State high butane current fraction discharges

    SciTech Connect (OSTI)

    R.Raman

    2003-10-08

    The CT injector originally used for injecting CTs into 1T toroidal field discharges in the TdeV tokamak was shipped PPPL from the Affiliated Customs Brokers storage facility in Montreal during November 2002. All components were transported safely, without damage, and are currently in storage at PPPL, waiting for further funding in order to begin advanced fueling experiments on NSTX. The components are currently insured through the University of Washington. Several technical presentations were made to investigate the feasibility of the CT injector installation on NSTX. These technical presentations, attached to this document, were: (1) Motivation for Compact Toroida Injection in NSTX; (2) Assessment of the Engineering Feasibility of Installing CTF-II on NSTX; (3) Assessment of the Cost for CT Installation on NSTX--A Peer Review; and (4) CT Fueling for NSTX FY 04-08 steady-state operation needs.

  4. Functional requirements for Waste Area Grouping 6 Monitoring Station 3 upgrade

    SciTech Connect (OSTI)

    Fiuzat, A.A. )

    1991-06-01

    The surface Waste Area Grouping (WAG)6 at ORNL may undergo many changes in the future as part of the closure activities. Changes in surface characteristics will cause changes in runoff characteristics of the MS 3 watershed. Appropriate assumptions are to be made in this project regarding the future surface conditions of the watershed. The extent to which the assumed surface conditions will affect the project objectives (defined in Section 1.0) is to be identified. The purpose of this FRD is to establish performance requirements for MS 3 consisting of the following: (1) The expected range of discharges passing through the station and the required accuracy levels for discharge measurements. (2) The equipment required to measure the expected discharges at the required accuracy levels. (3) The sampling requirements for monitoring water quality. (4) The hydraulic requirements for the discharge conveyance structure to be located under the IWMF access road. (5) The design loads to be used for the bridge over the IWMF access road. 12 refs., 5 figs.

  5. Requirements for shipment of DOE radioactive mixed waste

    SciTech Connect (OSTI)

    Gablin, K.; No, Hyo; Herman, J.

    1993-08-01

    There are several sources of radioactive mixed waste (RMW) at Argonne National Laboratory which, in the past, were collected at waste tanks and/or sludge tanks. They were eventually pumped out by special pumps and processed in an evaporator located in the waste operations area in Building No. 306. Some of this radioactive mixed waste represents pure elementary mercury. These cleaning tanks must be manually cleaned up because the RMW material was too dense to pump with the equipment in use. The four tanks being discussed in this report are located in Building No. 306. They are the Acid Waste Tank, IMOX/FLOC Tanks, Evaporation Feed Tanks, and Waste Storage Tanks. All of these tanks are characterized and handled separately. This paper discusses the process and the requirements for characterization and the associated paperwork for Argonne Waste to be shipped to Westinghouse Hanford Company for storage.

  6. Solid Waste Information and Tracking System (SWITS) Software Requirements Specification

    SciTech Connect (OSTI)

    MAY, D.L.

    2000-03-22

    This document is the primary document establishing requirements for the Solid Waste Information and Tracking System (SWITS) as it is converted to a client-server architecture. The purpose is to provide the customer and the performing organizations with the requirements for the SWITS in the new environment. This Software Requirement Specification (SRS) describes the system requirements for the SWITS Project, and follows the PHMC Engineering Requirements, HNF-PRO-1819, and Computer Software Qualify Assurance Requirements, HNF-PRO-309, policies. This SRS includes sections on general description, specific requirements, references, appendices, and index. The SWITS system defined in this document stores information about the solid waste inventory on the Hanford site. Waste is tracked as it is generated, analyzed, shipped, stored, and treated. In addition to inventory reports a number of reports for regulatory agencies are produced.

  7. Mixed Waste Integrated Program Quality Assurance requirements plan

    SciTech Connect (OSTI)

    Not Available

    1994-04-15

    Mixed Waste Integrated Program (MWIP) is sponsored by the US Department of Energy (DOE), Office of Technology Development, Waste Management Division. The strategic objectives of MWIP are defined in the Mixed Waste Integrated Program Strategic Plan, and expanded upon in the MWIP Program Management Plan. This MWIP Quality Assurance Requirement Plan (QARP) applies to mixed waste treatment technologies involving both hazardous and radioactive constituents. As a DOE organization, MWIP is required to develop, implement, and maintain a written Quality Assurance Program in accordance with DOE Order 4700.1 Project Management System, DOE Order 5700.6C, Quality Assurance, DOE Order 5820.2A Radioactive Waste Management, ASME NQA-1 Quality Assurance Program Requirements for Nuclear Facilities and ANSI/ASQC E4-19xx Specifications and Guidelines for Quality Systems for Environmental Data Collection and Environmental Technology Programs. The purpose of the MWIP QA program is to establish controls which address the requirements in 5700.6C, with the intent to minimize risks and potential environmental impacts; and to maximize environmental protection, health, safety, reliability, and performance in all program activities. QA program controls are established to assure that each participating organization conducts its activities in a manner consistent with risks posed by those activities.

  8. System requirements specification for waste information and control system

    SciTech Connect (OSTI)

    Harris, R.R.

    1994-09-01

    This document defines the requirements for the Waste Information and Control System (WICS). The document defines the functions, constraints, and objectives that pertain to WICS. This shall serve as the baseline document to ensure the needs of the Hazardous Material Control group (HMC) at 222-S Laboratory are met with regard to assurance of accuracy and quality of data taken with WICS.

  9. Pennsylvania to require statewide recycling of solid wastes

    SciTech Connect (OSTI)

    Not Available

    1988-11-01

    The new law, requiring trash recycling in 407 communities affecting 7.8 million Pennsylvanians, is a key component of the Casey administration's comprehensive environmental clean up plant. The new recycling law requires municipalities with more than 10,000 residents to start curb-side recycling programs within two years. Communities with 5000 to 10,000 residents must start recycling in three years. The goal is to reduce the state's volume of solid waste by 25 percent by 1997. Nine million tons of trash are generated each year in Pennsylvania, with 95 percent of it landfilled and only one percent recycled. Much of the state's solid waste must be transported over increasing distances at increasing costs to be disposed of. Average trash disposal costs have increased 150 percent in the past three years. The new law requires communities to recycle three of eight materials, including glass, colored glass, aluminum, steel and bimetallic cans, high-grade office paper, newsprint, corrugated paper and plastics. All communities must recycle leaf waste. The legislation shifts responsibility for planning solid waste disposal from municipalities to counties, reimbursing counties 80 percent of the cost of developing comprehensive recycling plans and 50 percent of the cost of hiring a recycling coordinator. The program will be self-supporting through a $2-per-ton fee on all garbage going to landfills and resource recovery.

  10. Tank waste remediation system functions and requirements document

    SciTech Connect (OSTI)

    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.

  11. Remediation of DOE hazardous waste sites: Planning and integration requirements

    SciTech Connect (OSTI)

    Geffen, C.A.; Garrett, B.A.; Cowan, C.E.; Siegel, M.R.; Keller, J.F. )

    1989-09-01

    The US Department of Energy (DOE) is faced with a immense challenge in effectively implementing a program to mitigate and manage the environmental impacts created by current operations and from past activities at its facilities. The current regulatory framework and public interest in the environmental arena have made operating DOE facilities in an environmentally responsible manner a compelling priority. This paper provides information on the results of a project funded by DOE to obtain a better understanding of the regulatory and institutional drivers in the hazardous waste market and the costs and timeframes required for remediation activities. Few realize that before remediating a hazardous waste site, a comprehensive planning process must be conducted to characterize the nature and extent of site contamination, calculate the risk to the public, and assess the effectiveness of various remediation technologies. The US Environmental Protection Agency (EPA) and others have found that it may take up to 7 years to complete the planning process at an average cost of $1.0 million per site. While cost information is not yet available for DOE sites, discussions with hazardous waste consulting firms indicate that average characterization and assessment costs will be 5 to 10 times this amount for DOE sites. The higher costs are expected because of the additional administrative requirements placed on DOE sites, the need to handle mixed wastes, the amount and extent of contamination at many of these sites, and the visibility of the sites. 15 refs., 1 fig., 2 tabs.

  12. Supplemental design requirements document solid waste operations complex

    SciTech Connect (OSTI)

    Ocampo, V.P.; Boothe, G.F.; Broz, D.R.; Eaton, H.E.; Greager, T.M.; Huckfeldt, R.A.; Kooiker, S.L.; Lamberd, D.L.; Lang, L.L.; Myers, J.B.

    1994-11-01

    This document provides additional and supplemental information to the WHC-SD-W112-FDC-001, WHC-SD-W113-FDC-001, and WHC-SD-W100-FDC-001. It provides additional requirements for the design and summarizes Westinghouse Hanford Company key design guidance and establishes the technical baseline agreements to be used for definitive design common to the Solid Waste Operations Complex (SWOC) Facilities (Project W-112, Project W-113, and WRAP 2A).

  13. Waste disposal technology transfer matching requirement clusters for waste disposal facilities in China

    SciTech Connect (OSTI)

    Dorn, Thomas; Nelles, Michael; Flamme, Sabine; Jinming, Cai

    2012-11-15

    Highlights: Black-Right-Pointing-Pointer We outline the differences of Chinese MSW characteristics from Western MSW. Black-Right-Pointing-Pointer We model the requirements of four clusters of plant owner/operators in China. Black-Right-Pointing-Pointer We examine the best technology fit for these requirements via a matrix. Black-Right-Pointing-Pointer Variance in waste input affects result more than training and costs. Black-Right-Pointing-Pointer For China technology adaptation and localisation could become push, not pull factors. - Abstract: Even though technology transfer has been part of development aid programmes for many decades, it has more often than not failed to come to fruition. One reason is the absence of simple guidelines or decision making tools that help operators or plant owners to decide on the most suitable technology to adopt. Practical suggestions for choosing the most suitable technology to combat a specific problem are hard to get and technology drawbacks are not sufficiently highlighted. Western counterparts in technology transfer or development projects often underestimate or don't sufficiently account for the high investment costs for the imported incineration plant; the differing nature of Chinese MSW; the need for trained manpower; and the need to treat flue gas, bunker leakage water, and ash, all of which contain highly toxic elements. This article sets out requirements for municipal solid waste disposal plant owner/operators in China as well as giving an attribute assessment for the prevalent waste disposal plant types in order to assist individual decision makers in their evaluation process for what plant type might be most suitable in a given situation. There is no 'best' plant for all needs and purposes, and requirement constellations rely on generalisations meaning they cannot be blindly applied, but an alignment of a type of plant to a type of owner or operator can realistically be achieved. To this end, a four-step approach is

  14. U.A.C. R315-5: Hazardous Waste Generator Requirements | Open...

    Open Energy Info (EERE)

    5: Hazardous Waste Generator Requirements Jump to: navigation, search OpenEI Reference LibraryAdd to library Legal Document- RegulationRegulation: U.A.C. R315-5: Hazardous Waste...

  15. Contained recovery of oily waste

    DOE Patents [OSTI]

    Johnson, Jr., Lyle A.; Sudduth, Bruce C.

    1989-01-01

    A method is provided for recovering oily waste from oily waste accumulations underground comprising sweeping the oily waste accumulation with hot water to recover said oily waste, wherein said area treated is isolated from surrounding groundwater hydraulically. The hot water may be reinjected after the hot-water displacement or may be treated to conform to any discharge requirements.

  16. Conceptual Model of Uranium in the Vadose Zone for Acidic and Alkaline Wastes Discharged at the Hanford Site Central Plateau

    SciTech Connect (OSTI)

    Truex, Michael J.; Szecsody, James E.; Qafoku, Nikolla; Serne, R. Jeffrey

    2014-09-01

    Historically, uranium was disposed in waste solutions of varying waste chemistry at the Hanford Site Central Plateau. The character of how uranium was distributed in the vadose zone during disposal, how it has continued to migrate through the vadose zone, and the magnitude of potential impacts on groundwater are strongly influenced by geochemical reactions in the vadose zone. These geochemical reactions can be significantly influenced by the disposed-waste chemistry near the disposal location. This report provides conceptual models and supporting information to describe uranium fate and transport in the vadose zone for both acidic and alkaline wastes discharged at a substantial number of waste sites in the Hanford Site Central Plateau. The conceptual models include consideration of how co-disposed acidic or alkaline fluids influence uranium mobility in terms of induced dissolution/precipitation reactions and changes in uranium sorption with a focus on the conditions near the disposal site. This information, when combined with the extensive information describing uranium fate and transport at near background pH conditions, enables focused characterization to support effective fate and transport estimates for uranium in the subsurface.

  17. Design requirements document for project W-520, immobilized low-activity waste disposal

    SciTech Connect (OSTI)

    Ashworth, S.C.

    1998-08-06

    This design requirements document (DRD) identifies the functions that must be performed to accept, handle, and dispose of the immobilized low-activity waste (ILAW) produced by the Tank Waste Remediation System (TWRS) private treatment contractors and close the facility. It identifies the requirements that are associated with those functions and that must be met. The functional and performance requirements in this document provide the basis for the conceptual design of the Tank Waste Remediation System Immobilized Low-Activity Waste disposal facility project (W-520) and provides traceability from the program-level requirements to the project design activity.

  18. Classification methodology for tritiated waste requiring interim storage

    SciTech Connect (OSTI)

    Cana, D.; Dall'ava, D.

    2015-03-15

    Fusion machines like the ITER experimental research facility will use tritium as fuel. Therefore, most of the solid radioactive waste will result not only from activation by 14 MeV neutrons, but also from contamination by tritium. As a consequence, optimizing the treatment process for waste containing tritium (tritiated waste) is a major challenge. This paper summarizes the studies conducted in France within the framework of the French national plan for the management of radioactive materials and waste. The paper recommends a reference program for managing this waste based on its sorting, treatment and packaging by the producer. It also recommends setting up a 50-year temporary storage facility to allow for tritium decay and designing future disposal facilities using tritiated radwaste characteristics as input data. This paper first describes this waste program and then details an optimized classification methodology which takes into account tritium decay over a 50-year storage period. The paper also describes a specific application for purely tritiated waste and discusses the set-up expected to be implemented for ITER decommissioning waste (current assumption). Comparison between this optimized approach and other viable detritiation techniques will be drawn. (authors)

  19. Consequences of proposed changes to Clean Water Act thermal discharge requirements

    SciTech Connect (OSTI)

    Veil, J.A.; Moses, D.O.

    1995-12-31

    This paper summarizes three studies that examined the economic and environmental impact on the power industry of (1) limiting thermal mixing zones to 1,000 feet, and (2) eliminating the Clean Water Act (CWA) {section}316(1) variance. Both of these proposed changes were included in S. 1081, a 1991 Senate bill to reauthorize the CWA. The bill would not have provided for grandfathering plants already using the variance or mixing zones larger than 1000 feet. Each of the two changes to the existing thermal discharge requirements were independently evaluated. Power companies were asked what they would do if these two changes were imposed. Most plants affected by the proposed changes would retrofit cooling towers and some would retrofit diffusers. Assuming that all affected plants would proportionally follow the same options as the surveyed plants, the estimated capital cost of retrofitting cooling towers or diffusers at all affected plants ranges from $21.4 to 24.4 billion. Both cooling towers and diffusers exert a 1%-5.8% energy penalty on a plant`s output. Consequently, the power companies must generate additional power if they install those technologies. The estimated cost of the additional power ranges from $10 to 18.4 billion over 20 years. Generation of the extra power would emit over 8 million tons per year of additional carbon dioxide. Operation of the new cooling towers would cause more than 1.5 million gallons per minute of additional evaporation. Neither the restricted mixing zone size nor the elimination of the {section}316(1) variance was adopted into law. More recent proposed changes to the Clean Water Act have not included either of these provisions, but in the future, other Congresses might attempt to reintroduce these types of changes.

  20. Waste Receiving and Processing Facility Module 1 Data Management System Software Requirements Specification

    SciTech Connect (OSTI)

    Brann, E.C. II

    1994-09-09

    This document provides the software requirements for Waste Receiving and Processing (WRAP) Module 1 Data Management System (DMS). The DMS is one of the plant computer systems for the new WRAP 1 facility (Project W-026). The DMS will collect, store and report data required to certify the low level waste (LLW) and transuranic (TRU) waste items processed at WRAP 1 as acceptable for shipment, storage, or disposal.

  1. Conceptual waste package interim product specifications and data requirements for disposal of borosilicate glass defense high-level waste forms in salt geologic repositories

    SciTech Connect (OSTI)

    Not Available

    1983-06-01

    The conceptual waste package interim product specifications and data requirements presented are applicable specifically to the normal borosilicate glass product of the Defense Waste Processing Facility (DWPF). They provide preliminary numerical values for the defense high-level waste form parameters and properties identified in the waste form performance specification for geologic isolation in salt repositories. Subject areas treated include containment and isolation, operational period safety, criticality control, waste form/production canister identification, and waste package performance testing requirements. This document was generated for use in the development of conceptual waste package designs in salt. It will be revised as additional data, analyses, and regulatory requirements become available.

  2. Preliminary design requirements document for Project W-378, low-level waste vitrification plant

    SciTech Connect (OSTI)

    Swanson, L.M.

    1995-03-31

    The scope of this preliminary Design Requirements Document (DRD) is to identify and define the functions, with associated requirements, which must be performed to accomplish vitrification and disposal of the pretreated low-level waste (LLW) fraction of the Hanford Site tank waste. This document sets forth function requirements, performance requirements and design constraints necessary to begin conceptual design for the Low-Level Waste Vitrification Plant (LLWVP). System and physical interfaces between the LLWVP Project and the Tank Waste Remediation System (TWRS) are identified. The constraints, performance requirements, and transfer of information and data across a technical interface will be documented in an Interface Control Document. The design requirements provided in this document will be augmented by additional detailed design data to be documented by the project.

  3. Supplemental design requirements document, Multifunction Waste Tank Facility, Project W-236A. Revision 1

    SciTech Connect (OSTI)

    Groth, B.D.

    1995-01-11

    The Multi-Function Waste Tank Facility (MWTF) consists of four, nominal 1 million gallon, underground double-shell tanks, located in the 200-East area, and two tanks of the same capacity in the 200-West area. MWTF will provide environmentally safe storage capacity for wastes generated during remediation/retrieval activities of existing waste storage tanks. This document delineates in detail the information to be used for effective implementation of the Functional Design Criteria requirements.

  4. Critique of Hanford Waste Vitrification Plant off-gas sampling requirements

    SciTech Connect (OSTI)

    Goles, R.W.

    1996-03-01

    Off-gas sampling and monitoring activities needed to support operations safety, process control, waste form qualification, and environmental protection requirements of the Hanford Waste Vitrification Plant (HWVP) have been evaluated. The locations of necessary sampling sites have been identified on the basis of plant requirements, and the applicability of Defense Waste Processing Facility (DWPF) reference sampling equipment to these HWVP requirements has been assessed for all sampling sites. Equipment deficiencies, if present, have been described and the bases for modifications and/or alternative approaches have been developed.

  5. Reverse logistics network for municipal solid waste management: The inclusion of waste pickers as a Brazilian legal requirement

    SciTech Connect (OSTI)

    Ferri, Giovane Lopes; Diniz Chaves, Gisele de Lorena; Ribeiro, Glaydston Mattos

    2015-06-15

    Highlights: • We propose a reverse logistics network for MSW involving waste pickers. • A generic facility location mathematical model was validated in a Brazilian city. • The results enable to predict the capacity for screening and storage centres (SSC). • We minimise the costs for transporting MSW with screening and storage centres. • The use of SSC can be a potential source of revenue and a better use of MSW. - Abstract: This study proposes a reverse logistics network involved in the management of municipal solid waste (MSW) to solve the challenge of economically managing these wastes considering the recent legal requirements of the Brazilian Waste Management Policy. The feasibility of the allocation of MSW material recovery facilities (MRF) as intermediate points between the generators of these wastes and the options for reuse and disposal was evaluated, as well as the participation of associations and cooperatives of waste pickers. This network was mathematically modelled and validated through a scenario analysis of the municipality of São Mateus, which makes the location model more complete and applicable in practice. The mathematical model allows the determination of the number of facilities required for the reverse logistics network, their location, capacities, and product flows between these facilities. The fixed costs of installation and operation of the proposed MRF were balanced with the reduction of transport costs, allowing the inclusion of waste pickers to the reverse logistics network. The main contribution of this study lies in the proposition of a reverse logistics network for MSW simultaneously involving legal, environmental, economic and social criteria, which is a very complex goal. This study can guide practices in other countries that have realities similar to those in Brazil of accelerated urbanisation without adequate planning for solid waste management, added to the strong presence of waste pickers that, through the

  6. Design requirements document for Project W-465, immobilized low-activity waste interim storage

    SciTech Connect (OSTI)

    Burbank, D.A.

    1998-05-19

    The scope of this Design Requirements Document (DRD) is to identify the functions and associated requirements that must be performed to accept, transport, handle, and store immobilized low-activity waste (ILAW) produced by the privatized Tank Waste Remediation System (TWRS) treatment contractors. The functional and performance requirements in this document provide the basis for the conceptual design of the TWRS ILAW Interim Storage facility project and provides traceability from the program level requirements to the project design activity. Technical and programmatic risk associated with the TWRS planning basis are discussed in the Tank Waste Remediation System Decisions and Risk Assessment (Johnson 1994). The design requirements provided in this document will be augmented by additional detailed design data documented by the project.

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

    SciTech Connect (OSTI)

    ROOT, R.W.

    1999-05-18

    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.

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

    SciTech Connect (OSTI)

    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.

  9. Waste encapsulation storage facility (WESF) standards/requirements identification document (S/RIDS)

    SciTech Connect (OSTI)

    Maddox, B.S., Westinghouse Hanford

    1996-07-29

    This Standards/Requirements Identification Document (S/RID) sets forth the Environmental Safety and Health (ES{ampersand}H) standards/requirements for the Waste Encapsulation Storage Facility (WESF). This S/RID is applicable to the appropriate life cycle phases of design, construction, operation, and preparation for decommissioning. These standards/requirements are adequate to ensure the protection of the health and safety of workers, the public, and the environment.

  10. Habitat requirements and burrowing depths of rodents in relation to shallow waste burial sites

    SciTech Connect (OSTI)

    Gano, K.A.; States, J.B.

    1982-05-01

    The purpose of this paper is to provide a review of the literature and summarize information on factors affecting habitat selection and maximum recorded burrowing depths for representative small mammals that we consider most likely to inhibit waste burial sites in arid and semi-arid regions of the West. The information is intended for waste management designers who need to know what to expect from small mammals that may be present at a particular site. Waste repositories oculd be designed to exclude the deep burrowing rodents of a region by creating an unattractive habitat over the waste. Summaries are given for habitat requirements of each group along with generalized modifications that could be employed to deter habitation. Representatives from the major groups considered to be deep burrowers are discussed. Further, detailed information about a particular species can be obtained from the references cited.

  11. Supplemental design requirements document enhanced radioactive and mixed waste storage Phase V Project W-112

    SciTech Connect (OSTI)

    Ocampo, V.P.; Boothe, G.F.; Greager, T.M.; Johnson, K.D.; Kooiker, S.L.; Martin, J.D.

    1994-11-01

    This document provides additional and supplemental information to WHC-SD-W112-FDC-001, Project W-112 for radioactive and mixed waste storage. It provides additional requirements for the design and summarizes Westinghouse Hanford Company key design guidance and establishes the technical baseline agreements to be used for definitive design of the Project W-112 facilities.

  12. High level waste storage tank farms/242-A evaporator Standards/Requirements Identification Document (S/RID), Volume 6

    SciTech Connect (OSTI)

    Not Available

    1994-04-01

    The High-Level Waste Storage Tank Farms/242-A Evaporator Standards/Requirements Identification Document (S/RID) is contained in multiple volumes. This document (Volume 6) outlines the standards and requirements for the sections on: Environmental Restoration and Waste Management, Research and Development and Experimental Activities, and Nuclear Safety.

  13. Study on Shielding Requirements for Radioactive Waste Transportation in a Mo-99 Production Plant - 13382

    SciTech Connect (OSTI)

    Melo Rego, Maria Eugenia de; Kazumi Sakata, Solange; Vicente, Roberto; Hiromoto, Goro

    2013-07-01

    Brazil is currently planning to produce {sup 99}Mo from fission of low enriched uranium (LEU) targets. The planned end of irradiation activity of {sup 99}Mo is about 185 TBq (5 kCi) per week to meet the present domestic demand of {sup 99m}Tc generators. The radioactive wastes from the production plant will be transferred to a waste treatment facility at the same site. The total activity of the actinides, fission and activation products present in the wastes can be predicted based on the yields of fission and activation data for the irradiation conditions, such as composition and mass of uranium targets, irradiation time, neutron flux, production schedule, etc., which were in principle already established by the project management. The transportation of the wastes from the production plant to the treatment facility will be done by means of special shielded packages. An assessment of the shielding required for the packages has been done and the results are presented here, aiming at contributing to the design of the waste management facility for the {sup 99}Mo production plant. (authors)

  14. Disposal of LLW and ILW in Germany - Characterisation and Documentation of Waste Packages with Respect to the Change of Requirements

    SciTech Connect (OSTI)

    Bandt, G.; Spicher, G.; Steyer, St.; Brennecke, P.

    2008-07-01

    Since the 1998 termination of LLW and ILW emplacement in the Morsleben repository (ERAM), Germany, the treatment, conditioning and documentation of radioactive waste products and packages have been continued on the basis of the waste acceptance requirements as of 1995, prepared for the Konrad repository near Salzgitter in Lower Saxony, Germany. The resulting waste products and packages are stored in interim storage facilities. Due to the Konrad license issued in 2002 the waste acceptance requirements have to be completed by additional requirements imposed by the licensing authority, e. g. for the declaration of chemical waste package constituents. Therefore, documentation of waste products and packages which are checked by independent experts and are in parts approved by the responsible authority (Office for Radiation Protection, BfS) up to now will have to be checked again for fulfilling the final waste acceptance requirements prior to disposal. In order to simplify these additional checks, databases are used to ensure an easy access to all known facts about the waste packages. A short balance of the existing waste products and packages which are already checked and partly approved by BfS as well as an overview on the established databases ensuring a fast access to the known facts about the conditioning processes is presented. (authors)

  15. METHODS FOR DETERMINING AGITATOR MIXING REQUIREMENTS FOR A MIXING & SAMPLING FACILITY TO FEED WTP (WASTE TREATMENT PLANT)

    SciTech Connect (OSTI)

    GRIFFIN PW

    2009-08-27

    The following report is a summary of work conducted to evaluate the ability of existing correlative techniques and alternative methods to accurately estimate impeller speed and power requirements for mechanical mixers proposed for use in a mixing and sampling facility (MSF). The proposed facility would accept high level waste sludges from Hanford double-shell tanks and feed uniformly mixed high level waste to the Waste Treatment Plant. Numerous methods are evaluated and discussed, and resulting recommendations provided.

  16. Alternatives generation and analysis for the Phase I intermediate waste feed staging system design requirements

    SciTech Connect (OSTI)

    Claghorn, R.D., Fluor Daniel Hanford

    1997-02-06

    This alternatives generation and analysis (AGA) addresses the question: What is the design basis for the facilities required to stage low-level waste (LLW) feed to the Phase I private contractors? Alternative designs for the intermediate waste feed staging system were developed, analyzed, and compared. Based on these analyses, this document recommends installing mixer pumps in the central pump pit of double-shell tanks 241-AP-102 and 241-AP-104. Also recommended is installing decant/transfer pumps at these tanks. These recommendations have clear advantages in that they provide a low shedule impact/risk and the highest operability of all the alternatives investigated. This revision incorporates comments from the decision board.

  17. FY2001 Tank Characterization Technical Sampling Basis & Waste Information Requirements Document

    SciTech Connect (OSTI)

    ADAMS, M.R.

    2000-08-02

    The Fiscal Year 2001 Tank Characterization Technical Sampling Basis and Waste Information Requirements Document (TSB-WIRD) has the following purposes: (1) To identify and integrate sampling and analysis needs for fiscal year (FY) 2001 and beyond. (2) To describe the overall drivers that require characterization information and to document their source. (3) To describe the process for identifying, prioritizing, and weighting issues that require characterization information to resolve. (4) To define the method for determining sampling priorities and to present the sampling priorities on a tank-by-tank basis. (5) To define how the characterization program is going to satisfy the drivers, close issues, and report progress. (6)To describe deliverables and acceptance criteria for characterization deliverables.

  18. Development of a computer code to predict a ventilation requirement for an underground radioactive waste storage tank

    SciTech Connect (OSTI)

    Lee, Y.J.; Dalpiaz, E.L.

    1997-08-01

    Computer code, WTVFE (Waste Tank Ventilation Flow Evaluation), has been developed to evaluate the ventilation requirement for an underground storage tank for radioactive waste. Heat generated by the radioactive waste and mixing pumps in the tank is removed mainly through the ventilation system. The heat removal process by the ventilation system includes the evaporation of water from the waste and the heat transfer by natural convection from the waste surface. Also, a portion of the heat will be removed through the soil and the air circulating through the gap between the primary and secondary tanks. The heat loss caused by evaporation is modeled based on recent evaporation test results by the Westinghouse Hanford Company using a simulated small scale waste tank. Other heat transfer phenomena are evaluated based on well established conduction and convection heat transfer relationships. 10 refs., 3 tabs.

  19. Load requirements for maintaining structural integrity of Hanford single-shell tanks during waste feed delivery and retrieval activities

    SciTech Connect (OSTI)

    JULYK, L.J.

    1999-09-22

    This document provides structural load requirements and their basis for maintaining the structural integrity of the Hanford Single-Shell Tanks during waste feed delivery and retrieval activities. The requirements are based on a review of previous requirements and their basis documents as well as load histories with particular emphasis on the proposed lead transfer feed tanks for the privatized vitrification plant.

  20. SEISMIC DESIGN REQUIREMENTS SELECTION METHODOLOGY FOR THE SLUDGE TREATMENT & M-91 SOLID WASTE PROCESSING FACILITIES PROJECTS

    SciTech Connect (OSTI)

    RYAN GW

    2008-04-25

    In complying with direction from the U.S. Department of Energy (DOE), Richland Operations Office (RL) (07-KBC-0055, 'Direction Associated with Implementation of DOE-STD-1189 for the Sludge Treatment Project,' and 08-SED-0063, 'RL Action on the Safety Design Strategy (SDS) for Obtaining Additional Solid Waste Processing Capabilities (M-91 Project) and Use of Draft DOE-STD-I 189-YR'), it has been determined that the seismic design requirements currently in the Project Hanford Management Contract (PHMC) will be modified by DOE-STD-1189, Integration of Safety into the Design Process (March 2007 draft), for these two key PHMC projects. Seismic design requirements for other PHMC facilities and projects will remain unchanged. Considering the current early Critical Decision (CD) phases of both the Sludge Treatment Project (STP) and the Solid Waste Processing Facilities (M-91) Project and a strong intent to avoid potentially costly re-work of both engineering and nuclear safety analyses, this document describes how Fluor Hanford, Inc. (FH) will maintain compliance with the PHMC by considering both the current seismic standards referenced by DOE 0 420.1 B, Facility Safety, and draft DOE-STD-1189 (i.e., ASCE/SEI 43-05, Seismic Design Criteria for Structures, Systems, and Components in Nuclear Facilities, and ANSI!ANS 2.26-2004, Categorization of Nuclear Facility Structures, Systems and Components for Seismic Design, as modified by draft DOE-STD-1189) to choose the criteria that will result in the most conservative seismic design categorization and engineering design. Following the process described in this document will result in a conservative seismic design categorization and design products. This approach is expected to resolve discrepancies between the existing and new requirements and reduce the risk that project designs and analyses will require revision when the draft DOE-STD-1189 is finalized.

  1. Microsoft Word - Groundwater Discharge Permit

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    State Renews Groundwater Discharge Permit for WIPP CARLSBAD, N.M., September 11, 2008 - The New Mexico Environment Department (NMED) has renewed the U.S. Department of Energy's (DOE) Waste Isolation Pilot Plant (WIPP) groundwater discharge permit until 2013. The permit regulates the discharge of water from WIPP facilities and operations to lined ponds, which protect groundwater resources. The permit allows WIPP to discharge domestic wastewater, non-hazardous wastewater and storm water into 13

  2. Greater-than-Class C low-level radioactive waste shipping package/container identification and requirements study. National Low-Level Waste Management Program

    SciTech Connect (OSTI)

    Tyacke, M.

    1993-08-01

    This report identifies a variety of shipping packages (also referred to as casks) and waste containers currently available or being developed that could be used for greater-than-Class C (GTCC) low-level waste (LLW). Since GTCC LLW varies greatly in size, shape, and activity levels, the casks and waste containers that could be used range in size from small, to accommodate a single sealed radiation source, to very large-capacity casks/canisters used to transport or dry-store highly radioactive spent fuel. In some cases, the waste containers may serve directly as shipping packages, while in other cases, the containers would need to be placed in a transport cask. For the purpose of this report, it is assumed that the generator is responsible for transporting the waste to a Department of Energy (DOE) storage, treatment, or disposal facility. Unless DOE establishes specific acceptance criteria, the receiving facility would need the capability to accept any of the casks and waste containers identified in this report. In identifying potential casks and waste containers, no consideration was given to their adequacy relative to handling, storage, treatment, and disposal. Those considerations must be addressed separately as the capabilities of the receiving facility and the handling requirements and operations are better understood.

  3. Standard for Communicating Waste Characterization and DOT Hazard Classification Requirements for Low Specific Activity Materials and Surface Contaminated Objects

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    STD-5507-2013 February 2013 DOE STANDARD Standard for Communicating Waste Characterization and DOT Hazard Classification Requirements for Low Specific Activity Materials and Surface Contaminated Objects [This Standard describes acceptable, but not mandatory means for complying with requirements. Standards are not requirements documents and are not to be construed as requirements in any audit or appraisal for compliance with associated rule or directives.] U.S. Department of Energy SAFT

  4. High-level waste storage tank farms/242-A evaporator Standards/Requirements Identification Document (S/RID), Volume 5

    SciTech Connect (OSTI)

    Not Available

    1994-04-01

    The High-Level Waste Storage Tank Farms/242-A Evaporator Standards/Requirements Identification Document (S/RID) is contained in multiple volumes. This document (Volume 5) outlines the standards and requirements for the Fire Protection and Packaging and Transportation sections.

  5. High-level waste storage tank farms/242-A evaporator Standards/Requirements Identification Document (S/RID), Volume 4

    SciTech Connect (OSTI)

    Not Available

    1994-04-01

    The High-Level Waste Storage Tank Farms/242-A Evaporator Standards/Requirements Identification Document (S/RID) is contained in multiple volumes. This document (Volume 4) presents the standards and requirements for the following sections: Radiation Protection and Operations.

  6. DISPOSAL OF TRU WASTE FROM THE PLUTONIUM FINISHING PLANT IN PIPE OVERPACK CONTAINERS TO WIPP INCLUDING NEW SECURITY REQUIREMENTS

    SciTech Connect (OSTI)

    Hopkins, A.M.; Sutter, C.; Hulse, G.; Teal, J.

    2003-02-27

    The Department of Energy is responsible for the safe management and cleanup of the DOE complex. As part of the cleanup and closure of the Plutonium Finishing Plant (PFP) located on the Hanford site, the nuclear material inventory was reviewed to determine the appropriate disposition path. Based on the nuclear material characteristics, the material was designated for stabilization and packaging for long term storage and transfer to the Savannah River Site or, a decision for discard was made. The discarded material was designated as waste material and slated for disposal to the Waste Isolation Pilot Plant (WIPP). Prior to preparing any residue wastes for disposal at the WIPP, several major activities need to be completed. As detailed a processing history as possible of the material including origin of the waste must be researched and documented. A technical basis for termination of safeguards on the material must be prepared and approved. Utilizing process knowledge and processing history, the material must be characterized, sampling requirements determined, acceptable knowledge package and waste designation completed prior to disposal. All of these activities involve several organizations including the contractor, DOE, state representatives and other regulators such as EPA. At PFP, a process has been developed for meeting the many, varied requirements and successfully used to prepare several residue waste streams including Rocky Flats incinerator ash, Hanford incinerator ash and Sand, Slag and Crucible (SS&C) material for disposal. These waste residues are packed into Pipe Overpack Containers for shipment to the WIPP.

  7. Fractured rock modeling in the National Waste Terminal Storage Program: a review of requirements and status

    SciTech Connect (OSTI)

    St. John, C.; Krug, A.; Key, S.; Monsees, J.

    1983-05-01

    Generalized computer codes capable of forming the basis for numerical models of fractured rock masses are being used within the NWTS program. Little additional development of these codes is considered justifiable, except in the area of representation of discrete fractures. On the other hand, model preparation requires definition of medium-specific constitutive descriptions and site characteristics and is therefore legitimately conducted by each of the media-oriented projects within the National Waste Terminal Storage program. However, it is essential that a uniform approach to the role of numerical modeling be adopted, including agreement upon the contribution of modeling to the design and licensing process and the need for, and means of, model qualification for particular purposes. This report discusses the role of numerical modeling, reviews the capabilities of several computer codes that are being used to support design or performance assessment, and proposes a framework for future numerical modeling activities within the NWTS program.

  8. Supplemental design requirements document enhanced radioactive and mixed waste storage: Phase 5, Project W-113

    SciTech Connect (OSTI)

    Ocampo, V.P.

    1994-11-01

    This Supplemental Design Requirements Document (SDRD) is used to communicate Project W-113 specific plant design information from Westinghouse Hanford Company (WHC) to the United States Department of Energy (DOE) and the cognizant Architect Engineer (A/E). The SDRD is prepared after the completion of the project Conceptual Design report (CDR) and prior to the initiation of definitive design. Information in the SDRD serves two purposes: to convey design requirements that are too detailed for inclusion in the Functional Design Criteria (FDC) report and to serve as a means of change control for design commitments in the Title I and Title II design. The Solid Waste Retrieval Project (W-113) SDRD has been restructured from the equipment based outline used in previous SDRDs to a functional systems outline. This was done to facilitate identification of deficiencies in the information provided in the initial draft SDRD and aid design confirmation. The format and content of this SDRD adhere as closely as practicable to the requirements of WHC-CM-6-1, Standard Engineering Practices for Functional Design Criteria.

  9. 1997 annual report on waste generation and waste minimization progress as required by DOE Order 5400.1, Hanford Site

    SciTech Connect (OSTI)

    Segall, P.

    1998-04-13

    Hanford`s missions are to safely clean up and manage the site`s legacy wastes, and to develop and deploy science and technology. Through these missions Hanford will contribute to economic diversification of the region. Hanford`s environmental management or cleanup mission is to protect the health and safety of the public, workers, and the environment; control hazardous materials; and utilize the assets (people, infra structure, site) for other missions. Hanford`s science and technology mission is to develop and deploy science and technology in the service of the nation including stewardship of the Hanford Site. Pollution Prevention is a key to the success of these missions by reducing the amount of waste to be managed and identifying/implementing cost effective waste reduction projects. Hanford`s original mission, the production of nuclear materials for the nation`s defense programs, lasted more than 40 years, and like most manufacturing operations, Hanford`s operations generated large quantities of waste and pollution. However, the by-products from Hanford operations pose unique problems like radiation hazards, vast volumes of contaminated water and soil, and many contaminated structures including reactors, chemical plants and evaporation ponds. The cleanup activity is an immense and challenging undertaking, which includes characterization and decommissioning of 149 single shell storage tanks, treating 28 double shell tanks, safely disposing of over 2,100 metric tons of spent nuclear fuel stored on site, removing numerous structures, and dealing with significant solid waste, ground water, and land restoration issues.

  10. Application of value of information of tank waste characterization: A new paradigm for defining tank waste characterization requirements

    SciTech Connect (OSTI)

    Fassbender, L.L.; Brewster, M.E.; Brothers, A.J.

    1996-11-01

    This report presents the rationale for adopting a recommended characterization strategy that uses a risk-based decision-making framework for managing the Tank Waste Characterization program at Hanford. The risk-management/value-of-information (VOI) strategy that is illustrated explicitly links each information-gathering activity to its cost and provides a mechanism to ensure that characterization funds are spent where they can produce the largest reduction in risk. The approach was developed by tailoring well-known decision analysis techniques to specific tank waste characterization applications. This report illustrates how VOI calculations are performed and demonstrates that the VOI approach can definitely be used for real Tank Waste Remediation System (TWRS) characterization problems.

  11. Comparison of selected DOE and non-DOE requirements, standards, and practices for Low-Level Radioactive Waste Disposal

    SciTech Connect (OSTI)

    Cole, L.; Kudera, D.; Newberry, W.

    1995-12-01

    This document results from the Secretary of Energy`s response to Defense Nuclear Facilities Safety Board Recommendation 94--2. The Secretary stated that the US Department of Energy (DOE) would ``address such issues as...the need for additional requirements, standards, and guidance on low-level radioactive waste management. `` The authors gathered information and compared DOE requirements and standards for the safety aspects Of low-level disposal with similar requirements and standards of non-DOE entities.

  12. Characteristics of spent fuel, high-level waste, and other radioactive wastes which may require long-term isolation

    SciTech Connect (OSTI)

    1988-06-01

    The purpose of this report, and the information contained in the associated computerized data bases, is to establish the DOE/OCRWM reference characteristics of the radioactive waste materials that may be accepted by DOE for emplacement in the mined geologic disposal system as developed under the Nuclear Waste Policy Act of 1982. This report provides relevant technical data for use by DOE and its supporting contractors and is not intended to be a policy document. This document is backed up by five PC-compatible data bases, written in a user-oriented, menu-driven format, which were developed for this purpose.

  13. NWTS program criteria for mined geologic disposal of nuclear waste: program objectives, functional requirements, and system performance criteria

    SciTech Connect (OSTI)

    1981-04-01

    At the present time, final repository criteria have not been issued by the responsible agencies. This document describes general objectives, requirements, and criteria that the DOE intends to apply in the interim to the National Waste Terminal Storage (NWTS) Program. These objectives, requirements, and criteria have been developed on the basis of DOE's analysis of what is needed to achieve the National objective of safe waste disposal in an environmentally acceptable and economic manner and are expected to be consistent with anticipated regulatory standards. The qualitative statements in this document address the broad issues of public and occupational health and safety, institutional acceptability, engineering feasibility, and economic considerations. A comprehensive set of criteria, general and project specific, of which these are a part, will constitute a portion of the technical basis for preparation and submittal by the DOE of formal documents to support future license applications for nuclear waste repositories.

  14. Management of offshore wastes in the United States.

    SciTech Connect (OSTI)

    Veil, J. A.

    1998-10-22

    During the process of finding and producing oil and gas in the offshore environment operators generate a variety of liquid and solid wastes. Some of these wastes are directly related to exploration and production activities (e.g., drilling wastes, produced water, treatment workover, and completion fluids) while other types of wastes are associated with human occupation of the offshore platforms (e.g., sanitary and domestic wastes, trash). Still other types of wastes can be considered generic industrial wastes (e.g., scrap metal and wood, wastes paints and chemicals, sand blasting residues). Finally, the offshore platforms themselves can be considered waste materials when their useful life span has been reached. Generally, offshore wastes are managed in one of three ways--onsite discharge, injection, or transportation to shore. This paper describes the regulatory requirements imposed by the government and the approaches used by offshore operators to manage and dispose of wastes in the US.

  15. Greater-than-Class C low-level radioactive waste transportation regulations and requirements study. National Low-Level Waste Management Program

    SciTech Connect (OSTI)

    Tyacke, M.; Schmitt, R.

    1993-07-01

    The purpose of this report is to identify the regulations and requirements for transporting greater-than-Class C (GTCC) low-level radioactive waste (LLW) and to identify planning activities that need to be accomplished in preparation for transporting GTCC LLW. The regulations and requirements for transporting hazardous materials, of which GTCC LLW is included, are complex and include several Federal agencies, state and local governments, and Indian tribes. This report is divided into five sections and three appendices. Section 1 introduces the report. Section 2 identifies and discusses the transportation regulations and requirements. The regulations and requirements are divided into Federal, state, local government, and Indian tribes subsections. This report does not identify the regulations or requirements of specific state, local government, and Indian tribes, since the storage, treatment, and disposal facility locations and transportation routes have not been specifically identified. Section 3 identifies the planning needed to ensure that all transportation activities are in compliance with the regulations and requirements. It is divided into (a) transportation packaging; (b) transportation operations; (c) system safety and risk analysis, (d) route selection; (e) emergency preparedness and response; and (f) safeguards and security. This section does not provide actual planning since the details of the Department of Energy (DOE) GTCC LLW Program have not been finalized, e.g., waste characterization and quantity, storage, treatment and disposal facility locations, and acceptance criteria. Sections 4 and 5 provide conclusions and referenced documents, respectively.

  16. Characteristics of spent fuel, high-level waste, and other radioactive wastes which may require long-term isolation

    SciTech Connect (OSTI)

    1987-12-01

    The purpose of this report, and the information contained in the associated computerized data bases, is to establish the DOE/OCRWM reference characteristics of the radioactive waste materials that may be accepted by DOE for emplacement in the mined geologic disposal system. This report provides relevant technical data for use by DOE and its supporting contractors and is not intended to be a policy document. This document is backed up by five PC-compatible data bases, written in a user-oriented, menu-driven format, which were developed for this purpose. The data bases are the LWR Assemblies Data Base; the LWR Radiological Data Base; the LWR Quantities Data Base; the LWR NFA Hardware Data Base; and the High-Level Waste Data Base. The above data bases may be ordered using the included form. An introductory information diskette can be found inside the back cover of this report. It provides a brief introduction to each of these five PC data bases. 116 refs., 18 figs., 67 tabs.

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

    SciTech Connect (OSTI)

    Hall, C.E.

    1998-01-06

    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).

  18. Waste water filtration enhancement

    SciTech Connect (OSTI)

    Martin, H.L.

    1989-01-01

    Removal of submicron particles from process solutions and waste water is now economically achievable using a new Tyvek{reg sign} media in conventional filtration equipment. This new product greatly enhances filtration and allows use of the much improved filter aids and polymers which were recently developed. It has reduced operating costs and ensures a clean effluent discharge to the environment. This significant technical development is especially important to those who discharge to a small stream with low 7Q10 flow and must soon routinely pass the Toxicity tests that are being required by many States for NPDES permit renewal. The Savannah River Plant produces special nuclear materials for the US Government. Aluminum forming and metal finishing operations in M-Area, that manufacture fuel and target assemblies for the nuclear reactors, discharge to a waste water treatment facility using BAT hydroxide precipitation and filtration. The new Tyvek{reg sign} media and filter aids have achieved 55% less solids in the filtrate discharged to Tims Branch Creek, 15% less hazardous waste (dry filter cake), 150%-370% more filtration capacity, 74% lower materials purchase cost, 10% lower total M-Area manufacturing cost, and have improved safety. Performance with the improved polymers is now being evaluated.

  19. Assessment of economic impact of offshore and coastal discharge requirements on present and future operations in the Gulf of Mexico. Final report

    SciTech Connect (OSTI)

    Lindsey, R.

    1996-06-01

    The high potential costs of compliance associated with new effluent guidelines for offshore and coastal oil and gas operations could significantly affect the economics of finding, developing, and producing oil and gas in the Gulf of Mexico. This report characterizes the potential economic impacts of alternative treatment and discharge regulations for produced water on reserves and production in Gulf of Mexico coastal, territorial and outer continental shelf (OCS) waters, quantifying the impacts of both recent regulatory changes and possible more stringent requirements. The treatment technologies capable of meeting these requirements are characterized in terms of cost, performance, and applicability to coastal and offshore situations. As part of this analysis, an extensive database was constructed that includes oil and gas production forecasts by field, data on existing platforms, and the current treatment methods in place for produced water treatment and disposal on offshore facilities. This work provides the first comprehensive evaluation of the impacts of alternative regulatory requirements for produced water management and disposal in coastal and offshore areas of the Gulf of Mexico.

  20. HOLLOW CARBON ARC DISCHARGE

    DOE Patents [OSTI]

    Luce, J.S.

    1960-10-11

    A device is described for producing an energetic, direct current, hollow, carbon-arc discharge in an evacuated container and within a strong magnetic field. Such discharges are particularly useful not only in dissociation and ionization of high energy molecular ion beams, but also in acting as a shield or barrier against the instreaming of lowenergy neutral particles into a plasma formed within the hollow discharge when it is used as a dissociating mechanism for forming the plasma. There is maintained a predetermined ratio of gas particles to carbon particles released from the arc electrodes during operation of the discharge. The carbon particles absorb some of the gas particles and are pumped along and by the discharge out of the device, with the result that smaller diffusion pumps are required than would otherwise be necessary to dispose of the excess gas.

  1. Characterization of Tank 23H Supernate Per Saltstone Waste Acceptance Criteria Analysis Requirements -2005

    SciTech Connect (OSTI)

    Oji, L

    2005-05-05

    Variable depth Tank 23H samples (22-inch sample [HTF-014] and 185-inch sample [HTF-013]) were pulled from Tank 23H in February, 2005 for characterization. The characterization of the Tank 23H low activity waste is part of the overall liquid waste processing activities. This characterization examined the species identified in the Saltstone Waste Acceptance Criteria (WAC) for the transfer of waste into the Salt-Feed Tank (SFT). The samples were delivered to the Savannah River National Laboratory (SRNL) and analyzed. Apart from radium-226 with an average measured detection limit of < 2.64E+03 pCi/mL, which is about the same order of magnitude as the WAC limit (< 8.73E+03 pCi/mL), none of the species analyzed was found to approach the limits provided in the Saltstone WAC. The concentration of most of the species analyzed for the Tank 23H samples were 2-5 orders of magnitude lower than the WAC limits. The achievable detection limits for a number of the analytes were several orders of magnitude lower than the WAC limits, but one or two orders of magnitude higher than the requested detection limits. Analytes which fell into this category included plutonium-241, europium-154/155, antimony-125, tin-126, ruthenium/rhodium-106, selenium-79, nickel-59/63, ammonium ion, copper, total nickel, manganese and total organic carbon.

  2. Characterization of Tank 23H Supernate Per Saltstone Waste Acceptance Criteria Analysis Requirements-2005

    SciTech Connect (OSTI)

    Oji, L

    2005-06-01

    Variable depth Tank 23H samples (22-inch sample [HTF-014] and 185-inch sample [HTF-013]) were pulled from Tank 23H in February, 2005 for characterization. The characterization of the Tank 23H low activity waste is part of the overall liquid waste processing activities. This characterization examined the species identified in the Saltstone Waste Acceptance Criteria (WAC) for the transfer of waste into the Salt-Feed Tank (SFT). The samples were delivered to the Savannah River National Laboratory (SRNL) and analyzed. Apart from radium-226 with an average measured detection limit of < 2.64E+03 pCi/mL, which is about the same order of magnitude as the WAC limit (< 8.73E+03 pCi/mL), none of the species analyzed was found to approach the limits provided in the Saltstone WAC. The concentration of most of the species analyzed for the Tank 23H samples were 2-5 orders of magnitude lower than the WAC limits. The achievable detection limits for a number of the analytes were several orders of magnitude lower than the WAC limits, but one or two orders of magnitude higher than the requested detection limits. Analytes which fell into this category included plutonium-241, europium-154/155, antimony-125, tin-126, ruthenium/rhodium-106, selenium-79, nickel-59/63, ammonium ion, copper, total nickel, manganese and total organic carbon.

  3. HLW Glass Waste Loadings

    Office of Environmental Management (EM)

    HLW Glass Waste Loadings Ian L. Pegg Vitreous State Laboratory The Catholic University of ... (JHCM) technology Factors affecting waste loadings Waste loading requirements ...

  4. High level waste storage tanks 242-A evaporator standards/requirement identification document

    SciTech Connect (OSTI)

    Biebesheimer, E.

    1996-01-01

    This document, the Standards/Requirements Identification Document (S/RIDS) for the subject facility, represents the necessary and sufficient requirements to provide an adequate level of protection of the worker, public health and safety, and the environment. It lists those source documents from which requirements were extracted, and those requirements documents considered, but from which no requirements where taken. Documents considered as source documents included State and Federal Regulations, DOE Orders, and DOE Standards

  5. 2013 Radiological Monitoring Results Associated with the Advanced Test Reactor Complex Cold Waste Pond

    SciTech Connect (OSTI)

    Mike Lewis

    2014-02-01

    This report summarizes radiological monitoring performed of the Idaho National Laboratory Site’s Advanced Test Reactor Complex Cold Waste wastewater prior to discharge into the Cold Waste Pond and of specific groundwater monitoring wells associated with the Industrial Wastewater Reuse Permit (#LA-000161-01, Modification B). All radiological monitoring is performed to fulfill Department of Energy requirements under the Atomic Energy Act.

  6. 2011 Radiological Monitoring Results Associated with the Advanced Test Reactor Complex Cold Waste Pond

    SciTech Connect (OSTI)

    Mike Lewis

    2012-02-01

    This report summarizes radiological monitoring performed of the Idaho National Laboratory Site's Advanced Test Reactor Complex Cold Waste wastewater prior to discharge into the Cold Waste Pond and of specific groundwater monitoring wells associated with the Industrial Wastewater Reuse Permit (LA-000161-01, Modification B). All radiological monitoring is performed to fulfill Department of Energy requirements under the Atomic Energy Act.

  7. 2010 Radiological Monitoring Results Associated with the Advance Test Reactor Complex Cold Waste Pond

    SciTech Connect (OSTI)

    mike lewis

    2011-02-01

    This report summarizes radiological monitoring performed of the Idaho National Laboratory Site’s Advanced Test Reactor Complex Cold Waste wastewater prior to discharge into the Cold Waste Pond and of specific groundwater monitoring wells associated with the Industrial Wastewater Reuse Permit (#LA-000161-01, Modification B). All radiological monitoring is performed to fulfill Department of Energy requirements under the Atomic Energy Act.

  8. 2012 Radiological Monitoring Results Associated with the Advanced Test Reactor Complex Cold Waste Pond

    SciTech Connect (OSTI)

    Mike Lewis

    2013-02-01

    This report summarizes radiological monitoring performed of the Idaho National Laboratory Site’s Advanced Test Reactor Complex Cold Waste wastewater prior to discharge into the Cold Waste Pond and of specific groundwater monitoring wells associated with the Industrial Wastewater Reuse Permit (#LA-000161-01, Modification B). All radiological monitoring is performed to fulfill Department of Energy requirements under the Atomic Energy Act.

  9. 2014 Radiological Monitoring Results Associated with the Advanced Test Reactor Complex Cold Waste Pond

    SciTech Connect (OSTI)

    Lewis, Mike

    2015-02-01

    This report summarizes radiological monitoring performed of the Idaho National Laboratory Site’s Advanced Test Reactor Complex Cold Waste wastewater prior to discharge into the Cold Waste Pond and of specific groundwater monitoring wells associated with the Industrial Wastewater Reuse Permit (#LA-000161-01, Modification B). All radiological monitoring is performed to fulfill Department of Energy requirements under the Atomic Energy Act.

  10. High-level waste storage tank farms/242-A evaporator standards/requirements identification document (S/RID), Vol. 7

    SciTech Connect (OSTI)

    Not Available

    1994-04-01

    This Requirements Identification Document (RID) describes an Occupational Health and Safety Program as defined through the Relevant DOE Orders, regulations, industry codes/standards, industry guidance documents and, as appropriate, good industry practice. The definition of an Occupational Health and Safety Program as specified by this document is intended to address Defense Nuclear Facilities Safety Board Recommendations 90-2 and 91-1, which call for the strengthening of DOE complex activities through the identification and application of relevant standards which supplement or exceed requirements mandated by DOE Orders. This RID applies to the activities, personnel, structures, systems, components, and programs involved in maintaining the facility and executing the mission of the High-Level Waste Storage Tank Farms.

  11. WAC - 173-216 State Wastewater Discharge Permit Program | Open...

    Open Energy Info (EERE)

    Abstract These rules implement a state permit program, applicable to the discharge of waste materials from industrial, commercial, and municipal operations into ground and...

  12. A review of Title V operating permit application requirements caused by the use of waste-derived fuel at cement plants

    SciTech Connect (OSTI)

    Yarmac, R.F.

    1994-12-31

    The Clean Air Act Amendments of 1990 required the USEPA to establish a comprehensive operating permit program which is being administered by the states. Most major air pollution sources will be required to submit operating permit applications by November 15, 1995 or earlier. Portland cement plants that burn waste-derived fuel face some special permitting problems that need to be addressed during the permit application process. This paper presents a brief summary of the Title V application with special emphasis on the permitting requirements incurred by the utilization of waste fuel at cement plants.

  13. High-level waste storage tank farms/242-A evaporator Standards/Requirements Identification Document (S/RID), Volume 7. Revision 1

    SciTech Connect (OSTI)

    Burt, D.L.

    1994-04-01

    The High-Level Waste Storage Tank Farms/242-A Evaporator Standards/Requirements Identification Document (S/RID) is contained in multiple volumes. This document (Volume 7) presents the standards and requirements for the following sections: Occupational Safety and Health, and Environmental Protection.

  14. Colorado Discharge Permit System General Permit | Open Energy...

    Open Energy Info (EERE)

    to discharge, as of this date, inaccordance with permit requirements and conditions set forth in Parts I and II hereof. All discharges authorized herein shall be consistent with...

  15. Guidelines for generators to meet HWHF acceptance requirements for hazardous, radioactive, and mixed wastes at Berkeley Lab. Revision 3

    SciTech Connect (OSTI)

    Albert, R.

    1996-06-01

    This document provides performance standards that one, as a generator of hazardous chemical, radioactive, or mixed wastes at the Berkeley Lab, must meet to manage their waste to protect Berkeley Lab staff and the environment, comply with waste regulations and ensure the continued safe operation of the workplace, have the waste transferred to the correct Waste Handling Facility, and enable the Environment, Health and Safety (EH and S) Division to properly pick up, manage, and ultimately send the waste off site for recycling, treatment, or disposal. If one uses and generates any of these wastes, one must establish a Satellite Accumulation Area and follow the guidelines in the appropriate section of this document. Topics include minimization of wastes, characterization of the wastes, containers, segregation, labeling, empty containers, and spill cleanup and reporting.

  16. Enterprise Assessments Review of the Los Alamos National Laboratory Transuranic Waste Facility 90% Draft Documented Safety Analysis and Technical Safety Requirements Submittals – EA-LANL-2015-07-07

    Office of Energy Efficiency and Renewable Energy (EERE)

    Operational Awareness Record for the Review of the Transuranic Waste Facility 90% Draft Documented Safety Analysis and Technical Safety Requirements Submittals

  17. Revk - a Tool for the Fulfilment of Requirements from National Rules for Tracking and Documentation of Radioactive Residual Material and Radioactive Waste

    SciTech Connect (OSTI)

    Hartmann, B.; Haeger, M.; Gruendler, D.

    2006-07-01

    According to the German Radiation Protection Ordinance treatment, storage, whereabouts of radioactive material etc. have to be documented. Due to legal requirements an electronic documentation system for radioactive waste has to be installed. Within the framework of the currently largest decommissioning project of nuclear facilities by Energiewerke Nord GmbH, a material flow-waste tracking and control system (ReVK) has been developed, tailored to the special needs of the decommissioning of nuclear facilities. With this system it is possible to record radioactive materials which can be released after treatment or decay storage for restricted and unrestricted utilization. Radioactive waste meant for final storage can be registered and documented as well. Based on ORACLE, ReVK is a client/server data base system with the following modules: 1. data registration, 2. transport management, 3. waste tracking, 4. storage management, 5. container management, 6. reporting, 7. activity calculation, 8. examination of technical acceptance criteria for storages and final repositories. Furthermore ReVK provides a multitude of add-ons to meet special user needs, which enlarge the spectrum of application enormously. ReVK is validated and qualified, accepted by experts and authorities and fulfils the requirements for a radioactive waste documentation system. (authors)

  18. Method of and apparatus for recovery of waste energy

    SciTech Connect (OSTI)

    Molitor, V. D.

    1985-07-16

    A holding tank receives waste water from a dishwasher or laundry machine having a rinse cycle and at least one wash cycle. A pump moves the waste water through a heat exchanger at the same time that the rinse cycle requires hot water from a hot water heater. The cold water feed for the hot water heater is also passed in countercurrent heat exchange relationship with the waste water to provide warmed or heated makeup water at the same time that hot water is being withdrawn therefrom. The cooled waste water from the heat exchanger may be collected in a tank and supplied to any one or more of several additional devices, such as a water cooled refrigerant compressor, a grease extraction ventilator having water contact means, a waste food grinder, etc. The ventilator and compressor may also be placed in series, while the cooling water heated in the compressor is recirculated to the heat exchanger. The holding tank may be mounted directly beneath the dishwasher, or the holding tank and countercurrent heat exchanger may be placed in a common housing, with the holding tank beneath the heat exchanger and a pump to transfer the waste water from the holding tank to the appropriate tubes of the coils of the heat exchanger, from which waste water may be discharged into a discharge area adjacent the holding tank. A removable screen for the waste water may be provided above the holding tank in each instance. When a discharge area is adjacent the holding tank, the screen will be self-cleaning, due to flow of incoming waste water across the screen and into the discharge area, when the screen is occluded.

  19. Regulators, Requirements, Statutes

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Air Act (CAA) Requirements for air quality and air emissions from facility operations Clean Water Act (CWA) Requirements for water quality and water discharges from facility...

  20. A DOE contractor`s perspective of environmental monitoring requirements at a low-level waste facility

    SciTech Connect (OSTI)

    Ferns, T.W.

    1989-11-01

    Environmental monitoring at a low-level waste disposal facility (LLWDF) should, (1) demonstrate compliance with environmental laws; (2) detect any spatial or temporal environmental changes; and (3) provide information on the potential or actual exposure of humans and/or the environment to disposed waste and/or waste by-products. Under the DOE Order system the LLWDF site manager has more freedom of implementation for a monitoring program than either the semi-prescriptive NRC, or the prescriptive EPA hazardous waste programs. This paper will attempt to compare and contrast environmental monitoring under the different systems (DOE, NRC, and EPA), and determine if the DOE might benefit from a more prescriptive system.

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

    SciTech Connect (OSTI)

    Hall, C.E.

    1998-01-09

    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.

  2. Closure Report for Corrective Action Unit 151: Septic Systems and Discharge Area, Nevada Test Site, Nevada

    SciTech Connect (OSTI)

    NSTec Environmental Restoration

    2008-04-01

    Corrective Action Unit (CAU) 151 is identified in the Federal Facility Agreement and Consent Order (FFACO) as Septic Systems and Discharge Area. CAU 151 consists of the following eight Corrective Action Sites (CASs), located in Areas 2, 12, and 18 of the Nevada Test Site, approximately 65 miles northwest of Las Vegas, Nevada: (1) CAS 02-05-01, UE-2ce Pond; (2) CAS 12-03-01, Sewage Lagoons (6); (3) CAS 12-04-01, Septic Tanks; (4) CAS 12-04-02, Septic Tanks; (5) CAS 12-04-03, Septic Tank; (6) CAS 12-47-01, Wastewater Pond; (7) CAS 18-03-01, Sewage Lagoon; and (8) CAS 18-99-09, Sewer Line (Exposed). CAU 151 closure activities were conducted according to the FFACO (FFACO, 1996; as amended February 2008) and the Corrective Action Plan for CAU 151 (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, 2007) from October 2007 to January 2008. The corrective action alternatives included no further action, clean closure, and closure in place with administrative controls. CAU 151 closure activities are summarized in Table 1. Closure activities generated liquid remediation waste, sanitary waste, hydrocarbon waste, and mixed waste. Waste generated was appropriately managed and disposed. Waste that is currently staged onsite is being appropriately managed and will be disposed under approved waste profiles in permitted landfills. Waste minimization activities included waste characterization sampling and segregation of waste streams. Some waste exceeded land disposal restriction limits and required offsite treatment prior to disposal. Other waste meeting land disposal restrictions was disposed of in appropriate onsite or offsite landfills. Waste disposition documentation is included as Appendix C.

  3. Powerful glow discharge excilamp

    DOE Patents [OSTI]

    Tarasenko, Victor F.; Panchenko, Aleksey N.; Skakun, Victor S.; Sosnin, Edward A.; Wang, Francis T.; Myers, Booth R.; Adamson, Martyn G.

    2002-01-01

    A powerful glow discharge lamp comprising two coaxial tubes, the outer tube being optically transparent, with a cathode and anode placed at opposite ends of the tubes, the space between the tubes being filled with working gas. The electrodes are made as cylindrical tumblers placed in line to one other in such a way that one end of the cathode is inserted into the inner tube, one end of the anode coaxially covers the end of the outer tube, the inner tube penetrating and extending through the anode. The increased electrodes' surface area increases glow discharge electron current and, correspondingly, average radiation power of discharge plasma. The inner tube contains at least one cooling liquid tube placed along the axis of the inner tube along the entire lamp length to provide cathode cooling. The anode has a circumferential heat extracting radiator which removes heat from the anode. The invention is related to lighting engineering and can be applied for realization of photostimulated processes under the action of powerful radiation in required spectral range.

  4. Environmental Requirements Management

    SciTech Connect (OSTI)

    Cusack, Laura J.; Bramson, Jeffrey E.; Archuleta, Jose A.; Frey, Jeffrey A.

    2015-01-08

    CH2M HILL Plateau Remediation Company (CH2M HILL) is the U.S. Department of Energy (DOE) prime contractor responsible for the environmental cleanup of the Hanford Site Central Plateau. As part of this responsibility, the CH2M HILL is faced with the task of complying with thousands of environmental requirements which originate from over 200 federal, state, and local laws and regulations, DOE Orders, waste management and effluent discharge permits, Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) response and Resource Conservation and Recovery Act (RCRA) corrective action documents, and official regulatory agency correspondence. The challenge is to manage this vast number of requirements to ensure they are appropriately and effectively integrated into CH2M HILL operations. Ensuring compliance with a large number of environmental requirements relies on an organization’s ability to identify, evaluate, communicate, and verify those requirements. To ensure that compliance is maintained, all changes need to be tracked. The CH2M HILL identified that the existing system used to manage environmental requirements was difficult to maintain and that improvements should be made to increase functionality. CH2M HILL established an environmental requirements management procedure and tools to assure that all environmental requirements are effectively and efficiently managed. Having a complete and accurate set of environmental requirements applicable to CH2M HILL operations will promote a more efficient approach to: • Communicating requirements • Planning work • Maintaining work controls • Maintaining compliance

  5. Information on commercial disposal facilities that may have received offshore drilling wastes.

    SciTech Connect (OSTI)

    Gasper, J. R.; Veil, J. A.; Ayers, R. C., Jr.

    2000-08-25

    The U.S. Environmental Protection Agency (EPA) is developing regulations that would establish requirements for discharging synthetic-based drill cuttings from offshore wells into the ocean. Justification for allowing discharges of these cuttings is that the environmental impacts from discharging drilling wastes into the ocean may be less harmful than the impacts from hauling them to shore for disposal. In the past, some onshore commercial facilities that disposed of these cuttings were improperly managed and operated and left behind environmental problems. This report provides background information on commercial waste disposal facilities in Texas, Louisiana, California, and Alaska that received or may have received offshore drilling wastes in the past and are now undergoing cleanup.

  6. Lessons Learned for Construction and Waste Water Management at Radioactive Waste Closure Site

    SciTech Connect (OSTI)

    Anderson, K.D.

    2008-07-01

    Environmental remediation of three different radioactive waste closure sites each required exhaustive characterization and evaluation of sampling and analytical information in resolving regulatory and technical issues that impact cleanup activities. One of the many regulatory and technical issues shared by all three and impacting the cleanup activities is the compliant management and discharge of waste waters generated and resulting from the remediation activities. Multiple options were available for each closure site in resolving waste water management challenges depending upon the base regulatory framework defined for the cleanup or closure of the site. These options are typically regulated by the federal Clean Water Act (CWA), with exemptions available under the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) and the Superfund Amendments and Reauthorization Act of 1986 (SARA) or Memorandum of Understanding (MOU) between regulatory agencies. In general, all parties must demonstrate equivalent compliance when concerns related to the protection of the general public and the environment. As such, all options for management of waste water resulting from closure activities must demonstrate compliance to or equivalent actions under the CWA. The CWA provides for the National Pollution Discharge Elimination System (NPDES) that is typically maintained by individual states through permitting process to generators, public utilities, and more recently, construction sites. Of the three sites, different compliance strategies were employed for each. The approach for the Columbus Closure Project (CCP) was to initiate full scale compliance to the Ohio EPA General Construction Permit No. OHC000002. The CCP provided Notice of Intent (NOI) to the Ohio EPA to discharge under the general permit according to the regulator approved Storm Water Pollution Prevention Plan. For the second site, the Li Tungsten Superfund Site in Glen Cove, New York, the option

  7. Igniter for gas discharge pipe with a flame detection system

    SciTech Connect (OSTI)

    Guerra, R.E.

    1990-03-06

    This patent describes a method of burning waste gas, using an igniter of the type having a nozzle, a main gas conduit extending to the nozzle, and an electrical spark means for creating a spark in the nozzle. It comprises: mounting the igniter to a waste gas discharge pipe with the nozzle directed across the opening of the gas discharge pipe; supplying a gaseous fuel to the main gas conduit; igniting the gaseous fuel with the electrical spark means, creating a flame for igniting the waste gas being discharged from the gas discharge pipe; providing the igniter with an auxiliary gas line extending to the vicinity of the nozzle; and supplying a second and lower volume source of waste gas to the auxiliary gas line for burning at the nozzle.

  8. Radioactive Waste Management Manual

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    1999-07-09

    This Manual further describes the requirements and establishes specific responsibilities for implementing DOE O 435.1, Radioactive Waste Management, for the management of DOE high-level waste, transuranic waste, low-level waste, and the radioactive component of mixed waste. Change 1 dated 6/19/01 removes the requirement that Headquarters is to be notified and the Office of Environment, Safety and Health consulted for exemptions for use of non-DOE treatment facilities. Certified 1-9-07.

  9. Application of the office of civilian radioactive waste management QA requirements to the hanford spent nuclear fuel project

    SciTech Connect (OSTI)

    MCCORMACK, R.L.

    1999-05-12

    This document identifies, at a high-level, the Hanford SNF Project systems, structures, and components and activities that must implement to some degree the OCRWM QARD requirements to ensure compliance with RL direction. This document will also be used to support development of a QARD requirements matrix for the implementation of QARD requirements.

  10. Design requirements document for the interim store phase I solidified high-level waste function 4.2.4.1.2

    SciTech Connect (OSTI)

    Calmus, R.B.

    1996-09-30

    The U.S. Department of Energy (DOE) has embarked upon a course to acquire Hanford site.t,,nk waste tr:atment and immobilization services using privatized facilities. This plan contains a two-phased approach. Phase I is a ``proof-of-principle/commercial demonstration-scale`` effort and Phase II is a full-scale production effort. In accordance with the planned approach, interim storage and disposal of various products from privatized facilities are to be DOE furnished. The path forward adopted for Phase I solidified high-level waste (HLW) interim storage entails use of Vaut 2 and 3 in the Hanford Site Spent Nuclear Fuels Canister Storage Building (CSB), to be located in the Hanford Site 200 East Area. This design requirements document establishes the functions, with associated requirements, allocated to the Phase I solidified HLW interim storage system. These requirements will be used as the basis for conceptual design of the CSB and supporting systems. This document will also provide the basis for preparation of a performance specification for design and construction activities necessary to achieve the overall project mission.

  11. Listed waste determination report. Environmental characterization

    SciTech Connect (OSTI)

    Not Available

    1993-06-01

    On September 23, 1988, the US Environmental Protection Agency (EPA) published a notice clarifying interim status requirements for the management of radioactive mixed waste thereby subjecting the Idaho National Engineering Laboratory (INEL) and other applicable Department of Energy (DOE) sites to regulation under the Resource Conservation and Recovery Act (RCRA). Therefore, the DOE was required to submit a Part A Permit application for each treatment, storage, and disposal (TSD) unit within the INEL, defining the waste codes and processes to be regulated under RCRA. The September 1990 revised Part A Permit application, that was approved by the State of Idaho identified 101 potential acute and toxic hazardous waste codes (F-, P-, and U- listed wastes according to 40 CFR 261.31 and 40 CFR 261.33) for some TSD units at the Idaho Chemical Processing Plant. Most of these waste were assumed to have been introduced into the High-level Liquid Waste TSD units via laboratory drains connected to the Process Equipment Waste (PEW) evaporator (PEW system). At that time, a detailed and systematic evaluation of hazardous chemical use and disposal practices had not been conducted to determine if F-, P-, or Unlisted waste had been disposed to the PEW system. The purpose of this investigation was to perform a systematic and detailed evaluation of the use and disposal of the 101 F-, P-, and Unlisted chemicals found in the approved September 1990 Part A Permit application. This investigation was aimed at determining which listed wastes, as defined in 40 CFR 261.31 (F-listed) and 261.33 (P & Unlisted) were discharged to the PEW system. Results of this investigation will be used to support revisions to the RCRA Part A Permit application.

  12. High level waste storage tank farms/242-A evaporator standards/requirements identification document phase 1 assessment report

    SciTech Connect (OSTI)

    Biebesheimer, E., Westinghouse Hanford Co.

    1996-09-30

    This document, the Standards/Requirements Identification Document (S/RID) Phase I Assessment Report for the subject facility, represents the results of an Administrative Assessment to determine whether S/RID requirements are fully addressed by existing policies, plans or procedures. It contains; compliance status, remedial actions, and an implementing manuals report linking S/RID elements to requirement source to implementing manual and section.

  13. Nonsputtering impulse magnetron discharge

    SciTech Connect (OSTI)

    Khodachenko, G. V.; Mozgrin, D. V.; Fetisov, I. K.; Stepanova, T. V.

    2012-01-15

    Experiments with quasi-steady high-current discharges in crossed E Multiplication-Sign B fields in various gases (Ar, N{sub 2}, H{sub 2}, and SF{sub 6}) and gas mixtures (Ar/SF{sub 6} and Ar/O{sub 2}) at pressures from 10{sup -3} to 5 Torr in discharge systems with different configurations of electric and magnetic fields revealed a specific type of stable low-voltage discharge that does not transform into an arc. This type of discharge came to be known as a high-current diffuse discharge and, later, a nonsputtering impulse magnetron discharge. This paper presents results from experimental studies of the plasma parameters (the electron temperature, the plasma density, and the temperature of ions and atoms of the plasma-forming gas) of a high-current low-pressure diffuse discharge in crossed E Multiplication-Sign B fields.

  14. High-level waste storage tank farms/242-A evaporator standards/requirements identification document (S/RID), Vol. 1

    SciTech Connect (OSTI)

    Not Available

    1994-04-01

    The purpose of this Requirements Identification Document (RID) section is to identify, in one location, all of the facility specific requirements and good industry practices which are necessary or important to establish an effective Issues Management Program for the Tank Farm Facility. The Management Systems Functional Area includes the site management commitment to environmental safety and health (ES&H) policies and controls, to compliance management, to development and management of policy and procedures, to occurrence reporting and corrective actions, resource and issue management, and to the self-assessment process.

  15. High-level waste storage tank farms/242-A evaporator standards/requirements identification document (S/RID), Vol. 2

    SciTech Connect (OSTI)

    Not Available

    1994-04-01

    The Quality Assurance Functional Area Requirements Identification Document (RID), addresses the programmatic requirements that ensure risks and environmental impacts are minimized, ensure safety, reliability, and performance are maximized through the application of effective management systems commensurate with the risks posed by the Tank Farm Facility and its operation. This RID incorporates guidance intended to provide Tank Farms management with the necessary requirements information to develop, upgrade, or assess the effectiveness of a Quality Assurance Program in the performance of organizational and functional activities. Quality Assurance is defined as all those planned and systematic actions necessary to provide adequate confidence that a facility, structure, system, or component will perform satisfactorily and safely in service. This document will provide the specific requirements to meet DNFSB recommendations and the guidance provided in DOE Order 5700.6C, utilizing industry codes, standards, regulatory guidelines, and industry good practices that have proven to be essential elements for an effective and efficient Quality Assurance Program as the nuclear industry has matured over the last thirty years.

  16. Radioactive Waste Management Manual

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    1999-07-09

    This Manual further describes the requirements and establishes specific responsibilities for implementing DOE O 435.1, Radioactive Waste Management, for the management of DOE high-level waste, transuranic waste, low-level waste, and the radioactive component of mixed waste. The purpose of the Manual is to catalog those procedural requirements and existing practices that ensure that all DOE elements and contractors continue to manage DOE's radioactive waste in a manner that is protective of worker and public health and safety, and the environment. Does not cancel other directives.

  17. Notice of Intent for Stormwater Discharges Associated with Constructio...

    Open Energy Info (EERE)

    to library Form: Notice of Intent for Stormwater Discharges Associated with Construction Activity on Moderate Risk Sites Abstract Notice of Intent for required for...

  18. Notice of Intent for Stormwater Discharges Associated with Constructio...

    Open Energy Info (EERE)

    Application: Notice of Intent for Stormwater Discharges Associated with Construction Activity on Low Risk SitesLegal Abstract Notice of Intent for required for...

  19. Zero discharge firmly entrenched as a powerplant design strategy

    SciTech Connect (OSTI)

    Strauss, S.D.

    1994-10-01

    This article describes how, drawing on a variety of options, this environmentally friendly practice has become a fact of life for new powerplant projects. Driven by regulatory restrictions and penalties for withdrawals from the nation's watercourses, powerplant designers have focused strongly on recycling water to minimize flows both into and outside plant boundaries. Quality of, and proximity to, water sources are a major environmental factor in the siting stage and process design. Thereafter, wastewater discharge draws primary emphasis. Cooling-tower blowdown and other waste streams are now processed to recycle water while converting remaining dissolved solids (TDS) to a disposable cake. The available techniques involve mechanical evaporation, side-stream softening, crystallization or spray drying, membrane treatment, and staged cooling. Space limitations, water quality, and other variables determine the best choice for any plant. While each offers certain advantages, none provides a panacea without attendant challenges, ranging from capital cost to pretreatment requirements to equipment operating difficulties.

  20. Environmental Compliance Guide. Guidance manual for Department of Energy compliance with the Clean Water Act: National Pollutant Discharge Elimination System (NPDES)

    SciTech Connect (OSTI)

    Not Available

    1982-07-01

    This manual provides general guidance for Department of Energy (DOE) officials for complying with Sect. 402 of the Clean Water Act (CWA) of 1977 and amendments. Section 402 authorizes the US Environmental Protection Agency (EPA) or states with EPA approved programs to issue National Pollutant Discharge Elimination System (NPDES) permits for the direct discharge of waste from a point source into waters of the United States. Although the nature of a project dictates the exact information requirements, every project has similar information requirements on the environmental setting, type of discharge(s), characterization of effluent, and description of operations and wastewater treatment. Additional information requirements for projects with ocean discharges, thermal discharges, and cooling water intakes are discussed. Guidance is provided in this manual on general methods for collecting, analyzing, and presenting information for an NPDES permit application. The NPDES program interacts with many sections of the CWA; therefore, background material on pertinent areas such as effluent limitations, water quality standards, toxic substances, and nonpoint source pollutants is included in this manual. Modifications, variances, and extensions applicable to NPDES permits are also discussed.

  1. High-level waste storage tank farms/242-A evaporator standards/requirements identification document (S/RID), Vol. 4

    SciTech Connect (OSTI)

    Not Available

    1994-04-01

    Radiation protection of personnel and the public is accomplished by establishing a well defined Radiation Protection Organization to ensure that appropriate controls on radioactive materials and radiation sources are implemented and documented. This Requirements Identification Document (RID) applies to the activities, personnel, structures, systems, components, and programs involved in executing the mission of the Tank Farms. The physical boundaries within which the requirements of this RID apply are the Single Shell Tank Farms, Double Shell Tank Farms, 242-A Evaporator-Crystallizer, 242-S, T Evaporators, Liquid Effluent Retention Facility (LERF), Purgewater Storage Facility (PWSF), and all interconnecting piping, valves, instrumentation, and controls. Also included is all piping, valves, instrumentation, and controls up to and including the most remote valve under Tank Farms control at any other Hanford Facility having an interconnection with Tank Farms. The boundary of the structures, systems, components, and programs to which this RID applies, is defined by those that are dedicated to and/or under the control of the Tank Farms Operations Department and are specifically implemented at the Tank Farms.

  2. World nuclear capacity and fuel cycle requirements, November 1993

    SciTech Connect (OSTI)

    Not Available

    1993-11-30

    This analysis report presents the current status and projections of nuclear capacity, generation, and fuel cycle requirements for all countries in the world using nuclear power to generate electricity for commercial use. Long-term projections of US nuclear capacity, generation, fuel cycle requirements, and spent fuel discharges for three different scenarios through 2030 are provided in support of the Department of Energy`s activities pertaining to the Nuclear Waste Policy Act of 1982 (as amended in 1987). The projections of uranium requirements also support the Energy Information Administration`s annual report, Domestic Uranium Mining and Milling Industry: Viability Assessment.

  3. Longitudinal discharge laser electrodes

    DOE Patents [OSTI]

    Warner, B.E.; Miller, J.L.; Ault, E.R.

    1994-08-23

    The improved longitudinal discharge laser electrode with IR baffle includes an electrode made up of washers spaced along the laser axis in order to form inter-washer spaces for hollow cathode discharge to take place and for IR radiation to be trapped. Additional IR baffles can be placed between the electrode ann the window. 2 figs.

  4. Longitudinal discharge laser electrodes

    DOE Patents [OSTI]

    Warner, Bruce E.; Miller, John L.; Ault, Earl R.

    1994-01-01

    The improved longitudinal discharge laser electrode with IR baffle includes an electrode made up of washers spaced along the laser axis in order to form inter-washer spaces for hollow cathode discharge to take place and for IR radiation to be trapped. Additional IR baffles can be placed between the electrode ann the window.

  5. Co-axial discharges

    DOE Patents [OSTI]

    Luce, J. S.; Smith, L. P.

    1960-11-22

    An apparatus is described for producing coaxial arc discharges in an evacuated enclosure and within a strong, confining magnetic field. The arcs are maintained at a high potential difference. Electrons diffuse to the more positive arc from the negative arc, and positive ions diffuse from the more positive arc to the negative arc. Coaxial arc discharges have the advantuge that ions that return to strike the positive arc discharge will lose no energy since they do not strike a solid wall or electrode. These discharges are useful in confining an ionized plasma between the discharges and have the advantage of preventing impurities from the walls of the enclosure from entering the plasma area because of the arc barrier set up by the cylindrical outer arc. (auth)

  6. CO-AXIAL DISCHARGES

    DOE Patents [OSTI]

    Luce, J.S.; Smith, L.P.

    1960-11-22

    A method and apparatus are given for producing coaxial arc discharges in an evacuated enclosure and within a strong, confining magnetic field. The arcs are maintained at a high potential difference. Electrons will diffuse to the more positive arc from the negative arc, and positive ions will diffuse from the more positive arc to the negative arc. Coaxial arc discharges have the advantage that ions which return to strike the positive arc discharge will lose no energy since they do not strike a solid wall or electrode. Those discharges are useful in confining an ionized plasma between the discharges, and have the advantage of preventing impurities from the walls of the enclosure from entering ihe plasma area because of the arc barrier set up bv the cylindrical outer arc.

  7. Site Discharge Pollution Prevention Plan (SDPPP)

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    SDPPP Individual Permit: Site Discharge Pollution Prevention Plan (SDPPP) The 2015 SDPPP Update fully incorporates all changes made during the year and reflects changes projected for 2016. Contact Environmental Communication & Public Involvement P.O. Box 1663 MS M996 Los Alamos, NM 87545 (505) 667-0216 Email Site Discharge Pollution Prevention Plan (SDPPP) The 2015 Update to the SDPPP, Revision 1, fulfills the requirements of Part 1.F of the Individual Permit. The first six drop-down items

  8. Waste Isolation Pilot Plant Nitrate Salt Bearing Waste Container Isolation

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Plan | Department of Energy Nitrate Salt Bearing Waste Container Isolation Plan Waste Isolation Pilot Plant Nitrate Salt Bearing Waste Container Isolation Plan The purpose of this document is to provide the Plan required by the New Mexico Environment Department Administrative Order 05-20001 issued on May 20, 2014 to the U. S. Department of Energy and Nuclear Waste Partnership LLC. The Order, at paragraph 22, requires the Permittees to submit a WIPP Nitrate Salt Bearing Waste Container

  9. Glow discharge detector

    DOE Patents [OSTI]

    Koo, Jackson C.; Yu, Conrad M.

    2002-01-01

    A highly sensitive electronic ion cell for the measurement of trace elements in He carrier gas which involves glow discharge. A constant wave (CW) glow discharge detector which is controlled through a biased resistor, can detect the change of electron density caused by impurities in the He carrier gas by many orders of magnitude larger than that caused by direct ionization or electron capture. The glow discharge detector utilizes a floating pseudo-electrode to form a probe in or near the plasma. By using this probe, the large variation of electron density due to trace amounts of impurities can be directly measured.

  10. Effects of discharge voltage waveform on the discharge characteristics...

    Office of Scientific and Technical Information (OSTI)

    atmospheric plasma jet Citation Details In-Document Search Title: Effects of discharge voltage waveform on the discharge characteristics in a helium atmospheric plasma jet We ...

  11. Radioactive Waste Management Manual

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    1999-07-09

    This Manual further describes the requirements and establishes specific responsibilities for implementing DOE O 435.1, Radioactive Waste Management, for the management of DOE high-level waste, transuranic waste, low-level waste, and the radioactive component of mixed waste. Change 1 dated 6/19/01 removes the requirement that Headquarters is to be notified and the Office of Environment, Safety and Health consulted for exemptions for use of non-DOE treatment facilities. Certified 1-9-07. Admin Chg 2, dated 6-8-11, supersedes DOE M 435.1-1 Chg 1.

  12. 2014 Annual Industrial Wastewater Reuse Report for the Idaho National Laboratory Site’s Materials and Fuels Complex Industrial Waste Ditch and Industrial Waste Pond

    SciTech Connect (OSTI)

    Lewis, Mike

    2015-02-01

    This report describes conditions, as required by the state of Idaho Industrial Wastewater Reuse Permit (WRU-I-0160-01, formerly LA 000160 01), for the wastewater reuse site at the Idaho National Laboratory Site’s Materials and Fuels Complex Industrial Waste Ditch and Industrial Waste Pond from November 1, 2013 through October 31, 2014. The report contains the following information; Facility and system description; Permit required effluent monitoring data and loading rates; Groundwater monitoring data; Status of special compliance conditions; Noncompliance issues; and Discussion of the facility’s environmental impacts During the 2014 reporting year, an estimated 10.11 million gallons of wastewater were discharged to the Industrial Waste Ditch and Pond which is well below the permit limit of 17 million gallons per year. The concentrations of all permit-required analytes in the samples from the down gradient monitoring wells were below the applicable Idaho Department of Environmental Quality’s groundwater quality standard levels.

  13. 2012 Annual Industrial Wastewater Reuse Report for the Idaho National Laboratory Site’s Materials and Fuels Complex Industrial Waste Ditch and Industrial Waste Pond

    SciTech Connect (OSTI)

    Mike Lewis

    2013-02-01

    This report describes conditions, as required by the state of Idaho Industrial Wastewater Reuse Permit (WRU-I-0160-01, formerly LA 000160 01), for the wastewater reuse site at the Idaho National Laboratory Site’s Materials and Fuels Complex Industrial Waste Ditch and Industrial Waste Pond from November 1, 2011 through October 31, 2012. The report contains the following information: • Facility and system description • Permit required effluent monitoring data and loading rates • Groundwater monitoring data • Status of special compliance conditions • Discussion of the facility’s environmental impacts During the 2012 reporting year, an estimated 11.84 million gallons of wastewater were discharged to the Industrial Waste Ditch and Pond which is well below the permit limit of 17 million gallons per year. The concentrations of all permit-required analytes in the samples from the down gradient monitoring wells were below the Ground Water Quality Rule Primary and Secondary Constituent Standards.

  14. 2011 Annual Industrial Wastewater Reuse Report for the Idaho National Laboratory Site's Materials and Fuels Complex Industrial Waste Ditch and Industrial Waste Pond

    SciTech Connect (OSTI)

    David Frederick

    2012-02-01

    This report describes conditions, as required by the state of Idaho Industrial Wastewater Reuse Permit (LA-000160-01), for the wastewater reuse site at the Idaho National Laboratory Site's Materials and Fuels Complex Industrial Waste Ditch and Industrial Waste Pond from November 1, 2010 through October 31, 2011. The report contains the following information: (1) Facility and system description; (2) Permit required effluent monitoring data and loading rates; (3) Groundwater monitoring data; (4) Status of special compliance conditions; and (5) Discussion of the facility's environmental impacts. During the 2011 reporting year, an estimated 6.99 million gallons of wastewater were discharged to the Industrial Waste Ditch and Pond which is well below the permit limit of 13 million gallons per year. Using the dissolved iron data, the concentrations of all permit-required analytes in the samples from the down gradient monitoring wells were below the Ground Water Quality Rule Primary and Secondary Constituent Standards.

  15. 2010 Annual Industrial Wastewater Reuse Report for the Idaho National Laboratory Site's Materials and Fuels Complex Industrial Waste Ditch and Industrial Waste Pond

    SciTech Connect (OSTI)

    David B. Frederick

    2011-02-01

    This report describes conditions, as required by the state of Idaho Industrial Wastewater Reuse Permit (#LA 000160 01), for the wastewater reuse site at the Idaho National Laboratory Site’s Materials and Fuels Complex Industrial Waste Ditch and Industrial Waste Pond from May 1, 2010 through October 31, 2010. The report contains the following information: • Facility and system description • Permit required effluent monitoring data and loading rates • Groundwater monitoring data • Status of special compliance conditions • Discussion of the facility’s environmental impacts During the 2010 partial reporting year, an estimated 3.646 million gallons of wastewater were discharged to the Industrial Waste Ditch and Pond which is well below the permit limit of 13 million gallons per year. The concentrations of all permit-required analytes in the samples from the down gradient monitoring wells were below the Ground Water Quality Rule Primary and Secondary Constituent Standards.

  16. Evaluation of slurry injection technology for management of drilling wastes.

    SciTech Connect (OSTI)

    Veil, J. A.; Dusseault, M. B.

    2003-02-19

    Each year, thousands of new oil and gas wells are drilled in the United States and around the world. The drilling process generates millions of barrels of drilling waste each year, primarily used drilling fluids (also known as muds) and drill cuttings. The drilling wastes from most onshore U.S. wells are disposed of by removing the liquids from the drilling or reserve pits and then burying the remaining solids in place (called pit burial). This practice has low cost and the approval of most regulatory agencies. However, there are some environmental settings in which pit burial is not allowed, such as areas with high water tables. In the U.S. offshore environment, many water-based and synthetic-based muds and cuttings can be discharged to the ocean if discharge permit requirements are met, but oil-based muds cannot be discharged at all. At some offshore facilities, drilling wastes must be either hauled back to shore for disposal or disposed of onsite through an injection process.

  17. Waste Characterization, Reduction, and Repackaging Facility...

    Office of Environmental Management (EM)

    Waste Characterization, Reduction, and Repackaging Facility (WCRRF)Technical Safety Requirements (TSR), ABD-WFM-006, Revision 2.1 Waste Characterization, Reduction, and Repackaging ...

  18. A perimeter-based groundwater protection strategy for waste management units at a petroleum refinery

    SciTech Connect (OSTI)

    Wenzlau, R.K.

    1996-12-01

    This article presents a groundwater management strategy and its application to regulatory compliance for the Shell Oil Company Martinez Manufacturing Complex, a refinery located within northern California. The purpose of the strategy is to protect the beneficial uses of groundwater which are present beyond the facility boundary while recognizing the occurrence of limited degradation of groundwater upgradient of the perimeter. The strategy applies perimeter-based groundwater monitoring and control to two general sources of groundwater quality degradation: historic spill and leak sites and inactive waste management units. To regulate the groundwater contaminant plumes originating form historic spill and leak sites the California Regional Water Quality Control Board (Regional Board) has issued Site Cleanup Requirements (SCR). To satisfy the SCR Shell developed in 1989 a Basin Boundary Control Plan as the first implementation of the groundwater strategy. To regulate groundwater quality impacts from solid waste management units, the Regional Board issues Waste Discharge Requirements (WDR). In 1995 the Regional Board issued revised WDR that established consistency between waste management unit regulation and the facility groundwater management strategy. The Regional Board made two findings that allowed this consistency. The first finding was that the Points of Compliance for all 23 solid waste management units are at the down-gradient perimeter of the facility. The second finding was that all waste management units were within corrective action, regardless of whether a known release of waste constituents occurred from a given waste unit.

  19. Stable glow discharge detector

    DOE Patents [OSTI]

    Koo, Jackson C.; Yu, Conrad M.

    2004-05-18

    A highly sensitive electronic ion cell for the measurement of trace elements in He carrier gas which involves glow discharge. A constant wave (CW) stable glow discharge detector which is controlled through a biased resistor, can detect the change of electron density caused by impurities in the He carrier gas by many orders of magnitude larger than that caused by direct ionization or electron capture. The stable glow discharge detector utilizes a floating pseudo-electrode to form a probe in or near the plasma and a solid rod electrode. By using this probe, the large variation of electron density due to trace amounts of impurities can be directly measured. The solid rod electrode provides greater stability and thus easier alignment.

  20. Secondary Waste Cast Stone Waste Form Qualification Testing Plan

    SciTech Connect (OSTI)

    Westsik, Joseph H.; Serne, R. Jeffrey

    2012-09-26

    The Hanford Tank Waste Treatment and Immobilization Plant (WTP) is being constructed to treat the 56 million gallons of radioactive waste stored in 177 underground tanks at the Hanford Site. The WTP includes a pretreatment facility to separate the wastes into high-level waste (HLW) and low-activity waste (LAW) fractions for vitrification and disposal. The LAW will be converted to glass for final disposal at the Integrated Disposal Facility (IDF). Cast Stone – a cementitious waste form, has been selected for solidification of this secondary waste stream after treatment in the ETF. The secondary-waste Cast Stone waste form must be acceptable for disposal in the IDF. This secondary waste Cast Stone waste form qualification testing plan outlines the testing of the waste form and immobilization process to demonstrate that the Cast Stone waste form can comply with the disposal requirements. Specifications for the secondary-waste Cast Stone waste form have not been established. For this testing plan, Cast Stone specifications are derived from specifications for the immobilized LAW glass in the WTP contract, the waste acceptance criteria for the IDF, and the waste acceptance criteria in the IDF Permit issued by the State of Washington. This testing plan outlines the testing needed to demonstrate that the waste form can comply with these waste form specifications and acceptance criteria. The testing program must also demonstrate that the immobilization process can be controlled to consistently provide an acceptable waste form product. This testing plan also outlines the testing needed to provide the technical basis for understanding the long-term performance of the waste form in the disposal environment. These waste form performance data are needed to support performance assessment analyses of the long-term environmental impact of the secondary-waste Cast Stone waste form in the IDF

  1. Longitudinal discharge laser baffles

    DOE Patents [OSTI]

    Warner, B.E.; Ault, E.R.

    1994-06-07

    The IR baffles placed between the window and the electrode of a longitudinal discharge laser improve laser performance by intercepting off-axis IR radiation from the laser and in doing so reduce window heating and subsequent optical distortion of the laser beam. 1 fig.

  2. Longitudinal discharge laser baffles

    DOE Patents [OSTI]

    Warner, Bruce E.; Ault, Earl R.

    1994-01-01

    The IR baffles placed between the window and the electrode of a longitudinal discharge laser improve laser performance by intercepting off-axis IR radiation from the laser and in doing so reduce window heating and subsequent optical distortion of the laser beam.

  3. WIPP WASTE MINIMIZATION PROGRAM DESCRIPTION

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    NOV 2 3 2015 New Mexico Environment Department 2905 Rodeo Park Drive East, Building 1 Santa Fe, New Mexico 87505-6303 Subject: Transm ittal of the Waste Isolation Pilot Plant Project 2015 Waste Minimization Report, Permit Number NM4890139088-TSDF Dear Mr. Kieling: The purpose of this letter is to provide you with the Waste Isolation Pilot Plant (WIPP) Project 2015 Waste Minimization Report. This report, required by and prepared in accordance with the WIPP Hazardous Waste Facility Permit Part 2,

  4. WIPP WASTE MINIMIZATION PROGRAM DESCRIPTION

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Carlsbad, New Mexico 8822 1 NOV 2 3 2011 Mr. John Kieling , Acting Bureau Chief Hazardous Waste Bureau New Mexico Environme nt Department 2905 Rodeo Park Drive East, Building 1 Santa Fe, New Mexico 87505-6303 Subject: Transmittal of the Waste Isolation Pilot Plant Annual Waste Minimization Report Dear Mr. Kieling: This letter provides the submittal of the Waste Isolation Pilot Plant Annual Waste Minimization Report. This report is required by and has bee n prepared in accordance with the WIPP

  5. Transuranic (TRU) Waste | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Transuranic (TRU) Waste Transuranic (TRU) Waste Transuranic (TRU) Waste Defined by the WIPP Land Withdrawal Act as "waste containing more than 100 nanocuries of alpha-emitting transuranic isotopes per gram of waste with half-lives greater than 20 years, except for (A) high-level radioactive waste, (B) waste that the Secretary of Energy has determined, with concurrence of the Administrator of the Environmental Protection Agency, does not need the degree of isolation required by the disposal

  6. Turning nuclear waste into glass

    SciTech Connect (OSTI)

    Pegg, Ian L.

    2015-02-15

    Vitrification has emerged as the treatment option of choice for the most dangerous radioactive waste. But dealing with the nuclear waste legacy of the Cold War will require state-of-the-art facilities and advanced glass formulations.

  7. Utah Code Ann. 19-5-107: Discharge of pollutants unlawful...

    Open Energy Info (EERE)

    Ann. 19-5-107: Discharge of pollutants unlawful -- Discharge permit required Jump to: navigation, search OpenEI Reference LibraryAdd to library Legal Document- StatuteStatute:...

  8. Removal of Radioactive Nuclides from Mo-99 Acidic Liquid Waste - 13027

    SciTech Connect (OSTI)

    Hsiao, Hsien-Ming; Pen, Ben-Li

    2013-07-01

    About 200 liters highly radioactive acidic liquid waste originating from Mo-99 production was stored at INER (Institute of Nuclear Energy Research). A study regarding the treatment of the radioactive acidic liquid waste was conducted to solve storage-related issues and allow discharge of the waste while avoiding environmental pollution. Before discharging the liquid waste, the acidity, NO{sub 3}{sup -} and Hg ions in high concentrations, and radionuclides must comply with environmental regulations. Therefore, the treatment plan was to neutralize the acidic liquid waste, remove key radionuclides to reduce the dose rate, and then remove the nitrate and mercury ions. Bench tests revealed that NaOH is the preferred solution to neutralize the high acidic waste solution and the pH of solution must be adjusted to 9?11 prior to the removal of nuclides. Significant precipitation was produced when the pH of solution reached 9. NaNO{sub 3} was the major content in the precipitate and part of NaNO{sub 3} was too fine to be completely collected by filter paper with a pore size of approximately 3 ?m. The residual fine particles remaining in solution therefore blocked the adsorption column during operation. Two kinds of adsorbents were employed for Cs-137 and a third for Sr-90 removal to minimize cost. For personnel radiation protection, significant lead shielding was required at a number of points in the process. The final process design and treatment facilities successfully treated the waste solutions and allowed for environmentally compliant discharge. (authors)

  9. Recycled Water Reuse Permit Renewal Application for the Materials and Fuels Complex Industrial Waste Ditch and Industrial Waste Pond

    SciTech Connect (OSTI)

    No Name

    2014-10-01

    ABSTRACT This renewal application for the Industrial Wastewater Reuse Permit (IWRP) WRU-I-0160-01 at Idaho National Laboratory (INL), Materials and Fuels Complex (MFC) Industrial Waste Ditch (IWD) and Industrial Waste Pond (IWP) is being submitted to the State of Idaho, Department of Environmental Quality (DEQ). This application has been prepared in compliance with the requirements in IDAPA 58.01.17, Recycled Water Rules. Information in this application is consistent with the IDAPA 58.01.17 rules, pre-application meeting, and the Guidance for Reclamation and Reuse of Municipal and Industrial Wastewater (September 2007). This application is being submitted using much of the same information contained in the initial permit application, submitted in 2007, and modification, in 2012. There have been no significant changes to the information and operations covered in the existing IWRP. Summary of the monitoring results and operation activity that has occurred since the issuance of the WRP has been included. MFC has operated the IWP and IWD as regulated wastewater land treatment facilities in compliance with the IDAPA 58.01.17 regulations and the IWRP. Industrial wastewater, consisting primarily of continuous discharges of nonhazardous, nonradioactive, routinely discharged noncontact cooling water and steam condensate, periodic discharges of industrial wastewater from the MFC facility process holdup tanks, and precipitation runoff, are discharged to the IWP and IWD system from various MFC facilities. Wastewater goes to the IWP and IWD with a permitted annual flow of up to 17 million gallons/year. All requirements of the IWRP are being met. The Operations and Maintenance Manual for the Industrial Wastewater System will be updated to include any new requirements.

  10. Hanford Dangerous Waste Permit

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Dangerous Waste Permit Suzanne Dahl and Jeff Lyon Nuclear Waste Program April 17, 2012 Tank-Related Units Why have permits? * To regulate dangerous waste treatment, storage, and disposal facilities: - Thermal treatment units - Landfills - Tank systems - Container storage - Containment buildings * To protect humans and the environment Parts of the Unit Permit * Fact Sheet * Unit description * Operations and processes * Permit conditions * Requirements or limitations to maintain safe operating

  11. Hanford Site Secondary Waste Roadmap

    SciTech Connect (OSTI)

    Westsik, Joseph H.

    2009-01-29

    performance requirements, waste composition, preliminary waste form screening, waste form development, process design and support, and validation. The regulatory and performance requirements activity will provide the secondary waste-form performance requirements. The waste-composition activity will provide workable ranges of secondary waste compositions and formulations for simulants and surrogates. Preliminary waste form screening will identify candidate waste forms for immobilizing the secondary wastes. The waste form development activity will mature the waste forms, leading to a selected waste form(s) with a defensible understanding of the long-term release rate and input into the critical decision process for a secondary waste treatment process/facility. The process and design support activity will provide a reliable process flowsheet and input to support a robust facility design. The validation effort will confirm that the selected waste form meets regulatory requirements. The final outcome of the implementation of the secondary waste roadmap is the compliant, effective, timely, and cost-effective disposal of the secondary wastes. The work necessary to address the programmatic, regulatory, and technical risks and uncertainties identified through the Secondary Waste Roadmap Workshop are assembled into several program needs elements. Programmatic/Regulatory needs include: • Select and deploy Hanford tank waste supplemental treatment technology • Provide treatment capability for secondary waste streams from tank waste treatment • Develop consensus on secondary waste form acceptance. Technology needs include: • Define secondary waste composition ranges and uncertainties • Identify and develop waste forms for secondary waste immobilization and disposal • Develop test methods to characterize secondary waste form performance. Details for each of these program elements are provided.

  12. Final Hanford Site Transuranic (TRU) Waste Characterization QA Project Plan

    SciTech Connect (OSTI)

    GREAGER, T.M.

    1999-09-09

    The Transuranic Waste Characterization Quality Assurance Program Plan required each US Department of Energy (DOE) site that characterizes transuranic waste to be sent the Waste Isolation Pilot Plan that addresses applicable requirements specified in the QAPP.

  13. Laser activated diffuse discharge switch (Patent) | DOEPatents

    Office of Scientific and Technical Information (OSTI)

    Laser activated diffuse discharge switch Title: Laser activated diffuse discharge switch The invention is a gas mixture for a diffuse discharge switch which is capable of changing ...

  14. Continuous pile discharging machine

    DOE Patents [OSTI]

    Smith, Phillips P.

    1976-05-11

    A device for discharging cartridges from tubes under fluid pressure includes a cylindrical housing adapted to be seated in a leak-tight manner on the end of one of the tubes, a chute depending from the cylindrical housing near the end seated on the end of the tube, a rotatable piston having a wrench on the forward end thereof disposed in the cylindrical housing and adapted to manipulate a plug in the end of the tube, and a telescopic hydraulic ram adapted to move the piston toward the plug. In addition the wrench contains a magnet which prevents inadvertent uncoupling of the wrench and the plug.

  15. Mixed waste characterization reference document

    SciTech Connect (OSTI)

    1997-09-01

    Waste characterization and monitoring are major activities in the management of waste from generation through storage and treatment to disposal. Adequate waste characterization is necessary to ensure safe storage, selection of appropriate and effective treatment, and adherence to disposal standards. For some wastes characterization objectives can be difficult and costly to achieve. The purpose of this document is to evaluate costs of characterizing one such waste type, mixed (hazardous and radioactive) waste. For the purpose of this document, waste characterization includes treatment system monitoring, where monitoring is a supplement or substitute for waste characterization. This document establishes a cost baseline for mixed waste characterization and treatment system monitoring requirements from which to evaluate alternatives. The cost baseline established as part of this work includes costs for a thermal treatment technology (i.e., a rotary kiln incinerator), a nonthermal treatment process (i.e., waste sorting, macronencapsulation, and catalytic wet oxidation), and no treatment (i.e., disposal of waste at the Waste Isolation Pilot Plant (WIPP)). The analysis of improvement over the baseline includes assessment of promising areas for technology development in front-end waste characterization, process equipment, off gas controls, and monitoring. Based on this assessment, an ideal characterization and monitoring configuration is described that minimizes costs and optimizes resources required for waste characterization.

  16. Preoperational Subsurface Conditions at the Idaho Nuclear Technology and Engineering Center Service Wastewater Discharge Facility

    SciTech Connect (OSTI)

    Ansley, Shannon L.

    2002-02-20

    The Idaho Nuclear Technology and Engineering Center (INTEC) Service Wastewater Discharge Facility replaces the existing percolation ponds as a disposal facility for the INTEC Service Waste Stream. A preferred alternative for helping decrease water content in the subsurface near INTEC, closure of the existing ponds is required by the INTEC Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Record of Decision (ROD) for Waste Area Group 3 Operable Unit 3-13 (DOE-ID 1999a). By August 2002, the replacement facility was constructed approximately 2 miles southwest of INTEC, near the Big Lost River channel. Because groundwater beneath the Idaho National Engineering and Environmental Laboratory (INEEL) is protected under Federal and State of Idaho regulations from degradation due to INEEL activities, preoperational data required by U.S. Department of Energy (DOE) Order 5400.1 were collected. These data include preexisting physical, chemical, and biological conditions that could be affected by the discharge; background levels of radioactive and chemical components; pertinent environmental and ecological parameters; and potential pathways for human exposure or environmental impact. This document presents specific data collected in support of DOE Order 5400.1, including: four quarters of groundwater sampling and analysis of chemical and radiological parameters; general facility description; site specific geology, stratigraphy, soils, and hydrology; perched water discussions; and general regulatory requirements. However, in order to avoid duplication of previous information, the reader is directed to other referenced publications for more detailed information. Documents that are not readily available are compiled in this publication as appendices. These documents include well and borehole completion reports, a perched water evaluation letter report, the draft INEEL Wellhead Protection Program Plan, and the Environmental Checklist.

  17. Process for treating waste water having low concentrations of metallic contaminants

    DOE Patents [OSTI]

    Looney, Brian B; Millings, Margaret R; Nichols, Ralph L; Payne, William L

    2014-12-16

    A process for treating waste water having a low level of metallic contaminants by reducing the toxicity level of metallic contaminants to an acceptable level and subsequently discharging the treated waste water into the environment without removing the treated contaminants.

  18. Oregon Industrial Stormwater Discharge Monitoring Report (DEQ...

    Open Energy Info (EERE)

    discharge. Form Type ApplicationNotice Form Topic Industrial Stormwater Discharge Monitoring Report Organization Oregon Department of Environmental Quality Published...

  19. Method for processing aqueous wastes

    DOE Patents [OSTI]

    Pickett, J.B.; Martin, H.L.; Langton, C.A.; Harley, W.W.

    1993-12-28

    A method is presented for treating waste water such as that from an industrial processing facility comprising the separation of the waste water into a dilute waste stream and a concentrated waste stream. The concentrated waste stream is treated chemically to enhance precipitation and then allowed to separate into a sludge and a supernate. The supernate is skimmed or filtered from the sludge and blended with the dilute waste stream to form a second dilute waste stream. The sludge remaining is mixed with cementitious material, rinsed to dissolve soluble components, then pressed to remove excess water and dissolved solids before being allowed to cure. The dilute waste stream is also chemically treated to decompose carbonate complexes and metal ions and then mixed with cationic polymer to cause the precipitated solids to flocculate. Filtration of the flocculant removes sufficient solids to allow the waste water to be discharged to the surface of a stream. The filtered material is added to the sludge of the concentrated waste stream. The method is also applicable to the treatment and removal of soluble uranium from aqueous streams, such that the treated stream may be used as a potable water supply. 4 figures.

  20. Method for processing aqueous wastes

    SciTech Connect (OSTI)

    Pickett, John B.; Martin, Hollis L.; Langton, Christine A.; Harley, Willie W.

    1993-01-01

    A method for treating waste water such as that from an industrial processing facility comprising the separation of the waste water into a dilute waste stream and a concentrated waste stream. The concentrated waste stream is treated chemically to enhance precipitation and then allowed to separate into a sludge and a supernate. The supernate is skimmed or filtered from the sludge and blended with the dilute waste stream to form a second dilute waste stream. The sludge remaining is mixed with cementitious material, rinsed to dissolve soluble components, then pressed to remove excess water and dissolved solids before being allowed to cure. The dilute waste stream is also chemically treated to decompose carbonate complexes and metal ions and then mixed with cationic polymer to cause the precipitated solids to flocculate. Filtration of the flocculant removes sufficient solids to allow the waste water to be discharged to the surface of a stream. The filtered material is added to the sludge of the concentrated waste stream. The method is also applicable to the treatment and removal of soluble uranium from aqueous streams, such that the treated stream may be used as a potable water supply.

  1. Method for processing aqueous wastes

    SciTech Connect (OSTI)

    Pickett, J.B.; Martin, H.L.; Langton, C.A.; Harley, W.W.

    1992-12-31

    This invention is comprised of a method for treating waste water such as that from an industrial processing facility comprising the separation of the waste water into a dilute waste stream and a concentrated waste stream. The concentrated waste stream is treated chemically to enhance precipitation and then allowed to separate into a sludge and a supernate. The supernate is skimmed or filtered from the sludge and blended with the dilute waste stream to form a second dilute waste stream. The sludge remaining is mixed with cementitious material, rinsed to dissolve soluble components, then pressed to remove excess water and dissolved solids before being allowed to cure. The dilute waste stream is also chemically treated to decompose carbonate complexes and metal ions and then mixed with cationic polymer to cause the precipitated solids to flocculate. Filtration of the flocculant removes sufficient solids to allow the waste water to be discharged to the surface of a stream. The filtered material is added to the sludge of the concentrated waste stream. The method is also applicable to the treatment and removal of soluble uranium from aqueous streams, such that the treated stream may be used as a potable water supply.

  2. Advanced Waste Retrieval System. Innovative Technology Summary Report

    SciTech Connect (OSTI)

    2001-09-01

    At West Valley, following the baseline removal operations, bulk waste retrieval methods may be augmented if required, with the deployment of the Advanced Waste Retrieval System (AWRS). The AWRS is a hydraulic boom mounted on a trolley on the Mast-Mounted Tool Delivery System. The boom is about 15 ft long with a pan and tilt mechanism at the end. On the end is a steam jet with a suction tool that can reach down around the tank internal structure and vacuum up zeolite or sludge off the bottom of the tank from a thirty-foot diameter reach. A grinder is included topside in the discharge path to pulverize the zeolite so it can be readily retrieved from the destination tank.

  3. EPA issues draft general permits for industrial stormwater discharges

    SciTech Connect (OSTI)

    Not Available

    1994-01-01

    EPA on Nov. 16, 1990, issued stormwater discharge regulations associated with industrial activity'' under the authority of CWA's National Pollutant Discharge Elimination System (NPDES). Those regulations established NPDES permit application requirements for industrial and certain municipal separate stormwater discharge systems. Three permit application options were made available for industrial stormwater discharges -- filing an individual application, becoming a participant in a group application or filing a notice of intent to be covered under a general permit and its requirements. The Agency of Nov. 19 proposed a draft general permit for group applications. Industrial dischargers choosing the group option previously were required to file in two parts. Part 1 was due by Sept. 30, 1991, and Part 2 was due by Oct. 1, 1992. The proposed permit would apply to industrial facilities, including certain Indian lands, in selected areas of EPA Regions I, II, III, IV, VI, VIII, IX and X. The permit would cover industrial stormwater discharges to US waters, and would include discharges transmitted through large, medium-sized and other municipal separate storm sewer systems.

  4. Hanford Waste Vitrification Plant technical background document for best available radionuclide control technology demonstration

    SciTech Connect (OSTI)

    Carpenter, A.B.; Skone, S.S.; Rodenhizer, D.G.; Marusich, M.V. )

    1990-10-01

    This report provides the background documentation to support applications for approval to construct and operate new radionuclide emission sources at the Hanford Waste Vitrification Plant (HWVP) near Richland, Washington. The HWVP is required to obtain permits under federal and state statutes for atmospheric discharges of radionuclides. Since these permits must be issued prior to construction of the facility, draft permit applications are being prepared, as well as documentation to support these permits. This report addresses the applicable requirements and demonstrates that the preferred design meets energy, environmental, and economic criteria for Best Available Radionuclide Control Technology (BARCT) at HWVP. 22 refs., 11 figs., 25 tabs.

  5. Historical Liquid Discharges and Outfalls

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    liquids were discharged to Pueblo and Los Alamos Canyons. August 1, 2013 Contamination from the Acid Canyon outfall has been clean up to below residential levels...

  6. Hanford Tank Waste - Near Source Treatment of Low Activity Waste

    SciTech Connect (OSTI)

    Ramsey, William Gene

    2013-08-15

    Abstract only. Treatment and disposition of Hanford Site waste as currently planned consists of 100+ waste retrievals, waste delivery through up to 8+ miles of dedicated, in-ground piping, centralized mixing and blending operations- all leading to pre-treatment combination and separation processes followed by vitrification at the Hanford Tank Waste Treatment and Immobilization Plant (WTP). The sequential nature of Tank Farm and WTP operations requires nominally 15-20 years of continuous operations before all waste can be retrieved from many Single Shell Tanks (SSTs). Also, the infrastructure necessary to mobilize and deliver the waste requires significant investment beyond that required for the WTP. Treating waste as closely as possible to individual tanks or groups- as allowed by the waste characteristics- is being investigated to determine the potential to 1) defer, reduce, and/or eliminate infrastructure requirements, and 2) significantly mitigate project risk by reducing the potential and impact of single point failures. The inventory of Hanford waste slated for processing and disposition as LAW is currently managed as high-level waste (HLW), i.e., the separation of fission products and other radionuclides has not commenced. A significant inventory of this waste (over 20M gallons) is in the form of precipitated saltcake maintained in single shell tanks, many of which are identified as potential leaking tanks. Retrieval and transport (as a liquid) must be staged within the waste feed delivery capability established by site infrastructure and WTP. Near Source treatment, if employed, would provide for the separation and stabilization processing necessary for waste located in remote farms (wherein most of the leaking tanks reside) significantly earlier than currently projected. Near Source treatment is intended to address the currently accepted site risk and also provides means to mitigate future issues likely to be faced over the coming decades. This paper

  7. NEVADA TEST SITE WASTE ACCEPTANCE CRITERIA

    SciTech Connect (OSTI)

    U.S. DEPARTMENT OF ENERGY, NATIONAL NUCLEAR SECURITY ADMINISTRATION, NEVADA SITE OFFICE

    2005-07-01

    This document establishes the U. S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) waste acceptance criteria (WAC). The WAC provides the requirements, terms, and conditions under which the Nevada Test Site will accept low-level radioactive and mixed waste for disposal. Mixed waste generated within the State of Nevada by NNSA/NSO activities is accepted for disposal. It includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the Nevada Test Site Area 3 and Area 5 Radioactive Waste Management Site for storage or disposal.

  8. Reactor-specific spent fuel discharge projections, 1984 to 2020

    SciTech Connect (OSTI)

    Heeb, C.M.; Libby, R.A.; Holter, G.M.

    1985-04-01

    The original spent fuel utility data base (SFDB) has been adjusted to produce agreement with the EIA nuclear energy generation forecast. The procedure developed allows the detail of the utility data base to remain intact, while the overall nuclear generation is changed to match any uniform nuclear generation forecast. This procedure adjusts the weight of the reactor discharges as reported on the SFDB and makes a minimal (less than 10%) change in the original discharge exposures in order to preserve discharges of an integral number of fuel assemblies. The procedure used in developing the reactor-specific spent fuel discharge projections, as well as the resulting data bases themselves, are described in detail in this report. Discussions of the procedure cover the following topics: a description of the data base; data base adjustment procedures; addition of generic power reactors; and accuracy of the data base adjustments. Reactor-specific discharge and storage requirements are presented. Annual and cumulative discharge projections are provided. Annual and cumulative requirements for additional storage are shown for the maximum at-reactor (AR) storage assumption, and for the maximum AR with transshipment assumption. These compare directly to the storage requirements from the utility-supplied data, as reported in the Spent Fuel Storage Requirements Report. The results presented in this report include: the disaggregated spent fuel discharge projections; and disaggregated projections of requirements for additional spent fuel storage capacity prior to 1998. Descriptions of the methodology and the results are included in this report. Details supporting the discussions in the main body of the report, including descriptions of the capacity and fuel discharge projections, are included. 3 refs., 6 figs., 12 tabs.

  9. Hanford Site Transuranic (TRU) Waste Certification Plan

    SciTech Connect (OSTI)

    GREAGER, T.M.

    2000-12-06

    As a generator of transuranic (TRU) and TRU mixed waste destined for disposal at the Waste Isolation Pilot Plant (WIPP), the Hanford Site must ensure that its TRU waste meets the requirements of US. Department of Energy (DOE) 0 435.1, ''Radioactive Waste Management,'' and the Contact-Handled (CH) Transuranic Waste Acceptance Criteria for the Waste Isolation Pilot Plant (WIPP-WAC). WIPP-WAC requirements are derived from the WIPP Technical Safety Requirements, WIPP Safety Analysis Report, TRUPACT-II SARP, WIPP Land Withdrawal Act, WIPP Hazardous Waste Facility Permit, and Title 40 Code of Federal Regulations (CFR) 191/194 Compliance Certification Decision. The WIPP-WAC establishes the specific physical, chemical, radiological, and packaging criteria for acceptance of defense TRU waste shipments at WIPP. The WPP-WAC also requires that participating DOE TRU waste generator/treatment/storage sites produce site-specific documents, including a certification plan, that describe their program for managing TRU waste and TRU waste shipments before transferring waste to WIPP. Waste characterization activities provide much of the data upon which certification decisions are based. Waste characterization requirements for TRU waste and TRU mixed waste that contains constituents regulated under the Resource Conservation and Recovery Act (RCRA) are established in the WIPP Hazardous Waste Facility Permit Waste Analysis Plan (WAP). The Hanford Site Quality Assurance Project Plan (QAPjP) (HNF-2599) implements the applicable requirements in the WAP and includes the qualitative and quantitative criteria for making hazardous waste determinations. The Hanford Site must also ensure that its TRU waste destined for disposal at WPP meets requirements for transport in the Transuranic Package Transporter-11 (TRUPACT-11). The US. Nuclear Regulatory Commission (NRC) establishes the TRUPACT-11 requirements in the Safety Analysis Report for the TRUPACT-II Shipping Package (TRUPACT-11 SARP). In

  10. Hanford Site Transuranic (TRU) Waste Certification Plan

    SciTech Connect (OSTI)

    GREAGER, T.M.

    2000-12-01

    As a generator of transuranic (TRU) and TRU mixed waste destined for disposal at the Waste Isolation Pilot Plant (WIPP), the Hanford Site must ensure that its TRU waste meets the requirements of US. Department of Energy (DOE) 0 435.1, ''Radioactive Waste Management,'' and the Contact-Handled (CH) Transuranic Waste Acceptance Criteria for the Waste Isolation Pilot Plant (WIPP-WAC). WIPP-WAC requirements are derived from the WIPP Technical Safety Requirements, WIPP Safety Analysis Report, TRUPACT-II SARP, WIPP Land Withdrawal Act, WIPP Hazardous Waste Facility Permit, and Title 40 Code of Federal Regulations (CFR) 191/194 Compliance Certification Decision. The WIPP-WAC establishes the specific physical, chemical, radiological, and packaging criteria for acceptance of defense TRU waste shipments at WIPP. The WPP-WAC also requires that participating DOE TRU waste generator/treatment/storage sites produce site-specific documents, including a certification plan, that describe their program for managing TRU waste and TRU waste shipments before transferring waste to WIPP. Waste characterization activities provide much of the data upon which certification decisions are based. Waste characterization requirements for TRU waste and TRU mixed waste that contains constituents regulated under the Resource Conservation and Recovery Act (RCRA) are established in the WIPP Hazardous Waste Facility Permit Waste Analysis Plan (WAP). The Hanford Site Quality Assurance Project Plan (QAPjP) (HNF-2599) implements the applicable requirements in the WAP and includes the qualitative and quantitative criteria for making hazardous waste determinations. The Hanford Site must also ensure that its TRU waste destined for disposal at WPP meets requirements for transport in the Transuranic Package Transporter-11 (TRUPACT-11). The US. Nuclear Regulatory Commission (NRC) establishes the TRUPACT-11 requirements in the Safety Analysis Report for the TRUPACT-II Shipping Package (TRUPACT-11 SARP). In

  11. Differential pressure pin discharge apparatus

    DOE Patents [OSTI]

    Oakley, D.J.

    1984-05-30

    Disclosed is a discharge assembly for allowing elongate pins to be discharged from an area of relatively low pressure to an area of relatively greater pressure. The discharge assembly includes a duck valve having a lip piece made of flexible material. The flexible lip piece responds to a fluctuating pressure created downstream by an aspirator. The aspirator reduces the downstream pressure sensed by the duck valve when the discharge assembly is in the open position. This allows elongate pins to be moved through the duck valve with no backflow because the aspirator pressure is less than the pressure in the low pressure area from which the pins originate. Closure of the assembly causes the aspirator static pressure to force the flexible duck valve lip piece into a tightly sealed position also preventing backflow. The discharge assembly can be easily controlled using a single control valve which blocks the flow of aspirator gas and closes the pins passageway extending through the assembly.

  12. Capillary discharge source

    DOE Patents [OSTI]

    Bender, III, Howard Albert

    2003-11-25

    Debris generation from an EUV electric discharge plasma source device can be significantly reduced or essentially eliminated by encasing the electrodes with dielectric or electrically insulating material so that the electrodes are shielded from the plasma, and additionally by providing a path for the radiation to exit wherein the electrodes are not exposed to the area where the radiation is collected. The device includes: (a) a body, which is made of an electrically insulating material, that defines a capillary bore that has a proximal end and a distal end and that defines at least one radiation exit; (b) a first electrode that defines a first channel that has a first inlet end that is connected to a source of gas and a first outlet end that is in communication with the capillary bore, wherein the first electrode is positioned at the distal end of the capillary bore; (c) a second electrode that defines a second channel that has a second inlet end that is in communication with the capillary bore and an outlet end, wherein the second electrode is positioned at the proximal end of the capillary bore; and (d) a source of electric potential that is connected across the first and second electrodes, wherein radiation generated within the capillary bore is emitted through the at least one radiation exit and wherein the first electrode and second electrode are shielded from the emitted radiation.

  13. High level waste storage tank farms/242-A evaporator standards/requirements identification document phase 1 assessment corrective actions/compliance schedule approval report

    SciTech Connect (OSTI)

    Biebesheimer, E.

    1996-09-30

    This document, the Standards/Requirements Identification Document (S/RID) Phase I Assessment Corrective Actions/Compliance Schedule Approval Report for the subject facility, contains the corrective actions required to bring the facility into compliance as a result of an Administrative Assessment to determine whether S/RID requirements are fully addressed by existing policies, plans or procedures. These actions are delineated in the Compliance Schedule Approvals which also contain; noncompliances, risks, compensatory measures, schedules for corrective actions, justifications for approval, and resource impacts.

  14. Waste Guide

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Disposal Waste Disposal Trucks transport debris from Oak Ridge’s cleanup sites to the onsite CERCLA disposal area, the Environmental Management Waste Management Facility. Trucks transport debris from Oak Ridge's cleanup sites to the onsite CERCLA disposal area, the Environmental Management Waste Management Facility. The low-level radiological and hazardous wastes generated from Oak Ridge's cleanup projects are disposed in the Environmental Management Waste Management Facility (EMWMF). The

  15. Process Waste Assessment - Paint Shop

    SciTech Connect (OSTI)

    Phillips, N.M.

    1993-06-01

    This Process Waste Assessment was conducted to evaluate hazardous wastes generated in the Paint Shop, Building 913, Room 130. Special attention is given to waste streams generated by the spray painting process because it requires a number of steps for preparing, priming, and painting an object. Also, the spray paint booth covers the largest area in R-130. The largest and most costly waste stream to dispose of is {open_quote}Paint Shop waste{close_quotes} -- a combination of paint cans, rags, sticks, filters, and paper containers. These items are compacted in 55-gallon drums and disposed of as solid hazardous waste. Recommendations are made for minimizing waste in the Paint Shop. Paint Shop personnel are very aware of the need to minimize hazardous wastes and are continuously looking for opportunities to do so.

  16. Waste acceptance criteria for the Waste Isolation Pilot Plant

    SciTech Connect (OSTI)

    NONE

    1996-04-01

    The Waste Isolation Pilot Plant (WIPP) Waste Acceptance Criteria (WAC), DOE/WIPP-069, was initially developed by a U.S. Department of Energy (DOE) Steering Committee to provide performance requirements to ensure public health and safety as well as the safe handling of transuranic (TRU) waste at the WIPP. This revision updates the criteria and requirements of previous revisions and deletes those which were applicable only to the test phase. The criteria and requirements in this document must be met by participating DOE TRU Waste Generator/Storage Sites (Sites) prior to shipping contact-handled (CH) and remote-handled (RH) TRU waste forms to the WIPP. The WIPP Project will comply with applicable federal and state regulations and requirements, including those in Titles 10, 40, and 49 of the Code of Federal Regulations (CFR). The WAC, DOE/WIPP-069, serves as the primary directive for assuring the safe handling, transportation, and disposal of TRU wastes in the WIPP and for the certification of these wastes. The WAC identifies strict requirements that must be met by participating Sites before these TRU wastes may be shipped for disposal in the WIPP facility. These criteria and requirements will be reviewed and revised as appropriate, based on new technical or regulatory requirements. The WAC is a controlled document. Revised/changed pages will be supplied to all holders of controlled copies.

  17. Flexible Distributed Energy & Water from Waste for the Food ...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    COD reduction * Meetimprove discharge water quality (COD, NH 3 , NO 3 ) * Reduce ... UASB EGSB Gas UASB UASB EGSB EGSB Gas Waste Water Effluent Digester AS MBR 3 State of ...

  18. Estimating Waste Inventory and Waste Tank Characterization |...

    Office of Environmental Management (EM)

    Estimating Waste Inventory and Waste Tank Characterization Estimating Waste Inventory and Waste Tank Characterization Summary Notes from 28 May 2008 Generic Technical Issue ...

  19. Hanford Site solid waste acceptance criteria

    SciTech Connect (OSTI)

    Ellefson, M.D.

    1998-07-01

    Order 5820.2A requires that each treatment, storage, and/or disposal facility (referred to in this document as TSD unit) that manages low-level or transuranic waste (including mixed waste and TSCA PCB waste) maintain waste acceptance criteria. These criteria must address the various requirements to operate the TSD unit in compliance with applicable safety and environmental requirements. This document sets forth the baseline criteria for acceptance of radioactive waste at TSD units operated by WMH. The criteria for each TSD unit have been established to ensure that waste accepted can be managed in a manner that is within the operating requirements of the unit, including environmental regulations, DOE Orders, permits, technical safety requirements, waste analysis plans, performance assessments, and other applicable requirements. Acceptance criteria apply to the following TSD units: the Low-Level Burial Grounds (LLBG) including both the nonregulated portions of the LLBG and trenches 31 and 34 of the 218-W-5 Burial Ground for mixed waste disposal; Central Waste Complex (CWC); Waste Receiving and Processing Facility (WRAP); and T Plant Complex. Waste from all generators, both from the Hanford Site and from offsite facilities, must comply with these criteria. Exceptions can be granted as provided in Section 1.6. Specific waste streams could have additional requirements based on the 1901 identified TSD pathway. These requirements are communicated in the Waste Specification Records (WSRds). The Hanford Site manages nonradioactive waste through direct shipments to offsite contractors. The waste acceptance requirements of the offsite TSD facility must be met for these nonradioactive wastes. This document does not address the acceptance requirements of these offsite facilities.

  20. Mixed waste characterization, treatment & disposal focus area

    SciTech Connect (OSTI)

    1996-08-01

    The mission of the Mixed Waste Characterization, Treatment, and Disposal Focus Area (referred to as the Mixed Waste Focus Area or MWFA) is to provide treatment systems capable of treating DOE`s mixed waste in partnership with users, and with continual participation of stakeholders, tribal governments, and regulators. The MWFA deals with the problem of eliminating mixed waste from current and future storage in the DOE complex. Mixed waste is waste that contains both hazardous chemical components, subject to the requirements of the Resource Conservation and Recovery Act (RCRA), and radioactive components, subject to the requirements of the Atomic Energy Act. The radioactive components include transuranic (TRU) and low-level waste (LLW). TRU waste primarily comes from the reprocessing of spent fuel and the use of plutonium in the fabrication of nuclear weapons. LLW includes radioactive waste other than uranium mill tailings, TRU, and high-level waste, including spent fuel.

  1. Introduction to DOE Order 435.1 Low Level Radioactive Waste Disposal...

    Office of Environmental Management (EM)

    Introduction to DOE Order 435.1 Low Level Radioactive Waste Disposal Requirements Introduction to DOE Order 435.1 Low Level Radioactive Waste Disposal Requirements Christine ...

  2. HIGH ENERGY GASEOUS DISCHARGE DEVICES

    DOE Patents [OSTI]

    Josephson, V.

    1960-02-16

    The high-energy electrical discharge device described comprises an envelope, a pair of main discharge electrodes supported in opposition in the envelope, and a metallic shell symmetrically disposed around and spaced from the discharge path between the electrodes. The metallic shell comprises a first element of spaced helical turns of metallic material and a second element of spaced helical turns of methllic material insulatedly supported in superposition outside the first element and with the turns overlapping the gap between the turns of the first element.

  3. Historical Liquid Discharges and Outfalls

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    This drop-down provides the most current six months and six years of data for the table below. For complete history do one of the following: Click on a cell value in the table for the history of an individual data series. Click on the "Download All History" link for all data series shown in the table. Close Window

    Historical Liquid Discharges and Outfalls Historical Liquid Discharges and Outfalls During the 1940s and 1950s, untreated radioactive liquids were discharged to Pueblo and

  4. DISCHARGE DEVICE FOR RADIOACTIVE MATERIAL

    DOE Patents [OSTI]

    Ohlinger, L.A.

    1958-09-23

    A device is described fur unloading bodies of fissionable material from a neutronic reactor. It is comprised essentially of a wheeled flat car having a receptacle therein containing a liquid coolant fur receiving and cooling the fuel elements as they are discharged from the reactor, and a reciprocating plunger fur supporting the fuel element during discharge thereof prior to its being dropped into the coolant. The flat car is adapted to travel along the face of the reactor adjacent the discharge ends of the coolant tubes.

  5. Waste Determination Equivalency - 12172

    SciTech Connect (OSTI)

    Freeman, Rebecca D.

    2012-07-01

    Secretary of Energy in January of 2006 based on proposed processing techniques with the expectation that it could be revised as new processing capabilities became viable. Once signed, however, it became evident that any changes would require lengthy review and another determination signed by the Secretary of Energy. With the maturation of additional salt removal technologies and the extension of the SWPF start-up date, it becomes necessary to define 'equivalency' to the processes laid out in the original determination. For the purposes of SRS, any waste not processed through Interim Salt Processing must be processed through SWPF or an equivalent process, and therefore a clear statement of the requirements for a process to be equivalent to SWPF becomes necessary. (authors)

  6. Effluent and Discharges

    Broader source: Energy.gov [DOE]

    A question on DOE O 458.1, CRD, 2.g.(4). When performing the analysis, I envision performing a settleable solids test such as Standard Methods 2540 F, Settleable Solids, and then performing gross alpha and gross beta analysis. Is this the correct interpretation of the requirement or does isotopic analysis of the settleable solids need to be performed? Yes, this is a correct interpretation of the requirement. Guidance on this topic is provided in Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance (DOE/EH-0173T); January 1991).

  7. Hanford Dangerous Waste Permit

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Double-Shell Tank System 204-AR Waste Unloading Facility Operating Unit #12 241-AP Tank Farm construction. See black pickup trucks for scale. The DSTs have limited capacity and are aging. Maintaining these tanks is important to ensure that waste is ready to supply the Waste Treatment Plant. The permit requires continuous leak detection to protect humans and the environment. 200 West & East * 28 tanks in 6 groups, or tank farms. * Capacity: 1 - 1.2 million gallons each. * The double-shell

  8. Tank Waste and Waste Processing | Department of Energy

    Office of Environmental Management (EM)

    Tank Waste and Waste Processing Tank Waste and Waste Processing Tank Waste and Waste Processing The Defense Waste Processing Facility set a record by producing 267 canisters filled ...

  9. Radioactive waste storage issues

    SciTech Connect (OSTI)

    Kunz, D.E.

    1994-08-15

    In the United States we generate greater than 500 million tons of toxic waste per year which pose a threat to human health and the environment. Some of the most toxic of these wastes are those that are radioactively contaminated. This thesis explores the need for permanent disposal facilities to isolate radioactive waste materials that are being stored temporarily, and therefore potentially unsafely, at generating facilities. Because of current controversies involving the interstate transfer of toxic waste, more states are restricting the flow of wastes into - their borders with the resultant outcome of requiring the management (storage and disposal) of wastes generated solely within a state`s boundary to remain there. The purpose of this project is to study nuclear waste storage issues and public perceptions of this important matter. Temporary storage at generating facilities is a cause for safety concerns and underscores, the need for the opening of permanent disposal sites. Political controversies and public concern are forcing states to look within their own borders to find solutions to this difficult problem. Permanent disposal or retrievable storage for radioactive waste may become a necessity in the near future in Colorado. Suitable areas that could support - a nuclear storage/disposal site need to be explored to make certain the health, safety and environment of our citizens now, and that of future generations, will be protected.

  10. Application to ship nonmixed transuranic waste to the Nevada Test Site for interim storage. Waste Cerification Program

    SciTech Connect (OSTI)

    Not Available

    1993-12-01

    This report documents various regulations on radioactive waste processing and discusses how the Waste Isolation Pilot Plant will comply with and meet these requirements. Specific procedures are discussed concerning transuranic, metal scrap, salt block, solid, and glove box wastes.

  11. ROAD MAP FOR DEVELOPMENT OF CRYSTAL-TOLERANT HIGH LEVEL WASTE GLASSES

    SciTech Connect (OSTI)

    Fox, K.; Peeler, D.; Herman, C.

    2014-05-15

    The U.S. Department of Energy (DOE) is building a Tank Waste Treatment and Immobilization Plant (WTP) at the Hanford Site in Washington to remediate 55 million gallons of radioactive waste that is being temporarily stored in 177 underground tanks. Efforts are being made to increase the loading of Hanford tank wastes in glass while meeting melter lifetime expectancies and process, regulatory, and product quality requirements. This road map guides the research and development for formulation and processing of crystaltolerant glasses, identifying near- and long-term activities that need to be completed over the period from 2014 to 2019. The primary objective is to maximize waste loading for Hanford waste glasses without jeopardizing melter operation by crystal accumulation in the melter or melter discharge riser. The potential applicability to the Savannah River Site (SRS) Defense Waste Processing Facility (DWPF) will also be addressed in this road map. The planned research described in this road map is motivated by the potential for substantial economic benefits (significant reductions in glass volumes) that will be realized if the current constraints (T1% for WTP and TL for DWPF) are approached in an appropriate and technically defensible manner for defense waste and current melter designs. The basis of this alternative approach is an empirical model predicting the crystal accumulation in the WTP glass discharge riser and melter bottom as a function of glass composition, time, and temperature. When coupled with an associated operating limit (e.g., the maximum tolerable thickness of an accumulated layer of crystals), this model could then be integrated into the process control algorithms to formulate crystal-tolerant high-level waste (HLW) glasses targeting high waste loadings while still meeting process related limits and melter lifetime expectancies. The modeling effort will be an iterative process, where model form and a broader range of conditions, e.g., glass

  12. Transportation considerations related to waste forms and canisters for Defense TRU wastes

    SciTech Connect (OSTI)

    Schneider, K.J.; Andrews, W.B.; Schreiber, A.M.; Rosenthal, L.J.; Odle, C.J.

    1981-09-01

    This report identifies and discusses the considerations imposed by transportation on waste forms and canisters for contact-handled, solid transuranic wastes from the US Department of Energy (DOE) activities. The report reviews (1) the existing raw waste forms and potential immobilized waste forms, (2) the existing and potential future DOE waste canisters and shipping containers, (3) regulations and regulatory trends for transporting commercial transuranic wastes on the ISA, (4) truck and rail carrier requirements and preferences for transporting the wastes, and (5) current and proposed Type B external packagings for transporting wastes.

  13. Discharge cell for ozone generator

    DOE Patents [OSTI]

    Nakatsuka, Suguru

    2000-01-01

    A discharge cell for use in an ozone generator is provided which can suppress a time-related reduction in ozone concentration without adding a catalytic gas such as nitrogen gas to oxygen gas as a raw material gas. The discharge cell includes a pair of electrodes disposed in an opposed spaced relation with a discharge space therebetween, and a dielectric layer of a three-layer structure consisting of three ceramic dielectric layers successively stacked on at least one of the electrodes, wherein a first dielectric layer of the dielectric layer contacting the one electrode contains no titanium dioxide, wherein a second dielectric layer of the dielectric layer exposed to the discharge space contains titanium dioxide in a metal element ratio of not lower than 10 wt %.

  14. World nuclear fuel cycle requirements 1990

    SciTech Connect (OSTI)

    Not Available

    1990-10-26

    This analysis report presents the projected requirements for uranium concentrate and uranium enrichment services to fuel the nuclear power plants expected to be operating under three nuclear supply scenarios. Two of these scenarios, the Lower Reference and Upper Reference cases, apply to the United States, Canada, Europe, the Far East, and other countries with free market economies (FME countries). A No New Orders scenario is presented only for the United States. These nuclear supply scenarios are described in Commercial Nuclear Power 1990: Prospects for the United States and the World (DOE/EIA-0438(90)). This report contains an analysis of the sensitivities of the nuclear fuel cycle projections to different levels and types of projected nuclear capacity, different enrichment tails assays, higher and lower capacity factors, changes in nuclear fuel burnup levels, and other exogenous assumptions. The projections for the United States generally extend through the year 2020, and the FME projections, which include the United States, are provided through 2010. The report also presents annual projections of spent nuclear fuel discharges and inventories of spent fuel. Appendix D includes domestic spent fuel projections through the year 2030 for the Lower and Upper Reference cases and through 2040, the last year in which spent fuel is discharged, for the No New Orders case. These disaggregated projections are provided at the request of the Department of Energy's Office of Civilian Radioactive Waste Management.

  15. Magnetism in LithiumOxygen Discharge Product

    SciTech Connect (OSTI)

    Lu, Jun; Jung, Hun-Ji; Lau, Kah Chun; Zhang, Zhengcheng; Schlueter, John A.; Du, Peng; Assary, Rajeev S.; Greeley, Jeffrey P.; Ferguson, Glen A.; Wang, Hsien-Hau; Hassoun, Jusef; Iddir, Hakim; Zhou, Jigang; Zuin, Lucia; Hu, Yongfeng; Sun, Yang-Kook; Scrosati, Bruno; Curtiss, Larry A.; Amine, Khalil

    2013-05-13

    Nonaqueous lithiumoxygen batteries have a much superior theoretical gravimetric energy density compared to conventional lithium-ion batteries, and thus could render long-range electric vehicles a reality. A molecular-level understanding of the reversible formation of lithium peroxide in these batteries, the properties of major/minor discharge products, and the stability of the nonaqueous electrolytes is required to achieve successful lithiumoxygen batteries. We demonstrate that the major discharge product formed in the lithiumoxygen cell, lithium peroxide, exhibits a magnetic moment. These results are based on dc-magnetization measurements and a lithium oxygen cell containing an ether-based electrolyte. The results are unexpected because bulk lithium peroxide has a significant band gap. Density functional calculations predict that superoxide- type surface oxygen groups with unpaired electrons exist on stoichiometric lithium peroxide crystalline surfaces and on nanoparticle surfaces; these computational results are consistent with the magnetic measurement of the discharged lithium peroxide product as well as EPR measurements on commercial lithium peroxide. The presence of superoxide-type surface oxygen groups with spin can play a role in the reversible formation and decomposition of lithium peroxide as well as the reversible formation and decomposition of electrolyte molecules.

  16. Nevada Test Site Waste Acceptance Criteria

    SciTech Connect (OSTI)

    U. S. Department of Energy, National Nuclear Security Administration Nevada Site Office

    2005-10-01

    This document establishes the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) waste acceptance criteria (WAC). The WAC provides the requirements, terms, and conditions under which the Nevada Test Site (NTS) will accept low-level radioactive (LLW) and mixed waste (MW) for disposal. It includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the NTS Area 3 and Area 5 Radioactive Waste Management Complex (RWMC) for storage or disposal.

  17. Mixed Waste Working Group report

    SciTech Connect (OSTI)

    Not Available

    1993-11-09

    The treatment of mixed waste remains one of this country`s most vexing environmental problems. Mixed waste is the combination of radioactive waste and hazardous waste, as defined by the Resource Conservation and Recovery Act (RCRA). The Department of Energy (DOE), as the country`s largest mixed waste generator, responsible for 95 percent of the Nation`s mixed waste volume, is now required to address a strict set of milestones under the Federal Facility Compliance Act of 1992. DOE`s earlier failure to adequately address the storage and treatment issues associated with mixed waste has led to a significant backlog of temporarily stored waste, significant quantities of buried waste, limited permanent disposal options, and inadequate treatment solutions. Between May and November of 1993, the Mixed Waste Working Group brought together stakeholders from around the Nation. Scientists, citizens, entrepreneurs, and bureaucrats convened in a series of forums to chart a course for accelerated testing of innovative mixed waste technologies. For the first time, a wide range of stakeholders were asked to examine new technologies that, if given the chance to be tested and evaluated, offer the prospect for better, safer, cheaper, and faster solutions to the mixed waste problem. In a matter of months, the Working Group has managed to bridge a gap between science and perception, engineer and citizen, and has developed a shared program for testing new technologies.

  18. Desensitizing nano powders to electrostatic discharge ignition

    SciTech Connect (OSTI)

    Steelman, Ryan; Clark, Billy; Pantoya, Michelle L.; Heaps, Ronald J.; Daniels, Michael A.

    2015-08-01

    Electrostatic discharge (ESD) is a main cause for ignition in powder media ranging from grain silos to fireworks. Nanoscale particles are orders of magnitude more ESD ignition sensitive than their micron scale counterparts. This study shows that at least 13 vol. % carbon nanotubes (CNT) added to nano-aluminum and nano-copper oxide particles (nAl + CuO) eliminates ESD ignition sensitivity. The CNT act as a conduit for electric energy and directs electric charge through the powder to desensitize the reactive mixture to ignition. For nanoparticles, the required CNT concentration for desensitizing ESD ignition acts as a diluent to quench energy propagation.

  19. Hanford tank waste pretreatment overview

    SciTech Connect (OSTI)

    Gasper, K.A.

    1994-12-31

    The U.S. Department of Energy (DOE) has established the Tank Waste Remediation System (TWRS) to safely manage and dispose of the Hanford Site tank waste. Pretreatment is one of the major program elements of the TWRS. The scope of the TWRS Tank Waste Pretreatment Program is to treat tank waste to separate it into high- and low-level waste fractions and to provide additional treatment as required to feed low-level and high-level waste immobilization processes. The Pretreatment Program activities include technology development, design, fabrication, construction, and operation of facilities to support the pretreatment of radioactive mixed waste retrieved from 28 large underground double-shell tanks and 149 single-shell tanks.

  20. Formulation and Analysis of Compliant Grouted Waste Forms for SHINE Waste Streams

    SciTech Connect (OSTI)

    Ebert, William; Pereira, Candido; Heltemes, Thad A.; Youker, Amanda; Makarashvili, Vakhtang; Vandegrift, George F.

    2014-01-01

    Optional grouted waste forms were formulated for waste streams generated during the production of 99Mo to be compliant with low-level radioactive waste regulations. The amounts and dose rates of the various waste form materials that would be generated annually were estimated and used to determine the effects of various waste processing options, such as the of number irradiation cycles between uranium recovery operations, different combinations of waste streams, and removal of Pu, Cs, and Sr from waste streams for separate disposition (which is not evaluated in this report). These calculations indicate that Class C-compliant grouted waste forms can be produced for all waste streams. More frequent uranium recovery results in the generation of more chemical waste, but this is balanced by the fact that waste forms for those waste streams can accommodate higher waste loadings, such that similar amounts of grouted waste forms are required regardless of the recovery schedule. Similar amounts of grouted waste form are likewise needed for the individual and combined waste streams. Removing Pu, Cs, and Sr from waste streams lowers the waste form dose significantly at times beyond about 1 year after irradiation, which may benefit handling and transport. Although these calculations should be revised after experimentally optimizing the grout formulations and waste loadings, they provide initial guidance for process development.

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

    SciTech Connect (OSTI)

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

    1994-11-01

    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.

  2. Corrective Action Decision Document (CADD), Area 12 fleet operations steam cleaning discharge area, Nevada Test Site Corrective Action Unit 339

    SciTech Connect (OSTI)

    Bonn, J.F.

    1996-12-01

    This Corrective Action Decision Document (CADD) incorporates the methodology used for evaluating the remedial alternatives completed for a former steam cleaning discharge area at the Nevada Test Site (NTS). The former steam cleaning site is located in Area 12, east of the Fleet Operations Building 12-16. The discharge area has been impacted by Resource Conservation and Recovery Act (RCRA) F Listed volatile organic compounds (VOCs) and petroleum hydrocarbons waste. Based upon these findings, resulting from Phase 1 and Phase 2 site investigations, corrective action is required at the site. To determine the appropriate corrective action to be proposed, an evaluation of remedial alternatives was completed. The evaluation was completed using a Corrective Measures Study (CMS). Based on the results of the CMS, the favored closure alternative for the site is plugging the effluent discharge line, removing the sandbagged barrier, completing excavation of VOC impacted soils, and fencing the soil area impacted by total petroleum hydrocarbons (TPH), east of the discharge line and west of the soil berm. Management of the F Listed VOCs are dictated by RCRA. Due to the small volume of impacted soil, excavation and transportation to a Treatment Storage and Disposal Facility (TSDF) is the most practical method of management. It is anticipated that the TPH (as oil) impacted soils will remain in place based upon; the A through K Analysis, concentrations detected (maximum 8,600 milligrams per kilogram), expected natural degradation of the hydrocarbons over time, and the findings of the Phase 2 Investigation that vertical migration has been minimal.

  3. A case-study of landfill minimization and material recovery via waste co-gasification in a new waste management scheme

    SciTech Connect (OSTI)

    Tanigaki, Nobuhiro; Ishida, Yoshihiro; Osada, Morihiro

    2015-03-15

    Highlights: • A new waste management scheme and the effects of co-gasification of MSW were assessed. • A co-gasification system was compared with other conventional systems. • The co-gasification system can produce slag and metal with high-quality. • The co-gasification system showed an economic advantage when bottom ash is landfilled. • The sensitive analyses indicate an economic advantage when the landfill cost is high. - Abstract: This study evaluates municipal solid waste co-gasification technology and a new solid waste management scheme, which can minimize final landfill amounts and maximize material recycled from waste. This new scheme is considered for a region where bottom ash and incombustibles are landfilled or not allowed to be recycled due to their toxic heavy metal concentration. Waste is processed with incombustible residues and an incineration bottom ash discharged from existent conventional incinerators, using a gasification and melting technology (the Direct Melting System). The inert materials, contained in municipal solid waste, incombustibles and bottom ash, are recycled as slag and metal in this process as well as energy recovery. Based on this new waste management scheme with a co-gasification system, a case study of municipal solid waste co-gasification was evaluated and compared with other technical solutions, such as conventional incineration, incineration with an ash melting facility under certain boundary conditions. From a technical point of view, co-gasification produced high quality slag with few harmful heavy metals, which was recycled completely without requiring any further post-treatment such as aging. As a consequence, the co-gasification system had an economical advantage over other systems because of its material recovery and minimization of the final landfill amount. Sensitivity analyses of landfill cost, power price and inert materials in waste were also conducted. The higher the landfill costs, the greater the

  4. Lawrence Livermore National Laboratory (LLNL) Experimental Test Site (Site 300) Salinity Evaluation and Minimization Plan for Cooling Towers and Mechanical Equipment Discharges

    SciTech Connect (OSTI)

    Daily III, W D

    2010-02-24

    This document was created to comply with the Central Valley Regional Water Quality Control Board (CVRWQCB) Waste Discharge Requirement (Order No. 98-148). This order established new requirements to assess the effect of and effort required to reduce salts in process water discharged to the subsurface. This includes the review of technical, operational, and management options available to reduce total dissolved solids (TDS) concentrations in cooling tower and mechanical equipment water discharges at Lawrence Livermore National Laboratory's (LLNL's) Experimental Test Site (Site 300) facility. It was observed that for the six cooling towers currently in operation, the total volume of groundwater used as make up water is about 27 gallons per minute and the discharge to the subsurface via percolation pits is 13 gallons per minute. The extracted groundwater has a TDS concentration of 700 mg/L. The cooling tower discharge concentrations range from 700 to 1,400 mg/L. There is also a small volume of mechanical equipment effluent being discharged to percolation pits, with a TDS range from 400 to 3,300 mg/L. The cooling towers and mechanical equipment are maintained and operated in a satisfactory manner. No major leaks were identified. Currently, there are no re-use options being employed. Several approaches known to reduce the blow down flow rate and/or TDS concentration being discharged to the percolation pits and septic systems were reviewed for technical feasibility and cost efficiency. These options range from efforts as simple as eliminating leaks to implementing advanced and innovative treatment methods. The various options considered, and their anticipated effect on water consumption, discharge volumes, and reduced concentrations are listed and compared in this report. Based on the assessment, it was recommended that there is enough variability in equipment usage, chemistry, flow rate, and discharge configurations that each discharge location at Site 300 should be

  5. Constricted glow discharge plasma source

    DOE Patents [OSTI]

    Anders, Andre; Anders, Simone; Dickinson, Michael; Rubin, Michael; Newman, Nathan

    2000-01-01

    A constricted glow discharge chamber and method are disclosed. The polarity and geometry of the constricted glow discharge plasma source is set so that the contamination and energy of the ions discharged from the source are minimized. The several sources can be mounted in parallel and in series to provide a sustained ultra low source of ions in a plasma with contamination below practical detection limits. The source is suitable for applying films of nitrides such as gallium nitride and oxides such as tungsten oxide and for enriching other substances in material surfaces such as oxygen and water vapor, which are difficult process as plasma in any known devices and methods. The source can also be used to assist the deposition of films such as metal films by providing low-energy ions such as argon ions.

  6. Waste form product characteristics

    SciTech Connect (OSTI)

    Taylor, L.L.; Shikashio, R.

    1995-01-01

    The Department of Energy has operated nuclear facilities at the Idaho National Engineering Laboratory (INEL) to support national interests for several decades. Since 1953, it has supported the development of technologies for the storage and reprocessing of spent nuclear fuels (SNF) and the resultant wastes. However, the 1992 decision to discontinue reprocessing of SNF has left nearly 768 MT of SNF in storage at the INEL with unspecified plans for future dispositioning. Past reprocessing of these fuels for uranium and other resource recovery has resulted in the production of 3800 M{sup 3} calcine and a total inventory of 7600 M{sup 3} of radioactive liquids (1900 M{sup 3} destined for immediate calcination and the remaining sodium-bearing waste requiring further treatment before calcination). These issues, along with increased environmental compliance within DOE and its contractors, mandate operation of current and future facilities in an environmentally responsible manner. This will require satisfactory resolution of spent fuel and waste disposal issues resulting from the past activities. A national policy which identifies requirements for the disposal of SNF and high level wastes (HLW) has been established by the Nuclear Waste Policy Act (NWPA) Sec.8,(b) para(3)) [1982]. The materials have to be conditioned or treated, then packaged for disposal while meeting US Environmental Protection Agency (EPA) and Nuclear Regulatory Commission (NRC) regulations. The spent fuel and HLW located at the INEL will have to be put into a form and package that meets these regulatory criteria. The emphasis of Idaho Chemical Processing Plant (ICPP) future operations has shifted toward investigating, testing, and selecting technologies to prepare current and future spent fuels and waste for final disposal. This preparation for disposal may include mechanical, physical and/or chemical processes, and may differ for each of the various fuels and wastes.

  7. Ultraviolet radiation induced discharge laser

    DOE Patents [OSTI]

    Gilson, Verle A.; Schriever, Richard L.; Shearer, James W.

    1978-01-01

    An ultraviolet radiation source associated with a suitable cathode-anode electrode structure, disposed in a gas-filled cavity of a high pressure pulsed laser, such as a transverse electric atmosphere (TEA) laser, to achieve free electron production in the gas by photoelectric interaction between ultraviolet radiation and the cathode prior to the gas-exciting cathode-to-anode electrical discharge, thereby providing volume ionization of the gas. The ultraviolet radiation is produced by a light source or by a spark discharge.

  8. Compact monolithic capacitive discharge unit

    DOE Patents [OSTI]

    Roesler, Alexander W.; Vernon, George E.; Hoke, Darren A.; De Marquis, Virginia K.; Harris, Steven M.

    2007-06-26

    A compact monolithic capacitive discharge unit (CDU) is disclosed in which a thyristor switch and a flyback charging circuit are both sandwiched about a ceramic energy storage capacitor. The result is a compact rugged assembly which provides a low-inductance current discharge path. The flyback charging circuit preferably includes a low-temperature co-fired ceramic transformer. The CDU can further include one or more ceramic substrates for enclosing the thyristor switch and for holding various passive components used in the flyback charging circuit. A load such as a detonator can also be attached directly to the CDU.

  9. The Waste Isolation Pilot Plant Hazardous Waste Facility Permit...

    Office of Environmental Management (EM)

    The Waste Isolation Pilot Plant Hazardous Waste Facility Permit, Waste Analysis Plan The Waste Isolation Pilot Plant Hazardous Waste Facility Permit, Waste Analysis Plan This ...

  10. Electrostatic Discharge testing of propellants and primers

    SciTech Connect (OSTI)

    Berry, R.B.

    1994-02-01

    This report presents the results of testing of selected propellants and primers to Electrostatic Discharge (ESD) characteristic of the human body. It describes the tests and the fixturing built to accommodate loose material (propellants) and the packed energetic material of the primer. The results indicate that all powders passed and some primers, especially the electric primers, failed to pass established requirements which delineate insensitive energetic components. This report details the testing of components and materials to four ESD environments (Standard ESD, Severe ESD, Modified Standard ESD, and Modified Severe ESD). The purpose of this study was to collect data based on the customer requirements as defined in the Sandia Environmental Safety & Health (ES&H) Manual, Chapter 9, and to define static sensitive and insensitive propellants and primers.

  11. Cost effectiveness of silent discharge plasma for point-of-use VOC emissions control in semiconductor fabrication

    SciTech Connect (OSTI)

    Cummings, M.; Booth, S.R.

    1996-12-11

    Extensive research into the treatment and control of Volatile Organic Compounds (VOCs) from semiconductor industry manufacturing processes has identified the need for alternatives to existing combustion devices. Specifically, semiconductor manufacturing design is moving toward the application of effective, small-scale, abatement control technologies for specific point-of-use (POU) waste streams associated with a particular component or manufacturing tool. The consortium of companies involved in semiconductor precompetitive research and development known collectively as SEMATECH recently evaluated eleven emerging environmental technologies designed to treat POU process emissions of VOCs specific to the semiconductor industry. After rigorous technical review only one technology, the Silent Discharge Plasma (SDP) developed at Low Alamos National Laboratory, was considered to successfully meet the required technical performance standards and potential cost effectiveness necessary for continued consideration by SEMATECH in their point-of-use emissions control plans.

  12. INVESTIGATING SUSPENSION OF MST, CST, AND SIMULATED SLUDGE SLURRIES IN A PILOT-SCALE WASTE TANK

    SciTech Connect (OSTI)

    Poirier, M.; Qureshi, Z.; Restivo, M.; Steeper, T.; Williams, M.

    2011-05-24

    The Small Column Ion Exchange (SCIX) process is being developed to remove cesium, strontium, and actinides from Savannah River Site (SRS) Liquid Waste using an existing waste tank (i.e., Tank 41H) to house the process. Savannah River National Laboratory (SRNL) is conducting pilot-scale mixing tests to determine the pump requirements for suspending and resuspending monosodium titanate (MST), crystalline silicotitanate (CST), and simulated sludge. The purpose of this pilot scale testing is for the pumps to resuspend the MST, CST, and simulated sludge particles so that they can be removed from the tank, and to suspend the MST so it can contact strontium and actinides. The pilot-scale tank is a 1/10.85 linear scaled model of Tank 41H. The tank diameter, tank liquid level, pump nozzle diameter, pump elevation, and cooling coil diameter are all 1/10.85 of their dimensions in Tank 41H. The pump locations correspond to the proposed locations in Tank 41H by the SCIX program (Risers B5, B3, and B1). Previous testing showed that three Submersible Mixer Pumps (SMPs) will provide sufficient power to initially suspend MST in an SRS waste tank, and to resuspend MST that has settled in a waste tank at nominal 45 C for four weeks. The conclusions from this analysis are: (1) Three SMPs will be able to resuspend more than 99.9% of the MST and CST that has settled for four weeks at nominal 45 C. The testing shows the required pump discharge velocity is 84% of the maximum discharge velocity of the pump. (2) Three SMPs will be able to resuspend more than 99.9% of the MST, CST, and simulated sludge that has settled for four weeks at nominal 45 C. The testing shows the required pump discharge velocity is 82% of the maximum discharge velocity of the pump. (3) A contact time of 6-12 hours is needed for strontium sorption by MST in a jet mixed tank with cooling coils, which is consistent with bench-scale testing and actinide removal process (ARP) operation.

  13. Hanford site transuranic waste certification plan

    SciTech Connect (OSTI)

    GREAGER, T.M.

    1999-05-12

    As a generator of transuranic (TRU) and TRU mixed waste destined for disposal at the Waste Isolation Pilot Plant (WIPP), the Hanford Site must ensure that its TRU waste meets the requirements of U.S. Department of Energy (DOE) Order 5820.2A, ''Radioactive Waste Management, and the Waste Acceptance Criteria for the Waste Isolation Pilot Plant' (DOE 1996d) (WIPP WAC). The WIPP WAC establishes the specific physical, chemical, radiological, and packaging criteria for acceptance of defense TRU waste shipments at WIPP. The WIPP WAC also requires that participating DOE TRU waste generator/treatment/storage sites produce site-specific documents, including a certification plan, that describe their management of TRU waste and TRU waste shipments before transferring waste to WIPP. The Hanford Site must also ensure that its TRU waste destined for disposal at WIPP meets requirements for transport in the Transuranic Package Transporter41 (TRUPACT-11). The U.S. Nuclear Regulatory Commission (NRC) establishes the TRUPACT-I1 requirements in the ''Safety Analysis Report for the TRUPACT-II Shipping Package'' (NRC 1997) (TRUPACT-I1 SARP).

  14. Transuranic Waste Characterization Quality Assurance Program Plan

    SciTech Connect (OSTI)

    NONE

    1995-04-30

    This quality assurance plan identifies the data necessary, and techniques designed to attain the required quality, to meet the specific data quality objectives associated with the DOE Waste Isolation Pilot Plant (WIPP). This report specifies sampling, waste testing, and analytical methods for transuranic wastes.

  15. RMACS software requirements specification

    SciTech Connect (OSTI)

    Gneiting, B.C.

    1996-10-01

    This document defines the essential user (or functional) requirements of the Requirements Management and Assured Compliance System (RMACS), which is used by the Tank Waste Remediation System program (TWRS). RMACS provides a computer-based environment that TWRS management and systems engineers can use to identify, define, and document requirements. The intent of the system is to manage information supporting definition of the TWRS technical baseline using a structured systems engineering process. RMACS has the capability to effectively manage a complete set of complex requirements and relationships in a manner that satisfactorily assures compliance to the program requirements over the TWRS life-cycle.

  16. Nevada National Security Site Waste Acceptance Criteria

    SciTech Connect (OSTI)

    NSTec Environmental Management

    2011-01-01

    This document establishes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) Nevada National Security Site Waste Acceptance Criteria (NNSSWAC). The NNSSWAC provides the requirements, terms, and conditions under which the Nevada National Security Site (NNSS) will accept low-level radioactive waste and mixed low-level waste for disposal. The NNSSWAC includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the NNSS Area 3 and Area 5 Radioactive Waste Management Complex for disposal. The NNSA/NSO and support contractors are available to assist you in understanding or interpreting this document. For assistance, please call the NNSA/NSO Waste Management Project at (702) 295-7063 or fax to (702) 295-1153.

  17. Nevada National Security Site Waste Acceptance Criteria

    SciTech Connect (OSTI)

    NSTec Environmental Management

    2010-09-03

    This document establishes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) Nevada National Security Site Waste Acceptance Criteria (NNSSWAC). The NNSSWAC provides the requirements, terms, and conditions under which the Nevada National Security Site (NNSS) will accept low-level radioactive waste and mixed low-level waste for disposal. The NNSSWAC includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the NNSS Area 3 and Area 5 Radioactive Waste Management Complex for disposal. The NNSA/NSO and support contractors are available to assist you in understanding or interpreting this document. For assistance, please call the NNSA/NSO Waste Management Project at (702) 295-7063 or fax to (702) 295-1153.

  18. Radioactive Waste Management BasisApril 2006

    SciTech Connect (OSTI)

    Perkins, B K

    2011-08-31

    This Radioactive Waste Management Basis (RWMB) documents radioactive waste management practices adopted at Lawrence Livermore National Laboratory (LLNL) pursuant to Department of Energy (DOE) Order 435.1, Radioactive Waste Management. The purpose of this Radioactive Waste Management Basis is to describe the systematic approach for planning, executing, and evaluating the management of radioactive waste at LLNL. The implementation of this document will ensure that waste management activities at LLNL are conducted in compliance with the requirements of DOE Order 435.1, Radioactive Waste Management, and the Implementation Guide for DOE Manual 435.1-1, Radioactive Waste Management Manual. Technical justification is provided where methods for meeting the requirements of DOE Order 435.1 deviate from the DOE Manual 435.1-1 and Implementation Guide.

  19. 2013 Annual Industrial Wastewater Reuse Report for the Idaho National Laboratory Site’s Materials and Fuels Complex Industrial Waste Ditch and Industrial Waste Pond

    SciTech Connect (OSTI)

    Mike Lewis

    2014-02-01

    This report describes conditions, as required by the state of Idaho Industrial Wastewater Reuse Permit (WRU-I-0160-01, formerly LA 000160 01), for the wastewater reuse site at the Idaho National Laboratory Site’s Materials and Fuels Complex Industrial Waste Ditch and Industrial Waste Pond from November 1, 2012 through October 31, 2013. The report contains the following information: • Facility and system description • Permit required effluent monitoring data and loading rates • Groundwater monitoring data • Status of special compliance conditions • Discussion of the facility’s environmental impacts During the 2013 reporting year, an estimated 9.64 million gallons of wastewater were discharged to the Industrial Waste Ditch and Pond which is well below the permit limit of 17 million gallons per year. The concentrations of all permit-required analytes in the samples from the down gradient monitoring wells were below the applicable Idaho Department of Environmental Quality’s groundwater quality standard levels.

  20. Optimization of biological recycling of plant nutrients in livestock waste by utilizing waste heat from cooling water

    SciTech Connect (OSTI)

    Maddox, J.J.; Behrends, L.L.; Burch, D.W.; Kingsley, J.B.; Waddell, E.L. Jr.

    1982-05-01

    Results are presented from a 5-year study to develop aquatic methods which beneficially use condenser cooling water from electric generating power plants. A method is proposed which uses a system for aquatic farming. Livestock waste is used to fertilize planktonic algae production and filter-feeding fish are used to biologically harvest the algae, condenser cooling water (simulated) is used to add waste heat to the system, and emergent aquatic plants are used in a flow through series as a bio-filter to improve the water quality and produce an acceptable discharge. Two modes of operation were tested; one uses untreated swine manure as the source of aquatic fertilizer and the other uses anaerobic digester waste as a means of pretreating the manure to produce an organic fertilizer. A set of operating conditions (temperature, retention time, fish stocking rate, fertilizer rates, land and water requirements, suggested fish and plant species, and facility design) were developed from these results. The integrated system allows continual use of power plant condenser cooling water from plants in the southeastern United States.

  1. 2011 Annual Industrial Wastewater Reuse Report for the Idaho National Laboratory Site's Advanced Test Reactor Complex Cold Waste Pond

    SciTech Connect (OSTI)

    Mike Lewis

    2012-02-01

    This report describes conditions, as required by the state of Idaho Industrial Wastewater Reuse Permit (LA 000161 01, Modification B), for the wastewater land application site at the Idaho National Laboratory Site's Advanced Test Reactor Complex Cold Waste Pond from November 1, 2010 through October 31, 2011. The report contains the following information: Facility and system description Permit required effluent monitoring data and loading rates Groundwater monitoring data Status of compliance activities Noncompliance and other issues Discussion of the facility's environmental impacts During the 2011 permit year, approximately 166 million gallons of wastewater were discharged to the Cold Waste Pond. This is well below the maximum annual permit limit of 375 million gallons. As shown by the groundwater sampling data, sulfate and total dissolved solids concentrations are highest near the Cold Waste Pond and decrease rapidly as the distance from the Cold Waste Pond increases. Although concentrations of sulfate and total dissolved solids are elevated near the Cold Waste Pond, both parameters were below the Ground Water Quality Rule Secondary Constituent Standards in the down gradient monitoring wells.

  2. 2012 Annual Industrial Wastewater Reuse Report for the Idaho National Laboratory Site's Advanced Test Reactor Complex Cold Waste Pond

    SciTech Connect (OSTI)

    Mike Lewis

    2013-02-01

    This report describes conditions, as required by the state of Idaho Industrial Wastewater Reuse Permit (#LA 000161 01, Modification B), for the wastewater land application site at the Idaho National Laboratory Site’s Advanced Test Reactor Complex Cold Waste Pond from November 1, 2011 through October 31, 2012. The report contains the following information: Facility and system description Permit required effluent monitoring data and loading rates Groundwater monitoring data Status of compliance activities Noncompliance issues Discussion of the facility’s environmental impacts During the 2012 permit year, approximately 183 million gallons of wastewater were discharged to the Cold Waste Pond. This is well below the maximum annual permit limit of 375 million gallons. As shown by the groundwater sampling data, sulfate and total dissolved solids concentrations are highest near the Cold Waste Pond and decrease rapidly as the distance from the Cold Waste Pond increases. Although concentrations of sulfate and total dissolved solids are elevated near the Cold Waste Pond, both parameters were below the Ground Water Quality Rule Secondary Constituent Standards in the down gradient monitoring wells.

  3. Naval Waste Package Design Report

    SciTech Connect (OSTI)

    M.M. Lewis

    2004-03-15

    A design methodology for the waste packages and ancillary components, viz., the emplacement pallets and drip shields, has been developed to provide designs that satisfy the safety and operational requirements of the Yucca Mountain Project. This methodology is described in the ''Waste Package Design Methodology Report'' Mecham 2004 [DIRS 166168]. To demonstrate the practicability of this design methodology, four waste package design configurations have been selected to illustrate the application of the methodology. These four design configurations are the 21-pressurized water reactor (PWR) Absorber Plate waste package, the 44-boiling water reactor (BWR) waste package, the 5-defense high-level waste (DHLW)/United States (U.S.) Department of Energy (DOE) spent nuclear fuel (SNF) Co-disposal Short waste package, and the Naval Canistered SNF Long waste package. Also included in this demonstration is the emplacement pallet and continuous drip shield. The purpose of this report is to document how that design methodology has been applied to the waste package design configurations intended to accommodate naval canistered SNF. This demonstrates that the design methodology can be applied successfully to this waste package design configuration and support the License Application for construction of the repository.

  4. Contact-Handled and Remote-Handled Transuranic Waste Packaging

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2011-08-09

    Provides specific instructions for packaging and/or repackaging contact-handled transuranic (CH-TRU) and remote-handled transuranic (RH-TRU) waste in a manner consistent with DOE O 435.1, Radioactive Waste Management, DOE M 435.1-1 Chg 1, Radioactive Waste Management Manual, CH-TRU and RH-TRU waste transportation requirements, and Waste Isolation Pilot Plant (WIPP) programmatic requirements. Does not cancel/supersede other directives.

  5. Solid Waste Management Program Plan

    SciTech Connect (OSTI)

    Duncan, D.R.

    1990-08-01

    The objective of the Solid Waste Management Program Plan (SWMPP) is to provide a summary level comprehensive approach for the storage, treatment, and disposal of current and future solid waste received at the Hanford Site (from onsite and offsite generators) in a manner compliant with current and evolving regulations and orders (federal, state, and Westinghouse Hanford Company (Westinghouse Hanford)). The Plan also presents activities required for disposal of selected wastes currently in retrievable storage. The SWMPP provides a central focus for the description and control of cost, scope, and schedule of Hanford Site solid waste activities, and provides a vehicle for ready communication of the scope of those activities to onsite and offsite organizations. This Plan represents the most complete description available of Hanford Site Solid Waste Management (SWM) activities and the interfaces between those activities. It will be updated annually to reflect changes in plans due to evolving regulatory requirements and/or the SWM mission. 8 refs., 9 figs., 4 tabs.

  6. Acceptable knowledge document for INEEL stored transuranic waste -- Rocky Flats Plant waste. Revision 2

    SciTech Connect (OSTI)

    1998-01-23

    This document and supporting documentation provide a consistent, defensible, and auditable record of acceptable knowledge for waste generated at the Rocky Flats Plant which is currently in the accessible storage inventory at the Idaho National Engineering and Environmental Laboratory. The inventory consists of transuranic (TRU) waste generated from 1972 through 1989. Regulations authorize waste generators and treatment, storage, and disposal facilities to use acceptable knowledge in appropriate circumstances to make hazardous waste determinations. Acceptable knowledge includes information relating to plant history, process operations, and waste management, in addition to waste-specific data generated prior to the effective date of the RCRA regulations. This document is organized to provide the reader a comprehensive presentation of the TRU waste inventory ranging from descriptions of the historical plant operations that generated and managed the waste to specific information about the composition of each waste group. Section 2 lists the requirements that dictate and direct TRU waste characterization and authorize the use of the acceptable knowledge approach. In addition to defining the TRU waste inventory, Section 3 summarizes the historical operations, waste management, characterization, and certification activities associated with the inventory. Sections 5.0 through 26.0 describe the waste groups in the inventory including waste generation, waste packaging, and waste characterization. This document includes an expanded discussion for each waste group of potential radionuclide contaminants, in addition to other physical properties and interferences that could potentially impact radioassay systems.

  7. Disposal of NORM waste in salt caverns

    SciTech Connect (OSTI)

    Veil, J.A.; Smith, K.P.; Tomasko, D.; Elcock, D.; Blunt, D.; Williams, G.P.

    1998-07-01

    Some types of oil and gas production and processing wastes contain naturally occurring radioactive materials (NORM). If NORM is present at concentrations above regulatory levels in oil field waste, the waste requires special disposal practices. The existing disposal options for wastes containing NORM are limited and costly. This paper evaluates the legality, technical feasibility, economics, and human health risk of disposing of NORM-contaminated oil field wastes in salt caverns. Cavern disposal of NORM waste is technically feasible and poses a very low human health risk. From a legal perspective, there are no fatal flaws that would prevent a state regulatory agency from approving cavern disposal of NORM. On the basis of the costs charged by caverns currently used for disposal of nonhazardous oil field waste (NOW), NORM waste disposal caverns could be cost competitive with existing NORM waste disposal methods when regulatory agencies approve the practice.

  8. Low-level-waste-form criteria

    SciTech Connect (OSTI)

    Barletta, R.E.; Davis, R.E.

    1982-01-01

    Efforts in five areas are reported: technical considerations for a high-integrity container for resin wastes; permissible radionuclide loadings for organic ion exchange resin wastes; technical factors affecting low-level waste form acceptance requirements of the proposed 10 CFR 61 and draft BTP; modeling of groundwater transport; and analysis of soils from low-level waste disposal sites (Barnwell, Hanford, and Sheffield). (DLC)

  9. Office of Civilian Radioactive Waste Management-Quality Assurance

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Requirements and Description | Department of Energy Management-Quality Assurance Requirements and Description Office of Civilian Radioactive Waste Management-Quality Assurance Requirements and Description A report detailling the requirements and description of the Quality Assurance program. Office of Civilian Radioactive Waste Management-Quality Assurance Requirements and Description (566.23 KB) More Documents & Publications Quality Assurance Requirements Civilian Radioactive Waste

  10. A perspective of hazardous waste and mixed waste treatment technology at the Savannah River Site

    SciTech Connect (OSTI)

    England, J.L.; Venkatesh, S.; Bailey, L.L.; Langton, C.A.; Hay, M.S.; Stevens, C.B.; Carroll, S.J.

    1991-12-31

    Treatment technologies for the preparation and treatment of heavy metal mixed wastes, contaminated soils, and mixed mercury wastes are being considered at the Savannah River Site (SRS), a DOE nuclear material processing facility operated by Westinghouse Savannah River Company (WSRC). The proposed treatment technologies to be included at the Hazardous Waste/Mixed Waste Treatment Building at SRS are based on the regulatory requirements, projected waste volumes, existing technology, cost effectiveness, and project schedule. Waste sorting and size reduction are the initial step in the treatment process. After sorting/size reduction the wastes would go to the next applicable treatment module. For solid heavy metal mixed wastes the proposed treatment is macroencapsulation using a thermoplastic polymer. This process reduces the leachability of hazardous constituents from the waste and allows easy verification of the coating integrity. Stabilization and solidification in a cement matrix will treat a wide variety of wastes (i.e. soils, decontamination water). Some pretreatments may be required (i.e. Ph adjustment) before stabilization. Other pretreatments such as soil washing can reduce the amount of waste to be stabilized. Radioactive contaminated mercury waste at the SRS comes in numerous forms (i.e. process equipment, soils, and lab waste) with the required treatment of high mercury wastes being roasting/retorting and recovery. Any unrecyclable radioactive contaminated elemental mercury would be amalgamated, utilizing a batch system, before disposal.

  11. A perspective of hazardous waste and mixed waste treatment technology at the Savannah River Site

    SciTech Connect (OSTI)

    England, J.L.; Venkatesh, S.; Bailey, L.L.; Langton, C.A.; Hay, M.S.; Stevens, C.B.; Carroll, S.J.

    1991-01-01

    Treatment technologies for the preparation and treatment of heavy metal mixed wastes, contaminated soils, and mixed mercury wastes are being considered at the Savannah River Site (SRS), a DOE nuclear material processing facility operated by Westinghouse Savannah River Company (WSRC). The proposed treatment technologies to be included at the Hazardous Waste/Mixed Waste Treatment Building at SRS are based on the regulatory requirements, projected waste volumes, existing technology, cost effectiveness, and project schedule. Waste sorting and size reduction are the initial step in the treatment process. After sorting/size reduction the wastes would go to the next applicable treatment module. For solid heavy metal mixed wastes the proposed treatment is macroencapsulation using a thermoplastic polymer. This process reduces the leachability of hazardous constituents from the waste and allows easy verification of the coating integrity. Stabilization and solidification in a cement matrix will treat a wide variety of wastes (i.e. soils, decontamination water). Some pretreatments may be required (i.e. Ph adjustment) before stabilization. Other pretreatments such as soil washing can reduce the amount of waste to be stabilized. Radioactive contaminated mercury waste at the SRS comes in numerous forms (i.e. process equipment, soils, and lab waste) with the required treatment of high mercury wastes being roasting/retorting and recovery. Any unrecyclable radioactive contaminated elemental mercury would be amalgamated, utilizing a batch system, before disposal.

  12. Electrostatic discharge testing of electroexplosive devices

    SciTech Connect (OSTI)

    Hingorani, S.L.

    1990-01-01

    Electrostatic discharge (ESD) testing of electroexplosive devices has previously been regarded as single pulse, go/no-go testing, the emphasis being on the safety of the devices when exposed to human handling. For some components it has been found to be a destructive test; for others the test is performed 100% in production product-acceptance testing and is considered a nondestructive and nondegrading test if the component does not fire. Recent studies performed by R. J. Fisher at Sandia have resulted in a new model of the worst case human body electrostatic discharge that is more accurate than the model that is currently in use for testing electroexplosive components. In addition, recent requirements for no degradation or loss of reliability after multiple exposures (up to 100) have changed the go/no-go nature of the test. Several components have been tested to the new ESD model; results regarding both safety and reliability will be presented and discussed. 9 refs., 7 figs., 2 tabs.

  13. Waste certification: Who really is on first?

    SciTech Connect (OSTI)

    Smith, M.A.

    1989-11-01

    Waste certification is the process of stating whether or not a given waste package meets the acceptance criteria of whatever facility is receiving the package. Establishing a program for certification of low-level waste requires coordination of a variety of requirements and limitations, including regulations, physical characteristics of the waste and of the type of radiation emitted by radionuclides in the waste, uncertainty in measurements, quality assurance, and personnel exposures. The goal of such a program must be to provide an acceptable degree of assurance that the waste generating facility will be able to convince the waste receiving facility that individual waste packages do meet the applicable waste acceptance criteria. The preceding paragraph raises many questions: what is an acceptable degree of assurance? What does one have to do to convince a receiving facility? How can the measurement uncertainty be taken into account? This paper attempts to address several of those questions in the context of the development being done in the solid low-level waste (SLLW) certification program at the Oak Ridge National Laboratory (ORNL). First, a brief history of the SLLW certification program at ORNL is presented. The remaining discussions are devoted to considering the problems and pitfalls of implementing a waste certification program, concentrating on such areas as the responsibilities of various organizations and individuals, waste characterization techniques, handling levels of uncertainty, and development of waste acceptance criteria.

  14. Office of Civilian Radioactive Waste Management-Quality Assurance...

    Energy Savers [EERE]

    Quality Assurance Requirements Civilian Radioactive Waste Management System Requirements Document Root Cause Analysis Report In Response to Condition Report 5223 Regarding Emails ...

  15. Corrective Action Plan for Corrective Action Unit 262: Area 25 Septic Systems and Underground Discharge Point, Nevada Test Site, Nevada

    SciTech Connect (OSTI)

    K. B. Campbell

    2002-06-01

    This Corrective Action Plan (CAP) provides selected corrective action alternatives and proposes the closure methodology for Corrective Action Unit (CAU) 262, Area 25 Septic Systems and Underground Discharge Point. CAU 262 is identified in the Federal Facility Agreement and Consent Order (FFACO) of 1996. Remediation of CAU 262 is required under the FFACO. CAU 262 is located in Area 25 of the Nevada Test Site (NTS), approximately 100 kilometers (km) (62 miles [mi]) northwest of Las Vegas, Nevada. The nine Corrective Action Sites (CASs) within CAU 262 are located in the Nuclear Rocket Development Station complex. Individual CASs are located in the vicinity of the Reactor Maintenance, Assembly, and Disassembly (R-MAD); Engine Maintenance, Assembly, and Disassembly (E-MAD); and Test Cell C compounds. CAU 262 includes the following CASs as provided in the FFACO (1996); CAS 25-02-06, Underground Storage Tank; CAS 25-04-06, Septic Systems A and B; CAS 25-04-07, Septic System; CAS 25-05-03, Leachfield; CAS 25-05-05, Leachfield; CAS 25-05-06, Leachfield; CAS 25-05-08, Radioactive Leachfield; CAS 25-05-12, Leachfield; and CAS 25-51-01, Dry Well. Figures 2, 3, and 4 show the locations of the R-MAD, the E-MAD, and the Test Cell C CASs, respectively. The facilities within CAU 262 supported nuclear rocket reactor engine testing. Activities associated with the program were performed between 1958 and 1973. However, several other projects used the facilities after 1973. A significant quantity of radioactive and sanitary waste was produced during routine operations. Most of the radioactive waste was managed by disposal in the posted leachfields. Sanitary wastes were disposed in sanitary leachfields. Septic tanks, present at sanitary leachfields (i.e., CAS 25-02-06,2504-06 [Septic Systems A and B], 25-04-07, 25-05-05,25-05-12) allowed solids to settle out of suspension prior to entering the leachfield. Posted leachfields do not contain septic tanks. All CASs located in CAU 262 are

  16. PUREX low-level waste radionuclide characterization

    SciTech Connect (OSTI)

    Ellis, M.W.; LeBaron, G.J.

    1995-01-16

    The PUREX low-level waste (LLW) radionuclide characterization document describes the methodology for the characterization of solid LLW and solid low-level mixed waste (MW) with the respect to radiological characteristics. This document only serves as an overview of the PUREX radionuclide characterization methodology and provides specific examples for how the radionuclide distribution is derived. It would be impractical to provide all background information in this document. If further clarification and background information is required, consult the PUREX Regulatory Compliance group files. This document applies to only that waste generated in or is the responsibility of the PUREX facilities. The US Department of Energy (DOE) establishes the requirements for radioactive solid waste in DOE Order 5820.2A Radioactive Waste Management. Chapters 2 and 3 from DOE Order 5820.2A requires that generators of solid wastes in the LLW categories and the radioactive mixed waste subcategories: (1) identify the major radionuclides in each solid waste matrix and (2) determine the radionuclide concentrations and waste classes of their solid wastes. In addition, the Order also requires each generator to carry out a compliance program that ensures the proper certification of the solid waste generated.

  17. Interaction between pulsed discharge and radio frequency discharge burst at atmospheric pressure

    SciTech Connect (OSTI)

    Zhang, Jie; Guo, Ying; Shi, Yuncheng; Zhang, Jing; Shi, J. J.

    2015-08-15

    The atmospheric pressure glow discharges (APGD) with dual excitations in terms of pulsed voltage and pulse-modulation radio frequency (rf) power are studied experimentally between two parallel plates electrodes. Pulse-modulation applied in rf APGD temporally separates the discharge into repetitive discharge bursts, between which the high voltage pulses are introduced to ignite sub-microsecond pulsed discharge. The discharge characteristics and spatio-temporal evolution are investigated by means of current voltage characteristics and time resolved imaging, which suggests that the introduced pulsed discharge assists the ignition of rf discharge burst and reduces the maintain voltage of rf discharge burst. Furtherly, the time instant of pulsed discharge between rf discharge bursts is manipulated to study the ignition dynamics of rf discharge burst.

  18. The Waste Isolation Pilot Plant Hazardous Waste Facility Permit, Waste

    Office of Environmental Management (EM)

    Analysis Plan | Department of Energy The Waste Isolation Pilot Plant Hazardous Waste Facility Permit, Waste Analysis Plan The Waste Isolation Pilot Plant Hazardous Waste Facility Permit, Waste Analysis Plan This document was used to determine facts and conditions during the Department of Energy Accident Investigation Board's investigation into the radiological release event at the Waste Isolation Pilot Plant. Additional documents referenced and listed in the Phase 2 Radiological Release

  19. BERNAS ION SOURCE DISCHARGE SIMULATION

    SciTech Connect (OSTI)

    RUDSKOY,I.; KULEVOY, T.V.; PETRENKO, S.V.; KUIBEDA, R.P.; SELEZNEV, D.N.; PERSHIN, V.I.; HERSHCOVITCH, A.; JOHNSON, B.M.; GUSHENETS, V.I.; OKS, E.M.; POOLE, H.J.

    2007-08-26

    The joint research and development program is continued to develop steady-state ion source of decaborane beam for ion implantation industry. Bemas ion source is the wide used ion source for ion implantation industry. The new simulation code was developed for the Bemas ion source discharge simulation. We present first results of the simulation for several materials interested in semiconductors. As well the comparison of results obtained with experimental data obtained at the ITEP ion source test-bench is presented.

  20. Cold cathode vacuum discharge tube

    DOE Patents [OSTI]

    Boettcher, Gordon E.

    1998-01-01

    A cold cathode vacuum discharge tube, and method for making same, with an interior surface of the trigger probe coated with carbon deposited by carbon vapor deposition (CVD) or diamond-like carbon (DLC) deposition. Preferably a solid graphite insert is employed in the probe-cathode structure in place of an aluminum bushing employed in the prior art. The CVD or DLC probe face is laser scribed to allow resistance trimming to match available trigger voltage signals and to reduce electrical aging.

  1. A Compact Reactor Gate Discharge Monitor for Spent Fuel.

    SciTech Connect (OSTI)

    Franco, J. B.; Menlove, Howard O.; Eccleston, G. W.; Miller, M. C.

    2005-01-01

    This paper presents a new design for a reactor gate discharge monitor that has evolved from the baseline discharge monitors used at the Fugen and Tokai-1 reactors in Japan. The main design innovation is the ability to determine direction-of-motion of spent fuel using a single sensor module, as opposed to the two modules used in both baseline design systems. Use of a single module reduces the final system complexity and weight significantly without compromising functionality. The reactor gate discharge monitor uses standard International Atomic Energy Agency (IAEA) hardware and software components. The requirements to determine direction-of-motion from a single module precipitated several development efforts described herein in both the MiniGRAND data acquisition hardware and in the uninterruptible power supply source.

  2. Waste Handeling Building Conceptual Study

    SciTech Connect (OSTI)

    G.W. Rowe

    2000-11-06

    The objective of the ''Waste Handling Building Conceptual Study'' is to develop proposed design requirements for the repository Waste Handling System in sufficient detail to allow the surface facility design to proceed to the License Application effort if the proposed requirements are approved by DOE. Proposed requirements were developed to further refine waste handling facility performance characteristics and design constraints with an emphasis on supporting modular construction, minimizing fuel inventory, and optimizing facility maintainability and dry handling operations. To meet this objective, this study attempts to provide an alternative design to the Site Recommendation design that is flexible, simple, reliable, and can be constructed in phases. The design concept will be input to the ''Modular Design/Construction and Operation Options Report'', which will address the overall program objectives and direction, including options and issues associated with transportation, the subsurface facility, and Total System Life Cycle Cost. This study (herein) is limited to the Waste Handling System and associated fuel staging system.

  3. Environmental and economic assessment of discharges from Gulf of Mexico region oil and gas operations. Quarterly technical progress report, April 1995--June 1995

    SciTech Connect (OSTI)

    Gettleson, D.A.

    1995-07-31

    Progress is described on the determination of environmental impacts from waste discharges to the aquatic ecosystems from oil and gas operations. Task 2 (Preparation of the Sampling and Analysis Plan) activities involved revisions and additions to the Sampling and Analysis Plan. Task 3 (Environmental Field Sampling and Analysis of NORM, Heavy Metals, and Organics) work included analyses of water, sediment, and tissue samples as well as data management. Task 4 (Monitoring of the Recovery of Impacted Wetland and Open Bay Produced Water Discharge Sites in Coastal Louisiana and Texas) activities involved the continued analyses of samples and conducting field sampling at Bay de Chene. Task 5 (Assessment of Economic Impacts of Offshore and Coastal Discharge Requirements on Present and Future Operations in the Gulf of Mexico Region) activities included preparing a draft final report and review by the Scientific Review Committee (SRC). Task 6 (Synthesis of Gulf of Mexico Seafood Consumption and Use Patterns) work involved the preparation of the draft final report and review by the SRC. Task 7 (Technology Transfer Plan) activities involved the presentation of four papers. Task 8 (Project Management and Deliverables) activities involved the submission of the necessary reports and routine management.

  4. Identification of radioactive mixed wastes in commercial low-level wastes

    SciTech Connect (OSTI)

    Bowerman, B.S.; Kempf, C.R.; MacKenzie, D.R.; Siskind, B.; Piciulo, P.L.

    1986-01-01

    A literature review and survey were conducted on behalf of the US NRC Division of Waste Management to determine whether any commercial low-level radioactive wastes (LLW) could be considered hazardous as defined by EPA under 40 CFR Part 261. The purpose of the study was to identify broad categories of LLW which may require special management as radioactive mixed waste, and to help address uncertainties regarding the regulation of such wastes. Of 239 questionnaires sent out to reactor and non-reactor LLW generators, there were 91 responses representing 29% by volume of all low-level wastes disposed of at commercial disposal sites in 1984. The analysis of the survey results indicated that the following waste types generic to commercial LLW may be potential radioactive mixed wastes: Wastes containing oil, disposed of by reactors and industrial facilities, and representing 4.2% of the total LLW volume reported in the survey. Wastes containing organic liquids, disposed of by all types of generators, and representing 2.3% by volume of all wastes reported. Wastes containing lead metal, i.e., discarded shielding and lead containers, representing <0.1% by volume of all wastes reported. Wastes containing chromium, i.e., process wastes from nuclear power plants which use chromates as corrosion inhibitors; these represent 0.6% of the total volume reported in the survey. Certain wastes, specific to particular generators, were identified as potential mixed wastes as well.

  5. TRU waste acceptance criteria for the Waste Isolation Pilot Plant: Revision 3

    SciTech Connect (OSTI)

    Not Available

    1989-01-01

    This document is intended to delineate the criteria by which unclassified waste will be accepted for emplacement at the Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico and describe the bases upon which these criteria were established. These criteria are not intended to be specifications but rather limits that will allow waste generating and shipping sites to develop their own procedures and specifications for preparation of TRU waste for shipment to the WIPP. These criteria will also allow waste generating sites to plan future facilities for waste preparation that will produce TRU waste forms compatible with WIPP waste emplacement and isolation requirements. These criteria only apply to contract-handled (CH) and remote-handled (RH) transuranic (TRU) waste forms and are not intended to apply to beta-gamma wastes, spent fuel, high-level waste (HLW), low-level waste (LLW), low specific activity (LSA) waste, or forms of radioactive waste for experimental purposes. Specifications for receipt of experimental waste forms will be prepared by the responsible projects in conjunction with the staff of the WIPP project at a later date. In addition, these criteria only apply to waste emplaced in bedded rock salt. Technical bases for these criteria may differ significantly from those for other host rocks. 25 refs. 4 figs., 1 tab.

  6. 2014 Annual Industrial Wastewater Reuse Report for the Idaho National Laboratory Site’s Advanced Test Reactor Complex Cold Waste Pond

    SciTech Connect (OSTI)

    Lewis, Mike

    2015-02-01

    This report describes conditions, as required by the state of Idaho Industrial Wastewater Reuse Permit (LA 000161 01, Modification B), for the wastewater land application site at the Idaho National Laboratory Site’s Advanced Test Reactor Complex Cold Waste Pond from November 1, 2013–October 31, 2014. The report contains the following information; Facility and system description; Permit required effluent monitoring data and loading rates; Permit required groundwater monitoring data; Status of compliance activities; Noncompliance issues; and Discussion of the facility’s environmental impacts. During the 2014 permit year, approximately 238 million gallons of wastewater were discharged to the Cold Waste Pond. This is well below the maximum annual permit limit of 375 million gallons. As shown by the groundwater sampling data, sulfate and total dissolved solids concentrations are highest near the Cold Waste Pond and decrease rapidly as the distance from the Cold Waste Pond increases. Although concentrations of sulfate and total dissolved solids are elevated near the Cold Waste Pond, both parameters are below the Ground Water Quality Rule Secondary Constituent Standards in the downgradient monitoring wells.

  7. DOE Completes Annual Determination of the Adequacy of the Nuclear Waste Fund Fee

    Broader source: Energy.gov [DOE]

    As required by the Nuclear Waste Policy Act of 1982 (NWPA), DOE has completed its annual review of the adequacy of the Nuclear Waste Fund fee.

  8. Oak Ridge National Laboratory Waste Management Plan

    SciTech Connect (OSTI)

    Not Available

    1991-12-01

    The goal of the Oak Ridge National Laboratory (ORNL) Waste Management Program is the protection of workers, the public, and the environment. A vital aspect of this goal is to comply with all applicable state, federal, and DOE requirements. Waste management requirements for DOE radioactive wastes are detailed in DOE Order 5820.2A, and the ORNL Waste Management Program encompasses all elements of this order. The requirements of this DOE order and other appropriate DOE orders, along with applicable Tennessee Department of Environment and Conservation (TDEC) and US Environmental Protection Agency (EPA) rules and regulations, provide the principal source of regulatory guidance for waste management operations at ORNL. The objective of the Oak Ridge National Laboratory Waste Management Plan is to compile and to consolidate information annually on how the ORNL Waste Management is to compile and to consolidate information annually on how the ORNL Waste Management Program is conducted, which waste management facilities are being used to manage wastes, what forces are acting to change current waste management systems, what activities are planned for the forthcoming fiscal year (FY), and how all of the activities are documented.

  9. Nevada National Security Site Waste Acceptance Criteria

    SciTech Connect (OSTI)

    none,

    2013-06-01

    This document establishes the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Field Office (NNSA/NFO), Nevada National Security Site Waste Acceptance Criteria (NNSSWAC). The NNSSWAC provides the requirements, terms, and conditions under which the Nevada National Security Site (NNSS) will accept the following: • DOE hazardous and non-hazardous non-radioactive classified waste • DOE low-level radioactive waste (LLW) • DOE mixed low-level waste (MLLW) • U.S. Department of Defense (DOD) classified waste The LLW and MLLW listed above may also be classified waste. Classified waste is the only waste accepted for disposal that may be non-radioactive and shall be required to meet the waste acceptance criteria for radioactive waste as specified in this document. Classified waste may be sent to the NNSS as classified matter. Section 3.1.18 provides the requirements that must be met for permanent burial of classified matter. The NNSA/NFO and support contractors are available to assist the generator in understanding or interpreting this document. For assistance, please call the NNSA/NFO Environmental Management Operations (EMO) at (702) 295-7063, and the call will be directed to the appropriate contact.

  10. Hanford Tank Waste Remediation Systems (TWRS) Waste Pretreatment Program strategy and issues

    SciTech Connect (OSTI)

    Gasper, K.A.

    1994-02-01

    The US Department of Energy (DOE) has established the Tank Waste Remediation System (TWRS) to safely manage an dispose of the Hanford Site tank waste. Pretreatment is one of the major program elements of the TWRS. The scope of the TWRS Tank Waste Pretreatment Program is to treat tank waste to separate it into high- and low-level waste fractions and to provide additional treatment as required to feed low-level waste fractions and to provide additional treatment as required to feed low-level and high-level waste immobilization processes. The Pretreatment Program activities include technology development, design, fabrication, construction, and operation of facilities to support the pretreatment of radioactive mixed waste retrieved from 28 large underground double-shell tanks and 149 single-shell tanks.